ML022690280
| ML022690280 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/22/2002 |
| From: | Ernstes M Division of Reactor Safety II |
| To: | Scarola J Carolina Power & Light Co |
| References | |
| -RFPFR, 50-400/02301 50-400/02301 | |
| Download: ML022690280 (152) | |
See also: IR 05000400/2002301
Text
Final Submittal
(Blue Paper)
1I. Administrative Questions/JPMs
2. In-plant JPMs
3. Control Room JPMs (simulator JPMs)
SHEARON HARRIS
EXAM 2002-301
50-400
AUGUST 26 - 29, 2002
Examination Outline Form ES-201-2
Quality Assurance Checklist
Date of Examination: 26-Aug-02
Facility: HARRIS
Initials
Task Description a b* 1#
Item
a. Verify that the outline(s) fit(s) the appropriate model per ES-40 1.
I of
W b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.
R ES-401 and whether all knowledge and ability categories are appropriately sampled.
T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
E d. Assess whetherthejustifications fordeselected orrejected /A statements are appropriate. At6 LO' VW
N
number of normal
a. Using Form ES-30 1-5, verify that the proposed scenario sets cover the required
2. evolutions, instrument and component failures, and major transients. M &
projected number and mix of
S b. Assess whether there are enough scenario sets (and spares) to test the AT66
I applicants in accordance with the expected crew composition and rotation schedule without compromising
M exam integrity; ensure each applicant can be tested using at least one new scenario and scenarios will not be
repeated over successive days.
whether the outline(s) conform(s) with the qualitative and quantitative criteria * A,. C
c. To the extent possible, assessand described in Appendix D.
specified on Form ES-301-4
a. Verify that: in-plant tasks,
3. (I) the outline(s) contain(s) the required number of control room and
material is repeated from the last NRC examination, MS
(2) no more than 30% of the test
W (3) *no tasks are duplicated from the applicants audit test(s), and
bank.
test is taken directly from the licensee's exam
T/ (4) no more than 80% of the operating
b. Verify that:
1,
(1) the tasks are distributed among the safety function groupings as specified in ES-30
(2) one task is conducted in a low-power or shutdown condition,
procedure,
(3) 40% of the tasks require the applicant to implement an alternate path condition, and
applicant's response to an emergency or abnormal
(4) one in-plant task tests the
(5) the in-plant walk-through requires the applicant to enter the RCA.
activities. A re,
c. Verify that the required administrative topics are covered, with emphasis on performance-based
d. Determine if there are enough different outlines to test the projected number and mix of
applicants and A"3
days.
ensure that no more than 30% of the items are duplicated on successive
whether plant-specific priorities (including PRA and PE insights) are covered in the appropriate
a. Assesssection.
M6 @
4. exam
G b. Assess whether the 10 CFR 55.41143 and 55.45 sampling is appropriate. A6
E
N c. Ensure that K/A importance ratings (except for plarnt-specific priorities) are at least 2.5.
l
R d. Check for duplication and overlap among exam sections. 6
A A
L e. Check the entire exam for balance of coverage.
f. Assess whether the exam fits the appropriate job level (RO or SRO).
, w6
Printed Name / Signature Date
William J.Gros /,,-/-. 30 May 200 2
a. Author
b.Facility Reviewer(*) Ay'Ar T. 3ocd-oet (Zt~ rM SoJ I Ma~e- ceta.
F C '2- .
c. Chief Examiner(#)
d. NRC Supervisor 1 -L
0* r*, h . 1 C4 " t/2p/bL
Note: * Not applicable for NRC-developed examinations. See. a44oc
required.
- Independent NRC reviewer initial items in Column "c;" chief examiner concurrence
NUREG- 1021, Revision 8, Supplement I
HARRIS NUCLEAR PLANT - AUG 2002
tTý -TA oowr&OY4e L041 S'S-301 54er-4rb-A
0,0,6 Q- arp- -:ýt omlox +a +Awse +esA,6 oyl
4- 4e
Administrative Topics Outline FORM ES-301-1
Facility: HARRIS Date of Examination: 26-Aug-02
Examination Level: RO Operating Test Number: b
"Describe method of evaluation:
"-Administrative 1. ONE Administrative JPM, OR
Topic/Subject 2. TWO Administrative Questions
Description
(KA #)
"'A.
1 Determine Rod Misalignment Using Thermocouples (AOP-001)
CONDUCT OF
OPERATIONS
(2.1.19)
Perform a Manual Power Range Heat Balance Calculation
(OST-1204)
(2.1.25)
"A.
Review an Equipment Clearance (OPS-NGGC-1 301)
EQUIPMENT
CONTROL
(2.2.13)
"A.
RADIATION
CONTROL (2.311) ? 6 5Xzto(,c t @-'-V s p
"A.
4 Activate the Emergency Response Organization - Dialogic
EMERGENCY System (PEP-310)
PLAN
(2.4.43)
NUREG-1021, Revision 8, Supplement 1
Administrative Topics Outline FORM ES-301-1
HARRIS Date of Examination: 26-Aug-02
Facility:
Examination Level: SRO Operating Test Number:
"Describe method of evaluation:
"-Administrative 1. ONE Administrative JPM, OR
Topic/Subject 2. TWO Administrative Questions
Description I(KA #)
"A,1 Perform Review of Daily Surveillance Requirements Log
LA.JJ-,
-irnT
OPERAIONS
nc I(OST-1021)
OPERATIONS
(2.1.18)
Perform a Manual Power Range Heat Balance Calculation
(OST-1204)
(2.1.25)
2 Review an Equipment Clearance (OPS-NGGC-1 301)
EQUIPMENT
CONTROL
(2.2.13)
"A.
Question Topic - License Requirements for Conducting a Waste
3 Release with Inoperable Instrumentation and Administrative
Controls Ensuring Requirements Met (2.3.6)
RADIATION
CONTROL
Question Topic - Selection Process for Individuals Performing
Emergency Entries into Radiation Fields Resulting in Exceeding
Permissible Exposure Limits (2.3.4)
"A.
4 Perform an Emergency Action Level Classification and
Recommend Protective Actions (PEP-1 10)
PLAN
(2.4.41 / 2.4.44)
NUREG-1021, Revision 8, Supplement 1
Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2
HARRIS Date of Examination: 26-Aug-02
Facility:
RO Operating Test Number: 2002-301
Examination Level:
B.1 Control Room Systems
Safety
System/JPM Title Type Function
Code* (KA #)
NAS 3
a. Respond to a Failed High Pressurizer Pressure Channel (AOP-019) (010.A2.03)
b.NAS 6
LOOP While Paralleling EDG from MCB for Testing (OP-155) (064A4.01)
C. DS 8
Secure One Train of CCW to the RHR HXs (OP-145) (008A2.01)
d. DASL 5
Manually Align Containment Spray (PATH-l) (026A4.01)
e, DASL 2
Transfer to Hot Leg Recirculation (EPP-011) (006A4.05)
f. DSL 4P
Start an RCP Following Maintenance (OP-1 00) (003A4.06)
g. NS 7
Power Range NI Gain Adjustment (OP-1 05) (015A4.02)
B.2 Facility Walk-Through
a. DL 1
Local Actions for a Dropped Rod Recovery (AOP-001) (003AA1.02)
b.DRL 2
b. (004A2.11)
(AOP-017)
Manually Align Charging Due to a Loss of IA
c.DL 5
C. (028A4.01)
Start Up a Hydrogen Recombiner (OP-125)
path, (C)ontrol Room, (S)imulator,
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate
(L)ow-Power, (R)CA
NUREG-1021, Revision 8, Supplement 1
Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2
HARRIS Date of Examination: 26-Aug-02
Facility:
SRO-I Operating Test Number: 2002-301
Examination Level:
B.1 Control Room Systems
Safety
System/JPM Title Code* Function
NAa
a. Respond to a Failed High Pressurizer Pressure Channel (AOP-019) NAS 3
(010.A2 .03)
b.NAS 6
LOOP While Paralleling EDG from MCB for Testing (OP-155) (064A4.01)
DS08A.)
Secure One Train of CCW to the RHR HXs (OP-1 45)
(0264A4.01)
DS
d. (0264.01
Manually Align Containment Spray (PATH-l)
e.DASL 2
(006A4.05)
Transfer to Hot Leg Recirculation (EPP-011)
f.DSL 4P
(0034P
Start an RCP Following Maintenance (OP-100) (003A4.06)
Power Range NI Gain Adjustment (OP-105) (01 5A4.02)
B.2 Facility Walk-Through
a.DL 1
a. (003AA1.02)
(AOP-001)
Local Actions for a Dropped Rod Recovery
b. DRL 2
Manually Align Charging Due to a Loss of IA (AOP-017) (004A2.11)
c.DL 5
C.
DL40
Start Up a Hydrogen Recombiner (OP-125)
I (028A4.01)
path, (C)ontrol Room, (S)imulator,
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate
(L)ow-Power, (R)CA
NUREG-1021, Revision 8, Supplement 1
ES-301 Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2
Facility: HARRIS Date of Examination: 26-Aug-02
Examination Level: SRO-U Operating Test Number: 2002-301
B.1 Control Room Systems
Safety
System/JPM Title Code* Function
(KA#)
a.
(AOP-019) NAS( 3
Respond to a Failed High Pressurizer Pressure Channel (0l0.A2.03)
b.NAS 6
b.
55) (064A4.0l)
LOOP While Paralleling EDG from MCB for Testing (OP-1
C.
d.
e.
f.
g.
B.2 Facility Walk-Through
a.DL 1
a.
(OO3AA1.02)
Local Actions for a Dropped Rod Recovery (AOP-001)
b. b.DRL 2
(004A2.1l)
Manually Align Charging Due to a Loss of IA (AOP-017)
c. c.DL 5
(028A4.01)
Start Up a Hydrogen Recombiner (OP-125)
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator,
(L)ow-Power, (R)CA
NUREG-1021, Revision 8, Supplement 1
JPM SRO-A.1-1
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM SRO-A. 1.1
Perform Review of Daily Surveillance Requirements
Log
CANDIDATE:
EXAMINER:
Page 1 of 8
Rev Date 07/25/02
JPM SRO-A.1-1
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Perform Review of Daily Surveillance Requirements Log
ALTERNATE PATH: None
FACILITY JPM NUMBER: NEW
KA: 2.1.18 IMPORTANCE: SRO 3.0 RO NA
KA STATEMENT: Ability to make accurate, clear and concise logs, regards,
status boards, and reports.
TASK STANDARD: Four of five (4/5) errors on attached log sheet are identified.
PREFERRED EVALUATION LOCATION: SIMULATOR v' IN PLANT
PREFERRED EVALUATION METHOD: PERFORM *1 SIMULATE
REFERENCES: OST-1021, Daily Surveillance Requirements, Daily Interval, Mode
1 and 2
VALIDATION TIME: 20 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 8
Rev Date 07/25/02
JPM SRO-A.l-1
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
" Complete OST- 1021, Attachment 4, for the 0300 readings using values expected at
100% power.
"* Substitute the following incorrect data:
"* Accumulator CLAB Previous Day Level @ 68% (both 924 and 926) with 0300
readings at 78% and 79%, while indicating sampling is NOT required.
"* RWST Level Channel 993 @ 91%.
"* Pressurizer Pressure channels 455 @ 2220 psig, 456 @ 1960 psig, 457 @ 2230
psig while indicating acceptance criteria is met and channel check is SAT.
"* Containment Temperature channel TCV97540 as "NA", 7542 @ 121'F, 7541 @
11 60F while indicating acceptance criteria is met.
"* EDG Room Temperature channel TDG6903A @ @ 11 80F and TDG6903B @
121°F
OST-1021, "Daily Surveillance Requirements, Daily Interval, Mode 1 and 2,"
Attachment 4, "Daily Surveillance Requirements Log"
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant is operating at 100% power.
The Daily Surveillance Logs (OST-1021, Attachment 4) for 0300 have been
completed.
INITIATING CUE(S):
You are to review OST-1021, Attachment 4, noting all errors.
Page 3 of 8
Rev Date 07/25/02
JPM SRO-A.l-1
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH COMPLETED OST-1021,
ATTACHMENT 4.
NOTE: ONLY THOSE ITEMS IN THE LOGS WHICH ARE INCORRECT ARE
IDENTIFIED IN THIS JPM.
- 1 Attach 4 Cold Leg Accumulator Identifies that level has Critical to
Sheet 1 CLA B requires sampling increased more than identify error that
due to increase in level of > 9% and requires sampling is
9% sampling required.
- 2 Attach 4 RWST Level Channel 993 is * Identifies that level Critical to
Sheet 2 below minimum required is below minimum identify BOTH
level of 92% AND Channel required level is below
Check is NOT sat * Identifies that minimum
Channel Check is required AND
not sat channel check is
not sat
- 3 Attach 4 Pressurizer Pressure is Determines channel Critical to identify
Sheet 3 incorrectly logged for 456 should be marked that channel 456
NA in reading OR should either be
Channel 456
should be included in logged as NA or
should be included
calculation in the calculation.
If required, the
attached followup
question must also
be correctly
answered to
consider this error
identification as
SAT.
NOTE: IF REQUIRED TO DETERMINE REASON FOR DECLARING
PRESSURIZER PRESSURE INCORRECTLY LOGGED IN JPM STEP 3 ABOVE,
USE THE ATTACHED FOLLOWUP QUESTION.
- 4 Attach 4 Containment Temperature Identifies that Critical to
Sheet 8 Channel TI-7542 exceeds temperature exceeds identify that
limit of 1200 F maximum limit temperature is
above maximum
allowed.
Page 4 of 8
Rev Date 07/25/02
JPM SRO-A.1-1
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP UNSAT
- 5 Attach 4 Diesel Generator Room 261 Identifies that Critical to
Sheet 10 temperature TDG6903B temperature exceeds identify that
exceeds limit of 1200F maximum limit temperature is
above maximum
allowed.
NOTE: FOUR OF THE ABOVE FIVE ERRORS (4/5) ARE REQUIRED TO BE
IDENTIFIED TO DEMONSTRATE SATISFACTORY PERFORMANCE OF THE
JPM.
TASK COMPLETE
STOP TIME:
Page 5 of 8
Rev Date 07/25/02
JPM SRO-A.1-1
HARRIS
JPM FOLLOWUP QUESTION
QUESTION:
When determining that the Pressurizer Pressure reading was incorrectly logged, what was
your reasoning for making this determination?
EXPECTED RESPONSE:
Channel 456 falls well outside the range of conditions for the other channels and for plant
conditions.
If the channel is inoperable, the value should NOT be logged. "NA" should be inserted
with a note included stating that the channel has been declared inoperable.
If the channel is not declared inoperable until after taking the reading, the value of
channel 456 should be used in the calculation to determine if acceptance criteria is met.
In this case, both the channel check and the acceptance criteria would NOT be met and
the initials should have not been included stating that both are met.
RESPONSE:
SAT UNSAT
Page 6 of 8
Rev Date 07/25/02
JPM SRO-A.1-1
HARRIS
JPM ATTACHMENT
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
OST-1021, Attachment 4, Sheets 1-15
Page 7 of 8
Rev Date 07/25/02
JPM SRO-A.1-1
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant is operating at 100% power.
The Daily Surveillance Logs (OST-1021, Attachment 4) for 0300 have been
completed.
INITIATING CUE(S):
You are to review OST-1021, Attachment 4, noting all errors.
Page 8 of 8
Rev Date 07/25/02
JPM RO-A.1-1
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM RO-A. 1.1
Determine Rod Misalignment Using
Thermocouples
CANDIDATE:
EXAMINER:
Page 1 of 8
Rev Date 07/21/02
JPM RO-A.1-1
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Determine Rod Misalignment Using Thermocouples
ALTERNATE PATH: None
FACILITY JPM NUMBER: NEW
KA: 2.1.19 IMPORTANCE: SRO NA RO 4.4
KA STATEMENT: Ability to use plant computer to obtain and evaluate
parametric information on system or component status.
TASK STANDARD: Determines Shutdown Bank A Rod C9 is misalignment is
NOT verifiable using incore thermocouples
PREFERRED EVALUATION LOCATION: SIMULATOR v' IN PLANT
PREFERRED EVALUATION METHOD: PERFORM *1'
SIMULATE
REFERENCES: AOP-001, Malfunction of Rod Control and Indication System
VALIDATION TIME: 10 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 8
Rev Date 07/21/02
JPM RO-A.1-1
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
Provide candidate with values from JPM Attachment which contains list of thermocouple
temperatures in alphanumeric order after candidate states how information will be
obtained.
AOP-001, "Malfunction of Rod Control and Indication System"
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant is operating at 100% power.
AOP-001, "Malfunction of Rod Control and Indication System," is being performed in
response to suspected indications that Shutdown Bank A Rod C9 may be misaligned
by more than 12 steps.
INITIATING CUE(S):
You have been directed to determine whether the Core Exit Thermocouples support
the indication of a misaligned rod per AOP-00 1, Attachment 1, "Indications of
Misaligned Rod."
Page 3 of 8
Rev Date 07/21/02
JPM RO-A.1-1
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH CURRENT COPY OF AOP-001,
ATTACHMENTS 1 AND 2
NOTE: EXAMINER'S ANSWER KEY IS INCLUDED, WHICH INDICATES
THE INFORMATION THAT THE CANDIDATE SHOULD DETERMINE.
PROCEDURE STEPS LISTED ON THIS JPM IDENTIFY THOSE STEPS AS
LISTED ON THE ATTACHMENTS.
Att 1 Greater than 100F difference Refers to AOP-001,
between thermocouples Attachment 2
adjacent to the misaligned rod
and the average of symmetric
thermocouples (Perform
Attachment 2)
- 2 Att 2 - 1 Determine thermocouple * Using core grid Critical to
location(s) adjacent to the map, determines determine
misaligned rod using core thermocouple adjacent
grid map (Sheet 1), and adjacent to Rod C9 thermocouple
circle locations(s) in Table is in location C8 location to allow
above. These thermocouple(s) * Circles location C8 determining
are affected. on table which
thermocouples
are symmetric.
