ML023400249

Not Available

SRO Not Available

K/A CATALOG NUMBER:

Generic K/A 2.14

"J'

K/A CATALOG JTA IMPORTANCE RATING:

3.0

3.40

OPERATOR APPLICABILITY:

Senior Reactor Operator (SRO)

GZENE

L:REFERENCES:,A rini t t&

10AC-MGR-020-OS Rev 0

Unit 1 or 2 Tech Specs, Section 5.2.2.e

O

1OAC-MGR-020-OS (current revision)

I Unit 1 or 2 Tech Specs

APPROXIMATE COMPLETION TIME:

SIMULATOR SETUP:

N/A

15.0 Minutes

UNIT 1 & 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1. Unit 2 is commencing a startup next shift.

2. Preparations for startup are in progress.

3.

One RO must be held over two hours.

4. The following work history (excluding turnover time) of available ROs on

shift (hours reflect worked PRIOR to the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months holdover). A break of at

least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months occurred between all work periods.

INITIATING CUES:

Detemine which operator(s), if any, can be held over for two hours

without overtime approval, and determine which operators CANNOT be

held over for two hours without prior overtime APPROVAL. If they

CANNOT be held over then indicate which guidelines would be violated.

LR-JP-25045-00

Page 3 of 3

STEP]

PROMNE~?&w~

i~3/4

STUST

A,

4Y,;,,`

<2

>1 <COMMENTSY

START

TIME:

PROMPT:

AT this time, GIVE the operator the attached operator work history.

a

I

Operator identifies the procedure

needed to perform the task.

I1

Operator has obtained procedure

10AC-MGR-020-OS, or Unit 1 or

2 Tech Specs

DETERMINES that Operator #1

WILL violate the overtime limits.

(24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period and

>72 hours during 7 period and

would require overtime

authorization)

-t

PROMPT:

IF asked, INFORM the applicant that operator 1 received authorization for

exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 period between days 4 and 5.

3. Operator determines that Operator #1

DETERMINES that Operator #1

DID violate overtime restrictions,

violated the overtime limits by

exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

period between days 4 & 5.

RESPONSE CUE:

N/A

SOperatof etermines that OV ato #

DETERMINES that Operator #2

WILL

latevertine

, WILL violate the overtime limits.

'V,:

t

,

(>72 hours in a 7 day period and

,'>>

would require overtime

%....

authorization)

RESPONSE CUE:

N/A

5

... 6dp irdetermines that P~?4ftt.

.

DETERMINES that Operator #3

IL~pate 6%~rtineettsftit~ioosý,,,

WILL violate the overtime limits.

(>16 hours in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

and >24 hours in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period

...;

and would require overtime

>,I, authorization)

RESPONSE CUE:

N/A

(** Indicates critical step)

LR-JP-25045-00

Page 4 of 4

STEP

IMNESE SADIlD'

S'AT/UNSAT'

