ML023400211
| ML023400211 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/09/2003 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Sumner H Southern Nuclear Operating Co |
| References | |
| 50-321/02-301, 50-366/02-301, ES-301-1, ES-301-2 50-321/02-301, 50-366/02-301 | |
| Download: ML023400211 (206) | |
See also: IR 05000321/2002301
Text
Draft Submittal
(Pink Paper)
E. I. HATCH NUCLEAR PLANT
EXAM 2002-301
50-321 & 50-366
OCTOBER 16 - 18, 21 - 25, &
OCTOBER 30, 2002,
1. Administrative Questions/JPMs
2. In-plant JPMs
3. Control Room JPMs (simulator JPMs)
4. Administrative Topics Outline ES-301-1
5. Control Room Systems and Facility Walk-Through
Test Outline ES-301-2
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
SBLC OPERABLE (ADMIN)
IR. L.SMITH
LR-JP-25046-00 15 Minutes
I
10/07/02 1
T. F. PHILLIPS R. S. GRANTHAM
R. S. GRANTHAM
I T. F. PHILLIPS
4k
SOUTHERN Afl
COMPANY
Energy to Serve Your WorldsM
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-25046
00 10/07/02 Initial Development RLS RSG
___ ___ I I
I I
S I I I
II -i I
I I t --- t--
F
I I -II
I I i I
I I
I 1 1 I
I I I I
i. i i I
I I
_______ .1 I I
_ _ _ _ I I
I I1t
I It
_ __ _ _ I I S
______ I I *1 S
I I I
I. I i I
LR-JP-25046-00
Page 2 of 5
UNIT 1 (X) UNIT 2 (X)
S SBLC OPERABLE (ADMIN)
LR-JP-25046-00
The task is complete when the RO determines that SBLC is
inoperable and Tech Spec entry to 3.1.7 is required.
XXX.XXX
ýN IIIýMW,
F10,1" XXX.XXX.x
PLANT HATCH JTA IMPORTANCE RATING:
RO N/A
SRO N/A
K/A CATALOG NUMBER: G2.1.25
K/A CATALOG JTA IMPORTANCE RATING:
RO 2.8
SRO 3.1
OPERATOR APPLICABILITY: Reactor Operator (RO)
Unit 1 Tech Specs I Unit 2 Tech Specs d
APPROXIMATE COMPLETION TIME: 15 Minutes
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 5
AiVIVflYIEINt LR
Pa
7
START
TIME:
T I
Operator enters Unit 1 Tech Specs Operator enters unit 1 Tech Specs
section 3.1.7. section 3.1.7
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.
Se ai e Using Unit 1 Tech Specs figure
3.1.7-1 the operator determines
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 1 Tech Specs. that Sodium Pentaborate is inside
the permissable region A.
RESPONSE CUE: Plots the location in the nonpermnsslble region or A or b.
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. 4
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) of
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
& C
111111M
START
TIME:
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.
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
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations TrainingJPM
II
DETERMINING OVERTIME AVAILABILITY
R. L. SMITH LR-JP-25045-00 15.0 Minutes
T. F. PHILLIPS R. S. GRANTHAM 10/07/02
SOUTHERN
COMPANY
Energy to Serve Your World'
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: JP-25045
LR-JP-25045-00
Page 1 of 5
UNIT 1 (X) UNIT 2 (X)
DETERMINING OVERTIME AVAILABILITY
WINEEM
The task shall be complete when the operator has determined
which operators are available for overtime per
300.001
B 300.001.J
PLANT HATCH JTA IMPORTANCE RATING:
RO Not Available
SRO Not Available
K/A CATALOG NUMBER: Generic K/A 2.14
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.0
SRO 3.40
OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)
Nm?
1OAC-MGR-020-OS Rev 0
Unit 1 or 2 Tech Specs, Section 5.2.2.e
APPROXIMATE COMPLETION TIME: 15.0 Minutes
SIMULATOR SETUP: N/A
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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> holdover). A break of at
least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 5
Lrr tttrcŽttflaSfl
I? >i;77 i
START
TIME:
PROMPT: AT this time, GIVE the operator the attached operator work history.
RESPONSE CUE: N/A
PROMPT: IF asked, INFORM the applicant that operator 1 received authorization for
exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
period between days 4 & 5.
RESPONSE CUE: N/A
RESPONSE CUE: N/A
DETERMINES that Operator #3
WILL violate the overtime limits.
(>16 hours in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period
and >24 hours in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period
and would require overtime
authorization)
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25045-00
Page 4 of 5
TB> Nq'rp~,q mtWM0U0wmi , 1
lfi4~ O M M*
.DETERMINES that Operator #4
WILL NOT violate any overtime
limits.
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
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
DAY 1 2 3 4 5 6 7 8
(Today)
Operator
- 1 0 0 13 11 14 10 14 10
Operator
- 2 0 3 10 12 12 12 8 14
Operator
- 3 0 0 12 12 12 8 8 15
Operator
- 4 0 8 12 10 10 8 10 12
Operator
- 5 0 4 12 10 10 14 10 12
Page 5 of 5
4k
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training JPM
TITLE
PREPARE EQUIPMENT CLEARANCE AND HOLD TAGS
AUTHOR MEDIA NUMBER TIME
R. L. SMITH LR-JP-25019-03 20.0 MINUTES
RECOMMENDED BY APPROVED BY DATE
T. F. PHILLIPS R. S. GRANTHAM 10/07/02
4#
SOUTHERN fl
COMPANY
Energy to Serve Your WorldsM
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of 1
FORM TITLE:
TRAINING MATERIAL REVISION SHEET
Program/Course Code: LICENSE REQUAL Media Number: LR-JP-25019
Author's Supv's
Rev. No. Date Reason for Revision Initials Initials
01 10/1/92 General revision and format change WMM RSG
02 07/14/94 General revision, add 2 valves to required tag out, word RAB SMC
processor change
03 10/7/02 Format change removed Record of Completion sheet. RLS RSG
___ ___ I I I
I 1* I
J. I t I
I. Itt
I1 I .
I I j t
III I
I I
I I4 I I
_______ I I
I I
________ I I I
_______ I 1-
I. I *I
I. I t I
4 1 I t
I I. t
4 I t
4 I
I I I I
I 4 I
I 4 1 I
LR-JP-25019-03
Page 1 of 4
FACILITY: PLANT E. I. HATCH UNIT 1( ) UNIT 2 (X)
PREPARE EQUIPMENT CLEARANCE AND HOLD
ETAGS
BLR-JP-25019-03
S rASK The task shall be completed when the operator has generated a
clearance for CRD Suction Filter 2A per 30AC-OPS-001-OS.
_300.016
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.20
SRO 2.74
K/A CATALOG NUMBER: 294001A107
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.00
SRO 3.70
OPERATOR APPLICABILITY: Reactor Operator (RO)
I
CNC Procedure: 30AC-OPS-001-OS Rev 23.1
Plant Drawing H-26007
APPROXIMATE COMPLETION TIME: 20.0 Minutes
SIMULATOR SETUP: N/A
Page 2 of 4
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The CRD pump, 2C 11-COO 1A, 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 1 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.
LR-JP-25019-03
Page 3 of 4
afA
START
TIME:
NOTE: Steps of this JPM may be completed in any order.
1. 1 Operator identifies the Operator has identified the correct
procedure needed to perform procedure as 30AC-OPS-001-OS.
the task.
2.1 Operator reviews the Operator has reviewed the
procedure's precautions and precautions and limitations.
limitations.
3. Operator identifies the Operator has identified the
materials which are required. required materials and where to
obtain them.
Plant Drawing 1H26007
34SO-Cl 1-005-2S, 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.
The operator has determined the
following must be tagged:
2C1 1-Fl 14A
2C 11 -F 144A
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25019-03
Page 4 of 4
oNR CM~
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)
4k
w
Southern Nuclear Affm:ak
E. I. Hatch Nuclear Plant
Operations Training JPM
TITLE
PREPARE EQUIPMENT CLEARANCE AND HOLD TAGS
AUTHOR MEDIA NUMBER TIME
R. L. SMITH LR-JP-25019-03 20.0 MINUTES
RECOMMENDED BY APPROVED BY DATE
T. F. PHILLIPS R. S. GRANTHAM 10/07/02
SOUTHERN Sa
COMPANY 9M
Energy to Serve Your World
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of 1
FORM TITLE:
TRAINING MATERIAL REVISION SHEET
Program/Course Code: LICENSE REQUAL Media Number: LR-JP-25019
Author's Supv's
Rev. No. Date Reason for Revision Initials Initials
01 10/1/92 General revision and format change WMM RSG
02 07/14/94 General revision, add 2 valves to required tag out, word RAB SMC
processor change
03 10/7/02 Format change removed Record of Completion sheet. RLS RSG
___ I __ I I I
_______ I
_ I__ I t i
_ __ I- _ I__ t i
J. I t I
I. I 1
I I. 1
II
I I
I I
.1 I I I
I I 1 I
II t I
______ I I 1
______ I I t t
______ .1 J *1
______ I I I I
_ I__ I I I
- I I i I
LR-JP-25019-03
Page 1 of 4
FACILITY: PLANT E. I. HATCH UNIT 1 ( ) UNIT 2 (X)
PREPARE EQUIPMENT CLEARANCE AND HOLD
TAGS
P LR-JP-25019-03
The task shall be completed when the operator has generated a
I -- I TEy1" M clearance for CRD Suction Filter 2A per 30AC-OPS-001-OS.
f300.016
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.20
SRO 2.74
K/A CATALOG NUMBER: 294001A107
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.00
SRO 3.70
OPERATOR APPLICABILITY: Reactor Operator (RO)
Eiiý , I Procedure: 30AC-OPS-001-OS Rev23.1
F "ýNPlant Drawin H-26007 II
APPROXIMATE COMPLETION TIME: 20.0 Minutes
SIMULATOR SETUP: N/A
Page 2 of 4
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The CRD pump, 2C1 1-CO01A, 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 1 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.
LR-JP-25019-03
Page 3 of 4
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 30AC-OPS-001-OS.
the task.
2. Operator reviews the Operator has reviewed the
procedure's precautions and precautions and limitations.
limitations.
3. Operator identifies the Operator has identified the
materials which are required. required materials and where to
obtain them.
Plant Drawing H26007
34SO-Cl 1-005-2S, 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.
The operator has determined the
following must be tagged:
2C 11-F144A
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25019-03
Page 4 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 k
COMPANY
Energy to Serve Your World'
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-25305
00 05/02/94 Initial development RAB DHG
01 09/06/96 Format change, convert to use SPDS information RAB DHG
02 09/12/96 Editorial, correct MIDAS result numbers for peak RAB RSG
TEDE and site boundaries
03 10/03/97 Revised based on comments from the 1997 annual SCB DHG
exam.
04 09/16/98 Revised due to a procedure/MIDAS program revision. SCB DHG
05 01/21/99 Revised per feedback from EP. SCB DHG
06 03/21/00 Format modification, change time allowance based on RAB DHG
running average, change MIDAS for due to revision
07 11/06/00 Include objective number RAB DHG
08 03/14/02 Include initial operator statement RAB RAB
09 10/07/02 Added prompts for SRO candidates to determine RLS RSG
EAL.
LR-JP-25305-09
Page I of 12
UNIT 1 (X) UNIT 2 (X)
W" IIIral JUVE = DURING AN EMERGENCY, PERFORM A PROMPT
OFFSITE DOSE ASSESSMENT CALCULATION
V "LR-JP-25305-09
The task shall be complete when the Total Offsite Dose Rate has
been calculated per 73EP-EIP-01l8-OS and the SOS/ED has been
informed of the correct radiological assessment, and for an SRO
candidate determine EAL.
[200.060, 200.052
A 200.060.0, 200.052A
PLANT HATCH JTA IMPORTANCE RATING:
RO 4.57, 4.67
SRO 3.92, 4.04
K/A CATALOG NUMBER: 295038EA203, G2.2.41
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.50, 2.30
SRO 4.30, 4.10
OPERATOR APPLICABILITY: Reactor Operator (RO)
34AB-D11-001-2S Rev 1 Ed 2
73EP-EIP-001-OS Rev 14.1
73EP-EIP-018-OS Rev6
HORN iE i ... .
73EP-EIP-018-OS (current revision)
73EP-EIP-001-OS (current revision)
Computer with the MIDAS program
APPROXIMATE COMPLETION TIME: 30.0 Minutes
SIMULATOR SETUP: N/A
UNIT 1 & 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. A pipe break has occurred causing a Primary System discharge outside
2. RX BLDG RADIATION HIGH is alarming on Unit 2.
3. 34AB-D1 1-001-2S, "Radioactivity Release Control," is in progress.
4. SPDS is available for use.
5. The SOS is acting in the Emergency Director's position.
INITIATING CUES:
DETERMINE Total Offsite Dose Rate per 73EP-EIP-018-OS, NOTIFY
the SOS/ED if a release is progress, and NOTIFY the SOS/ED if
emergency classification should be addressed.
LR-JP-25305-09
Page 3 of 12
N ý - .. r
START
TIME:
1. Operator locates the correct Operator has LOCATED
procedure. 73EP-EIP-018-OS at the Shift
Supervisor's desk (may use the
copy from SOS's office).
2. Operator reviews procedure's Operator has REVIEWED the
Precautions and Limitations. Precautions and Limitations
section of the procedure.
PROMPT: IF addressed by the operator, INDICATE that the following annunciators
are NOT ILLUMINATED.
MAIN STACK EFFLUENT ANY COLLECTOR RADN LEVEL MAXIMUM
MAIN STACK EFFLUENT ALL COLLECTORS RADN LEVEL MAXIMUM
RB VENT EFFL ANY COLLECTOR RADN LEVEL MAX
RB VENT EFFL ALL COLLECTORS RADN LEVEL MAX
RB VENT EFFL ANY COLLECTOR RADN LEVEL MAX
RB VENT EFFL ALL COLLECTORS RADN LEVEL MAX
(** Indicates critical step)
LR-JP-25305-09
Page 4 of 12
PROMPT: IF addressed by the operator, INDICATE the status of the following
Panel Number Annunciator Title Alarm Status
IH1 1-P601-4 OFFGAS VENT RADIATION HIGH-HIGH Not Illuminated
1HI1-P601-4 OFFGAS VENT RADIATION HIGH Not Illuminated
1H1I-P601-4 OFFGAS VENT RADIATION DNSC/INOP Not Illuminated
lH11-P601-4 OFFGAS VENT SAMPLE FLOW HIGH/LOW Not Illuminated
IH11-P601-4 RX BLDG VENT SAMPLE FLOW HIGH/LOW Not Illuminated
IH 11-P601-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not Illuminated
IHI1-P603-2 RX BLDG STACK RADN MON HIGH-HIGH Not Illuminated
iH 11-P603-2 RX BLDG STACK RADN MON HIGH Not Illuminated
2H11-P601-2 RX BLDG VENT EXHAUST RADIATION HI-HI Not Illuminated
2H11-P601-2 RX BLDG VENT EXHAUST RADIATION HIGH Illuminated
(223)
2H11-P601-4 RX BLDG VT MON HIGH/LOW DOWYNSCALE/INOP Illuminated
(433)
2H! 1-P601-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not Illuminated
PROMPT: IF addressed by the operator, as the Shift Supervisor, INFORM the
operator that SPDS is available.
NOTE: The operator may collect the required data from SPDS prior to starting the
computer. Therefore, Step 5 may be completed prior to Step 3.
NOTE: The computer that may be used is at the STA's desk. The computer
requires a Startup disk from the Emergency Director's notebook. If the
Startup disk is not used, the following critical step cannot be completed.
RESPONSE CUE: N/A
4. Operator enters the correct date and When prompted by the computer,
time. the operator ENTERS the correct
date and time, OR, if the date and
time are correct, PRESSES
"ENTER".
