ML20248G570
| ML20248G570 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/31/1989 |
| From: | Burdick T, Hopkins J, Lennartz J, Shepard D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20248G566 | List: |
| References | |
| 50-266-OL-89-01, 50-266-OL-89-1, 50-301-OL-89-01, 50-301-OL-89-1, NUDOCS 8904130485 | |
| Download: ML20248G570 (161) | |
Text
- _ -_
j f
1 U.S.' NUCLEAR REGULATORY COMMISSION REGION III' Reports No. 50-266/0L-89-01; 50-301/0L-89-01 Docket Nos-50-266; 50-301 Licenses No. DPR-24; DPR-27
. Licensee:
Wisconsin Electric Power Company Point' Beach Nuclear Plant 6610 Nuclear Road Two-Rivers ~, WI 54241 Facility Name:.PoihtLBeach Examination Administered At:
Point Beach /Kewaunee Simulator Examination Conducted:
Requalification Examinations for Six Reactor Operators and Six. Senior Reactor Operators.
. RIII Examiners:
M 3/[O J. Ho~pkins 6
Dhte-
'l
]/ TilFf D. Shepard Date Chief Examiner:
7[h/ff J. Lennartz 0
Date Approved By:
O T[2'!O T. M. Burdick, Chief Date Operating Licensing Section 2 Examination Summary Examination administered.on Februaii 27 through March 3, 1989 (Reports No. 50-266/0L-89-01; 50-301/0L-89-01))
Areas Inspected:
Written and operating requalification examinations were administered to six Reactor Operators and Six Senior Reactor Operators.
Results:
All operators passed the operating examinations.
Three Reactor Operators and four Senior Reactor Operators passed the written examinations while three Reactor Operators and two Senior Reactor Operators failed the written examinations resulting in 58% of the operators passing the written
. examination.
Therefore, the. licensees requalification program is declared unsatisfactory in accordance with the program performance criteria in NUREG-1021, " Operator Licensing Examiner Standard," ES 601, " Administration of NRC Requalification Program Evaluations," Section D.3.c(2)(b) which states that at least 75% of all operators must pass the written examination in order for the requalification program to be judged satisfactory.
8904130485 890404 r
.hDR ADOCK 05000266 i
REPORT DETAILS I
1.
Examiners
- J.
Lennartz, NRC D. Shepard, NRC i
J. Hopkins, NRC T. Guilfoil, Sonalysts G. Weale, Sonalysts
- Chief Examiner 2.
Examination Development The facilities effort and tineliness in developing the requalification examination material in accordance with the requirements as. stated in the Operating Licensing Examiner Standards (ES-601) in regards to both quality and quantity of material was commendable.
The examination team, which consisted of NRC examiners and facility representatives, was able to develop all phases of the examination entirely from the facilities developed materials.
However, the NRC identified some material that failed to meet the requirements of ES-601 and therefore could not be used.
The identified material deficiencies were brought 60 the attention of the facility representatives on the examination team so that appropriate revisions could be made to the material for future examinations.
The following are a few specific examples of material deficiencies:
Some written examinations Part B, " Limits and Controls," questions developed could be simply answered from memory (057-02-009; 057-02-008; 057-02-001).
These type of questions are not allowed on open-reference examinations.
Part B developed questions 086-01-002, 057-02-015, and 057-02-017 were "look up" type questions.
These type of questions do not meet, i
as a minimum, the comprehension level of understanding, and therefore l
are not allowed on open-reference examinations.
Dynamic simulator scenario OP-88-12 failed to meet the criteria of ES-601, Attachment 6, " Simulator Scenario Review Checklist," in that it did not contain at least one time critical crew re:ponse and therefore could not be used for examination purposes.
3.
Examination Administration The facility was re consible for examination administration with the NRC observing the pr> cess.
The following are a few specific program deficiencies that were identified by the NRC during examination administration:
I 2
?
1 l
t No formal checklists had been developed by the facility which -
could be utilized to brief the operators prior to each phase of the examination.
The lack of a formal briefirg checklist',
hampered the ability.-of the. facility representative to provide consistent information to each group of operators to ensure they fully understood the examination process.
During administration of the JPMs, a few of the facility evaluators used excessive verbal-cues and/or excessive prompting which would a
lead the operator to'a correct decision / action resulting in an adequate examination.
When this occurred, the NRC examiner would privately counsel the facility evaluator and point out deficiencies in his examination administration techniques In all cases where the NRC had to provide private counseling, the facility evaluators examination techniques improved, anu subsequent reminders were not needed.
The facility failed to provide a sufficient number.of examination proctors during administration of the written examinations.
The two part examination was administered in two separate rooms, with only two facility representatives available to proctor both examination rooms while at the same time prov.iding escorts to any individual wanting to leave the examination rooms ensuring that they did not answer with any other individual participating in the examination.
The NRC proctored the examination rooms and break areas to ensure that examination security was not compromised.
The facility provided a third representative to assist in proctoring duties after it was determined that two facility proctors was insufficient.
4.
Examination Evaluations Coevaluation by the NRC examiners and the facility evaluators of the operators performance on the examination was incorporated.
Coevaluations provided the NRC with the necessary information to assess the individual operators performance as well as the facilities requalification program performance.
The overall evaluations on the operating examinations; which consisted of dynamic simulator scenario operations and job performance measure (JPM) plant walkdowns, were consistent between the NRC examiners and the facility evaluators for all 12 operators.
More specifically, the NRC was more conservative then the facility on JPM evaluations for two operators, while the facility was more conservative than the NRC on their evaluation of JPMs for one operator.