P~~itFORMANCE0

STP

II'(OMENTS)

~~~~~~~~(

.

SY,,

,

%:*,**

K->

END

TIME:

-

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

TERMINATING CUE:

We will stop here.

(** Indicates critical step)

SOperato*deter~mines tihat

jOpe'x

4

DETERMINES that Operator #4

"W NOTviolate overtime'

WILL NOT violate any overtime

restrctl s ....

.limits.

RESPONSE CUE:

N/A

StDETERMINES

that Operator #5

S

ILovertime

strieti

WILL violate the overtime limits.

(>72 hours in a 7 day period and

would require overtime

authorization)

RESPONSE CUE:

N/A

DAY

1

2

3

4

5

6

7

8

Y

1. 6(Today)

Operator

1

Operator

2

Operator

3

Operator

4

Operator

5

0

3

0

8

4

13

10

12

11

12

10

14

12

10

12

8

14

8

10

14

15

12

Page 5 of 5

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERN

COMPANY

Energy to Serve Your World -

SBLC OPERABLE (ADMIN)

AUTHOR

MEDA NUMBER.

ETIME.

R. L.SMITH

LR-JP-25046-00

15 Minutes

RCOMME.NDD

BYPPROVED

BY

DATE

REED

BY .......

P R

...

.

..

...

Program/Course Code:

OPERATIONS TRAINING

Media Number:

LR-JP-25046

A

Re&sbn for Reyision

LR-JP-25046-00

Page 2 of 1

SBLC OPERABLE (ADMIN)

LR-JP-25046-00

TASK

TASK NUMBER:

OBJECTIVE N.UMBEF

The task is complete when the RO determines that SBLC is

,inoperable and Tech Spec entry to 3.1.7 is required.

xxx.xxx

1: XXX.XXX.X

PLANT HATCH JTA IMPORTANCE RATING:

N/A

SRO N/A

K/A CATALOG NUMBER: G2.1.25

K/A CATALOG JTA IMPORTANCE RATING:

2.8

3.1

OPERATOR APPLICABILITY:

Reactor Operator (RO)

GENERAL RWFERNCESU:

Unit 1 Tech Specs

Unit 2 Tech Specs

REQUIRED M

RIALS:

Untý

.. K

U

..

Unit 1 Tech Specs

APPROXIMATE COMPLETION TIME:

15 Minutes

STASK. TITLE:,.

JPMiNUMBERý:

UNIT 1 (X)

UNIT 2

(X)

!!i*

UNIT 1

READ TO THE OPERATOR

INITIAL CONDITIONS:

1. Chemistry has just added Sodium Pentaborate to the Unit 1 SBLC storage

tank.

2. Tank level is currently at 3000 gallons and solution temperature is at 95

degrees F.

3. Chemisrty has just reported that tank concentration level is 13.5%.

INITIATING CUES:

Determine the status of SBLC for Unit 1.

LR-JP-25046-00

Page 4 of 3

STEPDk

STUNA

STEP

'VERORMANCESE

tOMNS

START

TIME:

1.

Operator enters Unit 1 Tech Specs

Operator enters unit 1 Tech Specs

section 3.1.7.

section 3.1.7

2. Plots location on the Unit 1 SBLC

Using Unit 1 Tech Specs the

figures, 3.1.7-1 and 3.1.7-2.

operator plots location on SBLC

figures 3.1.7-1 and 3.1.7-2.

Deter iiids that Sodium ntabdat

Using Unit 1 Tech Specs figure

is

the

p

s

b

nl f s

3.1.7-1 the operator determines

Fi

pe Pnitl T6h

P

that Sodium Pentaborate is

,, ,

outside the permissable region A

and B.

RESPONSE CUE:

Plots the location in the permissible region of A or B.

4.

Determines that Sodium Pentaborate

Using Unit 1 Tech Specs figure

is inside the permissable region of

3.1.7-2 the operator determines

Figure 3.1.7-2 per Unit I Tech Specs.

that Sodium Pentaborate is inside

the permissable region A.

RESPONSE CUE:

Plots the location in the nonpermissible region of A or B.

Det e*mine

LCO entry co

indji"' Using Unit 1 Tech Specs the

Unit

h Specs sect*on 3,I.7.

,

operator determines that a LCO

I

X

7

exists for section 3.1.7.

RESPONSE CUE:

No Tech Spec entry condition exists.

NOTE: The operator may identify applicable Unit 1 Tech Spec action statement,

but this is not critical or required.

END

TIME:

-

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

TERMINATING CUE:

(** Indicates critical step)

We will stop here.

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1. Chemistry has just added Sodium Pentaborate to the Unit 2 SBLC storage

tank.

2. Tank level is currently at 3000 gallons and solution temperature is at 95

degrees F.

3. Chemisrty has just reported that tank concentration level is 13.5%.

INITIATING CUES:

Determine the status of SBLC for Unit 2.

LR-JP-25046-00

Page 6 of 5

ISTE'P

?OMNCIE~..t~.)

.ŽCMET

RESPONSE CUE:

No Tech Spec entry condition exists.

NOTE: The operator may identify applicable Unit 2 Tech Spec action statement,

but this is not critical or required.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

Page 6 of 5

START

TIME:

1. Operator enters Unit 2 Tech Specs

Operator enters Unit 2 Tech

section 3.1.7.

Specs section 3.1.7

2. Plots location on the Unit 2 Tech

Using Unit 2 Tech Specs the

Specs SBLC figures, 3.1.7-1 and

operator plots location on SBLC

3.1.7-2.

figures 3.1.7-1 and 3.1.7-2.

- 3

Deteri

that Sodiurm

inabbtat66

Using Unit 2 Tech Specs figure

is ud.

prmissable #i

n

3.1.7-1 the operator determines

Fig

3I

1 per Un

S

that Sodium Pentaborate is

outside the permissable region A

and B.

RESPONSE CUE:

Plots the location in the permissible region of A or B.

4. Determines that Sodium Pentaborate

Using Unit 2 Tech Specs figure

is inside the permissable region of

3.1.7-2 the operator determines

Figure 3.1.7-2 per Unit 2 TS.

that Sodium Pentaborate is inside

the permissable region A.

RESPONSE CUE:

Plots the location in the nonpermissible region of A or B.

4*5.: 13Deternin'a LCO entr condjtion fito

Using Unit 2 Tech Specs the

Unit,2' Te hSpecs section 3.T7

operator determines that a LCO

I

exists for section 3.1.7.

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERNU

COMPANY

Energy to Serve Your WorldmS.

'TITLE

IRM ALTERNATE POWER CHECKS PRIOR TO TAKING THE MODE

SWITCH TO RUN (ADMIN)

AUTHOR

MEDIA NUBER

I

TIME

R. L. SMITH

LR-JP-25047-00

15 Minutes

RECOMMENDED BY

ADATE

IRMS

RANGE

READING

18

20

22

18

22

24

Page 11 of 10

IRM DATA

A

C

E

G

B

D

F

H

9

10

9

10

9

UNIT 1

READ TO THE OPERATOR

INITIAL CONDITIONS:

1. Reactor Startup is in progress, and the crew is making preparations to

transfer the Reactor Mode Switch to Run.

2.

The STA has adjusted all APRMs to 7% power.

3.

All APRMs are currently reading 7% power.

INITIATING CUES:

Per Step 7.4.4.2 of 34GO-OPS-001-1, perform alternate power level

check per Attachment 10.

[

CONTINUOUS

1.0 Record the IRM readings below AND estimate reactor power using the following formulas:

For IRM Ranges 7 and 8:

For IRM Ranges 9 and 10:

IRM A

RANGE

IRM C

RANGE

IRM E

RANGE q

IRM G

RANGE

IRM B

RANGE

IRM D

RANGE

IRM F

RANGE

IRM H

RANGE

% Power = (IRM Reading) x (.0353)

% Power = (IRM Reading) x (.353)

READING

As

Ag

if

II

LI

% POWER

% POWER __

% POWER__

% POWER

AVERAGE % POWER =

Confirm that each APRM reading is greater than the average * IRM Reactor

Power Value.

Calculations Verified

I _F

any APRM reading is NOT greater than the average IRM power, the STA will perform an

evaluation of power level indication to ensure that the APRM readings are conservative to

actual reactor power. The evaluation will be attached to this attachment.

OPS-1128 Rev. N/A

G16.30

MGR-0009 Rev 4

Program/Course Code:

OPERATIONS TRAINING

Media Number:

LR-JP-25047

Ron

LR-JP-25047-00

Page 2 of 1

UNIT 1 (X)

"T ASK TTE

TASK STANDAD

TASKýNUMBER:ý

OBJECTIVE

UMBER:

UNIT 2

(X)

IRM ALTERNATE POWER CHECKS PRIOR TO

TAKING THE MODE SWITCH TO RUN (ADMIN)

LR-JP-25047-00

The task is complete when the IRM alternate power checks are

performed and the SRO determines that Average % power

calculated is higher then current APRM power readings and a

STA evaluation of power level indication is required.

XXX.XXX

XXX.XXX.X

PLANT HATCH JTA IMPORTANCE RATING:

X.XX

X.XX

K/A CATALOG NUMBER: G2.1.23

K/A CATALOG JTA IMPORTANCE RATING:

3.0

4.0

OPERATOR APPLICABILITY:

Reactor Operator (RO)

34GO-OPS-001-1

34GO-OPS-001-2 Rev

35.3

FREQUIRE

AEIL:int

ht

34GO-OPS-001-1

34GO-OPS-001-2

(Attachment 10)

APPROXIMATE COMPLETION TIME:

15 Minutes

..

SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING

PAGE

LR-JP-25047-00

Page 4 of 3

....

P... .... .

. ...

AT/UNSAT

P[STEP.....

"STANDAR.h.

OMMENTS)

S . . ..

.

. ... . ... . ... .. .

.. ..

. . . .o:

( E 'S

F M M N

N - 1

RESPONSE CUE:

The average 1KM1 /o is less man me I-RmlvI ,re

ig.

(** Indicates critical step)

START

TIME:

-____

1. The operator locates a copy of

Either from the LAN computer or

34GO-OPS-001-1.

MCR procedure books the

candidate obtains a copy of

34GO-OPS-001-1.

PROMPT:

AT this time give the operator the attached copy of UNIT 1

ATTACHMENT 10.

2 The operator identifies where he will

At IH 11-P603, the operator

obtain IRM power and range

identifies, IRM recorders where

information to record on attachment

power information is obtained,

10.

and locates the range switches to

determine what range each IRM

is on.

PROMPT:

AT this time give the operator a copy of the IRM power and range

information.

3.

The operator copies the IRM range

Using the copy of

and power level data onto the copy of

34GO-OPS-001-1 Attachment 10,

34GO-OPS-001-1 Attachment 10.

the data is recorded by operator.

RESPONSE CUE:

Data is not recorded.

I*

4. T

The operator uses the recorded

to the.IRM'data... ..

IRM data and MULTIPLIES it by

the correct constant (.353).

THEN adds them up and divides

them by 8.

RESPONSE CUE:

Incorrect constant used or not added or not divided by 8.

PROMPT:

IF the operator request that the Calculations be verified, THEN as another

operator perform verification but DO NOT correct any errors.

.Thejdpeikatbrdetei

Using the Average % power, the

%/ poweris greater than.

pR$

,.f1\\V

] operator DETERMINES that

settin.

APRMs readings are NOT greater

than the Average IRM power.

LR-JP-25047-00

Page 5 of 4

I TEP]

r1ORMANP'E":',

[>TANDR~

t QMETY

*6.

lthe peto[r 4eternnesran:e(aboo

The operator informs the SS that

ýof pb*f

& by t

1

the STA must perform an

evaluation of power level

indication.

RESPONSE CUE:

The operator does not request an SIA evaluation oi power level

indication.

(N I

Lý

NOTE:

The terminating cu shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

END

TIME:

-

We will stop here.

(** Indicates critical step)

c&JA>s

TERMINATING CUE:

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1. Reactor Startup is in progress, and the crew is making preparations to

transfer the Reactor Mode Switch to Run.

2. The STA has adjusted all APRMs to 7% power.

3.

All APRMs are currently reading 7% power.

INITIATING CUES:

Per Step 7.4.4.2 of 34GO-OPS-001-2, perform alternate power level

check per Attachment 10.

LR-JP-25047-00

Page 7 of 6

SPTEPER....CEStrP,

STANDARD ..

I

RESPONSE CUE:

The average IRKM %i is less tnan tne ArLSvi readUgs.

(** Indicates critical step)

START

TIME:

1. The operator locates a copy of

Either from the LAN computer or

34GO-OPS-001-2.

MCR procedure books the

candidate obtains a copy of

34GO-OPS-001-2.

PROMPT:

AT this time give the operator the attached copy of UNIT 2

ATTACHMENT 10.

2 The operator identifies where he will

At 2H11-P603, the operator

obtain IRM power and range

identifies, IRM recorders where

information to record on attachment

power information is obtained,

10.

and locates the range switches to

determine what range each IRM

is on.

PROMPT:

AT this time give the operator a copy of the IRM power and range

information.

3. The operator copies the IRM range

Using the copy of

and power level data onto the copy of

34GO-OPS-001-2 Attachment 10,

34GO-OPS-001-2 Attachment 10.

the data is recorded by operator.

RESPONSE CUE:

Data is not recorded.

The operator perform the d

t

The operator uses the recorded

to tIh IRM 4ata.

IRM data and MULTIPLIES it by

the correct constant (.353).

THEN adds them up and divides

them by 8.

RESPONSE CUE:

Incorrect constant used or not added or not divided by 8.

PROMPT:

IF the operator request that the Calculations be verified, THEN as another

operator perform verification but DO NOT correct any errors.

'*

h

5p

ggtoV determinesThtet Ai0p

Using the Average % power, the

% pdw~ri* greater than AP

eVr'

operator DETERMINES that

settingsI

APRMs readings are NOT greater

than the Average IRM power.

LR-JP-25047-00

Page 8 of 7

STEPP

TE

"STANDERD>

SAT/UNSAT

A(COMMENTS

jThe, opprato,&termn'es:" a

a

The operator informs the SS that

. fpodwer*lveliby the STXh s

e

the STA must perform an

.

..

evaluation of power level

.................

.....

indication.

RESPONSE CUE:

The operator does not request an bS

1A evaluauon of power

ucw

indication.

END

TIME:.

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

SOUTHERN NUCLEAR

PLANT E.I. HATCH

DOUENT NUMBER:

DCMNPLANT STARTUPTLE

34GO-OPS-001-2

-*

ATTACHMENT 10

PAGE 10 OF 11

REVIVER

NO:

35.2

ATTACHMENT

PAGE:

TITLE:

IRM ALTERNATE POWER CHECK

-48 OF 1

CONTINUOUS

1.0 Record the IRM readings below AND estimate reactor power using one of the following formulas:

For IRM Ranges 7 AND 8:

% Power = (IRM Reading) x (.0353)

For IRM Ranges 9 AND 10:

% Power = (IRM Reading) x (.353)

IRM A

RANGE

IRM C

RANGE

IRM E

RANGE

IRM G

RANGE

IRM B

RANGE

IRM D

RANGE

IRM F

RANGE

IRM H

RANGE

READING

"% POWER

% POWER

AVERAGE % POWER =

Confirm that each APRM reading is greater than the average *

IRM Reactor Power Value.

Calculations Verified

IF any APRM reading is NOT greater than the average IRM power, the STA will perform an

evaluation of power level indication to ensure that the APRM readings are conservative to

actual reactor power. The evaluation will be attached to this attachment.

OPS-1077 Rev. N/A

G16.30

MGR-0009 Rev 4

- - - DO NOT GIVE THIS TO THE CANIDATE****

ANSWER

IRMS!

A

C

E

G

B

D

F

H

RANGE

READING %POWER

9

18

6.35

9

20

7.06

9

20

7.06

10

20

7.06

9

22

7.77

9

18

6.35

10

22

7.77

9

24

8.47

Total = 57.9 +/-.4

57.9/8 = 7.24 +/-.1%

Average % power = 7.24% +/-. 1%

Page 12 of 11

___

__

JP2OiS 2RO DOC

_

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training JPM

SOUTHERN LA

COMPANY

Energy to Serve Your World"

T

TITLE

PREPARE EQUIPMENT CLEARANCE AND HOLD TAGSPREPARE

EQUIPMENT CLEARANCE AND HOLD TAGS

AUTHOR

MEDIA NUMBER

TIME

R. L. SMITHR. L. SMITH

LR-JP-25019-03LR-JP-25019-03

20.020.0 minutes

RECOMMENDED BY

APPROVED BY

DATE

t. f. phillips

r. s. grantham

10/07/02

I--

4WA

AEVýdk

othKýl b:- -J J519A2

OP.-ge:

LR-JP-25019-03

Page 2 of 0

Program/Course Code: LICENSE REQUAL

Media Number: LR-JP-25019

[Tthy Kiobi-JP25b19A2RO1DOC

Page

LR-JP-25019-03

Page 3 of 0

<* j>

S ..

..........

."..

..

Pa qe

oLR-019A2RO.DOC

LR-JP2093

FACILITY:

PLANT E. I. HATCH

UNIT 1 ( )

UNIT 2 (X)

PREPARE EQUIPMENT CLEARANCE AND HOLD

TAGS

_ )&N

LR-JP-25019-03

,

F1

- I

ig'Awmgqff

fL

NM

The task shall be completed when the operator has generated a

clearance for CRD Suction Filter 2A per 30AC-OPS-001-0S.

r 300.016300.016

PLANT HATCH JTA IMPORTANCE RATING:

3.203.20

SRO 2.742.74

K/A CATALOG NUMBER:

294001A107294001AI07

K/A CATALOG JTA IMPORTANCE RATING:

3.003.00

3.703.70

OPERATOR APPLICABILITY:

Reactor Operator (RO)

W

F*R