(** Indicates critical step)
LR-JP-25305-09
Page 5 of 12
P1i?-Sp 1I
I
PROMPT: WHEN the operator addresses SPDS, the MIDAS Information screen,
DISPLAY to the operator the MIDAS Information attachment.
PROMPT: WHEN the operator addresses the individual flow recorders, as each
recorder is identified, DISPLAY to the operator the correct recorder
attachment.
5. Operator records the required Using the MIDAS Data Input
information for the Dose Assessment. Acquisition Form, the operator
GATHERS/RECORDS the
appropriate information to
perform the calculation.
RESPONSE CUE: N/A
RESPONSE CUE: N/A
PROMPT: IF asked, INFORM the operator to assume a duration of 240 minutes.
NOTE: Durations other than 240 minutes will vary the resulting projected doses
and potentially affect PARs.
RESPONSE CUE: N/A
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25305-09
Page 6 of 12
PROMPT: WHEN the operator addresses informing the SOS/ED, ACKNOWLEDGE
the operator's report and INFORM the operator as the SOS/ED that you
understand a release is in progress.
RESPONSE CUE: N/A
NOTE: Peak TEDE should calculate as 7.2E - 02 mR/hr.
To successfully complete Step 9, the calculated values must agree with the
values on the attached ENN Form.
PROMPT: WHEN the operator addresses informing the SOS/ED, ACKNOWLEDGE
the operator's report and INFORM the operator as the SOS/ED that you
will declare the Emergency. (IF the operator is an SRO CANDIDATE,
INFORM the operator to determine the emergency classification.)
NOTE:THE NEXT STEP IS N/A FOR RO CANDIDATES.
RESPONSE CUE: N/A
11. Operator gives the working copy of When the printing process is
the ENN Form to the SOS/ED. complete, the operator removes
the ENN Form and addresses
giving the form to the SOS/ED.
PROMPT: WHEN addressed by the operator, as the SOS/ED, RECEIVE the printed
ENN Form.
(** Indicates critical step)
LR-JP-25305-09
Page 7 of 12
PROMPT: WHEN addressed by the operator, as the SOS, INFORM the operator that
another operator will perform additional dose projections.
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)
MAIN STACK FLOW
INST BUS 1A
o 5 10 15 20 25
X10001 1 11 1 25
0 5 10 15 20 25
XIOl00
MAIN STACK FLOW
RED-(CHANNEL B) 0-25 CFM X 1000
BLK-(CHANNEL A) 0-25 CFM X 1000
ID11-R625 6050K60-858
Page 8 of 12
STACK VENT FLOW
INST BUS ]A
I AIL 3A4 5'x lO5CFM
0-
r I 3I i 4I 5x 1OCFM
1
RX BLDG VENT FLOW
RED-(CHANNEL B) 0-5 X1O0 5SCFM
BLK-(CHANNEL A) 0-5 X 10 5SCFM
1T41-R621 CTA6445200
Page 9 of 12
STACK VENT FLOW
2T41 -R621
INST BUS 2B
0 50 10 150 250 300 360 400 X 1000CFM
H11111 IIH IIII II II
0 50 100 150 250 300 350 4010 X 1000 CFM
RB STACK MONITOR
RED-RB STACK FLOW (CH-B) 0-400,000 SCFM
BLK-RB STACK FLOW (CH-A) 0-400,000 SCFM
2T41 -R621 CTA6445100
Page 10 of 12
MIDAS INFORMATION
METEOROLOGICAL
1OM WIND SPD 1OOM WIND SPD 1OM WIND DIR 1 OM WIND DIR
1Y33-R601 1Y33-R603 1Y33-R601 1Y33-R603
3.0 5.0 160 165
AMBIENT TEMP DELTA T DELTA T RAINFALL
(F) 1DM 60-10 100-10 15 MIN. AVG
54 1.1 2.4 .000
RADIOLOGICAL
MAIN STACK U] RX. BLDG. VENT U2 RX. BLDG. VENT
NORMAL RANGE KAMAN NORMAL RANGE KAMAN NORMAL RANGE KAMAN
IDi I-K600A 1Dl I-R631 1D11 -K619A Di 1D-R631 2D1 1-K636A 2D11-R631
1.40E 03 4.OOE 01 4.OOE 01
1D 11-K600B 1D11-K619B 2D1 1-K636B
1.39E 03 3.90E 01 4.OOE 01
fJQ
0
C
STABILITY CLASS
E
EMERGENCY NOTIFICATION
MESSAGE NUMBER _______
1. THIS IS: [ ] A DRILL [ ]ACTUAL EMERGENCY [ ] INITIAL [ I FOLLOW-UP I
2. SITE: PLANT HATCH UNIT: REPORTED BY:
3. TRANSMITTAL TIME/DATE: (Eastern) mm / dd / yy CONFIRMATION PHONE NO: 1-912-367-7781 ext.
4. AUTHENTICATION (If Required): N/A N/A
(Number) (Codeword)
5. EMERGENCY CLASSIFICATION:
[A] NOTIFICATION OF UNUSUAL EVENT [B] ALERT
[C] SITE AREA EMERGENCY [D] GENERAL EMERGENCY
6. [A] Emergency Declaration At: [B] Termination At: TIME/DATE:
(If B, go to Item 16) (Eastern) mm dd yy
7. EMERGENCY DESCRIPTION/REMARKS:
8. PLANT CONDITION: [A] IMPROVING [B] STABLE [C] DEGRADING
9. REACTOR STATUS: [A] SHUTDOWN TIME/DATE: _(Eastern) _/_ / [B] _%POWER
mm dd yy
10. EMERGENCY RELEASE(S):
[A] NONE (Go to Item 14.) [B] POTENTIAL (Go to Item 14.)
[C] IS OCCURRING [D] HAS OCCURRED
- 11. TYPE OF RELEASE: [ I ELEVATED [ ] GROUND LEVEL
[A] AIRBORNE: Started: / / Stopped: / I__
Time/Date (Eastern) mm dd yy Time/Date (Eastern) mm dd yy
[B] LIQUID: Started: I / Stopped: / /
Time/Date (Eastern) mm dd yy Time/Date (Eastern) mm dd yy
- 12. RELEASE MAGNITUDE: [X ] CURIES PER SEC. I CURIES
NORMAL OPERATING LIMITS: BELOW []ABOVE
[A] NOBLE GASES 3.1E-02 [B] IODINES 3.8E-04
[C] PARTICULATES 0.OE+00 [D] OTHER
"*13.ESTIMATE OF PROJECTED OFFSITE DOSE:
[ I NEW [] UNCHANGED PROJECTION TIME:
(Eastern)
(mrem) (mrem) ESTIMATED DURATION: HRS
SITE BOUNDARY 2.9E-01 2.OE-01
2 MILES 2.8E-01 7.3E-01
5 MILES 1.8E-01 1.IE+00
10 MILES 5.8E-02 4.4E-01
14. METEOROLOGICAL DATA:
[A] WIND DIRECTION(from) 165 [B] SPEED (mph) 5.0
[C] STABILITY CLASS E [D] PRECIPITATION (type) NO RAIN
15. RECOMMENDED PROTECTIVE ACTIONS:
[A] NO RECOMMENDED PROTECTIVE ACTIONS
[B] EVACUATE
[C] SHELTER-IN-PLACE
[D] OTHER
16. APPROVED BY: Emergency Director TIME/DATE: / /
(Name) (Title) (Eastern) mm dd yy
Information may not be available on initial notifications.
TRN-0001 Rev. 10 G16.70 73EP-EIP-073-OS
Page 12 of 12
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
I ý; 41ý
DETERMINE STAY TIMES TO TAKE A PIECE OF EQUIPMENT OOS
11MEN " Effiffimmammam-, Ammmlmmmml
R. L. SMITH LR-JP-25049-00 20 Minutes
flORM&I x1mNNW ýc - 11I - N."Offi6i
ft
T. F. PHILLIPS R. S. GRANTHAM 10/07/02
SOUTHERN 3kO
COMPANY
Energy to Serve Your Worlds"
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-25049
LR-JP-25049-00
Page 2 of 6
UNIT 1 0 UNIT 2 (X)
DETERMINE STAY TIMES TO TAKE A PIECE OF
EQUIPMENT OOS
LR-JP-25049-00
This task will be completed when stay times are determined by
the operator, based on current accumulated dose for the year and
dose that would be received while in a radiation field.
PLANT HATCH JTA IMPORTANCE RATING:
RO N/A
SRO N/A
K/A CATALOG NUMBER: G2.3.2
K/A CATALOG JTA IMPORTANCE RATING:
RO 2.5
SRO 2.9
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.
Part 1
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The 4 th 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
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.
LR-JP-25049-00
Page 4 of 6
Timp Fllowi*IEN
I
START
TIME:
PROMPT: AT this time give the operator the copy survey map of the Unit 1 Condenser
Bay.
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
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
Part 2
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The 4 th 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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.
LR-JP-25049-00
Page 6 of 6
ISTE
I~~~!
WAT/UpIS-ligjwth*I ii (~MM1N
START
TIME:
PROMPT: AT this time give the operator the copy of the survey map of the Unit 2
Condenser Bay 164' el.
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.
RESPONSE CUE: N/A
RESPONSE CUE: N/A
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25049-00
Page 7 of 6
TER I i~r>cdMA
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
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
REVIEW OF SCRAM DISCHARGE VOLUME ISOLATION VALVE TIMING &
CLOSURE TEST
T. F. PHILLIPS R. S. GRANTHAM 10/07/02
44
SOUTHERN 3.
COMPANY
Energy to Serve Your World' M
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
0 10/07/02} Initial development. RLS RSG
I
___ I __ I ___ ___
4 1. I
4 I I
1 I* i I
4I 1
I 4 t 1
I I i I
I I iI
II I T
i i I I
II IT
I I i t
_______ I t
_________ I I I
_______ I J I I
I I I I
_ I__ 4-
I-
__ _ _ I I.
_______ .1 4- 1
LR-JP-25048-00
Page 2 of 6
UNIT 1 0 UNIT 2 (X)
REVIEW OF SCRAM DISCHARGE VOLUME
ISOLATION VALVE TIMING & CLOSURE TEST
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.
MXXX.XXX
3DXXX.XXX.X
PLANT HATCH JTA IMPORTANCE RATING:
RO X.XX
SRO X.XX
K/A CATALOG NUMBER: G2.1.33
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.4
SRO 4.0
OPERATOR APPLICABILITY: Reactor Operator (RO)
34SV-C 11-002-2 Rev 4.2
APPROXIMATE COMPLETION TIME: 20 Minutes
SIMULATOR SETUP: 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-C 11-002-2S, "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 6
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
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 l-002-2S, the operator
EVALUATES the closing stroke
2C11-F01OA SDV Vent Vlv
time data for:
2C11 -F035A SDV Vent Vlv 2C11-FOlOA SDV Vent Vlv
2C11-F01OB SDV Vent Vlv 2C1 1-F035A SDV Vent Vlv
2C11 -F035B SDV Vent Vlv
2C1 1-F010B SDV Vent Vlv
2C1 1-FO 1 SDV Drain Vlv
2C1 1-F035B SDV Vent Vlv
2C1 1-F037 SDV Drain Vlv 2C01 -FO11 SDV Drain Vlv
Per step 7.2.7 and 7.2.8 of
34SV-Cl 1-002-2S, the operator
DETERMINES the closing stroke
time data for:
2C1 1-F035A SDV Vent Vlv
2C1 l-FO11 SDV Drain Vlv
2C11 -F037 SDV Drain Vlv
Have exceeded their closing time
limit per steps 7.2.7 and 7.2.8,
and they are
UNSATISFACTORY.
RESPONSE CUE: N/A
PROMPT: 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.
(** Indicates critical step)
LR-JP-25048-00
Page 5 of 6
IRMN FM
4. The operator evaluates the closing Per steps 7.2.20 and 7.2.22 of
time difference data for: 34SV-C1 1-002-2S, the operator
EVALUATES the closing time
2C1 1-F010A SDV Vent Vlv
difference data for:
2C1 1-F035A SDV Vent Vlv
2C1 1-F01OA SDV Vent Vlv
2C1 1-F010B SDV Vent Vlv
2C1 1-F035A SDV Vent Vlv
2C1 1-F035B SDV Vent Vlv
2C 11 -FO1OB SDV Vent Vlv
2C1 1-F011 SDV Drain Vlv
2C11-F035B SDV Vent Vlv
2C1 1-F037 SDV Drain Vlv
2C1 1-F011 SDV Drain Vlv
2CI 1-F037 SDV Drain Vlv
and DETERMINES it to be
SATISFACTORY.
5. The operator evaluates the opening Per steps 7.2.23 and 7.2.25 of
time difference data for: 34SV-Cl 1-002-2S, the operator
EVALUATES the opening time
2C1 l-FO1OA SDV Vent Vlv
difference data for:
2C1 l-F035A SDV Vent Vlv
2C1 1-F010A SDV Vent Vlv
2C11-F01OB SDV Vent Vlv
2C1 1-F035A SDV Vent Vlv
2C11 -F035B SDV Vent Vlv
2C1 1-F010B SDV Vent Vlv
2C011-F035B SDV Vent Vlv
2C011-F037 SDV Drain Vlv
2C1 l-FOI 1 SDV Drain Vlv
and DETERMINES it to be
SATISFACTORY.
condition A and B, the operator
DETERMINES, that 3.1.8A
applies to 2C11 -F035A, 2C1
FO11, & 2C 11-F037 valves, and
3.1.8.B applies to 2C1 1-F0 11 and
2C1 1-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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25048-00
Page 6 of 6
NOTE: The operator may note that the Drain line valves (2C1 1-F011 and 2C 11
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)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
IRM ALTERNATE POWER CHECKS PRIOR TO TAKING THE MODE
SWITCH TO RUN (ADMIN)
LR-JP-25047-00 15 Minutes
R. L. SMITH I
T. F. PHILLIPS R. S. GRANTHAM 10/07/02
k
SOUTHERN fl.
COMPANY
Energy to Serve Your World'M
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-25047
00 10/07/02 Initial Development. RLS RSG
I I i t
I I I
I I i i
4. I I I
I. I I
I. Ii I
I I. I I
I I
I I i I
I IiI
_______ _______ I t t
_______ _______ I t
_______ I t
_________ ________ I t I
II I
1. 1. I I
I. I*t
_______ .1 4. I I
__ _ _ I I1t1
1 4 t 1
LR-JP-25047-00
Page 2 of 12
UNIT 1 (X) UNIT 2 (X)
-IRM
-The
TAKING THE MODE SWITCH TO RUN (ADMIN)
ALTERNATE POWER CHECKS PRIOR TO
- LR-JP-25047-00
task is complete when the IRM alternate power checks are
perftrmed 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.
WES xxx.xxx.x
PLANT HATCH JTA IMPORTANCE RATING:
RO X.XX
SRO X.XX
K/A CATALOG NUMBER: G2.1.23
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.0
SRO 4.0
OPERATOR APPLICABILITY: Reactor Operator (RO)
34GO-OPS-001-1 34UU1-UFNS-UU1-2 iev .I3.
34GO-OPS-001-1 34U0-ULI-'-UU 1-2
(Attachment 10) (Attachment 10)
APPROXIMATE COMPLETION TIME: 15 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
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.
LR-JP-25047-00
Page 4 of 12
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
PROMPT: AT this time give the operator the attached copy of UNIT 1
ATTACHMENT 10.
2 The operator identifies where he will At 1H11 -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.
The operator uses the recorded
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.
ARs raigs are NO geater
[than the Avrge IRM pwer.
Uing
% is less thethe
than Averag~e
APR %power,
readings. the
RESPONSE CUE: The average IR
PROMPT: IF the operator is trying to determine current APRM power levels,
INFORM the operator that was part of the initial conditions.
(** Indicates critical step)
LR-JP-25047-00
Page 5 ofl12
4imil MY , Mm
evaluation of power level
indication.
RESPONSE CUE: The operator does not request an STA evaluation of power level
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)
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 12
i N j
g,' CoiuK
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
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.
