ML032020380

DDRGFT

Administrative Topics Outline

Form ES-301-1

Describe activity to be performed

Calculate Reactor Vessel Head Venting Time (New JPM)

2.1.25 (2.8/3.1)

Facility:

Farlev

Date of Examination:

5/19-27/2003

Examination Level (circle one): @ / SRO

Operating Test Number:

1

Administrative Topic

(see Note)

Conduct of Operations

Equipment Control

Perform ECP [CRO-O25A]

2.1.10 (plant parameter verification)

(2.7/3.9)

Maintenance Retest of 1 B RHR Pump (New JPM)

KIA 2.2.12 3.0/3.4

Perform A Shielding Calculation (New JPM)

2.3.2 (2.9 2.9)

N/A

Radiation Control

Emergency Plan

they are retaking only the administrative topics, when 5 are required.

DRbw

Administrative Topics Outline

Form ES-301-1

Facility:

Farley

Date of Examination: 5119-27/2003

Examination Level (circle one): RO I SRO

Operating Test Number:

1

l

i

Administrative Topic

(see Note)

I

Conduct of Operations

11 Conduct of Operations c

Equipment Control

Emergency Plan

Describe activity to be performed

Calculate Reactor Vessel Head Venting Time (New JPM)

2.1.25 (2.8/3.1)

Perform ECP [CRO-O25A]

2.1.10 (plant parameter verification)

(2.713.9)

Maintenance Retest of 1 B RHR Pump (New JPM)

WA 2.2.12 3.013.4

Perform A Shielding Calculation (New JPM)

2.3.2 (2.51 2.9)

Classification of an Emergency Event (New JPM)

2.4.41 (2.314.1)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless

they are retaking only the administrative topics, when 5 are required.

DRAFT

Conduct of Operations: Calculate Reactor Vessel Head Venting Time

Initial Conditions:

FNP-1-FRP-1.3, Response to Voids in Reactor Vessel, has been implemented and completed

through subsequent step 20.1. The following conditions exist:

Containment Pressure

9 psig

Lower Containment Temperature

140°F

H, Concentration

1.8%

RCS Pressure

290 psig

Referenced Documents:

FNP-1-FRP-1.3, Response to Voids in Reactor Vessel

FR-1.3. HP-Rev. I C Base Documents

Task Standard:

Reactor Vessel Head venting time calculated to be 13 minutes 5 seconds.

lnitiatina Cues:

The SRO has directed you to complete Step 20.3 by recording the maximum venting time per

TABLE 1 (Maximum Reactor Head Vent Time (Minutes-Seconds)).

Terminatina Cues:

When the applicant completes Step 20.3 and indicated the maximum vent time.

NOTE:

Provide applicant with a working copy of FNP-1-FRP-1.3, Response to Voids in

Reactor Vessel.

-

KIA 2.1.25

2.813.1

FORMAL OJt REQUIRED PRIOR TO EVALUATION

CRO-025A

TITLE: Perform An Estimated Critical Condition Calculation

PROGRAM APPLICABLE: SOT __ SOCT -

O L T X LOCTJ

ACCEPTABLE EVALUATION METHOD: X PERFORM X SIMULATE -

DISCUSS

EVALUATION LOCATION:

PROJECTED TIME: 40 MIN

SIMULATOR IC NUMBER: N/A

SIMULATOR X CONTROL ROOM -

PLANT

ALTERNATE PATH -

TIME CRITICAL -

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

0

e

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unib'traidcomponent is potentially operated

4.

JPM Approved: 2003 NRC EXAM

Supervisor - Operations Training

Operations

JPM CORRECTION FORM

LESSON TITLE:

Perform An Estimated Critical Condition Calculation

LESSON NO.:

JPM CRO-025A

DATE

04/26/02

9/19/02

3/28/03

4/2/03

PAGE

All

3 & 6

Footer

3,4, & 6

NEEDED CORRECTION

(Typo, DCP, Tech. Error, Etc.)

Changed element standards (expected reactivity

values) to reflect cycle 18 rather than cycle 17

Take the statement out that says: This is a pre-job

brief: in the condition section.

Added Path for JPM File to footer

Changed values to the EOL numbers to be

consistent with current Xe/Sm & DBW Programs

INITIAL

Developer

JWW

cvr

STANDARDS

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin, you are to PERFORM AN ESTIMATED CRITICAL CONDITION

CALCULATION. The conditions under which this task is to be performed are:

a.

b.

c.

d.

e.

f.

The Unit tripped 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago.

Prior to the trip, the unit had been operating at 100% power for 2 months.

Conditions at time of trip: 100% power, Bank D rods at 227 steps, 185 ppm boron, 18,000

MWDMTU burnup.

The Unit is presently in Mode 3 with T,, at 547'F.

Plans are to perform a reactor startup now with a critical rod height of 150 steps on Bank D.

DBW, XENON, and SAMARIUM programs are attached.

I ~~ NOTE: THIS JPM HAS BEEN DESIGNED FOR UNIT 1 CYCLE 18 CORE PHYSICS

~

CURVES. DBW, XENON, AND SAMARIUM PROGRAMS ARE ATTACHED.

EVALUATION CHECKLIST

ELEMENTS:

__ START TIME

1.

Determine total reactivity associated with

prior critical conditions.

2.

Determine xenon reactivity change.

3.

Determine samarium reactivity change.

4.

Determine the reactivity associated with

the desired critical rod height.

Determine the reactivity change due to

temperature.

5.

STANDARDS:

Reactivity total 2200 pcm.

Correct reactivity change

calculated using xenon worth

program (+2260 pcm).

Correct reactivity change

calculated using samarium worth

program. (-85 pcm).

Current reactivity determined for

desired rod height. (-502 pcm).

Correct reactivity determined for

temperature. (0 pcm).

RESULTS:

(CIRCLE)

s / u

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

-

START TIME

6.

Add algebraically the xenon, samarium,

Total reactivity calculated

s / u

7.

Determine the critical boron

Boron concentration calculated

s / u

rod, and temperature reactivity.

correctly. (+1673 pcm).

concentration.

correctly. (55 1 to 58 1 ppm).

8.

Determine the minimum critical rod

Correct rod height determined.

S I U

9.

Determine the maximum critical rod

Correct rod height determined.

S I U

10.

If ECP computer program is used, attach

ECC Calculation Worksheet is

s / u

height.

(D at 21).

height.

(D at 227).

completed ECC Calculation worksheet to

Appendix 1.

Worksheet to Appendix 1.

-

STOP TIME

1

Terminate when maximum critical rod height is determined.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

GENERAL REFERENCES

1.

2.

FNP-1-STP-29.6 Revision 2.0

Core Physics Curve Book, Unit 1, Cycle 18

3.

K/A: 001A4.10

RO-3.5

SRO-3.9

GENERAL TOOLS AND EOUIPMENT

1.

STP-29.6

2.

Xenon Worth Program

3.

Samarium Worth Program

4.

Core Physics Curves

5.

Calculator

6.

COMMENTS

DBW and/or ECP Computer Program

CONDITIONS

When I tell you to begin, you are to PERFORM AN ESTIMATED CRITICAL CONDITION

CALCULATION. The conditions under which this task is to be performed are:

a.

b.

C.

d.

e.

f.

g.

h.

i.

The Unit tripped 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago.

Prior to the trip, the unit had been operating at 100% power for 2 months.

Conditions at time of trip: 100% power, Bank D rods at 227 steps, 185 ppm boron, 18,000

M WD/MTU burnup.

The Unit is presently in Mode 3 with Tav8 at 547°F.

Plans are to perform a reactor startup now with a critical rod height of 150 steps on Bank D.

Initial conditions given to examinee

The ECC has been completed up through Section A, Step 1

The startup date and time has been entered in Section B, Step 1

Access to DBW and ECP computer programs may or may not be available. (Determined by

the examiner.)

DRAFT

EauiDment Control: Maintenance Retest of 1B RHR Pump

Initial Conditions:

Following work on the RHR system a maintenance retest of 1 B RHR pump requires FNP-1-

STP-11.2, 1B RHR Pump Quarterly Inservice Test, to be conducted.

Set the IC so that normal full power conditions are set.

FNP-1-STP-11.2 steps 3.1 through 3.1 1 have been completed.

1B RHR standstill oil reservoir levels are between the MAX and 1/4 inch below the MAX

Referenced Documents:

FNP-1-STP-11.2, 1 B RHR Pump Quarterly Inservice Test

Task Standard:

FNP-1-STP-11.2, 16 RHR Pump Quarterly lnservice Test meets acceptance Criteria.

lnitiatina Cues:

The SRO has directed you to complete FNP-1-STP-11.2, 1B RHR Pump Quarterly Inservice

Test. FNP-1-STP-11.2 steps 3.1 through 3.11 have been completed.

Terminatina Cues:

When all arrangements have been made to enter the very high radiation area.

