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August 2002 Exam 50-400/2002-301 Final JPMs & Outlines
	ML022690280
Person / Time
Site:	Harris
Issue date:	03/22/2002
From:	Ernstes M; Division of Reactor Safety II
To:	Scarola J; Carolina Power & Light Co
References
	-RFPFR, 50-400/02301 50-400/02301
	Download: ML022690280 (152)
	v • d • e

Final Submittal

(Blue Paper)

1I. Administrative Questions/JPMs

2. In-plant JPMs

3. Control Room JPMs (simulator JPMs)

SHEARON HARRIS

EXAM 2002-301

50-400

AUGUST 26 - 29, 2002

Examination Outline Form ES-201-2

ES-201

Quality Assurance Checklist

Date of Examination: 26-Aug-02

Facility: HARRIS

Initials

Task Description a b* 1#

Item

a. Verify that the outline(s) fit(s) the appropriate model per ES-40 1.

I of

W b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.

R ES-401 and whether all knowledge and ability categories are appropriately sampled.

T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

E d. Assess whetherthejustifications fordeselected orrejected /A statements are appropriate. At6 LO' VW

N

number of normal

a. Using Form ES-30 1-5, verify that the proposed scenario sets cover the required

2. evolutions, instrument and component failures, and major transients. M &

projected number and mix of

S b. Assess whether there are enough scenario sets (and spares) to test the AT66

I applicants in accordance with the expected crew composition and rotation schedule without compromising

M exam integrity; ensure each applicant can be tested using at least one new scenario and scenarios will not be

repeated over successive days.

whether the outline(s) conform(s) with the qualitative and quantitative criteria * A,. C

c. To the extent possible, assessand described in Appendix D.

specified on Form ES-301-4

a. Verify that: in-plant tasks,

3. (I) the outline(s) contain(s) the required number of control room and

material is repeated from the last NRC examination, MS

(2) no more than 30% of the test

W (3) *no tasks are duplicated from the applicants audit test(s), and

bank.

test is taken directly from the licensee's exam

T/ (4) no more than 80% of the operating

b. Verify that:

1,

(1) the tasks are distributed among the safety function groupings as specified in ES-30

(2) one task is conducted in a low-power or shutdown condition,

procedure,

(3) 40% of the tasks require the applicant to implement an alternate path condition, and

applicant's response to an emergency or abnormal

(4) one in-plant task tests the

(5) the in-plant walk-through requires the applicant to enter the RCA.

activities. A re,

c. Verify that the required administrative topics are covered, with emphasis on performance-based

d. Determine if there are enough different outlines to test the projected number and mix of

applicants and A"3

days.

ensure that no more than 30% of the items are duplicated on successive

whether plant-specific priorities (including PRA and PE insights) are covered in the appropriate

a. Assesssection.

M6 @

4. exam

G b. Assess whether the 10 CFR 55.41143 and 55.45 sampling is appropriate. A6

E

N c. Ensure that K/A importance ratings (except for plarnt-specific priorities) are at least 2.5.

l

R d. Check for duplication and overlap among exam sections. 6

A A

L e. Check the entire exam for balance of coverage.

f. Assess whether the exam fits the appropriate job level (RO or SRO).

, w6

Printed Name / Signature Date

William J.Gros /,,-/-. 30 May 200 2

a. Author

b.Facility Reviewer(*) Ay'Ar T. 3ocd-oet (Zt~ rM SoJ I Ma~e- ceta.

F C '2- .

c. Chief Examiner(#)

d. NRC Supervisor 1 -L

0* r*, h . 1 C4 " t/2p/bL

Note: * Not applicable for NRC-developed examinations. See. a44oc

required.