Only
determination is
critical.
Page 4 of 8
Rev Date 07/21/02
JPM RO-A.1-1
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
3 Att 2 - 2 Record values for all operable Records following
affected and symmetric values for affected and
thermocouples using the symmetric
RVLIS Console or ERFIS. thermocouples:
Symmetric thermocouples are . C08 (aff) - 6020 F
those in the same row. a H13 (sym)- 6080 F
- N08 (sym) - 608'F
- H03 (sym) - 609'F
CUE (PROVIDED AFTER CANDIDATE STATES THEY MUST OBTAIN
THERMOCOUPLE TEMPERATURES FROM RVLIS CONSOLE OR ERFIS)
PROVIDE TEMPERATURES WHICH CANDIDATE REQUESTS BASED ON
THERMOCOUPLE LOCATION FROM JPM ATTACHMENT.
- 4 Att 2 - 3 Determine the average of Determines average of Critical to
symmetric thermocouples, symmetric correctly
for each affected thermocouples - determine the
thermocouple. 608.33T average of the
symmetric
thermocouples
for comparison to
the affected
thermocouple.
- 5 Att 1 Determine if Core Exit Determines Core Exit Critical to
Thermocouples support Thermocouples do' determine that
indication of misaligned rod NOT support the thermocouple
indication of indications do not
misaligned rod due to support
difference between indication of a
affected thermocouple misaligned rod.
and symmetric
thermocouple being
<10F ( 6.330 F)
TASK COMPLETE
STOP TIME:
Page 5 of 8
Rev Date 07/21/02
JPM RO-A.1-1
HARRIS
JPM RO-A.1.1 ATTACHMENT
INCORE THERMOCOUPLE TEMPERATURES
(Thermocouples are listed in alphanumeric order)
THERMOCOUPLE TEMP THERMOCOUPLE TEMP
LOCATION (in °F) LOCATION (in °F)
A08 ABANDONED H09 622
B05 590 Hil 618
B1O 588 H13 608
C08 602 H15 603
C12 605 J02 604
D03 608 J10 615
D05 611 J12 ABANDONED
E04 606 K03 604
E07 610 K05 611
E08 619 K08 615
El0 618 Kl1 ABANDONED
E12 614 L06 615
E14 604 LOB 614
F03 ABANDONED L12 609
F05 614 L14 ABANDONED
F09 614 M03 606
Fll 615 M09 618
F13 608 M11 617
G01 ABANDONED N04 609
G02 604 N06 610
G06 611 N08 608
G08 621 N10 608
G15 603 P07 607
H03 609 P08 604
H05 616 R07 613
Page 6 of 8
Rev Date 07/21/02
JPM RO-A.1-1
HARRIS
ANSWER KEY FOR JPM RO-A.1-1
Attachment 2
Sheet 2 of 2
Affected and Symmetric Thermocouple Locations
NOTE
810, E07, K08, and P08 have no symmetric locations.
GRID I II ____I1l IV
TRAIN A B A B A B A B
A08* H15
G01* G15 R07
S L BE5 214 L14"
Y 0 _C08_ H13 N08 H03
M C 0 X C12 N04 M03
M A E04 D05 E12 M11 L12
E T Hll E08 LOB H05
T I F05 F11 E10 K1"* K05 L06
R 0 F03* F13 N10 N06 K03
I N G06 F09 J10
C S G08 H09
G02 J02 P07
M09 J12*
- Thermocouples abandoned by EC 47997
1. Determine thermocouple location(s) adjacent to the misaligned rod using core grid map
(Sheet 1), and circle locations(s) in Table above. These thermocouple(s) are affected.
2. Record values for all operable affected and symmetric thermocouples using the RVLIS
Console or ERFIS. Symmetric thermocouples are those in the same row.
6 3
"* Affected TC #2 Symmetric TC(s) (AVERAGE = 608.33)
"* Affected TC #3 ._ Symmetric To(s)
"* Affected TC #4 __ Symmetric TC(s)
3. Determine the average of symmetric thermocouples, for each affected thermocouple.
Page 7 of 8
Rev Date 07/21/02
JPM RO-A.1-I
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant is operating at 100% power.
AOP-001, "Malfunction of Rod Control and Indication System," is being performed in
response to suspected indications that Shutdown Bank A Rod C9 may be misaligned
by more than 12 steps.
INITIATING CUE(S):
You have been directed to determine whether the Core Exit Thermocouples support
the indication of a misaligned rod per AOP-00 1, Attachment 1, "Indications of
Misaligned Rod."
Page 8 of 8
Rev Date 07/21/02
JPM COM-A. 1-2
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-A. 1-2
Perform a Manual Power Range Heat Balance
Calculation
CANDIDATE:
EXAMINER:
Page 1 of 12
Rev. Date 07/21/02
JPM COM-A. 1-2
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Perform a Manual Power Range Heat Balance Calculation
ALTERNATE PATH: None
FACILITY JPM NUMBER: NEW
KA: 2.1.25 IMPORTANCE: SRO 4.6 RO 4.4
KA STATEMENT: Ability to obtain and interpret station reference materials
such as graphs, monographs, and tables which contain
performance data.
TASK STANDARD: Heat balance has been calculated within allowable tolerance
PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT
PREFERRED EVALUATION METHOD: PERFORM .- SIMULATE
REFERENCES: "* OST-1204, Power Range Heat Balance, Manual Calculation, Daily
Interval, Mode 1 (Above 15% Power)
"* Steam Tables
VALIDATION TIME: 30 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 12
Rev. Date 07/21/02
JPM COM-A.1-2
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
"* Provide candidate with Attachment which contains collected data and required forms
to fill out.
"* Examiner's Answer Key is also included as Attachment.
"* OST-1204, Power Range Heat Balance, Manual Calculation, Daily Interval, Mode 1
(Above 15% Power)
"* Steam Tables
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant is operating at approximately 100% power. ERFIS is out-of-service and is
expected to be out for an extended period of time.
OST-1204, Power Range Heat Balance, Manual Calculation, Daily Interval, Mode 1
(Above 15% Power) is to be performed to meet the periodic surveillance requirement
for Technical Specification 4.3.1.1, Table 4.3-1, Item 2a.
Steam Generator Blowdown is isolated.
I&C Technicians have collected all necessary data for the calculation.
INITIATING CUE(S):
You have been directed to perform OST-1204, Power Range Heat Balance, Manual
Calculation, Daily Interval, Mode 1 (Above 15% Power), by completing Attachment
5, "Calorimetric Worksheet," and Attachment 6, "Certifications and Reviews."
NOTE: The Examiner will provide you with completed Attachments 1-4 and copies
of Attachments 5 and 6 for you to complete.
Page 3 of 12
Rev. Date 07/21/02
JPM COM-A. 1-2
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH COMPLETED ATTACHED copy of OST
1204, ATTACHMENTS 1-6.
NOTE: FOLLOWING JPM STEPS DESCRIBE HOW ATTACHMENTS 5 AND 6
OF OST-1204 ARE TO BE FILLED OUT.
EXAMINER'S ANSWER KEY IS INCLUDED. BOLDED ITEMS ARE
CONSIDERED TO BE THE CRITICAL STEPS REQUIRED TO
SUCCESSFULLY COMPLETE THIS JPM.
PROCEDURE STEPS LISTED ON THIS JPM IDENTIFY THOSE STEPS AS
I ,ITIT*f AN THE ATTACHMENTS.
_ _ I__ I Ir
I-
_____________________________________________________________________________ ___________________
- 1 Att. 5 Calculate Steam Generator 1) Fills in SG Pressures Critical to
Exit Enthalpies: from Att 3 as SG A accurately
la
- Steam Tables Lookup: - 900, SG B - 890, determine steam
SGC-900 enthalpy to
Saturated Steam,
2) Looks up liq determine power
Liquid Enthalpies
enthalpy for SG level.
pressures as SG A
526.7, SG B Note liquid
525.0+0.2 enthalpy value is
(interpolation NOT critical
required), SG C since it will be
526.7 multiplied by
3) Looks up steam zero in next step.
enthalpy for SG
pressures as SG A
- 1196.4, SG B
1196.7+0.2
(interpolation
required), SG C
1196.4
1 1 L - - --
Page 4 of 12
Rev. Date 07/21/02
JPM COM-A. 1-2
HARRIS
STANDARD NOTES SAT /
3PM PROC ELEMENT
STEP STEP UNSAT
lb Steam Enthalpies enthalpies, by accurately
multiplying liq calculate exit
enthalpy by zero and enthalpy to
then substracting from determine power
steam enthalpy (same level.
value as steam
enthalpy), as SG A - Note that
1196.4, SG B - tolerance is
1196.7+0.2, SG C - carried forward.
1196.4
- 3 Att. 5 - 2 Feedwater Enthalpy (Steam Using temperature Critical to use
Tables Lookup) value of feedwater, temperature and
determines enthalpy of not pressure of
sat liquid at 4400 F to feed to determine
be 419.0 enthalpy.
- 4 Att. 5 - 3 Enthalpy Rise Across the Determines enthalpy Critical to
Steam Generators rise across SGs, by accurately
subtracting FW calculate
enthalpy from SG exit enthalpy rise to
enthalpy, as SG A - determine reactor
777.4, SG B - power.
777.7+02, SG C
777.4 Note that
tolerance is
carried forward.
- 5 Att. 5 - 4 Steam Generator Powers 1) Fills in FW Flows Critical to
from Att 3 as SG A accurately
4.223, SG C - 4.255 power to
2) Determines SG determine reactor
powers, by power.
multiplying FW
Flows by SG Note that
enthalpy rise, as SG tolerance is
A - 3300.84, SG B - carried forward
3284.23+0.85, SG C and adjusted due
- 3307.84 to multiplication.
Page 5 of 12
Rev. Date 07/21/02
JPM COM-A. 1-2
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
- 6 Att. 5 - 5 Calculate Total Reactor Determines total Critical to
Power reactor power, by accurately
adding the SG powers calculate total
and subtracting RCP reactor power to
heat input, as determine reactor
9850.60+0.85 power.
Note that
tolerance is
carried forward.
- 7 Att. 5 -- 6 Convert Mbtu/hr to MWth Converts to thermal Critical to
power, by dividing accurately
total reactor power by convert to
a conversion factor, as determine reactor
2886.96+0.25 power.
Note that
tolerance is
carried forward
and adjusted for
division.
- 8 Att. 5 - 7 Calculate Percent of Rated Determines percent Critical to
Thermal Power reactor power, by accurately
dividing thermal power convert to
by rated thermal determine percent
power, as 99.6+0.1 reactor power.
Note that
tolerance is
carried forward
and adjusted for
division.
Page 6 of 12
Rev. Date 07/21/02
JPM COM-A. 1-2
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
- 9 Att. 5 - 8 Power Range NI 1) Fills in highest and Critical to
Surveillance lowest indicated PR accurately
channels from Att 3 determine
as 100 and 99.5 difference
2) Determines between
difference between indicated and
indicated and actual power to
calculated power, determine if PR
by subtracting NI channels
calculated from require
indicated, as adjustment.
Highest Indicated
0.4+0.1% and Note that
Lowest Indicated - tolerance is
(-)0.1+0.1% carried forward.
10 Att 5 Perf Sign Attachment 5 as Signs Attachment 5
Performer
11 Calculation Verified Requests verification of
calculation
421 TF. INDEPENDENT VERIFICATION IS COMPLETED.
12 Att 6 Check OST performed for Checks periodic
periodic surveillance surveillance
13 Fill in plant conditions Fills in plant conditions
as 100% power, Mode 1
14 Sign / date completion of Signs and dates
OST completion of OST
TASK COMPLETE
STOP TIME:
Page 7 of 12
Rev. Date 07/21/02
JPM COM-A. 1-2
HARRIS
ANSWER KEY FOR JPM COM-A1-2
Attachment 5
Sheet 1 of 2
Calorimetric Worksheet
1. Calculate Steam Generator Exit Enthalpies
a. Steam Tables Lookup: Saturated Steam, Liquid Enthalpies
SG Pressure Liq. Enthalpy (h!) Stm. Enthalpy (h,)
526.7 btu/lbm, 1196.4 btu/Ibm
SG A: 900 psia
SG B: 890 psia
-4 525.0+/-0.2 btu/lbm, 1196.7+/-0.2 btu/lbm
SG C: 900 psia
_> 526.7 btu/lbm, 1196.4 btu/lbm
b. Calculate SG Exit Steam Enthalpies
Stm. Enthalpy Liq. Enthalpy Exit Enthalpy
(h,) (h~t)
SG A: 1.00 x 1196.4 . o.oo , 526.7 1196.4 btu/Ibm
1.00 )196.7+/-0.2+ 0.00 525.0+/-0.2 1196.7+/-0.2 btu/ibm
SG B:
1196.4 + 0.00 x 526.7 1196.4 btu/ibm
SG C: 1.00 x
2. Feedwater Enthalpy (Stm Tables Lookup)
FrW (TempiPress) FW Enthalpy (hw*)
h 440 1080 419.0 btu/ibm
hr.
VW Avg -F Fa Psia
3. Enthalpy Rise across the Steam Generators
Exit Enthalpy FW Enthalpy A Enthalpy
(h~i+/-) (h49) (Ahsa)
SC A: ______
1196.4 419.0 777.4 btu/lbm
419.0 =777.7+/-0.2 btu/lbm
SG B: 1196.7+/-0.2
1196.4 419.0 777.4 btu/lbm
SG C:
ANSWER KEY FOR JPM COM-A1-2
Page 8 of 12
Rev. Date 07/21/02
JPM COM-A. 1-2
HARRIS
ANSWER KEY FOR JPM COM-A1-2
Attachment 5
Sheet 2 of 2
Calorimetric Worksheet
4. Steam Generator Powers
FW Flow A Enthalpy %*G
(MPPH) (btu/lbm) (Mbtu/hr)
4.246 777.4 3300.84 Mbtu/hr
QO A: x
Qý ~4.223 x 777.7+/-0.2 3284.23+/-0.85 Mbtu/hr
x 777.4 3307.84 Mbtu/hr
Qý c4.255
5. Calculate Total Reactor Power
3300.84 3300.23+/-0.85-A 3307.84 - 42.31
9850.60+/-0.85 Mbtu/hr
+
QSQA QsoB Qs c QRCP QRX
6. Convert Mbtu/hr to MWm
9850.60+/-0.85 Mbtu/hr 3.4121 Mbtu/hr/MWmh
Z886.96+/-0.25 mWm
7. Calculate Percent of Rated Thermal Power
2886.96+/-0.25 Mw", x 100 99.6+/-0.1 %RTP
2900 MW,,
8. Power Range NI Surveillance
100.0 99.6+/-0.1 0.4+/-0.1
Highest PR NI (M Calc'd Power (%)
99.5 99.6+/-0.1 -0.1+/-0.1
Lowest PR NI (M Calc'd Power (W)
Performed By:
CANDIDATE SIGN
Verified By:
N/A
ANSWER KEY FOR JPM COM-A1-2
Page 9 of 12
Rev. Date 07/21/02
JPM COM-A. 1-2
HARRIS
ANSWER KEY FOR JPM COM-A1-2
Attachment 6
Sheet 1 of 1
Certifications and Reviews
Periodic Surveillance Requiremeent:
x
This OST was oerformed as a:
Post Maintenance Operability Test:
Redundant Subsystem Test:
100% power Mode: 1
Plant Conditions:
OST Completed By:
CANDIDATE SIGN Date: CURRENT
Time: CURRENT
OST Performed By:
Initials Name (Print) Initials Name (Print)
BJ Bob Jones
S Samuel Snead
CANDIDATE INITIAL / PRINT NAME
General Comments/Recommendations/Corrective Actions! Exceptions:
Pages Used:
0ST Completed with NO EXCEPTIONS / EXCEPTIONS:
Date:
Unit SCO
After receiving the final review signature, this OST becomes a QA RECORD and
should be submitted to Document Services.
ANSWER KEY FOR JPM COM-A1-2
Page 10 of 12
Rev. Date 07/21/02
JPM COM-A. 1-2
HARRIS
JPM ATTACHMENT
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
OST-1204, Attachments 1-6
Page 11 of 12
Rev. Date 07/21/02
JPM COM-A.1-2
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant is operating at approximately 100% power. ERFIS is out-of-service and is
expected to be out for an extended period of time.
OST-1204, Power Range Heat Balance, Manual Calculation, Daily Interval, Mode 1
(Above 15% Power) is to be performed to meet the periodic surveillance requirement
for Technical Specification 4.3.1.1, Table 4.3-1, Item 2a.
Steam Generator Blowdown is isolated.
I&C Technicians have collected all necessary data for the calculation.
INITIATING CUE(S):
You have been directed to perform OST- 1204, Power Range Heat Balance, Manual
Calculation, Daily Interval, Mode 1 (Above 15% Power), by completing Attachment
5, 'ýCalorimetric Worksheet," and Attachment 6, 'Certifications and Reviews."
NOTE: The Examiner will provide you with completed Attachments 1-4 and copies
of Attachments 5 and 6 for you to complete.
Page 12 of 12
Rev. Date 07/21/02
JPM COM-A.2
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-A.2
Review an Equipment Clearance
CANDIDATE:
EXAMINER:
Page 1 of 8
Rev. Date 07/21/02
JPM COM-A.2
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Review an Equipment Clearance
ALTERNATE PATH: None
FACILITY JPM NUMBER: IP-164 (Modified)
KA: 2.2.13 IMPORTANCE: SRO 3.8 RO 3.6
KA STATEMENT: Knowledge of clearing and tagging procedures.
TASK STANDARD: Identifies both discrepancies on clearance as listed in JPM.