NOTE:

Provide applicant with a working copy of FNP-1-STP-11.2, 1 B RHR Pump

Quarterly Inservice Test.

Pump seal leakage is calculated to be 10 cclmin

-

K/A 2.2.12 3.0/3.4

DRAFT

Radiation Control: Perform A Shielding Calculation

Initial Conditions:

You have been directed to work in an area where the Gamma Radiation intensity is 10,000

Rad/ Hr. with no shielding. You cannot work in the area unless the field is reduced to no greater

than 200 Rad/ Hr.

Referenced Documents:

Basic Rad worker training

Task Standard:

The examinee will determine the Tenth value layer and the Half value layer of shielding required

for adequate protection of a worker. Operator determines 6 HVLs are required to reduce

intensity to less than 200 Rad/ hr. Operator determines 3 TVLs are required to reduce intensity

to less than 100 Rad/ hr.

lnitiatinq Cues:

You are to calculate the minimum number of half- value layers (HVLs) required to reduce the

Gamma level to no greater that 200 Rad/ hr.

You are also to calculate the minimum number of tenth- value layers (TVLs) required to reduce

the Gamma level to no greater than 100 Rad/ hr.

Terminatinq Cues:

The JPM is terminated when the applicant has determined the minimum number of half-value

layers and the minimum number of tenth-value layers required.

NOTE:

Applicant may use intensity equation. If Examinee uses equation then cue him/

her that lead will be used as shielding and the "

" , the total linear attenuation

coefficient for lead is 0.772 cm -1

~ K/ A 2.4.41 (2.3/4.1)

Validation Time: 15 mins

THIS INFORMATION FOR USE AND REFERENCE BY EXAMINER

lshielded =

lunshielded (I/

2)

HVL (I/

10)#WL

where #HVL = Shield Thickness (cm)

HVL (cm)

and

TVL = Shield Thickness (cm)

TVL (cm)

Shielding Equation I = I,,e-'"

Where: I - the exposure rate with the shield (Rad/ hr)

lo -the unshielded exposure rate (Rad/ hr)

x -the shield thickness (cm)

p -the total linear attenuation coefficient (cm -1 ).

Emeraencv Plan: Classification of an Emergency Event

Initial Conditions:

For the scenario event that the SRO applicants are in the SRO position, at the end of the

scenario the applicant will be required to make a classification based on the scenario

conditions.

Referenced Documents:

Each of the 4 scenarios

Emergency Classification and Actions, FNP-0-EIP-9.0

Task Standard:

Applicant has declared the event classification based on scenario conditions.

lnitiatina Cues:

As the SRO complete the event classification and make the appropriate declaration based on

your scenario conditions.

Terminatina Cues:

When the applicant has made the event declaration.

Note: There should be a specific classification for each of the scenarios.

-

K/A 2.4.29 2.6/4.0

Control Roomlln-Plant Systems

Form ES-301-2

Outline

b

Facility:

Farlev

Date of Examination: 5/19-27/2003

Exam Level (circle one): RO / SRO(I) / SRO(U)

Operating Test No.:

1

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System I

JPM Title

Type

Safety

Code*

Function

b. Start Containment Cooling System WA 22A4.01 3.6/3.6

CRO-133A.

a. 0 erate Service Water um s in Various Modes.

CEO-289

WA 078A4.61

2.912.9

D,S,L

5

e. Perform the re uired actions for transfer to simultaneous

cold le and hA le recirculation. CRO-333C

KIA 008EA4.07 4.84.4

c. Perform required actions in response to RCP Seal

Failures. CRO-047A

WA 003A2.02 3.7/3.9

D A S

3

9

I

DS I

d. Perform actions for a Liquid Waste Release. CRO-277

WA 068A4.01 3.813.7

U

i. Align SGBD from Ru tured SG to Main Condenser

6 assin the SGB8Demineralizers. SO-151B

d1035td.13 2.7/2.8

R,D

4P

f. Shift Auxiliary buses between UA transformers and SU

6

transformers. CRO-245

WA 062A2.01 3.4/3.9

g. Perform an emer enc boration. CRO-65B

KIA 024AA2.02 %.9/24

h. N/A

11 Implant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

j. Shift AFW um suction emergency supply. SO-31 1

4s

I/

WA 0611$10.? 3.9/3.9

k. Startup an Instrumentation Inverter. SO-344

)I

KIA 057AA1.01 3.713.7

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

Control Roomlln-Plant Systems

Form ES-301-2

Outline

System / JPM Title

Type

Code*

a. Start an RCP. CRO-043A WA 003A2.01 3.5/3.9

D,ASS

Farlev

Date of Examination: W19-27/2003

)

Operating Test No.: 1

/ SKO(I) I SRO(u

Facility:

Exam Level (circle one):

Safety

Function

4

b. Start Containment Cooling System WA 22A4.01 3.6/3.6

c. Perform required actions in response to RCP Seal

d. Perform actions for a Liquid Waste Release. CRO-277

CRO-133A.

Failures. CRO-047A

WA 003A2.02 3.7/3.9

WA 068A4.01 3.8/3.7

D,S,L

5

M A S

2

D S

9

e. Perform the required actions for transfer to simultaneous

cold leg and hot leg recirculation. CRO-333C

WA 006EA4.07 4.4/4.4

f. Shift Auxiliary buses between UA transformers and SU

transformers. CRO-245

WA 062A2.01 3.4/3.9

WA 024AA2.02 3.914.4

CRO-127A

WA 015A4.02 3.9/3.9

g.

h.

Perform an emergency boration. CRO-65B

Corrective actions in response to an Excore NIS failure.