Independent NRC reviewer initial items in Column "c;" chief examiner concurrence

NUREG- 1021, Revision 8, Supplement I

HARRIS NUCLEAR PLANT - AUG 2002

tTý -TA oowr&OY4e L041 S'S-301 54er-4rb-A

0,0,6 Q- arp- -:ýt omlox +a +Awse +esA,6 oyl

4- 4e

Administrative Topics Outline FORM ES-301-1

Facility: HARRIS Date of Examination: 26-Aug-02

Examination Level: RO 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) ? 6 5Xzto(,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

HARRIS Date of Examination: 26-Aug-02

Facility:

Examination Level: SRO 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

OPERAIONS

nc I(OST-1021)

OPERATIONS

(2.1.18)

Perform a Manual Power Range Heat Balance Calculation

(OST-1204)

(2.1.25)

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

EQUIPMENT

CONTROL

(2.2.13)

"A.

Question Topic - License Requirements for Conducting a Waste

3 Release with Inoperable Instrumentation and Administrative

Controls Ensuring Requirements Met (2.3.6)

RADIATION

CONTROL

Question Topic - Selection Process for Individuals Performing

Emergency Entries into Radiation Fields Resulting in Exceeding

Permissible Exposure Limits (2.3.4)

"A.

4 Perform an Emergency Action Level Classification and

Recommend Protective Actions (PEP-1 10)

PLAN

(2.4.41 / 2.4.44)

NUREG-1021, Revision 8, Supplement 1

Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2

ES-301

HARRIS Date of Examination: 26-Aug-02

Facility:

RO Operating Test Number: 2002-301

Examination Level:

B.1 Control Room Systems

Safety

System/JPM Title Type Function

Code* (KA #)

NAS 3

a. 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.DRL 2

b. (004A2.11)

(AOP-017)

Manually Align Charging Due to a Loss of IA

c.DL 5

C. (028A4.01)

Start Up a Hydrogen Recombiner (OP-125)

path, (C)ontrol Room, (S)imulator,

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate

(L)ow-Power, (R)CA

NUREG-1021, Revision 8, Supplement 1

Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2

ES-301

HARRIS Date of Examination: 26-Aug-02

Facility:

SRO-I Operating Test Number: 2002-301

Examination Level:

B.1 Control Room Systems

Safety

System/JPM Title Code* Function

NAa

a. 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)

DS08A.)

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

(0264A4.01)

DS

d. (0264.01

Manually Align Containment Spray (PATH-l)

e.DASL 2

(006A4.05)

Transfer to Hot Leg Recirculation (EPP-011)

f.DSL 4P

(0034P

Start an RCP Following Maintenance (OP-100) (003A4.06)

Power Range NI Gain Adjustment (OP-105) (01 5A4.02)

B.2 Facility Walk-Through

a.DL 1

a. (003AA1.02)

(AOP-001)

Local Actions for a Dropped Rod Recovery

b. DRL 2

Manually Align Charging Due to a Loss of IA (AOP-017) (004A2.11)

c.DL 5

C.

DL40

Start Up a Hydrogen Recombiner (OP-125)

I (028A4.01)

path, (C)ontrol Room, (S)imulator,

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate

(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.

(AOP-019) NAS( 3

Respond to a Failed High Pressurizer Pressure Channel (0l0.A2.03)

b.NAS 6

b.

55) (064A4.0l)

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

C.

d.

e.

f.

g.

B.2 Facility Walk-Through

a.DL 1

a.

(OO3AA1.02)

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

b. b.DRL 2

(004A2.1l)

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

c. c.DL 5

(028A4.01)

Start Up a Hydrogen Recombiner (OP-125)

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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Perform Review of Daily Surveillance Requirements Log

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

KA: 2.1.18 IMPORTANCE: SRO 3.0 RO NA

KA STATEMENT: Ability to make accurate, clear and concise logs, regards,

status boards, and reports.

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

PREFERRED EVALUATION LOCATION: SIMULATOR v' IN PLANT

PREFERRED EVALUATION METHOD: PERFORM *1 SIMULATE

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

1 and 2

VALIDATION TIME: 20 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

Rev Date 07/25/02

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

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP 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

NA in reading OR should either be

Channel 456

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 1200 F maximum limit temperature is

above maximum

allowed.

