ML20246G957
| ML20246G957 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/07/1989 |
| From: | Burdick T, Damon D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20246G936 | List: |
| References | |
| 50-266-OL-89-04, 50-266-OL-89-4, 50-301-OL-89-04, 50-301-OL-89-4, NUDOCS 8907140289 | |
| Download: ML20246G957 (117) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION REGION III Report Ho.. 50-266/301-OL-89-04 Docket Nos. 50-266; 50-301 Licenses No. DPR-24; DPR-27 Licensee: Wisconsin Electric Power Company
~ 31 West Michigan Street - P379
?
- o Milwaukee, WI 53201 Facility Name: Point Beach Nuclear Plant Examination Administered At: Two Creeks, Wisconsin Examination Conducted: Requalification R0 and SR0
' Chief Examiner:
D. Da
~
~7,!"7!'d Date M
V 7!'7 9
Approved By:
T. M. Burdick, Operator Licensing Section 2 Dats t
Examination Summary Examination administered on June 26-28, 1989 (Report No. 50-266/301-0L-89-04)
Written requalification examination was administered to one SRO.
Results: The operator passed the exam.
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6g REPORT DETAILS
(
Examiner i
D. Damon i
I I
i 2
h Facility: Point Beach Nuclear Plant t
Examiner:
D. Damon Date of Evaluation: May 17, 1989 Areas Evaluated: X Written Oral Simulator Examination Results:
R0 SR0 Total Evaluation Pass / Fail Pass / Fail Pass / Fail (5, M, or U)
Written Examination 0/0 1/0 1/0 S
Operating Examination Oral Simulator Evaluation of facility written examination grading S
I Overall Program Evaluation Satisfactory Marginal Unsatisfactory (List major deficiency areas with brief descriptive comments)
This examination does not constitute a programmatic evaluation of the Point Beach requal program.
Submitted:
A prov Q
ys+v v DNon ur Examiner Section Chief 3
g ; *.
..)
c Print Date:
06/26/89 T89-023:
NRC MAKEUP EXAM II (KEY)
Instructions:
I 1.. Answer all questions enclosed on pages and show all calculations.
2.
Do not discuss exam, questions, or answers with anyone.
3.
Passing grades are 80% overall; 70% individual section grade.
4.
Choose BEST answer.
Multiple choice has only one correct answer.
5.
Do not write on back of pages.
Attach additional sheets if needed.
Section 1
2 3
Points-Received Section Point Value 22.6 10.8 9.4 42.8 Percentage Grade Overall SEE APPROVAL COPY COVERSHEET FOR SIGNATURES (ATTACHED) lif(/-gd i Lis L(JIy i TR-8.6.1 (10-87)
Exan Ouestion Number Ouestion Number 1-01 051-01-037A 1-02 039-01-003A 1-03 051-03-006A 1-04 053-01-026A 1-05 051-05-013A 1-06 052-01-004A 1-07 057-02-013A 1-08 043-03-009A 1-09 051-01-042A 1-10 055-02-060A 1-11 053-02-030A 1-12 053-03-013A 1-13 053-03-015A 1-14 055-01-002A 1-15 055-01-007A 1-16 055-02-082A 1-17 052-02-008A 1-18 057-02-023A 1-19 031-03-026A 1-20 031-03-053A 1-21 051-01-044A 1-22 043-02-011A 1-23 031-03-003A 1-24 039-01-005A 1-25 053-01-033A 1-26 052-03-005A 1-27 053-01-021A 2-01 055-02-106A 2-02 055-02-043A 2-03 053-04-012A 2-04 053-02-028A 2-05 053-02-025A 2-06 051-02-019A 2-07 051-01-047A 2-08 051-01-032A 2-09 031-03-107A i
i 2-10 031-03-112A 2-11 031-03-114A 2-12 031-03-109A 2-13 031-03-111A 2-14 052-02-001A 2-15 055-02-107A 3-01 054-01-010A 3-02 052-05-022A 3-03 033L-03-009A 3-04 054-01-001A 3-05 053-04-005A 3-06 055-01-020A 3-07 052-03-004A 3-08 051-01-020A 3-09 032-03-001A 3-10 031-03-130A 3-11 031-03-129A 3-12 031-03-102A
y t:
Section 1 I
--A
Question Number:
051-01-037A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
REACTOR COOLANT PUMP Task Number:
CO230 COT, C0303 COT Terminal Learnina Obiective:
CO230 COT During all modes of operation apply TS and procedural requirements associated with the RCS in accordance with appropriate operating procedures.
C0303 COT During all modes of operation predict the effect of loss of CCW on RCP operation in accordance with AOP-9B, " Loss of Component Cooling."
Question:
Instructor Use Only Unit 1 is at 60% power when the flow indicator FI 613, RCP B Total Component Cooling Water Flow, fails high.
How will CCW to the "B" RCP be affected by this failure?
Points Earned
' g'
'.. f ' :
4 *
?!
-Question No.:
051-01-037A Page 2 Answer::
Instructor Use Only-Hi= flow will close thermal barrier heat (exchanger outlet valve.(AOV-761B). (.6 pts) 197 Additional Information:
Technical
References:
AOP-9B AOP-1B-TRHB 10.2 TRHB 10.9
~ Items to be' Included with Ouestion:
None Time Validation:
2.00 Reaual Cycle:
N/A K/A
Reference:
System:
003 Mode:
000 Number:
K1.12 Ratings:
RO:
3.0 SRO:
3.3 E___________________
Question Number:
039-01-003A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89
]
Question Format:
W Question Type:
S Subject Area:
REACTOR COOLANT SYSTEM Task Numbar:
CO221 COT l
i Terminal Learnina Obiective:
CO221 COT During all modes of operation, and given the steam tables relate pressure und temperature for subcooled and saturated liquids in accordance with the steam tables.
Question:
Instructor Use Only calculate subcooling while performing an RCS cooldown on natural circulation using the following indications.
Th wide range
= 550*F Tc wide range
= 532'F Core exit TC's
= 552*F"'
RCS pressure
= 14d5 psig Points Earned
L Question No.:
039-01-003A Page 2 Answer:
Instructor Use Only Subcooling (based on core iC's) is Tsat (1435 psig)
- 552*F
= 591.70 - 552'F
= 39.7'F i 2* F (.6 pts.)
l 066 Additional Information:
T_echnical
References:
Steam Tables EOP 0.2 Items to be Included with Ouestion:
None Time validation:
3.00 Recual Cycle:
N/A K/A
Reference:
System:
002 Mode:
000 Number:
K5.09 Ratings:
RO:
3.7 SRO:
4.2
Question Number:
051-03-006A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
CONTAINMENT SPRAY SYSTEM Task Number:
P1904 COT Terminal Learnina Obiective:
P1904 COT With the RWST no longer supporting containment spray and
)
given a copy of EOP-1.3, transfer to containment sump I
recirculation in accordance with EOP-1.3.
Question:
Instructor Use Only Following a large break LOCA, transition was made from EOP-1 (" Loss of Reactor or Secondary Coolant")
to EOP-1.3 (" Transfer to Containment Sump Recirculation"). When checking if low head recirculation can be used per step 12, the operator notes these indications:
Containment pressure 8 psig 3
Containment radiation 10 R/hr RCS pressure 350 psig Sump "B"
level 15 inches What action is required?
Points Earned
Question No.:
051-03-006A Page 2 Answer:
Instructor Use Only Proceed to step 16 of EOP-1.3, " Transfer to Containment Sump Recirculation", to _e_gablis_h hiah head recirculation.
(.6 pts.)
778 Additional Information:
Technical
References:
EOP-1.3 Items to be Included with Ouestion:
None Time Validation:
4.00 Reaual Cycle:
N/A K/A
Reference:
System:
000 Mode:
011 Number:
EK3.15 Ratings:
RO:
4.3 SRO:
4.4
)
I
_J
I Question Number:
053-01-026A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
C j
Subject Area:
ROD CONTROL SYSTEM Task Number:
C0126 COT Terminal Learnina Obiective:
C0126 COT During any plant operations involving rod movement, diagnose a stuck rod or malfunctioning position indication in accordance with REI #7.
Question:
Instructor Use Only Power is at 55% and the turbine is ramping up at 1%
per minute.
Bank D is stepping out in auto with the following position indications:
Bank D Position Indication K7 84 inches G3 60 inches C7 84 inches G11 84 inches The operator is instructed to determine if the problem is a stuck rod or a malfunctioning position indicator. His next action is to stabilize power and then (Chose one answer.)
a.
drive Bank D rods in to determine if temperature decreases. If temperature decreases the problem is a malfunctioning rod position indicator, b.
call Reactor Engineering to evaluate the actual rod position using the incore detectors, since control board indications are not accurate in. determining rod position.
c.
reduce power to less than 50%. Operation greater than 50% is not allowed by Technical Specifications if either a rod is inoperable or a position indicator is inoperable.
d.
review the process computer printout of rod positions; evaluate whether or not a quadrant power tilt exists; and check the incore thermocouple for deviations in core symmetry.
j Points Earned
]
l JA Question No.:
053-01-026A Page 2
)
l Answer:
Instructor Use only d.
(0.8 pts.)
Additional Information:
Technical
References:
LP-1592 REI 7.0 AOP-6B T.S. 15.3.10 Items to be Included with Ouestion:
None Time validation:
3.60 Recual Cycle:
N/A K/A
Reference:
System:
001 Mode:
000 Number:
A2.03 Ratings:
RO:
3.5 SRO:
4.2 i
Question Number:
051-05-013A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
CONTAINMENT VENTILATION Task Number:
C1802 COT Terminal Learnina Obiective:
l C1802 COT During emergency operations and given a copy of EOP-0 l
assess the response of the containment ventilation system l
to a safeguards actuation signal in accordance with EOP-0,
" Reactor Trip or Safety Injection".