4s

I

~~~

~

j. Shift AFW pump suction emergency supply. SO-31 1

WA 061A10.1 3.913.9

D A S

3

DS,L

6

M A A

1

D S

7

i. Align SGBD from Ruptured SG to Main Condenser

R, D

Bypassing the SGBD Demineralizers. SO-151B

KIA 035K1 .I

3 2.712.8

4P

k. Startup an Instrumentation Inverter. SO-344

D

WA 057AA1.01 3.713.7

6

FORMAL OJt REQUIRED PRIOR TO EVALUATION

~

_

~

_

~

~~

CRO-289

TITLE: Operate SW Pumps In Various Combinations

PROGRAM APPLICABLE: SOT -

SOCT -

O L T X LOCT

ACCEPTABLE EVALUATION M E T H 0 D : X PERFORM

SIMULATE -

DISCUSS

EVALUATION LOCATION: X SIMULATOR

CONTROL ROOM -

PLANT

PROJECTED TIME:

15 MIN

SIMULATOR IC NUMBER

IC-20 EXM

ALTERNATE PATH

TIME CRITICAL -

1A SWP = 55 degraded head, 1B SWP = BREAKER CLOSE/FAIL, 1C SWP = broken shaft

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perfom this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unit/train/component is potentially operated

4.

JPM Approved: Modified for NRC EXAM

Supervisor - Operations Training or Operations

JPM CORRECTION FORM

LESSON TITLE:

Operate SW Pumps In Various Combinations

NEEDED CORRECTION

(Typo, DCP, Tech. Error, Etc.)

LESSON NO.:

JPM CRO-289

INITIAL

Developer

PAGE

STANDARDS

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessaly queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

The conditions under which this task is to be performed are:

a. The Plant is in Mode 1.

b. Proper lube and cooling flow and oil levels have been verified.

c. You are directed by Shift Supervisor to start the C SW pump

B SW pump.

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

r vibration analysis and secure the

RESULTS:

(CIRCLE)

-

START TIME

1.

Verify the Systems Operator is standing by

at the SWIS to observe pump conditions

Personnel are stationed at SWIS.

(CUE: A Systems Operator is

stationed at the SWIS.)

S / U

NOTE: EXAMINEE SHOULD MENTION THAT HE WOULD ANNOUNCE THE STARTING

OF C SW PUMP AND SECURING B SW PUMP.

2.

Start the C SW pump, and as soon as the

red breaker closed indicating light is lit,

secure the B SW pump.

C SW pump is verified to have

started by the red breaker closed

indication light being lit; then B

SW pump is secured. (CUE: C

SW pump started, the red breaker

closed indication light is lit; B

SW pump is secured, the green

indication light is lit.)

S / U

ANNUNCIATOR AD4 WILL COME INTO ALARM:

THE FOLLOWING TWO STEPS MAY NOT BE ACCOMPLISHED

3.

Immediately verify that all isolation MOVs

SW to Turb Bldg and SW from

s / u

for SW to and from the Turbine Building

remain open:

QlP16V514, SW TO TURB BLDG B TRN

Turb Bldg isolation valves are

verified to remain open.

(CUE: SW to Turb Bldg and SW

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

QlP16V515, SW TO TURB BLDG A TRN

QlP16V516, SW TO TURB BLDG A TRN

QlP16V517, SW TO TURB BLDG B TRN

QlP16V540, SW FROM TURB BLDG A

HDR IS0

QlP16V541, SW FROM TURB BLDG B

HDR IS0

QlP16V542, SW FROM TURB BLDG A

HDR IS0

QlP16V543, SW FROM TURB BLDG B

HDR IS0

from the Turb Bldg isolation

valves remained open.)

4.

Check indications to verify that pressure in

PI-3001AA, SW to CCW Hx

s / u

A Train SW header is maintained between

70 and 115 psig as indicated by PI3001AA

discharge pressure is checked.

(CUE: PI-3001AA reads 55 psig.)

Alternate path starts here

5.

IAW ARP- AD4, transition should be made

AOP-10.0 referenced

S I U

to AOP-10.0. Loss of Service Water

6.

Verify affected 4160v breakers closed.

DF02 IS CHECKED CLOSED

S I U

(Cue: DF02 red light is lit)

Verify 1B SW pump started. (Cue:

1B SW pump is tripped on

overload.)

A train SW pressure will be < 60

psig. (Cue: A train SW pressure =

55 psig.)

7.

IF a SW pump trips, THEN verify Standby

SW pump started.

S J U

8.

IF SW pressure in both trains > 60 psig,

THEN go to procedure and step in effect.

S / U

9.

Check DG running.

DGs checked. (Cue: No DG

S I U

running.)

10.

Verify all available SW Pumps in

nonaffected train running

D/E SW Pumps are checked. (Cue:

D & E SW Pumps are running with

red light lit and proper SW

pressure for conditions.)

S J U

11.

Check SW pressure in nonaffected train >

PI-3001BA, SW to CCW Hx

s / u

60 psig.

discharge pressure is checked.

(CUE: PI-3001BA reads 80 psig.)

EVALUATION CHECKLIST

ELEMENTS:

12.

Verify operating CCW train supplied from

affected train. Start 1A CCW pump.

13. Verify Charging pump operating in

nonaffected train. Start 1C Chg pump.

14.

Secure 1A Chg pump.

STANDARDS:

A Train is affected. 1A CCW

pump is started. (Cue: 1A CCW

pump red light lit with flow, if

checked.)

1A Chg pump is running. Start

Charging pump operating in

nonaffected train. Start 1C Chg

Pump.

1A Charging pump handswitch is

taken to stop. (Cue: 1A Chg pump

green light lit, amps will go to 0.)

RESULTS:

(CIRCLE)

S I U

s / u

S I U

__ STOP TIME

Terminate when IC Chg pump is secured.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) preceding the element

number.

GENERAL REFERENCES:

1.

FNP-1-SOP-24.0, Version 50.0

2.

FNP-1-ARP-1.1, Version 35.0

3.

FNP-1-AOP- 10.0, Version 11.0

4.

K/A

076A2.01

RO-3.5

076A2.02

RO-2.7

GENERAL TOOLS AND EOUIPMENT:

None

COMMENTS:

SRO-3.7

SRO-3.1

CONDITIONS

The conditions under which this task is to be performed are:

a. The Plant is in Mode 1.

b. Proper lube and cooling flow and oil levels have been verified.

c. You are directed by Shift Supervisor to start the C SW pump for vibration analysis and secure the

B SW pump.

CRO-133A

TITLE: Start Up The Containment Cooling System

PROGRAM APPLICABLE: SOT -

SOCT -

O L T X LOCT-

ACCEPTABLE EVALUATION METHOD: X PERFORM X SIMULATE -

DISCUSS

EVALUATION LOCATION: X SIMULATOR

CONTROL ROOM -

PLANT

PROJECTED TIME:

10 MIN

SIMULATOR IC NUMBER

IC-13 EXM

ALTERNATE PATH -

TIME CRITICAL -

PRA -

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

e

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unit/train/component is potentially operated

4.

Approved By: JOE POWELL 09/07/01

Supervisor - Operations Training or Operations

JPM CORRECTION FORM

LESSON TITLE:

Start Up The Containment Cooling System

LESSON NO.:

CRO-133A

STANDARDS

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin, you are to START UP THE CONTAINMENT COOLING SYSTEM PER SOP

12.1. The conditions under which this task is to be performed are:

a.

b.

c.

d.

The unit is in Mode 5.

Repairs and modifications to the Containment Air Cooling System have been completed.

Testing has been completed satisfactory.

All preparations have been completed.

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

-

STARTTIME

1.

Open the service water containment

Takes handswitch for SW TO CTMT CLR

s / u

cooler inlet valves

QIP16MOV3019A, B, C andD

(QlP16VOlOA, B, C and D).

CLR lA, B, C, and D AND CTMT FPS

MOV3019A, B, C, and D to open. (CUE:

MOV3019A, B, C, & D are open.)

2.

Open the service water containment

Takes handswitch for SW FROM 1 A, B, C,

s / u

cooler outlet valves

QlP16MOV3441A, B, C, & D.

and D QlP16MOV3441A, B, C, and D to

open. (CUE: MOV3441A, B, C, and D are

open.)

3.

Open the service water containment

cooler discharge valves

QlP16MOV3023A, B, C, and D

(QlP16V044A, B, C, and D.)

Takes handswitch for 1 A, B, C, and D CTMT

CLR SW DISCH QlP16MOV3023A, B, C,

and D to open. (CUE: MOV3023A, B, C,

and D are open.)

S 1 U

4.

Verify service water flow through

Verifies service water flow through A&B

S / U

A&B containment coolers 22000 gpm. containment coolers 22000 gpm on FI-3013A

and 3014A. (CUE: Flow is as read or > 2000

gpm whichever is higher.)

EVALUATION CHECKLIST

ELEMENTS:

5.

Verify service water flow through

C&D containment coolers 22675 gpm

6.

Start containment coolers lA, lB, 1C

and 1D in FAST (SLOW) speed.

7.

Verify CTMT CLR lA(B) and IC(D)

DISCH 3 186A(B) and 3 186C(D)

OPEN light illuminated.

8.

Place containment dome recirculation

fans lA, IB, lC, and ID in HIGH

(LOW) speed.