P-dure: 30AC-OPS-001-0S Rev 23.1

S;°t

Plant Drawing H-26007

APPROXIMATE COMPLETION TIME:

20.0 Minutes

SIMULATOR SETUP:

N/A

-x

. ý,,- , ý

, v -

,

.

g

I

g

0

1

giv HE

Kolb

-

JP25019A2RO.DOC

..

Page

LR-JP-25019-03

Page 5 of 1

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1. The CRD pump, 2C11-COOlA, has tripped.

2. The SO sent to investigate the tripped CRD pump has reported the supply

breaker has tripped.

3. Maintenance has determined that the suction filter for the pump must be

replaced.

4. The Maintenance Foreman, Ron Buckner, is writing up the MWO and

estimates that the job will take about I day. Maintenance will require the

CRD Suction Filter 2A be under clearance.

5. The Nucleis System is down and will not be restored for several days.

INITIATING CUES:

Identify all components that would be used to isolate CRD Suction Filter

2A with the CRD Pump 2A available.

I -

q[motfyjop2201..9A2RODO9C

Page

LR-JP-25019-03

Page 6 of 1

START

TIME:

NOTE: Steps of this JPM may be completed in any order.

1. Operator identifies the

Operator has identified the correct

procedure needed to perform

procedure as 3OAC-OPS-001-OS.

the task.

2. Operator reviews the

prOperator has reviewed the

I

7

procedure's precautions and

precautions and limitations.

limitations.

I

3. Operator identifies the

Operator has identified the

materials which are required.

required materials and where to

obtain them.

Plant Drawing H26007

34SO-C11-005-2S, Section 7.1.4

(Not required to use procedure)

NOTE: The valves listed in this JPM are the minimum requirements for safe

tagging. Components tagged in excess of this minimum will require case

by-case determination by the evaluator.

RESPONSE CUE:

N/A

(** Indicates critical step)

T

y Kol b - JP25019A2RO.DOC

Pm

LR-JP-25019-03

Page 7 of 4

PROMPT:

If the operator addresses preparing a clearance to perform the maintenance,

inform the operator another operator will perform the clearance.

END

TIME:

NOTE: The terminating cue shall be given to the operator when:

- with no reasonable progress, the operator exceeds double the

allotted time.

- operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERN

COMPANY

Energy to Serve Your World SM

REVIEW OF SCRAM DISCHARGE VOLUME ISOLATION VALVE TIMING &

CLOSURE TEST

AUTHOR ,'$IVNUBE

TIME

R. L. SMITH

LR-JP-25048-00

20 Minutes

RECOMMENDED BY:

APRoVEDBYDT

A

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page 1 of 1

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS TRAINING

Media Number:

LR-JP-25048

R..so

I*n

i

tialsua

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0

______Initial

development.

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LR-JP-25048-00

Page 2 of 9

UNIT 1

0

TASK NUM.ANDA:

TASK NUMBER:,

OB9JECTIVENUMBE R:

UNIT 2

(X)

REVIEW OF SCRAM DISCHARGE VOLUME

ISOLATION VALVE TIMING & CLOSURE TEST

LR-JP-25048-00

The task shall be complete when the operator reviews the

completed surveillance procedure, 34SV-C 11-002-2, and

determines if the test is satisfactory or unsatisfactory.

xxx.XXX

xxx.xxx.x

PLANT HATCH JTA IMPORTANCE RATING:

X.XX

X.XX

K/A CATALOG NUMBER: G2.1.33

K/A CATALOG JTA IMPORTANCE RATING:

3.4

SRO 4.0

OPERATOR APPLICABILITY:

Reactor Operator (RO)

GENERL REFERENCStJ2

34S V-Cl11-002-2 Rev 4.2

REQUIRED MATERIALS:

Uiiifakg:3S-1-0

Completed surveillance package: 34S V-C I 1-002-2

APPROXIMATE COMPLETION TIME:

SIMULATOR SETUP:

20 Minutes

N/A

2

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1. Unit 2 is at 100% RTP.

2. Maintenance has been performed on the SDV vent and drain valves.

3. 34SV-Cll-002-2S, "Scram Discharge Volume Isolation Valve Timing &

Closure Test," has just been completed due to the maintenance.

INITIATING CUES:

Review the procedure data and determine the acceptability of the test, and

determine if any required Tech Spec action(s) are necessary.

LR-JP-25048-00

Page 4 of 3

IKATUNSAT

S$~rTANDAIOI(OMTSI

RESPONSE CUE:

N/A

IF the operator recommends that section 7.3 needs to be performed to adjust

the timing of the UNSAT valves, INFORM the operator due to plant

conditions that section 7.3 CANNOT be performed at this time.

PROMPT:

(** Indicates critical step)

START

TIME:

PROMPT:

AT this time, GIVE the operator the completed copy of 34SV-C1 1-002-2S,

"Scram Discharge Volume Isolation Valve Timing & Closure Test"

1. The operator reviews the procedure.

The operator REVIEWS

34SV-C 11-002-2S, "Scram

Discharge Volume Isolation

Valve Timing & Closure Test."

2. The operator evaluates closing stroke

Per step 7.2.5, 7.2.7 and 7.2.8 of

time data for:

34SV-Cl 1-002-2S, the operator

EVALUATES the closing stroke

2C11l-F0lOA SDV Vent Vlv

tm

aafr

time data for:

2C11-F035A SDV Vent Vlv

2C11-F010A SDV Vent Vlv

2C1 1-F010B SDV Vent Vlv

2C1 I-F035A SDV Vent Vlv

2C11-F035B SDV Vent Vlv

2C11-F010B SDV Vent Vlv

2C1 1-F011 SDV Drain Vlv

2C11-F035B SDV Vent Vlv

2C11-F037 SDV Drain Vlv

2C11-F7l1 SDV Drain Vlv

2C 11 -F037 SDV Drain Vlv

,*3. The6P&t

1 truetermin'th66oMg

-

Per step 7.2.7 and 7.2.8 of

st0roe tifti* for:,2

34SV-Cl 1-002-2S, the operator

DETERMINES the closing stroke

2C11-F035

SDIV Vent VfQA

,.;

time data for:

2i O7D DaVv:

'

' 2CI 1-F035A SDV Vent Vlv

"2C1 1-F011 SDV Drain Vlv

j,,ertejs '27 and z'7.2

2C1

l-F037 SDV Drain Vlv

SH.

Have exceeded their closing time

l,

..

limit per steps 7.2.7 and 7.2.8,

and they are

UNSATISFACTORY.

LR-JP-25048-00

Page 5 of 4

STEI

P

P..

.... . .......................

T.

RtV

<(CMMNS)C

___________________________

I

The operator evaluates the closing

time difference data for:

2C11-FO10A SDV Vent Vlv

2C11 -F035A SDV Vent Vlv

2C11-F010B SDV Vent Vlv

2C1 1-F035B SDV Vent Vlv

2C11-F011 SDV Drain Vlv

2C1 1-F037 SDV Drain Vlv

Per steps 7.2.20 and 7.2.22 of

34SV-C 11-002-2S, the operator

EVALUATES the closing time

difference data for:

2C11-F010A SDV Vent Vlv

2C1 1-F035A SDV Vent Vlv

2C11-FO1OB SDV Vent Vlv

2C1 1-F035B SDV Vent Vlv

2C11-F011 SDV Drain Vlv

2C1 1-F037 SDV Drain Vlv

and DETERMINES it to be

SATISFACTORY.

I_

The operator evaluates the opening

time difference data for:

2C11-F010A SDV Vent Vlv

2C11-F035A SDV Vent Vlv

2C1 1-F010B SDV Vent Vlv

2C11-F035B SDV Vent Vlv

2Cl1-F011 SDV Drain Vlv

2C1 l-F037 SDV Drain Vlv

Per steps 7.2.23 and 7.2.25 of

34SV-Cl 1-002-2S, the operator

EVALUATES the opening time

difference data for:

2C11-FO10A SDV Vent Vlv

2C1 1-F035A SDV Vent Vlv

2C11-F010B SDV Vent Vlv

2C1 1-F035B SDV Vent Vlv

2C11-F011 SDV Drain Vlv

2C1 1-F037 SDV Drain Vlv

and DETERMINES it to be

SATISFACTORY.

Per Tech Specs Section 3.1.8

condition A and B, the operator

DETERMINES, that 3.1.8A

applies to 2C11-F035A, 2C11

FO 11, & 2C1 1-F037 valves, and

3.1.8.B applies to 2C11-F011 and

2C11-F037 valves.

3.1.8.A Restore valve to

OPERABLE status within 7days.

3.1.8.B Isolate the the associated

line within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

A

RESPONSE CUE:

N/A

(** Indicates critical step)

4.

5.

LR-JP-25048-00

Page 6 of 5

S

PE...

.MANCE

STEP

STANA1:D

S AT/ NS AT ,

2

'(COMMENTS

NOTE: The operator may note that the Drain line valves (2C11-F011 and 2C11

F037) may be opened under administrative control to allow draining of the

SDV.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

-

..

...

..

Paae 1

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERN Sa

COMPANY

Energy to Serve Your World"

1_

ITimothy Kolb- JP25049A3.doc

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page I of 1

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS training

Media Number:

LR-JP-25049

0

10/07/02

Initial Development

rls

rsR

2

jmothyKolb - JP25049A3.doc

Page

LR-JP-25049-00

Page 3 of 9

UNIT 1

0

DETERMINE

EEQUIPMENT

LR-JP-25049-00

This task will be

the operator, bas

dose that would 1

SXxX.XXX.X

UNIT 2

(X)

STAY TIMES TO TAKE A PIECE OF

OOS

completed when stay times are determined by

ed on current accumulated dose for the year and

be received while in a radiation field.

PLANT HATCH JTA IMPORTANCE RATING:

X.XXN/A

X.XXN/A

K/A CATALOG NUMBER: G2.3.2G2.3.2

K/A CATALOG JTA IMPORTANCE RATING:

2.52.5

SRO 2.92.9

OPERATOR APPLICABILITY:

Reactor Operator (RO)

APPROXIMATE COMPLETION TIME:

20 Minutes

SIMULATOR SETUP:

N/A

NOTE: First section is for RO Candidates and the second section is for SRO candidates.

L

3

LR-JP-25049-00

Page 4 of I

Part 1

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1. The 4tb Stage 'A' Feedwater heater has a leak on its shell side inlet flange.

2. You have been assigned as part of a crew that will enter the Cond Bay to

isolate, and drain the '4A' Feedwater Heater.

3. The estimated time to perform this task is approx 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

4. Your dose history for the year is 380 mr.

5.

Your administrative limit for the year is 1000 mr.

6. Current survey map of the area is available.

INITIATING CUES:

Determine your Maximum "Stay Time" for performing this task.

I

-....

..

Pa

[3

.othyKob

- JP25049A3 do,.

LR-JP-25049-00

Page 5 of I

PROMPT:

AT this time give the operator the copy survey map of the Unit I

Bay.

start

tim e:

Condenser

1. The operator examines the HP Survey

Using the survey Map the

map of the area.

operator DETERMINES the

general radiation in the area that

the tour will occur.

RESPONSE CUE:

N/A

RESPONSE CUE:

N/A

RESPONSE CUE:

N/A

RESPONSE CUE:

N/A

END

TIME:

-

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double th(

allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

ffirnoth*olb - JP25049A3.doc

..

LR-JP-25049-00

Page 6 of I

Part 2

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1. The 4th Stage 'A' Feedwater heater has a leak on its shell side inlet flange.

2. Your crew has been assigned the task to enter the Cond Bay to isolate, and

drain the '4A' Feedwater Heater.

3. The estimated time to perform this task is approx 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and you will

need a team of 3 operators.

4. The operators chosen to perform the task have a following dose history for

the year:

Operator #1

280 mr

Operator #2

370 mr

Operator #3

770 mr

5. Each operators administrative limit for the year is 1000 mr.

6. Current survey map of the area is available.

INITIATING CUES:

For each of the operators listed above, DETERMINE their Maximum

"Stay Time" and whether they can perform the task.

'K

Tibmohyj Ko- JP25049A3.doc

Page

LR-JP-25049-00

Page 7 of 1

start

time:

-

PROMPT:

AT this time give the operator the copy of the survey map of the Unit 2

Condenser Bay 164' el.

RESPONSE CUE:

N/A

RESPONSE CUE:

N/A

RESPONSE CUE:

N/A

(** Indicates critical step)

1. The operator examines the HP Survey

Using the survey Map of Unit 2

map of the Unit 2 164' el Condenser

164' el Condenser Bay, the

Bay.

operator DETERMINES the

general radiation in the area that

the work will occur.

I

-

--

FinhxKb-Jp25049A.doc

PaeE

LR-JP-25049-00

Page 8 of 6

-

EP

2

RESPONSE CUE:

N/A

NOTE: IF the operator states that the operators should not exceed the RWP Dose

limit of the Digital Alarming Dosimetry (DAD), this is also correct.

END

TIME:

-

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double tht

allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

"(** Indicates critical step)

Using his remaining dose margin

and highest dose rate for the area,

CALCULATE the Stay Times for

each operator:

frnotikolb- JP25205A4SRO.DOC

Pa

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training JPM

SRO ONLY

SOUTHERN NA

COMPANY

Energy to Serve Your World"

1

EVALUATE THE NEED FOR/RECOMMEND OFFSITE PROTECTIVE

ACTIONSE VALUATE THE NEED FOR/RECOMMEND OFFSITE

PROTECTIVE ACTIONS

U~.

.il

......

... IE h

R. L. SMITHR. L. SMITH

LR-JP-25205-06LR-JP-25205-06

16 .016.0 Minutes

"""Woe1NDE

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r. s. grantham

10/07/02

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SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page 1 of 1

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS training

Media Number:

LR-JP-25205

00

08/05/94

Initial development

rab

mmg

01

08/19/96

Format change

rab

dhg

02

07/02/97

Changed based on instructor feedback.

SCB

DHG

03

03/21/00

Format modification, change time allowance based on

rab

dhg

running average, change MIDAS form due to revision

04

11/06/00

Include objective number

rab

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05

03/25/02

Include initial operator statement

rab

06

10/07/02

JPM modified.

rls

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nTimoth y'Kolb - JP25205A4SRO.DOC

.

Pag

LR-JP-25205-06

Page 3 of9

UNIT 1

(X)

UNIT 2

(X)

EVALUATE THE NEED FOR/RECOMMEND

OFFSITE PROTECTIVE ACTIONS

1#0 M,,

E

LR-JP-25205-06

Eff

M

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?

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The task shall be completed when the Protective Action

Recommendation has been made per 73EP-EIP-054-OS.

200.105 (EP 001.088)200.105 (EP 001.088)

ED

200.105.A200.105.A

PLANT HATCH JTA IMPORTANCE RATING:

3.003.00

3.003.00

K/A CATALOG NUMBER: 295038EA201295038EA201

K/A CATALOG JTA IMPORTANCE RATING:

3.303.30

SRO 4.304.30

OPERATOR APPLICABILITY:

Senior Reactor Operator (SRO)

73EP-EIP-054-OS Rev 4 Ed I

q4I

yIagaiE~aga

114

MR,

I 73EP-EIP-054-OS (current revision)

PAR Worksheet/Approval Sheet

APPROXIMATE COMPLETION TIME:

SIMULATOR SETUP:

16.0 Minutes

N/A

3

JWMMSýM*

ni

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il law ]

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avj

aa

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.0,60. 412

LTmoty§

KolbI- JP25205A4SRO. DOC

Pag

LR-JP-25205-06

Page 4 of I

UNIT 1 & 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

The Prompt Offsite Dose Assessment has just been completed, and

projected Dose information is available.

2.

The Dose Assessment Staff is not available yet.

3.

The SOS has declared a Site Area Emergency due to the release.

4.

The SOS is performing the functions of the Emergency Director.

5.

SPDS is available.

INITIATING CUES:

Determine the Protective Action Recommendations, per

73EP-EIP-054-OS.

LT1mo1!1y K0b JP25205A4SRODOC

Page

LR-JP-25205-06

Page 5 of I

start

time:

PROMPT:

At this time, give the operator the projected Dose information.

1. Operator identifies the procedure

Operator has identified the correct

needed to perform the task.

procedure as 73EP-EIP-054-0S.

2. Operator reviews the procedure's

Operator has reviewed the

precautions and limitations,

precautions and limitations.

PROMPT:

When the operator identifies the proper wind indication instrument,

indicate that the wind direction (from) is 2250.

At%

t

5

ijAt