Page 4 of 8

Rev Date 07/25/02

JPM SRO-A.1-1

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP 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:

SAT 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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Determine Rod Misalignment Using Thermocouples

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

KA: 2.1.19 IMPORTANCE: SRO NA RO 4.4

KA STATEMENT: Ability to use plant computer to obtain and evaluate

parametric information on system or component status.

TASK STANDARD: Determines Shutdown Bank A Rod C9 is misalignment is

NOT verifiable using incore thermocouples

PREFERRED EVALUATION LOCATION: SIMULATOR v' IN PLANT

PREFERRED EVALUATION METHOD: PERFORM *1'

SIMULATE

REFERENCES: AOP-001, Malfunction of Rod Control and Indication System

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

Rev Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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.

Page 4 of 8

Rev Date 07/21/02

JPM RO-A.1-1

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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) - 6020 F

those in the same row. a H13 (sym)- 6080 F

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 ( 6.330 F)

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* H15

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.

6 3

Affected TC #1 _C08_(62) Symmetric TC(s) H13 608-- N08 08) -H0 (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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Perform a Manual Power Range Heat Balance Calculation

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

KA: 2.1.25 IMPORTANCE: SRO 4.6 RO 4.4

KA STATEMENT: Ability to obtain and interpret station reference materials

such as graphs, monographs, and tables which contain

performance data.

TASK STANDARD: Heat balance has been calculated within allowable tolerance

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PREFERRED EVALUATION METHOD: PERFORM .- 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: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 12

Rev. Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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-

_____________________________________________________________________________ ___________________

1 Att. 5 Calculate Steam Generator 1) Fills in SG Pressures Critical to

Exit Enthalpies: from Att 3 as SG A accurately

la

Steam Tables Lookup: - 900, SG B - 890, determine steam

SGC-900 enthalpy to

Saturated Steam,

2) Looks up liq determine power

Liquid Enthalpies

enthalpy for SG level.

pressures as SG A

526.7, SG B Note liquid

525.0+0.2 enthalpy value is

(interpolation NOT critical

required), SG C since it will be

526.7 multiplied by

3) Looks up steam zero in next step.

enthalpy for SG

pressures as SG A

- 1196.4, SG B

1196.7+0.2

(interpolation

required), SG C

1196.4

1 1 L - - --

Page 4 of 12

Rev. Date 07/21/02

JPM COM-A. 1-2

HARRIS

STANDARD NOTES SAT /

3PM PROC ELEMENT

STEP 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 4400 F 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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.

Page 6 of 12

Rev. Date 07/21/02

JPM COM-A. 1-2

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

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

421 TF. INDEPENDENT VERIFICATION IS COMPLETED.

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

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 Liq. Enthalpy (h!) Stm. Enthalpy (h,)

526.7 btu/lbm, 1196.4 btu/Ibm

SG A: 900 psia

SG B: 890 psia

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

SG C: 900 psia

_> 526.7 btu/lbm, 1196.4 btu/lbm

b. Calculate SG Exit Steam Enthalpies

Stm. Enthalpy Liq. Enthalpy Exit Enthalpy

(h,) (h~t)

SG A: 1.00 x 1196.4 . o.oo , 526.7 1196.4 btu/Ibm

1.00 )196.7+/-0.2+ 0.00 525.0+/-0.2 1196.7+/-0.2 btu/ibm

SG B:

1196.4 + 0.00 x 526.7 1196.4 btu/ibm

SG C: 1.00 x

2. Feedwater Enthalpy (Stm Tables Lookup)

FrW (TempiPress) FW Enthalpy (hw*)

h 440 1080 419.0 btu/ibm

hr.