9.

Operate the containment dome

recirculation fans and containment

coolers as necessary to maintain

CTMT temperature < 120°F.

lo.

Open 1A and 1B RX CAV CLG

DMPR QlE12HV3999A and B

(QlE12VOOlA and B).

-STOP

TIME

STANDARDS:

RESULTS:

(CIRCLE)

Verifies service water flow through C&D

S I U

containment coolers 22675 gpm on FI-3013B

and FI-3014B. (CUE: Flow is as read or >

2675 gpm whichever i s higher.)

Starts containment coolers lA, IB, IC and 1D S / U

in FAST speed by turning switches HOOl A,

B, C, and D to start. (CUE: The coolers are

running in FAST speed.)

Verifies CTMT CLR 1A(B) and 1C(D)

S I U

DISCH 3 186A(B) and 3 186C(D) OPEN light

illuminated. (CUE: The light is illuminated.)

Places containment dome recirculation fans

lA, IB, IC, and 1D in HIGH speed by

turning switches MOOIA, B, C, and D to

HIGH. (CUE: The dome recirculation fans

are running in HIGH speed.)

Operates the containment dome recirculation

fans as necessary to maintain containment

temperature < 120'F. (CUE: CTMT

temperature is 90°F and falling slowly.)

S / U

Open HV3999A and B by taking the

handswitch to the open position. (CUE:

HV3999A and B are open.)

S I U

i

Terminate when 1A and 1B reactor cavity cooling dampers are open.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) preceding the element

number.

GENERAL REFERENCES:

1. FNP-1-SOP-12.1, Version 23.0

2. US:

022A4.01 RO-3.6

SRO-3.6

022A4.03 RO-3.2

SRO-3.2

022A4.04 RO-3.1

SRO-3.2

022A4.05 RO-3.8

SRO-3.8

GENERAL TOOLS AND EOUIPMENT

None

COMMENTS:

CONDITIONS

When I tell you to begin, you are to START UP THE CONTAINMENT COOLING SYSTEM PER

SOP 12.1. The conditions under which this task is to be performed are:

a.

b.

c.

d.

The unit is in Mode 5.

Repairs and modifications to the containment air cooling system have been completed.

Testing has been completed satisfactory.

All preparations have been completed.

CRO-047A NRC MODIFIED

TITLE: Perform The Required Actions In Response To RCP Seal Failures

PROGRAM APPLICABLE: SOT -

SOCT -

O L T X L O C T X

ACCEPTABLE EVALUATION METHOD: X PERFORM X SIMULATE -

DISCUSS

EVALUATION LOCATION:

SIMULATOR

CONTROL ROOM -

PLANT

PROJECTED TIME:

5 MIN

SIMULATOR IC NUMBER:

JPM IC-8

ALTERNATE PATH X TIME CRITICAL -

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unit/train/component is potentially operated

4.

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

JPM Approved: JOE POWELL 09/07/01

Supervisor - Operations Training or Operations

12/09/02 0853

Page 2 of 5

JPM CORRECTION FORM

LESSON TITLE:

Perform The Required Actions In Response To RCP Seal Failures

LESSON NO.:

JPM CRO-047A

DATE

~

9/19/02

PAGE

3 & 5

NEEDED CORRECTION

(Typo, DCP, Tech. Error, Etc.)

Take the statement out that says: This is a pre-job

brief: in the condition section.

INITIAL

Developer

mgr

C:\\DATA\\I .X Drive\\pdff iles\\PDF Processing\\CRO-047A.DOC

12/09/02 08:53

Page 3 of 5

STANDARDS

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS IN RESPONSE TO RCP

SEAL FAILURES. The conditions under which this task is to be performed are:

a.

b.

c.

Plant is in Mode 1 at 100% power with Bank D rods at fully withdrawn.

RCP No. 1 seal leakoff flow Hi (DC2) MCB annunciator in alarm

RCP seal injection flow Lo (DDl) MCB annunciator in alarm

EVALUATION CHECKLIST

ELEMENTS:

-

START TIME

l.

2.

3.

4.

STANDARDS:

RESULTS:

(CIRCLE)

Determine value of #1 seal leakoff

FR-154Acheck. (CUE: 1A=2.6;

1B = 2.6; 1C =7.5) INSERT Next Page

S / U

Manually trip the reactor

Secure RCP C

Rx trip switch taken to trip. (CUE:

Rx trip breakers indicate open, all

rod bottom lights lit.)

S / U

C RCP handswitch taken to stop.

(CUE: RCP C breaker indicator

green light lit, amps = 0.)

S / U

Determine if C RCP has come to a

complete stop

Checks RCS loop flow indication.

(CUE: Loop C flow falls to 0%

and then returns to approx. lo%.)

S / U

C:\\DATA\\I .X Drive\\pdfFiles\\PDF Processing\\CRO-047A.DOC

Elements

Standards

Check #1 Seal Leakoff - Less Than 6 GPM

Check RCP Lower Seal Water Bearing and

Seal water outlet temperatures - Stable and

Less than 225'F

I Seal Leakoff is 7.5 GPM go to step 3, 4, 5

Temperature is greater than 225'F. Perform Element

Step 2.

-~

12/09/02 08 53

EVALUATION CHECKLIST

Page 4 of 5

RESULTS:

ELEMENTS:

STANDARDS:

(CIRCLE)

1

5.

Close RCP seal leakoff QlE21HV8141C

C RCP seal leakoff isolation

s / u

handswitch taken to close. (CUE:

QlE21HV8141C green light lit.)

-

STOP TIME

Terminate when QlE21HV8141C is closed

CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) before the element number.

GENERALREFERENCES

1.

FNP-I - ARP-I .4, Version 33

2.

WAS: 003 A2.01

RO-3.5

SRO-3.9

003 A2.02

RO-3.7

SRO-3.9

GENERAL TOOLS AND EQUIPMENT

None

COMMENTS

C \\DATA\\I X Dnve\\pdfF iles\\PDF Processing\\CRO-O47A DOC

CONDITIONS

When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS IN RESPONSE TO RCP

SEAL FAILURES. The conditions under which this task is to be performed are:

The Plant is in Mode 1 at 100% power with Bank D rods at fully withdrawn.

RCP No. 1 seal leakoff flow Hi (DC2) MCB annunciator in alarm.

RCP seal injection flow Lo (DDl) MCB annunciator in alarm.

b.

c.

C:\\DATA\\I .X Drive\\pdfFiles\\PDF Processing\\CRO-O47A DOC

FORMAL OJt REQUIRED PRIOR TO EVALUATION

CRO-277

TITLE: Perform Control Room Operations For A Liquid Waste Release

PROGRAM APPLICABLE: SOT -

SOCT -

O L T X LOCT

ACCEPTABLE EVALUATION METHOD: X PERFORM

DISCUSS

EVALUATION LOCATION: X SIMULATOR X CONTROL ROOM -

PLANT

SIMULATE

PROJECTED TIME:

15 MIN

SIMULATOR IC NUMBER:

IC- 1 8 EXM

ALTERNATE PATH -

TIME CRITICAL -

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

e

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong uniVtraidcomponent is potentially operated

4.

JPM Approved: 2003 NRC exam

Supervisor - Operations Training or Operations

JPM CORRECTION FORM

LESSON TITLE:

Perform Control Room Operations For A Liquid Waste Release

NEEDED CORRECTION

(Typo, DCP, Tech. Error, Etc.)

PAGE

LESSON NO.:

JPM CRO-277

INITIAL

Developer

DATE

STANDARDS

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin, you are to PERFORM CONTROL ROOM OPERATIONS FOR A LIQUID

WASTE RELEASE. The conditions under which this task is to be performed are:

a. A liquid waste release permit has been issued for the release of #1 WMT.

b. The System Operator has requested that you perform a test on radiation monitor R-18 per SOP-50.1,

Section 4.3.

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

-

START TIME

lfcandidate ash about WMTpump maintenance beingpeformed, tell them, NO pump maintenance

has been performed.

1.

Verify WMT #I and #2 discharge valves

Direct SO toverify: QlG2lVlll

S I U

locked closed

and QlG21V114 locked closed.

(CUE: SO reports that both valves

are locked closed.)

2.

Source check R-18

3.

OpenRCV-1 [I. .(2)G21V1

Place switch for R-18 to check

source and verify upscale reading.

(CUE: R-18 up scales, BLUE

channel test light illuminates on

the R-18 drawer and MCB

annunciator FH3 alarms)

s / u

Direct SO to open RCV-18.

S

(CUE: SO reports RCV-18 is

open.)

NOTE: SIMULATOR OPERATOR : INITIATE MK4 ALARM WHEN CANDIDATE IS

TURNING R-18 POT COUNTER CLOCKWISE.

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

4.

Initiate a high alarm on R-18 by lowering

Potentiometer adjusted counter-

s / u

potentiometer setpoint

clockwise to alarm. (CUE: Red

HIGH ALARM light is on. MCB

annunciator FHl alarms. RMS

panel alarm sounds.)

5.

Verify RCV-18 automatically closed

Direct SO to check RCV-18

s / u

closed. (CUE: SO reports RCV-

18 closed.)

6.

Attempts to open RCV-18

Direct SO to attempt to open RCV- S / U

18. (CUE: SO reports that RCV-

18 did not open when control

switch was placed in OPEN.)

NOTE: SIMULATOR OPERATOR CLEAR MK4 ALARM PRIOR TO CALLING CONTROL

ROOM WITH ABOVE INFORMATION.

7.

Adjust potentiometer to original setpoint

Potentiometer adjusted clockwise.

