ML023400249
| ML023400249 | |
| 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 50-321/02-301, 50-366/02-301 | |
| Download: ML023400249 (152) | |
See also: IR 05000321/2002301
Text
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Final Submittal
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)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations TrainingJPM
TITLE 7 7
DETERMINING OVERTIME AVAILABILITY
,AUTHO MEDI ~NMBER TiM
LR-JP-25045-00 15.0 Minutes
R. L. SMITH
RECOMMNDD BY 'PPOEDB DT
SOUTHERN
Ak
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 1
UNIT 1 (X) UNIT 2 (X)
TASK TITLK DETERMINING OVERTIME AVAILABILITY
JPSNMBR
The task shall be complete when the operator has determined
which operators are available for overtime per
S,TASK NUMBER: 300.001
OBJECTIVE NUMBER: 300.001.J
PLANT HATCH JTA IMPORTANCE RATING:
RO Not Available
SRO Not Available
K/A CATALOG NUMBER: Generic K/A 2.14
"J' K/A CATALOG JTA IMPORTANCE RATING:
RO 3.0
SRO 3.40
OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)
GZENE L:REFERENCES:,A rini t t&
10AC-MGR-020-OS Rev 0
Unit 1 or 2 Tech Specs, Section 5.2.2.e
O (current revision)
I Unit 1or 2 Tech Specs
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 3
STEP] PROMNE~?&w~ i~3/4A, >1 <COMMENTSY
STUST
4Y,;,,` <2
START
TIME:
PROMPT: AT this time, GIVE the operator the attached operator work history.
a I
Operator identifies the procedure Operator has obtained procedure
needed to perform the task. 10AC-MGR-020-OS, or Unit 1 or
2 Tech Specs
I1 -t
DETERMINES that Operator #1
WILL violate the overtime limits.
(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
>72 hours during 7 period and
would require overtime
authorization)
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
SOperatof etermines that OV ato # DETERMINES that Operator #2
WILL latevertine , WILL violate the overtime limits.
'V,: :, t (>72 hours in a 7 day period and
,'>> would require overtime
%.... authorization)
RESPONSE CUE: N/A
- 5 ... 6dpirdetermines that P~?4ftt.
. DETERMINES that Operator #3
- IL~pate 6%~rtineettsftit~ioosý,,, WILL violate the overtime limits.
(>16 hours in a 24 hour2.777778e-4 days <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
>,I, authorization)
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25045-00
Page 4 of 4
~~~~~~~~( S'AT/UNSAT'SY,,
STEP STP
. . .
P~~itFORMANCE0
- **
IMNESE
- ** *
II'(OMENTS)
, *
SADIlD' %:*,**
K->
SOperato*deter~mines tihat jOpe'x #4 DETERMINES that Operator #4
"W NOTviolate overtime' WILL NOT violate any overtime
restrctl s .... .limits.
RESPONSE CUE: N/A
StDETERMINES that Operator #5
S ILovertime strieti WILL violate the overtime limits.
(>72 hours in a 7 day period and
would require overtime
authorization)
RESPONSE CUE: N/A
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
Y 1.6(Today)
Operator
- 1 0 0 13 11 14 10 14 10
Operator 14
- 2 0 3 10 12 12 12 8
Operator
- 3 0 0 12 12 12 8 8 15
Operator
- 4 0 8 12 10 10 8 10 12
Operator
4 12 10 10 10 12
- 5 0
Page 5 of 5
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
SBLC OPERABLE (ADMIN)
AUTHOR ETIME.
MEDA NUMBER.
R. L.SMITH LR-JP-25046-00 15 Minutes
REED BY ....... P R * BY ... . .. ...
DATE
RCOMME.NDD BYPPROVED
SOUTHERN
COMPANY
Energy to Serve Your World -
Program/Course Code: OPERATIONS TRAINING Media Number: LR-JP-25046
A
Re&sbn for Reyision
LR-JP-25046-00
Page 2 of 1
UNIT 1 (X) UNIT 2 (X)
STASK. TITLE:,. SBLC OPERABLE (ADMIN)
JPMiNUMBERý: LR-JP-25046-00
TASK !!i* The task is complete when the RO determines that SBLC is
,inoperable and Tech Spec entry to 3.1.7 is required.
TASK NUMBER: xxx.xxx
OBJECTIVE N.UMBEF 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)
GENERAL RWFERNCESU:
Unit 1 Tech Specs Unit 2 Tech Specs
REQUIRED M RIALS: Untý ..K .. U
Unit 1 Tech Specs Unit 1 Tech Specs
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 3
STEPDk STUNA
STEP 'VERORMANCESE tOMNS
START
TIME:
1. Operator enters Unit 1 Tech Specs Operator enters unit 1 Tech Specs
section 3.1.7. section 3.1.7
2. Plots location on the Unit 1 SBLC Using Unit 1 Tech Specs the
figures, 3.1.7-1 and 3.1.7-2. operator plots location on SBLC
figures 3.1.7-1 and 3.1.7-2.
- Deter iiids that Sodium ntabdat Using Unit 1 Tech Specs figure
is the p s b nl f s 3.1.7-1 the operator determines
Fi pe Pnitl T6h P that Sodium Pentaborate is
,,, outside the permissable region A
and B.
RESPONSE CUE: Plots the location in the permissible region of A or B.
4. Determines that Sodium Pentaborate Using Unit 1 Tech Specs figure
is inside the permissable region of 3.1.7-2 the operator determines
Figure 3.1.7-2 per Unit I Tech Specs. that Sodium Pentaborate is inside
the permissable region A.
RESPONSE CUE: Plots the location in the nonpermissible region of A or B.
Det e*mine LCO entry co indji"' Using Unit 1 Tech Specs the
Unit h Specs sect*on 3,I.7. , operator determines that a LCO
I X 7 exists for section 3.1.7.
RESPONSE CUE: No Tech Spec entry condition exists.
NOTE: The operator may identify applicable Unit 1 Tech Spec action statement,
but this is not critical or required.
END
TIME: -
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Chemistry has just added Sodium Pentaborate to the Unit 2 SBLC storage
tank.
2. Tank level is currently at 3000 gallons and solution temperature is at 95
degrees F.
3. Chemisrty has just reported that tank concentration level is 13.5%.
INITIATING CUES:
Determine the status of SBLC for Unit 2.
LR-JP-25046-00
Page 6 of 5
ISTE'P ?OMNCIE~..t~.) .ŽCMET
START
TIME:
1. Operator enters Unit 2 Tech Specs Operator enters Unit 2 Tech
section 3.1.7. Specs section 3.1.7
2. Plots location on the Unit 2 Tech Using Unit 2 Tech Specs the
Specs SBLC figures, 3.1.7-1 and operator plots location on SBLC
3.1.7-2. figures 3.1.7-1 and 3.1.7-2.
- 3 Deteri that Sodiurm inabbtat66 Using Unit 2 Tech Specs figure
is ud. prmissable #i n 3.1.7-1 the operator determines
Fig 3I 1 per Un S that Sodium Pentaborate is
outside the permissable region A
and B.
RESPONSE CUE: Plots the location in the permissible region of A or B.
4. Determines that Sodium Pentaborate Using Unit 2 Tech Specs figure
is inside the permissable region of 3.1.7-2 the operator determines
Figure 3.1.7-2 per Unit 2 TS. that Sodium Pentaborate is inside
the permissable region A.
RESPONSE CUE: Plots the location in the nonpermissible region of A or B.
4*5.: 13Deternin'a LCO entr condjtion fito Using Unit 2 Tech Specs the
Unit,2' Te hSpecs section 3.T7 operator determines that a LCO
I exists for section 3.1.7.
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 Training
'TITLE
IRM ALTERNATE POWER CHECKS PRIOR TO TAKING THE MODE
SWITCH TO RUN (ADMIN)
AUTHOR MEDIA NUBER I TIME
LR-JP-25047-00 15 Minutes
R. L. SMITH
RECOMMENDED BY ADATE
SOUTHERNU
COMPANY m
Energy to Serve Your World S.
IRM DATA
IRMS RANGE 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 10
UNIT 1
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Reactor Startup is in progress, and the crew is making preparations to
transfer the Reactor Mode Switch to Run.
2. The STA has adjusted all APRMs to 7% power.
3. All APRMs are currently reading 7% power.
INITIATING CUES:
Per Step 7.4.4.2 of 34GO-OPS-001-1, perform alternate power level
check per Attachment 10.
[ CONTINUOUS
1.0 Record the IRM readings below AND estimate reactor power using the following formulas:
For IRM Ranges 7 and 8: % 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 As % POWER
IRM E RANGE q READING % POWER __
IRM G RANGE READING Ag % POWER __
READING % POWER__
IRM B RANGE
IRM D RANGE READING if % POWER
IRM F RANGE READING II % POWER
IRM H RANGE READING LI % POWER
AVERAGE % POWER =
Confirm that each APRM reading is greater than the average * IRM Reactor
Power Value.
Calculations Verified
an
any APRM reading is NOT greater than the average IRM power, the STA will perform
I _F
to
evaluation of power level indication to ensure that the APRM readings are conservative
actual reactor power. The evaluation will be attached to this attachment.
OPS-1128 Rev. N/A G16.30
MGR-0009 Rev 4
Program/Course Code: OPERATIONS TRAINING Media Number: LR-JP-25047
Ron
LR-JP-25047-00
Page 2 of 1
UNIT 1 (X) UNIT 2 (X)
IRM ALTERNATE POWER CHECKS PRIOR TO
"TASK TTE
TAKING THE MODE SWITCH TO RUN (ADMIN)
LR-JP-25047-00
TASK STANDAD : The task is complete when the IRM alternate power checks are
performed and the SRO determines that Average % power
calculated is higher then current APRM power readings and a
STA evaluation of power level indication is required.
TASKýNUMBER:ý XXX.XXX
OBJECTIVE UMBER: 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 34GO-OPS-001-2 Rev 35.3
FREQUIRE AEIL:int ht
(Attachment 10) (Attachment 10)
APPROXIMATE COMPLETION TIME: 15 Minutes
.. SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
LR-JP-25047-00
Page 4 of 3
S. . . . ...... ... . ..... . .... (. E
. .'S.o: .... P... ....
"STANDAR.h. . . ... FAT/UNSAT
MM N N- 1
OMMENTS)
P[STEP.....
START
TIME: -____
1. The operator locates a copy of Either from the LAN computer or
34GO-OPS-001-1. MCR procedure books the
candidate obtains a copy of
PROMPT: AT this time give the operator the attached copy of UNIT 1
ATTACHMENT 10.
2 The operator identifies where he will At IH 11-P603, the operator
obtain IRM power and range identifies, IRM recorders where
information to record on attachment power information is obtained,
10. and locates the range switches to
determine what range each IRM
is on.
PROMPT: AT this time give the operator a copy of the IRM power and range
information.
3. The operator copies the IRM range Using the copy of
and power level data onto the copy of 34GO-OPS-001-1 Attachment 10,
34GO-OPS-001-1 Attachment 10. the data is recorded by operator.
RESPONSE CUE: Data is not recorded.
- 4. T I* The operator uses the recorded
to the.IRM'data... .. IRM data and MULTIPLIES it by
the correct constant (.353).
THEN adds them up and divides
them by 8.
RESPONSE CUE: Incorrect constant used or not added or not divided by 8.
PROMPT: IF the operator request that the Calculations be verified, THEN as another
operator perform verification but DO NOT correct any errors.
.Thejdpeikatbrdetei Using the Average % power, the
%/poweris greater than. pR$ ,.f1\Voperator DETERMINES that
]
settin. APRMs readings are NOT greater
than the Average IRM power.
RESPONSE CUE: The average 1KM1 /o is less man me I-RmlvI ,re ig.
(** Indicates critical step)
LR-JP-25047-00
Page 5 of 4
I TEP] r1ORMANP'E":', *[>TANDR~ t QMETY
- lthe peto[r 4eternnesran:e(aboo
- 6. The operator informs the SS that
ýof pb*f & by t 1 the STA must perform an
evaluation of power level
indication.
RESPONSE CUE: The operator does not request an SIA evaluation oi power level
indication.
(N I Lý c&JA>s
END
TIME: -
NOTE: The terminating cu shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
- Operator states the task is complete.
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 6
SPTEPER....CEStrP, STANDARD ..
I
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.
The operator perform the d t The operator uses the recorded
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.
'* 5p h ggtoV determinesThtet Ai0p Using the Average % power, the
% pdw~ri* greater than AP eVr' operator DETERMINES that
settingsI APRMs readings are NOT greater
than the Average IRM power.
RESPONSE CUE: The average IRKM %iis less tnan tne ArLSvi readUgs.
(** Indicates critical step)
LR-JP-25047-00
Page 8 of 7
STEPP TE "STANDERD> SAT/UNSAT
A(COMMENTS
jThe, opprato,&termn'es:"a a The operator informs the SS that
. fpodwer*lveliby the STXh s e the STA must perform an
. .. evaluation of power level
................. ..... indication.
RESPONSE CUE: The operator does not request an bS 1A evaluauon of power
ucw
indication.
END
TIME:.
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
SOUTHERN NUCLEAR
PAGE 10 OF 11
PLANT E.I. HATCH
DOUENT NUMBER:
34GO-OPS-001-2 REVIVER
DCMNPLANT STARTUPTLE NO:
35.2
- -* ATTACHMENT 10 ATTACHMENT
PAGE:
-48 OF 1
TITLE: IRM ALTERNATE POWER CHECK
CONTINUOUS
1.0 Record the IRM readings below AND estimate reactor power using one of the following formulas:
For IRM Ranges 7 AND 8:
% Power = (IRM Reading) x (.0353)
For IRM Ranges 9 AND 10:
% Power = (IRM Reading) x (.353)
IRM A RANGE READING "%POWER
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
AVERAGE % POWER =
Confirm that each APRM reading is greater than the average *
IRM Reactor Power Value.