Question:
Instructor Use Only Why is it necessary for MOV 2907 and/or MOV 2908 (fan cooler service water outlet valves) to open during an SI initiation?
l Points Earned
j Question No.:
051-05-013A Page 2 l
Answer:
Instructor Use only To raise service water flowrate to provide adequate cooling to compensate for the increased heat load on the containment cooling system during an accident.
(.6 pts.)
Alternate answer: To raise service water f, low rate to provide adequate cooling to keep containment pressure within design limits or to increase service water flow through containment accident fan coolers during design basis accidents (Help limit containment pressure) 226 Additional Information:
Technical
References:
EOP-0 Items to be Included with Ouestion:
None Time Validation:
3.10 Recual Cycle:
N/A K/A
Reference:
System:
013 Mode:
000 Number:
K1.03 Rat (ngs:
RO:
3.8 SRO:
4.1
Question Number:
052-01-004A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
C Subject Area:
CIRCULATING WATER SYSTEM Task Number:
C5203 COT Terminal Learnino Obiective:
C5203 COT During the process of simulation or evaluation identify causes of interlocks, permissive and automatic functions associated with the circulating water system to maintain plant efficiency and condenser vacuum.
Question:
Instructor Use Only Lake injection temperature is increasing. Alarms indicate over-temperature in the Unit 1 main generator hydrcgen cooler.
The best course of action is to (Choose one answer.)
a.
cut in or direct more CW through the condensate cooler.
b.
increase hydrogen flow through the hydrogen coolers.
c.
decrease hotwell temperature by increasing CW flow to the condenser.
d.
decrease Unit I load to stabilize hydrogen cooling of main generator.
l Points Earned 1
\\
Question No.:: 052-01-004A Page 2 Answer:
Instructor Use Only a.
(0.8 pts.)
l 059 Additional Information:
Technical
References:
TRHB 11.7 Items to be Included with Ouestion:
None Time Validation:
1.40 Resual Cycle:
N/A K/A
Reference:
System:
075 Mode:
000 Number:
A2.03 i
Question Number:
057-02-013A Point Value:
1.0 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
M Subject Area:
TECHNICAL SPECIFICATIONS
)
Task Number:
C6S01 COT Terminal Learnina Obiective:
C6501 COT During all modes of operation assess TS and procedural requirements to equipment necessary for safe operation of the plant in accordance with all procedural and Technical Specification requirements without error.
Question:
Instructor Use Only Below are five statements concerning TS actions required for nuclear instrument malfunctions. Which one is correct?
a.
If a source range channel fails while a startup is in progress and reactor power is below P6, insert all control banks to zero steps.
b.
If an intermediate range channel fails while a startup is in progress and reactor power is above P6, but below P10, the power increase i
may continue using the operable intermediate range channel.
c.
Failure of one power range channel during shutdown precludes reactor startup until the failed channel is returned to operable
- status, d.
Failure of both source range channels, while j
shutdown, requires shutdown margin l
requirements to be verified within one hour.
l l
e.
Failure of both' intermediate range channels l
while at full power, requires the unit to be J
in hot shutdown within three hours.
]
l l
Points Earned l
l
Question No.:
057-02-013A Page 2
' Answer:
Instructor Use Only b (1.0 pts)
Additional Information:
Technical
References:
Tech Specs table 15.3.5-2 LP 618 Limiting Conditions for Operation Items to be Included with ouestion:
None Time Validation:
5.50 Reaual Cycle:
N/A K/A
Reference:
System:
015 Mode:
000 Number:
K3.01 Ratings:
RO:
3.9 SRO:
4.3 l
l 1
l I
i
\\
I L_ ____ _ - -
)
Question Number:
043-03-009A Point Value:
0.9 Revision Number:
0 Approval Date:
06/20/89
' Question Format:
W Question Type:
E Subject Area:
CHEMICAL & VOLUME CONTROL SYSTEM Task Number:
C0410 COT Terminal Learninc7.Obiective:
C0410 COT During normal operating conditions ASSESS a loss of CVCS on pressurizer level in terms of resultant trends and long l
term effects on pressurizer level.
Question:
Instructor Use Only Unit 1 is at 100% power with all control systems in automatic.
A controller malfunction causes the charging line control valve (HCV-142) to go closed.
The valve will not respond to any control operator actions.
a.
Explain how this malfunction will affect pressurizer level? (.3 pts.)
b.
Assuming the bypass valve around 1HCV-142 (1CV-323B) cannot be opened, what operator actions should be taken regarding the CVCS system? (Three required.) (.6 pts.)
\\
t Points Earned I
1 1
1
- - - a
i Question No.:
043-03-009A Page 2 Answer:-
Instructor Use Only a.
Pressurizer level will decrease (letdown operating with no' normal charging).
(.3 pts.)
b.
1.
Normal letdown should be isolated.
i'
(.2 pts.)
2.
Excess letdown should be established.
(.2 pts.)
3.
Charging should be reduced.
(.2 pts.)
4.
Establish aux, charging (.2 pts.)
l (any three of four) 315 Additional Information:
Technical
References:
TRHD 10.6 Figure 10.6.1/10.6.2 OP-5A Items to be Included with Ouestion:
Deleted " Explain the reasons for each operator action" based on a comment from K. Draska Time Validation:
3.00 Recual Cycle:
N/A K/A
Reference:
System:
004 Mode:
000 Number:
K3.02 Ratings:
RO:
3.7 SRO:
4.1
i I
Question Number:
051-01-042A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
PRESSURIZER PRESSURE CONTROL SYSTEM Task Number:
C0918 COT Terminal Learnina Obiective:
C0918 COT During all modes of operation, assess the effect of a loss of pressure control on subcooling margin prior to reaching saturation conditions in the RCS.
Question:
Instructor Use Only Urcit 2 is in hot shutdown at no load temperature and normal operating pressure with all safeguards equipment operable. A PZR safety valve fails partially open. RCS pressure starts decreasing at 100 psig per minute.
Explain whether or not RCS subcooling will be lost if no operator action is taken.
Points Earned
)
1 L *.
, Question No.:
051-01-042A Page 2 Answer:
Instructor Use only j
-.., ~
No RCS subcooling will not be lost (.2 pts.) RCS pressure will stabilize at approximately 1550 psig i
(SI pump shut off head). RCS temperature-will be I
maintained at approximately 547'F.-
Tsat for 1550 psig is approximately 600*F. (.6 pts) j 253 Additional Information:
1.
i Technical
References:
Steam Tables l
TRHB 10.3 TRhb 10.8 Items to be Included with Ouestion:
None Time Validation:
'2.70 Resual Cycle:
N/A K/A
Reference:
N/A
_ _ = _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ -.
l Question Number:
055-02-060A Point Value:
0.8 Revision Number:
1 Approval Date:.06/20/89 j
Question Format:
W Question Type:
S j
Subject Area:
STEAM GENERATOR SYSTEM
{
I Task Number:
Cl314 COT, C2402 COT Terminal Learnina Obiective:
1 C1314 COT During all modes of operation, apply TS and procedure
-j requirements associated with operation of the NIS in i
accordance with Technical Specification limits 15.3.5, i
" Instrumentation System".
j C2402 COT During all modes of operation, apply TS and procedural requirements for operation of the steam generators in accordance with Technical Specifications 15.3.4, " Steam and Power Conversion System."
Question:
Instructor Use Only With both units at 100%, the electric auxiliary feed pump (P-38B) was declared out-of-service on May 3 at 0500. At 0330 on May 5, Unit 2 tripped.
At 0630 on May 5, the post-trip review was completed. All equipment operated properly during the trip except for P-38B.
Explain whether or not Unit 2 can be started up.
Points Earned
7_
L Question No.:
055-02-060A Page 2 Answer:
Instructor Use Only No Unit 2 cannot be started up (.2 pts.) because all four auxiliary feedvater pumps must be operable. (Alternate answer: LCO only applies if the unit is already at power.) (0.6 pts) 147 Additional Information:
Technical
References:
T.S. 15.3.4.A.2.a Items to be Included with Ouestion:
None Time Validation:
2.00 Recual Cvele:
N/A K/A Refereneg:
System:
061 Mode:
000 Number:
GOS Ratings:
RO:
3.3 SRO:
4.0 4
. Question Number:
053-02-030A Point Value:
0.8
' Revision Number:
1 Approval Date:
06/20/09 Question Format:
W Question Type:. S Subject Area:
ROD CONTROL SYSTEM
. Task Number:
C0112 COT, C1102C0T Terminal Imarnina Obiective:
C0112 COT During all operations with the reactor trip breakers and/or bypass breakers closed, assess the response of the breakers to a reactor protection signal.
Assessment shall include all possible mechanisms that cause the trip breakers and bypass breakers to open.
C1102 COT During all plant operating conditions involving closed reactor trip breakers, recognize conditions requiring reactor protection actuation.
Recognition of all plant parameters that will cause a reactor trip as well as their corresponding setpoints are required, without error.
Question:
Instructor Use Only Unit 2 is operating at 100% power with Reactor Protection Logic Testing in progress on Train A. A reactor trip signal is generated due to OT Delta T.
Explain whether or not an automatic trip will occur if the reactor trip breaker B fails to operate.
Points Earned 1
L L
I Question No.:
053-02-030A Page 2 I
Answer:
Instructor Use only I
Yes a reactor trip will occur (.2 pts.) because the bypass breaker A is racked in during the Logic Testing of Train A (.3 pts.), and it receives a trip signal (UV) from Train B.
(.3 pts.)
067 Additional Information:
Technical
References:
TRHB 13.3 Figure 13.3.9 Logic Sht. 2 Items to be Included with Ouesti2D:
None Time Validation:
1.90 Recual Cvele:
N/A K/A
Reference:
System:
000 Mode:
001 Number:
EA2.01 Ratings:
RO:
4.2 SRO:
4.2 1
i 1
l l
)
i f
P Question Number:
053-03-013A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/89 Question, Format:
W Question Type:
C Subje-t Area:
NUCLEAR INSTRUMENTATION SYSTEM Task Number:
C1306 COT Terminal Learnina Obiective:
C1306 COT During a reactor startup or shutdown, recognize prerequisites for blocking and unblocking automatic NIS functions in accordance with OP-1B or OP-3B.