S / U

which was 6.0.

(CUE: Potentiometer adjusted to

original setpoint, 6.0.)

8.

Reset the high alarm on R-18

Operation selector switch placed in S / U

RESET position. (CUE: Red

HIGH ALARM light is off. Blue

CHANNEL TEST light is on.

MCB annunciator FHl is clear and

annunciator FH3 is in alarm.)

9.

Restore R-18 to normal

Operation Selector switch returned

to OPERATE position. (CUE:

Blue CHANNEL TEST light is

off. MCB annunciator FH3 is

clear.)

S / U

CUE: SIMULATOR OPERATOR Call CR as the Rad side SO to REQUEST THAT R-18

SETPOINT BE ADJUSTED FOR 5 10,000 CPM WITH > 20,000 GPM SERVICE WATER

DILUTION FLOW.

lo.

Adjust R-18 setpoint to value obtained from

Potentiometer adjusted to 15.70

S / U

discharge permit

per Figure 1 or Curve Book.

(CUE: Potentiometer is set at

5.70.)

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

NOTE: IF SERVICE WATER FLOW RECORDER IS NOT WORKING, THEN CUE

EXAMINEE THAT FLOW IS INDICATED AT 28,000 GPM.

11.

Verify SW dilution flow acceptable for

Dilution flow recorder check.

s / u

release

(CUE: SW dilution flow recorder

FR-4107 indicates 28,000 gpm.)

-

STOP TIME

Terminate when dilution flow is verified.

CRITICAL ELEMENTS: Critical elements are denoted with an Asterisk (*) preceding the element

number.

GENERAL REFERENCES:

1.

FNP-1- SOP-50.1, Version 48.0

2.

WAS: 068A4.01

RO-3.8

SRO-3.7

GENERAL TOOLS AND EOUIPMENT:

1.

FNP-1- SOP-50.1, Figure 1

2.

COMMENTS:

Operating Curve Book Volume 111

CONDITIONS

When I tell you to begin, you are to PERFORM CONTROL ROOM OPERATIONS FOR A LIQUID

WASTE RELEASE. The conditions under which this task is to be performed are:

a. A liquid waste release permit has been issued for the release of #1 WMT.

b. The System Operator has requested that you perform a test on radiation monitor R-18 per

SOP-50.1, Section 4.3.

FORMAL OJT REQUIRED PRIOR TO EVALUATION

CRO-333C

TITLE: Perform The Required Actions For Transfer to Simultaneous Cold Leg and Hot Leg

PROGRAM APPLICABLE: SOT -

SOCT -

O L T X L O C T X

ACCEPTABLE EVALUATION METHOD: X PERFORM X SIMULATE -

DISCUSS

EVALUATION LOCATION:

PROJECTED TIME:

15 MIN

SIMULATOR IC NUMBER

IC-14 EXM

Recirculation

SIMULATOR X CONTROL ROOM -

PLANT

ALTERNATE PATH X TIME CRITICAL - -

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

e

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unit/train/component is potentially operated

4.

Evaluator/Date:

Overall JPM Performance:

I Satisfactory

10

1 Unsatisfactory I 0

Evaluator Comments (attach additional sheets if necessary)

JPM Approved: C F Barefield 09/07/01

Supervisor - Operations Training or Operations

JPM CORRECTION FORM

LESSON TITLE:

Perform The Required Actions For Transfer to Simultaneous Cold Leg

and Hot Leg Recirculation

LESSON NO.:

JPM CRO-333C

DATE

PAGE

NEEDED CORRECTION

(Typo, DCP, Tech. Error, Etc.)

INITIAL

Developer

STANDARDS

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS FOR TRANSFER TO

SIMULTANEOUS COLD LEG AND HOT LEG RECIRCULATION. The conditions under which this

task is to be performed are:

a. A safety injection is in progress following a Large Break LOCA on Unit 1.

b. Seven and one-half hours have passed since the LOCA event started.

c. 1B Chg Pump is aligned to A train.

d. Directed by Shift Supervisor to align ECCS for Transfer To Simultaneous Cold Leg and Hot Leg

Recirculation starting at Step 1 of ESP-1.4.

Make sure ESP-1.4 rev 12 is in SIMULATOR PROCEDURE BOOK PRIOR TO RUNNING THIS.

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

__ START TIME

1.

Close lA(B) RHR HX TO RCS COLD

LEGS IS0 QlEllMOV8888A and 8888B.

Handswitch for MOV8888A & B

are taken to CLOSED. (CUE:

MOV8888A & B green lights lit,

valves are closed)

Handswitch for MOV8887A & B

are taken to OPEN. (CUE:

MOV8887A & B red lights lit,

valves are open)

S / U

2.

Open RHR TO RCS HOT LEGS XCON

QlEllMOV8887A and 8887B.

S I U

Alternate path starts here.

3.

Open RHR TO RCS HOT LEGS IS0

Handswitch for MOV8889 taken

S / U

QlEllMOV8889.

to OPEN. (CUE: MOV 8889

green light lit, valve remains

closed.)

Handswitch for MOV8887A & B

are taken to CLOSED. (CUE:

MOV8887A & B green lights lit,

valves are closed)

4.

Close RHR TO RCS HOT LEGS XCON

QlEl lMOV8887A and 8887B

S / U

EVALUATION CHECKLIST

ELEMENTS:

5.

Verify closed RHR TO RCS HOT LEGS

IS0 QlEllMOV8889

6.

Open lA(B) RHR HX TO RCS COLD

LEGS IS0 QlEl 1MOV8888A and 8888B.

7.

Stop 1A Chg Pump.

8.

Close HHSI TO RCS CL IS0 valves

QlE21MOV8803A and B

9.

Open CHG PUMP RECIRC TO HOT

LEGS valve QlE21MOV8886.

12.

Start either 1A or 1B HHSI Pump.

STANDARDS:

Light for MOV8889 checked.

(CUE: MOV8889 green light lit,

valve is closed.)

Handswitch for MOV8888A & B

are taken to OPEN. (CUE:

MOV8888A & B red lights lit,

valves are open.)

Handswitch for 1A Chg Pump

taken to OFF. (CUE: 1A Chg

Pump amps go to 0 and green

light lit.)

Handswitch for HHSI TO RCS CL

IS0 valves QlE21MOV8803A &

B taken to CLOSED. (CUE:

MOV8803A & B green lights lit,

valves are closed)

Handswitch for MOV8886 taken

to OPEN. (CUE: MOV 8886 red

light lit, valve is open.)

Handswitch for 1A or 1B HHSI

Pump taken to START. (CUE:

Pump red light lit, amps increase.)

RESULTS:

(CIRCLE)

S I U

s / u

S I U

NOTE:

IF EXAMINEE OBSERVES CHG PUMP AMPS - CUE: CHG PUMP AMPS 170

AND STABLE.

13.

Stop 1C Chg Pump

Handswitch for 1C Chg Pump

S I U

taken to OFF. (CUE: 1C Chg

Pump amps go to 0 and green

light lit.)

14.

Close CHG PUMP RECIRC TO RCS

Handswitch for MOV8885 taken

S / U

COLD LEGS valve QlE21MOV8885

to CLOSE. (CUE: MOV 8885

green light lit, valve is closed.)

I5

Open CHG PUMP RECIRC TO RCS HOT

Handswitch for MOV8884 taken

S I U

LEGS valve QlE21MOV8884

to OPEN. (CUE: MOV 8884 red

light lit, valve is open.)

EVALUATION CHECKLIST

ELEMENTS:

16.

Start 1C HHSI Pump

STANDARDS:

RESULTS:

(CIRCLE)

Handswitch for 1C HHSI Pump

taken to START. (CUE: Pump red

light lit, amps increase.)

S / U

NOTE: IF EXAMINEE OBSERVES CHG PUMP AMPS - CUE: CHG PUMP AMPS 170 AND

STABLE.

17.

Check RHR pumps aligned to the hot legs

Alignment checked for proper

s / u

and at least one train HHSI aligned to cold

legs OR RHR pumps aligned to cold legs

and at least one train HHSI aligned to hot

legs.

aligned for hot legs.)

RHR and HHSI line-up. (CUE:

Both Trains RHR aligned to cold

legs and both Trains HHSI is

18.

Verify SI flow stable

Flow checked on FI-943,940,

S I U

HHSI Flow A (B) train recirc flow

and FI-605N605B RHR HDR

flow. (CUE: FI-943 and FI-940

stable at 600 gpm. FI-605A and

FI-605 stable at 2600 gpm.)

__ STOP TIME

Terminate JPM.

CRITICAL ELEMENTS: Critical elements are denoted with an Asterisk (*) preceding the element

number.

GENERAL REFERENCES:

1. FNP-1- ESP-1.4, Rev. 12

2. KIA: 006 EA4.07

RO-4.4

SRO-4.4

GENERAL TOOLS AND EQUIPMENT:

None

COMMENTS:

CONDITIONS

When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS FOR TRANSFER TO

SIMULTANEOUS COLD LEG AND HOT LEG RECIRCULATION. The conditions under which this

task is to be performed are:

a. A safety injection is in progress following a Large Break LOCA on Unit 1.

b. Seven and one-half hours have passed since the LOCA event started.

c. 1B Chg Pump is aligned to A Train.

d. Directed by Shift Supervisor to align ECCS for Transfer To Simultaneous Cold Leg and Hot Leg

Recirculation starting at Step 1 of ESP-1.4.

CRO-245

TITLE: Shift Auxiliary Buses Between The Unit Auxiliary Transformer And The Startup

PROGRAM APPLICABLE: SOT -

SOCT -

O L T X LOCTJ

ACCEPTABLE EVALUATION METHOD:

PERFORM X SIMULATE -

DISCUSS

EVALUATION LOCATION X SIMULATOR X CONTROL ROOM -

PLANT

Transformers

PROJECTED TIME:

5 MIN

SIMULATOR IC NUMBER

JPM IC-26

ALTERNATE PATH -

TIME CRITICAL -

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unit/train/component is potentially operated

4.

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

JPM Approved: C F Barefield 09/07/01