Calculations Verified
an
to
evaluation of power level indication to ensure that the APRM readings are conservative
actual reactor power. The evaluation will be attached to this attachment.
OPS-1077 Rev. N/A G16.30
MGR-0009 Rev 4
- DO NOT GIVE THIS TO THE CANIDATE****
ANSWER
IRMS! 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 11
_ _ _ _
___ __ JP2OiS 2RO DOC _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
I--
4WA
Southern Nuclear AEVýdk
E. I. Hatch Nuclear Plant
Operations Training JPM
TITLE
PREPARE EQUIPMENT CLEARANCE AND HOLD TAGSPREPARE
EQUIPMENT CLEARANCE AND HOLD TAGS
AUTHOR MEDIA NUMBER TIME
R. L. SMITHR. L. SMITH LR-JP-25019-03LR-JP-25019-03 20.020.0 minutes
APPROVED BY DATE
RECOMMENDED BY
r. s. grantham 10/07/02
t. f. phillips
SOUTHERN LA
COMPANY
T
Energy to Serve Your World"
othKýl b:--JJ519A2 OP.-ge:
LR-JP-25019-03
Page 2 of 0
Program/Course Code: LICENSE REQUAL Media Number: LR-JP-25019
Page
[Tthy Kiobi-JP25b19A2RO1DOC
LR-JP-25019-03
Page 3 of 0
<* j>
S .. .......... .......... .".. .. Pa qe
oLR-019A2RO.DOC
LR-JP2093
FACILITY: PLANT E. I. HATCH UNIT 1 ( ) UNIT 2 (X)
g, ý
- .ý,,- , v- g I PREPARE EQUIPMENT CLEARANCE AND HOLD
HE
, .
0 1
giv TAGS
_)&N LR-JP-25019-03
,
F1ig'Awmgqff fL
-I
NM
The task shall be completed when the operator has generated a
clearance for CRD Suction Filter 2A per 30AC-OPS-001-0S.
r 300.016300.016
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.203.20
SRO 2.742.74
K/A CATALOG NUMBER: 294001A107294001AI07
K/A CATALOG JTA IMPORTANCE RATING:
-x
RO 3.003.00
SRO 3.703.70
OPERATOR APPLICABILITY: Reactor Operator (RO)
W F*R P-dure: 30AC-OPS-001-0S Rev 23.1
S;°t Plant Drawing H-26007
APPROXIMATE COMPLETION TIME: 20.0 Minutes
SIMULATOR SETUP: N/A
- JP25019A2RO.DOC
Kolb ..
Page
LR-JP-25019-03
Page 5 of 1
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The CRD pump, 2C11-COOlA, has tripped.
2. The SO sent to investigate the tripped CRD pump has reported the supply
breaker has tripped.
3. Maintenance has determined that the suction filter for the pump must be
replaced.
4. The Maintenance Foreman, Ron Buckner, is writing up the MWO and
estimates that the job will take about I day. Maintenance will require the
CRD Suction Filter 2A be under clearance.
5. The Nucleis System is down and will not be restored for several days.
INITIATING CUES:
Identify all components that would be used to isolate CRD Suction Filter
2A with the CRD Pump 2A available.
I-
q[motfyjop2201..9A2RODO9C Page
LR-JP-25019-03
Page 6 of 1
START
TIME:
NOTE: Steps of this JPM may be completed in any order.
1. Operator identifies the Operator has identified the correct
procedure needed to perform procedure as 3OAC-OPS-001-OS.
the task.
2. Operator reviews the prOperator has reviewed the I 7
procedure's precautions and precautions and limitations.
limitations. I
3. Operator identifies the Operator has identified the
materials which are required. required materials and where to
obtain them.
Plant Drawing H26007
34SO-C11-005-2S, Section 7.1.4
(Not required to use procedure)
NOTE: The valves listed in this JPM are the minimum requirements for safe
tagging. Components tagged in excess of this minimum will require case
by-case determination by the evaluator.
RESPONSE CUE: N/A
(** Indicates critical step)
T y Kol b - JP25019A2RO.DOC Pm
LR-JP-25019-03
Page 7 of 4
PROMPT: If the operator addresses preparing a clearance to perform the maintenance,
inform the operator another operator will perform the clearance.
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- with no reasonable progress, the operator exceeds double the
allotted time.
- operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
REVIEW OF SCRAM DISCHARGE VOLUME ISOLATION VALVE TIMING &
CLOSURE TEST
AUTHOR ,'$IVNUBE TIME
R. L. SMITH LR-JP-25048-00 20 Minutes
RECOMMENDED BY: APRoVEDBYDT
SOUTHERN A
COMPANY M
Energy to Serve Your WorldS
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of 1
FORM TITLE: TRAINING MATERIAL REVISION SHEET
Program/Course Code: OPERATIONS TRAINING Media Number: LR-JP-25048
I*n t R..so i tialsua
0 ______Initial development. RLS~
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LR-JP-25048-00
Page 2 of 9
UNIT 1 0 UNIT 2 (X)
REVIEW OF SCRAM DISCHARGE VOLUME
ISOLATION VALVE TIMING & CLOSURE TEST
LR-JP-25048-00
TASK NUM.ANDA: The task shall be complete when the operator reviews the
completed surveillance procedure, 34SV-C 11-002-2, and
determines if the test is satisfactory or unsatisfactory.
TASK NUMBER:, xxx.XXX
OB9JECTIVENUMBE R: xxx.xxx.x
PLANT HATCH JTA IMPORTANCE RATING:
RO X.XX
SRO X.XX
K/A CATALOG NUMBER: G2.1.33
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.4
SRO 4.0
OPERATOR APPLICABILITY: Reactor Operator (RO)
GENERL REFERENCStJ2
34S V-Cl11-002-2 Rev 4.2
REQUIRED MATERIALS: Uiiifakg:3S-1-0
Completed surveillance package: 34S V-C I 1-002-2
APPROXIMATE COMPLETION TIME: 20 Minutes
SIMULATOR SETUP: N/A
2
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Unit 2 is at 100% RTP.
2. Maintenance has been performed on the SDV vent and drain valves.
3. 34SV-Cll-002-2S, "Scram Discharge Volume Isolation Valve Timing &
Closure Test," has just been completed due to the maintenance.
INITIATING CUES:
Review the procedure data and determine the acceptability of the test, and
determine if any required Tech Spec action(s) are necessary.
LR-JP-25048-00
Page 4 of 3
S$~rTANDAIOI(OMTSI IKATUNSAT
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 1-002-2S, the operator
EVALUATES
tm aafr the closing stroke
2C11l-F0lOA SDV Vent Vlv time data for:
2C11-F035A SDV Vent Vlv 2C11-F010A SDV Vent Vlv
2C1 1-F010B SDV Vent Vlv 2C1 I-F035A SDV Vent Vlv
2C11-F035B SDV Vent Vlv 2C11-F010B SDV Vent Vlv
2C1 1-F011 SDV Drain Vlv 2C11-F035B SDV Vent Vlv
2C11-F037 SDV Drain Vlv 2C11-F7l1 SDV Drain Vlv
2C 11 -F037 SDV Drain Vlv
1 truetermin'th66oMg
- ,*3. The6P&t - Per step 7.2.7 and 7.2.8 of
st0roe tifti* for:,2 34SV-Cl 1-002-2S, the operator
DETERMINES the closing stroke
,.; time data for:
2i O7DDaVv:
- ' ' 2CI 1-F035A SDV Vent Vlv
j,,ertejs '27 and z'7.2 :2C1 l-F037 SDV Drain Vlv
SH. Have exceeded their closing time
l, .. : limit per steps 7.2.7 and 7.2.8,
and they are
UNSATISFACTORY.
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 4
P..
P . ....................... T.
STEI.... RtV <(CMMNS)C
I I
___________________________
4. The operator evaluates the closing Per steps 7.2.20 and 7.2.22 of
time difference data for: 34SV-C 11-002-2S, the operator
EVALUATES the closing time
2C11-FO10A SDV Vent Vlv difference data for:
2C11 -F035A SDV Vent Vlv 2C11-F010A SDV Vent Vlv
2C11-F010B SDV Vent Vlv 2C1 1-F035A SDV Vent Vlv
2C1 1-F035B SDV Vent Vlv 2C11-FO1OB SDV Vent Vlv
2C11-F011 SDV Drain Vlv 2C1 1-F035B SDV Vent Vlv
2C1 1-F037 SDV Drain Vlv 2C11-F011 SDV Drain Vlv
2C1 1-F037 SDV Drain Vlv
and DETERMINES it to be
SATISFACTORY.
I_
5. The operator evaluates the opening Per steps 7.2.23 and 7.2.25 of
time difference data for: 34SV-Cl1-002-2S, the operator
EVALUATES the opening time
2C11-F010A SDV Vent Vlv difference data for:
2C11-F035A SDV Vent Vlv 2C11-FO10A SDV Vent Vlv
2C1 1-F010B SDV Vent Vlv 2C1 1-F035A SDV Vent Vlv
2C11-F035B SDV Vent Vlv 2C11-F010B SDV Vent Vlv
2Cl1-F011 SDV Drain Vlv 2C1 1-F035B SDV Vent Vlv
2C1 l-F037 SDV Drain Vlv 2C11-F011 SDV Drain Vlv
2C1 1-F037 SDV Drain Vlv
and DETERMINES it to be
SATISFACTORY.
condition A and B, the operator
DETERMINES, that 3.1.8A
applies to 2C11-F035A, 2C11
FO11, & 2C1 1-F037 valves, and
3.1.8.B applies to 2C11-F011 and
2C11-F037 valves.
3.1.8.A Restore valve to
OPERABLE status within 7days.
3.1.8.B Isolate the the associated
line within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
A
RESPONSE CUE: N/A
(** Indicates critical step)
LR-JP-25048-00
Page 6 of 5
S PE... .MANCE STEP STANA1:D S AT/ NS AT ,
2 '(COMMENTS
NOTE: The operator may note that the Drain line valves (2C11-F011 and 2C11
F037) may be opened under administrative control to allow draining of the
SDV.
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
.. - ... ... .. Paae 1
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
SOUTHERN Sa
COMPANY
Energy to Serve Your World"
1_
ITimothy Kolb- JP25049A3.doc
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page I of 1
FORM TITLE: TRAINING MATERIAL REVISION SHEET
Program/Course Code: OPERATIONS training Media Number: LR-JP-25049
Initial Development rls rsR
0 10/07/02
2
Page
jmothyKolb - JP25049A3.doc
LR-JP-25049-00
Page 3 of 9
UNIT 1 0 UNIT 2 (X)
DETERMINE STAY TIMES TO TAKE A PIECE OF
EEQUIPMENT
LR-JP-25049-00
are determined by
This task will be completed when stay times
the operator, bas ed on current accumulated dose for the year and
field.
dose that would 1be received while in a radiation
SXxX.XXX.X
PLANT HATCH JTA IMPORTANCE RATING:
RO X.XXN/A
SRO X.XXN/A
K/A CATALOG NUMBER: G2.3.2G2.3.2
K/A CATALOG JTA IMPORTANCE RATING:
RO 2.52.5
SRO 2.92.9
OPERATOR APPLICABILITY: Reactor Operator (RO)
APPROXIMATE COMPLETION TIME: 20 Minutes
SIMULATOR SETUP: N/A
candidates.
NOTE: First section is for RO Candidates and the second section is for SRO
L 3
LR-JP-25049-00
Page 4 of I
Part 1
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The 4 tb 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.
I
-.... ..
Pa
[3 - JP25049A3 do,.
.othyKob
LR-JP-25049-00
Page 5 of I
starte:
tim
Condenser
PROMPT: AT this time give the operator the copy survey map of the Unit I
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 th(
allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
ffirnoth*olb - JP25049A3.doc ..
LR-JP-25049-00
Page 6 of I
Part 2
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The 4th Stage 'A' Feedwater heater has a leak on its shell side inlet flange.
2. Your crew has been assigned the task to enter the Cond Bay to isolate, and
drain the '4A' Feedwater Heater.
3. The estimated time to perform this task is approx 1 hour1.157407e-5 days <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.
'K
Page
Tibmohyj Ko- JP25049A3.doc
LR-JP-25049-00
Page 7 of 1
start
time: -
PROMPT: AT this time give the operator the copy of the survey map of the Unit 2
Condenser Bay 164' el.
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)
I - --
PaeE
FinhxKb-Jp25049A.doc
LR-JP-25049-00
Page 8 of 6
-
EP 2
Using his remaining dose margin
and highest dose rate for the area,
CALCULATE the Stay Times for
each operator:
RESPONSE CUE: N/A
NOTE: IF the operator states that the operators should not exceed the RWP Dose
limit of the Digital Alarming Dosimetry (DAD), this is also correct.
END
TIME: -
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double tht
allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
"(** Indicates critical step)
frnotikolb- JP25205A4SRO.DOC Pa
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training JPM
SRO ONLY
EVALUATE THE NEED FOR/RECOMMEND OFFSITE PROTECTIVE
ACTIONSE VALUATE THE NEED FOR/RECOMMEND OFFSITE
PROTECTIVE ACTIONS
U~. ... IE h
......
.il
R. L. SMITHR. L. SMITH LR-JP-25205-06LR-JP-25205-06 16.016.0 Minutes
- """Woe1NDE 0Wt' ,AMO
t. f. phillips r. s. grantham 10/07/02
SOUTHERN NA
COMPANY
Energy to Serve Your World"
1
rage
LTimstY Kob - JP25205A4SRO.DOC S.........*.g*
F-
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
E __ __ -- _ _ _ _ _ -i.