PREFERRED EVALUATION LOCATION: SIMULATOR %' IN PLANT
PREFERRED EVALUATION METHOD: PERFORM
'WI'
SIMULATE
REFERENCES: "* OPS-NGGC-1301, Equipment Clearance
"* S-1311, Simplified Flow Diagram Boron Recycle System
"* OP-109, Boron Recycle System
"* CAR 2166 B-401, Sheet 3587
VALIDATION TIME: 30 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 8
Rev. Date 07/21/02
JPM COM-A.2
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
"* Provide candidate with Attachment which is the completed clearance form
"* OPS-NGGC-1301, "Equipment Clearance"
"* S-1311, "Simplified Flow Diagram Boron Recycle System"
"* OP-109, "Boron Recycle System"
"* CAR 2166 B-401, Sheet 3587
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The unit is operating at 30% power.
The internals for 3BR-153, Recycle Evaporator Feed Pump 1&2B Discharge Check
Valve, must be replaced. Recycle Evaporator Feed Pump 1&2B has been secured and
Pump I&2A is aligned for operation.
Mechanical Maintenance has submitted a clearance request. The clearance has been
manually generated.
INITIATING CUE(S):
You are to review the Equipment Clearance Tag Sheet for 3BR-153 and identify
EVERY discrepancy.
NOTE: Individual tags have NOT been generated and are NOT part of the review
process.
Page 3 of 8
Rev. Date 07/21/02
JPM COM-A.2
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH ATTACHED PACKAGE, WHICH
INCLUDES CLEARANCE AND DRAWINGS S-1311 AND CAR 2166 B-401,
SHEET 3587.
ALSO, IF ASKED, PROVIDE A COPY OF OPS-NGGC-1301 AND OP-109 (OR
MAKE SURE COPIES ARE AVAILABLE).
NOTE: JPM IS WRITTEN FOLLOWING THE GUIDELINES OF OPS-NGGC
1301, STEPS 9.2.1.10,9.2.1.13, and 9.2.1.25. NO SPECIFIC ORDER FOR
PERFORMANCE OF THE JPM IS REQUIRED PROVIDED THE CANDIDATE
IDENTIFIES THE DISCREPANCIES. JPM STEPS ARE WRITTEN IN THE
GENERAL FLOWPATH THAT THE PUMP MUST BE TAGGED FIRST,
FOLLOWED BY DISCHARGE PATH, SUCTION PATH, AND THEN DRAINS
AND VENTS.
I 9.2.1.10.a For systems where a pump or Determines that
fan is affected by the clearance correctly has
clearance, the clearance pump secured (initial
should be installed in the conditions) and control
following sequence to prevent switches have info tag
damage to equipment: hung before tagging
- Secure pump/fan and power to pump
hang a tag on its control
switch.
- 2 9.2.1.10.b Remove the power source Determines that Critical to
for the pump/fan prime breaker for pump is determine that
mover (open breaker, tagged out of sequence sequence for
remove fuse, shut steam as it is to be tagged tagging pump
supply valve and so forth) prior to closing any breaker is not
and place tag on the power valves correct to ensure
source. pump protection.
3 .9.2.1.10.c Reposition valves from Determines that
control switches, as required clearance correctly does
by the clearance, and place not identify any motor
tags on the control switches. operated valves
Include tags for switches in requiring tagging
alternate locations if
_________
______ applicable. ____________________________
Page 4 of 8
Rev. Date 07/21/02
JPM COM-A.2
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
4 9.2.1.10.d Remove power source Determines that
(electrical, air, hydraulic, and clearance correctly does
so forth) from valves, if not identify any motor
applicable, and tag the power operated valves
source removed, requiring tagging
"*5 9.2.1.10.e Reposition manual valves as * Determines that Critical to isolate
required by the clearance discharge valve is all boundary
and place tag on correctly tagged isolations.
handwheels of the valves prior to suction
covered by the clearance, valve, but
For pumps, shut the incorrectly tagged
discharge valve before prior to pump
shutting the suction valve, breaker being tagged
(noted previously in
JPM Step 3)
& Determines that
3BR-157, REFP
1&2B Recire
Return to RttT Isol
(and Reach Rod), is
NOT included on
clearance, but
should be included
6 9.2.1.13 For devices having a remote Determines that all
operator, such as a valve valves on clearance that
reach rod, where both valve have reach rods have
and reach rod have a clearances hung
handwheel and are accessible, correctly on both the
the clearance should be valve handwheel and the
written such that both reach rod
mechanical devices are
tagged.
7 9.2.1.25 Whenever possible, an Determines that drain
atmospheric drain and/or vent and vent paths are
between the work area and included as part of
sources of pressure to the clearance
work area should be tagged in
the open position with the
cap/flange removed to release
pressure in systems and to
accommodate thermal
expansion and contraction.
Page 5 of 8
Rev. Date 07/21/02
JPM COM-A.2
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
8 Inform clearance preparer of Informs clearance
discrepancies preparer of 2
discrepancies
"* Incorrect order of
discharge valve!
pump breaker
"* Missing boundary
isolation valve
NOTE: IF CANDIDATE CREATES A SAFETY HAZARD OR THE
PROBABILITY OF EQUIPMENT DAMAGE BY IDENTIFYING ADDITIONAL
ERRORS, THIS WOULD CONSTITUTE A FAILURE OF THE JPM.
TASK COMPLETE
STOP TIME:
Page 6 of 8
Rev. Date 07/21/02
JPM COM-A.2
HARRIS
JPM ATTACHMENT
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
OPS-NGGC-1301, Attachments 3-4
S-1311
CAR 2166 B-401, Sheet 3587
Page 7 of 8
Rev. Date 07/21/02
JPM COM-A.2
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The unit is operating at 30% power.
The internals for 3BR-153, Recycle Evaporator Feed Pump 1&2B Discharge Check
Valve, must be replaced. Recycle Evaporator Feed Pump I&2B has been secured and
Pump 1&2A is aligned for operation.
Mechanical Maintenance has submitted a clearance request. The clearance has been
manually generated.
INITIATING CUE(S):
You are to review the Equipment Clearance Tag Sheet for 3BR- 153 and identify
EVERY discrepancy.
NOTE: Individual tags have NOT been generated and are NOT part of the review
process.
Page 8 of 8
Rev. Date 07/21/02
JPM SRO-A.3
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM SRO-A.3
Radiological Controls
CANDIDATE:
EXAMINER:
Page 1 of 8
Rev. Date 07/21/02
JPM SRO-A.3
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Radiological Controls
ALTERNATE PATH: NA - Questions
FACILITY JPM NUMBER: NA - Questions
KA: 1) 2.3.6 IMPORTANCE: SRO 1) 3.1 RO NA
2) 2.3.4 2)3.1
KA STATEMENT: 1) Knowledge of the requirements for reviewing and
approving release permits
2) Knowledge of radiation exposure limits and
contamination control, including permissible levels in
excess of those authorized
TASK STANDARD: NA - Questions
vi
PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT
PERFORM V. SIMULATE
PREFERRED EVALUATION METHOD:
REFERENCES: OP-120.06.02, Waste Evaporator Condensate Tanks
Offsite Dose Calculation Manual
PEP-330, Radiological Consequences
OWP-RM, Radiation, Effluent, and Explosive Gas Monitoring"
VALIDATION TIME: 15 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 8
Rev. Date 07/21/02
JPM SRO-A.3
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
NOTE: ENSURE THE FOLLOWING REFERENCES ARE AVAILABLE FOR USE
IN ANSWERING THE ATTACHED QUESTIONS:
OP- 120.06.02, "Waste Evaporator Condensate Tanks"
Offsite Dose Calculation Manual
PEP-330, "Radiological Consequences"
OWP-RM, "Radiation, Effluent, and Explosive Gas Monitoring"
Page 3 of 8
Rev. Date 07/21/02
JPM SRO-A.3
HARRIS
START TIME:
EXAMINER'S ANSWER KEY
QUESTION #1
Radwaste is making preparations to discharge the Waste Evaporator Condensate Tank
(WECT) when it is determined that FT-6119, WMT / WECT Discharge Flow, is
What are the license requirements that must be met to allow the WECT to be discharged
with FT-6119 inoperable?
ANSWER:
ODCM 3/4.3.3.10, Radioactive Liquid Effluent Monitoring Instrumentation, Table 3.3
12, Action 38 requires that the flow rate be estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
during the actual release (information can also be determined by referencing OWP
RM-14)
OP- 120.06.02 requires that the flow rate be estimated at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during
the actual release and that the estimated flow be documented on Attachment 5, Waste
Evaporator Condensate Tank Discharge Flow Instrument Inoperable Log
(Required response underlined and bolded)
REFERENCES:
OP- 120.06.02, "Waste Evaporator Condensate Tanks"
OWP-RM, "Radiation, Effluent, and Explosive Gas Monitoring"
Offsite Dose Calculation Manual
2.3.6 / SRO 3.1 / Knowledge of the requirements for reviewing and approving release
permits
STOP TIME:
Page 4 of 8
Rev. Date 07/21/02
JPM SRO-A.3
HARRIS
START TIME:
EXAMINER'S ANSWER KEY
QUESTION #2
The plant experienced a loss of coolant accident and cold leg recirculation operations
were established per EOP EPP-010, "Transfer to Cold Leg Recirculation." Prior to the
accident RHR Pump lB-SB had been out-of-service due to a damaged bearing. RHR
Pump IA-SA has just failed.
An emergency entry for repairs is to be made into the RHR Pump 1A-SA room. HP
reports general area radiation levels in the room are approximately 20 Rem/hour.
Maintenance estimates that it will take a 3-person team approximately 90 minutes to
make the necessary repairs.
The Maintenance Manager has supplied a list of 5 personnel that are available on site
and qualified to perform the repairs. The 5 persons are:
1) Anita Andrews is a 47-year-old married female, states she is not pregnant, she
has volunteered to make the entry, and she is fully aware of the radiological risks
involved. She has worked at the Harris plant for 22 years, the last 9 as a member
of the Maintenance department.
2) Bob Ballew is a 32-year-old married male, he has volunteered to make the entry,
and he is fully aware of the radiological risks involved. He has worked at the
Harris plant as a member of the Maintenance department since he left another
nuclear utility 3 years ago.
3) Charles Cotton is a 51-year-old single male and although he has not volunteered
to make the entry, he is fully aware of the radiological risks involved. He is the
most knowledgeable of the 5 persons, having been a member of the Maintenance
department for his entire 28 years at the Harris plant.
4) David Deaver is a 37-year-old married male, he has volunteered to make the
entry, and he is fully aware of the radiological risks involved. He has worked at
the Harris plant for 15 years, the last 11 years as a member of the Maintenance
department since he left Operations.
5) Frank Furstenburg is a 56-year-old single male, he has volunteered to make the
entry, and he is fully aware of the radiological risks involved. Although he has
only worked at Harris for the past 2 years, both years were spent in the
Maintenance department, and he has experience in these situations, having made
a similar entry 17 years ago at another nuclear utility.
Which 3 of these 5 persons should be selected to make the emergency entry, AND why
should these 3 be picked?
Page 5 of 8
Rev. Date 07/21/02
JPM SRO-A.3
HARRIS
ANSWER:
Anita Andrews, Bob Ballew, and David Deaver should be selected to make this
entry. In events where exposure levels exceeding 25 TEDE would be required all
personnel must be volunteers (eliminating Charles Cotton), they should have a full
awareness of the risks involved (all meet this requirement), and exposure under these
conditions should be limited to once in a lifetime (eliminating Fred Furstenburg).
Although it is preferable to use personnel over the age of 45, age should only be
considered where all other factors are equal. Females should not be considered if they
are declared pregnant, which Anita Andrews has not done.
(Required response underlined and bolded)
REFERENCES:
PEP-330, "Radiological Consequences"
2.3.4 / SRO 3.1 / Knowledge of radiation exposure limits and contamination control,
including permissible levels in excess of those authorized
STOP TIME:
Page 6 of 8
Rev. Date 07/21/02
JPM SRO-A.3
HARRIS
CANDIDATE QUESTION SHEET
QUESTION #2
(TO BE RETURNED TO EXAMINER UPON COMPLETION)
The plant experienced a loss of coolant accident and cold leg recirculation operations
were established per EOP EPP-010, "Transfer to Cold Leg Recirculation." Prior to the
accident RHR Pump 1B-SB had been out-of-service due to a damaged bearing. RHR
Pump 1A-SA has just failed.
An emergency entry for repairs is to be made into the RHR Pump 1A-SA room. HP
reports general area radiation levels in the room are approximately 20 Rem/hour.
Maintenance estimates that it will take a 3-person team approximately 90 minutes to
make the necessary repairs.
The Maintenance Manager has supplied a list of 5 personnel that are available on site and
qualified to perform the repairs. The 5 persons are:
1) Anita Andrews is a 47-year-old married female, states she is not pregnant, she has
volunteered to make the entry, and she is fully aware of the radiological risks
involved. She has worked at the Harris plant for 22 years, the last 9 as a member
of the Maintenance department.
2) Bob Ballew is a 32-year-old married male, he has volunteered to make the entry,
and he is fully aware of the radiological risks involved. He has worked at the
Harris plant as a member of the Maintenance department since he left another
nuclear utility 3 years ago.
3) Charles Cotton is a 51-year-old single male and although he has not volunteered
to make the entry, he is fully aware of the radiological risks involved. He is the
most knowledgeable of the 5 persons, having been a member of the Maintenance
department for his entire 28 years at the Harris plant.
4) David Deaver is a 37-year-old married male, he has volunteered to make the
entry, and he is fully aware of the radiological risks involved. He has worked at
the Harris plant for 15 years, the last 11 years as a member of the Maintenance
department since he left Operations.
5) Frank Furstenburg is a 56-year-old single male, he has volunteered to make the
entry, and he is fully aware of the radiological risks involved. Although he has
only worked at Harris for the past 2 years, both years were spent in the
Maintenance department, and he has experience in these situations, having made a
similar entry 17 years ago at another nuclear utility.
Which 3 of these 5 persons should be selected to make the emergency entry, AND why
should these 3 be picked?
Page 7 of 8
Rev. Date 07/21/02
JPM SRO-A.3
HARRIS
CANDIDATE QUESTION SHEET
QUESTION #1
(TO BE RETURNED TO EXAMINER UPON COMPLETION)
Radwaste is making preparations to discharge the Waste Evaporator Condensate Tank
(WECT) when it is determined that FT-6119, WMT / WECT Discharge Flow, is
What are the license requirenents that must be met to allow the WECT to be discharged
with FT-6119 inoperable?
Page 8 of 8
Rev. Date 07/21/02
JPM RO-A.3
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM RO-A.3
Radiological Controls
CANDIDATE:
EXAMINER:
Page 1 of 7
Rev. Date 07/27/02
JPM RO-A.3
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Radiological Controls
ALTERNATE PATH: INA - Questions
FACILITY JPM NUMBER: NA - Questions
KA: 1) 2.3.2 IMPORTANCE: SRO NA RO 1)2.5
2) 2.3.10 2) 2.9
KA STATEMENT: 1) Knowledge of the facility ALARA program.
2) Ability to perform procedures to reduce excessive levels
of radiation and guard against personnel exposure.
TASK STANDARD: NA - Questions
- 1'
PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT
PREFERRED EVALUATION METHOD: PERFORM Vt'
SIMULATE
REFERENCES: AP-545, Containment Entries
AP-504, Administrative Controls for Locked and Very High
Radiation Areas
VALIDATION TIME: 15 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 7
Rev. Date 07/27/02
JPM RO-A.3
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
NOTE: ENSURE THE FOLLOWING REFERENCES ARE AVAILABLE FOR USE
IN ANSWERING THE ATTACHED QUESTIONS:
AP-545, "Containment Entries"
AP-504, "Administrative Controls for Locked and Very High Radiation Areas"
Page 3 of 7
Rev. Date 07/27/02
JPM RO-A.3
HARRIS
START TIME:
EXAMINER'S ANSWER KEY
QUESTION #1
You are one member of a 5-member team performing an Emergent Entry into
Containment with the plant in Mode 1. The following conditions have been established:
"* The estimated gamma dose rate in the area is 100 mRem/hour.
"* The estimated neutron dose rate in the area is 4 mRem/hour.
"* A heat stress evaluation has NOT been performed and all personnel will be wearing
ice vests.
"* The HP Supervisor has limited the total gamma dose received by the team to
1 man-Rem and the total neutron dose received by the team to 0.03 man-Rem.
Assuming each team member's initial annual TEDE for the year is 100 mRem, WHY is
your Maximum Allowable Stay Time inside Containment only 45 minutes?
ANSWER:
Although the gamma dose rate would permit each team member to work for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,
and the neutron dose rate would permit each team member to work for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, since
a heat stress evaluation has NOT been performed each member's stay time is limited
to 45 minutes.
(Required response underlined and bolded)
REFERENCES:
AP-545, "Containment Entries"
2.3.2 / RO 2.5 / Knowledge of the facility ALARA program
STOP TIME:
Page 4 of 7
Rev. Date 07/27/02
JPM RO-A.3
HARRIS
START TIME:
EXAMINER'S ANSWER KEY
QUESTION #2
You require access into a Locked High Radiation Area (LHRA) to hang a clearance on a
valve. HP approval has been obtained to enter the area.
How is a key to the LHRA obtained?
ANSWER:
The HP Technician assigned to perform job coverage must check out an LHRA key
and maintain positive control of the key, returning it to the Lead HP Technician upon
exiting the LHRA.
(Required response underlined and bolded)
REFERENCES:
AP-504, "Administrative Controls for Locked and Very High Radiation Areas"
2.3.10 / RO 2.9 / Ability to perform procedures to reduce excessive levels of radiation
and guard against personnel exposure.
STOP TIME:
Page 5 of 7
Rev. Date 07/27/02
JPM RO-A.3
HARRIS
CANDIDATE QUESTION SHEET
QUESTION #2
(TO BE RETURNED TO EXAMINER UPON COMPLETION)
You require access into a Locked High Radiation Area (LHRA) to hang a clearance on a
valve. HP approval has been obtained to enter the area.