VW Avg -F Fa Psia

3. Enthalpy Rise across the Steam Generators

Exit Enthalpy FW Enthalpy A Enthalpy

(h~i+/-) (h49) (Ahsa)

SC A: ______

1196.4 419.0 777.4 btu/lbm

419.0 =777.7+/-0.2 btu/lbm

SG B: 1196.7+/-0.2

1196.4 419.0 777.4 btu/lbm

SG C:

ANSWER KEY FOR JPM COM-A1-2

Page 8 of 12

Rev. Date 07/21/02

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 A Enthalpy %*G

(MPPH) (btu/lbm) (Mbtu/hr)

4.246 777.4 3300.84 Mbtu/hr

QO A: x

Qý ~4.223 x 777.7+/-0.2 3284.23+/-0.85 Mbtu/hr

x 777.4 3307.84 Mbtu/hr

Qý c4.255

5. Calculate Total Reactor Power

3300.84 3300.23+/-0.85-A 3307.84 - 42.31

9850.60+/-0.85 Mbtu/hr

+

QSQA QsoB Qs c QRCP QRX

6. Convert Mbtu/hr to MWm

9850.60+/-0.85 Mbtu/hr 3.4121 Mbtu/hr/MWmh

Z886.96+/-0.25 mWm

7. Calculate Percent of Rated Thermal Power

2886.96+/-0.25 Mw", x 100 99.6+/-0.1 %RTP

2900 MW,,

8. Power Range NI Surveillance

100.0 99.6+/-0.1 0.4+/-0.1

Highest PR NI (M Calc'd Power (%)

99.5 99.6+/-0.1 -0.1+/-0.1

Lowest PR NI (M Calc'd Power (W)

Performed By:

CANDIDATE SIGN

Verified By:

N/A

ANSWER KEY FOR JPM COM-A1-2

Page 9 of 12

Rev. Date 07/21/02

JPM COM-A. 1-2

HARRIS

ANSWER KEY FOR JPM COM-A1-2

Attachment 6

Sheet 1 of 1

Certifications and Reviews

Periodic Surveillance Requiremeent:

x

This OST was oerformed as a:

Post Maintenance Operability Test:

Redundant Subsystem Test:

100% power Mode: 1

Plant Conditions:

OST Completed By:

CANDIDATE SIGN Date: CURRENT

Time: CURRENT

OST Performed By:

Initials Name (Print) Initials Name (Print)

BJ 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 OST becomes a QA RECORD and

should be submitted to Document Services.

ANSWER KEY FOR JPM COM-A1-2

Page 10 of 12

Rev. Date 07/21/02

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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Review an Equipment Clearance

ALTERNATE PATH: None

FACILITY JPM NUMBER: IP-164 (Modified)

KA: 2.2.13 IMPORTANCE: SRO 3.8 RO 3.6

KA STATEMENT: Knowledge of clearing and tagging procedures.

TASK STANDARD: Identifies both discrepancies on clearance as listed in JPM.

PREFERRED EVALUATION LOCATION: SIMULATOR %' IN PLANT

PREFERRED EVALUATION METHOD: PERFORM

'WI'

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: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

Rev. Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Radiological Controls

ALTERNATE PATH: NA - Questions

FACILITY JPM NUMBER: NA - Questions

KA: 1) 2.3.6 IMPORTANCE: SRO 1) 3.1 RO NA

2) 2.3.4 2)3.1

KA STATEMENT: 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

TASK STANDARD: NA - Questions

vi

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PERFORM V. SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: OP-120.06.02, Waste Evaporator Condensate Tanks

Offsite Dose Calculation Manual

PEP-330, Radiological Consequences

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

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature 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"

Offsite Dose Calculation Manual

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

JOB PERFORMANCE MEASURE

JPM RO-A.3

Radiological Controls

CANDIDATE:

EXAMINER:

Page 1 of 7

Rev. Date 07/27/02

JPM RO-A.3

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Radiological Controls

ALTERNATE PATH: INA - Questions

FACILITY JPM NUMBER: NA - Questions

KA: 1) 2.3.2 IMPORTANCE: SRO NA RO 1)2.5

2) 2.3.10 2) 2.9

KA STATEMENT: 1) Knowledge of the facility ALARA program.