.
1 4- t t
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II
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2
nTimothy'Kolb - JP25205A4SRO.DOC . Pag
LR-JP-25205-06
Page 3 of9
UNIT 1 (X) UNIT 2 (X)
"
W-W EVALUATE THE NEED FOR/RECOMMEND
1 .0,60. 412
OFFSITE PROTECTIVE ACTIONS
1#0M,, E LR-JP-25205-06
Eff M u ? The task shall be completed when the Protective Action
'r2 Recommendation has been made per 73EP-EIP-054-OS.
200.105 (EP 001.088)200.105 (EP 001.088)
ED 200.105.A200.105.A
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.003.00
SRO 3.003.00
K/A CATALOG NUMBER: 295038EA201295038EA201
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.303.30
SRO 4.304.30
OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)
JWMMSýM* ni
illaw
aa] RR g, R -avj
ay
!!!Mna
73EP-EIP-054-OS Rev 4 Ed I
q4I yIagaiE~aga 114MR,
I 73EP-EIP-054-OS (current revision)
PAR Worksheet/Approval Sheet
APPROXIMATE COMPLETION TIME: 16.0 Minutes
SIMULATOR SETUP: N/A
3
LTmoty§ KolbI-JP25205A4SRO. DOC Pag
LR-JP-25205-06
Page 4 of I
UNIT 1 & 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. The Prompt Offsite Dose Assessment has just been completed, and
projected Dose information is available.
2. The Dose Assessment Staff is not available yet.
3. The SOS has declared a Site Area Emergency due to the release.
4. The SOS is performing the functions of the Emergency Director.
5. SPDS is available.
INITIATING CUES:
Determine the Protective Action Recommendations, per
Page
LT1mo1!1y K0b JP25205A4SRODOC
LR-JP-25205-06
Page 5 of I
start
time:
PROMPT: At this time, give the operator the projected Dose information.
1. Operator identifies the procedure Operator has identified the correct
needed to perform the task. procedure as 73EP-EIP-054-0S.
2. Operator reviews the procedure's Operator has reviewed the
precautions and limitations, precautions and limitations.
PROMPT: When the operator identifies the proper wind indication instrument,
indicate that the wind direction (from) is 2250. e
(
At% t 5 R
ijAt
1 panel IHI 1-P690, the operator
N has determined wind direction to
be from 2250, using one of the
following recorders:
IY33-R601 (10 meter)
1Y33-R602 (60 meter)
~4 ~ 2 Y33-R603 (100 meter)
N OR
~
ýQjw At panel 1H 11-P689, the operator
has determined wind direction to
be from 2250, using recorder
1Y33-R604 (23 meter).
fj, V, 1X4tjfll ~At Unit I or 2 SPDS MIDAS or
R -
Ellý P MET screens the operator
Ndetermines wind direction to be
aial t2250.
RESPONSE CUE: N/A
NOTE: Accept the wind direction as 216 to 2500.
4. Record "wind direction from" on The operator has recorded wind
Attachment 3. direction (Wind From) on Step I
Iof Attachment 3.
(** Indicates critical step)
--
LTimothy Kolb - JP25205A4SR.DOC
LR-JP-25205-06
Page 6 of 6
PE BF1 K 0i4
The operator has determined the
affected zones to be:
RESPONSE CUE: N/A
6. Record the affected zones on The operator has recorded the
Attachment 3. affected zones on Step 2 of
Attachment 3.
7. Compare plant conditions with The operator has Determined a
Attachment 1 of procedure. General Emergency does not
exist.
PROMPT: If the operator addresses status of emergency classification, as the SOS,
inform the operator that a Site Area Emergency has been declared.
8. Determine PARs required for a Site The operator has determined there
Area Emergency per Attachment 1. are NO PARs for Site Area
Emergency per Attachment 1.
9. Record the plant condition PARs on The operator has recorded "N/A"
Attachment 3. or "NONE" for plant condition
PARs on Step 3 of Attachment 3.
10. Determine if Off-site dose has been The operator has determined that
measured or projected. the dose rate has been projected.
11. Determine if the population dose is Evaluating ALL TEDE and
greater than 1 REM TEDE or greater THYROID CDE Values the
than 5 REM CDE Thyroid. operator:
Determines the dose to the
population is greater than I
Answers YES to the flowchart
step.
(** Indicates critical step)
--- P rage
-- -
tTirnotrKolb - JP25205A4SRO.DOC
F- LR-JP-25205-06
Page 7 of 6
, -ý jMle'uu HIM
TL R 2E N. IN
W, " -. N1,1111.1 BRIN "I I HIM 10"K1%A4r/9VJJN,,,S
&W." '.q
12. Determine if the dose is greater than 1 Evaluating the 10 and 5 mile
REM TEDE or greater than 5 REM TEDE and THYROID CDE
CDE Thyroid at 5 - 10 miles. Values the operator:
Determines the dose to the
population is less than I REM
Thyroid at 5 - 10 miles.
Answers NO to the flowchart
step.
13. Determine if the dose is greater than 1 Evaluating the 5 AND 2 MILE
REM TEDE or greater than 5 REM TEDE and THYROID CDE
CDE Thyroid at 2 - 5 miles. Values the operator:
Determines the dose to the
population is less than 1 REM
Thyroid at 2 - 5 miles.
Answers NO to the flowchart
step.
A *4*P )* * * i VThe
~ operator has determined
MMi aPARs for dose projections per
S' Attachment 2 are:
Evacuate Zone A
Si *:J!*I Shelter Zones E-5.
RESPONSE CUE: N/A
PROMPT: If the operator addresses actual field measurements, as the SOS, inform the
operator that no actual field measurements have been obtained yet.
A-ri 4
45
SKI9Kt
s
If
The operator has determined the
PARs from dose projections are e
iEM j 4 most conservative.
RESPONSE CUE: N/A
16. Check the block to the left of the most The operator has checked the
conservative PAR of Step 3 on block to the left of the Dose
Attachment 3. Projections of Step 3 on
Attachment 3.
(** Indicates critical step)
-,Potý
-JP25205A4SRO.DOC ..... Pace
LR-JP-25205-06
Page 8 of 6
17. Record the zones from the most The operator has recorded the
conservative PAR to the Approval following on the Approval
Section of Attachment 3. Section on Attachment 3:
Evacuate Zone A
Shelter Zones E-5.
18. Obtain ED concurrence on PARs. Emergency Director has signed
Attachment 3.
NOTE: The evaluator may sign as the ED or tell the operator that it has been
signed.
PROMPT: If the operator addresses notifications, as the SOS, inform the operator that
another operator will make the State and Local notifications.
PROMPT: If the operator addresses continuing assessment, as the SOS, inform the
operator that another operator will continue the assessment of the emergency
conditions.
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double tht
allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(*': Indicates critical step)
_ _- Page9
fTirnothy Kolb - DOG C . ...........
LR-JP-25205-06
Page 9 of 1
"**13. ESTIMATE OF PROJECTED OFFSITE DOSE:
I NEW [ ] UNCHANGED PROJECTION TIME: (Eastern)
______________
TEDE THYROID ODE
ESTIMATED DURATION: _ HRS
(mrem) (mrem)
SITE BOUNDARY 1 .4E+03 6.9E+03
2 MILES 7.4E+02 3.OE+03
5 MILES 2.3E+02 6.9E+02
10 MILES 5.5E+01 1.7E+02
Page 9 of 7
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
TITLE"
FROM OUTSIDE THE CONTROL ROOM, INJECT BORON USING THE
SBLC SYSTEM WITH FAILURE OF "A" PUMP TO START
R. L. SMITH LR-JP-25043-00 21.0 Minutes
7RE O M ENDE D BY ... ,. ... B
Ar**
. AxPPROvED ........ ADTE
RECOMMENE
SOUTHERN
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-25043
Rev. No. I Date I
I.. ............ enjoUeiinfAhos4Sps I: Initials * Initials
00 Initial Development. RLS
~i. __________ II
_______ I I I I
_______ I I I
_______ .1 J t I
_______ .1 1. t I
_______ .1 1- t 1*
_______ _______ 4- t I
_ _ _ __ I I1t1
I 4 1 1
I L F I
__ _ _ I I
_________ I I I
II I
I I I
I I I
I1 I.
LR-JP-25043-00
Page 1 of 9
UNIT 1 (X) UNIT 2 (X)
- TASK TITLE:' FROM OUTSIDE THE CONTROL ROOM, INJECT
BORON USING THE SBLC SYSTEM WITH
FAILURE OF "A" PUMP TO START.
LR-JP-25043-00
,TASK STANDARD: 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.
TASK NUMBIER:, 011.012
OBJECTIVENUMBER. 011.012.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)
GENERAL RktERENCES Tnit~ AKJ~ iii
31EO-EOP-011-1S Rev 6 31EO-EOP-011-2S Rev 6
34SO-C41-003-1S Rev 10 34SO-C41-003-2S Rev 10
Ed 5 Ed 4
REQUIRED MATERIALSJ: Uit 1. . j.Uni.
34SO-C41-003-1S 34SO-C41-003-2S
(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-01 1-IS (RCA) is in progress.
3. SBLC has failed to initiate from the Control Room.
4. RWCU is isolated.
INITIATING CUES:
Manually initiate SBLC locally per 34SO-C41-003-lS.
LR-JP-25043-00
Page 3 of 3
STEP
PE<' STANDAlTISAUSA
1<I(OMENTS)
START
TIME:
1. Operator identifies the materials that Operator has identified the
are required. required materials and where to
obtain them.
2. Operator reviews the procedure's Operator has reviewed the
precautions and limitations, precautions and limitations.
- 3. Detonaitquib Valve.... 4.f.4A .. At Panel 1H21-PO 11, the
AND following jumpers are
S< tINSTALLED for 1C41-FO04A:
Detonat~ squib Valvei 4-pO4ýt
7z ýý",Terminal point BB-1 to Squib
Valve, 1C41-F004A, Junction
Box terminal C1 (white wire) and
terminal C (green wire).
Terminal point BB-4 to Squib
Valve, 1C41-FOO4A, Junction
Box terminal C2 (black wire) and
terminal C3 (red wire).
At Panel 1H21-P011, the
following jumpers are
Y INSTALLED for 1C41-FO04B:
Terminal point BB-8 to Squib
Valve, 1C41-F004B, Junction
Box terminal Cl (white wire) and
terminal C (green wire).
C Terminal point BB- 11 to Squib
Valve, 1C41-FO04B, Junction
Box terminal C2 (black wire) and
term*nal C3 (red wire).
RESPONSE CUE: Squib Valve 1C41-F004A(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 4
STEP P PERFORMANC . TP K K(OMNS
ST....R?. SATUNSAT
PROMPT: IF the operator addresses isolation of RWCU, as the Control Room operator
REPORT that RWCU is isolated.
4. Start SBLC Pump 1C41-COOlA. At panel 1H21-PO1I, SBLC
PUMP, SC41-COO1A, control
switch is in RUN.
PROMPT: WHEN operator addresses indications for pump start, INDICATE there is
no noise from the pump, and green light is illuminated and red light is
extinguished.
5. RETURN the control switch to the At panel 1H21-POl1, SBLC
STOP position PUMP, 1C41-C001A, control
switch is in STOP.
- 6. Start SBLC iC41-COOIB , At panel 1H21-POl1, SBLC
PUMP, 1C41-CO01B, control
switch is in RUN.
RESPONSE CUE: SBLC Pump 1C41-COOLB, pump motor is quiet, and green light is
illuminated.
7. Verify the SBLC solution is being At panel 11H21-PO11, the operator
injected into the Reactor. has VERIFIED SBLC Tank level
is DECREASING as indicated by
SBLC STORAGE TANK
LEVEL INDICATOR,
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 BUT curve.
2. 31EO-EOP-01 1-2S (RCA) is in progress.
3. SBLC has failed to initiate from the Control Room.
4. RWCU is isolated.
INITIATING CUES:
Manually initiate SBLC locally per 34SO-C41-003-2S.
LR-JP-25043-00
Page 6 of 6
STEP.PE.ORMANC......
STEP[M [ N:e: Y " 'W .. SAD : : D( .SAT/UNSATY...
,4 M E NI...
START
TIME:
1. Operator identifies the materials that Operator has identified the
are required. required materials and where to
obtain them.
2. Operator reviews the procedure's Operator has reviewed the
precautions and limitations, precautions and limitations.
DetondtSquib Valve 2C4J F004A* ,,ý At Panel 2H21-PO 11, the
- 3
ANDfollowing jumpers are
o, INSTALLED for 2C41-FO04A:
Detnatqibalv .4 4.. , Terminal point AA-5 to Squib
-. Valve, 2C41-FO04A, Junction
Box terminal point 1 (white wire)
and terminal point 3 (green wire).
Terminal point AA-6 to Squib
Valve, 2C41-F004A, Junction
Box terminal point 4 (red wire)
and terminal point 2 (black wire).
At Panel 2H21 -PO 11, the
following jumpers are
INSTALLED for 2C41-FOO4B:
Terminal point AA-10 to Squib
Valve, 2C41-FOO4B, Junction
- , Box terminal point 1 (white wire)
and terminal point 3 (green wire).
Terminal point AA-11 to Squib
Valve, 2C41-FO04B, Junction
Box terminal point 4 (red wire)
and terminal point 2 (black wire).
RESPONSE CUE: Squib Valve 2C41-F004 A(B), no noise is heard.
PROMPT: WHEN all terminals for a Squib Valve are correctly installed, INDICATE
an explosive noise from the vicinity of that Squib Valve.
NOTE: Detonation of one Squib Valve will satisfactorily meet the standard.
NOTE: The jumpers used to fire the Squib Valves are a jumper with 3 connections
to connect all three terminal points.