panel IHI 1-P690, the operator

N has determined wind direction to

be from 2250, using one of the

following recorders:

IY33-R601 (10 meter)

1

R

(

e

1Y33-R602 (60 meter)

~4 ~

2 Y33-R603 (100 meter)

N

OR

ýQjw

~

At panel 1H 11-P689, the operator

has determined wind direction to

be from 2250, using recorder

1Y33-R604 (23 meter).

OR

fj, V,

1X4tjfll

~At

Unit I or 2 SPDS MIDAS or

Ellý

R

P

-

MET screens the operator

N determines wind direction to be

aial

t2250.

RESPONSE CUE:

N/A

NOTE: Accept the wind direction as 216 to 2500.

4. Record "wind direction from" on

The operator has recorded wind

Attachment 3.

direction (Wind From) on Step I

Iof Attachment 3.

(** Indicates critical step)

--

LTimothy Kolb - JP25205A4SR.DOC

LR-JP-25205-06

Page 6 of 6

PE

BF1

0i4

K

RESPONSE CUE:

N/A

6. Record the affected zones on

The operator has recorded the

Attachment 3.

affected zones on Step 2 of

Attachment 3.

7. Compare plant conditions with

The operator has Determined a

Attachment 1 of procedure.

General Emergency does not

exist.

PROMPT:

If the operator addresses status of emergency classification, as the SOS,

inform the operator that a Site Area Emergency has been declared.

8. Determine PARs required for a Site

The operator has determined there

Area Emergency per Attachment 1.

are NO PARs for Site Area

Emergency per Attachment 1.

9. Record the plant condition PARs on

The operator has recorded "N/A"

Attachment 3.

or "NONE" for plant condition

PARs on Step 3 of Attachment 3.

10. Determine if Off-site dose has been

The operator has determined that

measured or projected.

the dose rate has been projected.

11.

Determine if the population dose is

Evaluating ALL TEDE and

greater than 1 REM TEDE or greater

THYROID CDE Values the

than 5 REM CDE Thyroid.

operator:

Determines the dose to the

population is greater than I

REM TEDE and greater than

5 REM CDE Thyroid.

Answers YES to the flowchart

step.

(** Indicates critical step)

The operator has determined the

affected zones to be:

---

P

--

-

rage

tTirnotrKolb - JP25205A4SRO.DOC

F-

W, IN -.

N

I HIM "K1%A4r/9VJJN,,,S '.q

, -ý

jMle'uu

HIM

10

TL R

2 E . "

N1,1111.1

BRIN

"I

&W."

(** Indicates critical step)

LR-JP-25205-06

Page 7 of 6

12. Determine if the dose is greater than 1

Evaluating the 10 and 5 mile

REM TEDE or greater than 5 REM

TEDE and THYROID CDE

CDE Thyroid at 5 - 10 miles.

Values the operator:

Determines the dose to the

population is less than I REM

TEDE and less than 5 REM CDE

Thyroid at 5 - 10 miles.

Answers NO to the flowchart

step.

13. Determine if the dose is greater than 1

Evaluating the 5 AND 2 MILE

REM TEDE or greater than 5 REM

TEDE and THYROID CDE

CDE Thyroid at 2 - 5 miles.

Values the operator:

Determines the dose to the

population is less than 1 REM

TEDE and less than 5 REM CDE

Thyroid at 2 - 5 miles.

Answers NO to the flowchart

step.

A *4*P )*

i

~

VThe

operator has determined

MMi

aPARs

for dose projections per

S' Attachment 2 are:

Evacuate Zone A

Si *:J!*I

Shelter Zones E-5.

RESPONSE CUE:

N/A

PROMPT:

If the operator addresses actual field measurements, as the SOS, inform the

operator that no actual field measurements have been obtained yet.

45

s

The operator has determined the

A-ri

4

SKI9Kt

PARs from dose projections are

If

e

iEM

j

4 most conservative.

RESPONSE CUE:

N/A

16. Check the block to the left of the most

The operator has checked the

conservative PAR of Step 3 on

block to the left of the Dose

Attachment 3.

Projections of Step 3 on

Attachment 3.

-,Potý

-JP25205A4SRO.DOC

.....

Pace

LR-JP-25205-06

Page 8 of 6

17. Record the zones from the most

The operator has recorded the

conservative PAR to the Approval

following on the Approval

Section of Attachment 3.

Section on Attachment 3:

Evacuate Zone A

Shelter Zones E-5.

18. Obtain ED concurrence on PARs.

Emergency Director has signed

Attachment 3.

NOTE: The evaluator may sign as the ED or tell the operator that it has been

signed.

PROMPT:

If the operator addresses notifications, as the SOS, inform the operator that

another operator will make the State and Local notifications.

PROMPT:

If the operator addresses continuing assessment, as the SOS, inform the

operator that another operator will continue the assessment of the emergency

conditions.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double tht

allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(*': Indicates critical step)

fTirnothy Kolb -

DOG .

...........

C

_

_-

Page9

LR-JP-25205-06

Page 9 of 1

"**13. ESTIMATE OF PROJECTED OFFSITE DOSE:

I NEW

[ ] UNCHANGED

PROJECTION TIME:

______________

(Eastern)

TEDE

THYROID ODE

(mrem)

ESTIMATED DURATION: _

HRS

SITE BOUNDARY

1 .4E+03

6.9E+03

2 MILES

7.4E+02

3.OE+03

5 MILES

2.3E+02

6.9E+02

10 MILES

5.5E+01

1.7E+02

Page 9 of 7

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERN

COMPANY

Energy to Serve Your World S

TITLE"

FROM OUTSIDE THE CONTROL ROOM, INJECT BORON USING THE

SBLC SYSTEM WITH FAILURE OF "A" PUMP TO START

R. L. SMITH

LR-JP-25043-00

21.0 Minutes

RECOMMENE

BY

AxPPROvED B

ADTE

7RE O

M ENDE D

Ar**

.

... ,. ...

........

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page 1 of 1

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS TRAINING

Media Number:

LR-JP-25043

Rev. No. I Date I

enjoUeiinfAhos4Sps

............

I..

I: Initials * Initials

00

Initial Development.

RLS

~i.

__________

II

_______

I

_______

I

_______

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I

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I.

I

LR-JP-25043-00

Page 1 of 9

UNIT 1

(X)

TASK TITLE:'

,TASK STANDARD:

TASK NUMBIER:,

OBJECTIVENUMBER.

FROM OUTSIDE THE CONTROL ROOM, INJECT

BORON USING THE SBLC SYSTEM WITH

FAILURE OF "A" PUMP TO START.

LR-JP-25043-00

The task shall be completed when one Standby Liquid Control

Squib Valve has been fired and "B" pump has been started

locally and the Standby Liquid Control System is injecting to the

Reactor, per 34SO-C41-003.

011.012

011.012.B

PLANT HATCH JTA IMPORTANCE RATING:

4.20

4.20

K/A CATALOG NUMBER: 2110002130

K/A CATALOG JTA IMPORTANCE RATING:

3.90

SRO 3.40

OPERATOR APPLICABILITY:

System Operator (SO)

GENERAL RktERENCES

Tnit~

AKJ~

iii

31EO-EOP-011-1S Rev 6

31EO-EOP-011-2S Rev 6

34SO-C41-003-1S Rev 10

34SO-C41-003-2S Rev 10

Ed 5

Ed 4

REQUIRED MATERIALSJ: Uit 1.

j.Uni.

.

34SO-C41-003-1S

(current revision)

Four (4) SBLC Squib Valve

jumper wires, from EOP file

next to Remote Shutdown

Panel 1H21-P173

Flathead screwdriver

34SO-C41-003-2S

(current revision)

Four (4) SBLC Squib Valve

jumper wires, from EOP file

next to Remote Shutdown

Panel 2C82-P001

Flathead screwdriver

"-'

APPROXIMATE COMPLETION TIME:

21.0 Minutes

SIMULATOR SETUP:

N/A

1

UNIT 2

(X)

UNIT 1

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

The Reactor has failed to Scram either manually or automatically, and the

Torus temperature is approaching the BIIT curve.

2.

31EO-EOP-01 1-IS (RCA) is in progress.

3.

SBLC has failed to initiate from the Control Room.

4.

RWCU is isolated.

INITIATING CUES:

Manually initiate SBLC locally per 34SO-C41-003-lS.

LR-JP-25043-00

Page 3 of 3

STEP

PE<'

STANDAlTISAUSA

1<I(OMENTS)

START

TIME:

RESPONSE CUE:

PROMPT:

Squib Valve 1C41-F004A(B), no noise is heard.

WHEN all terminals for a Squib Valve are correctly installed, INDICATE

an explosive noise from the vicinity of that Squib Valve.

NOTE: Detonation of one Squib Valve will satisfactorily meet the standard.

NOTE: The jumpers used to fire the Squib Valves are a jumper with 3 connections

to connect all three terminal points.

(** Indicates critical step)

1. Operator identifies the materials that

Operator has identified the

are required.

required materials and where to

obtain them.

2. Operator reviews the procedure's

Operator has reviewed the

precautions and limitations,

precautions and limitations.

- 3.

Detonaitquib Valve....

..

4.f.4A

At Panel 1H21-PO 11, the

AND

following jumpers are

S< tINSTALLED for 1C41-FO04A:

Detonat~ squib Valve i

4-pO4ýt 7z ýý",Terminal point BB-1 to Squib

Valve, 1C41-F004A, Junction

Box terminal C1 (white wire) and

terminal C (green wire).

Terminal point BB-4 to Squib

Valve, 1C41-FOO4A, Junction

Box terminal C2 (black wire) and

terminal C3 (red wire).

At Panel 1H21-P011, the

following jumpers are

Y INSTALLED for 1C41-FO04B:

Terminal point BB-8 to Squib

Valve, 1C41-F004B, Junction

Box terminal Cl (white wire) and

terminal C (green wire).

C Terminal point BB- 11 to Squib

Valve, 1C41-FO04B, Junction

Box terminal C2 (black wire) and

term*nal C3 (red wire).

LR-JP-25043-00

Page 4 of 4

STEP

.

ST....R?.

SATUNSAT

P

PERFORMANC

TP

K

K(OMNS

PROMPT:

IF the operator addresses isolation of RWCU, as the Control Room operator

REPORT that RWCU is isolated.

4. Start SBLC Pump 1C41-COOlA.

At panel

1H21-PO1I, SBLC

PUMP, SC41-COO1A, control

switch is in RUN.

PROMPT:

WHEN operator addresses indications for pump start, INDICATE there is

no noise from the pump, and green light is illuminated and red light is

extinguished.

5. RETURN the control switch to the

At panel 1H21-POl1, SBLC

STOP position

PUMP, 1C41-C001A, control

switch is in STOP.

- 6. Start SBLC iC41-COOIB ,

At panel 1H21-POl1, SBLC

PUMP, 1C41-CO01B, control

switch is in RUN.

RESPONSE CUE:

SBLC Pump 1C41-COOLB, pump motor is quiet, and green light is

illuminated.

7. Verify the SBLC solution is being

At panel 11H21-PO11, the operator

injected into the Reactor.

has VERIFIED SBLC Tank level

is DECREASING as indicated by

SBLC STORAGE TANK

LEVEL INDICATOR,

1C41-R001.

PROMPT:

WHEN the operator addresses SBLC tank level, INDICATE for the

operator that level is decreasing slowly, but is greater than 1300 gallons.

NOTE: It will take between 30 and 70 minutes to completely empty the SBLC

Storage Tank.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

TERMINATING CUE:

Indicates critical step)

We will stop here.

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

The Reactor has failed to Scram either manually or automatically, and the

Torus temperature is approaching the BUT curve.

2.

31EO-EOP-01 1-2S (RCA) is in progress.

3.

SBLC has failed to initiate from the Control Room.

4.

RWCU is isolated.

INITIATING CUES:

Manually initiate SBLC locally per 34SO-C41-003-2S.

LR-JP-25043-00

Page 6 of 6

STEP.PE.ORMANC...... "

'W ..

.SAT/UNSATY...

STEP

SAD

D(

M E NI...

[M

N

Y

[

e:

,4

START

TIME:

1. Operator identifies the materials that

Operator has identified the

are required.

required materials and where to

obtain them.

2. Operator reviews the procedure's

Operator has reviewed the

precautions and limitations,

precautions and limitations.

- 3

DetondtSquib Valve 2C4J F004A* ,,ý At Panel 2H21-PO 11, the

ANDfollowing

jumpers are

o, INSTALLED for 2C41-FO04A:

Detnatqibalv

.4

4.. ,

Terminal point AA-5 to Squib

-.

Valve, 2C41-FO04A, Junction

Box terminal point 1 (white wire)

and terminal point 3 (green wire).

Terminal point AA-6 to Squib

Valve, 2C41-F004A, Junction

Box terminal point 4 (red wire)

and terminal point 2 (black wire).

At Panel 2H21 -PO 11, the

following jumpers are

INSTALLED for 2C41-FOO4B:

Terminal point AA-10 to Squib

Valve, 2C41-FOO4B, Junction

,

Box terminal point 1 (white wire)

and terminal point 3 (green wire).

Terminal point AA-11 to Squib

Valve, 2C41-FO04B, Junction

Box terminal point 4 (red wire)

and terminal point 2 (black wire).

RESPONSE CUE:

Squib Valve 2C41-F004 A(B), no noise is heard.

PROMPT:

WHEN all terminals for a Squib Valve are correctly installed, INDICATE

an explosive noise from the vicinity of that Squib Valve.

NOTE: Detonation of one Squib Valve will satisfactorily meet the standard.

NOTE: The jumpers used to fire the Squib Valves are a jumper with 3 connections

to connect all three terminal points.

(** Indicates critical step)

LR-JP-25043-00

Page 7 of 7

STEP

$T/UNSAT

STPPERFORMA INCE

ft,ý§T*

STANDARD

O MNS

PROMPT:

IF the operator addresses isolation of RWCU, as the Control Room

operator, REPORT that RWCU is isolated.

4.

Start SBLC Pump 2C41-COO1A.

At panel 21121-P011, SBLC

PUMP, 2C41-COO1A, control

switch is in RUN.

PROMPT:

WHEN operator addresses indications for pump start, INDICATE there is

no noise from the pump, and green light is illuminated and red light is

extinguished.

5. RETURN the control switch to the

At panel 2H21-PO1 1, SBLC

STOP position

PUMP, 2C41-CO01A, control

switch is in STOP.

- 6.Srt QBC2C41-C

IB

1

At panel 2H21-POl, SBLC

PUMP, 2C41-CO01B, control

switch is in RUN.

RESPONSE CUE:

SBLC Pump 2C41-C001B, pump motor is quiet, and green light is

illuminated.

7.

Verify the SBLC solution is being

At panel 21121-PO 11, the operator

injected into the Reactor.

has VERIFIED SBLC Tank level

is DECREASING as indicated by

SBLC STORAGE TANK

LEVEL INDICATOR,

2C4 1-ROO1.

PROMPT:

WHEN the operator addresses SBLC tank level, INDICATE for the

operator that level is decreasing slowly, but is greater than 1000 gallons.

NOTE: It will take between 30 and 70 minutes to completely empty the SBLC

Storage Tank.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

TERMINATING CUE:

Indicates critical step)

We will stop here.

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

TITLE

-

FROM THE REMOTE SHUTDOWN PANEL, START RCIC FOR INJECTION

INTO THE REACTOR

AUTHOR

..... ..

ED. NU

..

I.ME

R. A. BELCHER

LR-JP-39.16-12

24.0 Minutes

RECOMMENDEDB"APOED

BY

DATE,

N/R

R. A. BELCHER

03/14/2002

SOUTHERN 4

COMPANY

Energy to Serve Your Worlds.

K->

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page 1 of t

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS TRAINING

Media Number:

LR-JP-39.16

Rev. No.

Date

,..

Init

ials

01

06/30/89

General revision and format change

JEM

SMC

02

08/18/89

Add LR lesson plan references

JEM

DHG

03

09/22/89

General revision

JEM

WRB

04

02/27/90 Procedure, format, & question revision

JEM

DHG

05

04/29/91

General/procedure revision

JLA

DHG

06

08/26/92

General revision and format change

WMM

SCB

07

09/02/93

General revision, word processor change

08

08/11/94

Modify simulator setup, adjust format

SMC

09

08/05/96

Format change, procedure changes

DHG

10

03/06/00

Format modification, update, K/As, upgrade to the

DHG

new simulator computer operating system, change

time allowance based on running average, change title

11

11/02/00

Include objective number, change time allowance

DHG

based on running average

12

03/14/02

Include initial operator statement

LR-JP-39.16-12

Page 1 of 1

UNIT 1 (X)

JMNUMBR

TSKSTANDARD:

TOSK NUMR:

M

ýOBJECTIVE`NUMBER:

UNIT 2

(X)

FROM THE REMOTE SHUTDOWN PANEL, START