2) Ability to perform procedures to reduce excessive levels

of radiation and guard against personnel exposure.

TASK STANDARD: NA - Questions

1'

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PREFERRED EVALUATION METHOD: PERFORM Vt'

SIMULATE

REFERENCES: AP-545, Containment Entries

AP-504, Administrative Controls for Locked and Very High

Radiation Areas

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 7

Rev. Date 07/27/02

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

August 22, 2002

MEMORANDUM TO: Kathleen O'Donohue, Senior Operations Engineer

George T. Hopper, Senior Operations Engineer

FROM: Michael E. Ernstes, Chief

Operator Licensing and Human Performance Branch

SUBJECT: EXAMINATION ASSIGNMENTS - SHEARON HARRIS NJUCLEAR

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

APPLICANT DOCKET NO. EXAMINATI ON TYPE

Gary M. Fulks 55-22617 RO

Mark 0. Christopherson 55-21791 SRO Upgrade

55-22319 SRO Upgrade

Timothy A. English

55-22620 SRO Instant

William S. Saunders

55-22621 SRO Instant

Edward L. Wills, Jr.

Facility and Location: Shearon Harris Nuclear Plant, New Hill, NC

Facility Contact: Terry Toler, (919) 362-3493

NRC Chief Examiner: Kathleen O'Donohue

Written Examinations to be Prepared by (RO): Shearon Harris Nuclear Plant

(SRO): Shearon Harris Nuclear Plant

Date of Operating Tests: August 26 , 28, 2002

Date of Written Examinations: August 29, 2002

Time of Written Examinations: 8:00 a.m.

cc: D. Trimble, IEHB

J. Goshen, NRR

J. Brady, Shearon Harris

Senior Resident Inspector

B. Michael, DRS

OL Exam File

JPM RO-A.4

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Activate the Emergency Response Organization - Dialogic System

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

KA: 2.4.43 IMPORTANCE: SRO NA RO 2.8

KA STATEMENT: Knowledge of emergency communications systems and

techniques

TASK STANDARD: The Emergency Response Organization has been notified of

a plant emergency using the Dialogic System

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PREFERRED EVALUATION METHOD: PERFORM SIMULATE

REFERENCES: PEP-3 10, Notifications and Communications

VALIDATION TIME: 15 MINUTES TIME CRITICAL: Yes

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

Rev. Date 08/09/02

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:

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

"APublic 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Perform an Emergency Action Level Classification and Recommend

Protective Actions

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

KA: 2.4.41 / 2.4.44 IMPORTANCE: SRO 4.1/4.0 RO NA

KA STATEMENT: Knowledge of the emergency action level thresholds and

classifications. / Knowledge of emergency plan protective

action recommendations.

TASK STANDARD: General Emergency determined due to three (3) fission

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

completed satisfactorily.

PREFERRED EVALUATION LOCATION: SIMULATOR V IN PLANT

PREFERRED EVALUATION METHOD: PERFORM V' SIMULATE

REFERENCES: "* Emergency Action Level Flowpath

"* PEP- 110, Emergency Classification and Protective Action

Recommendations

VALIDATION TIME: 15 MINUTES TIME CRITICAL: Yes

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE 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: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 14

Rev. Date 08/09/02

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

14000 F, 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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.

Page 5 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

1PM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM 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 > 12000 F

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

PARs.

Page 8 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

PARs.

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

PARs.

Page 9 of 14

Rev. Date 08/09/02

JPM SRO-A,4

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP 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

2300 0%, 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 23000 F, 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

PARs.

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

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP 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 1500 0 F and 16000 F

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

14000 F, 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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Secure One Train of CCW to the RHR HXs

ALTERNATE PATH: None

FACILITY JPM NUMBER: RO-B. 1.e (NRC Exam - Dec 2000)

KA: 008A2.01 IMPORTANCE: SRO 3.3 RO 3.1

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

CCW indications and controls.

TASK STANDARD: Train 'A' CCW is supplying the RHR HX and the non

essential loop.