Question:
Instructor Use Only In the blank to the left of each item, place the number corresponding to the sequence in which it would be performed in relation to the other items.
Assume the reactor is being started up from a source range count of 10 cps.
1.
Verify " Power Above P6" light energized.
2.
Manually block power range low setpoint high flux trip.
3.
Manually block source range level trip.
4.
Place high flux at shutdown switch in
" block."
5.
Verify " Low Power Range Trip Blocked" light energized.
6.
Verify " Power Above P10" light energized.
7.
Verify " Source Range Trip Blocked" light energized.
8.
Verify " Single-Loop-Flow-Trip-Blocked" light deenergized.
Points Earned
Question No.:
053-03-013A Page 2 Answer:
Instructor Use Only ggg 7[
g [ (.1 pts.each)
Note: Give credit only for numbers that appear in their correct order. No credit given for numbers out of sequence.
Additional Information:
Technical
References:
OP-1 " Reactor Start-up" steps 3.7 and 4.8.1 OP-1C, " Low Power Operation to Normal Power Operation" step 4.60 LP 251 NIS Controls and Indications Items to be Included with Ouestion:
None Time Validation:
5.80 Recual Cvele:
N/A K/A
Reference:
System:
015 Mode:
000 Number:
K4.07 Ratings:
RO:
3.7 SRO:
3.8 4
Question Number:.053-03-015A Point Value:
1.0 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
M Subject Area:
NUCLEAR INSTRUMENTATION SYSTEM Task Number:
C1316 COT Terminal Learninc Obiective:
C1316 COT During all modes of operation identify at least 80% of the causes of interlocks, permissives and automatic functions associated with the NIS.
Question:
Instructor Use Only Assume a power escalation is in progress from 5%
power. A reactor trip will occur from the power range low setpoint overpower trip if the operator fails to push (Chose one answer.)
a.
the intermediate range permissive defeat buttons.
b.
the low (power) range logic manual trip block buttons with power above P10.
c.
the intermediate range logic manual trip block buttons with power above P6.
d.
the low (power) range logic manual trip block buttons with power less than P10.
e.
the intermediate range permissive defeat buttons with power above P6.
)
l Points Earned l
.o, Question No.:
'053-03-015A Page 2' Answer:
Instructor Use only b (1.0 pts.)
Additional Information:
Technical
References:
Logic drawing 883D195 sheets 11 and 12 LP 251 NIS Controls and Indicaions Items to be Included with Ouestion:
None Time Validation:
2.30 Reaual Cvele:
N/A K/A
Reference:
System:
015 Moda:
000 Number:
K4.05-Ratings:
RO:
4.3 SRO:
4.5
'C_____m_______
._m.______m_______.
Question Number:
055-01-002A Point Value:
0.9 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
CHEMICAL & VOLUME CONTROL SYSTEM Task Number:
PC416 COT Terminal Learnina Obiective:
PO416 COT During a normal plant shutdown and given a copy of OP-3C, take the PZR solid in accordance with OP-3C, " Hot Shutdown to cold Shutdown".
i Question:
Instructor Use Only NOTE:
In responding to this item, treat each case separately and carry out to equilibrium conditions.
RCS pressure is initially stable at 395 psig. With no operator action, what would happen to RCS pressure if the single running charging pump is increased from =30% to 35% signal and:
a.
the pressurizer level is 80% with PCV-135, low pressure letdown controller, in manual?
(.3 pts) b.
the pressurizer is solid with PCV-135, low pressure letdown controller, in manual?
(.3 pts) the pressurizer is solid; letdown flow is via c.
RHR; and PCV-135, low pressure letdown controller, is in automatic? (.3 pts)
Points Earned i
1
Question No.:
055-01-002A Page 2 Answer:
Instructor Use Only a.
Small increase.
(.3 pts.)
b.
Increase.
(.3 pts.)
c.
Small increase until CV-135 responds. (.3 pts.)
n.p 768 Additional Information:
Technical
References:
TRHB 10.3 and 10.6 OP-3C Items to be Included with Ouestion:
Norte Time Validation:
5.80 Reaual Cycle:
N/A K/A
Reference:
System:
004 Mode:
010 Number:
A1.02 Ratings:
RO:
3.8 SRO:
3.8 i
l L____
Question Number:
055-01-007A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question _ Type:
C Subject Area:
REACTOR COOLANT SYSTEM Task Number:
P7104 COT Terminal Learnina Obiective:
P7104 COT During a.tormal plant shutdown and given a copy of OP-3C, cooldown from hot shutdown to cold shutdown in accordance with OP-3C, "hct Shutdown to Cold Shutdown".
Question:
Instructor Use Only The operator is conducting a nocrial plant cooldown.
During RCS depressurization from 1500 to less than 1000 psig, which one of the following statements is true?
a.
Two 40 gpm letdown orifices could be used with a mixed bed demineralized in service, b.
PCV-135, Letdown Pressure Control Valve, will be adjusted to higher pressures to cause more letdown flow.
c.
Normal letdown through all three orifices is used to provide extra letdown flow in addition to letdown flow from RHR.
d.
Lowering RCS pressure will increase letdown flow.
Points Earned
l Question No.:
055-01-007A Page 2 Answer:
Instructor Use only l
a.
(.8 pts.)
755 Additional Information:
Technical
References:
OP-5A OP-3C Items to be Included with Ouestion:
None Time Validation:
3.40 Recual Cycle:
N/A K/A
Reference:
System:
002 Mode:
000 Number:
Kl.06 Ratings:
RO:
3.7 SRO:
4.0
-4 9
1
Question Number:
055-02-082A Point Value:
1.0 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
E Subject Area:
REACTOR COOLANT SYSTEM Task Number:
CO203 COT Terminal Learnina Obiective:
CO203 COT During all modes of operation and given a copy of AOP-2B, analyze the effect of a loss of feedwater (main and/or auxiliary) on the RCS in accordance with AOP-2B, " Loss of Feedwater or Feedwater System Failure".
Question:
Instructor Use Only Unit 2 is at 80% power and rod control is in manual. The "A" SGFP trips.
The operator runs the main turbine back to 50% load at 200% per minute.
With D2 other operator actions taken, a reactor trip occurs. Explain why the reactor tripped?
(Include in your answer the trip signal that was exceeded and the plant conditions that caused this signal to be exceeded.)
1 Points Earned
--_-m_-__ _. _. _ _. _.,. _,., _ _ _
Question No.:'~ 055-02-082A Page 2 Answer:
Instructor Use Only The steam dumos will ooen and remain open holding power relatively constant. (0.5 pts.) With only one SGFP running a steam flow / feed flow nismatch (or Low Feedwater Flow alarm) occurs and when S/G level reaches the low level setooint a reactor trip occurs.(0.5 pts.)
084 j
Additional Information:
l Technical
References:
.AOP-2B Items to be Included with Ouestion:
None Time Validation:
4.10 Recual Cvele:
N/A K/A
Reference:
System: -002 Mode:
000 Number:
K1.11 Ratings:
RO:
4.1 SRO:
4.2 l
l l
J
Question Number:
052-02-008A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
EXTRACTION STEAM SYSTEM Task Number:
P2902 COT Terminal Learnina Obiective:
P2902 COT During conditions of normal power operation with the extraction steam system operating in automatic mode, respond to extraction steam bleeder trip valves not closing when required, without error.
Question:
Instructor Use Only Explain how the Extraction Steam System will a.
protect the turbine from water backing up in HP Heater SA. (.4 pts.)
b.
Explain how the Extraction Steam System will protect the turbine from an overspeed condition. (.4 pts.)
Points Earned
?.
, Question No.: _052-02-008A Page 2 fAnswer:
Instructor Use Only a.
The high level will cause the BTV's
)
i (BTV-2309 and 2310).to close.
(.4 pts.)
b.
The BTVs close on a turbine trip (.4 pts.)
1 790 Additional Information:
j Technical
References:
TRHB 11.5 STPT DOCUMENT 14.3 1
Items to be Included with Ouestion:
None Time Validation:
3.00 I
Recual Cycle:
N/A K/A
Reference:
System:
039 Mode:
000 Number:
K4.05 Ratings:
RO:
3.7 SRO:
3.7 l
I l
i
-Question Number:
057-02-023A Point Value:
1.0
' Revision Number:
1 Approval Date:
06/20/89 Question Format:
W-Question Type:
S Subject Area:
TECHNICAL SPECIFICATIONS Task Number:
C6501 COT Terminal Learnina Obiective:
C6501 COT During all modes of operation assess TS and procedural requirements to equipment necessary for safe operation of the plant in accordance with all procedural and Technical Specification requirements without error.
. Question:
Instructor Use Only A plant heatup in progress and the following data on the trend recorder is noted:
Time Temo.
0630 350*F 0640 372*F G650 388'F 0700 410*F Explain whether or not any actions should be taken-by the operator.
Points Earned
Question No.:
057-02-023A Page 2 Answer:
Instructor Use Only The operator should take action to reduce the heatup rate (.4 pts) because it is in excess of the maximum heatup race (100
- F/Hr). (. 6 pts)
Additional Information:-
Technical'
References:
T.S. 15.3.1.B.1 LP 618 Limiting Conditions for Operation Items to be Included with Ouestion:
None Time Validation:
2.50 Recual Cycle:
N/A K/A
Reference:
- System:
002 Mode:
000 Number:
G06 Ratings:
RO:
0.0 SRO:
3.8 1
l
Question Number:
031-03-026A Point Value:
0.8 Revision Humber:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S l
Subject Area:
PRESSURIZER LEVEL CONTROL SYSTEM l
Task Number:
C1013 COT, C4306 COT Terminal Learnina Obiective:
C1013 COT During an accident or emergency condition, recognize and diagnose the formation of a steam bubble in the reactor vessel head using available indications such as the reactor vessel level indicating system pressure level and RCS subcooling meter.