Supervisor - Operations Training or Operations

12109102 10:28

Page 2 of 6

JPM CORRECTION FORM

LESSON TITLE:

Shift Auxiliary Buses Between The Unit Auxiliary Transformer And The

Startup Transformers

LESSON NO.:

JPM CRO-245

5/08/02 I 5

5/15/02

I 4 & 5

9/23/02 I

NEEDED CORRECTION

(Typo, DCP, Tech. Error, Etc.)

Updated version number for SOP-36.2

El 1 & 13 Changed typo from 1A to the proper 1B

& 1C where appropriate.

Take the statement out that says: "This is a pre-

job brief:" in the condition section.

C:\\DATA\\I .X Drive\\pdfFiles\\PDF Processing\\CRO-245.DOC

INITIAL

Developer

CVR

12/09/02 10:28

STANDARDS

Page 3 of 6

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin, you are to SHIFT AUXILIARY BUSES BETWEEN THE UNIT AUXILIARY

TRANSFORMER AND THE STARTUP TRANSFORMERS. The conditions under which this task is to

be performed are:

a. Plant startup in progress per UOP-1.2

b. Reactor power is 20 - 25%

c. Unit auxiliary and startup transformers are prepared for operation per SOP-36.1

d. Directed by Shift Supervisor to place 4160V Bus A, B, and C on their normal supply per SOP-36.2.

EVALUATION CHECKLIST

ELEMENTS:

-

START TIME

1.

2.

3.

4.

5.

Turn voltmeter selector switch to bus A

position

Turn A bus synchronizing switch to the

MAN position

After 10 seconds then close the normal

supply breaker

Verify alternate supply breaker opens

Checks bus energized

STANDARDS:

RESULTS:

(CIRCLE)

Bus A selected on switch. (CUE:

Voltmeter indicates 4160V.)

S / U

MAN selected. (CUE:

s / u

Synchronizing meter indicates 12

oclock position, white indicating

light not lit.)

Breaker DAOl handswitch taken to

close. (CUE: Breaker position

indicator red light lit.)

Breaker DA07 position checked.

(CUE: Breaker position indicator

green light lit.)

Voltmeter and/or potential light for

1A bus checked. (CUE: For each

one checked voltmeter indicates

4160V and potential light is on.)

S / U

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12/09/02 1028

EVALUATION CHECKLIST

ELEMENTS:

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

Turn synchronizing switch to OFF

Turn voltmeter selector switch to bus B

position

Turn bus synchronizing switch to the MAN

position

After 10 seconds then close the normal

supply breaker

Verify alternate supply breaker opens

Checks bus energized

Turn synchronizing switch to OFF

Turn voltmeter selector switch to bus C

position

Turn bus synchronizing switch to the MAN

position

After 10 seconds then close the normal

supply breaker

Verify alternate supply breaker opens

STANDARDS:

OFF selected. (CUE:

Synchroscope goes to fail

position.)

Bus B selected on switch. (CUE:

Voltmeter indicates 41 60V.)

MAN selected. (CUE:

Synchronizing meter indicates 12

oclock position, white indicating

light not lit.)

Breaker DBOl handswitch taken to

close. (CUE: Breaker position

indicator red light lit.)

Breaker DB05 position checked.

(CUE: Breaker position indicator

green light lit.)

Page 4 of 6

RESULTS:

(CIRCLE)

S I U

Voltmeter andlor potential light for S I U

1B bus checked. (CUE: For each

one checked voltmeter indicates

4160V and potential light is on.)

OFF selected. (CUE:

S I U

Synchroscope goes to fail

position.)

Bus C selected on switch. (CUE:

Voltmeter indicates 4160V.)

S I U

MAN selected. (CUE:

S I U

Synchronizing meter indicates 12

oclock position, white indicating

light not lit.)

Breaker DC04 handswitch taken to

close. (CUE: Breaker position

indicator red light lit.)

S / U

Breaker DCOl position checked.

S I U

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12/09/02 10 28

EVALUATION CHECKLIST

Page 5 of 6

RESULTS:

ELEMENTS:

STANDARDS:

(CIRCLE)

(CUE: Breaker position indicator

green light lit.)

17.

Checks bus energized

Voltmeter and/or potential light for S / U

1C bus checked. (CUE: For each

one checked voltmeter indicates a

4160V and potential light is on.)

18.

Turn synchronizing switch to OFF

OFF selected. (CUE:

s / u

Synchroscope goes to fail

position.)

-

STOP TIME

Terminate when synchronizing switch is selected to OFF.

CRITICAL ELEMENTS: Critical elements are denoted with an Asterisk (*) preceding the element

number

GENERAL REFERENCES:

1.

FNP-1- SOP-36.2 Version 8

2.

WAS 062A2.01

RO-3.4

SRO-3.9

062A2.04

RO-3.1

SRO-3.4

GENERAL TOOLS AND EQUIPMENT:

None

COMMENTS:

C:\\DATA\\I .X Drive\\pdfFiles\\PDF Processing\\CRO-245.DOC

12109102 10:28

Page 6 of 6

CONDITIONS

When I tell you to begin, you are to SHIFT AUXILIARY BUSES BETWEEN THE UNIT

AUXILIARY TRANSFORMER AND THE STARTUP TRANSFORMERS. The conditions under

which this task is to be performed are:

a. Plant startup in progress per UOP-1.2

b. Reactor power is 20 - 25%

c. Unit auxiliary and startup transformers are prepared for operation per SOP-36.1

d. Directed by Shift Supervisor to place 4160V Bus A, B, and C on their normal supply per SOP-

36.2.

C:\\DATA\\I .X Drive\\pdFiles\\PDF Processing\\CRO-245.DOC

CRO-065 NEW

TITLE: Perform An Emergency Boration

PROGRAM APPLICABLE: SOT -

SOCT -

O L T X L O C T X

ACCEPTABLE EVALUATION METHOD:

PERFORM

SIMULATE -

DISCUSS

EVALUATION LOCATION: X SIMULATOR X CONTROL ROOM -

PLANT

PROJECTED TIME:

5 MIN

SIMULATOR IC NUMBER

IC-15 EXM

Place HOLD TAG on 1A BAT PUMP HS

ALTERNATE PATH __ TIME CRITICAL -

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

0

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unititraidcomponent is potentially operated

4.

JPM Approved: 2003 NRC EXAM

Supervisor - Operations Training

Operations

JPM CORRECTION FORM

LESSON TITLE:

Perform An Emergency Boration

NEEDED CORRECTION

DATE

PAGE

(Typo, DCP, Tech. Error, Etc.)

LESSON NO.:

JPM CRO-065 NEW

INITIAL

Developer

STANDARDS

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin, you are to PERFORM AN EMERGENCY BORATION. The conditions under

which this task is to be performed are:

a.

b.

c.

d.

e.

The Chemical and Volume Control System is in operation.

1A BAT pump is 00s for maintenance; 1B BAT pump is on service.

The Plant is in Mode 3 at normal operating temperature.

An error in the shutdown margin calculation has been discovered and it has been determined

that actual shutdown margin is less than the requirement of Technical Specifications.

The Shift Supervisor directs you to perform the actions of AOP-27.0.

EVALUATION CHECKLIST

ELEMENTS:

-

START TIME

l.

2.

3.

4.

Start 1 B BAT pump.

Align normal emergency boration

flowpath.

Verify at least one charging pump started.

Establish adequate letdown.

STANDARDS:

1B BAT Pump handswitch taken

to start. (CUE: Breaker indication

red light lit.)

Handswitch for MOV-8 104 taken

to open. (CUE: Valve position

indicator goes from green to red.

FI-11 OA indicates 0 gpm.)

Charging pump indications

checked. (CUE: Pump breaker

indicator red light lit; pump amps

are 85, FI-122 flow is 108 gpm.)

45 gpm LTDN orifice isolation

valve 8149A and either 8149B or

C verified open. (CUE: Valve

position indicator red lights lit for

8149A and either 8149B or C

letdown flow gpm 120.)

RESULTS:

(CIRCLE)

s / u

S I U

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

5.

Establish adequate charging flow.

6.

Verify emergency boration flow adequate.

Alternate path starts here

7.

Verify boration flow path using

ATTACHMENT 1

8.

Verify running charging pump header

valves open. (checks 1A charging pump

running)

9.

Check emergency boration > 30 gpm.

ATTACHMENT 1 alternatepath starts here

lo. Align charging pump suction to RWST

1 1.

Verify CHG PUMPS TO

REGENERATIVE HX MOV8107/8108

are open.

Verify only one charging line valve open,

either MOV 8146 or 8147.

12.

13.

Verify charging flow > 92 gpm.

Verify charging flow greater than

40 gpm by checking FI-122.

(CUE: Charging flow on FI-122

indicates 108 gpm.)

Checks emergency boration flow

greater than 30 gpm. (CUE: FI-

1 10 indicates 0 gpm.)

S / U

ATTACHMENT 1 opened.

s / u

Verifies CHG PUMP SUCTION

S / U