RCIC FOR INJECTION INTO THE REACTOR

LR-JP-39.16-12

The task shall be completed when the RCIC System is started

and injecting to the Reactor per 31RS-OPS-001.

039.016

039.016.O

PLANT HATCH JTA IMPORTANCE RATING:

3.86

3.80

K/A CATALOG NUMBER: 2950162130

K/A CATALOG JTA IMPORTANCE RATING:

3.90

3.40

OPERATOR APPLICABILITY:

Reactor Operator (RO)

GENEIRAL REVERENCE'S.1: Uixitl

Unit 2

31RS-OPS-001-IS Rev 5 Ed 2 31RS-OPS-001-2S Rev 6 Ed 1

REUIED MATERIALS:.

ntt

Ui

QUIRE

.

'___-"-

>_"__-%

_____

31RS-OPS-001-1S

(current revision)

Key for Remote Shutdown

Panel (if performed in Plant)

APPROXIMATE COMPLETION TIME:

SIMULATOR SETUP:

31RS-OPS-001-2S

(current revision)

Key for Remote Shutdown

Panel (if performed in Plant)

24.0 Minutes

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING

PAGE

LR-JP-39.16-12

Page 2 of 2

SIMULATOR SETUP

Simulator Initial Conditions:

1. RESET the Simulator to IC #127 and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS:

MALF#VI

>TTt

fAL

RAMP

AT

mfB21_48A

Steam Line A Break (After Restrictor) (Var)

1.0

1000

00000

mfN21_79A

Condensate Pump 2A Trip

00000

mfN21_79B

Condensate Pump 2B Trip

00000

mfN21_79C

Condensate Pump 2C

00000

mfE41_107

HPCI Failure to Start (F001 Stuck)

00000

mfE51_109

RCIC Failure to Auto Start

00000

3.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A.

Allow the simulator to run for two minutes.

B.

Secure all RHR and Core Spray pumps.

C.

Acknowledge all annunciators.

4.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5.

ESTIMATED Simulator SETUP TIME:

15 Minutes

UNIT 1

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

An event has occurred which required the Control Room to be evacuated.

2.

The Unit I Reactor was scrammed prior to the evacuation.

3.

RCIC is in standby.

4.

3 1RS-OPS-001- 1S is in progress.

5.

RWL is less than +12 inches and decreasing.

INITIATING CUES:

Start the RCIC System from the Remote Shutdown Panel and inject water

into the Reactor per 31RS-OPS-001-1S, Attachment 3.

LR-JP-39.16-12

Page 4 of 4

......

STEP.....

PERFORMANCE$TEPý

.

,.

STANDAMMES

S

.

START

TIME:

Operator identifies required the

materials and where to obtain

them.

I

IF the operator addresses posting of RCIC Diagonal, as the Shift

INFORM the operator that Health Physics is posting the area.

I.

T

Place the following Transfer Switches

in EMERGENCY:

1C82-$23G

1C82-$23B

IC82-$23C

IC82-$23D

1C82-$23E

1C82-$23F

Locally confirm the position of the

following valves:

1E51-FO1O

1E51-F012

1E51-F029

IE51-F031

At panel 1C82-P001, the

following Transfer Switches are

in EMER:

XFER SW 1C82-S23G

XFER SW 1C82-$23B

XFER SW 1C82-$23C

XFER SW 1C82-$23D

XFER SW 1C82-S23E

XFER SW 1C82-$23F

I

The operator has addressed

contacting an SO to VERIFY the

following valves are in the correct

position:

CONDENSATE STORAGE

SUCTION VLV, 1E51-F010, is

OPEN.

PUMP DISCHARGE VLV,

1E51-F012, is OPEN.

SUPPRESSION POOL

SUCTION VLV, 1E51--F029, is

CLOSED.

SUPPRESSION POOL

SUCTION VLV, 1E51-F031, is

CLOSED.

______________________________________________________ L _______________________________________________ a

Supervisor,

PROMPT:

WHEN the operator addresses locally confirming positions of valves, as the

SO, INFORM the operator that:

1E51-FO10 and 1E51-F012 are open.

1E51-F029 and 1E51-F031 are closed.

(** Indicates critical step)

PROMPT:

2.

3.

l

LR-JP-39.16-12

Page 5 of 5

STEP

PERFORMANC

STE

,

STNDR

SAI

S

Tt

6

}CO

MENTS)z Y,

4.

Confirm 1E51-F045 is closed.

At panel 1C82-POOI, STM TO

TURB VLV, 1E51-F045, is in

CLOSE, green light illuminated.

- 56 Open 1E51-F046.

At panel 1C82-POO1, TURB CLG

WTR VLV, 1E51-F046, is in

OPEN, red light illuminated.

RESPONSE CUE:

Valve, 1E51-F046, green light illuminated.

6. Confirm 1E51-F013 is closed.

At panel 1C82-POO1, RCIC

PUMP DISCH VLV, 1E51-F013,

is in CLOSE, green light

illuminated.

7. Confirm 1E51-F007 is open.

At panel 1C82-POO1, INBD ISOL

VLV, 1E51-F007, is in OPEN,

red light illuminated.

8. Confirm 1E51-F524 is open.

At panel 1C82-POO1, RCIC TRIP

& THRT VLV, 1E51-F524, is

OPEN, red light illuminated.

9. Confirm 1E51-F008 is open.

At panel 1C82-P001, OUTBD

ISOL VLV, 1E51-F008, is in

OPEN, red light illuminated.

10. Start the Barometric Condenser

At panel 1C82-P001,

Vacuum Pump.

BAROMETRIC CNDSR VAC

PUMP Switch is in START, red

light illuminated.

11. Start the Barometric Condenser

At panel 1C82-POO1,

Condensate Pump.

BAROMETRIC CNDSR COND

PUMP Switch is in RUN, red

light illuminated.

NOTE: The operator should not address opening 141-F011 and 1E51-F022 since

RCIC operation will NOT be for Reactor pressure control.

PROMPT:

IF the operator addresses purpose for RCIC operation, as the Shift

Supervisor, INFORM the operator that RCIC operation is for RWL control.

- 12.

Open valve;E51-F7045..

At panel 1C82-POO1, STM TO

TURB VLV, 1E51-F045, is

OPEN, red light illuminated.

RESPONSE CUE:

(** Indicates critical step)

Valve, 1E51-F045, green light illuminated.

LR-JP-39.16-12

Page 6 of 6

STEP

PERFO RMANt

§IE

TAjNAp

I

ATUNSAT"'.

(COMMENTS)'ý

NOTE: The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

Operator states the task is complete.

TERMINATING CUE:

We will stop here.

(** Indicates critical step)

- 13

Openivalve 1E1F03

At panel 1C82-POO1, RCIC

PUMP DISCH VLV, 1E51-F7013,

Is OPEN, red light illuminated.

RESPONSE CUE:

Valve, 1E51-F013, green light illuminated.

PROMPT:

WHEN the operator addresses RCIC Pump Flow, as the 1H21-P173 Panel

operator, INFORM the operator that flow is greater than 122.5 gpm on

RCIC PUMP FLOW 1E51-R070 indicator at panel 1H21-P173.

14. Locally confirm valve 1E51-F019

The operator has addressed

closes when RCIC flow exceeds 122.5

contacting an SO to confirm MIN

gpm.

FLOW VLV, 1E51-F019, is

CLOSED.

PROMPT:

WHEN the operator addresses 1E51l-F019, as the SO, INFORM the

operator that 1E51-F019 is closed.

PROMPT:

WHEN the operator addresses monitoring parameters at 1H21-P173, as the

Shift Supervisor, INFORM the operator that they are being monitored by an

operator at 1H21-P173.

PROMPT:

IF the operator addresses securing RCIC or system restoration, as the Shift

Supervisor, INFORM the operator that it is not desired at this time.

END

TIME:

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

An event has occurred which required the Control Room to be evacuated.

2.

The Unit 2 Reactor was scrammed prior to the evacuation.

3.

RCIC is in standby.

4.

31RS-OPS-001-2S is in progress.

5.

RWL is dearsig. .-SO '

Q

S ecrca

INITIATING CUES:

Start the RCIC System from the Remote Shutdown Panel and inject water

into the Reactor per 3 1RS-OPS-001-2S, Attachment 3.

LR-JP-39.16-12

Page 8 of 8

STA 'kdQMMENTMY

START

TIME:

1. Operator identifies the materials that

Operator identifies the required

are required.

materials and where to obtain

I

I them.

PROMPT:

IF the operator addresses posting of RCIC Diagonal, as the Shift Supervisor,

INFORM the operator that Health Physics is posting the area.

NOTE: Transfer Switch 2C82-S8 is not required to complete the critical step

satisfactorily.

Piace:*2.

K1

fignTtfno

At panel 2C82-P001, the

in EMERGENCY: -

'

following Transfer Switches are

2C82-5in

EMERGENCY:

2C82-S5

XFER SW 2C82-S7

2C82-SER

sw

XFER SW 2C82-S6 3"

2C82-S4

XFER SW 2C82-S4 V/

2....-55

XFER SW 2C82-$55

AA~ac

XFER SW 2C82-S3 V

22C82-S4

2

-'

.....

'

XFER SW 2C82-S84.

2C82-S1 .XFER

SW 2C82-S8 v-'

XFER SW 2C82-SB18ý

-7/)-

RESPONSE CUE:

Remote Shutdown Panel indications are not available.

(** Indicates critical step)

LR-JP-39.16-12

Page 9 of 9

..

P`ERFORMAN CE STE

STANDARD

SAT/UNSATJ,>; I

Confirm the following valves are

open:

2E51-F010,O

2E51-F012

.

2E51--F007

t.."

2E51--F008

At panel 2C82-P001, the operator

VERIFIES the following valves

are OPEN, red light illuminated:

CST SUCTION VLV, 2E51l-F010

DISCH VLV, 2E51-F012

STEAM SUPPLY

VLV, 2E51-F007

INBD ISOL

STEAM SUPPLY OUTBD ISOL

VLV, 2E51-F008.

NOTE: The operator should not perform Section 3.0 of Attachment 3 since RCIC

operation will NOT be for Reactor pressure control.

4.

Confirm the RCIC Flow Controller is

At panel 2C82-P001, the operator

in AUTO and set for 400 gpm.

VERIFIES RCIC FLOW

CONTROL, 2C82-RO01:

Is in AUTO.

Is set for 400 gpm (accept 350 to

450 gpm).

5. Confirm the following valves are

At panel 2C82-POO1, the operator

closed:

VERIFIES the following valves

2E51-F029

are CLOSED, green light

illuminated:

2E5 1-F031

TORUS OUTBD SUCTION

2E51-F022

VLV, 2E51-F029

TORUS INBD SUCTION VLV,

2E51-F031

TEST LINE TO CST, 2E51-F022

NOTE: The operator should not address opening 2E51-F029 and 2E51-F031 since

2E5 1-F010 is open.

6.

Start the Barometric Condenser

At panel 2C82-P00I, the

Vacuum Pump.

BAROMETRIC CNDSR VAC

PUMP, 2E51-C002-2, is in

START, red light illuminated.

(** Indicates critical step)

3.

I

iSTEP

LR-JP-39.16-12

Page 10 of 10

STEP

viTI

UNSAT.

7. Start the Barometric Condenser

At panel 2C82-POOL, the

Condensate Pump.

BAROMETRIC CNDSR COND

PUMP, 2E51-C002-1, is in

START, red fight illuminated.

8. Confirm the Trip and Throttle Vlv is

At panel 2C82-P001, the operator

open.

has verified TRIP & THROTTLE

VLV, 2E51-F524, is OPEN, red

light illuminated.

4*9,

Open valyeQESl-F046

At

panel 2C82-P001, TURB CLG

.

WTR VLV, 2E51-F046, is

... ,

OPEN, red light illuminated.

RESPONSE CUE:

Valve, 2E51-F046, green light illuminated.

10. Open valve 2E5 1-F019.

At panel 2C82-POO1, MIN

FLOW VLV, 2E51-F019, is

OPEN, red light illuminated.

SOpen valve ;2E51-,F045.

..

At panel 2C82-P001, STM TO

TURB VLV, 2E51-F045 is

OPEN, red light illuminated.

RESPONSE CUE:

Valve, 2E5 1 -F045, green light illuminated.

PROMPT:

IF the operator addresses purpose for RCIC operation, as the Shift

Supervisor, INFORM the operator that RCIC operation is for RWL control.

At

panel 2C82-POO1, DISCH

"

VLV, 2E51-F013, is OPEN, red

. . .,-

light illuminated.

RESPONSE CUE:

PROMPT:

Valve, 2E5 1 -FO13, green light illuminated.

Valve, 2E51--F019, red ight illuminated.

IF the operator addresses RWL band, as the Shift Supervisor, INFORM the

operator that another operator will maintain RWL.

(** Indicates critical step)

13.

Close (heMipimum Flow V

At panel 2C82-P001, when flow

is greater than 122.5 gpm o

gpntRCIC

FLOW,2CS2EDQ2'MIN

4

K

FLOW VLV, 2E5 1-F019, is

7' CLOSED, green light

illuminated.

-6 qaoTt'-

LR-JP-39.16-12

Page 11 of 11

'STEP

.PERFORMANCE

STEP

TANDARDT

PROMPT:

IF the operator addresses securing RCIC or system restoration, as the Shift

Supervisor, INFORM the operator that it is not desired at this time.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

I

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERN

COMPANY

Energy to Serve Your World3"

A

,TITLE

DURING A LOSS OF AIR, ISOLATE THE FIRE PROTECTION SPRINKLERS

MEIUBR

TIME

AUTHOR:

13.0 Minutes

LR-JP-36.13-07

R. A. BELCHER

RECOMMENDED BY

R.APPRELD

02

BYD

NIR

R. A. BELCHER

03/12/2002

Sk

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page 1 of t

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS TRAINING

Media Number:

LR-JP-36.13

01

09/04/92 General revision and format change

WMM

SMC

02

07/22/93

General revision, word processor change

03

08/19/94 Procedure change, adjust format, change initiating cue

SMC

to a direct command

04

08/01/96

Format change, modify time allowance

DHG

05

02/25/00

Format modification, change time allowance based on

DHG

running average, update K/As

06

11/02/00

Include objective number, change operator

DHG

applicability to Systems Operator

07

03/12/02

Include initial operator statement

I

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_______

£

I

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LR-JP-36.13-07

Page 1 of 1

UNIT 1 (X)

UNIT 2

(X)

TASK TITLE.

DURING A LOSS OF AIR, ISOLATE THE FIRE

PROTECTION SPRINKLERS

JPM NUMBER.:

LR-JP-36.13-07

TASKSTANDARD

The task shall be completed when the Fire Protection Sprinklers

have been isolated during a loss of air per 34AB-P51-001.

TASK NUMBER:

036.013

OBJECTIVE NUMBER:

036.013.O

PLANT HATCH JTA IMPORTANCE RATING:

3.57

3.70

K/A CATALOG NUMBER: 2860002130

KIA CATALOG JTA IMPORTANCE RATING:

3.90

3.40

OPERATOR APPLICABILITY:

Systems Operator (SO)

GEERAL RFRENCES:tftl

' tUzi2

I34AB-P51-001-1S Rev 2Ed 3

34A&B-P51-001-2S

Rev 2Ed 1

SREQUIRED MA..,:TERIALS:1Ui

34AB-P51-001-1S

(current revision)

APPROXIMATE COMPLETION TIME:

SIMULATOR SETUP:

N/A

34AB-P51-001-2S

(current revision)

13.0 Minutes

j

I

UNIT 1

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

A scram has occurred on Unit 1.

2.

Unit 1 has had a loss of control air pressure and header pressure is below

45 psig and NOT increasing.

3.

No fires exist in the plant.

4.

Another operator is isolating Fire Protection Sprinklers to the Start-up

Boiler and to the Main, Aux, and Startup Transformers.

5.

34AB-P51-001-1S, "Loss of Instrument and Service Air System," is in

progress.

INITIATING CUES:

Isolate the Fire Protection Sprinklers inside the Power Block per

Attachment 1 of 34AB-P51-001-lS.

LR-JP-36.13-07

Page 3 of 3

STEP

STAND ARD..SATUSAT>::

ŽPERORMACE~T~d

3/4}COMENTS)

START

TIME:

NOTE: The steps of this JPM may be performed in any order.

ya

1U43

At location 164TCT04, valve

I

RESPONSE CUE:

N/A1U3F2DiCLS.

Closevalv

1U4-F3OB.

~At

location l3OTETO4, valve

I 1U43-F301B is CLOSED.

RESPONSE CUE:

N/A

NOTE: This valve isolates the Generator Hydrogen Seal Oil System area.

1Z43-FO18A is CLOSED.

ClSPONSEvv1-F

AAt

location 1N/THT04, valve

RESPONSE CUE:

N/A

NOTE: This valve isolates the Lube Oil Storage Tank area.

PROMPT:

IF the operator addresses stationing a fire watch, as the Shift Supervisor,

INFORM the operator that a fire watch is being posted with back-up

suppression equipment.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

Operator states the task is complete.

TERMINATING CUE:

We will stop here.

(** Indicates critical step)

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

A scram has occurred on Unit 2.

2.

Unit 2 has had a loss of control air pressure and header pressure is below

45 psig and NOT increasing.

3.

No fires exist in the plant.

4.

Another operator is isolating Fire Protection Sprinklers to the Startup

Transformers.

5.

34AB-P51-001-2S, "Loss of Instrument and Service Air System," is in

progress.

INITIATING CUES:

Isolate the Fire Protection Sprinklers inside the Power Block per

Attachment 1 of 34AB-P51-001-2S.

LR-JP-36.13-07

Page 5 of 5

PERFRMACE

~tEA 4i4~4DOM.MENTSt

START

TIME:

NOTE: The steps of this JPM may be performed in any order.

I Close valve 2U43-F093.

,At

location 112TAT19, valve

........

12U43-F093 is CLOSED.

RESPONSE CUE:

N/A