C4306 COT During an emergency or accident condition assess the effect of electrical system malfunctioning on as a result of a loss of power to various electrical components.
Question:
Instructor Use Only During natural circulation cooldown and depressurization, pressurizer level unexpectedly increased from 25% to 85% with RVLIS narrow range at 30 feet and subcooling at 58* F. Charging pumps are in manual with charging and letdown flowrates equal.
a.
What caused pressurizer level to increase?
j
(.4 pts.)
)
b.
What action should be taken next? (.4 pts.)
{
i Points Earned j
Question No.:
031-03-026A Page 2 Answer:
Instructor Use only a.
Formation of a steam void (bubble) in the vessel (head). (0.4 pts.)
b.
Repressurize the RCS. (0.4 pts.)
(Alternate answer:
Continue cooldown)
(Also acceptable: Actions that would cause the cooldown to increase or repressurize.)
298 Additional Information:
Technical
References:
EOP-0.2 EOP-0.3 Items to be Included with Ouestion:
None Time Validation:
5.70 Recual Cycle:
N/A K/A
Reference:
System:
011 Mode:
000 Number:
K5.10 Ratings:
RO:
3.7 SRO:
4.0
-___m_m m.._____
Question Number:
031-03-053A Toint Value:
10 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
SAFETY INJECTION SYS'."EM i
Task Number:
C0602 COT, C7009 COT 1
Terminal Learnino Obiective:
C0602 COT During an emergency or accident condition the operator must be able to recognize the need for SI actuation in accordance with the criteria established per the Emergency Operating Procedures.
I C7009 COT From any plant condition following a reactor trip or safety injection actuation recognize the critical safety functions by verifying that all safety related parameters are i
satisfied in accordance with the critical safety function f
status trees.
i Question:
Instructor Use Only After a reactor trip with no operator action taken, the following data is observed:
A E
Onits S/G preesure 1000 980 psig S/G level 20 22 Tavg 547 547 Deg F PZR Press.
1720 psig PZR Level 13 RCP's ON ON SI Pumps OFF OFF RHR Pumps OFF OFF Source Range 2.0E3 2.0E3 CPS a.
What automatic action (s) has (have) not occurred?
(.5 pts.)
b.
What action is required to be taken by the i
operator? (.5 pts.)
Points Earned
s Question Number:
051-01-044A Point Value:
0.7 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
S l
Subject Area:
PRESSURIZER PRESSURE CONTROL SYSTEM t
Task Number:
C0917 COT Terminal Learnina Obiective:
C0917 COT During all modes of operation and given IU-1 assess the effect of a loss of pressure control on reactor coolant pump operation in accordance with OI-1, " Reactor Coolant Pump Operation Guide."
Question:
Instructor Use Only The Unit 1 RCS is solid at 340*F and 375 psig. RCP "A"
is running.
VCT pressure is 25 psig.
A control problem develops with letdown pressure control valve PCV-135 (in auto and manual control);
and RCS pressure drops to 315 psig, and then stabilizes. RCP "A"
- 1 seal leakoff flow drops from 1.0 gpm to 0.4 gpm.
Explain whether or not it is permissible to continue running RCP "A".
I Points Earned
Question No.:
031-03-053A Page 2 Answer:
Instructor Use only a.
PZR Press. is < 1735 psig with no SI/RHR pumps operating.
(SI has not actuated) (.5 pts.)
b.
Manually Actuate SI because PZR Press.
< 1735 psig.
(.5 pts.)
169 Additional Information:
Technical
References:
TRHB 10.8 EOP-0 EOP-0.1 Items to be Included with Ouestion:
None Time ValidatiRD:
3.50 Recual Cycle:
N/A K/A
Reference:
System:
000 Mode:
009 Number:
EK3.03 Ratings:
RO:
4.1 SRO:
4.4
i Question No.:.051-01-044A Page 2-
)
1 Answer:
Instructor Use Only.
-i t
Yes 1t is permissable (.2 pts.) Conditions of
~
~
OP-4B "RCP operation" are net. (alternate answGr:
- 1 seal leakoff flow and delta-p are adequate) (.5
/
pts.)
{
252
. Additional Information:
i Igchnical
References:
OP-1A OP-4B Items to be Included with Ouestion:
None Time Validation:
4.40 Recual Cycle:
N/A K/A
Reference:
System:
003 Mode:
000 Number:
K1.03 Ratings:.
RO:
3.2 SRO:
3.6 l
G
Question Number:
043-02-011A Point Value:
0.9 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Areat REACTOR. COOLANT SYSTEM Task Number:
CO223 COT Terminal Learninc Obiective:
CO223 COT During conditions of normal power operation PREDICT the effect of changes in the primary system on the secondary system in terms of steam generator parameters and turbine load,'without error.
Question:
Instructor Use Only Unit 1 is at 90% power. For each of the individual changes below, predict the effect (increase, decrease or remains the same) on steam generator pressure.
a.
Tavg is decreased by 5*F.
Assume power remains at 90%. (.3 pts.)
b.
Turbine power is decreased by 20%. (.3 pts.)
c.
Core delta T is decreased by 6*F.
Assume Tavg does not change. (.3 pts.)
Points Earned
Question No.:
043-02-011A' Page 2 Instructor Use Only
-Answer:
a.
Steam pressure decreases.
(.3 pts.)
b.
Steam pressure increases.
(.3 pts.)
c.
Steam pressure increases.
(.3 pts.)
168 Additional Information:
't Technical
References:
Steam Tables-Set Point Document LP-1486 Items to be Included with Ouestion:
None Time Validation:
3.00 Recual Cycle:
N/A K/A
Reference:
System:
002 Mode:
000 Number:
K5.11 Ratings:
RO:
4.0 SRO:
4.2 ll t
l i
w _-- _ _ _ _..- ___
Question Number:
031-03-003A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
E Subject Area:
STEAM GENERATOR SYSTEM Task Number:
C2408 COT, P0204 COT Terminal Learnina Obiective:
C2408 COT During an accident or emergency condition. recognize the significance of a loss of a steam generator on the heat removal capability and the importance of the remaining steam generator to removing decay heat.
P0204 COT During a shutdown condition following an emergency condition establish natural circulation in accordance with the guidelines established in the Emergency Operating Procedures (Steps contained in several specific EOPs).
Question:
Instructor Use Only Unit 1 is operating at 100% power when a steamline break occurs upstream of the "A" MSIV.
a.
Explain how decay heat should be removed from the core after the "A" S/G boils dry?
(.3 pts.)
b.
Explain whether or not AFW pump 1P29 would be available. (.5 pts.)
{
Points Earned
]
Question No.:
031-03-003A Page 2 Answer:
Instructor Use Only a.
By dumping steam from the "B" SG (through the condenser steam dumps, atmospheric steam dump or safeties) or increasing feed flow.
(.3 pts.) (Either answer acceptable.)
b.
Yes it is still available (.2 pts.) Steam can be supplied steam from the "B" SG. (.3 pts.)
128 Additional Information:
Technical
References:
M-201, Sht. 1 TRHB 11.4 Items to be Included with Ouestion:
None Time Validation:
2.80 Recual Cycle:
N/A K/A
Reference:
System:
035 Mode:
010 Number:
K3.01 Ratings:
RO:
4.4 SRO:
4.6
Question Number:
039-01-005A Point Value:
1.0 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
C l
Subject Area:
PRESSURIZER RELIEF TANK f
Task Fumber:
C0706 COT, C0707 COT Terminal Learnino Obiective:
C0706 COT During all modes of operation, relate the interdependence of extensive and intensive properties of water in the determination of the thermodynamic state without error.
C0707 COT During all modes of operation, evaluate energy conversions in the primary and secondary systems using the first law of thermodynamics to determine the direction of heat transfer without error.
\\
Question:
Instructor Use Only Assuming a pressurizer safety valve lifts, which one of the following statements is True?
a.
The downstream safety relief temperature detector will indicate Tsat for the pressurizer.
b.
PRT temperature will equal Tsat for the pressurizer.
c.
The downstream safety relief temperature detector will indicate T at for the PRT.
s d.
PRT pressure will equal Psat for the pressurizer.
e.
The downstream safety relief temperature will lower as pressurizer pressure lowers.
I Points Earned I
1
\\
l Question No.:
039-01-005A Page 2 l
l Answer:
Instructor Use Only c.
(1.0 pts.)
294 Additional Information:
Technical
References:
Steam Tables Items to be Included with Ouestion:
None l
Time Validation:
1.70 Reaual Cycle:
N/A K/A Referencq:
System:
007 Mode:
000 Number:
A4.10 Ratings:
RO:
3.6 SRO:
3.8 1
l l
t Question Number:
053-01-033A Point Value:
1.0 Revision Number:
0 Approval Date:
06/20/89 L
Question Format:
W Question Type:
M l
Subject Area:
ROD CONTROL SYSTEM Task Number:
C0107 COT l
Terminal Learnina obiective:
l C0107 COT During all modes of operation and given a copy of Technical Specifications, diagnose malfunctions of the rod control system prior to exceeding Technical Specification limits of 15.3.10, " Control Rod and Power Distribution Limits".
Question:
Instructor Use Only The rod control system is in automatic with power at 100%. Turbine impulse pressure transmitter (PT 485) fails low. Rods will (Choose one answer.)
a.
nove out at maximum speed.
b.
nove out at minimum speed.
C.
not move.
d.
nove inward at maximum speed.
e.
nove inward at minimum speed.
l
]
Points Earned
Question No.:
053-01-033A Page 2 Answer:
Instructor Use Only d.
(1.0 pts.)