PREFERRED EVALUATION LOCATION: SIMULATOR %' IN PLANT

PREFERRED EVALUATION METHOD: PERFORM .4 SIMULATE

REFERENCES: OP-145, Component Cooling Water

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 6

Rev Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP 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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Manually Align Containment Spray

ALTERNATE PATH: Starts Containment Spray and aligns valves

FACILITY JPM NUMBER: CR-106

KA: 026A4.01 IMPORTANCE: SRO 4.3 RO 4.5

KA STATEMENT: Manually operate in the control room: CSS controls.

TASK STANDARD: Containment Spray has been actuated and all RCPs have

been stopped.

PREFERRED EVALUATION LOCATION: SIMULATOR %1 IN PLANT

PREFERRED EVALUATION METHOD: PERFORM *1'

SIMULATE

REFERENCES: EOP-PATH-1

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 6

Rev Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: 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: SRO 3.8 RO 3.9

KA STATEMENT: Operate in the control room: Transfer of ECCS flowpaths

prior to recirculation.

TASK STANDARD: Hot leg recirculation has been established.

PREFERRED EVALUATION LOCATION: SIMULATOR 10 IN PLANT

PREFERRED EVALUATION METHOD: PERFORM *1'

SIMULATE

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

Recirculation

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 7

Rev Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP 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

CUE 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

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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Start an RCP Following Maintenance

ALTERNATE PATH: None

FACILITY JPM NUMBER: CR-005

KA: 003A4.06 IMPORTANCE: SRO 2.9 RO 2.9

KA STATEMENT: Operate in the Control Room: Reactor Coolant Pump

parameters

TASK STANDARD: RCP A has been started

PREFERRED EVALUATION LOCATION: SIMULATOR %' IN PLANT

PREFERRED EVALUATION METHOD: PERFORM SIMULATE

REFERENCES: OP- 100, Reactor Coolant System

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 6

Rev. Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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 1300 F 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

Page 4 of 6

Rev. Date 07/21/02

JPM COM-B.1.f

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

9 5.1.2.6 Verify the following normal Verifies parameters are

operating parameters: in the normal band

Running amps: Hot 460 "* Running amps

to 540 amps, Cold 715 "* RCS flow

amps "* No. 1 seal Ap

"* RCS flow: >98% "* No. 1 seal leakoff

"* No. 1 seal Ap: > 200 psid "* Motor winding

"* No. 1 seal leakoff: in the temperature

normal operating range of

Attachment 3

"* Motor winding

temnnerature: .c300°F

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

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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Power Range NI Gain Adjustment

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

KA: 015A4.02 IMPORTANCE: SRO 3.9 RO 3.9

KA STATEMENT: Operate in the Control Room: NIS Indicators

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

PREFERRED EVALUATION LOCATION: SIMULATOR V* IN PLANT

PREFERRED EVALUATION METHOD: PERFORM S SIMULATE

REFERENCES: OP-105, Excore Nuclear Instrumentation

VALIDATION TIME: 20 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

Rev Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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 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 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 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 4 Calculation in Steps 2 and 3 Requests independent

independently verified, verification of

calculation

CUE INDEPENDENT VERIFICATION HAS BEEN COMPLETED.

5 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 blocked

Page 4 of 8

Rev Date 07/21/02

JPM COM-B.1.g

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

6 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 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 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 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

12 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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Manually Control Charging Due to a Loss of IA

ALTERNATE PATH: None

FACILITY JPM NUMBER: IP-084

KA: 004.A2.11 IMPORTANCE: SRO 4.2 RO 3.6

KA STATEMENT: Correct, control, or mitigate the consequences on CVCS

caused by the following malfunction: Loss of IAS

TASK STANDARD: Charging flow is being controlled locally

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT *'

PREFERRED EVALUATION METHOD: PERFORM SIMULATE *'

REFERENCES: AOP-017, Loss of Instrument Air

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 6

Rev Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: 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: SRO 4.2 RO 4.1

KA STATEMENT: Ability to correct, control, or mitigate the consequences of

the following PRZ PCS malfunction: PORV failures

TASK STANDARD: Master PRZ Controller is in MANUAL, controlling pressure,

with PORV Block Valve 1RC-1 13 closed.