How is a key to the LHRA obtained?
Page 6 of 7
Rev. Date 07/27/02
JPM RO-A.3
HARRIS
CANDIDATE QUESTION SHEET
QUESTION #1
(TO BE RETURNED TO EXAMINER UPON COMPLETION)
You are one member of a 5-member team performing an Emergent Entry into
Containment with the plant in Mode 1. The following conditions have been established:
"* The estimated gamma dose rate in the area is 100 mRem/hour.
"* The estimated neutron dose rate in the area is 4 toRem/hour.
"* A heat stress evaluation has NOT been performed and all personnel will be wearing
ice vests.
"* The HP Supervisor has limited the total gamma dose received by the team to
1 man-Rem and the total neutron dose received by the team to 0.03 man-Rem.
Assuming each team member's initial annual TEDE for the year is 100 mRem, WHY is
your Maximum Allowable Stay Time inside Containment only 45 minutes?
Page 7 of 7
Rev. Date 07/27/02
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
SAM NUNN ATLANTA FEDERAL CENTER
61 FORSYTH STREET, SW, SUITE 23T85
ATLANTA, GEORGIA 30303-8931
August 22, 2002
MEMORANDUM TO: Kathleen O'Donohue, Senior Operations Engineer
George T. Hopper, Senior Operations Engineer
FROM: Michael E. Ernstes, Chief
Operator Licensing and Human Performance Branch
SUBJECT: EXAMINATION ASSIGNMENTS - SHEARON HARRIS NJUCLEAR
PLANT - EXAM NO. 50-400/2002-301
APPLICANT DOCKET NO. EXAMINATI ON TYPE
Gary M. Fulks 55-22617 RO
Mark 0. Christopherson 55-21791 SRO Upgrade
55-22319 SRO Upgrade
Timothy A. English
55-22620 SRO Instant
William S. Saunders
55-22621 SRO Instant
Edward L. Wills, Jr.
Facility and Location: Shearon Harris Nuclear Plant, New Hill, NC
Facility Contact: Terry Toler, (919) 362-3493
NRC Chief Examiner: Kathleen O'Donohue
Written Examinations to be Prepared by (RO): Shearon Harris Nuclear Plant
(SRO): Shearon Harris Nuclear Plant
Date of Operating Tests: August 26 , 28, 2002
Date of Written Examinations: August 29, 2002
Time of Written Examinations: 8:00 a.m.
cc: D. Trimble, IEHB
J. Goshen, NRR
J. Brady, Shearon Harris
Senior Resident Inspector
B. Michael, DRS
OL Exam File
JPM RO-A.4
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM RO-A.4
Activate the Emergency Response Organization
- Dialogic System
CANDIDATE:
EXAMINER:
Page 1 of 8
Rev. Date 08/09/02
JPM RO-A.4
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Activate the Emergency Response Organization - Dialogic System
ALTERNATE PATH: None
FACILITY JPM NUMBER: NEW
KA: 2.4.43 IMPORTANCE: SRO NA RO 2.8
KA STATEMENT: Knowledge of emergency communications systems and
techniques
TASK STANDARD: The Emergency Response Organization has been notified of
a plant emergency using the Dialogic System
PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT
PREFERRED EVALUATION METHOD: PERFORM SIMULATE
REFERENCES: PEP-3 10, Notifications and Communications
VALIDATION TIME: 15 MINUTES TIME CRITICAL: Yes
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 8
Rev. Date 08/09/02
JPM RO-A.4
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
Telephone System
PEP-3 10, "Notifications and Communications," Attachment 6, "Emergency Response
Organization Activation - Dialogic System"
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
"ASite Area Emergency has been declared. It is currently 1030 on Saturday morning.
"APublic Address System announcement directing on-site members of the ERO to
activate the Emergency Response Facilities has been made.
INITIATING CUE(S):
You have been directed to initiate activation of the remainder of the ERO using PEP
310, "Notifications and Communications," Attachment 6, "Emergency Response
Organization Activation - Dialogic System."
NOTES:
1. USE A SPEAKERPHONE TO ALLOW DIALOGIC RESPONSES TO BE
HEARD BY EXAMINER.
2. IF USING AN E&E CENTER PHONE (SIMULATOR OR EOF), DIAL A "9"
PRIOR TO THE NUMBER.
Page 3 of 8
Rev. Date 08/09/02
JPM RO-A.4
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH A CURRENT COPY OF PEP-310,
ATTACHMENT 6
NOTES:
1. PROCEDURE STEPS CORRESPOND TO STEPS IN ATTACHMENT 6. CUES
LISTED (IF USED) SHOULD BE READ DIRECTLY AS WRITTEN AS
AUTOMATIC RESPONSES TO OPERATOR ACTIONS.
2. UNDERLINED CUES ARE REQUIRED TO BE GIVEN, EVEN IF JPM IS
ACTUALLY PERFORMED.
- 1 1 Scenario Determination - Selects scenario Critical to
Select the appropriate number "23" based on determine correct
scenario number from the a Site Area Emergency scenario number to
provided options occurring during off ensure proper
normal hours activation.
(weekend) __ _ _ _
CUE FOR JPM PURPOSES ONLY, USE THE FOUR-DIGIT CODE 2509 (SIMULATOR),
2510 (EOF), OR 2511 (CONTROL ROOM). IF USING AN E&E CENTER PHONE
(SIMULATOR OR EOF), DIAL A "9" PRIOR TO THE NUMBER.
- 2 2A Connecting to the System Picks up a plant Critical to connect
extension and dials to system to
Dial 2452 on a plant "2452" or picks up a establish operation.
extension or dial 362- Southern Bell line and
2452 if using a Southern dials "362-2452"
Bell line
CUE "HELLO"
- 3 2B Immediately enter 4357 Enters "4357#" Critical to establish
followed by the "#" key. immediately upon proper connection
hearing "hello" to system.
response
Page 4 of 8
Rev. Date 08/09/02
JPM RO-A.4
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
CUE "ENTER THE SCENARIO NUMBER YOU WISH TO WORK WITH."
- 4 2C Enter the appropriate Enters "2509" or Critical to enter
scenario number followed "2510" or "2511", proper scenario
by the "#" key depending on location number to ensure
correct notification.
CUE "YOU ENTERED 2509 (2510/2511). IS THAT CORRECT? PLEASE PRESS 9 FOR
YES, 6 FOR NO."
- 5 2D If correct, enter 9 Enters "9" Critical to validate
proper plant
conditions.
CUE "THE SELECTED SCENARIO HAS BEEN COMPLETED. DO YOU WANT TO
QUEUE IT? PLEASE PRESS 9 FOR YES, 6 FOR NO."
- 6 2E Enter 9 Enters "9" Critical to direct
system to begin
making calls.
CUE "YOU WILL QUEUE SCENARIO 2509 (2510/2511) AS A DRILL. ARE YOU SURE
THIS IS WHAT YOU WANT TO DO? PLEASE PRESS 9 FOR YES, 6 FOR NO:'
- 7 2F Enter 9 Enters "9' Critical to direct
system to begin
making calls.
CUE "PRESS 1 TO STOP SCENARIO MONITOR OR PRESS 2 TO SPEAK OF THE
STATUS. THE SELECTED SCENARIO IS ACTIVE, GOODBYE."
8 2G Hang up and prepare for Hangs up phone Note: The previous
system activation verification message should be
(System will soon dial disregarded as this
telephones in the SIM (362- a system default
1497 or 362-6257), EOF message not
(362-3650 or 362-3651), or associated with
MCR (362-7992 or 362- the ERO activation
.717997)). 1 process at Harris.
Page 5 of 8
Rev. Date 08/09/02
JPM RO-A.4
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
CUE PHONE LINE RINGS.
- 9 3A System Activation Picks up line that rings Critical to answer
Verification - and says anything phone to provide
When one of the Direct Bell (voice activated) verification of
lines rings, answer the system start.
telephone
CUE "THIS IS THE HARRIS NUCLEAR PLANT DIALOGIC SYSTEM. PLEASE
ENTER A 2 PLUS YOUR SOCIAL SECURITY NUMBER."
CUE FOR JPM PURPOSES ONLY, THE SOCIAL SECURITY NUMBER TO BE USED
IS "987-65-4321" (SIMULATOR), "987-65-4320" (EOF), OR "123-45-6789"
(CONTROL ROOM).
"*10 3B Enter 2-followed by Enters "2987654321" Critical to enter
appropriate SSN (SIMULATOR), number to verify
"2987654320" (EOF), actual event
or "2123456789" occurring requiring
(CONTROL ROOM) notification.
CUE "YOU ENTERED 2-987-65-4321 (SIMULATOR), 2-987-65-4320 (EOF), 2-123-45
6789 (CONTROL ROOM). IS THAT CORRECT? PLEASE PRESS 9 FOR YES, 6
FOR NO."
"*11 3C If correct, enter 9 Enters "9" Critical to verify
previous
information to start
system.
CUE "THIS IS A DRILL. I REPEAT, THIS IS A DRILL. NO FACILITIES WILL BE
ACTIVATED FOR THIS DRILL. I REPEAT, NO FACILITIES WILL BE
ACTIVATED FOR THIS DRILL. ARE YOU FIT FOR DUTY?"
"*12 3D Enter 9 Enters "9" Critical to respond
with 'yes' response
to start system.
Page 6 of 8
Rev. Date 08/09/02
JPM RO-A.4
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP 7 UNSAT
CUE "PLEASE ENTER YOUR ETA IN MINUTES."
"*13 3E Enter 00 Enters "00" Note that any
number entry will
work for this entry.
Critical to enter any
number to initiate
dialing system.
CUE "YOU WILL BE FILLING THE POSITION OF MAIN CONTROL ROOM.
GOODBYE."
14 3F If the computer functioned as Notifies SEC-CR that
expected, notify the SEC-CR Dialogic is calling in the
that Dialogic is calling in the ERO
15 4 Completion - Signs and dates Previous step
Inform SEC-CR of the results completion of actually informed
of the system activation notification SEC-CR verbally.
TASK COMPLETE
STOP TIME:
Page 7 of 8
Rev. Date 08/09/02
JPM RO-A.4
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
A Site Area Emergency has been declared. It is currently 1030 on Saturday morning.
A Public Address System announcement directing on-site members of the ERO to
activate the Emergency Response Facilities has been made.
INITIATING CUE(S):
You have been directed to initiate activation of the remainder of the ERO using PEP
310, "Notifications and Communications," Attachment 6, "Emergency Response
Organization Activation - Dialogic System."
NOTES:
1) USE A SPEAKERPHONE TO ALLOW DIALOGIC RESPONSES TO BE
HEARD BY EXAMINER.
2) IF USING AN E&E CENTER PHONE (SIMULATOR OR EOF), DIAL A "9"
PRIOR TO THE NUMBER.
Page 8 of 8
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM SRO-A.4
Perform an Emergency Action Level
Classification and Recommend Protective
Actions
CANDIDATE:
EXAMINER:
Page 1 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Perform an Emergency Action Level Classification and Recommend
Protective Actions
ALTERNATE PATH: None
FACILITY JPM NUMBER: NEW
KA: 2.4.41 / 2.4.44 IMPORTANCE: SRO 4.1/4.0 RO NA
KA STATEMENT: Knowledge of the emergency action level thresholds and
classifications. / Knowledge of emergency plan protective
action recommendations.
TASK STANDARD: General Emergency determined due to three (3) fission
product barriers breached (EAL 2-1-4) AND PARs
completed satisfactorily.
PREFERRED EVALUATION LOCATION: SIMULATOR V IN PLANT
PREFERRED EVALUATION METHOD: PERFORM V' SIMULATE
REFERENCES: "* Emergency Action Level Flowpath
"* PEP- 110, Emergency Classification and Protective Action
Recommendations
VALIDATION TIME: 15 MINUTES TIME CRITICAL: Yes
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
NOTE: Performance Rating based on 20% for satisfactory classification during
simulator scenario, 20% for satisfactory classification during JPM, and 60% for
satisfactory protective action recommendation during JPM. Include documentation
from applicable simulator scenario as part of this JPM package.
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
PEP- 110, "Emergency Classification and Protective Action Recommendations,"
Attachment 3, "Protective Action Recommendations Process"
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
Following a small break Loss of Coolant Accident which occurred 25 minutes ago, the
crew has been performing the actions of EOP-FRP-C. 1, "Response to Inadequate Core
Cooling." In response to all Core Exit Thermocouples being between 1300'F and
14000 F, the crew has initiated Safety Injection and opened all PRZ PORVs. EOP
FRP-C. 1 has directed an evaluation of the EAL Network using Entry Point U.
The following plant conditions are noted:
"* Core Exit Thermocouples are still exceeding 1250 0F.
"* The PRT has ruptured and Containment Pressure is 4.3 psig and increasing slowly.
"* Containment Isolation has been verified.
"* SG Narrow Range Levels are all off-scale low with NO MFW or AFW flow
available.
"* All SG Safety Valves and PORVs are currently closed.
"* SG Tube Leakage prior to the Reactor Trip and Safety Injection was 55 gpd.
"* The most recent RCS 1-131 dose equivalent sample was 63 gtCi/cc.
"* The GFFD is inoperable and has been out-of-service for approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
"* Core damage assessments are NOT yet available.
"* Emergency dose projections are NOT yet available.
Page 3 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
RADIATION MONITORING PANEL INDICATIONS
NOTE: Assume all radiation monitors NOT included in this list are indicating at or near
their normal value.
MONITOR DESCRIPTION READING / ALARM STATUS
RM-lCR-3589-SA Cnmt Hi Range Accident Slowly Increasing, but currently
Monitor Normal (Green)
RM-1CR-3590-SB Cnmt Hi Range Accident Slowly Increasing, but currently
Monitor Normal (Green)
RM-ILT-3502-SA Cnmt Leak Detection Noble 4E-5 pCi/cc and slowly increasing
Gas Channel above Alert (Yellow) level
RM-1LT-3502-SA Cnmt Leak Detection Slowly Increasing, but currently
Particulate Channel Normal (Green)
INITIATING CUE(S):
You are to classify this event.
Page 4 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: ENSURE AN EAL FLOWPATH AND CURRENT COPY OF PEP-110 ARE
AVAILABLE.
NOTE: THERE IS ALSO A LARGE LAMINATED COPY OF THIS WHICH MAY
BE USED.
NOTES:
1. PROCEDURE STEPS ARE NOT LISTED SINCE ATTACHMENT 3 OF PEP
110 IS A FLOWCHART WHICH DOES NOT CONTAIN NUMBERING OF
STEPS.
2. NOT REQUIRED TO REFERENCE PEP-110.
3. THE FOLLOWING JPM STEPS ARE DECISION POINTS REQUIRED TO BE
MADE TO OBTAIN THE CORRECT EAL CLASSIFICATION AND ARE
ADDRESSED FOR THIS REASON, ALTHOUGH NOT ALL ARE
CONSIDERED CRITICAL STEPS.
4. THIS JPM HAS TWO (2) TIME CRITICAL ELEMENTS. THE FIRST TIME
CRITICAL ELEMENT STARTS WHEN THE JPM STARTS AND ENDS WHEN
THE CLASSIFICATION IS COMPLETED. THE SECOND TIME CRITICAL
ELEMENT STARTS WHEN THE CANDIDATE BEGINS TO PERFORM THE
PROTECTIVE ACTION RECOMMENDATIONS AND ENDS WHEN THE
PROTECTIVE ACTION RECOMMENDATIONS ARE COMPLETED.
PLACES TO ENTER THE START AND STOP TIMES FOR THE TIMES ARE
INCLUDED.
Page 5 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
1PM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
FIRST TIME CRITICAL ELEMENT START TIME:
proper location at Entry Point "U" and initial conditions
indicates RCS due to being
Breached on FPB directed to this
Status Board entry by EOP-FRP
C.1.
Critical to identify
RCS as
BREACHED.
An incorrect entry
here would result in
determining RCS
intact instead of
breached.
2 Indicate RCS Breached on Indicates RCS Breached
FPB Status Board on FPB Status Board
3 Initiates monitoring of Directs Unit-SCO to NOTE: Crew
Critical Safety Functions initiate monitoring should be already
monitoring due to
being in EOP
Network.
4 Any Rad Mon in EAL Table <NO> Determines no
1 in High Alarm Rad Monitors in EAL
Table 1 in High Alarm
- 5 Was Entry at Point "T" <NO> Determines NOTE: Given in
entry was made at initial conditions.
Point "U"
Critical to reach
determination that
Fuel is
JEOPARDIZED.
An incorrect
decision here
would result in
determining Fuel
intact instead of
jeopardized.
6 GFFD Increased > 1.0E5 cpm <NO> Determines NOTE: Given in
in 30 Mins GFFD is out-of-service initial conditions.
Page 6 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
STEST ETEP UNSAT
7 RCS Activity (1-131 Dose <NO> Determines RCS NOTE: Given in
Equivalent) > 300 uCi/cc Activity < 300 tCi/cc initial conditions.
(63 gCi/cc)
- 8 Core Cooling CSF Red <YES> Determines Critical to identify
Core Cooling CSF is Fuel as
RED due to CETs JEOPARDIZED.
being > 12000 F
An incorrect
decision here
would result in
determining Fuel
intact instead of
jeopardized.
9 Indicate Fuel Jeopardized on Indicates Fuel
FPB Status Board Jeopardized on FPB
Status Board
10 EOP-PATH-2 Entered <NO> Determines EOP
PATH-2 was NOT
entered
11 Cnmt Leak Det Rad Mon <NO> Determines Cnmt NOTE: Given in
Noble Gas Chnl > 8E-3 Leak Det Rad Mon initial conditions.
JtCi/cc Noble Gas Chnl < 8E-3
giCi/cc (4E-5 tCi/cc)
12 Was Entry at Point "U" <YES> Determines NOTE: Given in
entry was made at Point initial conditions.