Additional Information:
O Technical
References:
Ingic' Drawing 883D195 sh. 16 IP 1547 Rod control System Items to be Included with Ouestion:
None Tine Validation:
2.30 Recual cycle:
N/A l
K/A
Reference:
System:
001 Mode:
000 Number:
G07 1
Ratings:
RO:
3.2 SRO:
3.3 1
l l
i Question Number:
052-03-005A Point Value:
1.0
{
Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
ELECTRO-HYDRAULIC OIL SYSTEM Task Number:
C3122 COT, C3401 COT j
l Terminal Learnina Obiective:
C3122 COT Concerning the automatic operation of the main turbine generator IDENTIFY causes of interlocks, permissives, and automatic functions associated with the main turbine generator as referenced in the Setpoint Document.
C3401 COT During normal power operation involving the main turbine generator DIAGNOSE a failure of the EHC system without error using available indications on the main control board.
Question:
Instructor Use Only Unit 1 is at 100% power when the running (in auto)
EHC pump (P75) loses its power source due to an improperly operated breaker.
a.
What one control room alarm will annunciate?
(.5 pts.)
b.
Explain whether or not this loss will adversely affect the turbine generator EHC system. (.5 pts.)
I L
Points Earned j
i 0
l Question-No.:
052-03-005A Page 2' l
Answer:
Instructor Use only l
a.
EH Supply System. (.5 pts.) Alternate answer:
-l EH system low pressure b.
No it will not (.2 pts.) due to the auto start of the other EH pump. (.3 pts.)
.l 775 Additional Information:
i Technical
References:
TRHB 13.11 ARB 1CO3 l
Items to be Included with Ouestion:
None l
Time Validation:
2.00 j
Recrual Cycle:
N/A
~'
K/A
Reference:
- System:
045 I,
Mode:
050 Number:
K2.10 l
l 1:
l i
I I
Question Number:
053-01-021A Point Value:
0.8 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
E Subject Area:
ROD CONTROL SYSTEM Task Number:
C0102 COT, C0120 COT Terminal Learnino Obiective:
C0102 COT While operating with rod motion possible from either manual or automatic means, assess causes of interlocks, permissives and automatic functions associated with the rod control system without error.
C0120 COT With the rod control system in the automatic mode and the plant operating at an initial power level of 100% FP, assess the response of the rod control system to a turbine runback in terms of correct direction and speed, without error.
Question:
Instructor Use Only Unit 1 is operating at 100% power when a rod bottom bistable fails, causing a turbine runback. All control systems are in automatic. Assuming HQ operator action, describe the response of the rod control system to the turbine runback. Include in your description the signals that could cause rod motion, and specify when rod motion would stop. (No setpoints required.)
Points Earned
Question No.:
053-01-021A-Page 2 i
1
~ Answer:
Instructor Use Only 1
. Control rods will drive in (at max. rate) (.2 pts.)
due to a rate of change between the average nuclear power and turbine load (power mismatch (.2 pts.)
and Tavg/ Tref deviation. (.2 pts.)
They will continue to drive in until Tavg is within 1 degree of Tref (approx. 565'F). (.2 pts.)
091 Additional Information:
Technical
References:
TRHB 13.8, Figures 13.8.1'and 13.8.12 883D195 Sh 16 Items to be Included with Ouestion:
Nono Time Validation:
6.10 Recual Cvele:
N/A K/A
Reference:
System:
001 Mode:
000 Number:
A1.02 Ratings:
RO:
3.1 SRO:
3.4
e
. 4 Section 2 l
1 Question Number:
055-02-106A Point Value:
0.7 Revision Number:
O Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
REACTOR COOIANT PUMP Task Number:
C0313 COT Terminal Learnina Obiective:
C0313 COT During all modes of operation, and given a copy of OI-1 diagnose conditions requiring RCP tripping in accordance with OI-1, " Reactor Coolant Pump Operation Guide".
Question:
Instructor Use only Explain whether or not the affected RCP should remain running.
Points Earned
-_-__-_--__.--_a
,4-
]
. Question No.:
055-02-106A
.Page 2 Answer:
Instructor Use Only.
No it should not (.2 pts.)-the bearing (seal injection or seal outlet) temperature is high (geater.than 225'F. (.5 pts.)
ST 89-02 from 055-02-035A ST 88-01 Additional'Information:
Technical
References:
AOP 1B Items to be Included with Ouestion:
None Time Validation:
1.40 Recual Cycle:
N/A K/A
Reference:
System:
000 Mode:
009 Number:
EK3.23 Ratings:
RO:
4.2 SRO:
4.3
Question Number:
055-02-043A Point Value:
0.6 Revision Number: _ 0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
REACTOR COOLANT SYSTEM Task Number:
CO311 COT l
Terminal Learnina Obiective:
)
C0311 COT During all modes of operation and given a copy of OI-1, diagnose a failure of the RCP seal system in accordance with OI-1, " Reactor Coolan. Pump Operation Guide".
Question:
Instructor Use Only a.
Which RCP contains the failed seal (s)?
(.3 pts.)
b.
Which RCP seal (s) has/have failed? (.3 pts.)
Points Earned
t Question No.:
055-02-043A Page 2 Answer:
Instructor Use Only a.
"A" RCP (.3 pts.)
b.
all of ', hem (all three or #1, 2, and 3)
(.3 pte.)
ST 89-02 from 055-02-034A ST 88-01 Additional Information:
Technical
References:
AOP 1B Items to be Included with Ouestion:
None Time Validation:
1.10 Recual Cvele:
N/A K/A
Reference:
System:
003 Mode:
000 Number:
A4.05 Ratings:
RO:
3.1 SRO:
3.0 l
E_______
Question Number:
053-04-012A Point Value:
O.8 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
PRESSURIZER LEVEL CONTROL SYSTEM Task Number:
C1010 COT Terminal-Learnina obiective:
C1010 COT During all modes of operation invo:..ving pressurizer level control, identify causes of 80% of interlocks, permissives, and automatic functions associated with the pressurizer level control system.
Question:
Instructor Use Only a.
Explain why the " Pressurizer Level Setpoint Deviation" alarm is lit? (.4 pts.)
b.
Explain whether or not the backup heaters, selected for automatic control, are on because of the " Pressurizer Level Setpoint Deviation" alarm. (.4 pts.)
l Points Earned u-
l 1
. Question.No.:
053-04-012A-Page 2 Answer:
Instructor Use Only a.
Actual level is less than program level by au1 amount greater than the alarm setpoint.
(Also acceptable: correct setpoints or control board indications)
(.3 pts.)
b.
No they should not (.2 pts.) the heaters come on if there is a high deviation alarm (2 5%)(a low deviation alarm exists)
(.3 pts.)
ST-88-11 / ST 89-02 595 Additional Information:
Technical
References:
TRHB 13.6 STPT 5.3 Items to be Included with Ouestion:
None Time Validation:
6.80 Recual Cycle:
N/A K/A
Reference:
System:
004 Mode:
000 Number:
K1.01 Ratings:
RO:
3.6 SRO:
4.0 l
Question Number:
053-02-028A Point Value:
0.8 l
Revision Number:
1 Approval Date:
06/20/89 7
l Question Format:
W Question Type:
C Subject Area:
ROD CONTROL SYSTEM Task Number:
C0114 COT, C1102 COT Terminal Learnina Obiective:
l C0ll4 COT During all modes of operation with the reactor trip breakers closed, identify alternate means to open the reactor trip and bypass breakers upon failing to do so automatically, without error.
C1102 COT During all plant operating conditions involving closed reactor trip breakers, recognize conditions requiring reactor protection actuation.
Recognition of all plant parameters that will cause a reactor trip as well as their corresponding setpoints are required, without error.
Question:
Instructor Use Only Upon evaluating the current conditions, the operator should (Choose one answer.)
a.
i.itiate manual safety injection.
b.
run back the turbine in manual, with rod control in automatic, to < 20%.
c.
open supply breakers to B01/B02.
d.
monitor pressurizer level, and allow the power descent to continue.
Points Earned
Question No.:
053-02-028A Page 2 l
l l
Answer:
Instructor Use Only l
c.
(0.8 pts.)
ST-88-01 / ST 89-02 349 Additional Information:
Technical
References:
EOP-0 CSP-S.1 Items to be Included with Ouestion:
None Time Validation:
2.20 Recual Cycle:
N/A K/A
Reference:
System:
000 Mode:
029 Number:
EA1.12 Ratings:
RO:
4.1 SRO:
4.0
(
b
Question Number:
053-02-025A Point Value:
0.9 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
REACTOR PROTECTION SYSTEM Task Number:
C1105 COT Terminal Learnina Obiective:
C1105 COT Upon receipt of indications and alarms that a reactor trip actuation has occurred, assess the response of the reactor trip breakers to the actuation in accordance with EOP-0.
Question:
Instructor Use only Consider the current plant conditions.
a.
Explain whether or not the reactor tripped.
(.4 pts.)
b.
Explain whether or not the SI pumps should be running at this time. (Include in your answer all auto start signals; setpoints not required.) (.5 pts.)
1 l
I Points Earned
l Question No.:,053-02-025A page 2 i
Answer:
Instructor Use Only 1
1 a.
No the reactor did not trip (.2 pts.) because
- Reactor trip breakers are closed (not open).
- All rods are withdrawn (no rod bottom bystables).
l
- Neutron flux not decreasing (power is at 70% or current value).
(Any one of three) (.2 pts) b.
No the SI pumps should not be running
(.2 pts.)
Pressuriz ure is not low (<1735 psig).
(.1 pts.
- Steamli, preesu is not low (<530 psig).
(.1 pts.
Containmen pressure is not high (>5 psig).
(.1 pts.)
(Also acceptable: current values on the simulator)
(No credit will be given or taken away if manual SI signal is included)
ST-88-01 / ST 89-02 342 Additional Information:
Technical _
References:
EOP-0 Items to be Included with Ouestika:
None Time Validation:
2.70 Recual Cycle:
N/A K/A
Reference:
System:
000 Mode:
029 Number:
EK3.01 Ratings:
RO:
4.2 SRO:
4.5 1
' ?.