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.
Using the Average % power, the
operator DETERMINES that
APRMs readings are NOT greater
than the Average IRM power.
RESPONSE CUE: The average IRM % is less than the APRM readings.
PROMPT: IF the operator is trying to determine current APRM power levels,
INFORM the operator that was part of the initial conditions.
(** Indicates critical step)
LR-JP-25047-00
Page 8 of 12
Aqr'. W
z "'
RESPONSE CUE: The operator does not request an STA evaluation of power level
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 ]PAGE 9 OF 13
PLANT E.I. HATCHI
DOCUMENT TITLE: DOCUMENT REV/VER NO:
PLANT STARTUP[ NUMBER: 29.2
ATTACHMENT 10 ATTACHMENT
PAGE:
TITLE: IRM ALTERNATE POWER CHECK -56 OF 1
CONTINUOUS
1.0 Record the IRM readings below AND estimate reactor power using 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__ READING__ % POWER
IRM C RANGE__ READING__ % POWER__
IRM E RANGE__ READING__ % POWER
IRM G RANGE__ READING__ % POWER__
IRM B RANGE__ READING__ % POWER__
IRM D RANGE__ READING__ % POWER
IRM F RANGE__ READING__ % POWER__
IRM H RANGE__ READING__ % POWER__
AVERAGE % POWER =
Confirm that each APRM reading is greater than the average * IRM Reactor
Power Value.
Calculations Verified
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.
fl'P-1I19R Rev NI/A G16.30
MGR-0009 Rev 4
OUTHERN
PLANT NUCLEARAGE
E.I. HATCH PAE0O1 O 3
DOCUMENT TITLE: DOCUMENT NUMBER: REV/VER
PLANTSTARTUP 34GO-OPS-00 1-2 NO:
35.2
ATTACHMENT 10 ATTACHMENT
PAGE:
TITLE: IRM ALTERNATE POWER CHECK -48 OF 1
I 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)
IRMA RANGE READING % POWER
IRM C RANGE READING % POWER
RANGE READING % POWER
IRM E
IRM G RANGE READING % POWER
RANGE READING % POWER
IRM B
RANGE READING % POWER
IRM D
IRM F RANGE READING % POWER
RANGE READING % POWER
IRM H
AVERAGE % POWER =
Confirm that each APRM reading is greater than the average *
IRM Reactor Power Value.
Calculations Verified
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.
np*.1 107 '7 Rev N/A G16.30
MGR-0009 Rev 4
IRM DATA
IRMS IRANGE READING
A 9 18
C 9 20
E 9 20
G 10 20
B 9 22
D 9 18
F 10 22
H 9 24
Page 11 of 12
- DO NOT GIVE THIS TO THE CANIDATE****
ANSWER
IRMS RANGE READING %POWER
A 9 18 6.35
C 9 20 7.06
E 9 20 7.06
G 10 20 7.06
B 9 22 7.77
D 9 18 6.35
F 10 22 7.77
H 9 24 8.47
Total = 57.9 +/-.4
57.9/8 = 7.24 +/-.1%
Average % power = 7.24% +/-. 1%
Page 12 of 12
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training JPM
SRO ONLY
AC~~EVALUATE THE NEED FOR/RECOMMEND OFFSITE PROTECTIVE
R. L. SMITH LR-JP-25205-06 16.0 Minutes
SOUTHERN La
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-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 DHG
05 03/25/02 Include initial operator statement RAB RAB
06 10/07/02 JPM modified. RLS RSG
___ I
__ I __ I
LR-JP-25205-06
Page 1 of 7
UNIT 1 (X) UNIT 2 (X)
EVALUATE THE NEED FOR/RECOMMEND
OFFSITE PROTECTIVE ACTIONS
LR-JP-25205-06
The task shall be completed when the Protective Action
Recommendation has been made per 73EP-EIP-054-OS.
200.105 (EP 001.088)
OB 1 200.105.A
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.00
SRO 3.00
K/A CATALOG NUMBER: 295038EA201
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.30
SRO 4.30
OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)
APPROXIMATE COMPLETION TIME: 16.0 Minutes
SIMULATOR SETUP: N/A
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
LR-JP-25205-06
Page 3 of 7
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 panel 1H 11 -P690, the operator
has DETERMINED wind
direction to be from 2250, using
one of the following recorders:
1Y33-R601 (10 meter)
1Y33-R602 (60 meter)
1Y33-R603 (100 meter)
At panel 1H11 -P689, the operator
has determined wind direction to
be from 2250, using recorder
1Y33-R604 (23 meter).
At Unit 1 or 2 SPDS MIDAS or
MET screens the operator
determines wind direction to be
2250.
RESPONSE CUE: N/A
NOTE: Accept the wind direction as 216 to 2500.
IF- - -
The operator has RECORDED
wind direction (Wind From) on
I
Step 1 of Attachment 3.
(** Indicates critical step)
LR-JP-25205-06
Page 4 of 7
NC A1NDA
US P.4I
The operator has DETERMINED
the affected zones to be:
A
E-5
J-10
K-10
RESPONSE CUE: N/A
6. Record the affected zones on The operator has RECORDED
Attachment 3. the affected zones on Step 2 of
Attachment 3.
7. Compare plant conditions with The operator has DETERMINED
Attachment 1 of procedure. a 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
Area Emergency per Attachment 1. there are NO PARs for Site Area
Emergency per Attachment 1.
9. Record the plant condition PARs on The operator has RECORDED
Attachment 3. "N/A" or "NONE" for plant
condition PARs on Step 3 of
Attachment 3.
10. Determine if Off-site dose has been The operator has DETERMINED
measured or projected. that 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 1
ANSWERS YES to the flowchart
step.
(** Indicates critical step)
LR-JP-25205-06
Page 5 of 7
VE gggg NOM111WA
12. Determine if the dose is greater than 1 EVALUATING the 10 AND 5
REM TEDE or greater than 5 REM MILE TEDE and THYROID
CDE Thyroid at 5 - 10 miles. CDE Values the operator:
DETERMINES the dose to the
population is less than 1 REM
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
REM TEDE or greater than 5 REM MILE TEDE and THYROID
CDE Thyroid at 2 - 5 miles. CDE Values the operator:
DETERMINES the dose to the
population is less than I REM
Thyroid at 2 - 5 miles.
ANSWERS NO to the flowchart
step.
The operator has DETERMINED
PARs for dose projections per
Attachment 2 are:
EVACUATE Zone A
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.
The operator has DETERMINED
the PARs from dose projections
are most conservative.
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25205-06
Page 6 of 7
W it A SAT/AUN
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.
17. Record the zones from the most The operator has RECORDED
conservative PAR to the Approval the 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
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
"*13.ESTIMATE OF PROJECTED OFFSITE DOSE:
NEW [ ] UNCHANGED PROJECTION TIME:
(Eastern)
(mrem) (mrem) ESTIMATED DURATION:
SITE BOUNDARY 1.4E+03 6.9E+03
2 MILES 7.4E+02 3.0E+03
5 MILES 2.3E+02 6.9E+02
10 MILES 5.5E+01 1.7E+02
Page 7 of 7
AI.1 (ROISRO)
TASK CONDITIONS:
A startup is planned for the following shift. One Reactor Operator must be held over two hours
for startup. The following is the work history (excluding shift turnover time) of the available
reactor operators on shift (hours reflect those worked PRIOR to the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> holdover). A break
of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> occurred between all work periods.
DAY 1 2 3 4 5 6 7 8
1 1 1 _(Today)
Operator
- 1 0 0 13 11 14 10 14 10
Operator
- 2 0 3 10 12 12 12 8 14
Operator
- 3 0 0 12 12 12 8 8 15
Operator
- 4 0 8 12 10 10 8 10 12
Operator
- 5 0 4 12 10 10 14 10 12
Evaluate the work history for all 5 operators. Determine which operator(s), if any, can be held
over for two hours without prior overtime approval, and determine which operators CANNOT be
held over for two hours without prior overtime approval. If CANNOT be held over then
indicate which guidelines would be violated.
Task Standard:
GEN 2.1.3 (3.0/3.4) Knowledge of shift turnover practices CFR 41.10 RO and SRO
Step Description Standard = SAT/UNSAT
1 Obtain a current Current Revision of 10-AC-MGR
revision of 10-AC- 020-OS.
MGR-020-0S.
2 Evaluate Operator 1 Determine Operator #1 would Critical
exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period
and and would exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a
7 day period and would require
overtime authorization.
PROMPT:
If asked, inform applicant that operator I received authorization for exceeding 24
hours in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period between days 5 and 6.
Evaluate Operator 1 Determine Operator exceeded 24
hours in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period between
days 5 and 6.
4 Evaluate Operator 2 Determine Operator #2 would Critical
exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period
and would require overtime
authorization.
5 Evaluate Operator 3 Determine Operator #3 would Critical
exceed 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period
and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period and
would require overtime authorization.
6 Evaluate Operator 4 exceed that
Determine
not Operator #4 would
any overtime guidelines.
7 Evaluate Operator 5 Determine Operator #2 would Critical
exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period
and would require overtime
authorization.
SOUTHERN NUCLEAR DOCUMENT TYPE: PAGE
PLANT E. I. HATCH SURVEILLANCE PROCEDURE I OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-C11-002-2S NO:
TIMING & CLOSURE TEST 4.2
EXPIRATION APPROVALS: C.R. Dedrickson DATE 10-07-99 EFFECTIVE
DATE: DEPARTMENT MGR DATE:
N/A NPGM/POAGM/PSAGM N/A DATE N/A 09/27/01
This JPM should be written so that the SRO can review the results after the operator has performed all
of his steps. The operator incorrectly signed off steps 7.2.7, 7.2.8 and 7.2.26. This caused the operator
to skip section 7.3. The operator also incorrectly signed step 7.5.3 as Satisfactory. I want the SRO to
figure out which valves are INOPERABLE and the Tech Spec actions that apply. I believe with the
times that I have filled in that valves 2C11 -F035A, 2C11-F037 and 2C1 1-F01I are INOPERABLE and
the Tech Specs that should be entered are:
1) 3.1.8 Condition A for valve 2C1 1-F035A since a Separate Condition entry is allowed for each
SDV vent and drain line.
2) 3.1.8 Condition A for valves 2C1 I-F037 and 2C1 1-F7011 since a Separate Condition entry is allowed
for each SDV vent and drain line.
3) 3.1.8 Condition B for valves 2C11-F037 and 2C1 -F011.
The SRO should also understand that the drain line may be unisolated periodically to drain the line as
long as an operation is specifically dedicated to close the valves if the need arises.
MGR-0002 Rev 8
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 1 2 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-Cl 1-002-2S NO:
TIMING & CLOSURE TEST 4.2
1.0 OBJECTIVE
This procedure provides instructions for verifying that the scram discharge volume vent and
drain valves close in the proper amount of time when given a simulated scram signal and that
they open when that signal is removed. This procedure satisfies the requirements of Unit 2 TS
SR 3.1.8.3, TS 5.5.6, and ASME OM Code Subsection ISTC.
TABLE OF CONTENTS
Section Page
2.0 APPLICABILITY .......................................................................................................... 2
3.0 R E FE R EN C ES .................................................................................................................... 3
4.0 R EQ UIR EM ENTS .......................................................................................................... 3
5.0 PRECAUTIONS/LIMITATIONS ....................................................................................... 4
6.0 PR ER EQ UIS ITES .......................................................................................................... 4
7.0 PROCEDURE ............................................................................................................. 5
7.1 P R ET EST ............................................................................................................. 5
7.2 TIMING AND CLOSURE TEST ............................................................................... 6
7.3 A DJUSTM ENT ...................................................................................................... 11
7.4 RESTORATION ..................................................................................................... 14
7.5 TEST R ESU LTS ..................................................................................................... 15
7.6 TEST R EV IEW ....................................................................................................... 17
2.0 APPLICABILITY
2.1 This procedure applies to the Unit 2 Scram Discharge Volume Vent and Drain VIvs,
2C11-FO10A & B, 2C11-F035A & B, 2C0 1-F011 and 2C11-F037; their associated Solenoid
Operated Pilot Valves, 2C1 i-F009 and 2C1 1-F040; and their actuating relays, 2C71-K21A-D.
This procedure is required to be performed at least once per 18 months.
2.2 This procedure is performed after maintenance on the SDV Valves that could affect valve
2.3 IF performing this procedure for setup and timing only and no maintenance was performed on
the SDV Valves, the stem verification will be marked N/R.
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 3 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: IREVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-C11-002-2S NO:
TIMING & CLOSURE TEST 4.2
3.0 REFERENCES
3.1 90AC-OAM-001-OS, Test and Surveillance Control
3.2 Unit 2 TS 5.5.6 and TS SR 3.1.8.3
3.3 H-26006 and H-26007, Control Rod Drive Hydraulic System P&IDs
3.4 H-27605 thru H-27619 and H-27850, Reactor Protection System Elementary Diagrams
3.5 Edwin I. Hatch Nuclear Plant Unit 2 - Valve Inservice Testing Plan
3.6 42EN-INS-001-0S, Inservice Testing Program
3.7 31GO-INS-001-0S, ISI Pump and Valve Operability Tests
4.0 REQUIREMENTS
4.1 PERSONNEL REQUIREMENTS
The number and qualification level of personnel performing this procedure will be determined
by the Shift Supervisor.
4.2 MATERIAL AND EQUIPMENT
4.2.1 2 HFA Gagging devices (optional)
4.2.2 Six calibrated stopwatches - one for each valve
4.3 SPECIAL REQUIREMENTS
4.3.1 Independent verification, as described in 10AC-MGR-019-0S, Procedure Use and
Adherence, will be required for portions of this procedure.
4.3.2 The VERIFIED part of any step requiring independent verification may be performed out
of sequence any time after completion of the first signoff.
4.3.3 The RESTORATION section of this procedure must be performed anytime the procedure
is begun, regardless of whether the results are acceptable OR unacceptable.
4.3.4 Ifin mode 1 or 2, this test will be immediately EXITED and the RESTORATION section
will be performed if annunciator 603-238, ROD OUT BLOCK alarms due to high SDV
level. This action is taken to allow the SDV to be drained prior to receipt of a SCRAM.
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 4 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISION/VERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-Ci 1-002-2S NO:
TIMING & CLOSURE TEST 4.2
5.0 PRECAUTIONS/LIMITATIONS
5.1 PRECAUTIONS
5.1.1 Observe safety rules outlined in the Southern Nuclear Safety and Health Manual.
5.1.2 Observe proper radiation protection practices to maintain personnel exposure ALARA
and to limit the spread of contamination. Remain alert for changes which might require
additional radiation protection.
5.1.3 IF the CRD System is operating during this test, leaking scram valves will cause
the scram valves discharge volume to begin filling during this test. IF the level
reaches 57 gal., a reactor scram will result.
5.1.4 The following annunciators may alarm during this test:
603-119, SCRAM DISCH VOL NOT DRAINED
603-238, ROD OUT BLOCK
603-239, RMCS / RWM ROD BLOCK OR SYSTEM TROUBLE
5.2 LIMITATIONS
N/A - Not applicable to this procedure
6.0 PREREQUISITES
6.1 The scram valve pilot air header is pressurized to between 70 PSIG and 75 PSIG.
6.2 The RPS is in operation and the scram relays are reset.
6.3 The Scram Discharge Volume Vent and Drain VIvs, 2C1 1-FO10A & B, 2C1 1-F035A & B,
2C11-F011 and 2C11-F037 are OPEN.
6.4 This test may be performed with the reactor in ANY mode of operation. It is preferable that the
reactor is in Modes 3, 4 or 5 with all operable control rods fully inserted, AND all other control
rods tagged under clearance such that they will NOT scram in the event of a scram signal
occurring.
6.5 Communications have been established between the RPS Panels, 2H11-P609, 2H11-P611,
and Panel 2H11-P603.
6.6 A Radiation Work Permit may be required for entry to areas for valve stem position
verification.