"U"
13 Was Entry at Point "V" <NO> Determines entry NOTE: Given in
was made at Point "U" initial conditions
"*14 Is Cnmt Phase A or Vent <YES> Determines NOTE: Safety
Isolation Required? Phase A and Vent Injection actuated
Isolation required due in EOP-FRP-C. 1 if
to Safety Injection not previously.
signal
Critical to prevent
changing decision
for RCS and Fuel
to intact.
An incorrect
decision here
would result in
RCS and Fuel
being considered
intact.
Page 7 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
15 Primary-to-secondary leakage <NO> Determines NOTE: SG tube
in any SG > 10 gpm primary-to-secondary leakage given in
leakage in all SGs < 10 initial conditions as
gpm 55 gpd.
16 SG Pressure > 1230 psig <NO> Determines SG NOTE: Given in
pressure < 1230 psig due initial conditions.
to all SG Safeties and
PORVs being closed
- 17 Cnmt > 3 psig <YES> Determines NOTE: Given in
Cnmt pressure > 3 psig initial conditions.
(4.3 psig)
Critical to identify
Containment as
JEOPARDIZED.
An incorrect
decision here
would result in
Containment being
considered intact
instead of
jeopardized.
18 Indicate Cnmt Jeopardized on Indicates Cnmt
FPB Status Board Jeopardized on FPB
Status Board
"*19 3 FPBs Breached I <YES> Determines all NOTE: Incorrect
Jeopardized 3 FPBs are breached response to this
decision would
result in improper
classification due to
only 2 FPBs being
considered
breached.
Critical to allow
determination of
proper EAL
classification and
PARs.
Page 8 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
- 20 General Emergency EAL 2- Determines General Critical to
1-4 exceeded Emergency EAL 2-1-4 determine proper
exceeded EAL classification
and allow
determination of
PARs.
NOTE: MUST BE
FIRST TIME CRITICAL ELEMENT STOP TIME: COMPLETE WITHIN 15
MIN TO COMPLETE SAT.
CUE IF CANDIDATE DOES DETERMINE EAL NOTE: Although
CLASSIFICATION TO BE GENERAL conditions are
EMERGENCY, PROVIDE CANDIDATE WITH different in
ATTACHMENT 'A' (WIND SPEED AND Attachment B,
DIRECTION) AND DIRECT CANDIDATE TO same process and
NOW DETERMINE PROTECTIVE ACTION responses are used
RECOMMENDATIONS BASED ON THIS EVENT. in remainder of
JPM.
COND. CUE IF CANDIDATE DOES NOT DETERMINE EAL
CLASSIFICATION TO BE GENERAL
EMERGENCY, PROVIDE CANDIDATE WITH
ATTACHMENT 'B' (CUE SHEET) AND DIRECT
CANDIDATE TO DETERMINE PROTECTIVE
ACTION RECOMMENDATIONS BASED ON THIS
ATTACHED EVENT.
NOTE: ENSURE A CURRENT COPY OF PEP-110, ATTACHMENT 3, IS
AVAILABLE.
NOTE: THERE IS ALSO A LARGE LAMINATED COPY OF THIS WHICH MAY
BE USED.
SECOND TIME CRITICAL ELEMENT START TIME:
"*21 General Emergency <YES> Determines NOTE: If using
Declared? General Emergency Attachment B
declared based on just conditions, this
determined EAL should be YES due
to given conditions.
Critical to allow
determination of
PARs.
Page 9 of 14
Rev. Date 08/09/02
JPM SRO-A,4
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP IUNSAT
- 22 Substantial core damage is <NO> Determines NO NOTE: Conditions
imminent or has occurred substantial core all given in initial
damage is imminent or conditions.
has occurred due to not
having any core NOTE: If using
damage assessment Attachment B
damage, CETs being < conditions, this
2300 0%, and the core should be NO due
being uncovered for < to Core Damage
30 minutes. being less than 1%
Additionally, Note 4 on melt, CETs being <
PAR Flowchart does 23000 F, and the
NOT apply due to no core being
direct pathway from uncovered for < 30
the containment to the minutes.
environment.
Critical to allow
determination of
PARs.
- 23 Determine wind direction Determines wind NOTE: Wind
direction from 2200 direction is always
given "from".
Critical to
determine proper
evacuation and
sheltering
subzones.
- 24 Determine evacuation areas Determines evacuation NOTE: Based on 2
subzones to be A,B,C mile radius and
wind direction
using 2 miles
radius / 5 mile
downwind table.
Critical to
determine proper
evacuation
subzones.
Page 10 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP UNSAT
- 25 Determine shelter areas Determines shelter NOTE: Based on 5
subzones to be miles downwind
D,E,F,G,H,I,J,K,L,M,N and wind direction
using 2 miles
radius / 5 mile
downwind table.
Critical to
determine proper
sheltering
subzones.
NOTE: MUST BE
SECOND TIME CRITICAL ELEMENT STOP TIME: COMPLETE WITHIN 15
MIN TO COMPLETE SAT.
TASK COMPLETE
STOP TIME:
Page 11 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
CANDIDATE ATTACHMENT B
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
A GENERAL EMERGENCY has been declared following a large break loss of
coolant accident.
The following conditions are noted:
"* Core Exit Thermocouple temperatures are all between 1500 0 F and 16000 F
following the core being uncovered for 18 minutes.
"* Radiochemistry analysis indicates that approximately 0.2% of the fuel volume has
melted.
"* RHR is injecting through the RCS cold legs.
"* Containment Spray is operating with Containment Pressure at 18 psig.
"* Containment hydrogen concentration is 5.5%.
"* Wind Direction is 2200.
"* Wind Speed is 18 mph.
INITIATING CUE(S):
Determine the Protective Action Recommendations for these conditions.
Page 12 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
CANDIDATE ATTACHMENT A
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
WIND DIRECTION AND SPEED
"* Wind Direction is 2200.
"* Wind Speed is 18 mph.
Page 13 of 14
Rev. Date 08/09/02
JPM SRO-A.4
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Following a small break Loss of Coolant Accident which occurred 25 minutes ago, the
crew has been performing the actions of EOP-FRP-C. 1, "Response to Inadequate Core
Cooling." In response to all Core Exit Thermocouples being between 1300'F and
14000 F, the crew has initiated Safety Injection and opened all PRZ PORVs. EOP
FRP-C. 1 has directed an evaluation of the EAL Network using Entry Point U.
The following plant conditions are noted:
"* Core Exit Thermocouples are still exceeding 1250'F.
"* The PRT has ruptured and Containment Pressure is 4.3 psig and increasing slowly.
"* Containment Isolation has been verified.
"* SG Narrow Range Levels are all off-scale low with NO MFW or AFW flow
available.
"* All SG Safety Valves and PORVs are currently closed.
"* SG Tube Leakage prior to the Reactor Trip and Safety Injection was 55 gpd.
"* The most recent RCS 1-131 dose equivalent sample was 63 jiCi/cc.
"* The GFFD is inoperable and has been out-of-service for approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
"* Core damage assessments are NOT yet available.
"* Emergency dose projections are NOT yet available.
RADIATION MONITORING PANEL INDICATIONS
NOTE: Assume all radiation monitors NOT included in this list are indicating at or near
their normal value.
MONITOR DESCRIPTION READING / ALARM STATUS
RM-1CR-3589-SA Cnmt Hi Range Accident Slowly Increasing, but currently
Monitor Normal (Green)
RM-1CR-3590-SB Cnmt Hi Range Accident Slowly Increasing, but currently
Monitor Normal (Green)
RM-ILT-3502-SA Cnmt Leak Detection Noble 4E-5 MCi/cc and slowly increasing
Gas Channel above Alert (Yellow) level
RM-1LT-3502-SA Cnmt Leak Detection Slowly Increasing, but currently
Particulate Channel Normal (Green)
INITIATING CUE(S):
You are to classify this event.
Page 14 of 14
Rev. Date 08/09/02
JPM COM-B.I.c
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B.1.c
Secure One Train of CCW to the RHR HXs
CANDIDATE:
EXAMINER:
Page 1 of 6
Rev Date 07/21/02
JPM COM-B. .c
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Secure One Train of CCW to the RHR HXs
ALTERNATE PATH: None
FACILITY JPM NUMBER: RO-B. 1.e (NRC Exam - Dec 2000)
KA: 008A2.01 IMPORTANCE: SRO 3.3 RO 3.1
KA STATEMENT: Ability to operate and / or monitor in the control room:
CCW indications and controls.
TASK STANDARD: Train 'A' CCW is supplying the RHR HX and the non
essential loop.
PREFERRED EVALUATION LOCATION: SIMULATOR %' IN PLANT
PREFERRED EVALUATION METHOD: PERFORM .4 SIMULATE
REFERENCES: OP-145, Component Cooling Water
VALIDATION TIME: 15 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 6
Rev Date 07/21/02
JPM COM-B.1.c
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
- Ensure both 'A' and 'B' CCW pumps are operating.
- Adjust CCW flows <MRF CCW030 25> and <MRF CCW048 48>.
- FREEZE the simulator
- When candidate is ready, place simulator in RUN
OP-145, "Component Cooling Water," Section 8.14
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant is in Mode 4. Train 'B' RHR has been removed from service.
Both trains of CCW are in operation, with Train 'A' CCW supplying only the essential
loop and Train 'B' CCW supplying the essential and non-essential loops.
INITIATING CUE(S):
You are to secure CCW Pump 'B' in accordance with OP-145, Section 8.14.
Page 3 of 6
Rev Date 07/21/02
JPM COM-B. L.c
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH COPY OF OP-145, SECTION 8.14.
taken out of service is CCW FROM RHR establish flow
being supplied by the same HEAT limitations within
CCW pump as the Non- EXCHANGER B- the capability of a
Essential loop then SB single pump
perform the following * Verifies the valve
steps: closed by position Verification is not
taken out of service,
FROM RHR HEAT
EXCHANGER B-SB
3 8.14.2.1.2 * Verify total system flow Verifies total system
is less than 12,650 gpm flow is less than 12,000
gpm by adding the
indication on FI-652.1
and FI-653.1
- 4 8.14.2.1.3 Verify open, the following * Places 1CC-99 Critical to allow
valves: control switch in supplying the non
"* 1CC-99, CCW HEAT OPEN essential loop
EXCHANGER A TO * Places 1CC-128 from the running
NONESSENTIAL SUP control switch in ccw pump
EXCHANGER B TO * Verifies all valves Only critical to
NONESSENTIAL SUP now open by open ICC-99 and
"* 1CC-127, CCW observing position 1CC-128
NONESSENTIAL indicating lights
RETURN TO HEADER
B
NONESSENTIAL
RETURN TO
HEADER A
Page 4 of 6
Rev Date 07/21/02
JPM COM-B.1.c
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP UNSAT
- 5 8.14.2.1.4 At the MCB, stop the 0 Places CCW Pump Critical to
desired CCW Pump A-SA 1B-SB control establish a single
or B-SB switch in STOP running CCW
- Verifies the pump pump
stops by observing
breaker indicating Verification is not
lights critical
6 8.14.2.1.5 Verify Train B flow stops Verifies flow stops by
via FI-653.1 and that observing FI-653.1
pressure remains greater decreases to zero and
than 62 psig as per PI-650 pressure remains >62
psig on PI-650
7 8.14.2.2 If the RHR train to be taken Determines RHR train is
out of service is the only not the only flowpath for
flowpath for the CCW the CCW pump and does
pump, perform the following not perform Step
steps: 8.14.2.2
TASK COMPLETE
STOP TIME:
Page 5 of 6
Rev Date 07/21/02
JPM COM-B. L.c
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant is in Mode 4. Train B' RHR has been removed from service.
Both trains of CCW are in operation, with Train 'A' CCW supplying only the essential
loop and Train 'B' CCW supplying the essential and non-essential loops.
INITIATING CUE(S):
You are to secure CCW Pump Win accordance with OP-145, Section 8.14.
Page 6 of 6
Rev Date 07/21/02
JPM COM-B. 1.b
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B. 1.b
LOSP While Paralleling EDG from MCB for
Testing
CANDIDATE:
EXAMINER:
Page 1 of 7
Rev Date 07/21/02
JPM COM-B. l.d
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B.1.d
Manually Align Containment Spray
CANDIDATE:
EXAMINER:
Page 1 of 6
Rev Date 07/21/02
JPM COM-B. id
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Manually Align Containment Spray
ALTERNATE PATH: Starts Containment Spray and aligns valves
FACILITY JPM NUMBER: CR-106
KA: 026A4.01 IMPORTANCE: SRO 4.3 RO 4.5
KA STATEMENT: Manually operate in the control room: CSS controls.
TASK STANDARD: Containment Spray has been actuated and all RCPs have
been stopped.
PREFERRED EVALUATION LOCATION: SIMULATOR %1 IN PLANT
PREFERRED EVALUATION METHOD: PERFORM *1'
SIMULATE
REFERENCES: EOP-PATH-1
VALIDATION TIME: 10 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 6
Rev Date 07/21/02
JPM COM-B. 1.d
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
"* Initialize to a 100 percent condition.
"* Defeat Hi-3 Containment Pressure Signal such that Containment Spray and Phase B Isolation
are not actuated. <ZRPK:519A, ZRPK:519B>
"* Defeat the manual Containment Spray actuation switches on the MCB. <ICOR ZRPK:505A,
ZRPK:505B, ZRPK:506A, ZRPK:506B>
"* Insert an RCS break of sufficient size to sustain containment pressure greater than 10# and
follow PATH-1 to Step 10-- CNMT PRESSURE REMAINED BELOW 10 PSIG. <IMF
RCS 18A 80>
"* Maintain RCPs operating.
"* Place simulator in FREEZE
"* When candidate is ready, place simulator in RUN
EOP-PATH-1 and EOP-PATH-1 Guide
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
An RCS break has occurred inside containment and a reactor trip and SI have been
initiated.
PATH-1 is being implemented.
INITIATING CUE(S):
Step 10, CNMT PRESSURE REMAINED BELOW 10 PSIG, of PATH-1 has just
been reached.
Perform Step 10 of PATH-1.
Page 3 of 6
Rev Date 07/21/02
JPM COM-B. 1.d
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH COPY OF EOP-GUIDE-1, PAGE 13 (STEP
10).
10 CNMT pressure has remained Checks pressure on
less than 10 psig MCB indicaters, ERFIS,
or Recorder Panel and
determines pressure has
exceeded 10 psig
2 10.a Verify Containment Spray Determines Containment
(RNO) actuated Spray Pumps A-SA and
B-SB NOT running
and/or checks ALB
001/4-1 Containment
Spray Actuation NOT lit
3 10.a Manually actuate Places two (2) Note: May attempt
(RNO) Containment Spray Containment Spray different
Actuation Hand combinations of
Switches in ACTUATE hand switches, two
position at a time.
- 4 10.a Manually actuate Places Pumps in Critical to start
(RNO) Containment Spray START: pumps and position
"* Containment Spray valves to provide
Pump A-SA spray flow
Pump B-SB
Places valves in OPEN:
"* 1CT-50, Cnmt
Spray Pump A-SA
Discharge
"* 1CT-88, Cnmt
Spray Pump B-SB
Discharge
"* 1CT-12, Cnmt
Spray Chemical
Addition
"* ICT-11, Cnmt
Spray Chemical
Addition
Page 4 of 6
Rev Date 07/21/02
JPM COM-B. 1.d
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
5 10.a Verify Phase B Isolation Places valves in NOTE: This is
(RNO) Valves shut CLOSE: NOT considered a
"* 1CC-207, CCW to critical step, and
RCPs may NOT be
"* ICC-208, CCW to performed since the
RCPs procedure does NOT
Thermal Barriers This step will be
Return performed in Step
"* 1CC-251, RCP 12 of PATH-1 when
Thermal Barriers Attachment 6 is
Return performed.
Bearing Oil Coolers Candidates may
Return perform this step at
"* 1CC-299, RCP this time, but it is
Bearing Oil Coolers NOT required to be
Return performed.
(RNO) STOP RCPs due to
isolating CCW
cooling flow to
TASK COMPLETE
STOP TIME:
Page 5 of 6
Rev Date 07/21/02
JPM COM-B. 1.d
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
An RCS break has occurred inside containment and a reactor trip and SI have been
initiated.
PATH- 1 is being implemented.
INITIATING CUE(S):
Step 10, CNMT PRESSURE REMAINED BELOW 10 PSIG, of PATH-1 has just
been reached.
Perform Step 10 of PATH-1.
Page 6 of 6
Rev Date 07/21/02
JPM COM-B.1.e
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B. 1.e
Transfer to Hot Leg Recirculation
CANDIDATE:
EXAMINER:
Page 1 of 7
Rev Date 07/21/02
JPM COM-B. L.e
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Transfer to Hot Leg Recirculation
ALTERNATE PATH: Train B high head flow is re-established through cold leg
injection due to failure of hot leg injection valve to open
FACILITY JPM NUMBER: CR-066
KA: 006A4.05 IMPORTANCE: SRO 3.8 RO 3.9
KA STATEMENT: Operate in the control room: Transfer of ECCS flowpaths
prior to recirculation.
TASK STANDARD: Hot leg recirculation has been established.
PREFERRED EVALUATION LOCATION: SIMULATOR 10 IN PLANT
PREFERRED EVALUATION METHOD: PERFORM *1'
SIMULATE
REFERENCES: EOP-EPP-01 1, Transfer Between Cold Leg and Hot Leg
Recirculation
VALIDATION TIME: 15 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 7
Rev Date 07/21/02
JPM COM-B. 1.e
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
Establish the following conditions:
"* Post-LOCA, the plant is aligned for cold leg recirculation per EPP-010, with SI-341
open and SI-340 closed.
"* A and B CSIPs are operating.
"* A and B RHR pumps are operating.
"* RCS pressure is approximately 0 PSIG.
"* Insert a failure for 1SI-86 to normal so it will not open <IOR XA11063 NORMAL>
"* Place simulator in FREEZE.