NOTE: This valve isolates the Reactor Feed Pump and Oil Conditioner area.

Closevalve 2U43-14.At

location 136THT20, valve

RES

E2U43-F214

is CLOSED.

RESPONSE CUE:

N/A

NOTE: This valve isolates the Hydrogen Seal Oil System, W End Cond A & B

(Below 130') and W End Cond A & B (Above 130') areas.

S '

Close<4e 243-F1O1.

iiAt

location 1 12THT13, valve

2Z43 F101 is CLOSED.

RESPONSE CUE:

N/A

NOTE: This valve isolates the Main Turbine Lube Oil Reservoir area.

PROMPT:

IF the operator addresses stationing a fire watch, as the Shift Supervisor,

INFORM the operator that a fire watch is being posted with back-up

suppression equipment.

Close a

U.

,

At location 13OTAT19, valve

.' -

,

.2U43-F090

is CLOSED.

RESPONSE CUE:

N/A

NOTE: This valve isolates the RFP Oil Conditioner area.

END

TIME:

-

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

(** Indicates critical step)

LR-JP-36. 13-07

Page 6 of 6

STEP

P.R.O..ANCE..

...

............

ATI.NSAT `

TERMINATING CUE: We will stop here.

(** Indicates critical step)

.. .... .

..

.

.. .. . ..

P a

I

,Kob

J0006ECIRCMMDOC

SOUTHERNA L

COMPANY

Energy to Serve Your WorldM

1

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

S.. ..

....

..........................

0C

Page 2

(T

m t*~

- JPOO406RECIRCMM.DOC

.

.......... .....................

__-_

Program/Course Code:

OPERATIONS training

Media Number:

LR-JP-04.06

01

06/09/89

General revision and format change

wgw

rs

02

08/03/89

Procedure revision

jem

dh

03

08/24/89

Revised initial conditions

jem

smc

04

09/22/89

General revision

jem

wrb

05

08/29/90

Procedure, format, and question revision

jem

dhR

06

05/20/91

General/procedure revision

la

dhg

07

08/21/92

General revision and format change

wmm

seb

08

07/08/93

Incorporate new controllers and word processor

mmg

DHG

change

09

07/24/94

Procedure changes, modify simulator setup, adjust

rab

smc

format, change initiating cue to a direct command

10

02/20/95

Adjust time allotment, modify simulator setup to

rab

DHG

incorporate instructor feedback, adjust format, put

phonetics into the initiating cues

11

05/15/96

Format change

rab

dhg

12

05/28/97

Revised due to procedure change.

SCB

DHG

13

01/18/00

Format modification, change time allowance based on

rab

dhg

running average

14

05/19/00

Incorporate student/instructor comments

rab

dhg

15

10/30/00 Include objective number, incorporate instructor

rab

dhg

comments, correct simulator setup

16

02/22/02

Include initial operator statement

rab

2

...

-..

Paqe**-.

,*

w-*

z

...

. v'

,

rTimobthy Kob- JP00406RECIRCMM.DOC

LR-JP-04.06-16

Page 3 of B

UNIT 1

(X)

UNIT 2

(X)

q

SHIFT RECIRC CONTROL FROM INDIVIDUAL TO

MASTER CONTROL

LR-JP-04.06-16

task shall be completed when Reactor Recirculation Pump

"2A" and "2B" have been shifted from Individual to Master

Control, per 34SO-B31-001.

1 004.006004.006

004.006.A004.006.A

PLANT HATCH JTA IMPORTANCE RATING:

3.203.20

SRO 3.193.19

K/A CATALOG NUMBER: 202001A401202001A401

K/A CATALOG JTA IMPORTANCE RATING:

3.703.70

3.703.70

OPERATOR APPLICABILITY:

Reactor Operator (RO)

I340-B53 1-001-2S

I(current revision)

APPROXIMATE COMPLETION TIME:

11.0 Minutes

SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING

PAGE

3

~~R

....

................

....

MM DO 1C

Pag 4

LR-JP-04.06-16

Page 4 of 0

SIMULATOR SETUP

Simulator Initial Conditions:

1.

Reset the Simulator to IC #128 and leave in FREEZE.

2.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Ensure pump speeds are >45%. Place Recirc Pumps A and B in Individual Manual

Mode.

B.

Using Individual Pump Controllers, ensure there is approximately a 5% mismatch in

individual pump speeds, but both are >45%.

C.

Reduce Master Controller to <45% output.

D. Ensure the plant has stabilized.

3.

Place the Simulator in FREEZE until the INITIATING CUE is given.

4.

ESTIMATED Simulator SETUP TIME:

10 Minutes

4

Timothy Koib - JP004O6RECIRC .MM.DOG

Page...

LR-JP-04.06-16

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

Recirc Pumps "2A" and "21" are in Individual Manual Control mode.

Both individual controllers are in MANUAL.

2.

Recirc Pumps "2A" and "2B" are greater than 45% speed.

INITIATING CUES:

Place Recirc Pump "2A" and "28" in Master Manual Control.

Page 5 of 6

Kolb - JP0406REClRCMM.DOCPage

mrothy

........

.....

......

.............

........

_

LR-JP-04.06-16

Page 6 of 6

start

time:

-

RESPONSE CUE:

N/A

NOTE: When the PF lamp is lit, the vertical barograph and the digital display both

indicate the controller output. Depressing the PF key will switch off the

PF lamp and the controller input will then be displayed on both the vertical

barograph and digital display.

(** Indicates critical step)

.....

..

.Page

LR-JP-04.06-1 6

Page 7 of 6

REPNECU:

SpenonrlertB1

r621,

ManualR6M" Ambe i

ghAto

thealll

"A" gren pusbutto

iilluminated.

PROMPT:

IF the operator asks permission to reduce power to perform the next step,

INFORM the operator as the Shift Supervisor that power reduction is

permitted.

RESPONSE CUE:

N/A

RESPONSE CUE:

2]]At

panel 2H11I-P602, the operator

S*places

Recirc pump 2B Speed

~~Control,

.,

2B31-R621B, in Auto, the "A"

~green

pushbutton illuminated.

Speed Controller, 2B331-R6211B, Manual "M" amber light

illuminated.

PROMPT:

If the operator addresses changing Reactor power in Master Manual Control,

as the Shift Supervisor, inform the operator that you want to maintain the

present Reactor power level.

(** Indicates critical step)

U hi~h Kolb- JP00406REC]RCMM.DOC

--

m* e

--.

t.--

-

T i o

, =

. .. ......

....

...........

.. . ... .

....

.

LR-JP-04.06-16

Page 8 of 6

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double thb

allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERN

COMPANY

Energy to Serve Your World V

TI TLE

INITIATE EMERGENCY TORUS VENTING USING THE EMERGENCY

VENT PATH

AUTHORý

ýMEDIA NMBER

TIME

R. A. BELCHER

LR-JP-13.53-10

12.0 Minutes

RECOMMENDED BY

A

V

Y

DATE

N/R

R. A. BELCHER

03/07/2002

k

Program/Course Code:

OPERATIONS TRAINING

Media Number:

LR-JP-13.53

r~ir~e~ibu

itiias

08/01/90 General revision and format change

JEM

05/24/91

General/procedure revision

JLA

08/18/92

06/23/93

12/02/93

06/17/96

02/04/00

General revision and format change

Task change, rename, procedure change, word

processor change

Change initiating cue to a command, change valve

ding to match the plant

Format change, modify time allowance

Format modification, title change, change time

allowance based on running average

11/02/00

Include objective number

01/03/02

Change Unit 2 control pressure to 56

03/07/02 1 Include initial operator statement

,j filtiasi

DHG

WMM

SCB

Rev. No

01

02

03

04

LR-JP-13.53-10

Page 1 of 1

UNIT 1 (X)

UNIT 2

(X)

.TITLE:

INITIATE EMERGENCY TORUS VENTING USING

THE EMERGENCY VENT PATH

i JPM NUMBER:

LR-JP-13.53-10

T, ASK STANDA

This task shall be completed when the Torus is lined up to vent

via the Emergency Vent per 31EO-EOP-101.

TASK NUMBER

013.053

OBJECTIVE NUMBER:

013.053.O

PLANT HATCH JTA IMPORTANCE RATING:

4.14

4.50

K/A CATALOG NUMBER: 223001A207

K/A CATALOG JTA IMPORTANCE RATING:

4.20

4.30

OPERATOR APPLICABILITY:

Reactor Operator (RO)

34SO-T48-002-1S Rev 19

34SO-T48-002-2S Rev 19

Ed 2

Ed 3

31EO-EOP-101-1S Rev 3

31EO-EOP-101-2S Rev 4

31EO-EOP-012-1S Rev 4

31EO-EOP-012-2S Rev 4

REQUIRED M4ATERIALS:

Un,*fit 1

,Ui,

31EO-EOP-101-1S

31EO-EOP-101-2S

(current revision)

Designated jumpers(2) in EOP

jumper book

Screwdriver or nutdriver

APPROXIMATE COMPLETION TIME:

12.0 Minutes

SIMULATOR SETUP:

N/A

UNIT 1

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

Unit 1 Torus pressure is above the Pressure Suppression Pressure.

2.

31EO-EOP-012-1S (PC-i) is in progress.

3.

Standby Gas Treatment is in operation, taking a suction from the Reactor

Building.

4.

Torus Venting with CAD is in progress and Torus pressure cannot be

maintained below 54 psig.

5.

Normal AC Power is available.

INITIATING CUES:

Perform Torus venting using the emergency vent path per

31EO-EOP-101-1S, Step 3.1.6.

LR-JP-13.53-10

Page 3 of 3

STA NDAP

I

SATNSAT/

RESPONSE CUE:

SBGT A Fan, 1T46-COU1B, red ngnt llunminateu.

(** Indicates critical step)

START

TIME:

1. Operator identifies the materials that

Operator identifies the required

are required.

materials and where to obtain

them.

PROMPT:

IF addressed by the operator, as the Shift Supervisor, INFORM the

operator that another operator is monitoring the NPSH curves for RHR and

Core Spray.

PROMPT:

IF addressed by the operator, INFORM the operator that normal AC power

and Non-interruptible air are available.

I.,

IClose SBGT4iletIsoi436tYaP&Yl At panel 1H 11-P654, the operator

1748-108.

CLOSES 1T48-F081, SBGT

INLET ISOL VLV, green light

illuminated.

RESPONSE CUE:

Valve 1T48-F081, red light illuminated.

3. Close or verify closed SBGT Inlet

At panel IH 11-P654, the operator

Isolation Bypass Valve, 1T48-F083.

CLOSES or verifies closed

1T48-F083, SBGT INLET ISOL

BYP VLV, green light

illuminated.

- 4. Plac* 1T4!6-COlA*

SBGT'A ýFato 9I At panel IH11 -P657, the operator

Off an

ts thatthefeii stdps.

PLACES 1T46-CO01A, SBGT A

V

FAN to OFF, green light

illuminated and VERIFIES that

fan stops.

RESPONSE CUE:

SBGT A Fan, 1T46-CO01A, red light illuminated

- 5

Place 1+/--C0

, SBGTB*ato4

At panel 1H 11-P654, the operator

OFF and cqnfirm that th

n sbf

PLACES lT46-COOlB, SBGT B

j...

Fan to OFF, green light

illuminated and VERIFIES that

fan stops.

LR-JP-13.53-10

Page 4 of 4

STEP]

PROM NESE

SADR

A/NA

(COMMENTS).:

6.

PlI

At panel

IH11-P657, the operator

qCnt*rol

Da

r to cse

.

CLOSES 1T46-F005, DISCH

CONTROL DAMPER, green

light illuminated.

RESPONSE CUE:

Damper 1T46-F005, red light illuminated.

- 7*

1 nstallju~per from UU-4z8 to&UUA6 4* At panel 1Hi11-P6OlD, the

S 1 T48-F326,

'>......

,;: :: ,:*,

<,* from uu-48 to uu-61, for valve

RESPONSE CUE:

N/A

rAt

panel 1H11-P602A, the

m panel.1HI- .60

operator INSTALLS a jumper

lT48-F*i.:

from AA-70 to AA-81, for valve

1T48-F3218.

RESPONSE CUE:

N/A

.

On

Vn

v3

At panel 1H 11-P601, the operator

I . ...

I ............

. ..... ...

OPEN..S 1T48-F326, TORUS

li:

VENT VLV, red light

RESPONSE CUE:

Valve 1T48-F326, green light illuminated.

I*1.

Ope Torus VentValve, 1148-P318.

At panel 1H 11-P602, the operator

OPENS 1T48-F318, TORUS

VENT VLV, red light

...........

i l u m i n a t e d .

RESPONSE CUE:

Valve 1T48-F3 18, green light illuminated.

PROMPT:

IF addressed by the operator, as the Shift Supervisor, INFORM the

operator that the EOF Dose Assessment Staff and the TSC HP Supervision

have been notified of the potential radioactivity release.

911.,

Oe

o ustme..g.nc**y VeX"tValve,

At panel IHl 1-P654, the operator

0T48F2.'

<<

OPENS 1T48-F082, SUPP

CHBR EMER VENT VLV, red

light'illuminated.

RESPONSE CUE:

Valve IT48-F082, green light luumlnateu.

(** Indicates critical step)

LR-JP-13.53-10

Page 5 of 5

S-'ýPiiiORMA

iý

.,V

SAT/[NSAT

'

PROMPT:

IF the operator addresses Torus pressure, INDICATE for the operator that

Torus pressure is <54 psig and decreasing.

PROMPT:

IF the operator addresses System Restoration, INFORM the operator as the

Shift Supervisor that it is not desired at this time.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

Unit 2 Torus pressure is above the Pressure Suppression Pressure.

2.

3 1EO-EOP-012-2S (PC-i) is in progress.

3.

Standby Gas Treatment is in operation, taking a suction from the Reactor

Building.

4.

Torus venting with CAD is in progress and Torus pressure cannot be

maintained below 56 psig.

5.

Normal AC Power is available.

INITIATING CUES:

Perform Torus venting using the emergency vent path per

31EO-EOP-101-2S, Step 3.1.6.

LR-JP-13.53-10

Page 7 of 7

STE

E

O

ANCE STZP

STAN.A.

.

(COMMENTS)

START

TIME:

iiI

.

operator identifies the materials that

Operator identifies the required

are required.

materials and where to obtain

I them.

PROMPT:

IF addressed by the operator, as the Shift Supervisor, INFORM the

operator that another operator is monitoring the NPSH curves for RHR and

Core Spray.

PROMPT:

IF addressed by the operator, INFORM the operator that normal AC power

and Non-interruptible air are available.

Close SBG

Inlet Isolation

At panel 2H 11-P654, the operator

2T4

........

CLOSES 2T48-F081, SBGT

x*

INLET ISOL VLV, green light

illuminated.

RESPONSE CUE:

Valve 2T48-FO81, red light illuminated.

3. Close or verify closed SBGT Inlet

At panel 2H1 11-P654, the operator

Isolation Bypass Valve, 2T48-F083.

CLOSES or verifies closed

2T48-F083, SBGT INLET ISOL

BYP VLV, green light

illuminated.

- 4

a2

-

AAt

panel 2H111 -P657, the operator

SBGTA

OFF'anidverifyt tat 2T46-EOF

,

PLACES 2T46D~A SG

SBGT AFilter Discfhatgeýcloses:::i*!!*i*

FAN/FILTER to OFF, green light

,2T46-FOO2A,

FLTRDISCH

illuminated and VERIFIES that

.......... ::

246-1F002A, FLTR DISCH

CLOSES, green light illuminated.

RESPONSE CUE:

SBGT A Fan/Filter, 2T46-DOO1A, red light illuminated and/or

Damper, 2T46-FO02A, red light illuminated.

145

st: a~i

P1 rrAt

panel 2H11-P601D, the

inpanef

operator INSTALLS a jumper

2

from UU-45 to UU-61, for valve

2T48-17326.

RESPONSE CUE:

N/A

(* Indicates critical step)

LR-JP-13.53-10

Page 8 of 8

STEPý

rEJOMN

SADR

A/NA

V s.aAt

panel 211 -P602A, the

in p6

operator INSTALLS a jumper

2

1

..

.

from AA-70 to AA-73, for valve

...

.

2T48-F318.

RESPONSE CUE:

N/A

I OpenjbisVent Va

At panel 2H11 1-P601, the operator

OPENS 2T48-F326, TORUS

VENT VLV, red light

illuminated.

RESPONSE CUE:

Valve 2T48-F326, green light illuminated.

8.

pe nTorus: Vent

ve,4-31

8.

At panel 2H 11 -P602, the operator

OPENS 2T48-F3 18, TORUS

VENT VLV, red light

-

illumrinated.

RESPONSE CUE:

Valve 2T48-F318, green light illuminated.

9. Close or confirm closed Torus

At panel 2H111 -P654, the operator

Emergency Vent Drain Valve,

VERIFIES that 2T48-F085,

2T48-F085.

SUPP CHMBR EMERG VENT

DRN VLV, is CLOSED.

¶O.Opne T

sEmergency Ye&YtveJ K At panel 211-P654, the operator

2........-

OPENS 2T48-F082, SUPP

C... MBR EMERG VENT VLV,

rdlight illuminated.

RESPONSE CUE:

Valve 2T48-17082, green lngnt iummateu.

PROMPT:

IF the operator addresses Torus pressure, INDICATE for the operator that

Torus pressure is <56 psig and decreasing.

PROMPT:

IF the operator addresses System Restoration, as the Shift Supervisor,

INFORM the operator that it is not desired at this time.

END

TIME:

1:;2

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double

the allotted time.

-

Operator states the task is complete.

(** Indicates critical step)

LR-JP-13.53-10

Page 9 of 9

STEP

PtRFRMANCSTP.

tSAAD$TUNA

TERMINATING CUE: We will stop here.