8130A,8130B,813 lA,813 1B open.

(CUE: For each item checked,

valve is open, red light is lit.)

Checks emergency boration flow

greater than 30 gpm. (CUE: FI-

1 10 indicates 0 gpm.)

HDR IS0 QlE21MOV-

S / U

Open RWST TO CHG PUMP

S f U

QlE21LCV115B and

QlE21LCVl15D. Close VCT

OUTLET IS0 QlE21LCV115C

and QlE21LCVllSE (CUE: LCV

115B/D breaker indicator red light

lit and LCV 11 5C/E breaker

indicator Green light lit)

MOV8107/8108checked. (CUE:

S / U

MOVs are open, Red light is lit.)

MOV 8146 and 8147 checked.

(CUE: red light is lit on only one

of the valves.)

s / u

Charging flow checked. (Cue:

s / u

charging flow is 108 gpm.)

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

s / u

14.

Notify the shift supervisor ofboration

SS notified.

status.

-

STOP TIME

Terminate when SS notified.

CRITICAL ELEMENTS: Critical Elements are denoted by an Asterisk (*) before the element number.

GENERAL REFERENCES

1.

FNP-1-AOP-27.0, Version 8.0

2.

Technical Specifications

3.

WAS: 024 AA1.17

RO-3.9

SRO-3.9

024 AA2.01

RO-3.8

SRO-4.1

GENERAL TOOLS AND EQUIPMENT

None

COMMENTS

CONDITIONS

When I tell you to begin, you are to PERFORM AN EMERGENCY BORATION. The conditions under

which this task is to be performed are:

a.

b.

c.

d.

e.

The Chemical and Volume Control System is in operation.

1A BAT pump is 00s for maintenance; 1B BAT pump is on service.

The Plant is in Mode 3 at normal operating temperature.

An error in the shutdown margin calculation has been discovered and it has been determined

that actual shutdown margin is less than the requirement of Technical Specifications.

The Shift Supervisor directs you to perform the actions of AOP-27.0.

CRO-127A

TITLE: Perform Corrective Actions In Response To A Malfunction Of The Excore NIS - Power

PROGRAM APPLICABLE: SOT -

SOCT -

O L T X LOCTJ

ACCEPTABLE EVALUATION METHOD: X PERFORM

SIMULATE -

DISCUSS

ALUATION LOCATION: X SIMULATOR X CONTROL ROOM -

PLANT

PROJECTED TIME:

10 MIN

SIMULATOR IC NUMBER:

IC- 17 EXM

II

Range Failure

ALTERNATE PATH -

TIME CRITICAL -

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

0

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unitkraidcomponent is potentially operated

4.

JPM Approved: MODIFIED FOR 2003 NRC EXAM

Supervisor - Operations Training or Operations

JPM CORRECTION FORM

PAGE

LESSON TITLE:

Perform Corrective Actions In Response To A Malhnction of the Excore

NIS - Power Range Failure

NEEDED CORRECTION

INITIAL

Developer

(Typo, DCP, Tech. Error, Etc.)

LESSON NO.:

JPM CRO-127A

DATE

STANDARDS

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin, you are to PERFORM CORRECTIVE ACTIONS IN RESPONSE TO A

MALFUNCTION OF THE EXCORE NIS - POWER RANGE FAILURE. The conditions under which thi:

task is to be performed are:

a. The Plant is at 100% power with the ramp on hold for a calorimetric.

b. N44 upper detector current indicator has failed low.

c. You are to perform annunciator FB4 supplementary actions.

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

-

START TIME

1.

Verify rod control is in manual.

Rod control is placed in manual.

s / u

(CUE: The rods are in manual.)

Rod stop bypass switch taken to N- S / U

44. (CUE: Selector switch in N-

44 position.)

2.

Defeat the rod stop bypass for N-44.

3.

Defeat the channel comparator for N-44.

N-44 selected on comparator

s / u

channel defeat switch. (CUE:

Annunciator FC5 has cleared.)

4.

Defeat the upper and lower detector on the

N-44 selected on the upper and

S I U

detector current comparator drawer for

N-44.

switches. (CUE: Annunciators

lower detector current comparator

FB4 and FB5 cleared.)

EVALUATION CHECKLIST

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

5.

Remove the control power fuses from the

Correct fuses removed. (CUE:

S I U

A drawer for N-44.

Annunciators FCl & FC3 alarm &

the drawer bistable lights go dark.

Examinee should recognize that

7300 cabinet test switches are not

required to be operated for NI-44

failure.)

__ STOP TIME

Terminate after the fuses are removed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) preceding the element

number.

GENERAL REFERENCES

1.

FNP-1-ARP-1.6, Version 37.0

2.

FNP-2-ARP- 1.6, Version 3 1 .O

3.

UAs: 015A4.02

RO-3.9

SRO-3.9

015A2.01

RO-3.5

SRO-3.9

GENERAL TOOLS AND EQUIPMENT

None

COMMENTS

CONDITIONS

When I tell you to begin, you are to PERFORM CORRECTIVE ACTIONS IN RESPONSE TO A

MALFUNCTION OF THE EXCORE NIS - POWER RANGE FAILURE. The conditions under which

this task is to be performed are:

a. The Plant is at 100% power with the ramp on hold for a calorimetric.

b. N44 upper detector current indicator has failed low.

c. You are to perform annunciator FB4 supplementary actions.

12/09/02 I I :38 AM

Page 1 of 7

SO-151B

TITLE: Align SGBD From Ruptured SG To Main Condenser Bypassing The SGBD Demineralizers

PROGRAM APPLICABLE: SOT X SOCT -

OLT -

LOCT

ACCEPTABLE EVALUATION METHOD: -

PERFORM -

SIMULATE -

DISCUSS

EVALUATION LOCATION: -

SIMULATOR -

CONTROL ROOM -

PLANT

PROJECTED TIME:

45 MIN

SIMULATOR IC NUMBER N/A

ALTERNATE PATH -

TIME CRITICAL -

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

0

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unitltraidcomponent is potentially operated

4.

JPM Approved: JOE POWELL 10/09/01

Supervisor - Operations Training or Operations

C\\DATA\\I .X Drive\\pdfFiles\\PDF Processing\\SO- I5 I B.DOC

12/09/02 I I .38 AM

Page 2 of 7

JP M CORRECTION FORM

LESSON TITLE:

Align SGBD From Ruptured SG To Main Condenser Bypassing The

SGBD Demineralizers

LESSON NO.:

JPM SO-151B

DATE

9/30/02

PAGE

3 & 7

NEEDED CORRECTION

(Typo, DCP, Tech. Error, Etc.)

Take the statement out that says: This is a pre-job

brief: in the condition section.

INITIAL

Developer

C:\\DATA\\I .X Drive\\pdffiles\\PDF Processing\\SO-15 1 B.DOC

STANDARDS

Apply the following criteria during the performance of this JPM:

4.

Set SGBD heat exchanger temperature

HIK-1150 adjusted to maintain 5

S 1 U

controller HIK-1150 to maintain 5 190°F

190°F. (CUE: HIK-I 150 properly

adjusted.)

clockwise. (CIJE: V005 is open.)

5.

Open SGBD inlet filter bypass

N1[2]G24VOOSis turned counter-

S / U

N1[2]G24V005(V-7641)

C:\\DATA\\I .X Drive\\pdfFiles\\PDF Processing\\SO- I5 1 B.DOC

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin you are to ALIGN SGBD FROM RUPTURED SG TO MAIN CONDENSER

BYPASSING THE SGBD DEMINERALIZERS PER SOP-16.1. The conditions under which this task is to

be performed are:

a. Unit 1 has experienced a tube rupture in the B steam generator and ESP-3.2 is in progress.

b. The SGBD system was previously secured per SOP-16.1.

c. All other systems are aligned per the appropriate step.

d. All initial conditions of SOP-16.1 have been met.

e. The control room instructs you to align SGBD from the B SG bypassing the deminerilizers to the

main condenser.

f. RCV-023B has been verified closed per ESP-3.2.

NOTE: THIS JPM MAY BE PERFROMED ON EITHER UNIT. THE UNIT TWO NUMBERS

ARE [BRACKETED].

11

EVALUATION CHECKLIST

ELEMENTS:

I

STANDARDS:

RESULTS:

(CIRCLE)

START TIME

111 -

1.

Place range selector switch in HIGH

Range selector switch taken to

S I U

RANGE

high range. (CUE: Range selector

is in high range.)

2.

Verify demin temperature divert valve

TCV-1150 green closed light lit.

S I U

N1[2]G24V086(TCV-1150) closes

(CUE: TCV-1150 is closed.)

3.

Open demin bypass valve

N1[2]G24V026(HV-7604)

I

The handswitch for HV-7604 is

taken to the open position. (CUE:

HV-7604 is open)

S I U

12/09/02 I1:38 AM

EVALUATION CHECKLIST

ELEMENTS:

Page 4 of 7

STANDARDS:

RESULTS:

(CIRCLE)

6

Close SGBD inlet filter inlet and outlet

N1[2]G24V007 and

s / u

isolation.

N1[2]G24V009Vis turned

clockwise. (CUE: V007 and

V009 are closed.)

7.

Open SGBD to main condenser.

The handswitch for HV-7607 is

S I U

placed in the open position. (CUE:

V013 is open.)

NOTE TO EXAMINER IT IS PERMISSABLE TO CONTACT TB SYSTEMS OPERATOR TO