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 5 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-Cl 1-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.0 PROCEDURE
7..1 PRETEST
7.1. 1 Confirm that all prerequisites have been met. JD
JD
7.1. .2 Obtain Shift Supervisor's permission to perform this surveillance.
JD
7.1. .3 Record stopwatch numbers:
- 1 #4
- 2 #5
- 3 #6
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. . HATCH 6 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-CI 1-002-2S NO:
TIMING &CLOSURE TEST 4.2
7.2 TIMING AND CLOSURE TEST
CONTINUOUS
7.2.1 At Panel 2H1 1-P609, GAG or FINGER CLOSED relay 2C71-K21A. _JDO
NOTES
-The valve closing time is measured from the closing of relay 2C71-K21C until the red light
extinguishes. The stopwatches are to be started WHEN the relay is closed and stopped WHEN the
red light extinguishes.
-Ensure that the following relay remains closed until after all closing times have been recorded.
-The following step simulates a full scram and will cause all scram discharge volume vent and drain
valves to close.
7.2.2 At Panel 2H1 1-P609, GAG or FINGER CLOSED relay 2C71-K21C. _JD_
7.2.3 At Panel 2H1 1-P603, simultaneously START the stopwatches. _JJD
7.2.4 WHEN the individual scram discharge volume vent or drain valves
stop closing, STOP the stopwatches. .JDO
7.2.5 Record the closing times of the scram discharge volume vent and drain valves:
Scram Discharge Volume Vent VIv, 2C1 1-F01OA 53 Sec. _JD_
Scram Discharge Volume Vent VIv, 2C1 1-F035A 61 Sec. _JDO
Scram Discharge Volume Vent VIv, 2C1 1-F010B 48 Sec. _JD
Scram Discharge Volume Vent VIv, 2C1 1-F035B 54 Sec. _JDO
Scram Discharge Volume Drain VIv, 2C11-F011 56 Sec. _JD
Scram Discharge Volume Drain VIv, 2C1 1-F037 61.5 Sec. _JD
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 7 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-CI 1-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.2.6 Confirm that the SDV vent and drain valves are actually closed by
observing valve stem
position.
Scram Discharge Volume Vent VIv, 2C1 1-FO10A, CLOSED -JD
Scram Discharge Volume Vent VIv, 2C1 1-F035A, CLOSED JD
Scram Discharge Volume Vent VIv, 2C1 1-F010B, CLOSED JD
Scram Discharge Volume Vent VIv, 2C1 1-F035B, CLOSED JD
CLOSED JD
Scram Discharge Volume Drain VIv, 2C0 1-F011,
Scram Discharge Volume Drain VIv, 2C1 1-F037, CLOSED JD
7.2.7 Confirm that valves 2C1 1-FO10A, 2C1 1-F010B and 2C1 1-F01 1
close in less than or equal to 55 seconds. JD
7.2.8 Confirm that valves 2C1 1-F035A, 2C1 1-F035B and 2C1 1-F037
close in less than or equal to 60 seconds. _JD
NOTE
The valve opening time delay is measured from the release of relay 2C71-K21C until the red light
illuminates. The stopwatches are to be started WHEN the relay is released and stopped WHEN the red
light illuminates.
7.2.9 At Panel 2H11-P609, RELEASE relay 2C71-K21C. JD
7.2.10 At Panel 2H1 1-P603, simultaneously START the stopwatches. JD
7.2.11 At Panel 2H1-1-P609, RELEASE relay 2C71-K21A. JD
7.2.12 WHEN the individual scram discharge volume vent or drain valves
JD
begin to open, STOP the stopwatches.
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 1 8 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-Cl 1-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.2.13 Record the valve opening time delay for each of the scram discharge volume vent and
drain valves.
Scram Discharge Volume Vent Vlv, 2C1 1-F010A 20 Sec. . JD
Scram Discharge Volume Vent VIv, 2C1 1-F035A 14 Sec. -JDO
Scram Discharge Volume Vent VIv, 2C1 1-F010B 22 Sec. JD
Scram Discharge Volume Vent VIv, 2C1 1-F035B 15 Sec. -JD
Scram Discharge Volume Drain VIv, 2C11-F011 22 Sec. -JD
Scram Discharge Volume Drain VIv, 2C11-F037 17 Sec. -JD
7.2.14 Confirm that the SDV vent and drain valves are actually OPEN by observing valve stem
position.
Scram Discharge Volume Vent VIv, 2C1 1-FOI0A OPEN -JD
Scram Discharge Volume Vent VIv, 2C1 1-F035A OPEN -JD
Scram Discharge Volume Vent VIv, 2C1 1-FO01B OPEN _JJD
Scram Discharge Volume Vent VIv, 2C1 1-F035B OPEN _JJD
Scram Discharge Volume Drain VIv, 2C0 1-F011 OPEN -JD
Scram Discharge Volume Drain Viv, 2C1 1-F037 OPEN -JD
7.2.15 At Panel 2H1 1-P61 1, GAG or FINGER CLOSED relay 2C71-K21 B. _JJD
7.2.16 At Panel 2H11 -P61 1, GAG or FINGER CLOSED relay 2C71-K21 D. -JD
7.2.16.1 Confirm that all scram discharge volume vent and drain valves CLOSE:
Scram Discharge Volume Vent Vlv, 2C1 1-FO10A JD
Scram Discharge Volume Vent VIv, 2C1 1-F035A JD
Scram Discharge Volume Vent VIv, 2C0 1-F01OB JD
Scram Discharge Volume Vent VIv, 2C1 1-F035B -JD
Scram Discharge Volume Drain VIv, 2C0 1-F01l1 -JD
Scram Discharge Volume Drain VIv, 2C1 1-F037 JD
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 9 OF 17
IREVISIONNERSION
4.
DOCUMENT TITLE: DOCUMENT NUMBER:
NO:
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-C11-002-2S
4.2
TIMING & CLOSURE TEST
7.2.17 At Panel 2H1 1-P61 1, RELEASE relay 2C71-K21D. JD
JD
7.2.18 At Panel 2H1 1-P611, RELEASE relay 2C71-K21 B.
7.2.19 Confirm that all scram discharge volume vent and driain valves OPEN:
OPENS -JD
Scram Discharge Volume Vent VIv, 2C 1-F01 OA
OPENS -JD
Scram Discharge Volume Vent VIv, 2C1 1-F035A
OPENS _JDO
Scram Discharge Volume Vent VIv, 2C11-F010B
OPENS -JD
Scram Discharge Volume Vent VIv, 2C11 -F035B
OPENS -JD
Scram Discharge Volume Drain VIv, 2C11-F011
OPENS -JD
Scram Discharge Volume Drain VIv, 2C11-F037
in closing time between the valves
7.2.20 Using times from step 7.2.5, calculate the difference
listed below:
2C11-F035A closing time 61 Sec.
MINUS
2C11-F010A closing time 53 Sec.= 8 Sec. JD
2C11-F035B closing time 54 Sec.
MINUS
2C11-F01OB closing time 48 Sec. = 6 Sec. JD
2C11 -F037 closing time 61.5_ Sec.
MINUS
2C11-F011 closing time 56 Sec. = 5.5 Sec. JD
DJ
7.2.21 Verify all calculations in the previous step are correct. LIC.OPER.
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. 1. HATCH 10 OF 17
DOCUMENT TITLE: IDOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-Cll-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.2.22 Confirm that the difference in closing time between valves 2C1 1-F035A
and 2C11-FO10A, 2C1 1-F035B and 2C1 1-FO10B, and 2C11-F037 and
2C1 1-F011 is greater than or equal to 5 Seconds. . D
7.2.23 Using times from step 7.2.13, calculate the difference in valve opening time delay
between the valves listed below:
2C11-FO10A opening delay time 20 Sec.
MINUS
2C11-F035A opening delay time 14 Sec. = 6 Sec. JD
2C11-F701B opening delay time 22 Sec.
MINUS
2C11-F035B opening delay time 15 Sec. = 7 Sec. JD
2C1 1-F011 opening delay time 22 Sec.
MINUS
2C1 1-F037 opening delay time 17 Sec.= 5 Sec. JD
DJ
7.2.24 Verify all calculations in the previous step are correct. Lic. Oper.
7.2.25 Confirm that the difference in valve opening time delay between valves
2C1 1-F010A and 2C1 1-F035A, 2C1 1--F0101B and 2C1 1-F035B, and
2C1 1-F011 and 2C1 1-F037 is greater than or equal to 5 Seconds. JD
7.2.26 IF all of the valve times recorded in this Section meet the acceptance
criteria, proceed to the Restoration Section of this procedure; JD
otherwise, continue with the Adjustment Section.
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 11 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-Cl 1-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.3 ADJUSTMENT
CONTINUOUS
NOTE
This section only needs to be done if any of the valve closing or opening delay times can NOT meet the
acceptance criteria.
7.3.1 IF Scram Discharge Volume Vent and Drain Vlvs, 2C11-F035A & B and 2C1 1-F037,
do NOT meet the acceptance criteria for valve closing time, perform the following:
7.3.1.1 On the wall between MCCs 2R24-S018 A and B (130RHR17),
ADJUST Speed Control Valve, 2C1 1-F081, accordingly (OPEN to
increase closing speed, CLOSED to decrease it).
7.3.1.2 At Panel 2H11-P611, GAG or FINGER CLOSED relay 2C71-K21B.
7.3.1.3 At Panel 2H1-1 -P611, GAG or FINGER CLOSED relay 2C71-K21 D.
7.3.1.3.1 Note the closing time on all scram discharge volume vent and
drain valves following closure of 2C71 -K21 D.
7.3.1.4 At Panel 2H11-P611, RELEASE relay 2C71-K21D.
7.3.1.5 At Panel 2H1 1-P61 1, RELEASE relay 2C71--K21 B.
7.3.1.6 Repeat steps 7.3.1.1 through 7.3.1.5 until the acceptance criteria for
valve closing time (steps 7.5.2.3-7.5.2.5) can be met. Record the final
closing times of the scram discharge valve vent and drain valves.
Scram Discharge Volume Vent VIv, 2C1 1-F01OA Sec.
Scram Discharge Volume Vent VIv, 2C1 1-F035A Sec.
Scram Discharge Volume Vent VIv, 2C11-F01OB Sec.
Scram Discharge Volume Vent VIv, 2C11 -F035B Sec.
Scram Discharge Volume Drain VIv, 2C1 1-F01 1 Sec.
Scram Discharge Volume Drain VIv, 2C0 1-F037 Sec.
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 12 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-Cl 1-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.3.1.7 Calculate the difference in closing time between the valves listed below:
2C1 1-F035A closing time Sec.
MINUS
2Cl 1-F01OA closing time Sec.= Sec.
2C11-F035B closing time Sec.
MINUS
2C 1-F01OB closing time Sec. = Sec.
2C1 1-F037 closing time Sec.
MINUS
2C11-F011 closing time Sec. = Sec.
7.3.1.8 Verify all calculations in the previous step are correct.
7.3.1.9 Confirm that the difference in closing time between valves 2Cl 1-F035A
and 2C1 1-FO10A, 2C11-F035B and 2C11-F010B, and 2C1 1-F037 and
2C1 1-F01 1 is greater than or equal to 5 Seconds.
7.3.2 IF Scram Discharge Volume Vent and Drain Valves, 2C1 1-F01 0 A&B and 2C1 I-F01 1,
do NOT meet the acceptance criteria for valve opening time delay, perform the following:
7.3.2.1 At the CRD Flow Control Area (130RAR21), ADJUST Speed Control
Valve, 2C1 1-F086, accordingly (OPEN to decrease the time delay,
CLOSED to increase it).
7.3.2.2 At Panel 2H1 1-P61 1, GAG or FINGER CLOSED relay 2C71-K21 B.
7.3.2.3 At Panel 2H11-P611, GAG or FINGER CLOSED relay 2C71-K21D.
7.3.2.4 AFTER all of the scram discharge volume vent and drain valves
have CLOSED, RELEASE relay 2C71-K21D.
7.3.2.4.1 Note the valve opening time delay on all scram discharge
volume vent and drain valves.
7.3.2.5 At Panel 2H11-P611, RELEASE relay 2C71-K21B.
G16.30
MGR-0001 Rev 3
PAGE
SOUTHERN NUCLEAR 13 OF 17
PLANT E. I. HATCH
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-C11-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.3.2.6 Repeat steps time7.3.2.1 an b7.3.2.4.1
through
elay(ste.7.5..6) until theth acceptance criteria for valve opening
met.Recod
time delay (step 7.5.2.6) can be met. Record the final opening time delays oT me
scram discharge volume vent and drain valves.
Scram Discharge Volume Vent VIv, 2C1 1-FG10A Sec.
-_ Sec.
Scram Discharge Volume Vent VIv, 2C 1-F035A
-_ Sec.
Scram Discharge Volume Vent VIv, 2C1 1-F010B
-_ Sec.
Scram Discharge Volume Vent VIv, 2C0 1-F035B
-_ Sec.
Scram Discharge Volume Drain VIv, 2C0 1-F011
___._Sec.
Scram Discharge Volume Drain VIv, 2C11-F037
7.3.2.7 Calculate the difference in valve opening time delay between the valves listed below:
2C11-F010A opening delay Sec.
MINUS
2C1 1-F035A opening delay Sec. = Sec.
2C1 1-F01GB opening delay Sec.
MINUS
2C11-F035B opening delay Sec. = Sec.
2C11-F011 opening delay Sec.
MINUS
2C11-F037 opening delay Sec. = Sec.
7.3.2.8 Verify all calculations in the previous step are correct. LIC. OPER.
7.3.2.9 Confirm that the difference in valve opening time delay between valves
2C11 -FO10A and 2C1 1-F035A, 2C11--FG010B and 2C11-F035B, and
2C1 1-F01 1 and 2C1 1-F037 is greater than or equal to 5 Seconds.
G16.30
MGR-0001 Rev 3
PAGE
SOUTHERN NUCLEAR
PLANT E. I. HATCH 14 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-C11-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.4 RESTORATION
7.4.1 At Panel 2H11-P609, REPLACE all relay faceplates.
7.4.2 At Panel 2H11-P611, REPLACE all relay faceplates.
7.4.3 At Panel 2H11-P609, Confirm and VERIFY the following relays are DE-ENERGIZED:
VERIFIED
VERIFIED
7.4.4 At Panel 2H11-P611, Confirm and VERIFY the following relays are DE-ENERGIZED:
VERIFIED
VERIFIED
vent and drain
7.4.5 At Panel 2H11-P603, confirm AND verify that all scram discharge volume
valves are OPEN:
Scram Discharge Volume Vent VIv, 2C1 1-F010A
VERIFIED
Scram Discharge Volume Vent VIv, 2C1 1-F035A
VERIFIED
Scram Discharge Volume Vent VIv, 2C1 1-F01OB
VERIFIED
Scram Discharge Volume Vent VIv, 2C1 1-F035B
VERIFIED
Scram Discharge Volume Drain VIv, 2C1 1-F011
VERIFIED
Scram Discharge Volume Drain VIv, 2C1 1-F037
VERIFIED -JD
G16.30
MGR-0001 Rev 3
PAGE
SOUTHERN NUCLEAR
PLANT E. I. HATCH 15 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-Cl1-002-2S NO:
4.2
TIMING & CLOSURE TEST
7.5 TEST RESULTS
7.5.1 Reason for test: (X)Norm. Surv. ( )MWO #
( ) Other
7.5.2 Acceptance Criteria
7.5.2.1 ALL scram discharge volume vent and drain valves close when given a simulated
scram signal.
7.5.2.2 ALL scram discharge volume vent and drain valves open when the signal is removed.
7.5.2.3 Valves 2C1 1-FO10A, 2C1 1-F010B and 2C1 1-FOI 1 close in less than or equal
to 55 Seconds.
7.5.2.4 Valves 2C1 1-F035A, 2Cl 1-F035B and 2C1 1-F037 close in less than or equal
to 60 Seconds.