"* When candidate is ready, place simulator in RUN.
EOP-EPP-01 1, "Transfer Between Cold Leg and Hot Leg Recirculation"
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant has experienced a LB LOCA.
It has been 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> since the LOCA occurred and the plant is aligned for cold leg
recirculation per EOP-EPP-010, "Transfer to Cold Leg Recirculation."
INITIATING CUE(S):
You have been directed to perform a transfer to hot leg recirculation per EOP-EPP
011, "Transfer Between Cold Leg and Hot Leg Recirculation."
Page 3 of 7
Rev Date 07/21/02
JPM COM-B. 1.e
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH COPY OF EOP-EPP-011.
Check charging line isolated Determines charging
line is isolated by
checking charging flow
FI-122.1 indicating 0 or
by checking valves 1CS
235 and ICS-238 closed
2 2 Check SI aligned for Cold Determines aligned for
Leg Recirculation Cold Leg Recirculation
by checking valves or by
checking flow on FI
943 and FI-940
- 3 3.a Align RHR Pumps For Hot Places control power to Critical to isolate CL
Leg Recirculation: ON and then places recirc to allow
- Shut low head SI to cold valve to CLOSED: alignment for HL
leg valves 1SI-340 and * 1SI-341, Low Head recirc
Leg Cont Pwr & Only critical to shut
Vlv Pos AND Low valve SI-341 since
Head SI Train B to SI-340 is already
Cold Leg closed.
Verifies closed:
1SI-340, Low Head
SI Train A to Cold
Leg
- 4 3.b * Open low head SI to hot Places control power to Critical to provide
leg valve 1SI-359 ON and then places flowpath for HL
valve to OPEN: recirc
- lSI-359, Low Head
SI Trains A & B to
Cold Leg Cont Pwr
& Vlv Pos AND
Low Head SI
Trains A & B to
Cold Leg
Page 4 of 7
Rev Date 07/21/02
JPM COM-B. L.e
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
5 4 Check CSIP injection flow Determines valves
path: OPEN by checking
"* Alternate high head SI to position:
cold leg valve - OPEN: * 1SI-52, Alt High
iSI-52 Head SI to Cold Leg
"* Any BIT outlet valve - * 1SI-3, Boron Inj
OPEN: 1SI-3 or 1SI-4 Tank Outlet
Tank Outlet
- 6 5.a Align both CSIPs for hot leg Places CSIP A in Critical to prevent
recirculation STOP damage to pump due
- Stop Train A CSIP to no flowpath
- 7 5.b 0 Shut alternate high Places control power to Critical to isolate CL
head SI to cold leg ON and then places recirc to allow
valve: 1SI-52 valve to CLOSE: alignment for HL
- 1SI-52, Alt High recirc
Head SI to Cold
Leg Cont Pwr &
Vlv Pos AND Alt
High Head SI to
Cold Leg
- 8 5.c * Open alternate high Places control power to Critical to provide
head SI to hot leg valve: ON and then places flowpath for HL
1SI-107 valve to OPEN: recirc
- 1SI-107, Alt High
Head SI to Hot Leg
Cont Pwr & VIv
Pos AND Alt High
Head SI to Hot Leg
- 9 5.d * Start Train A CSIP Places CSIP A in Verification of
START and verifies current and flow is
current on EI-221 and NOT critical
flow on FI-940
Critical to provide
flow
"*10 5.e * Stop Train B CSIP Places CSIP B in STOP Critical to prevent
damage to pump due
to no flowpath
11 5.f * Shut BIT outlet valves: Places valves to
Tank Outlet
Tank Outlet
Page 5 of 7
Rev Date 07/21/02
JPM COM-B. L.e
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP UNSAT
12 5.g * Open high head SI to hot Places control power to 1SI-86 FAILS TO
leg valve: 1SI-86 ON and then places OPEN
valve to OPEN:
1SI-86, High Head
SI to Hot Leg Cont
Pwr & Vlv Pos
AND High Head SI
to Hot Leg
"*13 5.g.1 Open BIT outlet valves: Places valves to OPEN: Critical to provide
(RNO) 1SI-3 and 1SI-4 * 1SI-3, Boron Inj flowpath for CL
Tank Outlet recirc since HL
1 1SI-4, Boron Inj flowpath cannot be
Tank Outlet established
14 5.g.2 Consult the Plant Consults Plant
(RNO) Operations Staff to Operations Staff
evaluate use of
Attachment 1 to open
High Head SI to Hot Leg
Valve while continuing
with this procedure
CUE THE UNIT SCO WILL CONTACT THE TSC, AND DIRECTS YOU TO CONTINUE
WITH THE PROCEDURE UNTIL A RECOMMENDATION IS RECEIVED.
"*15 5.h * Start Train B CSIP Places CSIP B in Verification of
START and verifies current and flow is
current on EI-222 and NOT critical
flow on FI-943
Critical to provide
flow
TASK COMPLETE
STOP TIME:
Page 6 of 7
Rev Date 07/21/02
JPM COM-B. 1.e
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant has experienced a LB LOCA.
It has been 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> since the LOCA occurred and the plant is aligned for cold leg
recirculation per EOP-EPP-010, "Transfer to Cold Leg Recirculation."
INITIATING CUE(S):
You have been directed to perform a transfer to hot leg recirculation per EOP-EPP
011, "Transfer Between Cold Leg and Hot Leg Recirculation."
Page 7 of 7
Rev Date 07/21/02
JPM COM-B. 1.f
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B. 1.f
Start an RCP Following Maintenance
CANDIDATE:
EXAMINER:
Page 1 of 6
Rev. Date 07/21/02
JPM COM-B. 1.f
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Start an RCP Following Maintenance
ALTERNATE PATH: None
FACILITY JPM NUMBER: CR-005
KA: 003A4.06 IMPORTANCE: SRO 2.9 RO 2.9
KA STATEMENT: Operate in the Control Room: Reactor Coolant Pump
parameters
TASK STANDARD: RCP A has been started
PREFERRED EVALUATION LOCATION: SIMULATOR %' IN PLANT
PREFERRED EVALUATION METHOD: PERFORM SIMULATE
REFERENCES: OP- 100, Reactor Coolant System
VALIDATION TIME: 10 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 6
Rev. Date 07/21/02
JPM COM-B.1.f
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
"* Initialize the simulator to a Mode 3 hot standby condition, 557 OF and 2235 psig <IC
7>
"* Secure RCP A
"* Allow simulator to run until plant conditions are stable, then FREEZE
"* When candidate is ready, place simulator in RUN
OP-100, "Reactor Coolant System," Section 5.1
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant is in Mode 3, 557°F and 2235 psig.
RCP A has been out of service for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance. Maintenance has been
completed and the RCP is ready for operation
INITIATING CUE(S):
You have been directed to start RCP A in accordance with OP- 100, "Reactor Coolant
System," Section 5.1. All initial conditions have been completed.
Page 3 of 6
Rev. Date 07/21/02
JPM COM-B.1.f
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH COPY OF OP-100, SECTION 5.1.
1 5.1.2.1.a Verify the following before Verifies RCS pressure >
pump start: 325 psig (May not
0 If jogging RCPs per GP- check - not applicable to
001, RCS pressure > 325 start)
psig
2 5.1.2.1.b 9 No. 1 seal Ap > 200 psid Verifies RCP A seal Ap
>200 psid. (PI-156A1)
3 5.1.2.1.c * Seal injection flow is Verifies RCP A seal
between 8 and 13 gpm at injection flow indication
a temperature between (FI-130A) and VCT
60'F and 1300 F outlet temp indication
(TI- 116.1) in limits
4 5.1.2.1.d * No. 1 seal leakoff is in Verifies RCP A seal
the normal operating leakoff meets
range of Attachment 3. Attachment 3 require
ments (FR-154A)
pump switch to start interlock for
starting pump
6 5.1.2.3 Verify the amber permissive Verifies amber permis
light on the lift pump control sive light on the RCP A
switch is lit indicating proper oil lift pump switch is lit
lift oil pressure has been
achieved
7 5.1.2.4 Allow the RCP oil lift pump Verifies a minimum of 2
to run for a minimum of 2 minutes has passed since
minutes before starting an starting the pump
start breaker for RCP
Page 4 of 6
Rev. Date 07/21/02
JPM COM-B.1.f
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP UNSAT
9 5.1.2.6 Verify the following normal Verifies parameters are
operating parameters: in the normal band
- Running amps: Hot 460 "* Running amps
to 540 amps, Cold 715 "* RCS flow
amps "* No. 1 seal Ap
"* RCS flow: >98% "* No. 1 seal leakoff
"* No. 1 seal Ap: > 200 psid "* Motor winding
"* No. 1 seal leakoff: in the temperature
normal operating range of
Attachment 3
"* Motor winding
temnnerature: .c300°F
10 5.1.2.7 After at least 1 minute, stop Verifies one minute has
the RCP oil lift pump passed and places RCP
A oil lift pump switch to
off
TASK COMPLETE
STOP TIME:
Page 5 of 6
Rev. Date 07/21/02
JPM COM-B. 1.f
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant is in Mode 3, 557°F and 2235 psig.
RCP A has been out of service for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance. Maintenance has been
completed and the RCP is ready for operation
INITIATING CUE(S):
You have been directed to start RCP A in accordance with OP- 100, "Reactor Coolant
System," Section 5.1. All initial conditions have been completed.
Page 6 of 6
Rev. Date 07/21/02
JPM COM-B. 1.g
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B.1.g
Power Range NI Gain Adjustment
CANDIDATE:
EXAMINER:
Page 1 of 8
Rev Date 07/21/02
JPM COM-B.I.g
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Power Range NI Gain Adjustment
ALTERNATE PATH: None
FACILITY JPM NUMBER: NEW
KA: 015A4.02 IMPORTANCE: SRO 3.9 RO 3.9
KA STATEMENT: Operate in the Control Room: NIS Indicators
TASK STANDARD: Gain has been adjusted within limits for PR Channel N-44
PREFERRED EVALUATION LOCATION: SIMULATOR V* IN PLANT
PREFERRED EVALUATION METHOD: PERFORM S SIMULATE
REFERENCES: OP-105, Excore Nuclear Instrumentation
VALIDATION TIME: 20 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 8
Rev Date 07/21/02
JPM COM-B.1.g
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
"* Initialize to a 100% equilibrium condition
"* Place Rod Control in MAN
"* Place Meter Rate on front of PR channel NI-44 to Fast
"* Unlock gain pot on the front of PR channel NI-44
"* Slowly adjust the gain to 1.56 (verify that it indicates approximately 3% - 3.5% below
the other 3 PR channels)
"* Ensure any alarms caused by this adjustment are acknowledged
"* Lock gain pot
"* Place Meter Rate on front of PR channel NI-44 to Slow
"* Place Rod Control in AUTO
"* FREEZE the simulator
"* When candidate is ready, place simulator in RUN
OP-105, "Excore Nuclear Instrumentation," Section 8.3 and Attachment 2
(Provide marked up copy of Attachment 2 to candidate)
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant is at 100% equilibrium conditions.
Following maintenance on PR Channel N-44, all required testing has been completed
and the channel is ready to be returned to service. A calorimetric has just been
performed per OST-1004, "Power Range Heat Balance, Computer Calculation, Daily
Interval, Mode 1 (Above 15% Power)."
The calculated power is 99.8%. Indicated power on PR channel N-44 at the time of
the calorimetric was at its current value. Rod Control is in Automatic.
INITIATING CUE(S):
You are to perform the Power Range NI Gain Adjust for PR channel N-44 in
accordance with OP-105, "Excore Nuclear Instrumentation," Section 8.3 and
Attachment 2.
Page 3 of 8
Rev Date 07/21/02
JPM COM-B. 1.g
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE:
"* PROVIDE CANDIDATE WITH COPY OF OP-105, SECTION 8.3, AND
ATTACHED MARKED UP COPY OF ATTACHMENT 2 OF OP-105.
"* ALL IDENTIFIED PROCEDURE STEPS ARE FROM ATTACHMENT 2.
ACTIONS ARE ONLY TO BE PERFORMED ON PR CH N-44.
1 1 Record the as found setting of Records setting as 1.56
the GAIN potentiometer on (1.54 to 1.58)
the front of Power Range
Drawer B
2 2 Determine the difference, Calculates difference to Determined by
including sign, between the be 3.6 subtracting indicated
calculated power and the (3.3 to 3.9) value of 96.2% from
indicated reactor power at the 99.8% calculated
time data was obtained as power.
follows:
CALC PWR - N44 IND
PWR = N44 DIFFERENCE
3 3 Determine the desired Calculates desired N-44 Determined by
indication, including sign, of indication to be 99.8% algebraically
NIS as follows: summing N-44
difference from Step
N44 PRESENT IND + N44 2 (JPM Step 2) and
DIFFERENCE = N44 N-44 present
DESIRED IND indicated value
4 4 Calculation in Steps 2 and 3 Requests independent
independently verified, verification of
calculation
CUE INDEPENDENT VERIFICATION HAS BEEN COMPLETED.
5 5 Before each channel Verifies no PR trip
adjustment, verify that there bistables energized on
are no PR trip bistables TSLB-3 or TSLB-4,
energized on TSLB-3 or with exception of PR
TSLB-4, except for trip High Flux Lo Setpoint,
bistables that are manually which is manually
blocked blocked
Page 4 of 8
Rev Date 07/21/02
JPM COM-B.1.g
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP UNSAT
6 6 On Drawer A, place the Places Meter Rate
METER RATE switch in switch to Fast position
FAST
- 7 7 Before adjustment of GAIN Places Rod Bank Critical to prevent
potentiometer for N-44, the Selector switch in inadvertent rod
ROD BANK SELECTOR Manual position motion due to power
switch should be placed in mismatch circuit
MANUAL to prevent
undesired rod movement
during the adjustment
CUE IF CANDIDATE DIRECTS RO TO PLACE RODS IN MANUAL, DIRECT
CANDIDATE TO PERFORM ACTION TO PLACE ROD CONTROL IN MANUAL.
8 8 Before adjustment of GAIN Verifies Feed Reg
potentiometer for N-44, the Bypass Valve
Feed Reg Bypass Valve Controllers are already
Controllers should be placed in Manual position
in manual to prevent
undesired valve motion
during adjustment
9 9 If a RATE TRIP signal Resets any Rate Trip
occurs, before going to the signals generated before
next channel, reset the RATE completing task for
TRIP signal. channel N-44
CUE IF CANDIDATE ASKS, THE UNIT-SCO DIRECTS RESETTING THE POWER
RATE TRIP.
"*10 10 At each power range Unlocks and slowly Critical to establish
drawer B, unlock and adjusts Gain pot in proper indication
slowly adjust GAIN CW direction until and operation of
potentiometer until the indicated power is channel N-44
indicated power is within within 0.2% of value
0.2% of the DESIRED IND previously determined
from Step 3 in Step 3 (JPM Step 4)
11 11 If there is insufficient fine N/A's step since
gain adjustment using the adequate adjustment
drawer B gain potentiometer, exists
perform the following:
Page 5 of 8
Rev Date 07/21/02
JPM COM-B. 1.g
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
12 12 Lock GAIN potentiometer in Locks Gain pot on N-44
place in place
13 Independent verification is Requests independent
required verification
CUE INDEPENDENT VERIFICATION HAS BEEN COMPLETED.
14 13 Record the as left GAIN Records as left Gain pot
potentiometer setting setting (within + 0.02 of
actual)
15 14 On Drawer A, place the Places Meter Rate
METER RATE switch in switch in Slow position
SLOW.
16 Independent verification is Requests independent
required verification
CUE INDEPENDENT VERIFICATION HAS BEEN COMPLETED.
17 15 Record the new indicated Records the new N-44
power (on drawer A) indicated power
"*18 16 Verify that new indicated Verifies that N-44 Critical since 2% is
power is within 2% of indicated power is limit for performing
desired indication from within 2% of desired gain adjustment
Step 3 above, indication
19 17 Place ROD BANK Places Rod Control back May reference OP
SELECTOR switch in the in automatic 104 to place rods in
desired position AUTO
20 18 Place Feed Reg Bypass Valve Leaves Feed Reg Bypass
Controllers in the desired Valves in manual
position
TASK COMPLETE
STOP TIME:
Page 6 of 8
Rev Date 07/21/02
JPM COM-B.1.g
HARRIS
JPM ATTACHMENT
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
OP-105, Attachment 2, Sheets 1-6
Page 7 of 8
Rev Date 07/21/02
JPM COM-B.I.g
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant is at 100% equilibrium conditions.
Following maintenance on PR Channel N-44, all required testing has been completed
and the channel is ready to be returned to service. A calorimetric has just been
performed per OST-1004, "Power Range Heat Balance, Computer Calculation, Daily
Interval, Mode 1 (Above 15% Power)."
The calculated power is 99.8%. Indicated power on PR channel N-44 at the time of
the calorimetric was at its current value. Rod Control is in Automatic.
INITIATING CUE(S):
You are to perform the Power Range NI Gain Adjust for PR channel N-44 in
accordance with OP-105, "Excore Nuclear Instrumentation," Section 8.3 and
Attachment 2.
Page 8 of 8
Rev Date 07/21/02
JPM COM-B.2.b
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B.2.b
Manually Control Charging Due to a Loss of IA
CANDIDATE:
EXAMINER:
Page 1 of 6
Rev Date 07/21/02
JPM COM-B.2.b
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Manually Control Charging Due to a Loss of IA
ALTERNATE PATH: None
KA: 004.A2.11 IMPORTANCE: SRO 4.2 RO 3.6
KA STATEMENT: Correct, control, or mitigate the consequences on CVCS
caused by the following malfunction: Loss of IAS
TASK STANDARD: Charging flow is being controlled locally
PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT *'
PREFERRED EVALUATION METHOD: PERFORM SIMULATE *'
REFERENCES: AOP-017, Loss of Instrument Air
VALIDATION TIME: 10 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 6
Rev Date 07/21/02
JPM COM-B.2.b
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
AOP-017, "Loss of Instrument Air"
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All in plant
steps shall be performed for this JPM, including any required communications. DO
NOT operate any equipment without my permission. I will provide initiating cues and
reports on other actions when directed or asked by you. Ensure you indicate to me
when you understand your assigned task. To indicate that you have completed your
assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant is at 100 percent power.