(** Indicates critical step)
LR-JP-25043-00
Page 7 of 7
STEP $T/UNSAT
STPPERFORMA INCE ft,ý§T* STANDARD O MNS
PROMPT: IF the operator addresses isolation of RWCU, as the Control Room
operator, REPORT that RWCU is isolated.
4. Start SBLC Pump 2C41-COO1A. At panel 21121-P011, SBLC
PUMP, 2C41-COO1A, control
switch is in RUN.
PROMPT: WHEN operator addresses indications for pump start, INDICATE there is
no noise from the pump, and green light is illuminated and red light is
extinguished.
5. RETURN the control switch to the At panel 2H21-PO1 1, SBLC
STOP position PUMP, 2C41-CO01A, control
switch is in STOP.
- 6.Srt QBC2C41-C 1IB At panel 2H21-POl, SBLC
PUMP, 2C41-CO01B, control
switch is in RUN.
RESPONSE CUE: SBLC Pump 2C41-C001B, pump motor is quiet, and green light is
illuminated.
7. Verify the SBLC solution is being At panel 21121-PO 11, the operator
injected into the Reactor. has VERIFIED SBLC Tank level
is DECREASING as indicated by
SBLC STORAGE TANK
LEVEL INDICATOR,
2C4 1-ROO1.
PROMPT: WHEN the operator addresses SBLC tank level, INDICATE for the
operator that level is decreasing slowly, but is greater than 1000 gallons.
NOTE: It will take between 30 and 70 minutes to completely empty the SBLC
Storage Tank.
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
- Indicates critical step)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
- TITLE -
FROM THE REMOTE SHUTDOWN PANEL, START RCIC FOR INJECTION
INTO THE REACTOR
AUTHOR ..... .. ED. NU .. I.ME
R. A. BELCHER LR-JP-39.16-12 24.0 Minutes
RECOMMENDEDB"APOED BY DATE,
N/R R. A. BELCHER 03/14/2002
SOUTHERN 4
COMPANY
Energy to Serve Your Worlds.
K->
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of t
FORM TITLE: TRAINING MATERIAL REVISION SHEET
Program/Course Code: OPERATIONS TRAINING Media Number: LR-JP-39.16
Rev. No. Date ,.. Init ials
01 06/30/89 General revision and format change JEM SMC
02 08/18/89 Add LR lesson plan references JEM DHG
03 09/22/89 General revision JEM WRB
04 02/27/90 Procedure, format, & question revision JEM DHG
05 04/29/91 General/procedure revision JLA DHG
06 08/26/92 General revision and format change WMM SCB
07 09/02/93 General revision, word processor change 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
LR-JP-39.16-12
Page 1 of 1
UNIT 1 (X) UNIT 2 (X)
FROM THE REMOTE SHUTDOWN PANEL, START
RCIC FOR INJECTION INTO THE REACTOR
JMNUMBR LR-JP-39.16-12
TSKSTANDARD: The task shall be completed when the RCIC System is started
and injecting to the Reactor per 31RS-OPS-001.
TOSK NUMR: M 039.016
ýOBJECTIVE`NUMBER: 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)
GENEIRAL REVERENCE'S.1: Uixitl Unit 2
31RS-OPS-001-IS Rev 5 Ed 2 31RS-OPS-001-2S Rev 6 Ed 1
REUIED
QUIRE . MATERIALS:. ntt '___-"- Ui
>_"__-% _____
31RS-OPS-001-1S 31RS-OPS-001-2S
(current revision) (current revision)
Key for Remote Shutdown Key for Remote Shutdown
Panel (if performed in Plant) 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 2
SIMULATOR SETUP
Simulator Initial Conditions:
1. RESET the Simulator to IC #127 and leave in FREEZE.
2. INSERT the following MALFUNCTIONS:
MALF#VI >TTt fAL RAMP AT
mfB21_48A Steam Line A Break (After Restrictor) (Var) 1.0 1000 00000
mfN21_79A Condensate Pump 2A Trip 00000
mfN21_79B Condensate Pump 2B Trip 00000
mfN21_79C Condensate Pump 2C 00000
mfE41_107 HPCI Failure to Start (F001 Stuck) 00000
mfE51_109 RCIC Failure to Auto Start 00000
3. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A. Allow the simulator to run for two minutes.
B. Secure all RHR and Core Spray pumps.
C. Acknowledge all annunciators.
4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.
5. ESTIMATED Simulator SETUP TIME: 15 Minutes
UNIT 1
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. An event has occurred which required the Control Room to be evacuated.
2. The Unit I Reactor was scrammed prior to the evacuation.
3. RCIC is in standby.
4. 3 1RS-OPS-001- 1S is in progress.
5. RWL is less than +12 inches and decreasing.
INITIATING CUES:
Start the RCIC System from the Remote Shutdown Panel and inject water
into the Reactor per 31RS-OPS-001-1S, Attachment 3.
LR-JP-39.16-12
Page 4 of 4
...... STEP..... .
PERFORMANCE$TEPý ,. STANDAMMES S .
START
TIME:
I I
Operator identifies required the
materials and where to obtain
them.
l l
PROMPT: IF the operator addresses posting of RCIC Diagonal, as the Shift Supervisor,
INFORM the operator that Health Physics is posting the area.
I. T
2. Place the following Transfer Switches At panel 1C82-P001, the
in EMERGENCY: following Transfer Switches are
in EMER:
1C82-$23G
1C82-$23B
XFER SW 1C82-$23B
IC82-$23C
XFER SW 1C82-$23C
IC82-$23D
XFER SW 1C82-$23D
1C82-$23E
1C82-$23F
XFER SW 1C82-$23F
I I
3. Locally confirm the position of the The operator has addressed
following valves: contacting an SO to VERIFY the
following valves are in the correct
1E51-FO1O position:
1E51-F012 CONDENSATE STORAGE
1E51-F029 SUCTION VLV, 1E51-F010, is
IE51-F031 OPEN.
PUMP DISCHARGE VLV,
1E51-F012, is OPEN.
SUPPRESSION POOL
SUCTION VLV, 1E51--F029, is
CLOSED.
SUPPRESSION POOL
CLOSED.
______________________________________________________ L _______________________________________________ a
PROMPT: WHEN the operator addresses locally confirming positions of valves, as the
SO, INFORM the operator that:
1E51-FO10 and 1E51-F012 are open.
1E51-F029 and 1E51-F031 are closed.
(** Indicates critical step)
LR-JP-39.16-12
Page 5 of 5
STEP PERFORMANC STE
, STNDR SAI S Tt
6 }CO MENTS)z Y,
4. Confirm 1E51-F045 is closed. At panel 1C82-POOI, STM TO
CLOSE, green light illuminated.
OPEN, red light illuminated.
RESPONSE CUE: Valve, 1E51-F046, green light illuminated.
6. Confirm 1E51-F013 is closed. At panel 1C82-POO1, RCIC
is in CLOSE, green light
illuminated.
7. Confirm 1E51-F007 is open. At panel 1C82-POO1, INBD ISOL
red light illuminated.
8. Confirm 1E51-F524 is open. At panel 1C82-POO1, RCIC TRIP
OPEN, red light illuminated.
9. Confirm 1E51-F008 is open. At panel 1C82-P001, OUTBD
OPEN, red light illuminated.
10. Start the Barometric Condenser At panel 1C82-P001,
Vacuum Pump. BAROMETRIC CNDSR VAC
PUMP Switch is in START, red
light illuminated.
11. Start the Barometric Condenser At panel 1C82-POO1,
Condensate Pump. BAROMETRIC CNDSR COND
PUMP Switch is in RUN, red
light illuminated.
NOTE: The operator should not address opening 141-F011 and 1E51-F022 since
RCIC operation will NOT be for Reactor pressure control.
PROMPT: IF the operator addresses purpose for RCIC operation, as the Shift
Supervisor, INFORM the operator that RCIC operation is for RWL control.
OPEN, red light illuminated.
RESPONSE CUE: Valve, 1E51-F045, green light illuminated.
(** Indicates critical step)
LR-JP-39.16-12
Page 6 of 6
STEP PERFO RMANt §IE
TAjNAp I (COMMENTS)'ý
ATUNSAT"'.
PUMP DISCH VLV, 1E51-F7013,
Is OPEN, red light illuminated.
RESPONSE CUE: Valve, 1E51-F013, green light illuminated.
PROMPT: WHEN the operator addresses RCIC Pump Flow, as the 1H21-P173 Panel
operator, INFORM the operator that flow is greater than 122.5 gpm on
RCIC PUMP FLOW 1E51-R070 indicator at panel 1H21-P173.
14. Locally confirm valve 1E51-F019 The operator has addressed
closes when RCIC flow exceeds 122.5 contacting an SO to confirm MIN
CLOSED.
PROMPT: WHEN the operator addresses 1E51l-F019, as the SO, INFORM the
operator that 1E51-F019 is closed.
PROMPT: WHEN the operator addresses monitoring parameters at 1H21-P173, as the
Shift Supervisor, INFORM the operator that they are being monitored by an
operator at 1H21-P173.
PROMPT: IF the operator addresses securing RCIC or system restoration, as the Shift
Supervisor, INFORM the operator that it is not desired at this time.
END
TIME:
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. An event has occurred which required the Control Room to be evacuated.
2. The Unit 2 Reactor was scrammed prior to the evacuation.
3. RCIC is in standby.
4. 31RS-OPS-001-2S is in progress.
5. RWL is dearsig. .-SO ' Q S ecrca
INITIATING CUES:
Start the RCIC System from the Remote Shutdown Panel and inject water
into the Reactor per 3 1RS-OPS-001-2S, Attachment 3.
LR-JP-39.16-12
Page 8 of 8
STA 'kdQMMENTMY
START
TIME:
1. Operator identifies the materials that Operator identifies the required
are required. materials and where to obtain
I I them.
PROMPT: IF the operator addresses posting of RCIC Diagonal, as the Shift Supervisor,
INFORM the operator that Health Physics is posting the area.
- NOTE: Transfer Switch 2C82-S8 is not required to complete the critical step
satisfactorily.
- Piace:*2. fignTtfno K1At panel 2C82-P001, the
in EMERGENCY:- ' following Transfer Switches are
2C82-5in EMERGENCY:
2C82-SER sw
2....-55 XFER SW 2C82-$55 AA~ac
2 -' * ..... ' XFER SW 2C82-S84.
RESPONSE CUE: Remote Shutdown Panel indications are not available.
(** Indicates critical step)
LR-JP-39.16-12
Page 9 of 9
iSTEP P`ERFORMAN.. CE STE STANDARD SAT/UNSATJ,>; I
I I
3. Confirm the following valves are At panel 2C82-P001, the operator
open: VERIFIES the following valves
are OPEN, red light illuminated:
CST SUCTION VLV, 2E51l-F010
2E51--F007 t.."
STEAM SUPPLY INBD ISOL
STEAM SUPPLY OUTBD ISOL
NOTE: The operator should not perform Section 3.0 of Attachment 3 since RCIC
operation will NOT be for Reactor pressure control.
4. Confirm the RCIC Flow Controller is At panel 2C82-P001, the operator
in AUTO and set for 400 gpm. VERIFIES RCIC FLOW
CONTROL, 2C82-RO01:
Is in AUTO.
Is set for 400 gpm (accept 350 to
450 gpm).
5. Confirm the following valves are At panel 2C82-POO1, the operator
closed: VERIFIES the following valves
2E51-F029 are CLOSED, green light
illuminated:
2E5 1-F031 TORUS OUTBD SUCTION
NOTE: The operator should not address opening 2E51-F029 and 2E51-F031 since
2E5 1-F010 is open.
6. Start the Barometric Condenser At panel 2C82-P00I, the
Vacuum Pump. BAROMETRIC CNDSR VAC
PUMP, 2E51-C002-2, is in
START, red light illuminated.
(** Indicates critical step)
LR-JP-39.16-12
Page 10 of 10
STEP viTI UNSAT.
7. Start the Barometric Condenser At panel 2C82-POOL, the
Condensate Pump. BAROMETRIC CNDSR COND
PUMP, 2E51-C002-1, is in
START, red fight illuminated.
8. Confirm the Trip and Throttle Vlv is At panel 2C82-P001, the operator
open. has verified TRIP & THROTTLE
light illuminated.
Open valyeQESl-F046
4*9, *At panel 2C82-P001, TURB CLG
..., OPEN, red light illuminated.
RESPONSE CUE: Valve, 2E51-F046, green light illuminated.
10. Open valve 2E5 1-F019. At panel 2C82-POO1, MIN
OPEN, red light illuminated.
SOpen valve ;2E51-,F045. .. At panel 2C82-P001, STM TO
OPEN, red light illuminated.
RESPONSE CUE: Valve, 2E5 1-F045, green light illuminated.
PROMPT: IF the operator addresses purpose for RCIC operation, as the Shift
Supervisor, INFORM the operator that RCIC operation is for RWL control.
- At panel 2C82-POO1, DISCH
" * VLV, 2E51-F013, is OPEN, red
. . .,- light illuminated.
RESPONSE CUE: Valve, 2E5 1-FO13, green light illuminated. -6 qaoTt'-
- 13. Close (heMipimum Flow V At panel 2C82-P001, when flow
is greater than 122.5 gpm o
gpntRCIC FLOW,2CS2EDQ2'MIN
4 K FLOW VLV, 2E5 1-F019, is
7' CLOSED, green light
illuminated.
RESPONSE CUE: Valve, 2E51--F019, red ight illuminated.
PROMPT: IF the operator addresses RWL band, as the Shift Supervisor, INFORM the
operator that another operator will maintain RWL.