QuOstion Numbar:
051-02-019A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89 1
Question Format:- W Question Type:
S Subject Area:
CHEMICAL & VOLUME CONTROL SYSTEM Task Number:
C0401 COT Terminal Learnina Obiective:
C0401 COT During all modes of operation, and given CL-5A, assess lineups to verify proper operation of CVCS in accordance with CL-5A, "CVCS".
Question:
Instructor Use Only Explain whether or not makeup actuation should have occurred to the VCT.
Points Earned
1
. Question No.:
'051-02-019A Page 2 1
-Answer:
Instructor Use Only
.j VCT makeup actuation should have occurred.
(.2 pts.)
Level is.below the auto' makeup setpoint but was not armed (flags-are not matched) (.4 pts.)
ST-88-11 / ST 89-02 600 Additional Information:
Technical
References:
TRHB 10.6 CVCS Dwg. 685J175 Sec. 1 & 2 Jtems to be Included with Ouestion:
None Time Validation:
1.90 Eg.gual Cvele:
N/A K/A ReferenG; System:
004 Mode:
000
-Number:
K4.04 Ratings:
RO:
3.2 SRO:
3.1
r-Question Number:
051-01-047A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
C Subject Area:
Task Number:
CO211 COT Terminal,learnina Obiective:
CO211 COT During all modes of operation analyze the affect of a LOCA on the RCS to determine severity and location.
Question:
Instructor Use Only i
Explain whether or not the changs in pressurizer level alone could be used to indicate, with accuracy, the magnitude of the leak that existed prior to the reactor trip.
Points Earned 1
l u
. Question No.:
051-01-047A Page 2 Answer:
Instructor Use Only No it should not. (.2 pts.) Tavg changes (.3 pts.)
and charging flow changes (.3 pts.) must also be
-taken!into account.
ST 89-02 from 051-01-028A ST 88-01 Additional Information:
Technical
References:
AOP 1A Items to be Included with Ouestion:
None Time Validation:
2.00 Recual Cycle:
N/A K/A keference:
System:
000 Mode:
009 Number:
EA2.05 Ratings:
RO:
3.4 SRO:
3.9 e
f
' Question Number:
051-01-032A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject-Area:
REACTOR COOIANT PUMP Task Number:
C0301 COT Terminal Learnina Obiective:
C0301 COT During all modes of operation and given OI-1 assess the effect of a loss of seal injection on the RCPs in accordance with OI-1, " Reactor Coolant Pump Operation Guide."
Question:
Instructor Use Only State the root cause of the " Reactor Coolant Pump A or B Cooling Water Return Temperature High" alarm on 1CO3 D2-4.
1 I
Points Earned
____._________m
j..
-Question No.:. 051-01-032A-Page'2
-Answer:
Instructor Use Only The alarm is activated by TC-612 (RCP total CCW outlet). Caused by a seal failure on the A RCP.
(reactor coolant flow past the number one seal)
(.6 pts.)
ST 89-02 from 051-01-022A. ST 88-11 Additional Information:
Technical
References:
~AOP 1B ARB ICO3 TRHB 10.9 i
Items to be~ Included with Ouestion:
None Time Validation:
2.40 Resual cycle:
N/A K/A
Reference:
- System:
004 Mode:
000 Number:
K1.04 Ratings:
RO:
3.4 SRO:
3.8
____.m. _ _ _ _. _ _ _ _ _ _ _ _... _. _ _ _
Question Number:
031-03-107A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/09 Question Format:
W Question Type:
C Subject Area:
EMERGENCY TASKS Task Nu'ber:
c?L24 COT m
Terminal Learnina Obiective:
C7024 COT Given a set of Emergency Operating Procedures apply the procedural rules of usage to the EOPs by performing procedural steps in proper sequence making correct transitions to sequence through the EOPs to a termination point.
Question:
Instructor Use Only Following entry into EOP-0, " Reactor Trip or Safety Injection," the operator should a.
continue in EOP-0 until SI occurs; then, start EOP-0 again.
b.
continue in EOP-0 and transition to EOP-0.1,
" Reactor Trip Response."
c.
manually actuate safety injection and go to EOP-1, " Loss of Reactor or Secondary Coolant."
d.
leave EOP-0 and transition to CSP-S.1,
" Response to Nuclear Power Generation /ATWS."
Points Earned
ie':
Question No.:
031-03-107A Page 2 Answer:
Instructor Use Only d.
(.8 pts.)
ST-88-01 / ST 89-02 348 Additional Information:
' Technical Referenceg:
EOP-0 Items to be Included with Ouestion:
None Time Validation:
0.80 Recual Cvele:
N/A K/A
Reference:
System:
000 Mode:
029 Number:
EK3.12 Ratiings:
RO:
4.4 SRO:
4.7
Question Number:
031-03-112A Point Value:
0.8 Revision Number:- 1 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:. EMERGENCY TASKS Task Number:
C7007 COT Terminal Learnina Obiective:
C7007 COT From operating plant conditions with the reactor at power recognize an ATWS by identifying the cause and result of the ATWS using all available control room alarms and indications.
Question:
Instructor Use only a.
What two major accidents are in progress.
(.4 pts.)
b.
What independent' mechanisms in the Reactor Trip breakers receive signals to open?
(.4 pts.)
Points Earned
'i, Question No.:
031-03-112A Page 2 Answer:
Instructor Use Only a.
RCP seal failure
(.2 pts.)
Alternate answer:
(.2 pts.)
l b.
UV coil (undervoltage coil)
(.2 pts.)
Trip coil (shunt trip coil) (.2 ^ pts.)
ST-88-01 / ST 89-02 329 Additional Information:
Technical Referengt.g:
TRHB 13.3 Items to be Included with Ouestion:
None Time Validation:
2.70 Recual Cvele:
N/A K/A
Reference:
System:
000 Mode:
007 Number:
EA2.06 Ratings:
RO:
4.3 SRO:
4.5 1
l l
Question Number:
031-03-114A Point Value:
0.6 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
EMERGENCY TASKS Task Number:
C7003 COT q
Terminal Learnina Obiective:
l C7003 COT From an operating condition with the reactor critical, assess the response of the plant to a reactor' trip by verifying the response of all automrtic actions.
Questicn:
Instructor Use Only Explain why the turbine stop valves and governor valves are open at this time. (Include any reactor protection signals that affect the turbine.)
Points Earned
7_
Question No.:
031-03-114A Page 2 Answer:
Instructor Use Only The reactor trip breakers failed to open.
(.6 pts.)
(Alternate answer:
The "B" contacts on the reactor trip breakers did not pick up.)
ST-88-01 / ST 89-02 332 Additional Information:
Technical
References:
Logic Sht. 2 Items to be Included with ouestion:
None Time Validation:
2.40 Reaual Cycle:
N/A K/A
Reference:
System:
000 Mode:
007 Number:
EK1.03 Ratings:
RO:
3.7 SRO:
4.0 e
1 l
l L_______-
M'
. Question Number:
031-03-109A Point Value:
0.7 Revision Number:
l' Approval Date:
06/20/89 1
Question Format:
W Question Type:
S 7
Subject Area:
REACTOR COOLANT SYSTEM Task Number:
CO219 COT
-Terminal Learnina obiective:
C0219 COT During emergency conditions, analyze the effect of a I4CA g
on the containment.
Satisfactory understanding should I
include the containment design limits and sump capacity.
i Question:
Instructor Use Only Explain whether or not containment spray will be needed if the accident continues on its present course. (Assume no core damage.)
i 1
i Points Earned l
l
t
'l Question No.:
031-03-109A Page 2 1
Answer:
Instructor Use Only i
No containment. spray will not be t'seded (.2 pts.)
pressure is not expected to increase to above the spray. actuation setpoint (25 psig) for this accident-(also acceptable: a small LOCA or the accident fans can handle the leakage). (.5 pts.)
]
i ST-88-01 / ST 89-02 338 Additional Information:
Igchnical
References:
EOP-0 EOP-1 LP-1340 Items to be Included with Ouestion:
None Time validation:
3.10 Reaual Cycle:
N/A K/A
Reference:
System:
002 Mode:
020 Nur.ber:
K3.02 Ratings:
RO:
4.2 ERO:
4.6
Question Number:
031-03-111A Point Value:
0.7
'f Revision Number:
1 Approval Date:
06/20/89 it'
. Question Format:
W Question Type:
S Subject Area:
EMERGENCY TASKS Task Number:
P7001 COT Terminal Learnina obiective:
l P7001 COT During an accident condition respond to a loss of reactor coolant by performing the actions described in the Emergency Operating Procedures (EOP-1), " Loss of Reactor or Secondary Coolant").
Question:
Instructor Use Only Assume pressurizer level decreases at 4%/ minute.
Explain whether or not any ECCS pumps will inject l
water into the RCS in the next 15 minutes.
l l
l l
l i
Points Earned
'I 5
Question No.:
031-03-111A Page.2
-Answer:
Instructor Use only u
The SI pumps will inject (.2, pts.) the LOCA is more than charging pump. capacity. (The RCS trill depressurize below SI pump shutoff head pressure.)
~(.5 pts.)
. Additional Information:.
Technical
References:
LP-1340 EOP-1 Items to be Included with Ouestion:
None Time Validation:
5.20 Remial cycle:
N/A K/A
Reference:
System:
013 Mode:
000 Number:
A1.01 Ratings:
RO:
4.0 SRO:
4.2
_m_
_m_
Question Number:
052-02-001A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
ADMINISTRATIVE SYSTEM Task Number:
C2702 COT, C6501 COT Terminal Learnina Obiective:
C2702 COT During startup, shutdown and normal power operation apply TS and procedural requirements associated with operation of the MS system without error.
C6501 COT During all modes of operation assess TS and procedural requirements to equipment necessary for safe operation of the plant in accordance with all procedural and Technical Specification requirements without error.