7.5.2.5 The difference in closing time between valves 2C11 -F035A and 2C1 1-F010A, 2C11
F035B and 2C11-F010B, and 2C11-F037 and 2C11-F011 is greater than or equal to
5 Seconds.
7.5.2.6 The difference in valve opening time delay between 2C1 1-FO10A and 2C1 1-F035A,
2C1 1-F01OB and 2C11-F035B, and 2C1 1-F0I1 and 2C11-F037 is greater than or
equal to 5 Seconds.
7.5.2.7 Valve stem position agrees with light indication in Control Room.
(see steps 7.2.6 and 7.2.14)
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 16 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-C11-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.5.3 Test Result:
(( X) Satisfactory
) Unsatisfactory
7.5.4 Unsatisfactory Conditions:
7.5.5 Comments/Corrective Actions:
7.5.6 Test Completed and/or Verified by:
John Doe / Dat /
Date
Print Name Initials
Dave Jones / /
Initials Date
Print Name
/ !
Print Name Initials Date
/ N
Print Name Initials Date
/ /
Print Name Initials Date
/ I
Print Name Initials Date
/ /
Print Name Initials Date
/ /
Print Name Initials Date
G16.30
MGR-0001 Rev 3
SOUTHERN NUCLEAR PAGE
PLANT E. I. HATCH 17 OF 17
DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION
SCRAM DISCHARGE VOLUME ISOLATION VALVE 34SV-C11-002-2S NO:
TIMING & CLOSURE TEST 4.2
7.6 TEST REVIEW
7.6.1 The Shift Supervisor will review the procedure data for completeness and indicate
concurrence with the test satisfactory/unsatisfactory determination by signing below.
Results Reviewed By: /
Shift Supervisor Date
7.6.2 The Shift Supervisor will forward this procedure, with all sign offs complete through 7.7.1
to the IST Engineer for IST and ANII review
/
Date / Date
IST Engineer ANII
7.6.3 The IST Engineer will forward this procedure, with all sign offs complete, to Document
Control for retention in accordance with 20AC-ADM-002-OS, Quality Assurance Records
Administration.
G16.30
MGR-0001 Rev 3
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
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
T. F. PHILLIPS R. S. GRANTHAM 1/70
SOUTHERNAN
COMPANY
Energy to Serve Your World'
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-25043
00 10/07/02 Initial Development. RLS RSG
_ _I _ _ I JI _ I _
LR-JP-25043-00
Page 1 of 9
UNIT 1 (X) UNIT 2 (X)
FROM OUTSIDE THE CONTROL ROOM, INJECT
BORON USING THE SBLC SYSTEM WITH
FAILURE OF "A" PUMP TO START.
F;~a"EE 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
F011.012.B
PLANT HATCH JTA IMPORTANCE RATING:
RO 4.20
SRO 4.20
K/A CATALOG NUMBER: 2110002130
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.90
SRO 3.40
OPERATOR APPLICABILITY: System Operator (SO)
-E EM - R -
34SO-C41-003-1S 34S0-U41-UUJ-Zi
(current revision) (current revision)
Four (4) SBLC Squib Valve Four (4) SBLC Squib Valve
jumper wires, from EOP file jumper wires, from EOP file
next to Remote Shutdown next to Remote Shutdown
Panel 1H21-P173 Panel 2C82-P001
Flathead screwdriver Flathead screwdriver
APPROXIMATE COMPLETION TIME: 21.0 Minutes
SIMULATOR SETUP: N/A
1
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-0 1-1S (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-C41-003-1S.
LR-JP-25043-00
Page 3 of 7
10
START
TIME:
T
Operator has identified the
required materials and where to
obtain them. (Section 7.2.2)
- 1* -r
Operator has reviewed the
precautions and limitations.
I
At Panel 1H2 1-PO11, the
following jumpers are
INSTALLED for 1C41-FO04A:
Terminal point BB-l to Squib
Valve, 1C41-FO04A, Junction
Box terminal Cl (white wire) and
terminal C (green wire).
Terminal point BB-4 to Squib
Valve, 1C41-F004A, Junction
Box terminal C2 (black wire) and
terminal C3 (red wire).
At Panel 1H21-PO11, the
following jumpers are
INSTALLED for 1C41-FO04B:
Terminal point BB-8 to Squib
Valve, 1C41-FO04B, Junction
Box terminal C1 (white wire) and
terminal C (green wire).
Terminal point BB-11 to Squib
Valve, 1C41-F004B, Junction
Box terminal C2 (black wire) and
terminal C3 (red wire).
RESPONSE CUE: Squib Valve 1C41-FO04A(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 4 of 7
I E
PROMPT: IF the operator addresses isolation of RWCU, as the Control Room operator
REPORT that RWCU is isolated.
4. Start SBLC Pump 1C41-CO0LA. At panel 1H21-POll, SBLC
PUMP, 1C41-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-PO 11, SBLC
STOP position PUMP, 1C41 -COO1A, control
switch is in STOP.
At panel 1H21-PO1l, SBLC
PUMP, 1C41-COO1B, control
switch is in RUN.
RESPONSE CUE: SBLC Pump 1C41-COO1B, pump motor is quiet, and green light is
illuminated.
7. Verify the SBLC solution is being At panel 1H21-P011, the operator
injected into the Reactor. has VERIFIED SBLC Tank level
is DECREASING as indicated by
SBLC STORAGE TANK
LEVEL INDICATOR,
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: We will stop here.
(** Indicates critical step)
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 B11T 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 7
ASTT xP iN4R
START
TIME:
1. Operator identifies the materials that Operator has identified the
are required. required materials and where to
obtain them. (Section 7.2.2)
Operator reviews the procedure's Operator has reviewed the
precautions and limitations. peatin and limitations.
At Panel 21- 4PA11, the
following jumpers are
INSTALLED for 2C41-Fi04A:
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-FO04A, Junction
Box terminal point 4 (red wire)
and terminal point 2 (black wire).
At Panel 2S221-P01q1, the
following jumpers are
INSTALLED for 2C41-F004B:
Terminal point AA-10 to Squib
Valve, 2C41-F004B, Junction
Box terminal point 1 (white wire)
and terminal point 3 (green wire).
Terminal point AA-m11 to Squib
Valve, 2C41-ar004B, 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
RA6M~
PROMPT: IF the operator addresses isolation of RWCU, as the Control Room
operator, REPORT that RWCU is isolated.
4. Start SBLC Pump 2C41-C0O1A. At panel 2H21-PO11, 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-PO 11, SBLC
STOP position PUMP, 2C41-C0O1A, control
switch is in STOP.
% fN , ~ *V At panel 2H21-PO11, SBLC
PUMP, 2C41-COO1'B, control
switch is in RUIN.
RESPONSE CUE: SBLC Pump 2C41-CO01B, pump motor is quiet, and green light is
illuminated.
7. Verify the SBLC solution is being At panel 2H21-PO 11, the operator
injected into the Reactor. has VERIFIED SBLC Tank level
is DECREASING as indicated by
SBLC STORAGE TANK
LEVEL INDICATOR,
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: We will stop here.
(** Indicates critical step)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
FROM THE REMOTE SHUTDOWN PANEL, START RCIC FOR INJECTION
7:
FROM THE REMOTE SHUTDOWN PANEL, START RCIC FOR INJECTION
INTO THE REACTOR
R. A. BELCHER LR-JP-39.16-12 24.0 Minutes
N/R R. A. BELCHER 03/14/2002
SOUTHERN Ek
COMPANY
Energy to Serve Your World"
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-39.16
""._ W k
A,
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 RAB RSG
08 08/11/94 Modify simulator setup, adjust format RAB SMC
09 08/05/96 Format change, procedure changes RAB DHG
10 03/06/00 Format modification, update, K/As, upgrade to the RAB 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 RAB DHG
based on running average
12 03/14/02 Include initial operator statement RAB RAB
[ II
_ _ _ _ _ _ I_ _
LR-JP-39.16-12
Page 1 of 7
UNIT 1 (X) UNIT 2 (X)
FROM THE REMOTE SHUTDOWN PANEL, START
RCIC FOR INJECTION INTO THE REACTOR
~1
LR-JP-39.16-12
KSY The task shall be completed when the RCIC System is started
and injecting to the Reactor per 3 1RS-OPS-001.
039.016
TLE 039.016.O
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.86
SRO 3.80
K/A CATALOG NUMBER: 2950162130
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.90
SRO 3.40
OPERATOR APPLICABILITY: Reactor Operator (RO)
4K Y
(current revision)
Key for Remote Shutdown
Panel (if performed in Plant
APPROXIMATE COMPLETION TIME: 24.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
LR-JP-39.16-12
Page 2 of 9
SIMULATOR SETUP
Simulator Initial Conditions:
1. RESET the Simulator to IC #127 and leave in FREEZE.
2. INSERT the following MALFUNCTIONS:
mfB21 48A Steam Line A Break (After Restrictor) (Var) 1.0 1000 00000
mfN2179A Condensate Pump 2A Trip 00000
mfN21 79B Condensate Pump 2B Trip 00000
mfN21_79C Condensate Pump 2C 00000
mtE41107 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
2
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. 31 RS-OPS-001-2S is in progress.
5. RWL is -80" and decreasing.
INITIATING CUES:
Start the RCIC System from the Remote Shutdown Panel and inject water
into the Reactor per 31RS-OPS-001-2S, Attachment 3.
LR-JP-39.16-12
Page 4 of 7
START
1
S "1.0perator identifies the materials that Operator identifies the required TIME:__ __
are required. [materials and where to obtain
Sthem.
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.
RESPONSE CUE: Remote Shutdown Panel indications are not available.
(** Indicates critical step)
LR-JP-39.16-12
Page 5 of 7
M161 ROMME
- , j I
3. Confirm the following valves are At panel 2C82-POO 1, the operator
open: VERIFIES the following valves
are OPEN, red light illuminated:
STEAM SUPPLY INBD ISOL
2E51--F008 VLV, 2E5 1-F007
STEAM SUPPLY OUTBD ISOL
VLV, 2E5 l-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-POO1, the operator
in AUTO and set for 400 gpm. VERIFIES RCIC FLOW
CONTROL, 2C82-RC01:
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
2E5 1-F029 are CLOSED, green light
illuminated:
2E51--F031 TORUS OUTBD SUCTION
2E51--F031
TEST LINE TO CST, 2E5 1-F022
NOTE: The operator should not address opening 2E51-F029 and 2E51-F031 since
2E51-FO10 is open.
6. Start the Barometric Condenser At panel 2C82-POO1, the
Vacuum Pump. BAROMETRIC CNDSR VAC
PUMP, 2E5 1-C002-2, is in
START, red light illuminated.
(** Indicates critical step)
LR-JP-39.16-12
Page 6 of 7
- ST>E~ ~~~~~ ~R44>'
~u~MvMCM 4 ,
A/~$ AN", i~}%+~
-I r T
Start the Barometric Condenser At panel 2C82-POO 1, the
BAROMETRIC CNDSR COND
PUMP, 2E51-C002-1, is in
START, red light illuminated.
I
At panel 2C82-POO1, the operator
has verified TRIP & THROTTLE
light illuminated.
At panel 2C82-P001, TURB CLG
WTR VLV, 2E5 1-F046, is
OPEN, red light illuminated.
RESPONSE CUE: Valve, 2E5 1-F046, green light illuminated.
FLOW VLV, 2E5 1-FO 19, is
OPEN, red light illuminated.
OPEN, red light illuminated.
RESPONSE CUE: Valve, 2E51-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-P001, DISCH
RESPONSE CUE: Valve, 2E51-F013, green light illuminated.
PROMPT: INDICATE for the operator Flow increasing to 400gpm on the RCIC Flow
Controller.
RESPONSE CUE: Valve, 2E5 l-FO19, red light illuminated.
(** Indicates critical step)
LR-JP-39.16-12
Page 7 of 7
0 NoMME I
PROMPT: IF the operator addresses RWL band, as the Shift Supervisor, INFORM the
operator that another operator will maintain RWL.
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)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
=
aimummum
DURING A LOSS OF AIR, ISOLATE THE FIRE PROTECTION SPRINKLERS
R. A. BELCHER LR-JP-36.13-07 13.0 Minutes
N/R R. A. BELCHER 03/12/20 02
4k
SOUTHERN
COMPANY
Energy to Serve Your World' M
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-36.13
01 09/04/92 General revision and format change WMM SMC
02 07/22/93 General revision, word processor change RAB RSG
03 08/19/94 Procedure change, adjust format, change initiating cue RAB SMC
to a direct command
04 08/01/96 Format change, modify time allowance RAB DHG
05 02/25/00 Format modification, change time allowance based on RAB DHG
running average, update K/As 1
06 11/02/00 Include objective number, change operator RAB DHG
applicability to Systems Operator
07 03/12/02 Include initial operator statement RAB RAB
I I 1
I I t1
II t I
II r
4. I I I
_______ I J I
_______ .1 1. I I
_ _ _ _ I I.I
__ _ I_ I
_ _ _ __ I It
t t
_ _ _ _ I Itt
______ I t 7
______ I- I I I
______ 1. I I
______ .1 J I I
____________I
I__________
___________ ___________
LR-JP-36.13-07
Page 2 of 9
UNIT 1 (X) UNIT 2 (X)
DURING A LOSS OF AIR, ISOLATE THE FIRE
PROTECTION SPRINKLERS
MM
M" NBN LR-JP-36.13-07
The task shall be completed when the Fire Protection Sprinklers
have been isolated during a loss of air per 34AB-P51-001.
036.013
036.013.O
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.57
SRO 3.70
K/A CATALOG NUMBER: 2860002130
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.90
SRO 3.40
OPERATOR APPLICABILITY: Systems Operator (SO)
APPROXIMATE COMPLETION TIME: 13.0 Minutes
SIMULATOR SETUP: N/A
2
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 4 of 3
MOW
Wwv&l-Cn IMIM, iS1 NDig NEM ARM
I
START
TIME:
NOTE: The steps of this JPM may be performed in any order.
M At location 112TAT19, valve
22U43-F093 is CLOSED.
RESPONSE CUE: N/A
NOTE: This valve isolates the Reactor Feed Pump and Oil Conditioner area.
CI;" tJ3 *N4 At location 136THT20, valve
t* al% r 2U43-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.
I o RA
p3 ' 621
L6 ' 3 At location 112THT13, valve
2Z43-Fl101 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.
04 At location 130TAT19, 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.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
INITIATE EMERGENCY TORUS VENTING USING THE EMERGENCY
VENT PATH
R. A. BELCHER LR-JP-13.53-10 12.0 Minutes
N/R R. A. BELCHER 03/07/2002
SOUTHERN a
COMPANY
Energy to Serve Your World'"
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-13.53
01 08/01/90 General revision and format change JEM DHG
02 05/24/91 General/procedure revision JLA DHG
03 08/18/92 General revision and format change WMM SCB
04 06/23/93 Task change, rename, procedure change, word RAB RSG
processor change
05 12/02/93 Change initiating cue to a command, change valve RAB SMC
naming to match the plant
06 06/17/96 Format change, modify time allowance RAB RSG
07 02/04/00 Format modification, title change, change time RAB DHG
allowance based on running average
08 11/02/00 Include objective number RAB DHG
09 01/03/02 Change Unit 2 control pressure to 56 psig. RLS DHG
10 03/07/02 Include initial operator statement RAB RAB
___ I___ I I
___ ___
LR-JP-13.53-10
Page 1 of 8
UNIT 1 (X) UNIT 2 (X)
W
INITIATE EMERGENCY TORUS VENTING USING
SMIR
THE EMERGENCY VENT PATH
LR-JP-13.53-10
This task shall be completed when the Torus is lined up to vent
via the Emergency Vent per 31 EO-EOP- 101.