(** Indicates critical step)
LR-JP-39.16-12
Page 11 of 11
'STEP I STEP
.PERFORMANCE TANDARDT
PROMPT: IF the operator addresses securing RCIC or system restoration, as the Shift
Supervisor, INFORM the operator that it is not desired at this time.
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
A
,TITLE
DURING A LOSS OF AIR, ISOLATE THE FIRE PROTECTION SPRINKLERS
AUTHOR: MEIUBR TIME
R. A. BELCHER LR-JP-36.13-07 13.0 Minutes
RECOMMENDED BY R.APPRELD BYD 02
NIR R. A. BELCHER 03/12/2002
SOUTHERN Sk
COMPANY
Energy to Serve Your World3"
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of t
FORM TITLE: TRAINING MATERIAL REVISION SHEET
Program/Course Code: OPERATIONS TRAINING Media Number: LR-JP-36.13
01 09/04/92 General revision and format change WMM SMC
02 07/22/93 General revision, word processor change 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
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 t t
I I
I I I
_________ I t I
_______ £ I I I
_______ I I I
I.II I
_______ .1 1- t I
_ _ _ _ _ _I _ _ I-I
__ _ _ I I.t
I .1 t
_ _ _ _
_I I1t
I I
I I I
LR-JP-36.13-07
Page 1 of 1
UNIT 1 (X) UNIT 2 (X)
TASK TITLE. : DURING A LOSS OF AIR, ISOLATE THE FIRE
PROTECTION SPRINKLERS
JPM NUMBER.: LR-JP-36.13-07
TASKSTANDARD : The task shall be completed when the Fire Protection Sprinklers
have been isolated during a loss of air per 34AB-P51-001.
TASK NUMBER: 036.013
OBJECTIVE NUMBER: 036.013.O
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.57
SRO 3.70
K/A CATALOG NUMBER: 2860002130
KIA CATALOG JTA IMPORTANCE RATING:
RO 3.90
SRO 3.40
OPERATOR APPLICABILITY: Systems Operator (SO)
GEERAL RFRENCES:tftl ' tUzi2
I34AB-P51-001-1S Rev 2Ed 3 34A&B-P51-001-2S Rev 2Ed 1
SREQUIRED MA..,:TERIALS:1Ui
(current revision) (current revision) j
I
APPROXIMATE COMPLETION TIME: 13.0 Minutes
SIMULATOR SETUP: N/A
UNIT 1
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. A scram has occurred on Unit 1.
2. Unit 1 has had a loss of control air pressure and header pressure is below
45 psig and NOT increasing.
3. No fires exist in the plant.
4. Another operator is isolating Fire Protection Sprinklers to the Start-up
Boiler and to the Main, Aux, and Startup Transformers.
5. 34AB-P51-001-1S, "Loss of Instrument and Service Air System," is in
progress.
INITIATING CUES:
Isolate the Fire Protection Sprinklers inside the Power Block per
Attachment 1 of 34AB-P51-001-lS.
LR-JP-36.13-07
Page 3 of 3
STEP STAND ARD..SATUSAT>::
ŽPERORMACE~T~d 3/4}COMENTS)
START
TIME:
NOTE: The steps of this JPM may be performed in any order.
ya 1U43 I I At location 164TCT04, valve I
RESPONSE CUE: N/A1U3F2DiCLS.
Closevalv ~At location l3OTETO4, valve
I1U43-F301B is CLOSED.
RESPONSE CUE: N/A
NOTE: This valve isolates the Generator Hydrogen Seal Oil System area.
RESPONSE CUE: N/A
1Z43-FO18A is CLOSED.
ClSPONSEvv1-F AAt location 1N/THT04, valve
NOTE: This valve isolates the Lube Oil Storage Tank area.
PROMPT: IF the operator addresses stationing a fire watch, as the Shift Supervisor,
INFORM the operator that a fire watch is being posted with back-up
suppression equipment.
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. A scram has occurred on Unit 2.
2. Unit 2 has had a loss of control air pressure and header pressure is below
45 psig and NOT increasing.
3. No fires exist in the plant.
4. Another operator is isolating Fire Protection Sprinklers to the Startup
Transformers.
5. 34AB-P51-001-2S, "Loss of Instrument and Service Air System," is in
progress.
INITIATING CUES:
Isolate the Fire Protection Sprinklers inside the Power Block per
Attachment 1 of 34AB-P51-001-2S.
LR-JP-36.13-07
Page 5 of 5
~tEA 4i4~4DOM.MENTSt
PERFRMACE
START
TIME:
NOTE: The steps of this JPM may be performed in any order.
I Close valve 2U43-F093. ,At location 112TAT19, valve
........12U43-F093 is CLOSED.
RESPONSE CUE: N/A
NOTE: This valve isolates the Reactor Feed Pump and Oil Conditioner area.
Closevalve 2U43-14.At location 136THT20, valve
RES E2U43-F214 is CLOSED.
RESPONSE CUE: N/A
NOTE: This valve isolates the Hydrogen Seal Oil System, W End Cond A & B
(Below 130') and W End Cond A & B (Above 130') areas.
S '
Close<4e 243-F1O1. iiAt location 112THT13, valve
2Z43 F101 is CLOSED.
RESPONSE CUE: N/A
NOTE: This valve isolates the Main Turbine Lube Oil Reservoir area.
PROMPT: IF the operator addresses stationing a fire watch, as the Shift Supervisor,
INFORM the operator that a fire watch is being posted with back-up
suppression equipment.
Close a U. , , At location 13OTAT19, valve
.' - , .2U43-F090 is CLOSED.
RESPONSE CUE: N/A
NOTE: This valve isolates the RFP Oil Conditioner area.
END
TIME: -
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
- Operator states the task is complete.
(** Indicates critical step)
LR-JP-36. 13-07
Page 6 of 6
STEP P.R.O..ANCE.. ... ............ ATI.NSAT `
TERMINATING CUE: We will stop here.
(** Indicates critical step)
... .......
J0006ECIRCMMDOC
- ,Kob .. .. . .. Pa I
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
SOUTHERNAL
COMPANY
Energy to Serve Your WorldM
1
S.. ..
m t*~....
(T -
..........................
JPOO406RECIRCMM.DOC
0C
.
__-_ . . .......... .....................
Page 2
OPERATIONS training Media Number: LR-JP-04.06
Program/Course Code:
wgw rs
01 06/09/89 General revision and format change
Procedure revision jem dh
02 08/03/89
jem smc
03 08/24/89 Revised initial conditions
General revision jem wrb
04 09/22/89
jem dhR
05 08/29/90 Procedure, format, and question revision
la dhg
06 05/20/91 General/procedure revision
wmm seb
07 08/21/92 General revision and format change
mmg DHG
08 07/08/93 Incorporate new controllers and word processor
change
adjust rab smc
09 07/24/94 Procedure changes, modify simulator setup,
format, change initiating cue to a direct command
setup to rab DHG
10 02/20/95 Adjust time allotment, modify simulator
incorporate instructor feedback, adjust format, put
phonetics into the initiating cues
rab dhg
11 05/15/96 Format change
SCB DHG
12 05/28/97 Revised due to procedure change.
rab dhg
13 01/18/00 Format modification, change time allowance based on
running average
rab dhg
14 05/19/00 Incorporate student/instructor comments
rab dhg
15 10/30/00 Include objective number, incorporate instructor
comments, correct simulator setup
rab RAB
16 02/22/02 Include initial operator statement
2
... -.. ,* * w-* *z ... . v' , * Paqe**-.
rTimobthy Kob- JP00406RECIRCMM.DOC
LR-JP-04.06-16
Page 3 of B
UNIT 1 (X) UNIT 2 (X)
q SHIFT RECIRC CONTROL FROM INDIVIDUAL TO
MASTER CONTROL
LR-JP-04.06-16
task shall be completed when Reactor Recirculation Pump
"2A" and "2B" have been shifted from Individual to Master
Control, per 34SO-B31-001.
1 004.006004.006
004.006.A004.006.A
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.203.20
SRO 3.193.19
K/A CATALOG NUMBER: 202001A401202001A401
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.703.70
SRO 3.703.70
OPERATOR APPLICABILITY: Reactor Operator (RO)
I340-B53 1-001-2S
I(current revision)
APPROXIMATE COMPLETION TIME: 11.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
3
....
................ ~~R
.... MM DO 1C Pag 4
LR-JP-04.06-16
Page 4 of 0
SIMULATOR SETUP
Simulator Initial Conditions:
1. Reset the Simulator to IC #128 and leave in FREEZE.
2. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A. Ensure pump speeds are >45%. Place Recirc Pumps A and B in Individual Manual
Mode. in
B. Using Individual Pump Controllers, ensure there is approximately a 5% mismatch
individual pump speeds, but both are >45%.
C. Reduce Master Controller to <45% output.
D. Ensure the plant has stabilized.
3. Place the Simulator in FREEZE until the INITIATING CUE is given.
4. ESTIMATED Simulator SETUP TIME: 10 Minutes
4
Page...
Timothy Koib - JP004O6RECIRC .MM.DOG
LR-JP-04.06-16
Page 5 of 6
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Recirc Pumps "2A" and "21" are in Individual Manual Control mode.
Both individual controllers are in MANUAL.
2. Recirc Pumps "2A" and "2B" are greater than 45% speed.
INITIATING CUES:
Place Recirc Pump "2A" and "28" in Master Manual Control.
Kolb - JP0406REClRCMM.DOCPage........ ..... ...... ............. ........ _
mrothy
LR-JP-04.06-16
Page 6 of 6
start
time: -
RESPONSE CUE: N/A
both
NOTE: When the PF lamp is lit, the vertical barograph and the digital display
indicate the controller output. Depressing the PF key will switch off the
PF lamp and the controller input will then be displayed on both the vertical
barograph and digital display.
(** Indicates critical step)
......Page ..
LR-JP-04.06-1 6
Page 7 of 6
"A" gren pusbutto
thealll
REPNECU: SpenonrlertB1 r621, ManualR6M" Ambei ghAto
iilluminated.
PROMPT: IF the operator asks permission to reduce to perform
powerthat the next isstep,
power reduction
INFORM the operator as the Shift Supervisor
permitted.
RESPONSE CUE: N/A
- 2]]At
S*places panel 2H11I-P602,
Recirc pump 2BtheSpeed
operator
~~Control, .,
2B31-R621B, in Auto, the "A"
~green pushbutton illuminated.
RESPONSE CUE: Speed Controller, 2B331-R6211B, Manual "M" amber light
illuminated.
PROMPT: If the operator addresses changing Reactor power in Master Manual Control,
the
as the Shift Supervisor, inform the operator that you want to maintain
present Reactor power level.
(** Indicates critical step)
Uhi~hT Kolb-
i o JP00406REC]RCMM.DOC
- , =........... .... . .. ......
t.--
.. . ... . .... --. . m*
-
e
--.
LR-JP-04.06-16
Page 8 of 6
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double thb
allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
TITLE
INITIATE EMERGENCY TORUS VENTING USING THE EMERGENCY
VENT PATH
AUTHORý ýMEDIA NMBER TIME
R. A. BELCHER LR-JP-13.53-10 12.0 Minutes
RECOMMENDED BY A V Y DATE
N/R R. A. BELCHER 03/07/2002
SOUTHERN
k
COMPANY
Energy to Serve Your World V
OPERATIONS TRAINING Media Number: LR-JP-13.53
Program/Course Code:
itiias ,jfiltiasi
Rev. No r~ir~e~ibu
JEM DHG
01 08/01/90 General revision and format change
JLA DHG
02 05/24/91 General/procedure revision
General revision and format change WMM SCB
03 08/18/92
06/23/93 Task change, rename, procedure change, word RAB RSG
04
processor change
12/02/93 Change initiating cue to a command, change valve
ding to match the plant
06/17/96 Format change, modify time allowance
02/04/00 Format modification, title change, change time
allowance based on running average
11/02/00 Include objective number
01/03/02 Change Unit 2 control pressure to 56
03/07/02 1Include initial operator statement
LR-JP-13.53-101
Page 1 of
UNIT 1 (X) UNIT 2 (X)
.TITLE: INITIATE EMERGENCY TORUS VENTING USING
THE EMERGENCY VENT PATH
i JPM NUMBER: LR-JP-13.53-10
T,ASK STANDA This task shall be completed when the Torus is lined up to vent
via the Emergency Vent per 31EO-EOP-101.
TASK NUMBER 013.053
OBJECTIVE NUMBER: 013.053.O
PLANT HATCH JTA IMPORTANCE RATING:
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)
34SO-T48-002-1S Rev 19 34SO-T48-002-2S Rev 19
Ed 2 Ed 3
31EO-EOP-101-1S Rev 3 31EO-EOP-101-2S Rev 4
31EO-EOP-012-1S Rev 4 31EO-EOP-012-2S Rev 4
REQUIRED M4ATERIALS: Un,*fit 1 ,Ui,
31EO-EOP-101-1S 31EO-EOP-101-2S
(current revision) (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.
2. 31EO-EOP-012-1S (PC-i) is in progress.
3. Standby Gas Treatment is in operation, taking a suction from the Reactor
Building.
4. Torus Venting with CAD is in progress and Torus pressure cannot be
maintained below 54 psig.
5. Normal AC Power is available.
INITIATING CUES:
Perform Torus venting using the emergency vent path per
31EO-EOP-101-1S, Step 3.1.6.
LR-JP-13.53-10
Page 3 of 3
STA NDAP I SATNSAT/
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.
I., IClose SBGT4iletIsoi436tYaP&Yl At panel 1H 11-P654, the operator
1748-108. CLOSES 1T48-F081, SBGT
INLET ISOL VLV, green light
illuminated.
RESPONSE CUE: Valve 1T48-F081, red light illuminated.
3. Close or verify closed SBGT Inlet At panel IH 11-P654, the operator
Isolation Bypass Valve, 1T48-F083. CLOSES or verifies closed
illuminated.