VERIFY V501 OPEN IN THE FOLLOWING STEP. EXAMINEE

MAY POINT OUT V501 WHEN JPM COMPLETED. (CUE: TB

SYSTEMS OPERATOR HAS VERIFIED V501 OPEN.)

8.

Verify open main condenser isolation.

N1[2]G24V501is turned counter-

S / U

clockwise and verified open.

(CUE: V501 is open.)

PIC-1 151 is placed in manual by

pushing the A/M button to display

M. Press the SEL button until the

blue dot is over the setpoint

section. Use the up/down arrows

to adjust the setpoint to 200 PSID.

(CUE: PIC-1 151 is set at 200

PSID.)

9.

Set SGBD heat exchanger outlet pressure

controller N 1 [2]G24V 136(PIC- 1 15 1) to

maintain differential pressure (stndhdr inlet)

-

< 200 PSID

S / U

10.

On the Main Control Board, open the B

Steam Generator CTMT Isolation Valve

11.

Verify open PRIP isolation valves for the

B SG.

Contact control to open

s / u

N1[2]G24HV-7614B. (CUE:

CRO acknowledges and informs

you that HV-7614B is open.)

Q1[2]G24HV-7698A and

S I U

Q 1 [2]G24HV-7698B handswitches

taken to close and held until the

green light goes out. (CUE: HV-

7698A and HV-7698B red lights

are lit.)

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12/09/02 11:38AM

EVALUATION CHECKLIST

Page 5 of 7

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

12.

Open the SGBD heat exchanger outlet auto

N1[2]G24FCV-1152 handswitch

S / U

trip valve

taken to open, Red open light lit

and returned to auto. (CUE: FCV-

1152 red open light lit and

handswitch is in auto)

I CUE: SHIFT SUPERVISOR REQUEST SGBD FLOW FROM B SG TO BE 40 GPM.

13.

Adjust SGBD flow control valve to proper

flowrate

14.

Place SGBD surge tank level control valve

in auto and set to maintain =: 50%

15.

Start SGBD pump

N1[2]G24HV1172 Controller

s / u

adjusted until =: 40 gpm indicated

on flow indicator. (CUE: Flow

from B SG indicating 40 gpm.)

N1[2]G24LCV-1158 is placed in

auto and setpoint adjusted to

maintain =. 50%. (CUE: LCV-

1158 is in auto and setpoint at =:

50%)

Check the surge tank level greater

than 10% and start a pump. (CUE:

Surge tank level is 60 % and

SGBD pump A is running)

S / U

-

STOP TIME

[

Terminate JPM when SGBD pump is running.

CRITICAL ELEMENTS: CRITICAL ELEMENTS ARE DENOTED BY AN ASTERISK (*) IN FRONT

OF THE ELEMENT NUMBER.

C:\\DATA\\I.X Drive\\pdffiles\\PDF Processing\\SO-151 B.DOC

12/09/02 11:38 AM

GENERAL REFERENCES:

1.

FNP-1-SOP-16.1, Version 22.0

2.

FNP-2-SOP-16.1, Version 19.0

3.

WAS: 035K1.03

RO-2.4

SRO-2.9

4.

FNP-1-ESP-3.2, Version 16.0

5.

FNP-2-ESP-3.2, Version 13.0

GENERAL TOOLS AND EQUIPMENT:

None

COMMENTS:

Page 6 of 7

C:\\DATA\\I .X Drive\\pdfFiles\\PDF Processing\\SO-I 5 I B.DOC

CONDITIONS

When I tell you to begin you are to ALIGN SGBD FROM RUPTURED SG TO MAIN CONDENSER

BYPASSING THE SGBD DEMINERALIZERS PER SOP-16.1. The conditions under which this task

is to be performed are:

a. Unit 1 has experienced a tube rupture in the B steam generator and ESP-3.2 is in progress.

b. The SGBD system was previously secured per SOP-16.1.

c. All other systems are aligned per the appropriate step.

d. All initial conditions of SOP-16.1 have been met.

e. The control room instructs you to align SGBD from the B SG bypassing the demineralizers to

the main condenser.

f.

RCV-023B has been verified closed per ESP-3.2.

SO-311

TITLE: Shift Auxiliary Feed Pump Suction Emergency Supply

PROGRAM APPLICABLE: SOT

SOCT X OLT

LOCT

ACCEPTABLE EVALUATION METHOD: X PERFORM

SIMULATE -

DISCUSS

EVALUATION LOCATION: __ SIMULATOR -

CONTROL ROOM J

PLANT

PROJECTED TIME:

20 MIN

SIMULATOR IC NUMBER N/A

ALTERNATE PATH -

TIME CRITICAL -

PRA __

JPM DIRECTIONS:

1.

2.

3.

Access to tools, equipment, and references normally used to perform this task are allowed.

During initial training, it is encouraged that questions be asked as part of this OJT process to

assess the extent of trainee knowledge related to this task.

If the trainee is significantly deficient in knowledge or does not adhere to management

expectations as outlined below, then a re-examination of the JPM is warranted.

Potential physical harm could occur to the trainee or others

Potential damage to equipment could occur

A procedure step is missed in a continuous use procedure

Significant margin to reactor safety is eroded

Wrong unit/train/component is potentially operated

4.

All unsuccessful attempts, deficiencies, and other comments must be documented in the space

below and forwarded to a Training Administrative Assistant for tracking.

JPM Approved: JOE POWELL 03/05/02

Supervisor - Operations Training or Operations

12/09/02 11:43

Page 2 of 5

JPM CORRECTION FORM

LESSON TITLE:

Shift Auxiliary Feed Pump Suction Emergency Supply

LESSON NO.:

JPM SO-3 1 1

PAGE

~

3 &5

TITLE

3865

NEEDED CORRECTION

(Typo, DCP, Tech. Error, Etc.)

~

Changed low CST level alarm to a LO-LO CST

level alarm

~

Removed the To from title to accurately reflect

actual task

Take the statement out that says: This is a pre-job

brief: in the condition section

INITIAL

Developer

MHL

JMP

C\\DATA\\I .X Drive\\pdfFiles\\PDF Processing\\SOJ 11 .DOC

12/09/02 11:43

Page 3 of 5

STANDARDS

Apply the following criteria during the performance of this JPM:

a.

b.

c.

The task must be performed using the appropriate plant procedures, Technical Specifications, or

other references.

All critical elements must be performed, simulated, or discussed without error, prompting or

unnecessary queuing.

Management expectations regarding human performance tools (three way communications,

STAR, procedural adherence, etc.), radiological controls, and industrial safety.

CONDITIONS

When I tell you to begin, you are to SHIFT AUXILIARY FEED PUMP

SUCTION EMERGENCY SUPPLY. The conditions under which this task is to be performed are:

a. AFW pump suctions have been shifted to service water because of CST 10-10 level alarm.

b. A loss of A TRAIN SW has occurred.

c. You are directed by the Control Room Operator (CRO) to align B TRAIN SW to the TDAFW

Pump Suction per SOP-22.0.

NOTE: THIS JPM MAY BE PERFROMED ON EITHER UNIT. THE UNIT TWO NUMBERS

ARE [BRACKETED].

EVALUATION CHECKLIST

ELEMENTS:

-

START TIME

1.

Obtain keys for A and B Train SW

supply valves to TDAFWP suction

2.

Unlock and open B TRAIN SW to

TDAFWP suction valves Q1[2]N23VO15D

and Q1[2]N23V015C

3.

Unlock and close A TRAIN SW to

TDAFWP suction valves QlN23V015B and

QlN23V15A

STANDARDS:

RESULTS:

(CIRCLE)

Obtain the needed keys.

S I U

Simulating or discussing key

checkout satisfies this standard.

(CUE: Keys 2-142,Z-159,2-158,

V-881 have been obtained.)

& 2-149 [V-42G, V-66, V-74, &

Q1[2]N23V015D and

S I U

Q1[2]N23V015C are unlocked and

turned counterclockwise until

opened. (CUE: V015C and

V015D are open.)

Q1[2]N23VO15B and

s / u

Q1[2]N23V015A are unlocked and

turned clockwise until closed.

(CUE: V015B and V015A are

closed.)

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EVALUATION CHECKLIST

Page 4 of 5

ELEMENTS:

STANDARDS:

RESULTS:

(CIRCLE)

4.

Notify the CRO that B TRAIN SW is

The control room is notified.

S I U

aligned to the TDAFW Pump suction.

(CUE: The CRO acknowledges.)

-

STOP TIME

1

Terminate when the control room has been notified.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) preceding the element

number.

GENERAL REFERENCES:

1.

FNP-I -SOP-22.0, Version 46.0

2.

FNP-2-SOP-22.0, Version 42.0

3.

WAS: 061A1.04

RO-3.9

GENERAL TOOLS AND EOUIPMENT:

1.

Keys

2.

Gloves

3.

Safety spanner

COMMENTS:

SRO-3.9

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CONDITIONS

When I tell you to begin, you are to SHIFT AUXILIARY FEED PUMP SUCTION EMERGENCY

SUPPLY. The conditions under which this task is to be performed are:

a. AFW pump suctions have been shifted to service water because of CST 10-10 level alarm.

b. A loss of A TRAIN SW has occurred.

c. You are directed by the Control Room Operator (CRO) to align B TRAIN SW to the TDAFW

Pump Suction per SOP-22.0.