013.053
OXE &W 013.053.O
PLANT HATCH JTA IMPORTANCE RATING:
RO 4.14
SRO 4.50
K/A CATALOG NUMBER: 223001A207
K/A CATALOG JTA IMPORTANCE RATING:
RO 4.20
SRO 4.30
OPERATOR APPLICABILITY: Reactor Operator (RO)
W- 1
- IrmQUIR11
31EO-EOP-101-IS 31EO-EOP-101-2S
(current revision) (current revision)
Designated jumpers(2) in EOP Designated jumpers(2) in EOP
jumper book jumper book
Screwdriver or nutdriver 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
(Graph 7).
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 8
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
PROMPT: IF addressed by the operator, INFORM the operator that normal AC power
and Non-interruptible air are available.
RESPONSE CUE: Valve 1T48-F081, red light illuminated.
RESPONSE CUE: SBGT A Fan, 1T46-C001A, red light illuminated
RESPONSE CUE: SBGT A Fan, 1T46-COO1B, red light illuminated.
(** Indicates critical step)
LR-JP-13.53-10
Page 4 of 8
IVN1
ORP a w iQ; S4 z~UN
At panel IH 11-P657, the operator
CLOSES 1T46-F005, DISCH
CONTROL DAMPER, green
light illuminated.
RESPONSE CUE: Damper 1T46-F005, red light illuminated.
RESPONSE CUE: N/A
RESPONSE CUE: N/A
RESPONSE CUE: Valve 1T48-F326, green light illuminated.
RESPONSE CUE: Valve 1T48-F318, 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.
At panel 1H11 1-P654, the operator
OPENS 1T48-F082, SUPP
CHBR EMER VENT VLV, red
light illuminated.
RESPONSE CUE: Valve 1T48-F082, green light illuminated.
(** Indicates critical step)
LR-JP-13.53-10
Page 5 of 8
vv ~~~~:11 rUIORMNC RA
ir
HIM,,t~ A~j
PROMPT: IF the operator addresses Toms 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.
(Graph 7)
2. 31EO-EOP-012-2S (PC-1) 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 8
START
TIME:
1. Operator identifies the materials that Operator identifies the required
are required. materials and where to obtain
Ithem.
PROMPT: IF addressed by the operator, as the Shift Supervisor, INFORM the
operator that another operator is monitoring the NPSH curves for RHR and
PROMPT: IF addressed by the operator, INFORM the operator that normal AC power
and Non-interruptible air are available.
RESPONSE CUE: Valve 2T48-FO81, red light illuminated.
At panel 2H 1I-P657, the operator
PLACES 2T46-DO01A, SBGT A
FAN/FILTER to OFF, green light
illuminated and VERIFIES that
2T46-F002A, FLTR DISCH
CLOSES, green light illuminated.
RESPONSE CUE: SBGT A Fan/Filter, 2T46-DO01A, red light illuminated and/or
Damper, 2T46-FO02A, red light illuminated.
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-13.53-10
Page 8 of 8
CA/US STVNPRM
Sill dMMT~
RESPONSE CUE: N/A
RESPONSE CUE: Valve 2T48-F326, green light illuminated.
RESPONSE CUE: Valve 2T48-F318, green light illuminated.
At panel 2H1 1-P654, the operator
VERIFIES that 2T48-F085,
SUPP CHMBR EMERG VENT
At panel 2H411 -P654, the operator
OPENS 2T48-F082, SUPP
CHMBR EMERG VENT VLV,
red light illuminated.
RESPONSE CUE: Valve 2T48-F082, green light illuminated.
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:
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
TRANSFER THE MODE SWITCH TO STARTUP/HOT STANDBY, WITH AN
APRM AT 15% POWER
R. L. SMITH LR-JP-10.19-00 10.0 Minutes
ST.F. PHILLIPS R.S. GRANTHAM 10/7/02
SOU1 !HERN Ea
COMPANY
Energy to Serve Your World" M
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. RLS RSG
II t1
I IrT
-II i I
I I I I
I I I I
I1 Ii I
IIt
I I 1
I I t i
I It
_ _ _ _I I
_ _ _ _ I I.
_ _ _ _ I I11
________________ .1 1
LR-JP- 10.19-00
Page 1 of 5
UNIT 1 0 UNIT 2 (X)
TRANSFER THE MODE SWITCH TO
STARTUP/HOT STANDBY, WITH APRM AT 15%
POWER
PI LR-JP-10.019
The task shall be completed when the APRM is bypassed and the
Mode switch is transferred to Startup/Hot Standby.
010.019
OBJCT 010.019A
PLANT HATCH JTA IMPORTANCE RATING:
K/A CATALOG NUMBER: G2.1.23
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.9
SRO 4.0
OPERATOR APPLICABILITY: Reactor Operator (RO)
APPROXIMATE COMPLETION TIME: 10 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
LR-JP- 10.19-00
Page 2 of 5
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 ACT.
VALUE RATE TIME
mfC51 19A LPRM UPACALE 'B' LEVEL 20.29 0000
mf60323379 LPRM UPSCALE ALARM OFF 0000
4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.
5. ESTIMATED Simulator SETUP TIME: 10 Minutes
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Reactor Shutdown is in progress; steps through 7.3.16 of
34GO-OPS-013-2 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.
LR-JP- 10-019-00
Page 4 of 5
fih E "IOU*k
START
TIME:
1. Operator reviews the procedure's Operator has reviewed the
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 2H 11-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.
(** Indicates critical step)
LR-JP-10-019-00
Page 5 of 5
At panel 2H1 1-P603, the operator
PLACES the APRM 2B in
Bypass.
RESPONSE CUE: APRM 2B not in BypasSs.
6. Confirm all rod blocks clear. At panel 2H1 1-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.
- 7,In LESe~ e At panel 2H11-P603, the operator
places the Mode Switch into
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
9. Confirms the Annunciator "MSIV At panel 2H11-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
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
TRANSFER AN EMERGENCY
Al 4160 VAC BUS FROM THE EMERGENCY TO
TRANSFER AN EMERGENCY 4160 VAC BUS FROM THE EMERGENCY TO
THE NORMAL POWER SUPPLY
R. A. BELCHER LR-JP-27.11-14 22.0 Minutes
SOUTHERN oka
COMPANY
Energy to Serve Your World"T
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
"AMR.._ 10 Re on M iý V.__
01 06/09/89 General revision and format change WGW RSG
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 RAB RSG
05 07/18/94 Correct for D/G loading, adjust format RAB SMC
06 02/23/95 Correct simulator setup and prompts to include RAB 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 RAB SMC
Unit 1section
08 07/05/96 Format change RAB 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 (Ut) and Step 9 (U2) noncritical.
Revised for new simulator malfunction numbers.
11 02/11/00 Format modification, change time allowance based on RAB DHG
running average, update to new simulator operating
system
12 03/29/00 TLB comment; change step 10 of U2 for voltage RAB SMC
requirement of the diesel
13 11/02/00 Include objective number, TLB comment, correct Step RAB DHG
9 of Unit 1 section to agree with procedure change _
14 03/11/02 Incorporate instructor comment on goal for power RAB RAB
decrease of Step 12 for Unit 2, include initial operator
statement
I r I--
_______ I I I __
_______ +/- I I I --
_______ 4 I I I
_______ .1_______ J
LR-JP-27.11-14
Page 1 of 7
UNIT 1 (X) UNIT 2 (X)
Ji~jjTHE
s&*TRANSFER
SUPPLY
AN EMERGENCY 4160 VAC BUS FROM
EMERGENCY TO THE NORMAL POWER
SLR-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.
T027.011
~027.011.0
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.07
SRO 3.07
K/A CATALOG NUMBER: 262001A404
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.60
SRO 3.70
OPERATOR APPLICABILITY: Reactor Operator (RO)
Pt ...~~~.+/-_~ IbE IIE~ L
(current revisions)
APPROXIMATE COMPLETION TIME: 22.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
LR-JP-27.11-14
Page 2 of 9
SIMULATOR SETUP
Simulator Initial Conditions:
1. RESET the Simulator to IC #121 and leave in FREEZE.
2. INSERT the following REMOTE FUNCTIONS:
3. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A. Open the Normal and Alternate supply breakers to Bus "2F."
B. Verify the "1 B" D/G output breaker closes and match flags on the breaker
switch.
C. Place Diesel Generator "B" Volt Select switch in OFF position.
D. Ensure Diesel Generator load is greater than 500 kW. If necessary, start
another PSW pump on that bus.
4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.
5. ESTIMATED Simulator SETUP TIME: 15 Minutes
2
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. 4160 VAC Emergency Bus "2F" is being supplied from Emergency
Diesel Generator "lB."
2. The condition that caused Bus "2F" to deenergize has been corrected.
3. The normal off-site power supply is available.
4. 34AR-652-202-2S, LOSS OF OFF-SITE POWER, is in progress.
5. Diesel Generator "IB" control has been transferred to Unit 2.
INITIATING CUES:
Transfer the 4160 VAC Bus "2F" to the NORMAL power supply in
accordance with 34SO-R43-001-2S, per section 7.4.4, "Transfer 4160 V
Bus 2F From 1B Diesel Generator to Normal OR Alternate."
LR-JP-27.11-14
Page 4 of 7
~~STEP Rj'v6R'n
> .......
START
TIME:
1. Operator reviews the procedure. Operator has reviewed the
procedure.
2. Confirm power is available to Startup At panel 2H11-P651, the operator
Transformer "2C" &"2D." has VERIFIED that S/U AUX
XFMR 2C & 2D potential lights
are illuminated.
PROMPT: WHEN the operator addresses the requirements to reset the LOSP Lockout
Relay, as the Shift Supervisor, INFORM the operator that all requirements
are met per 30AC-OPS-003-OS.
RESPONSE CUE: Bus 2F LOSP relay locked out, white light extinguished.
RESPONSE CUE: Diesel Generator in Test annunciator is clear.
PROMPT: IF the operator addresses Diesel Generator "IB" keylock switch, as the SO,
INFORM the operator the switch is in the Remote Unit 2 position.
PROMPT: WHEN the operator addresses adjusting speed droop, the simulator operator
should TOGGLE REMOTE FUNCTION rfR43295, "D/G lB Engine
Remote Speed Droop (0 to 100)," to 50. As the SO, INFORM the operator
that speed droop has been adjusted to 50.
(** Indicates critical step)
LR-JP-27.11-14
Page 5 of 7
M$~~P4R 4~~h
RESPONSE CUE: Voltage Regulator, red light illuminated.
PROMPT: WHEN the operator addresses the position of the Unit 1 Voltage Regulator
Transfer switch, the simulator operator should TOGGLE REMOTE
FUNCTION rfR43188, "Diesel Gen lB Unit 1 Voltage Reg Transfer," to
MAN. As the Unit 1 Control Room operator, INFORM the operator that
the switch is in manual.
NOTE: Synchroscope lights and synchroscope may be cycling depending on
difference between sources.
RESPONSE CUE: Synchroscope lights are extinguished or synchroscope needle not
moving.
NOTE: Diesel Generator B Volt Select switch must be turned on to check DG
voltage.
8. Adjust the "IB" Diesel Generator At panel 2H11-P652, the "IB"
output voltage to 4160 V. Diesel output voltage is
ADJUSTED by using the
DIESEL GEN B VOLTAGE
ADJUST switch as necessary to
indicate approximately 4160 volts
on VOLTMETER for 4KV BUS
2F.
NOTE: For the purpose of this JPM, 4000 to 4300 volts is considered matched.
NOTE: For performance of this JPM, the Diesel Generator is NOT lightly loaded.
(** Indicates critical step)
LR-JP-27.11-14
Page 6 of 7
- 3TE4 4<4h, f4T~h N~~v V 4
W T/S-SI
9. Adjust the "IB" Diesel Generator At panel 2H11 l-P652, the DIESEL
synchroscope rotation. GEN B, SPEED ADJUST switch
MANIPULATED as needed until
the Synchroscope rotation is in
the clockwise direction.
RESPONSE CUE: Synchroscope is not rotating or rotating in counterclockwise
direction.
10. Adjust Diesel Generator voltage to the At panel 2H11 1-P652, Diesel
highest phase of SUT "2D" voltage, output voltage is ADJUSTED
using DIESEL GEN B,
VOLTAGE ADJUST to match
the highest phase of SUT "2D."
NOTE: The operator should not exceed 4400 volts on any phase of the Diesel
Generator (Although Step 10 is not a critical step, if operator exceeds
4400 volts, then Step 10 becomes a critical step and would constitute
operator failure).
NOTE: For the purpose of this JPM, +/-100 volts is considered matched.
At panel 2H11 -P652, 4160 "2F,"
NORMAL SUPPLY ACB
135574 control switch is taken to
CLOSE, when synchroscope is 2
minutes to 12:00 position and
when the synchroscope lights
approach the dimmest point, then
released to the midposition, red
light illuminated.
RESPONSE CUE: ACB 135574, green light illuminated.
NOTE: If the synchroscope for ACB 135574 was not energized the breaker
remains OPEN, green light on.
12. Decrease load on Diesel Generator to At panel 21111 -P652, DIESEL
400-500 kW with 400-500 kWar. GEN B, VOLT ADJUST and
SPEED ADJUST switches used
as necessary to reduce load on
Diesel to 400-500 kW while
maintaining 400-500 kVar.
(** Indicates critical step)
LR-JP-27.11-14
Page 7 of 7
dowuri4
(ogJ1j STANDA j 4YNA
RESPONSE CUE: ACB 135570, red light illuminated.
14. Confirm Diesel Generator output At panel 2H1 1-P652, the operator
breaker green light is illuminated. IDENTIFIES that the DIESEL
GEN B, EMERGENCY SUPPLY
ACB 135570 green light is
illuminated.
15. Turn off the "2F" Bus synchronizing At panel 2H11-P652, SSW ACB
switch. 135574 is in OFF.
PROMPT: WHEN the operator addresses securing of the Diesel Generator, as the Shift
Supervisor, INFORM the operator that another operator will shutdown the
Diesel Generator.
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
START A RECIRC MG SET FROM THE CONTROL ROOM WITH FAILURE
OF PUMP SEALS.
R. L. SMITH LR-JP-25042-00 38.0 Minutes
SOUTHERN ira
COMPANY
Energy to Serve Your World'M
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-25042
01 ý10/07/02 jnitial development. RLS RSG
01
__________
_________
___
10/07/02
_________
________
__
Initialdevelopment.
1.ija I
_________ __________
_________
I 4 1
I I ii
I I I I~
II t t
I. I 4 1*
L I I t
I. I i t
I Ii
III I
I I
I I I I
_______ I I
_______ I I I I
_______ _______ I t I*
I I t1
__ _ _ I I t1
1. I I
__ __ _I I
I I
___ _ I_ I
LR-JP-25042-00
Page 1 of 7
UNIT 1 0 UNIT 2 (X)
START A RECIRC MG SET FROM THE CONTROL
ROOM WITH FAILURE OF PUMP SEALS.
pugý ý11 I ý LR-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.
004.002, 004.003
WOMEN,R1111 001MEN 004.002.A, 004.003A
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.50, 2.79
SRO 3.22, 3.15
K/A CATALOG NUMBER: 202001A401, 202001A210
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.30, 3.50
SRO 3.10, 3.90
OPERATOR APPLICABILITY: Reactor Operator (RO)
APPROXIMATE COMPLETION TIME: 38.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
LR-JP-25042-00
Page 2 of 7
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.
VALUE RATE TIME
mfB31 39A 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 Recire 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
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. Circulating oil pumps A1, A2 (B 1, B2) are running.
4. Reactor Recirc Pump 2B(A) is still in operation.
5. Other operators are performing ATTACHMENT 5 through step 7.1.
INITIATING CUES:
Start 2A(B) Recirc Pump, using the normal startup section 7.1.2 of
LR-JP-25042-00
Page 4 of 7
SUR
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 2B3 1-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 2B31-PO03A(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, 2B31-F023A(B) is open. SUCTION VLV,
2B31-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)
LR-JP-25042-00
Page 5 of 7
Verify Master Recirc Flow Controller, At panel 2H11-P603, the
2B31-R620, is in manual. MASTER RECIRC FLOW
CONTROLLER, 2B31--R620, is
in MAN.