PREFERRED EVALUATION LOCATION: SIMULATOR %1 IN PLANT

PREFERRED EVALUATION METHOD: PERFORM V. SIMULATE

REFERENCES: AOP-019, Malfunction of RCS Pressure Control

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

Rev Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

17 3.1.10 Check at least one of the "* Determines

following conditions present, pressure, spray

orgo to Step 18: valves, and heaters

"* PRZ pressure is are controlled

uncontrolled "* Goes to Step 18

"* Status of a normal spray

valve or a PRZ heater

bank is uncontrolled

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

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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Local Actions for a Dropped Rod Recovery

ALTERNATE PATH: None

FACILITY JPM NUMBER: IP-153

KA: 003AAl.02 IMPORTANCE: SRO 2.9 RO 2.9

KA STATEMENT: Operate the demand position counter and pulse/analog

converter

TASK STANDARD: Local actions have been completed for rod recovery

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT *

PREFERRED EVALUATION METHOD: PERFORM SIMULATE *'

REFERENCES: AOP-001, Malfunction of Rod Control and Indication System

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

Rev Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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 Auto-Manual switch in proper operation of

(RNO) MANUAL 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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 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

JOB PERFORMANCE MEASURE

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

JOB PERFORMANCE MEASURE

TASK: Start Up a Hydrogen Recombiner

ALTERNATE PATH: None

FACILITY JPM NUMBER: IP-020

KA: 028A4.01 IMPORTANCE: SRO 4.0 RO 4.0

KA STATEMENT: Operate the Hydrogen Recombiner controls

TASK STANDARD: Electric Hydrogen Recombiner A is in operation with the

proper power setting

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT *1

PREFERRED EVALUATION METHOD: PERFORM SIMULATE V

REFERENCES: OP-125, Post Accident Hydrogen System

VALIDATION TIME: 20 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

Rev. Date 07/21/02

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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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)

Page 4 of 8

Rev. Date 07/21/02

JPM COM-B.2.c

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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 1

5.1.2.2.f 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP 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 1

5.1.2.2.k 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

JPM 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 0 F.

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

JOB PERFORMANCE MEASURE

TASK: LOSP While Paralleling EDG from MCB for Testing

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

manually opened

FACILITY JPM NUMBER NEW

KA: 056AA2.14 IMPORTANCE: SRO 4.6 RO 4.4

KA STATEMENT: Determine as related to a Loss of Offsite Power: Operational

status of EDGs

TASK STANDARD: EDG B output breaker 126 has been manually opened

PREFERRED EVALUATION LOCATION: SIMULATOR " IN PLANT

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: OP-155, Diesel Generator Emergency Power System

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 7

Rev Date 07/21/02

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

NOTES SATA/

JPM PROC ELEMENT STANDARD

STEP UNSAT

STEP

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

1 5.3.2.1 Notify Load Dispatcher EDG Request Unit SCO

lB-SB will be loaded notify Load Dispatcher

CUE DISPATCHER HAS BEEN NOTIFIED.

2 5.3.2.2 Review Precautions Reviews precautions

4.0.0.021, 4.0.0.022,

4.0.0.024 and 4.0.0.025

before paralleling

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

TO ITS NORMAL SOURCE.