Question:
Instructor Use only Assume prior to the event, Diesel Generator G02 failed its surviellance test and was still out of service. Breaker 1A52 63 (A04 to A06 feeder) trips open shortly after the safeguards actuation occurs.
Explain whether or not the electrical lineup will orevent you from mitigating the accident.
l l
t Points Earned
-a.,.
e i
Question No.:. 052-02-001A, Page 2' Answer:
Instructor Use Only
- i No.it will not.. (.2 pts. ) one train of ECCS (safeguards) equipment will remain powered
.(.4 pts.)
c Alernate answer: EOP's'and/or FSAR assume only one train of safeguards availthle.
l i
~
ST-88-05,-ST-89-02
. i l
K/A
Reference:
System:
013 Mode:
000 Number:
K4.08 Rating:
Ro 3.1 SRO 3,4
' l Note 2 467 1
i Additional' Information:
l l
Technical
References:
~TRHB 10.6 TRHB 12.5
)
' Items to be Included with Ouestion:
None l
l 1
Time validation:
,. 6.30 Eggral Cvele:.N/A
'-K/A Referenf3:- System:
013 Mode:
000 Number:
K4.08 i
Ratings:
RO:
3.1 SRO:
3.4 i
i D
Question Number:
055-02-107A Point Value:
0.8 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
CHEMICAL & VOLUME CONTROL SYSTEM Task Number:
C0313 COT, C0430 COT Terminal Learnina Obiective:
C0313 COT During all modes of operation, and given a copy of OI-1 diagnose conditions requirir.g RCP tripping in accordance with OI-1, " Reactor Coolant Pump Operation Guide".
C0430 COT During all modes of operation, assess the effect on the CVCS of a charging pump relief valve sticking open prior to causing a charging pump to reach it's maximum upper speed limit or excessive letdown temperature.
Question:
Instructor Use only Assume that prior to this event the unit was at 100% steady state power; charging pump 1P2A was in auto; 1P2B was in manual at minimum speed; and 1P2C was off.
The IP2A discharge relief valve (1-283A) failed open.
What are four indications / parameters available in the control room that would change due to 1-283A failing open?
Indicate whether the indication / parameter will INCREASE / DECREASE.
Points Earned
,4 t
[QuestionNo.:. 055-02-107A Page 2-Answer:
Instructor Use Only.
-1P2A charging pmap speed (.1 pts.) increase (.1 pts.).
-Pressurizer level (.1 pts.') decrease (.1 pts.)
-Charging flow (.1 pts.) decrease (.1 pts.)
-Letdown. temperature (.1 pts.) increase (.1 pts.)
-RCP lab seal. delta P (.1 pts.) decrease (.1 pts.)
-VCT level (.1 pts.) increase.(.1 pts.)
(any four. required)
ST-89-02 Additional Information:
Technical
References:
None Items'to be Included with ouestion:
None Time Validation:
3.40 Reaual cvele:
N/A K/A Referenqa:
System:
004
. Mode:
020
. Ntunber:
K1.05 Ratings:
RO:
3.4 SRO:
4.0 E-__
m_i____.__.__.______.___.
e.
4~
, 4
.q '
ys Section 3
t
. Question Number:
054-01-010A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89-Question Format:
W Question Type:
S Subject Area:
AC ELECTRICAL DISTRIBUTION SYSTEM
. Task Number:
C4309 COT
.i Terminal Learnina Obiective:
4 i
C4309 COT During all modes of operation, diagnose AC electrical system malfunctions without error.
Question:
Instructor Use Only What caused the "A" RCP to trip?
Points Earned
-Question No.:
054-01-010A Page 2 6.
Answer; Instructor Use Only Failure of the fast bus transfer to energize bus A01 after the reactor trip. (.6 pts.)
(Also acceptable:'A01 is deenergized.)
ST 89-03 from 054-01-003A ST 88-16 Additional Information:
Technical
References:
TRHB 12.5 and 10.2 Logic sheets 3 and 4 Itens to be Included with Ouestion:
None Tine Validation:
1.60 Recual Cvele:
N/A K/A
Reference:
System:
003 Mode:
000 Number:
K2.01 Ratings:
RO:
3.1 SRO:
3.1
1 Question Number:
052-05-022A Point Value:
0.6 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
CONDENSER AIR REMOVAL SYSTEM Task Number:
C3804 COT Terminal Learnina Oblective:
C3804 COT During turbine generator operation, relate the radiological hazards associated with operation of the condenser air removal system without error.
Question:
Instructor Use Only Identify two paths that are currently resulting in a significant radiological release to the environment.
l Points Earned I
L _ - _ __ _
g-
- , g <
3
, '
- r.
i
-> 4.
' Question No.:-
052 05-022A m
Page 2~
'j U
T Answer:
Instructor Use.Only.
l i
. Turbine-driven; auxiliary feedpump I
Air ejectors Gland Exhauster:
Wasting condensate--
Any 2 for full credit,
.3 pts each.
ST-88-04 / STL89-03 364-Additional Inforr.ation:
Technical
References:
AOP-3A Items to'be Included with Ouestion:
None Time Validation:'
3.60 Recual Cvele:
N/A K/A
Reference:
System:
000 Mode:-
038
. Number:
EA1.10 Ratings:
RO:- 3.7 SRO:
3.7
1 Question Number:
031-03-009A Point Value:
1.0 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
C Subject Area:
AC ELECTRICAL DISTRIBUTION SYSTEM Task Number:
C4304 COT Terminal Learnina Obiective:
C4304 COT During an emergency or accident condition assess the response of the diesel generators to an undervoltage condition on a safeguards bus in that the DG nust function to provide electrical power to its associated safeguards loads.
Question:
Instructor Use Only j
What is the status of diesel generators G01 and G02? (Chose one answer.)
a.
G01 is running unloaded; G02 is supplyl'.g 4160V bus 1A06.
b.
G01 1.s supplying 4160V bus 1A05; G02 is supplying 4160V bus 1A06.
c.
G01 is supplying 4160V bus 1A05; G02 is running unloaded.
d.
G01 and G02 are running unloaded.
e.
G01 is running unloaded; G02 did not receive a signal to start.
I l
Points Earned
(
(
I I
Question No.:
031-03-009A Page 2
]
i Answer:
Instructor Use Only d.
(1.0 pts.)
ST-88-16 / ST 89-03 732 Additional Information:
Technical
References:
TRHB 12.5 Items to be Included with Ouestion:
None Time Validation:
0.40 Recmal Cvele:
N/A K/A
Reference:
System:
062 Mode:
000 Number:
K1.02 Ratings:
RO:
4.1 SRO:
4.4 w--._.__.
Question Number:
054-01-001A Point Value:
1.0 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
AC ELECTRICAL DISTRIBUTION SYSTEM Task Number:
C4309 COT, P4320 COT Terminal Learnina Obiective:
C4309 COT During all modes of operation, diagnose AC electrical system malfunctions without error.
P4320 COT During all modes of operation, reset various electrical lockouts without damage to equipment or personal injury.
Question:
Instructor Use Only a.
Explain whether or not MCC B47 (Atcor panel) should be energized? (.6 pts.)
b.
What actions must be taken from the control room prior to being able to re-establish power to MCC B47? (Two required.) (.4 pts.)
l
)
l 1
Points Earned 1
y;m Question No.: ' 054-01-001A Page 2 Answer:
Instructor Use Only-a..
MCC'B47'should not be' energized-(.2 pts.)
MCC B47 is powered from MCC 1B31 which cets strioned on a Unit 1 SI via the 1B03 lockout device.
(.4 pts.)
b.
-Reset SI (.2 pts.) and reset the IB03 lockout
-(.2 pts.)
-ST-88-16 / ST 89-03 729 Additional Information:
Technical
References:
Logic sheet 9 Electrical Master Data Book TRHB 12.5 Items to be Included with Ouestion:
None Time Validation:
3.80 Recual Cyclg:- N/A K/A Referenc.g:
System:
062 Mode:
000 Number:
A2.04 l
Ratings:
RO:
3.1 SRO:
3.4
.m i
l
. Question Number:
053-04-005A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
PRESSURIZER PRESSURE CONTROL SYSTEM Task Number:
CO202 COT Terminal Learnina Obiective:
'CO202 COT During all modes of operation involving control of primary system pressure, analyze the effect of a malfunction of the pressurizer pressure control system on the RCS.. Analysis shall include all effects due to malfunctions that result from an increase-or decrease in the master controller output.
Question:
Instructor Use only Assume the pressurizer pressure channel 430 fails high under current plant conditions. Explain whether or not the pressurizer PORV.PCV-430 would open.
Points Earned
(. 4 l.
4 1
i ;.*
l; 1[
Question No.: -053-04-005A.
Page 2 l
Answer:
Instructor-Use Only No PCV 430 would not open.
(.2 pts.)
The PORV permissive bistable PC-429B would orevent it from
' opening since RCS oressure is < 2335 osia. (.4 pts.)
(Both bistables must be tripped to open the PORV.)
Reference:
System:
010 Mode:
000 Number:
A2.03 Rating:
RO 4.1 SRO 4.2 Note 2 519 Additional Information:
Technical
References:
TRHB 13.5 Logic 883D195 Sht. 18 STPT 5.3 Items to be Included with Ouestion:
None Time Validation:
5.10 Reaual Cycle:
N/A K/A
Reference:
System:
010 Mode:
000 Number:
A2.03 Ratings:
RO:
4.1 SRO:
4.2
- i 1
Question Number:
055-01-020A Point Value:
0.6 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
REACTOR COOLANT SYSTEM Task Number:
P0212 COT Terminal Learnina Obiective:
P0212 COT During a normal plant shutdown, cooldown the RCSLin accordance with administrative limits.