- 4. Plac* 1T4!6-COlA* SBGT'A ýFato 9I At panel IH11 -P657, the operator
Off an ts thatthefeii stdps. PLACES 1T46-CO01A, SBGT A
V FAN to OFF, green light
illuminated and VERIFIES that
fan stops.
RESPONSE CUE: SBGT A Fan, 1T46-CO01A, red light illuminated
- 5 Place 1+/--C0 , SBGTB*ato4 At panel 1H 11-P654, the operator
- OFF and cqnfirm that th n sbf PLACES lT46-COOlB, SBGT B
j... Fan to OFF, green light
illuminated and VERIFIES that
fan stops.
RESPONSE CUE: SBGT A Fan, 1T46-COU1B, red ngnt llunminateu.
(** Indicates critical step)
LR-JP-13.53-10
Page 4 of 4
STEP] PROM NESE SADR (COMMENTS).:
A/NA
- 6. PlI At panel IH11-P657, the operator
Da r to cseqCnt*rol . CLOSES 1T46-F005, DISCH
CONTROL DAMPER, green
light illuminated.
RESPONSE CUE: Damper 1T46-F005, red light illuminated.
- 7* 1nstallju~per from UU-4z8 to&UUA6 4*At panel 1Hi11-P6OlD, the
S 1 T48-F326, ,;: :: ,:*, '>...... <,* from uu-48 to uu-61, for valve
RESPONSE CUE: N/A
- rAt panel 1H11-P602A, the
m panel.1HI- .60 operator INSTALLS a jumper
lT48-F*i.: from AA-70 to AA-81, for valve
RESPONSE CUE: N/A
. On Vn v3 At panel 1H 11-P601, the operator
I . ... I . ..... ...
............ OPEN..S 1T48-F326, TORUS
li: VENT VLV, red light
RESPONSE CUE: Valve 1T48-F326, green light illuminated.
I*1. Ope Torus VentValve, 1148-P318. At panel 1H11-P602, the operator
OPENS 1T48-F318, TORUS
VENT VLV, red light
........... i lu minat ed .
RESPONSE CUE: Valve 1T48-F3 18, green light illuminated.
PROMPT: IF addressed by the operator, as the Shift Supervisor, INFORM the
operator that the EOF Dose Assessment Staff and the TSC HP Supervision
have been notified of the potential radioactivity release.
Oe
911., *:oustme..g.nc**y VeX"tValve, At panel IHl 1-P654, the operator
0T48F2.' << OPENS 1T48-F082, SUPP
CHBR EMER VENT VLV, red
light'illuminated.
RESPONSE CUE: Valve IT48-F082, green light luumlnateu.
(** Indicates critical step)
LR-JP-13.53-10
Page 5 of 5
S-'ýPiiiORMA
.,V iý SAT/[NSAT *'
PROMPT: IF the operator addresses Torus pressure, INDICATE for the operator that
Torus pressure is <54 psig and decreasing.
PROMPT: IF the operator addresses System Restoration, INFORM the operator as the
Shift Supervisor that it is not desired at this time.
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Unit 2 Torus pressure is above the Pressure Suppression Pressure.
2. 3 1EO-EOP-012-2S (PC-i) is in progress.
3. Standby Gas Treatment is in operation, taking a suction from the Reactor
Building.
4. Torus venting with CAD is in progress and Torus pressure cannot be
maintained below 56 psig.
5. Normal AC Power is available.
INITIATING CUES:
Perform Torus venting using the emergency vent path per
31EO-EOP-101-2S, Step 3.1.6.
LR-JP-13.53-10
Page 7 of 7
STE E O ANCE STZP .
STAN.A. (COMMENTS)
START
TIME: iiI
. operator identifies the materials that Operator identifies the required
are required. materials and where to obtain
I them.
PROMPT: IF addressed by the operator, as the Shift Supervisor, INFORM the
operator that another operator is monitoring the NPSH curves for RHR and
PROMPT: IF addressed by the operator, INFORM the operator that normal AC power
and Non-interruptible air are available.
Close SBG Inlet Isolation At panel 2H 11-P654, the operator
2T4........ CLOSES 2T48-F081, SBGT
x* INLET ISOL VLV, green light
illuminated.
RESPONSE CUE: Valve 2T48-FO81, red light illuminated.
3. Close or verify closed SBGT Inlet At panel 2H1 11-P654, the operator
Isolation Bypass Valve, 2T48-F083. CLOSES or verifies closed
illuminated.
- 4 a2 - AAt operator
panel 2H111 -P657, theSBGTA
OFF'anidverifyttat 2T46-EOF , PLACES 2T46D~A SG
SBGT AFilter ,2T46-FOO2A,
Discfhatgeýcloses:::i*!!*i* to OFF, green light
FAN/FILTER FLTRDISCH
.......... :: and
illuminated FLTR
246-1F002A, DISCHthat
VERIFIES
CLOSES, green light illuminated.
RESPONSE CUE: SBGT A Fan/Filter, 2T46-DOO1A, red light illuminated and/or
Damper, 2T46-FO02A, red light illuminated.
145
- st: a~i P1rrAt panel 2H11-P601D, the
inpanef operator INSTALLS a jumper
2 2 from UU-45 to UU-61, for valve
RESPONSE CUE: N/A
(* Indicates critical step)
LR-JP-13.53-10
Page 8 of 8
SADR A/NA rEJOMN
STEPý
V s.aAt panel 211 -P602A, the
in p6 operator INSTALLS a jumper
2 1 .. . . * from AA-70 to AA-73, for valve
... . 2T48-F318.
RESPONSE CUE: N/A
I OpenjbisVent Va At panel 2H11 1-P601, the operator
OPENS 2T48-F326, TORUS
VENT VLV, red light
illuminated.
RESPONSE CUE: Valve 2T48-F326, green light illuminated.
- 8. pe nTorus: Vent ve,4-31 8. At panel 2H 11 -P602, the operator
OPENS 2T48-F3 18, TORUS
VENT VLV, red light
- illumrinated.
RESPONSE CUE: Valve 2T48-F318, green light illuminated.
9. Close or confirm closed Torus At panel 2H111 -P654, the operator
Emergency Vent Drain Valve, VERIFIES that 2T48-F085,
2T48-F085. SUPP CHMBR EMERG VENT
¶O.Opne T sEmergency Ye&YtveJ K At panel 211-P654, the operator
2........- OPENS 2T48-F082, SUPP
rdlight illuminated.
RESPONSE CUE: Valve 2T48-17082, green lngnt iummateu.
PROMPT: IF the operator addresses Torus pressure, INDICATE for the operator that
Torus pressure is <56 psig and decreasing.
PROMPT: IF the operator addresses System Restoration, as the Shift Supervisor,
INFORM the operator that it is not desired at this time.
END
TIME: 1:;2
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double
the allotted time.
- Operator states the task is complete.
(** Indicates critical step)
LR-JP-13.53-10
Page 9 of 9
STEP :PtRFRMANCSTP. tSAAD$TUNA
TERMINATING CUE: We will stop here.
"3/4..>
(** Indicates critical step)
TimthyK9ýIb PW2ISDOC
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
SOUTHERN fl
COMPANY
Energy to Serve Your World"
I
riohKob-JP25O5OHPCI .DOC ___............................. Pa_____
Page
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of 1
FORM TITLE: TRAINING MATERIAL REVISION SHEET
Program/Course Code: OPERATIONS training Media Number: LR-JP-25050
2
Page
Timothy KoIb - JP25050HPCI.DOC
LR-LP-25050-00
Page 3 of 9
UNIT 1 ( ) UNIT 2 (X)
1PERFORM A MANUAL STARTUP OF HPCI AND
ID MAINTAIN REACTOR WATER LEVEL IN BAND
LR-LP-25050-00
The task shall be completed when the HPCI System is injecting
S$,
- to the Reactor with turbine speed greater than 2000 rpm per
0 111 34SO-E41-001-2S, and RWL is controlled in band.
005.002005.002
005.002.A005.002.A
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.003.00
SRO 3.003.00
K/A CATALOG NUMBER: 206000G009206000G009
K/A CATALOG JTA IMPORTANCE RATING:
RO 4.304.30
SRO 4.004.00
OPERATOR APPLICABILITY: Reactor Operator (RO)
APPROXIMATE COMPLETION TIME: 3.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
3
LR-LP-25050-00
Page 4 of 9
SIMULATOR SETUP
Simulator Initial Conditions:
1. Reset the Simulator to IC #121 and leave in FREEZE.
2. INSERT the following MALFUNCTIONS:
mfE51_109 RCIC Failure to Auto Start 00000
mfR22_180 4KV Bus 2C Fault 00000
mfR22_181 4KV Bus 20 Fault 00000
mfE41 235A HPCI Fails to Auto Start on Low Level 00000
mfE41_235B HPCI Fails to Auto Start on Hi Drywell 00000
Pressure
mfN21_87A Feedwater Pump A Trip 00000
mfN21_87B Feedwater Pump B Trip 00000
3. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A. Perform RC-1 and RC-2.
B. Allow simulator to mn until RWL as indicated on 2B21-R623A and B is <-80
inches.
C. Acknowledge annunciators.
4. Place the Simulator in FREEZE until the INITIATING CUE is given.
5. ESTIMATED Simulator SETUP TIME: 10 Minutes
4
I
[TimothyKolb - JP25050HPCI.DOC Pa e
LR-LP-25050-00
Page 5 of I
-V
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. 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".
JP25O50HPCI.DOC [TimothyKo.b- Pae
LR-LP-25050-00
Page 6 of 1
start
time: -
PROMPT: If the operator addresses HPCI suction transfer logic, as the Shift
Supervisor, inform the operator that the HPCI high Torus level suction
transfer logic has been overridden.
-, 'ýN 'b kl'W ,ýA ae 2H1 l-P601, LUBE OIL
01 ui 4. CLG WTR VLV, 2E41 -F059 is
!*;*1open, red light illuminated.
RESPONSE CUE: Valve, 2E41-17059, green light illuminated.
2. Start HPCI Barometric Condenser At panel 2-11 -P601, HPCI
Vacuum Pump, 2E41-C002-2. BAROM CNDSR VACUUM
PUMP, 2E41-C002-2 is
operating, red light illuminated.
PROMPT: If the operator addresses posting High Radiation Areas, as the Shift
Supervisor, inform the operator as Shift Supervisor that Health Physics is
posting the areas.
NEW At panel 2H1 1-P601, the TURB
STEAM SUPPLY VLV,
2E41 -F001 control switch is in
i the OPEN position, red light
p ,illuminated.
RESPONSE CUE: Valve, 2E41-FOO1, green light illuminated.
NOTE: Valve 2E41-F001 is not required to be full open prior to proceeding to
following steps.
At panel 2H11-P601, the AUX
- , 4 2 i I § digu
OIL PUMP, 2E41-C002-3, is
Soperating, red light illuminated.
RESPONSE CUE: HPCI Auxiliary Oil Pump, green light illuminated.
S* *1At panel 2H11 l-P601, PUMP
is open, red light illuminated.
RESPONSE CUE: Valve, 2E41-F006, green light illuminated.
(** Indicates critical step)
' I _ Page
[Timothy ~( - JP25050HPCI.DOC__
LR-LP-25050-00
Page 7 of 6
IfTis
Confirm the following valves are At panel 2H1 1-P601, the
open: following valves are open, red
light illuminated:
TURBINE CONTROL VLV
NOTE: If HPCI is started per the Placard, the following steps may be omitted.
(** Indicates critical step)
,Timothy Kolb - JP25050HPCI.DOC Fiage
LR-LP-25050-00
Page 8 of 6
10. Confirm the following valves are At panel 2HI l-P602, the operator
closed: has confirmed the following
2141 -F7028 valves are closed, green light
illuminated:
2E41-F025 2E41-E028, STEAM LINE
2E41-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 2H11 -P601, the operator
Condensate Pump, 2E41-C002-1 has verified HPCI BAROM
cycles automatically to maintain CNDSR LEVEL HIGH
barometric condenser water level, annunciator (601-129) is clear.
PROMPT: If the operator addresses HPCI BAROM CNDSR LEVEL HIGH, indicate
for the operator that it is extinguished.
PROMPT: If the operator addresses CST level or Torus water level, indicate for the
operator that CST level is 25 feet and Torus level is 148 inches.
PROMPT: If the operator addresses shutting down HPCI, as Shift Supervisor, inform
the operator that shutdown is not desired at this time.
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double the
allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
I (*' Indicates critical step)
rlnomt hyKolb -JP25O42Rec irc.D OC- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
START A RECIRC MG SET FROM THE CONTROL ROOMSTART A RECIRC
MG SET FROM THE CONTROL ROOM WITH FAILURE OF PUMP SEALS.
Dale MoranR. L. SMITH LR-JP-25042-OOLR-JP-25042-OO 3g.038.O Minutes
t. f. phillips r. s. grantham 10/07/02
SOUTHERN Lka
COMPANY
Energy to Serve Your World"
1
Tm5042Recirc .. Page
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page I of 1
FORM TITLE: TRAINING MATERIAL REVISION SHEET
Program/Course Code: OPERATIONS training Media Number: LR-JP-25042
2
LiTrmoth Kolb - JP25042RecirC.DoC wag
LR-JP-25042-0O
LR-JP-25042-00
Page 3 of 2
UNIT 1 0 UNIT 2 (X)
r r :T, 2r11R
START A RECIRC MG SET FROM THE CONTROL
ROOM WITH FAILURE OF PUMP SEALS.
R ILR-JP-25042-00
The task shall be completed when the Recirculation Motor
Generator set has been started and then Reactor Recirc
Pump is secured and isolated, per 34AR-602-116-2.