"3/4..>

(** Indicates critical step)

Timth yK9ýIb PW2ISDOC

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERN fl

COMPANY

Energy to Serve Your World"

I

Page

riohKob-JP25O5OHPCI .DOC

___.............................

Pa_____

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page 1 of 1

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS training

Media Number:

LR-JP-25050

2

Timothy KoIb - JP25050HPCI.DOC

Page

LR-LP-25050-00

Page 3 of 9

UNIT 1 ( )

UNIT 2

(X)

1PERFORM

A MANUAL STARTUP OF HPCI AND

ID

MAINTAIN REACTOR WATER LEVEL IN BAND

LR-LP-25050-00

The task shall be completed when the HPCI System is injecting

S$,

to the Reactor with turbine speed greater than 2000 rpm per

0

111

34SO-E41-001-2S, and RWL is controlled in band.

005.002005.002

005.002.A005.002.A

PLANT HATCH JTA IMPORTANCE RATING:

3.003.00

3.003.00

K/A CATALOG NUMBER: 206000G009206000G009

K/A CATALOG JTA IMPORTANCE RATING:

4.304.30

SRO 4.004.00

OPERATOR APPLICABILITY:

Reactor Operator (RO)

APPROXIMATE COMPLETION TIME:

3.0 Minutes

SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING

PAGE

3

LR-LP-25050-00

Page 4 of 9

SIMULATOR SETUP

Simulator Initial Conditions:

1.

Reset the Simulator to IC #121 and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS:

mfE51_109

RCIC Failure to Auto Start

00000

mfR22_180

4KV Bus 2C Fault

00000

mfR22_181

4KV Bus 20 Fault

00000

mfE41 235A

HPCI Fails to Auto Start on Low Level

00000

mfE41_235B

HPCI Fails to Auto Start on Hi Drywell

00000

Pressure

mfN21_87A

Feedwater Pump A Trip

00000

mfN21_87B

Feedwater Pump B Trip

00000

3.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Perform RC-1 and RC-2.

B.

Allow simulator to mn until RWL as indicated on 2B21-R623A and B is <-80

inches.

C. Acknowledge annunciators.

4.

Place the Simulator in FREEZE until the INITIATING CUE is given.

5.

ESTIMATED Simulator SETUP TIME:

10 Minutes

4

I

[TimothyKolb - JP25050HPCI.DOC

Pa e

LR-LP-25050-00

Page 5 of I

-V

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

2.

3.

4.

5.

6.

The HPCI System is in Standby.

A loss of the Feedwater pumps has occurred.

31EO-EOP-010-2S (RC) is in progress.

RWL is < -80 inches and decreasing.

HPCI failed to autostart.

HPCI is required to maintain RWL.

INITIATING CUES:

Start HPCI manually and inject into the Reactor and maintain Reactor

Water Level +3" to +50".

[TimothyKo.b-

JP25O50HPCI.DOC

Pae

LR-LP-25050-00

Page 6 of 1

start

time:

-

PROMPT:

If the operator addresses HPCI suction transfer logic, as the Shift

Supervisor, inform the operator that the HPCI high Torus level suction

transfer logic has been overridden.

-,

'ýN

'b

kl'W

,ýA

ae 2H1 l-P601, LUBE OIL

01 ui

4.

CLG WTR VLV, 2E41 -F059 is

!*;*1open,

red light illuminated.

RESPONSE CUE:

Valve, 2E41-17059, green light illuminated.

2. Start HPCI Barometric Condenser

At panel 2-11 -P601, HPCI

Vacuum Pump, 2E41-C002-2.

BAROM CNDSR VACUUM

PUMP, 2E41-C002-2 is

operating, red light illuminated.

PROMPT:

If the operator addresses posting High Radiation Areas, as the Shift

Supervisor, inform the operator as Shift Supervisor that Health Physics is

posting the areas.

NEW

At panel 2H1 1-P601, the TURB

STEAM SUPPLY VLV,

2E41 -F001 control switch is in

i

the OPEN position, red light

p

,illuminated.

RESPONSE CUE:

Valve, 2E41-FOO1, green light illuminated.

NOTE: Valve 2E41-F001 is not required to be full open prior to proceeding to

following steps.

, 4 2i

§

I

digu

A t panel 2H11-P601, the AUX

OIL PUMP, 2E41-C002-3, is

Soperating,

red light illuminated.

RESPONSE CUE:

HPCI Auxiliary Oil Pump, green light illuminated.

S*

1 At panel 2H11 l-P601, PUMP

DISCHARGE VLV, 2E41-F006

is open, red light illuminated.

RESPONSE CUE:

Valve, 2E41-F006, green light illuminated.

(** Indicates critical step)

'

I

Page

[Timothy ~( - JP25050HPCI.DOC__

_

LR-LP-25050-00

Page 7 of 6

IfTis

Confirm the following valves are

open:

At panel 2H1 1-P601, the

following valves are open, red

light illuminated:

TURBINE CONTROL VLV

NOTE: If HPCI is started per the Placard, the following steps may be omitted.

(** Indicates critical step)

,Timothy Kolb - JP25050HPCI.DOC

Fiage

LR-LP-25050-00

Page 8 of 6

10. Confirm the following valves are

At panel 2HI l-P602, the operator

closed:

has confirmed the following

2141 -F7028

valves are closed, green light

illuminated:

2E41-F025

2E41-E028, STEAM LINE

2E41-F029

DRAIN VLV

2E41-F026

2E41-F025, BAROM CNDSR

DISCH TO CRW

2E41-F029, STEAM LINE

DRAIN VLV

2E41-F026, BAROM CNDSR

DISCH TO CRW

PROMPT:

If the operator addresses HPCI BAROM CNDSR LEVEL HIGH, indicate

for the operator that it is extinguished.

PROMPT:

If the operator addresses CST level or Torus water level, indicate for the

operator that CST level is 25 feet and Torus level is 148 inches.

PROMPT:

If the operator addresses shutting down HPCI, as Shift Supervisor, inform

the operator that shutdown is not desired at this time.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double the

allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

I

(*' Indicates critical step)

11.

Confirm Barometric Condenser

At panel 2H11 -P601, the operator

Condensate Pump, 2E41-C002-1

has verified HPCI BAROM

cycles automatically to maintain

CNDSR LEVEL HIGH

barometric condenser water level,

annunciator (601-129) is clear.

rlnomt hyKolb -JP25O42Rec

irc.D OC-

_

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERN Lka

COMPANY

Energy to Serve Your World"

1

START A RECIRC MG SET FROM THE CONTROL ROOMSTART A RECIRC

MG SET FROM THE CONTROL ROOM WITH FAILURE OF PUMP SEALS.

Dale MoranR. L. SMITH

LR-JP-25042-OOLR-JP-25042-OO

3g.038.O Minutes

t. f. phillips

r. s. grantham

10/07/02

Tm5042Recirc ..

Page

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page I of 1

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS training

Media Number:

LR-JP-25042

2

LiTrmoth

Kolb -JP25042RecirC.DoC

wag

LR-JP-25042-0O

LR-JP-25042-00

Page 3 of 2

UNIT 1

0

UNIT 2

(X)

r :T,

r 2r11R

START A RECIRC MG SET FROM THE CONTROL

ROOM WITH FAILURE OF PUMP SEALS.

R

ILR-JP-25042-00

The task shall be completed when the Recirculation Motor

Generator set has been started and then Reactor Recirc

Pump is secured and isolated, per 34AR-602-116-2.

77

004.002004.002, 004.003

004.002.A004.002.A, 004.003A

PLANT HATCH JTA IMPORTANCE RATING:

3.503.50, 2.79

3.223.22, 3.15

K/A CATALOG NUMBER: 202001A401202001A401, 202001A210

K/A CATALOG JTA IMPORTANCE RATING:

3.303.30, 3.50

3.103.10, 3.90

OPERATOR APPLICABILITY:

Reactor Operator (RO)

N/A

34SO-B31-001-2 Rev 31.6

34AB-B31-001-2 Rev 7.3

34AR-602-116-2

Rev 2.2

34AR-602-122-2 Rev 4.4

V¶~

A

kr.

~0

APPROXIMATE COMPLETION TIME:

SIMULATOR SETUP:

38.0 Minutes

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING

PAGE

J~

Attachment 5

34AR-602-116-2

34AR-602-122-2

(current revisions)

3

N/A

[Timothy Kolb -i JP25042Recirc. DOC , ....................

.

.....................

LR-JP-25042-00

Page 4 of 9

SIMULATOR SETUP

Simulator Initial Conditions:

1.

Reset the Simulator to IC #121 and leave in FREEZE.

2.

Insert the following Malfunctions:

MALF#

TITLE

FINAL

RAMP

ACT.

I VALUE

RATE

TIME

mfB3139A

RECIRC 2A INNER SEAL FAILURE

9999

mfB31 45A

RECIRC 2A OUTER SEAL FAILURE

9999

3.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Stop Reactor Recirc Pump 2A(B); close and then throttle the discharge valve open,

and reduce 2B31-R621A speed to 30%.

B.

Reset annunciators (602-106) PUMP MOTOR A (B) OIL LEVEL HIGH and

(602-112) PUMP MOTOR A (B) OIL LEVEL LOW.

C.

Lower the Operating Recirc Pump Speed to reduce Recirc Flow to <22,000gpm

D. Backout the 2A RFPT to -2000 rpm.

E.

Insert Rod groups 44H and 44G to "00" position.

4.

Place the Simulator in FREEZE until the INITIATING CUE is given.

5.

ESTIMATED Simulator SETUP TIME:

10 Minutes

-V

4

L

LTmoyKolb-

P25042Recirc.DOC

.

Pas

LR-JP-25042-00

Page 5 of 2

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

Reactor Recirc Pump 2A(B) tripped one hour ago. The cause of

the pump trip has been found and corrected. Procedure 34AB

B31-001-2S has directed that the Reactor Recirc Pump be

restarted per 34SO-B31 -001 -2S.

2.

The Generator Lockout reset switch has been reset and the

Generator Field Ground Detect switch is in NORM position.

3.

4.

5.

Circulating oil pumps Al, A2 (B1, 62) are running.

Reactor Recirc Pump 2B(A) is still in operation.

Other operators are performing ATTACHMENT 5 through step 7.1.

1kteolqlpW4-. .

INITIATING CUES:

Start 2A(B) Recirc Pump, using the normal startup section 7.1.2 of

34SO-B31-001-2S.

J

J

[Timothi Koib - JP25042Recirc DOC

Page

LR-JP-25042-00

Page 6 of 2

start

time:

-

1. Operator reviews the procedure's

Operator has reviewed the

precautions and limitations,

precautions and limitations.

(Section 7.1.2)

PROMPT:

If addressed by the operator, inform the operator that PUMP MOTOR

2A(B) OIL LEVEL HIGH 602-106 (206), and PUMP MOTOR 2A(B) OIL

LEVEL LOW 602-112 (212) are cleared.

PROMPT:

If addressed by the operator, inform the operator that the MG Set A(B) lube

oil system is in operation.

PROMPT:

If addressed by the operator, inform the operator that the Generator Lockout

Reset Switch, on panel 2B31-P003A(B), is RESET and the yellow flag is

RESET.

PROMPT:

If addressed by the operator, inform the operator that the Generator Field

Ground Detect Test Switch, at panel 2B331 -P003A(B), is in the NORM

position.

PROMPT:

When the operator addresses lube oil temperature, as the SO, inform the

operator, that lube oil temperature is 105'F.

PROMPT:

IF addressed by the operator, INDICATE to the operator that Recire loop A

is not isolated.

PROMPT:

When the operator addresses the Seal Purge Isolation valves, as the SO,

inform the operator that the valves are open.

2. Verify Reactor Recirc Pump Suction

At panel 2H1 1-P602, PUMP

Valve, 2B 31-F023A(B) is open.

SUCTION VLV,

2B331-F023A(B) is open, red light

illuminated.

PROMPT:

When the operator addresses the Seal Flow Regulator, if necessary indicate

that the plant is at rated pressure, as the SO, then inform the operator that it

is set at 2 gpm.

PROMPT:

If addressed by the operator, inform the operator it is not required to vent

the Recirc pump seals.

(** Indicates critical step)

[itmoj lv

-' JP25042Recirc.DOC

Page

LR-JP-25042-00

Page 7 of 7

, g

ý , "Nýo

3-

N

jil

Qig

'0

"A

'J PON

1-0100

Verify Master Recirc Flow Controller,

2B31-R620, is in manual.

RESPONSE CUE:

Reactor Recirc Pump

at 44%.

At panel 2H11 -P603, the

MASTER RECIRC FLOW

CONTROLLER, 2B31-R620, is

in MAN.

At panel 2H11 -P602, SPEED

CONTROL, 2B31-R621A(B), is

in manual, amber manual

pushbutton light illuminated.

At panel 2H11 -P602, the Speed

Demand Indicator,

2B31-R661A(B), has been

adjusted to 44% +-4%.

2A(B) Speed Control, 2B31-R621A(B), is not

6. Confirm annunciator 602-126(226)

At panel 2H11 -P602, operator

Fluid Drive A(B) Scoop Tube Lock,

verifies 602-126(226) FLUID

clear.

DRIVE A(B) SCOOP TUBE

LOCK is clear, window is

extinguished.

7. Verify RWL is greater than +32

At panel 2H1 1-P603, the operator

inches.

verifies that RWL is greater than

+32 inches.

NOTE: The evalualtor must put current time on step 7.1 prior to giving the

copy to the operator.

PROMPT:

When the operator addresses ATTACHMENT 5, PROVIDE the operator

with the marked up copy of ATTACHMENT 5.

Confirm or start Reactor Recirc 2A(B)

MG Set Room Cooler

2T41-B012(B013).

At panel 2H11 -P657, the RX

RECIRC 2A(B) MG SET ROOM

COOLER, 2T41 -B012(B013), is

running, red light illuminated.

At panel 2H111 1-P602, PUMP

DISCH VLV 2B331 -FO3 IA(B) is

closed, green light illuminated.

RESPONSE CUE:

Discharge valve, 2B31-F031A(B), red light illuminated.

(** Indicates critical step)

I.

Timotiy Kolb - JP25042Recirc.DOC

..

LR-JP-25042-00

Page 8 of 7

OWN

au

RESPONSE CUE:

N/A

NOTE: While the operator is addressing his ARP steps a High Drywell Pressure

scram may come in due to Recirc pump seal leak.

PROMPT:

IF a reactor scram occurs while the operator is addressing actions to islolate

the Recirc pump seal leak, INFORM the operator that other operators will

take scram actions.

(** Indicates critical step)

I&*t*17At

panel 2H1I-P602, RX

P(,[

2 2B31-SOOIA(B) started, red light

T

I

4

illuminated.

RESPONSE CUE:

Reactor Recirc Pump MG Set, 2B31-S001A(B), green light

illuminated.

11.

Complete remainder of Attachment 5.

Attachment 5 has been completed

through step 7.4.

AFTER the pump is started and the Discharge valve is full open, ENTER

MALFUNTIONS mfB31_39A, "RECRIC PUMP 2A INNER SEAL FAILURE" and

mfB31_45A, "RECIRC PUMP 2A OUTER SEAL FAILURE"

12. Address ARPs 34AR-602-116-2

At panel 2H11-P602, ARPs

34AR-602-116-2 are addressed.

13.

Confirm 2B31-R603A, Seal A No.1

At Panel 2H1 1-P602,

pressure indicator decreases, and Seal

DETERMINE 2B31 -R603A, Seal

A No. 2 pressure indicator decreases.

A No.1 pressure indicator

decreases, and Seal A No. 2

pressure indicator decreases.

RESPONSE CUE:

N/A

PROMPT:

IF the operator addresses having leakage checks per 34SV-SUV-019-2,

Surveillance checks, to determine magnitude of the leak. inform the

operator another operator will perform the leakage calculations.

14. Confirm an increase in FPM to

At panel 2HI -P645, monitor

determine that Reactor coolant is

2D1 l-R630, FPM recorder, to

leaking from the seals, at monitor

DETERMINE if primary coolant

2D11-R630, fission Products recorder,

is leaking from the seals by

observing an increasing trend.

oimtvKolb-JP25042Recirc.DOC

PL

LR-JP-25042-00

Page 9 of 7

rTEPI

41

UVM

15.

Confirm an increase in Drywell

At panel 2H1 1-P602 OR 2HI 1

pressure on 2T48-R607A/B, Narrow

P654, DETERMINE an increase

Range Drywell/Torus Wtr. Lvi

in Drywell pressure trend on

Recorder(s).

recorder(s) 2T48-R607A/B.

RESPONSE CUE:

N/A

16. Shutdown the 2B31-S001A, MG Set

At panel 2H11 l-P602, Rx Recirc

IA.

MG Set 2B331-SOO1A is SHUT

I

I DOWN, green light illuminated.

RESPONSE CUE:

Reactor Recirc Pump MG Set, 2B31-S001A(B), red light

illuminated.

RESPONSE CUE:

Discharge Valve 2B31-F0031A or Suction Valve 2831-F023A, red

light illuminated.

PROMPT:

WHEN addressed by the operator, to CLOSE seal purge valve 28331

F0008A, INFORM the operator that another operator will be dispatched to

CLOSE the seal purge valve 28331-F008A.

END

time:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double thc

allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

At panel 2H11 -P602, CLOSE Rx

Recirc MG Set 2B31-S001A:

Discharge Valve 2B31 -F03I A,

and Suction Valve 28331-F023A,

green lights illuminated.

J

Fimothv Koib - JP10.19MODESW.D oc

Pagqe

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

(

SOUTHERN

wa

COMPANY