An instrument air header has ruptured on the RAB 236-foot elevation. The header has
been isolated but FCV-122, Charging Flow Control Valve, has failed open.
The Control Room has isolated charging (ICS-235 and 238 are shut). Pressurizer
level is 55 percent.
INITIATING CUE(S):
You have been directed to locally control charging flow per AOP-017, "Loss of
Instrument Air," Section 3.1, Step 6.b (RNO).
Page 3 of 6
Rev Date 07/21/02
JPM COM-B.2.b
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH CURRENT COPY OF AOP-017, SECTION
3.1
1 6.b.(1) Locally control charging flow Contacts Control Room
(RNO) by shutting at least one of the and requests 1CS-235
following: and /or be closed 1CS
"* 1CS-235, Charging Line 238
Isolation
"* ICS-238, Charging Line
Isolation
CUE THE CONTROL ROOM REPORTS BOTH 1CS-235 AND 1CS-238 ARE CLOSED
(ALSO GIVEN ON INITIATING CUE).
- 2 6.b.(2) Locally shut 1CS-228, * Rotates valve Critical to isolate
(RNO) Charging Line FCV Inlet handwheel in CW failed open FCV
Isolation Valve direction until no 122 to allow control
further movement of charging flow
is obtained
- Informs Control
Room that 1CS-228
is closed
CUE THE HANDWHEEL FOR 1CS-228 HAS BEEN ROTATED IN CW DIRECTION
AND NO FURTHER MOVEMENT CAN BE OBTAINED.
- 3 6.b.(3) Verify open the following: Contacts Control Critical to ensure
(RNO) o 1CS-235, Charging Line Room and requests the both valves are open
Isolation following valves both to allow charging
0 1CS-238, Charging Line be opened: flow to RCS
Isolation * 1CS-235
CUE THE CONTROL ROOM REPORTS BOTH 1CS-235 AND 1CS-238 ARE OPEN.
Page 4 of 6
Rev Date 07/21/02
JPM COM-B.2.b
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
- 4 6.b.(4) (CONTINUOUS ACTION) Throttles open ICS- Critical to provide
(RNO) Locally throttle 1CS-227, 227 by rotating required charging
Norm Charging Line FCV handwheel in CCW flow to RCS
Bypass, to obtain desired direction until directed
charging flow to stop opening by
Control Room
CUE THE HANDWHEEL FOR 1CS-227 IS BEING ROTATED IN CCW DIRECTION.
THE CONTROL ROOM DIRECTS YOU TO STOP OPENING VALVE AND
MAINTAIN CURRENT POSITION.
5 6.b.(4) Maintain current position of * Stops opening ICS
(RNO) lCS-227, Norm Charging 227 when directed
Line FCV Bypass by Control Room
- Informs Control
Room that 1CS-227
is being throttled to
required position
TASK COMPLETE
STOP TIME:
Page 5 of 6
Rev Date 07/21/02
JPM COM-B.2.b
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant is at 100 percent power.
An instrument air header has ruptured on the RAB 236-foot elevation. The header has
been isolated but FCV-122, Charging Flow Control Valve, has failed open.
The Control Room has isolated charging (1CS-235 and 238 are shut). Pressurizer
level is 55 percent.
INITIATING CUE(S):
You have been directed to locally control charging flow per AOP-017, "Loss of
Instrument Air," Section 3.1, Step 6.b (RNO).
Page 6 of 6
Rev Date 07/21/02
JPM COM-B.1.a
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B. 1.a
Respond to a Failed High Pressurizer Pressure
Channel
CANDIDATE:
EXAMINER:
Page 1 of 8
Rev Date 07/21/02
JPM COM-B.1.a
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Respond to a Failed High Pressurizer Pressure Channel
ALTERNATE PATH: Pressurizer PORV fails to reseat following actuation
FACILITY JPM NUMBER: NEW
KA: 010.A2.03 IMPORTANCE: SRO 4.2 RO 4.1
KA STATEMENT: Ability to correct, control, or mitigate the consequences of
the following PRZ PCS malfunction: PORV failures
TASK STANDARD: Master PRZ Controller is in MANUAL, controlling pressure,
with PORV Block Valve 1RC-1 13 closed.
PREFERRED EVALUATION LOCATION: SIMULATOR %1 IN PLANT
PREFERRED EVALUATION METHOD: PERFORM V. SIMULATE
REFERENCES: AOP-019, Malfunction of RCS Pressure Control
VALIDATION TIME: 10 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 8
Rev Date 07/21/02
JPM COM-B. L.a
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
"* Initialize to a 100% power IC.
"* FREEZE the simulator.
"* Enter malfunction to fail PRZ Pressure Channel 444 high and cause PORV to fail to
reseat <IMF PRS03F 0.1 10> <PT:444 2500 90>.
"* When candidate is ready, place simulator in RUN.
"* AOP-019, "Malfunction of RCS Pressure Control"
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant is operating at 100% power.
INITIATING CUE(S):
You are the Reactor Operator. Respond to any plant conditions.
Page 3 of 8
Rev Date 07/21/02
JPM COM-B. L.a
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
1 3.0.1 (IMMEDIATE ACTION) Determines bubble
Check that a bubble exists in exists due to plant
the PRZ conditions
- 2 3.0.2 (IMMEDIATE ACTION) * Determines PORV Critical to isolate the
Verify all PRZ PORVs and 444B failed to fully PORV to prevent
associated block valves close as pressure RPS and/or ESF
properly positioned for lowers actuation on low
current PRZ pressure and * Attempts to close pressure.
plant conditions PRZ PORV 444B by
placing control Only critical to close
switch in CLOSE PORV isolation
- Closes PRZ PORV valve.
444B isolation
valve, RC-113
- 3 3.0.3 (IMMEDIATE ACTION) Takes manual control Critical to close the
Check both PRZ spray of pressurizer spray spray valves to
valves properly positioned valves by either: prevent RPS and/or
for current PRZ pressure 0 Placing master ESF actuation on
and plant conditions. controller PK-444A low pressure.
in manual, or
- Placing spray Only critical to
valves in manual cause spray valves
to close, not perform
both actions.
CUE CONTINUE IN PROCEDURE (PROVIDE CANDIDATE WITH COPY OF AOP
019).
4 NA Obtain procedure Obtain current copy of
AOP-019, Sections 3.0
and 3.1
5 3.0.4 Go to Section 3.1, Pressure Refers to Section 3.1
Control Malfunctions While
Operating With a Pressurizer
Bubble.
Page 4 of 8
Rev Date 07/21/02
JPM COM-B. 1.a
HARRIS
3PM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP U
UNSAT
6 3.1.1 Refer to PEP-i1t0, Informs SRO of need to
Emergency Classification refer to PEP-I 10
and Protective Action
Recommendations, and enter
the EAL Network at entry
point X.
CUE OTHER OPERATORS WILL PERFORM EAL NETWORK CHECKS.
7 3.1.2 (CONTINUOUS ACTION) Monitors PRZ pressure
Monitor PRZ pressure by by observing one or
observing other reliable more of the following:
indication. * PI-455.1
- PI-456
- PI-457
8 3.1.3 Check plant in Mode 1 or 2. Determines plant in
Mode 1 by conditions
9 3.1.4 (CONTINUOUS ACTION) Determines PRZ
Check PRZ pressure pressure is controlled
controlled. using PK-444A in
MANUAL
10 3.1.5 (CONTINUOUS ACTION) Determines pressure is
Check PRZ pressure 2335 < 2335 psig
psig or less.
- 11 3.1.6 Check all of the following * Determines PRZ Critical to ensure 1
PRZ PORV block valves PORV block valves hour TS requirement
open or Refer to Technical open: for closed block
Specification 3.4.4 and * 1RC-117 valve is met.
implement action where * 1RC-115
appropriate: * Determines PRZ
"* 1RC-117 (for PCV- PORV block valve
"* 1RC-115 (for PCV- * Informs SRO of
445B) need to refer to TS
"* 1RC-113 (for PCV- 3.4.4.
444B SB)
CUE OTHER OPERATORS WILL REFER TO TECH SPECS.
Page 5 of 8
Rev Date 07/21/02
JPM COM-B.1.a
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
12 3.1.7 Check that a malfunction of Determines that PT-444
one or more of the following has failed high by
has occurred: comparing it to other
"* PT-444 channels.
"* PK-444A
"* PRZ heater(s)
"* PRZ spray valve(s) or
controller(s)
13 3.1.8 Verify PK-444A in Verifies PK-444A was
MANUAL. placed in MANUAL as
part of Immediate
Actions.
"*14 3.1.9.a Control PRZ pressure as Adjusts PK-444A Critical to maintain
follows: output by depressing control of PRZ
- Adjust PK-444A the UP or DOWN pressure.
output as necessary, to buttons as required to
attempt to restore and control pressure
maintain PRZ
pressure.
"*15 3.1.9.b (CONTINUOUS ACTION) * Checks both spray Only critical to
"* Check both PRZ spray valve controllers control spray valve
valve controllers in operating properly if positions to control
AUTO and both spray in auto PRZ pressure if
valves operating as . Manually operates spray valves are in
desired, OR spray controllers as manual control.
"* Verify both PRZ spray needed by
valve controllers in depressing LP or NOTE: If spray
MANUAL and operate DOWN buttons if valve controllers
spray valves as in manual were previously
necessary to control placed in manual
PRZ pressure they are to remain in
manual.
16 3.1.9.c (CONTINUOUS ACTION) Checks heaters operating
"* Check all PRZ heaters properly for pressure
operating as desired, OR
"* Manually operate
control switches for
heater groups as
necessary to control
PRZ pressure.
Page 6 of 8
Rev Date 07/21/02
JPM COM-B.L.a
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
STEP STEP UNSAT
17 3.1.10 Check at least one of the "* Determines
following conditions present, pressure, spray
orgo to Step 18: valves, and heaters
"* PRZ pressure is are controlled
uncontrolled "* Goes to Step 18
"* Status of a normal spray
valve or a PRZ heater
bank is uncontrolled
TASK COMPLETE WHEN DETERMINATION
MADE THAT RCS PRESSURE, HEATERS, AND
SPRAYS ARE UNDER CONTROL.
STOP TIME:
Page 7 of 8
Rev Date 07/21/02
JPM COM-B. L.a
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant is operating at 100% power.
INITIATING CUE(S):
You are the Reactor Operator. Respond to any plant conditions.
Page 8 of 8
Rev Date 07/21/02
JPM COM-B.2.a
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B.2.a
Local Actions for a Dropped Rod Recovery
CANDIDATE:
EXAMINER:
Page 1 of 8
Rev Date 07/21/02
JPM COM-B.2.a
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Local Actions for a Dropped Rod Recovery
ALTERNATE PATH: None
KA: 003AAl.02 IMPORTANCE: SRO 2.9 RO 2.9
KA STATEMENT: Operate the demand position counter and pulse/analog
converter
TASK STANDARD: Local actions have been completed for rod recovery
PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT *
PREFERRED EVALUATION METHOD: PERFORM SIMULATE *'
REFERENCES: AOP-001, Malfunction of Rod Control and Indication System
VALIDATION TIME: 15 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 8
Rev Date 07/21/02
JPM COM-B.2.a
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
Keys 33-36
AOP-001, "Malfunction of Rod Control and Indication System," Section 3.1
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All in plant
steps shall be performed for this JPM, including any required communications. DO
NOT operate any equipment without my permission. I will provide initiating cues and
reports on other actions when directed or asked by you. Ensure you indicate to me
when you understand your assigned task. To indicate that you have completed your
assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant was at 50% power when control bank D rod H2 dropped to the bottom of the
core.
Plant conditions have stabilized and the problem with rod H2 is fixed.
The crew is ready to retrieve the dropped rod.
INITIATING CUE(S):
Rod H2 is ready to be retrieved.
The SCO has directed you to obtain the correct key(s) and perform the local actions
associated with the retrieval of the dropped rod in accordance with AOP-001,
"Malfunction of Rod Control and Indication System," Section 3. 1.
Page 3 of 8
Rev Date 07/21/02
JPM COM-B.2.a
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH COPY OF AOP-001, SECTION 3.1
CUE THE CONTROL ROOM INFORMS YOU THEY ARE READY FOR YOU TO
PERFORM STEPS 3.1.12,3.1.13, AND 3.1.14.
1 3.1.12 Obtain the key for the Control Obtains keys 33-36
Rod Disconnect Switch Box
(keys 33-36)
- 2 3.1.13 Position lift coil disconnect * Unlocks cabinet Only critical to open
switches for rods in the and places the disconnect switches
affected bank as follows: disconnect switches for affect rods
"* Dropped rod - ROD for CBD group 1
CONNECTED (down) rods B8, H14, and Critical to ensure
"* All other rods - ROD P8 and group 2 only rod H2 moves
DISCONNECTED (up) rods F6, F10, K10, during retrieval
and K6 in the up
position
- Ensures rod H2 in
CBD group 1 is in
the down position
CUE THE DISCONNECT SWITCHES FOR CBD GROUP 1 RODS B8, H14, AND P8, AND
FOR GROUP 2 RODS F6, FlO, K10, AND K6 ARE IN THE UP POSITION. THE
DISCONNECT SWITCH FOR CBD ROD H2 IS IN THE DOWN POSITION.
3 Inform Control Room of Notifies Control Room
disconnect switch positions of disconnect switch
alignment
- 4 3.1.14 Record the Pulse-To- Opens the P/A Only critical to
Analog (P/A) converter converter cabinet, record P/A reading
reading for the affected selects Control Bank D,
bank: and records the Critical to ensure
"* Bank reading for Control proper response
"* P/A Reading Bank D after resetting P/A
converter later
CUE CONTROL BANK D HAS BEEN SELECTED AND THE INDICATION IS 165.
Page 4 of 8
Rev Date 07/21/02
JPM COM-B.2.a
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP j UNSAT
5 Inform Control Room of Step Informs Control Room
completion that Steps 3.1.12, 3.1.13,
and 3.1.14 are complete
CUE THE CONTROL INFORMS YOU THAT ROD H2 HAS BEEN RETRIEVED AND
YOU ARE TO PERFORM STEPS 3.1.23 AND 3.1.24.
6 Determine light status on Determines light status
Card A105 on Card A105
CUE THE LIGHT STATUS ON CARD A105 IS THE TOP, MIDDLE AND BOTTOM
LIGHTS ARE ALL LIT.
7 3.1.23 Repeatedly Press the "Master Depresses the Master
Cycler +1" button as needed Cycler +1 button and
to produce the following light determines the light
status on Card A 105: status on Card A105
"* Top light - LIT
"* Middle light - NOT LIT
"* Bottom light - LIT
CUE THE LIGHT STATUS ON CARD A105 IS THE TOP AND MIDDLE LIGHTS ARE
LIT AND THE BOTTOM LIGHT IS NOT LIT.
- 8 3.1.23 Repeatedly Press the * Depresses the Critical to ensure
"Master Cycler +1" button Master Cycler +1 Master Cycler light
as needed to produce the button and display is correct
following light status on determines the
Card A105: light status on
- Top light - LIT Card A105
- Middle light - NOT LIT * Determines light
- Bottom light - LIT status is correct
CUE THE LIGHT STATUS ON CARD A105 IS THE TOP AND BOTTOM LIGHTS ARE
LIT AND THE MIDDLE LIGHT IS NOT LIT.
9 Inform Control Room that Informs Control Room
Master Cycler indicates that Master Cycler
correctly indicates correctly
Page 5 of 8
Rev Date 07/21/02
JPM COM-B.2.a
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
- 10 3.1.24 Close all lift coil disconnect * Places the Only critical to
switches opened in step 13. disconnect switches connect disconnect
for CBD group 1 switches
rods B8, H14, and
P8 and group 2 Critical to ensure
rods F6, FlO, K10, movement of rods
and K6 in the down following
position completion of rod
- Closes and locks retrieval
cabinet
CUE ALL DISCONNECT SWITCHES ARE IN THE DOWN POSITION.
11 Inform Control Room that Informs Control Room
disconnect switches are in that disconnect switches
connect position are in connect position
CUE THE CONTROL ROOM DIRECTS YOU TO PERFORM THE RNO STEPS OF
STEP 3.1.26.
"*12 3.1.26. Perform the following at the Positions the Bank Critical to ensure
a Pulse-To-Analog (P/A) Display Selector Switch proper operation of
(RNO) Converter: to the Bank D position P/A converter and
- Position the Bank rod insertion limit
Display Selector Switch monitor
to the bank recorded in
step 14
CUE BANK DISPLAY SELECTOR SWITCH IS IN THE BANK POSITION INDICATED
BY THE CANDIDATE (EXPECTED POSITION IS 'D').
"*13 3.1.26. * Position and Hold the Positions and Holds the Critical to ensure
b Auto-Manual switch in Auto-Manual switch in proper operation of
(RNO) MANUAL MANUAL P/A converter and
rod insertion limit
monitor
CUE AUTO-MANUAL SWITCH IS BEING HELD IN THE MANUAL POSITION.
Page 6 of 8
Rev Date 07/21/02
JPM COM-B.2.a
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
CUE WHEN REQUESTED BY CANDIDATE BEFORE DEPRESSING THE DOWN
PUSHBUTTON, THE P/A READING IS 330 STEPS.