77 004.002004.002, 004.003
004.002.A004.002.A, 004.003A
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.503.50, 2.79
SRO 3.223.22, 3.15
K/A CATALOG NUMBER: 202001A401202001A401, 202001A210
K/A CATALOG JTA IMPORTANCE RATING:
J~
RO 3.303.30, 3.50
SRO 3.103.10, 3.90
OPERATOR APPLICABILITY: Reactor Operator (RO)
N/A 34SO-B31-001-2 Rev 31.6
34AB-B31-001-2 Rev 7.3
34AR-602-116-2 Rev 2.2
34AR-602-122-2 Rev 4.4
V¶~ kr. A ~0
N/A
Attachment 5
(current revisions)
APPROXIMATE COMPLETION TIME: 38.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
3
[Timothy Kolb -iJP25042Recirc. DOC , .................... . .....................
LR-JP-25042-00
Page 4 of 9
SIMULATOR SETUP
Simulator Initial Conditions:
1. Reset the Simulator to IC #121 and leave in FREEZE.
2. Insert the following Malfunctions:
MALF# TITLE FINAL RAMP ACT.
I VALUE RATE TIME
mfB3139A RECIRC 2A INNER SEAL FAILURE 9999
mfB31 45A RECIRC 2A OUTER SEAL FAILURE 9999
3. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A. Stop Reactor Recirc Pump 2A(B); close and then throttle the discharge valve open,
and reduce 2B31-R621A speed to 30%.
B. Reset annunciators (602-106) PUMP MOTOR A (B) OIL LEVEL HIGH and
(602-112) PUMP MOTOR A (B) OIL LEVEL LOW.
C. Lower the Operating Recirc Pump Speed to reduce Recirc Flow to <22,000gpm
D. Backout the 2A RFPT to -2000 rpm.
E. Insert Rod groups 44H and 44G to "00" position.
4. Place the Simulator in FREEZE until the INITIATING CUE is given.
5. ESTIMATED Simulator SETUP TIME: 10 Minutes
-V
4
L
LTmoyKolb- P25042Recirc.DOC . Pas
LR-JP-25042-00
Page 5 of 2
- J
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 Al, A2 (B1, 62) are running.
- J
4. Reactor Recirc Pump 2B(A) is still in operation.
5. Other operators are performing ATTACHMENT 5 through step 7.1.
1kteolqlpW4-. .
INITIATING CUES:
Start 2A(B) Recirc Pump, using the normal startup section 7.1.2 of
[Timothi Koib - JP25042Recirc DOC Page
LR-JP-25042-00
Page 6 of 2
start
time: -
1. Operator reviews the procedure's Operator has reviewed the
precautions and limitations, precautions and limitations.
(Section 7.1.2)
PROMPT: If addressed by the operator, inform the operator that PUMP MOTOR
2A(B) OIL LEVEL HIGH 602-106 (206), and PUMP MOTOR 2A(B) OIL
LEVEL LOW 602-112 (212) are cleared.
PROMPT: If addressed by the operator, inform the operator that the MG Set A(B) lube
oil system is in operation.
PROMPT: If addressed by the operator, inform the operator that the Generator Lockout
Reset Switch, on panel 2B31-P003A(B), is RESET and the yellow flag is
RESET.
PROMPT: If addressed by the operator, inform the operator that the Generator Field
Ground Detect Test Switch, at panel 2B331 -P003A(B), is in the NORM
position.
PROMPT: When the operator addresses lube oil temperature, as the SO, inform the
operator, that lube oil temperature is 105'F.
PROMPT: IF addressed by the operator, INDICATE to the operator that Recire loop A
is not isolated.
PROMPT: When the operator addresses the Seal Purge Isolation valves, as the SO,
inform the operator that the valves are open.
2. Verify Reactor Recirc Pump Suction At panel 2H1 1-P602, PUMP
Valve, 2B 31-F023A(B) is open. SUCTION VLV,
2B331-F023A(B) is open, red light
illuminated.
PROMPT: When the operator addresses the Seal Flow Regulator, if necessary indicate
that the plant is at rated pressure, as the SO, then inform the operator that it
is set at 2 gpm.
PROMPT: If addressed by the operator, inform the operator it is not required to vent
the Recirc pump seals.
(** Indicates critical step)
-'JP25042Recirc.DOC
Page
[itmoj lv
LR-JP-25042-00
Page 7 of 7
N
,g ý, "Nýo 3-
'J PON Qig 1-0100 '0 "A
jil
I.
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 2H11 -P602, SPEED
CONTROL, 2B31-R621A(B), is
in manual, amber manual
pushbutton light illuminated.
At panel 2H11 -P602, the Speed
Demand Indicator,
2B31-R661A(B), has been
adjusted to 44% +-4%.
RESPONSE CUE: Reactor Recirc Pump 2A(B) Speed Control, 2B31-R621A(B), is not
at 44%.
6. Confirm annunciator 602-126(226) At panel 2H11 -P602, operator
Fluid Drive A(B) Scoop Tube Lock, verifies 602-126(226) FLUID
clear. DRIVE A(B) SCOOP TUBE
LOCK is clear, window is
extinguished.
7. Verify RWL is greater than +32 At panel 2H1 1-P603, the operator
inches. verifies that RWL is greater than
+32 inches.
NOTE: The evalualtor must put current time on step 7.1 prior to giving the
copy to the operator.
PROMPT: When the operator addresses ATTACHMENT 5, PROVIDE the operator
with the marked up copy of ATTACHMENT 5.
Confirm or start Reactor Recirc 2A(B) At panel 2H11 -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 2H111 1-P602, PUMP
closed, green light illuminated.
RESPONSE CUE: Discharge valve, 2B31-F031A(B), red light illuminated.
(** Indicates critical step)
Timotiy Kolb - JP25042Recirc.DOC ..
LR-JP-25042-00
Page 8 of 7
OWN
au
I&*t*17At panel 2H1I-P602, RX
P(,[ 22B31-SOOIA(B) started, red light
T I 4 illuminated.
RESPONSE CUE: Reactor Recirc Pump MG Set, 2B31-S001A(B), green light
illuminated.
11. Complete remainder of Attachment 5. Attachment 5 has been completed
through step 7.4.
AFTER the pump is started and the Discharge valve is full open, ENTER
MALFUNTIONS mfB31_39A, "RECRIC PUMP 2A INNER SEAL FAILURE" and
mfB31_45A, "RECIRC PUMP 2A OUTER SEAL FAILURE"
12. Address ARPs 34AR-602-116-2 At panel 2H11-P602, ARPs
34AR-602-116-2 are addressed.
13. Confirm 2B31-R603A, Seal A No.1 At Panel 2H1 1-P602,
pressure indicator decreases, and Seal DETERMINE 2B31 -R603A, Seal
A No. 2 pressure indicator decreases. A No.1 pressure indicator
decreases, and Seal A No. 2
pressure indicator decreases.
RESPONSE CUE: N/A
PROMPT: IF the operator addresses having leakage checks per 34SV-SUV-019-2,
Surveillance checks, to determine magnitude of the leak. inform the
operator another operator will perform the leakage calculations.
14. Confirm an increase in FPM to At panel 2HI -P645, monitor
determine that Reactor coolant is 2D1 l-R630, FPM recorder, to
leaking from the seals, at monitor DETERMINE if primary coolant
2D11-R630, fission Products recorder, is leaking from the seals by
observing an increasing trend.
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)
oimtvKolb-JP25042Recirc.DOC PL
LR-JP-25042-00
Page 9 of 7
rTEPI 41 UVM
15. Confirm an increase in Drywell At panel 2H1 1-P602 OR 2HI 1
pressure on 2T48-R607A/B, Narrow P654, DETERMINE an increase
Range Drywell/Torus Wtr. Lvi in Drywell pressure trend on
Recorder(s). recorder(s) 2T48-R607A/B.
RESPONSE CUE: N/A
16. Shutdown the 2B31-S001A, MG Set At panel 2H11 l-P602, Rx Recirc
IA. MG Set 2B331-SOO1A is SHUT
I I DOWN, green light illuminated.
RESPONSE CUE: Reactor Recirc Pump MG Set, 2B31-S001A(B), red light
illuminated.
At panel 2H11 -P602, CLOSE Rx
Recirc MG Set 2B31-S001A:
Discharge Valve 2B31 -F03I A,
and Suction Valve 28331-F023A,
green lights illuminated.
RESPONSE CUE: Discharge Valve 2B31-F0031A or Suction Valve 2831-F023A, red
light illuminated.
- J
PROMPT: WHEN addressed by the operator, to CLOSE seal purge valve 28331
F0008A, INFORM the operator that another operator will be dispatched to
CLOSE the seal purge valve 28331-F008A.
END
time:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double thc
allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
Fimothv Koib - JP10.19MODESW.Doc Pagqe
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
( RANSFER THE
WITH AN APRM AT 15%
ODE SWITCH T
POWER
Dale MoranR. L. SMITH LR-JP-10.19-00LR-JP-10.19-00 38.010.0 Minutes
t. f phillips r. s. grantham 10/7/02
SOUTHERN wa
COMPANY
Energy to Serve Your World'"
1
I
Ko JP10.19MODESW DOC
- SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of 1
FORM TITLE: TRAINING MATERIAL REVISION SHEET
Program/Course Code: OPERATIONS training Media Number: LR-JP-10.19
01 10/7/02 Initial development. ris rsg
2
I Timothy Kolb - JP10.19MODESW.DOC .p..
LR-JP- 10.19-00
Page 3 of 2
UNIT 1 0 UNIT 2 (X)
TRANSFER THE MODE SWITCH TO
STARTUP/HOT STANDBY, WITH APRM AT 15%
POWER
FAIN", LR-JP-10.019
The task shall be completed when the APRM is bypassed
IIIr1a, and the Mode switch is transferred to Startup/Hot Standby.
004.002010.019
004.002.AO10.019A
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.50
SRO 3.22
K/A CATALOG NUMBER: G2.1.23202001A401
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.93.30
SRO 4.03.10
OPERATOR APPLICABILITY: Reactor Operator (RO)
APPROXIMATE COMPLETION TIME: 10 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
3
im Kolb - JP10.19MODESW.DOCp,
LR-JP-10.19-00
Pa 4. of 9
SIMULATOR SETUP
Simulator Initial Conditions:
1. Reset the Simulator to IC #105 and leave in FREEZE.
MANIPULATIONS:
2. Take the Simulator OUT OF FREEZE and PERFORM the following
A. Place the Mode Switch to RUN position
3. Insert the following Malfunctions:
MALF# TITLE FINAL RAMP AT.
I IVALUE RATE TIME
0000
mfCSll9A LPRM UPACALE 'B' LEVEL 20.29 0000
mf603233379 LPRM UPSCALE ALARM OFF
4. Place the Simulator in FREEZE until the INITIATING CUE is given.
5. ESTIMATED Simulator SETUP TIME: 10 Minutes
24
LTothIy Kolb - JP10.19MODESW. D P.a..
LR-JP- 10.19-00
Page 5 of 2
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Reactor Shutdown is in progress; steps through 7.3.16 of
34GO-OPS-01 3-2 have been completed.
2. The refueling bridge has power to it.
3. The SOS has reviewed Attachment 3 of 34GO-OPS-013-2 with the
operating crew.
4. All IRMs and SRMs are Operable.
5. All required neutron surveillances for APRMs, IRMs, and SRMs are
completed SAT.
INITIATING CUES:
Transfer the Mode switch to Start & Hot Standby per 34GO-OPS
013-2.
hyy Kolb - JP10.19MODESW.DOC _, ,,,,_ Page
LR-JP- 10.19-00
Page 6 of 2
start
time: -
1. 1 Operator reviews the procedure's Operator has reviewed the 1
precautions and limitations, precautions and limitations.
PROMPT: If addressed by the operator, inform the operator that the refueling bridge
has power to it per initial conditions.
2. Confirm that all OPERABLE IRMs At panel 2H11 -P603, the operator
channel Upscale Trip OR Inop lights VERIFIES that IRMs Upscale
are EXTINGUISHED. TRIP OR Inop lights are
EXTINGUISHED.
RESPONSE CUE: N/A
3. Confirms that INOPERABLE IRMs At panel 2H11 1-P603, the operator
AND/OR SRMs are bypassed. verifies that IRMs AND SRMs
INOP lights are extinguished.
RESPONSE CUE: N/A
RESPONSE CUE: N/A
NOTE: IF evaluating an RO and the RO identifies the 2B APRM reading > 11%
power the evaluator should declare the APRM INOP at this time.
PROMPT: IF the operator addresses checking the APRM 2B at the back panel for any
apparent problem, THEN as another operator INFORM the operator that
APRM 2B is reading 15%, and no apparent problem is indicated.
PROMPT: IF the operator request I&C assistance with APRM 2B. inform the operator
that several LPRMs inputting into APRM 2B appear to be out of calibration
and cannot be adjusted at this time.
PROMPT: IF the operator addresses placing the APRM 2B in bypass. inform the
operator to place the 2B APRM in bypass.
At panel 2H 11 -P603, the operator
PLACES the APRM 2B in
Bypass.
ET7QYt* Kolb- JP10.19MODESW.DOC -Pag
LR-JP-10-019-00
Page 7 of 5
EiEP
1
RESPONSE CUE: APRM 2B not in Bypass.
6. Confirm all rod blocks clear. At panel 2H11-P603, the operator
verifies 603-238 ROD OUT
BLOCK is clear, window is
extinguished.
PROMPT: IF the operator addresses SOS reviewing Attachment 3 of 34GO-OPS-013-2
with the operating crew. inform the operator that this has been reviewed per
the initial conditions.
- fl *I flJ**¢0o
dP the o 'i At panel 2H1 1-P603, the operator
places the Mode Switch into
I &* START & HOT STBY position.