3 5.3.2.3 Place DIESEL GEN B-SB Turns EDG B sync Critical to permit

SYNCHRONIZER control scope on closure of EDG

switch to SYNC breaker 126

4 5.3.2.4.a 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

5 5.3.2.4.b * 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

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

Position DIESEL GEN B-SB Adjust EDG B Governor

7 15.3.2.5.a

GOVERNOR CONTROL Control until EDG B

switch to RAISE or LOWER frequency is indicating

as necessary to perform the 59 HZ

following:

"* Lower frequency to 59

HZ

"* Raise frequency to 61 HZ Adjust EDG B Governor

8 5.3.2.5.b

Control until EDG B

frequency is indicating

61 HZ

Position DIESEL GEN B-SB Adjust EDG B Governor

9 5.3.2.5.c

GOVERNOR CONTROL Control until EDG B

switch to RAISE or LOWER sync scope is indicating

as necessary to perform the slow CW movement

following:

Adjust EDG speed until

the synchroscope is

rotating slowly in the

FAST direction

(CLOCKWISE)

Check synchronizing lights Verify sync lights

10 5.3.2.6

are cycling (OUT when the cycling properly in

synchroscope is at the 12 agreement with sync

o'clock position) in agreement scope

with the synchroscope

rotation

11 5.3.2.7 As necessary, position Readjust EDG B Auto

DIESEL GEN B-SB AUTO Voltage Adjust until

VOLTAGE ADJUST EDG voltage matches

control switch to adjust EDG 6.9KV Bus 1B-SB

voltage to zero differential voltage (0 A VOLTS)

voltage on EI-6953B SB , B

SYNC A VOLTS Critical to close

"*12 5.3.2.8 When the synchroscope Place EDG B breaker

126 to close position EDG breaker 126

reaches the 12 o'clock to permit EDG to

position and the when sync scope

indicates 12 o'clock pickup load

synchronizing lights are

TOTALLY DARK, place position and sync lights

the DIESEL GEN B-SB are totally dark

BREAKER 126 SB control

switch to CLOSE

Check DIESEL GEN B-SB Verify EDG B breaker is

13 5.3.2.9

I ~ I BREAKER 126 SB is closed I closedI

Page 5 of 7

Rev Date 07/21/02

JPM COM-B. L.b

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

SIMULATOR OPERATOR INSTRUCTIONS: INSERT OVERRIDE <ICOR ZCR31748 FAILASIS>

TO oPREVENT EDG B BREAKER 126 AFROM AUTOMATICALLY

APF*N'

OPENING ON SUBSEQUENT

TTATt'J TA*

I t AT * l'lXflT*TC' ATnoun

T/IATTAI

11uar i',VflA A4

XXTT XT~rfA IADtA TONa OPN

"*14 5.3.2.10 Position DIESEL GEN B- Adjust EDG B Critical to pickup

SB GOVERNOR Governor Control until load to prevent

CONTROL switch to EDG B load indicates reverse power

increase generator load to 2.2 to 2.4 MW trip of EDG

2.2 to 2.4 MW on El- breaker 126

6957B1 SB, B POWER

15 5.3.2.11 Position DIESEL GEN 1B- Adjust EDG B Auto

SB AUTO VOLTAGE Voltage Adjust until

ADJUST control switch to EDG reactive load

obtain 1.0 MVARs on El- indicates 1.0 MVARs

6958B SB, B REACTIVE

16 5.3.2.12 Place DIESEL GEN B-SB Place EDG B sync scope

SYNCHRONIZER control off

switch to OFF

17 5.3.2.13 Check DIESEL GEN B-SB Verify amber light lit on

BREAKER 126 SB amber EDG B breaker 126

light is lit

A

SIMULATOR OPERATOR INSTRUCTIONS: INSERT MALFUNCTION <IMF EPSO0> TO CAUSE

LOSS OF OFFSITE POWER TO THE PLANT.

18 NA Determine LOSP has * Determine EDG B

occurred and check for proper breaker 126 has

response of EDG B output failed to open

breaker 126 * Notifies Unit SCO

"*19 4.0.0.024 Open EDG B breaker 126 Place EDG B breaker Critical to

126 to open separate EDG

from grid to

prevent EDG

damage due to

overload

TASK COMPLETE

STOP TIME:

Page 6 of 7

Rev Date 07/21/02

JPM COM-B. 1.b

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

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 7 of 7

Rev Date 07/21/02

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