At panel 2H1 1-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%.
RESPONSE CUE: Reactor Recirc Pump 2A(B) Speed Control, 2B31-R621A(B), is not
at 44%.
6. Confirm annunciator 602-126(226) At panel 2H1 1-P602, operator
FLUID DRIVE A(B) SCOOP TUBE VERIFIES 602-126(226) FLUID
LOCK, clear. DRIVE A(B) SCOOP TUBE
LOCK is CLEAR, window is
extinguished.
7. Verify RWL is greater than +32 At panel 2H11-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.
I T
Confirm or start Reactor Recirc 2A(B) At panel 2H1 1-P657, the RX
MG Set Room Cooler RECIRC 2A(B) MG SET ROOM
2T41-B012(B013). COOLER, 2T41-B012(B013), is
RUNNING, red light illuminated.
At panel 2H11-P602, PUMP
DISCH VLV 2B3 1-F031A(B) is
CLOSED, green light
illuminated.
RESPONSE CUE: Discharge valve, 2B31 -F031A(B), red light illuminated.
(** Indicates critical step)
LR-JP-25042-00
Page 6 of 7
STE 6i4~t~S
l
rki0
- *At panel 2H11I-P602, RX
SRECIRC PUMP MG SET,
- [ 2B31-S001A(B) STARTED, red
S~light illuminated.
RESPONSE CUE: Reactor Recirc Pump MG Set, 2B31-SO01A(B), green light
illuminated.
11. Complete remainder of Attachmnent 5. Attachment 5 has been completed
.ethrough 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
mfB31l45A, "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 2H11 -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 2H11 -P645, monitor
determine that Reactor coolant is 2D 11-R630, FPM recorder, to
leaking from the seals, at monitor DETERMINE if primary coolant
2D1 I-R630, fission Products recorder, is leaking from the seals by
observing an increasing trend.
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)
LR-JP-25042-00
Page 7 of 7
ST "' - I. ilA AJ;P1IY1ý
15. Confirm an increase in Drywell At panel 2H1 11-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-SO0lA, MG Set At panel 2H11-P602, Rx Recirc
lA. MG Set 2B31-S001A is SHUT
DOWN, green light illuminated.
RESPONSE CUE: Reactor Recirc Pump MG Set, 2B31-SO01A(B), red light
illuminated.
At panel 2H1 l-P602, CLOSE Rx
Recirc MG Set 2B331-S001A:
Discharge Valve 2B31-F031A,
and Suction Valve 2B31-F023A,
green lights illuminated.
RESPONSE CUE: Discharge Valve 2B31-F0031A or Suction Valve 2B31-F023A, red
light illuminated.
PROMPT: WHEN addressed by the operator, to CLOSE seal purge valve 2B31
F0008A, INFORM the operator that another operator will be dispatched to
CLOSE the seal purge valve 2B31-F008A.
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
SHIFT RECIRC CONTROL FROM INDIVIDUAL TO MASTER CONTROL
N/R R. A. BELCHER 02/22/2002
SOUTHERN Am'
COMPANY
Energy to Serve Your World'M
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-04.06
01 06/09/89 General revision and format change WGW RSG I
02 08/03/89 Procedure revision JEM DHG
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 DHG
06 05/20/91 General/procedure revision JLA DHG
07 08/21/92 General revision and format change WMM SCB
08 07/08/93 Incorporate new controllers and word processor MMG DHG
Ichange
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 RAB
LR-JP-04.06-16
Page 1 of 6
-.
UNIT 1 (X) UNIT 2 (X)
SHIFT RECIRC CONTROL FROM INDIVIDUAL TO
-The
SMASTER 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.
-004.006
I004.006.A
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.20
SRO 3.19
K/A CATALOG NUMBER: 202001A401
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.70
SRO 3.70
OPERATOR APPLICABILITY: Reactor Operator (RO)
3400-OPS-001-2S Rev 34
Ed 6
34SO-B31-001-2S Rev 29
APPROXIMATE COMPLETION TIME: 11.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
LR-JP-04.06-16
Page 2 of 9
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
2
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Recirc Pumps "2A" and "2B" 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 "2B" in Master Manual Control.
LR-JP-04.06-16
Page 4 of 6
cfT
START
TIME:
1. Operator identifies the procedure Operator has identified the correct
needed to perform the task. procedure as 34SO-B31-001-2S.
(Section 7.1.4)
2. Operator reviews the procedure's Operator has reviewed the
precautions and limitations, precautions and limitations.
3. Confirm that Master Recirc Flow At panel 2H 11-P603, the operator
Controller is in Manual. VERIFIES that the MASTER
RECIRC FLOW CONTROL,
2B31-R620, is in MANUAL,
amber "M" pushbutton
illuminated.
4. Confirm feedwater flow is At panel 2H11 -P603, the operator
>2 X 106 lbm/hr. VERIFIES feedwater flow as
indicated by STM FLOW/FW
FLOW recorder, 2C32-R607, is
>2 X 106 Ibm/hr.
At panel 2H11-P603, the operator
ADJUSTS the MASTER
RECIRC FLOW CONTROL's
manual output lever to match the
input and output signal on Recirc
Pump A SPEED CONTROL,
2B31-R621A. The individual
controller input and output signals
are compared by depressing the
PF key and reading the controller
output (PF lamp lit), then
depressing the PF key so that the
input to the controller is displayed
(PF lamp is off) (+/- .1%).
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)
LR-JP-04.06-16
Page 5 of 6
M"
At panel 2H 11 -P602, the operator
PLACES Reeirc Pump A SPEED
CONTROL, 2B31-R621A, in
AUTO, the "A" green pushbutton
illuminated.
RESPONSE CUE: Speed Controller, 2B31-R621A, Manual "M" amber light
illuminated.
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.
At panel 2H 11 -P603, the operator
ADJUSTS the MASTER
RECIRC FLOW CONTROL's
manual output lever to match the
input and output signals on the
Recirc Pump B SPEED
CONTROL, 2B31-R621B. The
individual controller input and
output signals are compared by
depressing the PF key and
reading the controller output (PF
lamp lit), then depressing the PF
key so that the input to the
controller is displayed (PF lamp
is off). (+/ .%)
RESPONSE CUE: N/A
At panel 2H11I-P602, the operator
PLACES Recirc Pump 2B
SPEED CONTROL,
21331-R621 B, in AUTO, the "X"
green pushbutton illuminated.
RESPONSE CUE: Speed Controller, 2B31-R621B, Manual "M" amber light
illuminated.
(** Indicates critical step)
LR-JP-04.06-16
Page 6 of 6
I i0 I I
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.
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
TRANSFER THE MODE SWITCH TO STARTUP/HOT STANDBY, WITH AN
APRM AT 15% POWER
R. L. SMITH LR-JP-10.19-00 10.0 Minutes
T. F. PHILLIPS R. S. GRANTHAM 10/7/02
SOUTHERN iA
COMPANY
Energy to Serve Your World M
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page l of t
FORM TITLE: TRAINING MATERIAL REVISION SHEET
Program/Course Code: OPERATIONS TRAINING Media Number: LR-JP-10.19
01 10/7/02 Initial development. RLS RSG
I___ I__ I I__ I___
LR-JP-10.19-00
Page 1 of 5
UNIT 1 0 UNIT 2 (X)
U-wESTARTUP/HOT TRANSFER THE MODE SWITCH TO
POWER
STANDBY, WITH APRM AT 15%
-LR-JP-10.019
NThe task shall be completed when the APRM is bypassed and the
Mode switch is transferred to Startup/Hot Standby.
-010.019
010.019A
PLANT HATCH JTA IMPORTANCE RATING:
K/A CATALOG NUMBER: G2.1.23
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.9
SRO 4.0
OPERATOR APPLICABILITY: Reactor Operator (RO)
N/A 34GO-OPS-013-2 Rev 26.4
N/A 34GO-OPS-013-2
(current revisions)
APPROXIMATE COMPLETION TIME: 10 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
LR-JP- 10.19-00
Page 2 of 5
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 ACT.
VALUE RATE TIME
mfC51 19A LPRM UPACALE 'B' LEVEL 20.29 0000
mf60323379 LPRM UPSCALE ALARM OFF 0000
4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.
5. ESTIMATED Simulator SETUP TIME: 10 Minutes
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Reactor Shutdown is in progress; steps through 7.3.16 of
34GO-OPS-013-2 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.
LR-JP- 10-019-00
Page 4 of 5
START
TIME:
1. Operator reviews the procedure's Operator has reviewed the
Iprecautions 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 2H1 1-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 2H1-1-P603, the operator
AND/OR SRMs are bypassed. VERIFIES that IRMs AND
SRMs INOP lights are
extinguished.
RESPONSE CUE: N/A
At panel 2H1 1-P603, the operator
VERIFIES that all APRMs are
less than 11%, and informs the SS
that the 2B APRM is indicating
15% power.
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.
(** Indicates critical step)
LR-JP-10-019-00
Page 5 of 5
yLR 06ThMN-p
1
>At panel 2H11-P603, the operator
PLACES the APRM 2B in
Bypass.
RESPONSE CUE: APRM 2B not in Bypass.
6. Confirm all rod blocks clear. At panel 2H1 1-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.
i i *At panel 2H11-P603, the operator
[ o places the Mode Switch into
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
9. Confirms the Annunciator "MSIV At panel 2H1 1-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 2H11-P609/P611. 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
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
Southern Nuclear A
E. I. Hatch Nuclear Plant
Operations Training JPM
TITLE
PREPARE EQUIPMENT CLEARANCE AND HOLD TAGS
AUTHOR MEDIA NUMBER TIME
R. L. SMITH LR-JP-25019-03 20.0 MINUTES
RECOMMENDED BY APPROVED BY DATE
T. F. PHILLIPS R. S. GRANTHAM 10/07/02
SOUTHERN fl
4k
COMPANY
Energy to Serve Your World" M
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of 1
FORM TITLE:
TRAINING MATERIAL REVISION SHEET
Program/Course Code: LICENSE REQUAL Media Number: LR-JP-25019
Author's Supv's
Rev. No. Date Reason for Revision Initials Initials
01 10/1/92 General revision and format change WMM RSG
02 07/14/94 General revision, add 2 valves to required tag out, word RAB SMC
processor change
03 10/7/02 Format change removed Record of Completion sheet. RLS RSG
LR-JP-25019-03
Page 1 of 4
FACILITY: PLANT E. I. HATCH UNIT 1 ( ) UNIT 2 (X)
PREPARE EQUIPMENT CLEARANCE AND HOLD
TAGS
[AR~l
wlW9 10 $ DMB wmm LR-JP-25019-03
The task shall be completed when the operator has generated a
MIMME !**¸*i! M clearance for CRD Suction Filter 2A per 30AC-OPS-001-0S.
RIA, *300.016
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.20
SRO 2.74
K/A CATALOG NUMBER: 294001A107
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.00
SRO 3.70
OPERATOR APPLICABILITY: Reactor Operator (RO)
T--. RE, Procedure: 30AC-OPS-001-OS Rev23.1
l Plant Drawin H-26007
Procedure: 30AC-OPS-001-OS (current revision)
Equipment Clearance Sheet (current revision)
Danger Tags
Plant Drawing H-26007
APPROXIMATE COMPLETION TIME: 20.0 Minutes
SIMULATOR SETUP: N/A
Page 2 of 4
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The CRD pump, 2C11-C001A, 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 1 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.
LR-JP-25019-03
Page 3 of 4
START
TIME:
NOTE: Steps of this JPM may be completed in any order.
1.1 Operator identifies the Operator has identified the correct
procedure needed to perform procedure as 30AC-OPS-001-OS.
the task.
2.1 Operator reviews the Operator has reviewed the
procedure's precautions and precautions and limitations.
limitations.
3. Operator identifies the Operator has identified the
materials which are required. required materials and where to
obtain them.
Plant Drawing H26007
3480-C 11-005-2S, 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.
The operator has determined the
following must be tagged:
2C01 -Fl 14A
2C011-F 144A I I
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25019-03
Page 4 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
PERFORM A MANUAL STARTUP OF HPCI AND MAINTAIN REACTOR
WATER LEVEL IN BAND
RL.SIHLR-LP-25050-00 6.0 Minutes
T. F. PHILLIPS R. S. GRANTHAM 10/07/02
SOUTHERN 4
COMPANY
Energy to Serve Your World'
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
0 10/07/02 Initial development RLS RSG
________________ I ______________ I I ______________ I
I I t I*
I I t 1*
I I t t
I I t
I I I t
I I I t
I I i I
I I I t
___ __ __I __
LR-LP-25050-00
Page 1 of 6
UNIT I ( ) UNIT 2 (X)
-PERFORM MAINTAIN REACTOR WATER LEVEL IN BAND
-The
A MANUAL STARTUP OF HPCI AND
-LR-LP-25050-00
task shall be completed when the HPCI System is injecting
to the Reactor with turbine speed greater than 2000 rpm per
34SO-E41-001-2S, and RWL is controlled in band.
-005.002
0005.002.A
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.00
SRO 3.00
K/A CATALOG NUMBER: 206000G009
K/A CATALOG JTA IMPORTANCE RATING:
RO 4.30
SRO 4.00
OPERATOR APPLICABILITY: Reactor Operator (RO)
34SO-E41-001-2S (current revision)
APPROXIMATE COMPLETION TIME: 3.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
LR-LP-25050-00
Page 2 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 2D Fault 00000
mfE4l1235A 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 run 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
2
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The HPCI System is in Standby.
2. A loss of the Feedwater pumps has occurred.
3. 31EO-EOP-010-2S (RC) is in progress.
4. RWL is < -80 inches and decreasing.
5. HPCI failed to autostart.
6. HPCI is required to maintain RWL.
INITIATING CUES:
Start HPCI manually and inject into the Reactor and maintain Reactor
Water Level +3" to +50".
LR-LP-25050-00
Page 4 of 6
I~~~~ B ibd 41us~
ITCOM311
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.
At panel 2H 11 -P601, LUBE OIL
OPEN, red light illuminated.
RESPONSE CUE: Valve, 2E41-F059, green light illuminated.
2. Start HPCI Barometric Condenser At panel 2H I1-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.
RESPONSE CUE: Valve, 2E41-F001, green light illuminated.
NOTE: Valve 2E41-F001 is not required to be full open prior to proceeding to
following steps.
RESPONSE CUE: HPCI Auxiliary Oil Pump, green light illuminated.
(** Indicates critical step)
LR-LP-25050-00
Page 5 of 6
[1 F98
OH AT
AIL 11
Sa> 'A At panel 2Hl l-P601, PUMP
is OPEN, red light illuminated.
RESPONSE CUE: Valve, 2E41-F006, green light illuminated.
6. Confirm the following valves are At panel 2H1 1-P601, the
open: following valves are OPEN, red
Turbine Control Valve light illuminated:
Turbine Stop Valve TURBINE CONTROL VLV
TURBINE STOP VLV
7. Confirm HPCI Turbine comes up to At panel 2H 11 -P60 1, operator
speed as directed by the Turbine Flow VERIFIES HPCI turbine speed is
Controller, 2E41-R612. controlled by FLOW CONTROL,
8. Verify the Minimum Flow Valve, At panel 2H1 l-P601, the operator
2E41-F012, closes when flow is VERIFIES MIN FLOW VLV,
greater than 790 gpm. 2E41-F012 is CLOSED when
HPCI pump flow is greater than
790 gpm, green light illuminated.
At panel 2H1I-P601, the operator
MAINTAINS reactor water level
in band by one of the following
methods:
Decreases the set point of the
HPCI Flow controller
2E41-R612, or
Takes manual control of the
HPCI Flow controller 2E4 1-R612
and decreases flow, or
Shuts down HPCI by decreasing
Speed to -2000 RPM with the
Flow Controller 2E41-R612, and
then Trips HPCI with manual trip
PB, and then shuts the HPCI
steam supply valve 2E41-F001.