Energy to Serve Your World'"

1

RANSFER THE

ODE SWITCH T

WITH AN APRM AT 15%

POWER

Dale MoranR. L. SMITH

LR-JP-10.19-00LR-JP-10.19-00

38.010.0 Minutes

t. f phillips

r. s. grantham

10/7/02

I

Ko

JP10.19MODESW DOC

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page 1 of 1

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS training

Media Number:

LR-JP-10.19

01

10/7/02

Initial development.

ris

rsg

2

I Timothy Kolb - JP10.19MODESW.DOC .p..

UNIT 1

0

UNIT 2

(X)

TRANSFER THE MODE SWITCH TO

STARTUP/HOT STANDBY, WITH APRM AT 15%

POWER

LR-JP-10.019

The task shall be completed when the APRM is bypassed

and the Mode switch is transferred to Startup/Hot Standby.

004.002010.019

004.002.AO10.019A

PLANT HATCH JTA IMPORTANCE RATING:

3.50

3.22

K/A CATALOG NUMBER: G2.1.23202001A401

K/A CATALOG JTA IMPORTANCE RATING:

3.93.30

4.03.10

OPERATOR APPLICABILITY:

APPROXIMATE COMPLETION TIME:

Reactor Operator (RO)

10 Minutes

SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING

PAGE

3

LR-JP- 10.19-00

Page 3 of 2

FAIN",

III r1a,

im

Kolb - JP10.19MODESW.DOCp,

LR-JP-10.19-00

Pa

4. of 9

SIMULATOR SETUP

Simulator Initial Conditions:

1.

Reset the Simulator to IC #105 and leave in FREEZE.

2.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Place the Mode Switch to RUN position

3. Insert the following Malfunctions:

MALF#

TITLE

FINAL

RAMP

AT.

I I VALUE

RATE

TIME

mfCSll9A

LPRM UPACALE 'B' LEVEL 20.29

0000

mf603233379

LPRM UPSCALE ALARM OFF

0000

4.

Place the Simulator in FREEZE until the INITIATING CUE is given.

5.

ESTIMATED Simulator SETUP TIME:

10 Minutes

24

LTothIy Kolb - JP10.19MODESW. D

P.a..

LR-JP- 10.19-00

Page 5 of 2

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

Reactor Shutdown is in progress; steps through 7.3.16 of

34GO-OPS-01 3-2 have been completed.

2.

The refueling bridge has power to it.

3.

The SOS has reviewed Attachment 3 of 34GO-OPS-013-2 with the

operating crew.

4.

All IRMs and SRMs are Operable.

5.

All required neutron surveillances for APRMs, IRMs, and SRMs are

completed SAT.

INITIATING CUES:

Transfer the Mode switch to Start & Hot Standby per 34GO-OPS

013-2.

hyy Kolb - JP10.19MODESW.DOC

_,

,,,,_

Page

LR-JP- 10.19-00

Page 6 of 2

start

time:

-

1. 1 Operator reviews the procedure's

Operator has reviewed the

1

precautions and limitations,

precautions and limitations.

PROMPT:

If addressed by the operator, inform the operator that the refueling bridge

has power to it per initial conditions.

2. Confirm that all OPERABLE IRMs

At panel 2H11 -P603, the operator

channel Upscale Trip OR Inop lights

VERIFIES that IRMs Upscale

are EXTINGUISHED.

TRIP OR Inop lights are

EXTINGUISHED.

RESPONSE CUE:

N/A

3. Confirms that INOPERABLE IRMs

At panel 2H11 1-P603, the operator

AND/OR SRMs are bypassed.

verifies that IRMs AND SRMs

INOP lights are extinguished.

RESPONSE CUE:

N/A

RESPONSE CUE:

N/A

NOTE: IF evaluating an RO and the RO identifies the 2B APRM reading > 11%

power the evaluator should declare the APRM INOP at this time.

PROMPT:

IF the operator addresses checking the APRM 2B at the back panel for any

apparent problem, THEN as another operator INFORM the operator that

APRM 2B is reading 15%, and no apparent problem is indicated.

PROMPT:

IF the operator request I&C assistance with APRM 2B. inform the operator

that several LPRMs inputting into APRM 2B appear to be out of calibration

and cannot be adjusted at this time.

PROMPT:

IF the operator addresses placing the APRM 2B in bypass. inform the

operator to place the 2B APRM in bypass.

At panel 2H 11 -P603, the operator

PLACES the APRM 2B in

Bypass.

ET7QYt*

Kolb- JP10.19MODESW.DOC

-Pag

LR-JP-10-019-00

Page 7 of 5

EiEP

(" Indicates critical step)

1

RESPONSE CUE:

APRM 2B not in Bypass.

6.

Confirm all rod blocks clear.

At panel 2H11-P603, the operator

verifies 603-238 ROD OUT

BLOCK is clear, window is

extinguished.

PROMPT:

IF the operator addresses SOS reviewing Attachment 3 of 34GO-OPS-013-2

with the operating crew. inform the operator that this has been reviewed per

the initial conditions.

fl *I flJ* dP the

o

¢0o

'i

At panel 2H1 1-P603, the operator

places the Mode Switch into

I

&*

START & HOT STBY position.

RESPONSE CUE:

The MODE switch is in RUN position.

8. Record the Time the Mode switch is

The operator records the Time the

placed in START & HOT STBY.

Mode switch is placed in START

& HOT STBY position in

34GO-OPS-0! 3-2.

9. Confirms the Annunciator "MSIV

At panel 2H I l-P603, the operator

CLOSURE TRIP BYPASS"

confirms 603-113 is illuminated.

illuminates.

RESPONSE CUE:

Annunciator 603-113 is extinguished.

PROMPT:

WHEN the operator addresses Confirming that the MSIV Closure Trip

Bypass relays are energized on Panels 2H1 1-P609/P61 1. inform the

operator that another operator will complete the rest of this section of the

procedure.

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double th(

allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

Tb

- JP250O44RHRSW -D0C .P.. .. ...

. .a..

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

SOUTHERN Ma

COMPANY

Energy to Serve Your World"

_J2

CRSTERRSRVC

AECOSTIE

RHR

SRVICE WATER WITH

A FAILURE OF THE SECOND RHRSW PUMP TO START

t.f. phipilips

r. s. grantham

10/07/02

1

Tmoth KolD-JP5044RHRSW.DOG

Page

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page 1 of 1

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS training

Media Number:

LR-JP-25044

00

10/07/02

Initial Development

rls

rsg

2

w

ZTimh'o

I OP

044RHRSW.DOC

,

P

LR-JP-25044-00

Page 3 of 9

UNIT 1

0

30 N

'411

NNW

I~~

UNIT 2

(X)

CROSSTIE RHR SERVICE WATER WITH A

FAILURE OF THE SECOND RHRSW PUMP TO START

LR-JP-25044-00

The task will be completed when RHRSW loop "A "has been

cross-tied to RHRSW loop "B" and discharge flow is reduced to

below 4400 gpm due to trip of the one of the RHRSW pump, per

34SO-El1-010.

034.008034.008

~~Big

034.008.0034.008.0

PLANT HATCH JTA IMPORTANCE RATING:

3.293.29

SRO Not AvailableNot Available

K/A CATALOG NUMBER: 219000A215219000A215

K/A CATALOG JTA IMPORTANCE RATING:

3.303.30

SRO 3.403.40

OPERATOR APPLICABILITY:

Reactor Operator (RO)

APPROXIMATE COMPLETION TIME:

15.0 Minutes

SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING

PAGE

3

Lvmtx

l -.. .JP25044RHRSW.DOC

Page

LR-JP-25044-00

Page 4 of 7

SIMULATOR SETUP

Simulator Initial Conditions:

1. Reset the Simulator to IC #128 and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS:

3.

INSERT the following ors OVERRIDES:

1,1 KK

U"

SrVAT

El1-C001lA

RHR Service Water Pmp lB

OFF

00000

El1-C001SBB

RHR Service Water Pmp IB

OFF

00000

El 1-C001D_A

RHR Service Water Pmp 1D

OFF

00000

El1-COOIDB

RHR Service Water Pmp ID

OFF

00000

Ell-F028ADI

p

RHR A Torus Spray/Test Vlv

CLOSE

00000

Ell-F028A_A

I

RHR A Torus Spray/Test Vlv

off

00000

Ell-F028A_B

1

RHR A Torus Spray/Test VIv

off

00000

4.

PLACE Danger Tags on the following equipment:

5.

ESTIMATED Simulator SETUP TIME:

10 Minutes

(" Indicates critical step)

Timoth

lb - JP2544RHRSW.DOC

Page

LR-JP-25044-00

Page 5 of 7

UNIT 2

READ TO THE OPERATOR

INITIAL CONDITIONS:

1.

Unit 2 is at 75% power and Torus Cooling is desired.

2.

RHR Service Water Pumps 2B and 2D have been removed from service.

3.

2E1 1 -F028A is tagged closed for corrective maintenance.

INITIATING CUES:

Crosstie the "A" loop of RHR Service Water to the "B" loop of RHR

Service Water.

_moth_

Kolb - JP25044RHRSW.DOC

Pa

LR-JP-25044-00

Page 6 of 7

start

time:

-

1. Operator identifies the procedure

Operator has identified the correct

needed to perform the task.

procedure as 34SO-El 1-010-2S

(Section 7.2.6).

NOTE: It will not be necessary to override the RHRSW pump LOCA signal in this

condition, but to do so will not prevent system operation.

2. Depress the RHR Service Water Lube

At panel 2H1 1-P601, operator has

Valves push-button on 2H1 -P601.

depressed the RHR SERVICE

WATER LUBE VALVES push

button.

PROMPT:

If the operator addresses waiting for one minute, inform the operator that

one-minute has elapsed.

PROMPT:

If the operator addresses obtaining Shift Supervisor's permission to crosstie

RHRSW loops, inform the operator that the Shift Supervisor has given

permission to crosstie RHRSW loops.

I 1<

At panel 2H l-P601, operator

opens SERV WTR CROSSTIE

VLV 2El 1-F119A, red light

illuminated.

RESPONSE CUE:

Valve 2E1 I-Fl 19A, green light illuminated, red light extinguished.

At panel2

-P601,operator

opens SERV WTR CROSSTIE

VLV 2E1 l-F119B, red light

illuminated.

RESPONSE CUE:

Valve 2El 1-F 19B, green light illuminated, red light extinguished.

5.

Operator places the Interlock Override

At panel 2H 11 -P601, the

valve 2E1 1-F068B Keylock Switch in

Operator places the Interlock

the Override position.

Override Valve 2E 1 -F068B

Keylock Switch in the Override

position.

RESPONSE CUE:

N/A

NOTE: Using the Override Switch for 2E1 I-FO68A is not required, but if

performed, should be noted. Overriding 2E1 l-FO68A will not affect the

(** Indicates critical step)

Timoth Koilb - JP25044RHRSW.DOG

Page..

LR-JP-25044-00

Page 7 of 7

~CIE'

performance of the JPM.

6. Set the Heat Exchanger B Differential

At panel 2H 11 -P601, the operator

Pressure Control Valve Controller,

sets HX B DIFF PRESS

2E1 1-R600B to 40% OPEN.

CONTROL VLV F068B

controller, 2E1 1-R600B to 40%

OPEN.

7. Confirm the following:

At panel 2111 l-P601, the operator

S2EI 1 -F068A(B) OPENS (RED light

CONFIRMS that 2E1 1-F0681

ILLUMINATES)

Opens red light illuminates, and

RHR HX A(B) DIFF PRESS

RHR HX A(B) DIFF PRESS LOW

LOW Annunciator illuminates.

annunciator ILLUMINATES

NOTE: RHRSW Pump A or C may

be interchanged.

be started first. Therefore Steps 8 and 12 may

RESPONSE CUE:

SERVICE WATER PUMP 1 A, green light illuminated, red light

extinguished.

PROMPT:

IF the operator asks the Shift Supervisor if another RHRSW pump should

be started at this time, INFORM the operator that another RHRSW pump is

required to be started at this time.

"I

(** Indicates critical step)

T

Kolb - JP25044RHRSW.DOC

P...

.

LR-JP-25044-00

Page 8 of 7

I

(** Indicates critical step)

10. Depress the RHR Service Water Lube

At panel 211I-P601, operator has

Valves push-button on 2H1 -P601.

depressed the RHR SERVICE

WATER LUBE VALVES push

button.

11.

Adjust Diff Press Control Vlv

At panel 2H1I 1-P601, operator has

2E 1 -F068B to obtain desired

adjusted HX B DIFF PRESS

RHRSW flow rate, then open

CONTROL VLV F068B

2E] 1-F0681 an additional 5%.

controller, 2El 1-R600B, to obtain

desired flow rate, and then an

additional 5% is added.

Flow rate limit, prior to adding

5%, is 4400 gpm (+0, -200 gpm).

Pressure limit for RHR Service

Water is less than 450 psi.

NOTE: Flow rate will be monitored on PUMP TEST FLOW indicator

2E 1 -R619A and/or SERV WATER FLOW indicator 2El 1-R602A.

Pump discharge pressure will be monitored on DIV I PRESSURE

indicator 2E1 l-R650A.

f**

NYAt

panel 2n1 l-P601 operator

starts SERVICE WATER PUMP

INS,

~2El11-C001C.

RESPONSE CUE:

N/A

AFTER the second RHRSW pump is started and Flow is increased to -7000 gpm enter,

MALFUNCTION mfEll 120C, RHRSW 2C Pump Trip, to trip the RHRSW pump.

13. Enter ARP 34AR-601-325-2S,

At panel 2H11 -P601, the operator

RHRSW PUMP 2C TRIP.

enters the ARP for RHRSW

PUMP 2C TRIP, NO actions

apply.

WmothvKolb- JP25044RHRSW.DOC

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LR-JP-25044-00

Page 9 of 7

wfEMR

PROMPT:

When the operator informs the SS of the Trip of 2C RHRSW pump, inform

the operator that you will contact Maintenance to investigate the pump Trip.

PROMPT:

When the operator addresses starting RHR, inform the operator that another

operator will start that system.

PROMPT:

If the operator addresses the in-service RHR Service Water strainer

differential pressure, inform the operator that another operator is monitoring

this differential pressure and it is below 6 psid.

-V

END

TIME:

NOTE:

The terminating cue shall be given to the operator when:

-

With no reasonable progress, the operator exceeds double th(

allotted time.

-

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

Southern Nuclear

E. I. Hatch Nuclear Plant

Operations Training

'TITLE:

TRANSFER AN EMERGENCY 4160 VAC BUS FROM THE EMERGENCY TO

THE NORMAL POWER SUPPLY

AUTHOR

...

..

TA SLJM BER .

.

..

.

E

R. A. BELCHER

LR-JP-27.11-14

22.0 Minutes

RECOMMENDED By

AYD

N/R

R. A. BELCHER

03/11/2002

SOUTHERN Uk

COMPANY

Energy to Serve Your World S.

SOUTHERN NUCLEAR OPERATING COMPANY

PLANT E. I. HATCH

Page 1 of 1

FORM TITLE: TRAINING MATERIAL REVISION SHEET

Program/Course Code:

OPERATIONS TRAINING

Media Number:

LR-JP-27.11

Rev

No

9[Dte

~tao

tRvso

Auth r'ýjSupv's

__________IIniftil

A

.

Initial

01

06/09/89

General revision and format change

WGW

02

08/24/89

Revise questions & add LR lesson plans

JEM

DHG

03

07/01/92

General revision and format change

WMM

DHG

04

09/23/93

General revision, word processor change

05

07/18/94

Correct for D/G loading, adjust format

SMC

06

02/23/95

Correct simulator setup and prompts to include

DHG

directions for the simulator operator to place speed

drop and voltage regulator to the correct positions,

adjust format, include phonetics in the initiating cue

07

08/17/95

Format change, incorporate student comment about

SMC

Unit 1 section

08

07/05/96

Format change

SMC

09

10/01/97

Revised based on comments from the 1997 annual

SCB

DHG

exam.

10

03/05/99

Revised to make steps for direction of synchscope

SCB

DHG

rotation, step 8 (UI) and Step 9 (U2) noncritical.

Revised for new simulator malfunction numbers.

11

02/11/00

Format modification, change time allowance based on

DHG

running average, update to new simulator operating

system

12

03/29/00 TLB comment; change step 10 of U2 for voltage

SMC

requirement of the diesel

13

11/02/00

Include objective number, TLB comment, correct Step

DHG

9 of Unit 1 section to agree with procedure change

_

14

03/11/02 Incorporate instructor comment on goal for power

decrease of Step 12 for Unit 2, include initial operator

statement

LR-JP-27.1 1-14

Page 1 of 1

UNIT 1 (X)

UNIT 2

(X)

TSK TITLE:

JPM NUMBER:

TASK, STANDAD:

TRANSFER AN EMERGENCY 4160 VAC BUS FROM

THE EMERGENCY TO THE NORMAL POWER

SUPPLY

LR-JP-27.11-14

The task shall be completed when the operator has transferred the

"F' 4160 VAC Emergency Bus power supply from the

associated Emergency Diesel to the "D" Startup Transformer, per

34SO-R43-001, with exception of placing the selected Diesel

Generator in Standby.

T

U027.011

OBJECTIVE' NUBR

027.011.0

PLANT HATCH JTA IMPORTANCE RATING:

3.07

SRO 3.07

K/A CATALOG NUMBER: 262001A404

K/A CATALOG JTA IMPORTANCE RATING:

3.60