Question:
Instructor Use Only
' Assume the accident continued. The RCS cooldown per EOP 3,
" Steam Generator Tube Rupture", was 0
terminated at 470 F based on core exit thermocouple to ensure the Tech spec limit on cooldown rats was not exceeded. The target 0
temperature was 465 F, based on a ruptured S/G
. pressure of 800 psig.
Explain why.the cooldown should not have been terminated prior to reaching 465'F.
1 1
Points Earned 1
i t
Question No.:-
055-01-020A Page 2 Answer:.
Instructor Use Only Tech Spec. limits on cooldown may be violated per the EOP.-
(.6 pts.)
ST 88-04 / S'a' 89-03 30.1 Additional Information:
Technical
References:
T.S. 15.3'.1 EOP-3 l
Items to be Included with Ouestion:
None Time Validation:
3.40 Recual Cvele:
N/A K/A
Reference:
System:
000 Mode:
038 Number:
EA1.36 Ratings:
RO:
4.3 SRO:
4.5 s
s J
's
-Question Number:
052-03-004A Point Value:
1.0 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W
- Question Type:
S Subject Area:
MAIN TURBINE GENERATOR l
Task Number:
C3121 COT, P3107 COT l
l-Terminal Learnina Obiective:
C3121 COT During conditions of startup, shutdown and normal power operation APPLY Technical Specification and procedural requirements associated with operation of the main turbine generator as referenced in OP-1C, " Low Power to Normal Power" and Technical Specifications, Section 15.3.4.
P3107 COT During conditions of normal plant operation MONITOR the turbine generator in accordance with OP-2A, " Normal Power Operation".
Question:
Instructor Use Only Following the turbine runback and prior to the Reactor trip:
a.
Explain why the Reference Window on the Generator EHC display was no longer at 100%.
(.4 pts.)
b.
Explain whether or not turbine load would have increased if the Setter setting were placed at 100% and the "GO" button depressed.
(.6 pts.)
Points Earned
J Question No.:
052-03-004A Page 2 Answer:
Instructor Use Only a.
The EHC Load Reference was also lowered when the turbine experienced the runback. (.4 pts.)
b.
The Valve Position Limit had been lowered so the Governor Valves would not open any further. (.6 pts.)
(also acceptable is load may increase to the valve position limiter)
ST 88-03 / ST-89-01 / ST 89-03 431 Additional Information:
Technical
References:
TRHB 13.11 Items to be Included with Ouestion:
None Time Validation:
3.60 Rectual Cycle:
N/A K/A
Reference:
System:
045 Mode:
000 Number:
K4.12 Ratings:
RO:
3.3 SRO:
3.6 0
_a
Question Number:
051-01-020A Point Value:
1.0 1
Revision Number:
3 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
STEAM GENERATOR SYSTEM Task Number:
P2404 COT Terminal Learnina Obiectivg:
P2404 COT During all modes of operation and given operating logs monitor SG operation in accordance with operating logs.
l l
l Question:
Instructor Use Only Following the turbine runback and prior to the reactor trip, assume oower was lowered to 65% Der AOP-6A.
While the operators are withdrawing the dropped rod per procedure, would steam generator pressures INCREASE,' DECREASE or REMAIN THE SAME7 Explain why.
i l
l l
{
i
)
l l
I Points Earned i
Question No.:
051-01-020A Page 2
{
Answer:
Instructor Use only S/G pressure will DECREASE (.2 pts.) because TURBINE ISAD IS MANUALLY INCREASED. (.8 pts.)
ST-88-03 / ST 89-01 / ST 89-03 430 Additional Information:
Technigp1
References:
LP-1579 TRHB 11.1 AOP-6A Items to be Included with Ouestion:
None Time Validation:
4.60 Recual Cycle:
N/A K/A
Reference:
System:
001 Mode:
000 Number:
A1.03 Ratings:
RO:
3.6 SRO:
3.7 h
l Question Number:
031-03-130A Point Value:
0.8 Revision Number:
0 Approval Date:
06/20/89 Question Format:
W Question Type:
C Subject Area:
SAFETY INJECTION SYSTEM Task Number:
C0616 COT Terminal Learnino Obiective:
C0616 COT During an emergency or accident condition use safety related temperature and pressure indications (i.e..,
ASIP Subcooling Meter) to diagnose a loss of subcooling to less than the minimum required subcooling margin.
Question:
Instructor Use Only Assume that the transient is allowed to continue.
The cooldown (per EOP 3, " Steam Generator Tube Rupture") to 465'F is completed and terminated at approximately 465'F (based on S/G pressure of 800 Psig).
If RCS pressure subsequently drops to 650 psig and continues to fall with core exit TC's at 468'F, the operator should a.
verify other SI termination criteria and terminate SI.
b.
re-establish the cooldown to increase subcooling margin.
c.
transition to EGP-3.1, " Post Steam Generator Tube Rupture Cooldown Using Feedwater."
d.
transition to ECA-3.2, "SGTR With Loss of Reactor Coolant - Subcooled Recovery Desired."
l Points Earned
)
4
,:l:
Question No.: - 031'-03-130A
.Page 2 Answer:
Instructor Use Only
..d.
(0.8 pts.)
ST-88-04 / ST 89-03 350 Additional Information:
- Technical
References:
EOP-3 Steam Tables
- Items to be Included with Ouestion:
None Time-Validation:
3.40 Recual Cvele:
N/A K/A
Reference:
System:
000 Mode:
038 Number:
EK1.01 Ratings:
RO:
3.1 SRO:
3.4
__-----___an.-
3 Question Number:
031-03-129A Point Value:
0.8 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
STEAM GENERATOR SYSTEM Task Number:
C2417 COT Terminal Learnina Obiective:
C2417 COT During an emergency or accident condition analyze the effect of a stuck open MS safety or SG PORV on the steam generator in terms of SG pressure and temperature and its availability as a heat sink to remove decay heat.
Question:
Instructor Use Only Assume "B" S/G pressure is 1060 psig and its atmospheric steam dump valve is open. Explain whether or not it should be manually isolated.
l l
l l
Points Earned
[t '
Question No.:
031-03-129A-Page 2
' Answer:
Instructor Use Only No it should not. (.2 pts.) Prevents safety valves from lifting. (.6 pts.) (Safeties are more likely
- to fail to reseat.)
Alternate answer: EOP 3 limits pressure to less
. than 1050 psig.
ST-88-04 / ST 89-03 374 Additional Information:
Technical
References:
EOP-3 Items to be included with Ouestion:
None Time-Validation:
2.60 Reaual Cvele:
N/A K/A RefeJJ.D.GJt:
System:
000 Mode:
038 Number:
EK3.02 Ratings:
RO:
4.4 SRO:
4.5 m_____
___.___________m__
_m
________________._________________._m___________
l9
' Question Number:
031-03-102A Point Value:
0.8 Revision Number:
1 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
AUXILIARY TEEDWATER SYSTEM Task Number:
C4209 COT Terminal Learnina Obiective:
C4209 COT During a steam generator tube rupture accident analyze the
)
impact of operating the steam driven AFW pumps in relation to the effect it will have on the ruptured SG pressure.
I Question:
Instructor Use Only The steam supply valve (MOV-2019) from "B" steam generator to the turbine driven AFW pump (P29) will not close from the control room.
a.
What effect(s) would this have on "B" steam generator? (.4 pts.)
b.
How could the steam paths from the steam generator to the environment be isolated?
(Two methods required.) (.4 pts.)
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Points Earned
m t
Question No.:
031-03-102A-Page 2 i
Answer:
Instructor Use Only a.
Continual pressure decrease.
(0.2 pts) b.
-Manual (local) isolate (MOV-2019) (.1 pts. )
and isolate traps (.1 pts.)
-Close MS-126 steam-isolation valve to p29
(.1 pts.)'and isolate traps (.1 pts.)
-Close MS-237 (.2 pts.)
(any two of the three required)
-Additional Information:
Technical
References:
EOP-3 Items to be Included with Ouestion:
None Time Validation:
3.70 Reaual Cvele:
N/A K/A
Reference:
System:
000 Mode:
038 Number:
EK3.01 Ratings:
RO:
4.1 SRO:
4.3
m v
I Question Number:
032-03-001A Point Value:
0.6 Revision Number:
2 Approval Date:
06/20/89 Question Format:
W Question Type:
S Subject Area:
ROD CONTROL SYSTEM Task Number:
C0117 COT Terminal Learnina Obiective:
C0117 COT During all modes of operation and given the Reactor Operating Data Book, analyze associated reactor data when core reactivity is changing in accordance with the Reactor Operating Data Book.
Question:
Instructor Use Only Following the turbine runback and prior to the reactor trip, how many gallons of boric acid would 0
have been necessary to keep Tavg at 562 F while manually withdrawing bank D rods from 173 steps to i
190. steps? (Assume boron worth is -11.2 pcm/ ppm and i
the plant was stabilized at 65% power.)
l (Show all work.)
)
Points Earned
1 fr
, Question No.:
032-03-001A
.Page 2 Answer:
Instructor Use Only Reactivity worth at 173 steps on D:
5457 pcm Reactivity worth at 190 steps on D:
5535 pcm' Reactivity change due to control rod movement
+78 pcm (i 10 pcm)
(.2 pts.)
j Boric acid change necessary l
-78 oca
-11.2 pcm/ ppm
= +7.Opcm(
1 ppm)
(.2 pts.)
Gallons of boric acid
= (7.0 ppm). (1.75 gal / ppm) 12.19 gal (i 2 gal)
(.2 pts.)
n NOTE:
Answer key based on UIC17 Rod 4 Dev O.
Reference:
System:
001_
Mode:
000 Number:
KS.09 Rating:
l Additional Information:
l Technical
References:
1 L
ROD.4, 6.6, 14 L
Blender Book Items to be Included with Ouestion:
None Time Validation:
9.45 Reaual cycle:
N/A K/A
Reference:
System:
001 Mode:
000 Number:
K5.09
.-)
R2 tings:
RO:
3.5' SRO:
3.7 i
J J
l I
1 u___________