NOTE: If HPCI is started PER THE PLACARD, the following steps may be
omitted.
(** Indicates critical step)
LR-LP-25050-00
Page 6 of 6
MIT
0 t D
won
'P.R0
10. Confirm the following valves are At panel 2H11-P602, the operator
closed: has CONFIRMED the following
valves are CLOSED, green light
illuminated:
2E41-F028, STEAM LINE
2E41-F026 2E41-F025, BAROM CNDSR
DISCH TO CRW
2E41-F029, STEAM LINE
DRAIN VLV
2E41-F026, BAROM CNDSR
DISCH TO CRW
11. Confirm Barometric Condenser At panel 2H1 1-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.
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.
(** Indicates critical step)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
CROSSTIE RHR SERVICE WATER WITH A FAILURE
ýwmwý.= NMI RamgOF THE SECOND
CROSSTIE RHR SERVICE WATER WITH A FAILURE OF THE SECOND
RHRSW PUMP TO START
R. L. SMITH LR-JP-25044-00 15.0 Minutes
T. F. PHIPLLIPS R. S. GRANTHAM 10/07/02
SOUTHERN Na
COMPANY
Energy to Serve Your World'
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
LR-JP-25044-00
Page 1 of 7
UNIT 1 0 UNIT 2 (X)
-CROSSTIE FAILURE OF
RHR SERVICE WATER WITH A
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
-034.008
034.008.0
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.29
SRO Not Available
K/A CATALOG NUMBER: 219000A215
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.30
SRO 3.40
OPERATOR APPLICABILITY: Reactor Operator (RO)
N/A I 34SO-E11-010-2S Rev29
I n ~. R. I ft61"1V
101 Ut'A 2 U 1 1F*"i 11
N/A 34SO-E1 1-U1U-2S
(current revision)
APPROXIMATE COMPLETION TIME: 15.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
LR-JP-25044-00
Page 2 of 7
I I4X
SIMULATOR SETUP
Simulator Initial Conditions:
1. RESET the Simulator to IC #128 and leave in FREEZE.
2. INSERT the following MALFUNCTIONS:
mfEl l_120B RHRSW 2B Pump Trip 00000
inEl11_120D RHRSW 2D Pump Trip 00000
mfEl l_120A RHRSW 2A Pump Trip 99999
mfEl11120C RHRSW 2C Pump Trip 99999
3. INSERT the following ORS OVERRIDES:
E11-C001B A RHR Service Water Pmp lB OFF 00000
E11-C001BB RHR Service Water Pmrp 1B OFF 00000
Ell-COODA RHR Service Water Prmp 1D OFF 00000
Ell-CO01DB RHR Service Water Pmp 1D OFF 00000
Eli-F028ADI P RHR A Torus Spray/Test Vlv CLOSE 00000
Ell-F028AA L RHR A Torus Spray/Test Vlv OFF 00000
Ell-F028AB L RHR A Torus Spray/Test Vlv OFF 00000
4. PLACE DANGER TAGS on the following equipment:
2E1l-FO28A Torus Spray Or Test Vlv 2El 1-F028A CLOSE
2EIlI-CO01B Service Water Pump 2El l-C001B OFF
2El 1-C001D Service Water Pump 2El 1-COOlD OFF
5. ESTIMATED Simulator SETUP TIME: 10 Minutes
(** Indicates critical step)
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. 2El 1-F028A is tagged closed for corrective maintenance.
INITIATING CUES:
Crosstie the "A" loop of RHR Service Water to the "B" loop of RHR
LR-JP-25044-00
Page 4 of 7
pr V AIX
01
Rpm
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 1-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.
At panel 2H11 -P60 1, operator
opens SERV WTR CROSSTIE
VLV 2E lI -F1Il19A, red light
illuminated.
RESPONSE CUE: Valve 2El1 -F1 19A, green light illuminated, red light extinguished.
SERV WTR CROSSTIE S~opens
VLV 2E II-F 11913, red light
illuminated.
RESPONSE CUE: Valve 2El11-F 11913, green light illuminated, red light extinguished.
5. Operator places the Interlock Override At panel 2H1 1-P601, the
valve 2E1 1-F068B Keylock Switch in Operator PLACES the Interlock
the Override position. Override Valve 2E1 1-F068B
Keylock Switch in the
OVERRIDE position.
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25044-00
Page 5 of 7
NOTE: Using the Override Switch for 2El 1-F068A is not required, but if
performed, should be noted. Overriding 2E1 1-F068A will not affect the
performance of the JPM.
6. Set the Heat Exchanger B Differential At panel 2H11 -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 2H1 1-P601, the operator
2E 1-F068A(B) OPENS (RED light CONFIRMS that 2E1 17068B
ILLUMINATES) Opens red light illuminates, and
RHR HX A(B) DIFF PRESS LOW LOW Annunciator illuminates.
annunciator ILLUMINATES
NOTE: RHRSW Pump A or C may be started first. Therefore Steps 8 and 12 may
be interchanged.
' At panel 2H11 -P601, operator
starts SERVICE WATER PUMP
2El 1-CO01A.
RESPONSE CUE: SERVICE WATER PUMP IA, green light illuminated, red light
extinguished.
8. Operator places the Interlock Override At panel 2H1 1-P601, the
valve 2E1 1-F068B Keylock Switch in Operator PLACES the
the Normal position. INTERLOCK OVERRIDE VLV
2E1 1-F068B Keylock Switch in
the NORMAL position.
At panel 2H11 -P601, operator has
adjusted HX B DIFF PRESS
CONTROL VLV F068B
controller, 2E1 1-R600B, to obtain
desired flow rate, of about
4400gpm.
Pressure limit for RHR Service
Water is less than 450 psi.
(** Indicates critical step)
LR-JP-25044-00
Page 6 of 7
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.
10. Depress the RHR Service Water Lube At panel 2HI l-P601, operator has
Valves push-button on 2H1 1-P601. depressed the RHR SERVICE
WATER LUBE VALVES push
button.
11. Adjust Diff Press Control Vlv At panel 2H 11 -P601, operator has
2E 1 -F0681 to obtain desired adjusted HX B DIFF PRESS
RHRSW flow rate, then open CONTROL VLV F068B
2E 1 -F068B an additional 5%. controller, 2E1 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 1l-R619A and/or SERV WATER FLOW indicator 2E 11-R602A.
Pump discharge pressure will be monitored on DIV I PRESSURE
indicator 2E1 1-R650A.
- At panel 2H11 -P601, operator
starts SERVICE WATER PUMP
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 2H1 l-P601, the operator
RHRSW PUMP 2C TRIP. enters the ARP for RHRSW
PUMP 2C TRIP, NO actions
apply.
(** Indicates critical step)
LR-JP-25044-00
Page 7 of 7
1A
At panel 2H1 l-P601, operator has
adjusted HX B DIFF PRESS
CONTROL VLV F068B
controller, 2E1 1-R600B, to obtain
desired flow rate.
Flow rate limit is *4400 gpm for
one pump.
Pressure limit for RHR Service
Water is less than 450 psi.
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.
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
DETERMINE STAY TIMES TO TAKE A PIECE OF EQUIPMENT OOS
R. L. SMITH LR-JP-25049-00 20 Minutes
T. F. PHILLIPS R. S. GRANTHAM 1/70
SOUTHERNA4
COMPANY
Energy to Serve Your World'"
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of t
FORM TITLE: TRAINING MATERIAL REVISION SHEET
I
Program/Course Code: OPERATIONS TRAINING Media Number: LR-JP-25049
1
0 10/07/02 Initial Development RLS RSG
___ I__ I I__ ___
LR-JP-25049-00
Page 2 of 6
UNIT 1 0 UNIT 2 (X)
-IEDETERMINE
-LR-JP-25049-00
EQUIPMENT OOS
STAY TIMES TO TAKE A PIECE OF
This task will be completed when stay times are determined by
the operator, based on current accumulated dose for the year and
dose that would be received while in a radiation field.
PLANT HATCH JTA IMPORTANCE RATING:
RO N/A
SRO N/A
K/A CATALOG NUMBER: G2.3.2
K/A CATALOG JTA IMPORTANCE RATING:
RO 2.5
SRO 2.9
OPERATOR APPLICABILITY: Reactor Operator (RO)
IE III=
APPROXIMATE COMPLETION TIME: 20 Minutes
SIMULATOR SETUP: N/A
NOTE: First section is for RO Candidates and the second section is for SRO candidates.
Part 1
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The 4 th 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
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.
LR-JP-25049-00
Page 4 of 6
START
TIME:
PROMPT: AT this time give the operator the copy survey map of the Unit I Condenser
Bay.
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
Using the Survey Map the
operator will DETERMINE the
max general Dose Rate for the
area to be 250 mr/hr.
RESPONSE CUE: N/A
Using the initial Dose information
the operator calculates dose
margin left for the year is 620 mr
(1000 mr-380 mr = 620mr).
RESPONSE CUE: N/A
Using his remaining dose margin
and highest dose rate for the area,
CALCULATES his Stay Time to
be 2.48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 28.8
minutes.
(620/250/hr = 2.48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 2
hours and 28.8 minutes).
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
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
Part 2
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The 4 th 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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.
LR-JP-25049-00
Page 6 of 6
START
TIME:
PROMPT: AT this time give the operator the copy of the survey map of the Unit 2
Condenser Bay 164' cl.
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.
RESPONSE CUE: N/A
Using the Survey Map the
operator will DETERMINES the
max general Dose Rate for the
area to be 250 mr/hr.
RESPONSE CUE: N/A
Using the initial Dose information
the operator calculates dose
margin left for the year as
follows:
Operator #1:
1000 mr-280 mr = 720 mr
Operator #2:
1000 mr-370 mr = 630 mr
Operator #3:
1000 mr-770 mr = 230 mr
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25049-00
Page 7 of 6
Usiandhis rema5inng dose margin
and highest dose rate for the area,
CALCULATE the Stay Times for
each operator:
Operator #1
720 mr/250 mr/hr = 2.88 hrs or 2
hours and 52.8 minutes.
Operator #2
630 mr/250 mr/hr = 2.52 hrs or 2
hours and 31.2 minutes.
Operator #3
230 mr/250 mr/hr = .92 hrs or
RESPONSE CUE: N/A
Mu ýR "IýIlpclorUsing Stay Times that were just
lm ocalculated by the operator, it is
DETERMINE that operator #3
can not be use for this task due to
the operator Dose Limit being
exceeded.
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
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
ES-301 Administrative Topics Outline Form ES-301-1 (R8, SI)
Facility: Hatch Date of Examination: 10/21-25/02
Examination Level (circle one): RO / SRO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
A.1 Conduct of Use of Overtime Guidelines. K/A 2.1.3 3.0/3.4 (NEW)
Operations
Determine if SBLC tank meets requirements of Tech Specs per
Conduct of
table 3.1.7-1 and Table 3.1.7-2. K/A 2.1.25 2.8/3.1 (NEW)
Operations
A.2 Equipment Prepare Equipment Clearance and Hold Tags. JPM 25019
Control K/A 2.2.13, 3.6/3.8.
A.3 I Radiation Determine exposure limits for equipment OOS. K/A 2.3.2
Control 2.5/2.9 (NEW)
During an Emergency, Perform a Prompt Offsite Dose
A.4 Emergency
Assessment Calculation (JPM 25305) K/A 2.4.39 3.3/3.1
Drnnadi racIPIn
I I dre/Pa
<>
Form ES-301-1 (R8, S1)
[z-1= ) Administrative Topics Outline Fr S31l(8 I
Facility: Hatch Date of Examination: 10/21-25/02
Examination Level (circle one): RO / SRO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
A.1 Conduct of Use of Overtime Guidelines. K/A 2.1.3 3.0/3.4 (NEW)
Operations
Conduct of APRM Adjustment to Core Thermal Power. K/A 2.1.19 3.0/3.0
Operations (NEW)
A.2 Equipment Review 34SV-C11-002-2S, Scram Discharge Volume Isolation
Control Valve Timing and Closure Test K/A 2.1.33 3.4/4.0 (NEW)
A.3 i Radiation Determine exposure limits for equipment OOS. K/A 2.3.2
Control 2.5/2.9 (NEW)
A.4 Emergency During an Emergency, Perform a Prompt Offsite Dose
Procedures/Plan Assessment Calculation and Perform EAL Classification.
(JPM 25305) K/A 2.4.39 3.3/3.1
I I -
ES-301 Administrative Topics Outline Form ES-301-1 (R8, SI)
Facility: Hatch Date of Examination: 10/16-24/02
Examination Level (circle one): RO / SRO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
A.1 Conduct of Use of Overtime Guidelines. K/A 2.1.3 3.0/3.4 (NEW)
Operations
Conduct of Determine if SBLC tank meets requirements of Tech Specs per
Operations table 3.1.7-1 and Table 3.1.7-2. K/A 2.1.25 2.8/3.1 (NEW)
A.2 Equipment Prepare Equipment Clearance and Hold Tags. JPM 25019
Control K/A 2.2.13, 3.6/3.8.
A.3 Radiation Determine exposure limits for equipment OOS. K/A 2.3.2
Control 2.5/2.9 (NEW)
A.4 Emergency During an Emergency, Perform a Prompt Offsite Dose
Procedures/Plan Assessment Calculation (JPM 25305) K/A 2.4.39 3.3/3.1
<-V
ES-301 Administrative Topics Outline Form ES-301-1 (R8, S1)
Facility: Hatch Date of Examination: 10/16-24/02
Examination Level (circle one): RO / SRO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
A.1 Conduct of Use of Overtime Guidelines. K/A 2.1.3 3.0/3.4 (NEW)
Operations
Conduct of IRM Alternate Power Checks prior to taking the Mode Switch to
Operations Run. K/A 2.1.23 3.9/4.0 (NEW)
A.2 Equipment Review 34SV-C11-002-2S, Scram Discharge Volume Isolation
Control Valve Timing and Closure Test K/A 2.1.33 3.4/4.0 (NEW)
A.3 Radiation Determine exposure limits for equipment OOS. K/A 2.3.2
Control 2.5/2.9 (NEW)
A.4 Emergency During an Emergency, with information provided, Perform a
Procedures/Plan PAR. (JPM 25205) K/A 2.4.44 2.4/4.0
ES-301 Control Room Systems Form ES-301-2 (R8, Sl)
and Facility Walk-Through Test Outline
Facility: HATCH Date of Examination: October 2002
Exam Level (circle one): .O_(SRO
D*_S _(. Operating Test No.:
B.1 Control Room Systems
System / JPM Title Type Safety
Code* Function
a. Recirculation System / Shift Recirc Control from Individual D,S 7u
to Master Control. (4.06)
b. Containment / Initiate Evergency Torus Venting using the D,S 5
Emergency Vent Path. (13.53)
c. HPCI / Shutdown HPCI (Normal) (5.03) D,S 2
d. Recirculation System / Start a Recirc MG Set from the M,A,S 4
Control Room with Failure of Pump Seal. (4.02)
N,L,A,S 1u
e. Reactor Protection / Transfer the Mode Switch to S/U with
one APRM reading high.
f. RHRSW / Crosstie the RHR Service Water with a failure of M,S,A 8u
the second RHRSW pump to start. (34.08)
g. 4160 VAC / Transfer An Emergency 4160 VAC Bus From D,S 6
the Emergency to Normal Power Supply. (27.11)
B.2 Facility Walk-Through
a. RCIC / From the Remote Shutdown Panel, Start RCIC for D,R 2U
Injection into the Reactor. (39.16)
b. SBLC / From Outside the Control Room, Inject Boron M,A,R I
Using the SBLC System with Failure of "A" Pump to start.
(11.12)
c. Fire Protection / During a Loss of Air, Isolate the Fire D 8u
Protection Sprinklers. (36.13)
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate path, (C)ontrol
room, (S)imulator, (L)ow-Power, (R)CA