RESPONSE CUE: The MODE switch is in RUN position.
8. Record the Time the Mode switch is The operator records the Time the
placed in START & HOT STBY. Mode switch is placed in START
& HOT STBY position in
34GO-OPS-0! 3-2.
9. Confirms the Annunciator "MSIV At panel 2H I l-P603, the operator
CLOSURE TRIP BYPASS" confirms 603-113 is illuminated.
illuminates.
RESPONSE CUE: Annunciator 603-113 is extinguished.
PROMPT: WHEN the operator addresses Confirming that the MSIV Closure Trip
Bypass relays are energized on Panels 2H11-P609/P61 1. inform the
operator that another operator will complete the rest of this section of the
procedure.
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double th(
allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(" Indicates critical step)
Tb - JP250O44RHRSW -D0C .P.. .. ... . .a..
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
CRSTERRSRVC RHR
AECOSTIE SRVICE WATER WITH
A FAILURE OF THE SECOND RHRSW PUMP TO START
_J2
t.f. phipilips r. s. grantham 10/07/02
SOUTHERN Ma
COMPANY
Energy to Serve Your World"
1
Tmoth KolD-JP5044RHRSW.DOG Page
SOUTHERN NUCLEAR OPERATING COMPANY
PLANT E. I. HATCH Page 1 of 1
FORM TITLE: TRAINING MATERIAL REVISION SHEET
Program/Course Code: OPERATIONS training Media Number: LR-JP-25044
10/07/02 Initial Development rls rsg
00
2
, P
w I OP
ZTimh'o 044RHRSW.DOC
LR-JP-25044-00
Page 3 of 9
UNIT 1 0 UNIT 2 (X)
CROSSTIE RHR SERVICE WATER WITH A
30 N '411
FAILURE OF THE SECOND RHRSW PUMP TO START
NNW I~~ 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
034.008034.008
~~Big
034.008.0034.008.0
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.293.29
SRO Not AvailableNot Available
K/A CATALOG NUMBER: 219000A215219000A215
K/A CATALOG JTA IMPORTANCE RATING:
RO 3.303.30
SRO 3.403.40
OPERATOR APPLICABILITY: Reactor Operator (RO)
APPROXIMATE COMPLETION TIME: 15.0 Minutes
SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING
PAGE
3
Lvmtx l -..JP25044RHRSW.DOC
. Page
LR-JP-25044-00
Page 4 of 7
SIMULATOR SETUP
Simulator Initial Conditions:
1. Reset the Simulator to IC #128 and leave in FREEZE.
2. INSERT the following MALFUNCTIONS:
3. INSERT the following ors OVERRIDES:
1,1 KK SrVAT U"
El1-C001lA RHR Service Water Pmp lB OFF 00000
El1-C001SBB RHR Service Water Pmp IB OFF 00000
El 1-C001D_A RHR Service Water Pmp 1D OFF 00000
El1-COOIDB RHR Service Water Pmp ID OFF 00000
Ell-F028ADI p RHR A Torus Spray/Test Vlv CLOSE 00000
Ell-F028A_A I RHR A Torus Spray/Test Vlv off 00000
Ell-F028A_B 1 RHR A Torus Spray/Test VIv off 00000
4. PLACE Danger Tags on the following equipment:
5. ESTIMATED Simulator SETUP TIME: 10 Minutes
(" Indicates critical step)
Page
Timoth lb - JP2544RHRSW.DOC
LR-JP-25044-00
Page 5 of 7
UNIT 2
READ TO THE OPERATOR
INITIAL CONDITIONS:
1. Unit 2 is at 75% power and Torus Cooling is desired.
2. RHR Service Water Pumps 2B and 2D have been removed from service.
3. 2E1 1-F028A is tagged closed for corrective maintenance.
INITIATING CUES:
Crosstie the "A" loop of RHR Service Water to the "B" loop of RHR
Pa
_moth_ Kolb - JP25044RHRSW.DOC
LR-JP-25044-00
Page 6 of 7
start
time: -
1. Operator identifies the procedure Operator has identified the correct
needed to perform the task. procedure as 34SO-El 1-010-2S
(Section 7.2.6).
NOTE: It will not be necessary to override the RHRSW pump LOCA signal in this
condition, but to do so will not prevent system operation.
2. Depress the RHR Service Water Lube At panel 2H1 1-P601, operator has
Valves push-button on 2H1 -P601. depressed the RHR SERVICE
WATER LUBE VALVES push
button.
PROMPT: If the operator addresses waiting for one minute, inform the operator that
one-minute has elapsed.
PROMPT: If the operator addresses obtaining Shift Supervisor's permission to crosstie
RHRSW loops, inform the operator that the Shift Supervisor has given
permission to crosstie RHRSW loops.
I 1< At panel 2H l-P601, operator
opens SERV WTR CROSSTIE
VLV 2El 1-F119A, red light
illuminated.
RESPONSE CUE: Valve 2E1 I-Fl 19A, green light illuminated, red light extinguished.
At panel2 -P601,operator
opens SERV WTR CROSSTIE
VLV 2E1 l-F119B, red light
illuminated.
RESPONSE CUE: Valve 2El 1-F 19B, green light illuminated, red light extinguished.
5. Operator places the Interlock Override At panel 2H11 -P601, the
valve 2E1 1-F068B Keylock Switch in Operator places the Interlock
the Override position. Override Valve 2E 1 -F068B
Keylock Switch in the Override
position.
RESPONSE CUE: N/A
NOTE: Using the Override Switch for 2E1 I-FO68A is not required, but if
performed, should be noted. Overriding 2E1 l-FO68A will not affect the
(** Indicates critical step)
Page..
Timoth Koilb - JP25044RHRSW.DOG
LR-JP-25044-00
Page 7 of 7
~CIE'
performance of the JPM.
6. Set the Heat Exchanger B Differential At panel 2H 11 -P601, the operator
Pressure Control Valve Controller, sets HX B DIFF PRESS
2E1 1-R600B to 40% OPEN. CONTROL VLV F068B
controller, 2E1 1-R600B to 40%
OPEN.
7. Confirm the following: At panel 2111 l-P601, the operator
S2EI 1-F068A(B) OPENS (RED light CONFIRMS that 2E1 1-F0681
ILLUMINATES) Opens red light illuminates, and
RHR HX A(B) DIFF PRESS LOW LOW Annunciator illuminates.
annunciator ILLUMINATES
NOTE: RHRSW Pump A or C may be started first. Therefore Steps 8 and 12 may
be interchanged.
RESPONSE CUE: SERVICE WATER PUMP 1A, green light illuminated, red light
extinguished.
PROMPT: IF the operator asks the Shift Supervisor if another RHRSW pump should
be started at this time, INFORM the operator that another RHRSW pump is
required to be started at this time.
"I (** Indicates critical step)
. P...
T Kolb - JP25044RHRSW.DOC
LR-JP-25044-00
Page 8 of 7
I
10. Depress the RHR Service Water Lube At panel 211I-P601, operator has
Valves push-button on 2H1 -P601. depressed the RHR SERVICE
WATER LUBE VALVES push
button.
11. Adjust Diff Press Control Vlv At panel 2H1I 1-P601, operator has
2E 1-F068B to obtain desired adjusted HX B DIFF PRESS
RHRSW flow rate, then open CONTROL VLV F068B
2E] 1-F0681 an additional 5%. controller, 2El 1-R600B, to obtain
desired flow rate, and then an
additional 5% is added.
Flow rate limit, prior to adding
5%, is 4400 gpm (+0, -200 gpm).
Pressure limit for RHR Service
Water is less than 450 psi.
NOTE: Flow rate will be monitored on PUMP TEST FLOW indicator
2E 1-R619A and/or SERV WATER FLOW indicator 2El 1-R602A.
Pump discharge pressure will be monitored on DIV I PRESSURE
indicator 2E1 l-R650A.
f** ; NYAt panel 2n1 l-P601 operator
~2El11-C001C. INS, starts SERVICE WATER PUMP
RESPONSE CUE: N/A
AFTER the second RHRSW pump is started and Flow is increased to -7000 gpm enter,
pump.
MALFUNCTION mfEll 120C, RHRSW 2C Pump Trip, to trip the RHRSW
13. Enter ARP 34AR-601-325-2S, At panel 2H11 -P601, the operator
RHRSW PUMP 2C TRIP. enters the ARP for RHRSW
PUMP 2C TRIP, NO actions
apply.
(** Indicates critical step)
WmothvKolb- JP25044RHRSW.DOC Pa e-
LR-JP-25044-00
Page 9 of 7
wfEMR
PROMPT: When the operator informs the SS of the Trip of 2C RHRSW pump, inform
the operator that you will contact Maintenance to investigate the pump Trip.
PROMPT: When the operator addresses starting RHR, inform the operator that another
operator will start that system.
PROMPT: If the operator addresses the in-service RHR Service Water strainer
differential pressure, inform the operator that another operator is monitoring
this differential pressure and it is below 6 psid.
-V
END
TIME:
NOTE: The terminating cue shall be given to the operator when:
- With no reasonable progress, the operator exceeds double th(
allotted time.
- Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
Southern Nuclear
E. I. Hatch Nuclear Plant
Operations Training
'TITLE:
TRANSFER AN EMERGENCY 4160 VAC BUS FROM THE EMERGENCY TO
THE NORMAL POWER SUPPLY
AUTHOR ... .. TA SLJMBER . . .. . E
R. A. BELCHER LR-JP-27.11-14 22.0 Minutes
RECOMMENDED By AYD
N/R R. A. BELCHER 03/11/2002
SOUTHERN Uk
COMPANY S.
World
Energy to Serve Your
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
RevNo 9[Dte ~tao tRvso Auth r'ýjSupv's
__________IIniftil A . Initial
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 1 section
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 (UI) 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 1section 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
LR-JP-27.1 1-14
Page 1 of 1
UNIT 1 (X) UNIT 2 (X)
TSK TITLE: TRANSFER AN EMERGENCY 4160 VAC BUS FROM
THE EMERGENCY TO THE NORMAL POWER
SUPPLY
JPM NUMBER:
LR-JP-27.11-14
TASK, STANDAD: The task shall be completed when the operator has transferred the
"F' 4160 VAC Emergency Bus power supply from the
associated Emergency Diesel to the "D" Startup Transformer, per
34SO-R43-001, with exception of placing the selected Diesel
Generator in Standby.
T U027.011
OBJECTIVE' NUBR 027.011.0
PLANT HATCH JTA IMPORTANCE RATING:
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)
.GENERAL REFERENCES:Uit
34AR-652-202-2S Rev 4
34SO-R43-001-2S Rev 23 Ed 3
30AC-OPS-003-OS Rev 21 Ed 2
'REQUIRtD MATERIALS,:: (Ut) u&
(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:
REM#4,Tý
rfR43241 Diesel Gen 1B Engine Control Switch UNIT 2
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 "IB" 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/n ower supply ueirr-A%,3
34SO-R43-001-2S. ', . q.
L*.J . Ser r t'%
'ft(,ouj 6,, x F::- J6
AA-'-- Oth'e
LR-JP-27.11-14
Page 4 of 4
STE PEORMANCESE K STNAb
$T -'(COMMENSTS)
START
TIME:
1. Operator reviews the procedure. Operator has reviewed the
procedure.
2. Confirm power is available to Startup At panel 2H11 1-P651, the operator
Transformer "2D." has VERIFIED that S/U AUX
XFMR 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-003-0S.
....
Rese.he.Bus "2F" LOSPt6c6u'2t!.E At panel 2H11-P652, BUS 2F
.,Relay. <LOSPLOCKOUTRELAY
switch TURNED clockwise and
HELD until its white light
illuminates.
RESPONSE CUE: Bus 2F LOSP relay locked out, white light extinguished.
4. Confirm annunciator; LOSS OF At panel 2H1 I-P652, operator
OFFSITE POWER has cleared. IDENTIFIES that annunciator
652-202, LOSS OF OFFSITE
POWER, has cleared.
- 5 Diesel, "B" Mode Se1e
Plae tt<
- ,At panel 2H1-1-P652, DIESEL
Swijeb e. jTES GEN B, MODE SELECT switch
is in TEST.
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 1B 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 5
S.
. ..*
. . . . * ...... . , , ¸4¸ ; * <[ U, N A* T *
ST P . ... ... ]1tMd* .. T
f. , .a. ... . .. .. . ... ..... ...... .. T . .*
I *6. Place the!:Voltage Regulator Trgjsf At panel 2H 11-P652, the
swi.tc to' anual., VOLTAGE REG TRANSFER
switch is in MANUAL, green
light illumintd
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.
Place S~ynch Switch for 41
- At panel 2-111-P652, SSW ACB
Supply ACB 13t55
2F Normal2FN0* *<t2 K I 135574, is in the ON position.
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 2H1-1-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 6
STE IP iO~'AN
PEFR
gT I# $TANA, -"SV
I CMENTSY
9. Adjust the "IB" Diesel Generator At panel 2H1 1-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-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.
the 16
- Close At panel 2HI 1-P652, 4160 "2F,"
ACB 135574. 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
t released to the midposition, red
+.......lightilluminated.
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 2H1 1-P652, DIESEL
400-500 kW with 400-500 kVar. 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
I.
I
STEP PERM~~AN"ESE
M.
S~i
IdNDAII $TINA"
(COMMENTS)
Trip Diesel Gnratorq&tputp At panel 2H 11-P652, DIESEL
ker. GEN B, EMERGENCY SUPPLY
. ACB 135570 control switch is
taken to TRIP and released to
....
, midposition, green light
illuminated.
RESPONSE CUE: ACB 135570, red light illuminated.
14. Confirm Diesel Generator output At panel 2H 11 -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 2H141-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)