"*14 3.1.26. * Repeatedly Press either Depresses UP Critical to ensure
c the UP pushbutton or pushbutton until P/A proper operation of
(RNO) the DOWN pushbutton reading indicates 165 P/A converter and
as needed to make the rod insertion limit
display match the P/A monitor
reading recorded in step
14
CUE (COUNT NUMBER OF TIMES CANDIDATE DEPRESSES DOWN BUTTON AND
SUBTRACT FROM 330 TO DETERMINE THIS VALUE)
AFTER DEPRESSING THE DOWN PUSHBUTTON REPEATEDLY, THE P/A
READING IS THE VALUE DETERMINED BY COUNTING THE NUMBER OF
TIMES THE BUTTON WAS DEPRESSED AND SUBTRACTING THE NUMBER OF
TIMES DEPRESSED FROM 330 (FINAL EXPECTED VALUE IS 165 STEPS).
15 3.1.26. * Release the Auto-Manual Releases Auto-Manual
d switch switch
(RNO)
CUE THE AUTO-MANUAL SWITCH HAS BEEN RELEASED.
16 3.1.26. * Position the Bank Display * Positions Bank
e Selector Switch to Display Selector
(RNO) DISPLAY OFF Switch to DISPLAY
OFF and closes
cabinet
- Informs Control
Room that RNO
steps of Step 3.1.26
are complete
CUE BANK DISPLAY SELECTOR SWITCH IS IN THE DISPLAY OFF POSITION.
17 Inform Control Room that Informs Control Room
RNO steps of Step 3.1.26 are that RNO steps of Step
complete 3.1.26 are complete
TASK COMPLETE
STOP TIME:
Page 7 of 8
Rev Date 07/21/02
JPM COM-B.2.a
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant was at 50% power when control bank D rod H2 dropped to the bottom of the
core.
Plant conditions have stabilized and the problem with rod H2 is fixed.
The crew is ready to retrieve the dropped rod.
INITIATING CUE(S):
Rod H2 is ready to be retrieved.
The SCO has directed you to obtain the correct key(s) and perform the local actions
associated with the retrieval of the dropped rod in accordance with AOP-001,
"Malfunction of Rod Control and Indication System," Section 3.1.
Page 8 of 8
Rev Date 07/21/02
JPM COM-B.2,c
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
JPM COM-B.2.c
Start Up a Hydrogen Recombiner
CANDIDATE:
EXAMINER:
Page 1 of 8
Rev. Date 07/21/02
JPM COM-B.2.c
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Start Up a Hydrogen Recombiner
ALTERNATE PATH: None
KA: 028A4.01 IMPORTANCE: SRO 4.0 RO 4.0
KA STATEMENT: Operate the Hydrogen Recombiner controls
TASK STANDARD: Electric Hydrogen Recombiner A is in operation with the
proper power setting
PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT *1
PREFERRED EVALUATION METHOD: PERFORM SIMULATE V
REFERENCES: OP-125, Post Accident Hydrogen System
VALIDATION TIME: 20 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 8
Rev. Date 07/21/02
JPM COM-B.2.c
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
OP-125, "Post Accident Hydrogen System"
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All in plant
steps shall be performed for this JPM, including any required communications. DO
NOT operate any equipment without my permission. I will provide initiating cues and
reports on other actions when directed or asked by you. Ensure you indicate to me
when you understand your assigned task. To indicate that you have completed your
assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant has sustained a LOCA.
RCS pressure is 350 psig and core exit T/Cs are > 12000F.
INITIATING CUE(S):
EPP-FRP-C. 1, "Response to Inadequate Core Cooling," directs starting up a hydrogen
recombiner.
The Unit SCO directs you to start up Electrical Hydrogen Recombiner A using OP
125, "Post Accident Hydrogen System," Section 5.1.
Page 3 of 8
Rev. Date 07/21/02
JPM COM-B.2.c
HARRIS
START TIME:
- DENOTES CRITICAL STEP
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
NOTE: PROVIDE CANDIDATE WITH CURRENT COPY OF OP-125, SECTION
5.1
CUE ALL INITIAL CONDITIONS FOR SECTION 5.1 ARE COMPLETED.
1 5.1.2.1.a Perform the following Refers to SPTOP or
calculation: MCB containment
- Measure the contain- pressure indications to
ment pressure after a determine containment
LOCA using one of the pressure
following:
"* SPTOP
"* PI-950 SA, PI-952
953 SB
CUE: CONTAINMENT PRESSURE IS 5 PSIG.
2 5.1.2.1.b Determine the pre- Refers to DSR OST
LOCA containment 1021 to determine last
temperature from OST- known containment
1021 records temperature prior to
___ I____ I PRE-LOCA CONTAINMENT TEMPERATURE WAS 900F. _______ ____
CUE
3 5.1.2.1.c * Determine Pressure Refers to Attachment 8
Factor (Cp) from of OP-125 and
Attachment 8. determines Cp value of
1.25 (1.24 to 1.26)
Page 4 of 8
Rev. Date 07/21/02
JPM COM-B.2.c
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
- 4 5.1.2.1.d * Calculate required Refers to Attachment 8 Critical to
Electric Hydrogen of OP-125 and determine value to
Recombiner (EHR) calculates EHR power set EHR final
power by multiplying to be 51.1 KW (51.6 to setting
Cp x Reference Power 52. 1)
as shown on Attach- NOTE: Using
ment 8. values for EHR B
in error will result
in range of 49.8 to
50.8 (actual value
of 50.3)
5 5.1.2.2.a At the EHR Control Panel Verifies Power In
A-SA, perform the Available white light is
following: lit
Verify lit, Power In
Available, white light
CUE 'POWER IN AVAILABLE' WHITE LIGHT IS LIT.
6 5.1.2.2.b * Set the Power Adjust Rotates Power Adjust
potentiometer at zero pot fully CCW to zero
(000).
CUE 'POWER ADJUST' POT HAS BEEN ROTATED FULLY TO ZERO POSITION.
- 7 5.1.2.2.c * Place the Power Out Places Power Out Critical to provide
switch to on switch to on position output from EHR
CUE 'POWER OUT' SWITCH IS IN ON POSITION.
8 5.1.2.2.d * Verify lit the red light on Verifies red light lit on
the switch plate switch plate
CUE RED LIGHT ON SWITCH PLATE IS LIT.
9 1
5.1.2.2.f Turn the Power Adjust Rotates Power Adjust
potentiometer clockwise pot CW until Power Out
until 5 KW is obtained Meter indicates 5 KW
on the Power Out meter.
CUE 'POWER ADJUST' POT HAS BEEN ROTATED IN CW DIRECTION AND
'POWER OUT' METER READS 5 KW.
Page 5 of 8
Rev. Date 07/21/02
JPM COM-B.2.c
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
10 5.1.2.2.g * Maintain 5 KW for 10 Maintains current
minutes. position on Power
Adjust pot for 10
minutes
CUE 10 MINUTES HAVE ELAPSED.
11 5.1.2.2.h * Turn the Power Adjust Rotates Power Adjust
potentiometer clockwise pot CW until Power Out
until 10 KW is obtained Meter indicates 10 KW
on the Power Out meter
CUE 'POWER ADJUST' POT HAS BEEN ROTATED IN CW DIRECTION AND
'POWER OUT' METER READS 10 KW.
12 5.1.2.2.i * Maintain 10KW for 10 Maintains current
minutes. position on Power
Adjust pot for 10
minutes
CUE 10 MINUTES HAVE ELAPSED.
13 5.1.2.2.j Turn the Power Adjust Rotates Power Adjust
potentiometer clockwise pot CW until Power Out
until 20 KW is obtained Meter indicates 20 KW
on the Power Out meter.
CUE 'POWER ADJUST' POT HAS BEEN ROTATED IN CW DIRECTION AND
'POWER OUT' METER READS 20 KW.
14 1
5.1.2.2.k Maintain 20 KW for 5 Maintains current
minutes. position on Power
Adjust pot for 5 minutes
CUE 5 MINUTES HAVE ELAPSED.
Page 6 of 8
Rev. Date 07/21/02
JPM COM-B.2.c
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT/
[STEP STEP UNSAT
"*16 5.1.2.2.1 * Turn the Power Adjust Rotates Power Adjust Critical to establish
potentiometer pot CW until Power proper power
clockwise until the Out Meter indicates output from EHR
required power setting 51.1 to 52.1 KW (Value
calculated in Step determined in JPM
5.1.2.1.d (JPM Step 4) Step 4)
is obtained on the
Power Out meter.
CUE 'POWER ADJUST' POT HAS BEEN ROTATED IN CW DIRECTION AND
'POWER OUT' METER READS 51.1 to 52.1 KW (Value determined in JPM Step 4).
TASK COMPLETE
STOP TIME:
Page 7 of 8
Rev. Date 07/21/02
JPM COM-B.2.c
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant has sustained a LOCA.
RCS pressure is 350 psig and core exit TICs are > 1200 0 F.
INITIATING CUE(S):
EPP-FRP-C. 1, "Response to Inadequate Core Cooling," directs starting up a hydrogen
recombiner.
The Unit SCO directs you to start up Electrical Hydrogen Recombiner A using OP
125, "Post Accident Hydrogen System," Section 5.1.
Page 8 of 8
Rev. Date 07/21/02
JPM COM-B. L.b
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: LOSP While Paralleling EDG from MCB for Testing
ALTERNATE PATH: EDG output breaker 126 fails to open on LOSP and must be
manually opened
FACILITY JPM NUMBER NEW
KA: 056AA2.14 IMPORTANCE: SRO 4.6 RO 4.4
KA STATEMENT: Determine as related to a Loss of Offsite Power: Operational
status of EDGs
TASK STANDARD: EDG B output breaker 126 has been manually opened
PREFERRED EVALUATION LOCATION: SIMULATOR " IN PLANT
PERFORM SIMULATE
PREFERRED EVALUATION METHOD:
REFERENCES: OP-155, Diesel Generator Emergency Power System
VALIDATION TIME: 15 MINUTES TIME CRITICAL: No
CANDIDATE:
START TIME: FINISH TIME:
PERFORMANCE TIME: MINUTES
PERFORMANCE RATING: SAT UNSAT
COMMENTS:
EXAMINER:
Signature Date
Page 2 of 7
Rev Date 07/21/02
JPM COM-B. 1.b
HARRIS
TOOLS / EQUIPMENT / PROCEDURES NEEDED:
- Initialize the simulator to a 100% power condition.
- StartEDGB.
SEE INSTRUCTIONS AFTER STEPS 13 AND 18 TO ENTER ADDITIONAL
MALFUNCTIONS.
"* STEP 13 - Prevent EDG B breaker 126 from automatically opening on subsequent
LOSP (allowing manual operation to open) <ICOR ZCR31748 FAILASIS>.
"* STEP 17 - <IMF EPS01> To cause a loss of offsite power to the plant.
- Place simulator in FREEZE.
- When candidate is ready, place simulator in RUN.
OP- 155, "Diesel Generator Emergency Power System"
READ TO OPERATOR
INSTRUCTIONS TO CANDIDATE:
I will explain the initial conditions and state the task to be performed. All control
room steps shall be performed for this JPM, including any required communications. I
will provide initiating cues and reports on other actions when directed or asked by
you. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task, return the handout sheet I provide you.
INITIAL CONDITIONS:
The plant is operating at 100% power.
Emergency Diesel Generator lB-SB has been started and is ready to be paralleled to
the grid.
INITIATING CUE(S):
You have been directed to parallel EDG lB-SB to the grid in accordance with OP-155,
"Diesel Generator Emergency Power System," Section 5.3. All initial conditions of
Section 5.3.1 have been completed.
Exercising the Voltage and Governor Controls is required.
Page 3 of 7
Rev Date 07/21/02
JPM COM-B. 1b
HARRIS
START TIME:
- DENOTES CRITICAL STEP
NOTES SATA/
JPM PROC ELEMENT STANDARD
STEP UNSAT
STEP
NOTE: PROVIDE CANDIDATE WITH COPY OF OP-155, SECTION 5.3
1 5.3.2.1 Notify Load Dispatcher EDG Request Unit SCO
lB-SB will be loaded notify Load Dispatcher
CUE DISPATCHER HAS BEEN NOTIFIED.
2 5.3.2.2 Review Precautions Reviews precautions
4.0.0.021, 4.0.0.022,
4.0.0.024 and 4.0.0.025
before paralleling
CUE (IF ASKED WHEN REVIEWING PRECAUTION 4.0.0.021) UPP-1A IS ALIGNED
TO ITS NORMAL SOURCE.
- 3 5.3.2.3 Place DIESEL GEN B-SB Turns EDG B sync Critical to permit
SYNCHRONIZER control scope on closure of EDG
switch to SYNC breaker 126
4 5.3.2.4.a Position DIESEL GEN B-SB Adjust EDG B Auto
AUTO VOLTAGE ADJUST Voltage Adjust until
control switch to RAISE or EDG voltage indicates
LOWER as necessary to 6.6 KV
perform the following:
- Lower voltage to 6.6 KV
5 5.3.2.4.b * Raise voltage to 7.2 KV Adjust EDG B Auto
Voltage Adjust until
EDG voltage indicates
7.2 KV
6 5.3.2.4.c Position DIESEL GEN B-SB Adjust EDG B Auto
AUTO VOLTAGE ADJUST Voltage Adjust until
control switch to RAISE or EDG voltage matches
LOWER as necessary to 6.9KV Bus 1B-SB
perform the following: voltage (0 A VOLTS)
Adjust EDG voltage to
match the associated
Emergency 6.9KV Bus
voltage as indicated by
zero differential voltage
on EI-6953B SB , B
SYNC A VOLTS
Page 4 of 7
Rev Date 07/21/02
JPM COM-B. L.b
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
Position DIESEL GEN B-SB Adjust EDG B Governor
7 15.3.2.5.a
GOVERNOR CONTROL Control until EDG B
switch to RAISE or LOWER frequency is indicating
as necessary to perform the 59 HZ
following:
"* Lower frequency to 59
HZ
"* Raise frequency to 61 HZ Adjust EDG B Governor
8 5.3.2.5.b
Control until EDG B
frequency is indicating
61 HZ
Position DIESEL GEN B-SB Adjust EDG B Governor
9 5.3.2.5.c
GOVERNOR CONTROL Control until EDG B
switch to RAISE or LOWER sync scope is indicating
as necessary to perform the slow CW movement
following:
- Adjust EDG speed until
the synchroscope is
rotating slowly in the
FAST direction
(CLOCKWISE)
Check synchronizing lights Verify sync lights
10 5.3.2.6
are cycling (OUT when the cycling properly in
synchroscope is at the 12 agreement with sync
o'clock position) in agreement scope
with the synchroscope
rotation
11 5.3.2.7 As necessary, position Readjust EDG B Auto
DIESEL GEN B-SB AUTO Voltage Adjust until
VOLTAGE ADJUST EDG voltage matches
control switch to adjust EDG 6.9KV Bus 1B-SB
voltage to zero differential voltage (0 A VOLTS)
voltage on EI-6953B SB , B
SYNC A VOLTS Critical to close
"*12 5.3.2.8 When the synchroscope Place EDG B breaker
126 to close position EDG breaker 126
reaches the 12 o'clock to permit EDG to
position and the when sync scope
indicates 12 o'clock pickup load
synchronizing lights are
TOTALLY DARK, place position and sync lights
the DIESEL GEN B-SB are totally dark
BREAKER 126 SB control
switch to CLOSE
Check DIESEL GEN B-SB Verify EDG B breaker is
13 5.3.2.9
I ~ I BREAKER 126 SB is closed I closedI
Page 5 of 7
Rev Date 07/21/02
JPM COM-B. L.b
HARRIS
JPM PROC ELEMENT STANDARD NOTES SAT /
STEP STEP UNSAT
SIMULATOR OPERATOR INSTRUCTIONS: INSERT OVERRIDE <ICOR ZCR31748 FAILASIS>
TO oPREVENT EDG B BREAKER 126 AFROM AUTOMATICALLY
APF*N'
OPENING ON SUBSEQUENT
TTATt'J TA*
I t AT * l'lXflT*TC' ATnoun
T/IATTAI
11uar i',VflA A4
XXTT XT~rfA IADtA TONa OPN
"*14 5.3.2.10 Position DIESEL GEN B- Adjust EDG B Critical to pickup
SB GOVERNOR Governor Control until load to prevent
CONTROL switch to EDG B load indicates reverse power
increase generator load to 2.2 to 2.4 MW trip of EDG
2.2 to 2.4 MW on El- breaker 126
6957B1 SB, B POWER
15 5.3.2.11 Position DIESEL GEN 1B- Adjust EDG B Auto
SB AUTO VOLTAGE Voltage Adjust until
ADJUST control switch to EDG reactive load
obtain 1.0 MVARs on El- indicates 1.0 MVARs
6958B SB, B REACTIVE
16 5.3.2.12 Place DIESEL GEN B-SB Place EDG B sync scope
SYNCHRONIZER control off
switch to OFF
17 5.3.2.13 Check DIESEL GEN B-SB Verify amber light lit on
BREAKER 126 SB amber EDG B breaker 126
light is lit
A
SIMULATOR OPERATOR INSTRUCTIONS: INSERT MALFUNCTION <IMF EPSO0> TO CAUSE
LOSS OF OFFSITE POWER TO THE PLANT.
18 NA Determine LOSP has * Determine EDG B
occurred and check for proper breaker 126 has
response of EDG B output failed to open
breaker 126 * Notifies Unit SCO
"*19 4.0.0.024 Open EDG B breaker 126 Place EDG B breaker Critical to
126 to open separate EDG
from grid to
prevent EDG
damage due to
overload
TASK COMPLETE
STOP TIME:
Page 6 of 7
Rev Date 07/21/02
JPM COM-B. 1.b
HARRIS
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The plant is operating at 100% power.
Emergency Diesel Generator lB-SB has been started and is ready to be paralleled to
the grid.
INITIATING CUE(S):
You have been directed to parallel EDG lB-SB to the grid in accordance with OP-155,
"Diesel Generator Emergency Power System," Section 5.3. All initial conditions of
Section 5.3.1 have been completed.
Exercising the Voltage and Governor Controls is required.
Page 7 of 7
Rev Date 07/21/02