Also, the following are specific deficiencies in the operators' performance during the dynamic simulator scenarios that were identified by the NRC that the facility evaluators failed to identify and/or downgrade the operators performance for:
Group I Duty Operations Supervisor (DOS) incorrectly transitioned into Emergency Operating Procedures (E0P)-1.1, "SI Termination" while executing E0P-1, " Loss of Reactor or Secondary Coolant,"
1 3
1 during scenario of 88-06.
At Step 12 of E0P-1,'the DOS incorrectly transitioned into E0P-1.1 while Reactor Coolant System (RCS) pressure was still decreasing.
The correct transition would have been to transition to Step 14 of E0P-1 via the Response Not Obtained (RN0) column for Step 12 of E0P-1.
Group II DOS incorrectly transitioned into E0P-1.1 while executing E0P-1 during scenario 0P-88-06.
At Step 12 of E0P-1, the DOS i
incorrectly transitioned into E0P-1.1 with indicated pressurizer t
(PZR) level at 30% during adverse containment conditions.
The correct transition would have been to transition to Step 14 of E0P-1 via the RNO column for Step 12 of E0P-1.
Group III DOS incorrectly transitioned within ECA-3.1, "SGTR With j
Loss of Reactor Coolant - Subcooled Recovery Desired" during scenario OP-88-07.
The DOS failed to secure Reactor Coolant l
Pumps (RCPs) at Step 21 of ECA-3,1.
Instead, the DOS secured RCPs at Step 25 of ECA-3.1.
The correct transition would have been to secure one RCP at Step 22 of ECA-3.1 via RNO column Action a, and then proceed to Step 22.
At Step 23, the core exit thermocouple temperatures were reading greater than 310 F which would require l
a transition to Step 27 of ECA 3.1 via Step 23 RNO column.
The correct transitions within ECA-3.1 would.have bypassed the step (Step 25) that the DOS utilized to secure RCPs.
The above mentioned differences between the NRC and the facility on JPM l
evaluations as well as the operator deficiencies as identified solely by the NRC did not affect any pass / fail decisions on the operating examinations.
All 12 operators passed the operating examination as evaluate; by both the NRC and the facility.
Parallel grading of the written examination by the NRC and the facility resulted in consistent overall evaluations for all but one operator in which the facility grading was more conservative.
The NRC grading resulted in seven of twelve operators passing the examination while the facility grading resulted in six of twelve operators passing.
5.
Program Evaluation NUREG 1021, ES-601, Section D.3.c(2)(b) states that in order for the requalification program to be judged satisfactory, at least 75% of the operators must pass the written examinations.
Contrary to the above, only 58% (seven of twelve) of the operators passed the written examination and therefore, the facilities requalification program is declared to be unsatisfactory.
The NRC conducted an in depth analysis on the written examination to determine the cause of the high failure rate.
Each section of the examination as well as individual question in regards to each operators results were analyzed.
The following are specific deficiency areas that were identified by the NRC:
4
{
t
~
Part A, " Plant Proficiency" Section 1 of the examination was the major area of concern as evidenced by.an overall average for all operators of 72% as compared to an overall average.of 82% and 83%
on Part 1-Section 2 and Part B, " Limits and Controls," respectively.
The. questions that were directly related to the static simulator scenario in Part A were the cause of.the relatively low results.
. The overall average for all of the operators on those questions was 58%'as compared to an overal.1 average of 85.7% on the remaining questions.in Part A that were not directly related to thelstatic simulator scenario setup.
Of the nine questions in Part A that were directly related to the static simulator setup, questions 1-01, 1-04, 1-05, 1-06, 1-07, and 1-08 were the major area of weakness as evidenced by an overall average for all operators on those specific questions of 49%.
On question 1-01, eight of twelve operators lost full credit due to.
the inability to determine what percent turbine load would stabilize at if a dropped control _ rod event occu.ed following a turbine runback which was caused by a rod position indication (RPI) malfunction.
~
The average score for all of the operators on this question was 60%.
On question 1-04, seven of twelve' operators lost at least one-half credit with an average score for all of the operators of 53%.on this question.
The inability to predict how a turbine runback event would effect the overtemperature delta-temperature (OT delta T) reactor trip setpoint, and the inability to explain the effect each applicable plant parameter had on the OT delta T setpoint.
Six of twelve operators lost full credit on question 1-05 due to the inability to calculate the change in shutdown margin following a l
l turbine runback event which changed control bank rod height.
The average score for all of the operators on this question was 48%.
On question 1-06, six of twelve operators lost full credit due to the inability to diagnose whether a dropped rod event or an RPI malfunction had occurred.
In addition, the inability to predict how Reactor Coolant System (RCS) average temperature (Tavg) would be affected when moving control rods to determine if an RPI channel is malfunctioning was a contributing factor.
The average score for all of the operators on the question was 50%.
Six of twelve operators lost at least one-half credit on L
question 1-07.
The average score for all of the operators was l
58% on this question. The inability to explain how RCS Tavg would respond due to a failed open steam dump following a turbine runback l
event, and how the control rod system would respond to mitigate this event were the contributing factors to the relatively 'w results.
[
5 L
l l
l Five of twelve operators lost full credit on question 1-08.
The average score for all of the operators on this question was 53L The inability to diagnose whether an RPI malfunction event or a
}
dropped rod event had occurred was the contributing factor to l
the operators poor performance on this question.
k As evidenced by all above mentioned specific examination weaknesses, the NRC concluded that the root cause of the high failure rate was attributed to the operators inability to correctly predict overall plant transient response from normal control rod movement and control rod system malfunctions.
In addition, the inability of the operators to predict how the control rod system will respond to plant transients was also a contributing factor.
l 6.
Examiner Concerns During administration of the operating examinations, the NRC identified I
two operational concerns which are described below.
The ability of the Reactor Operators to carryout immediate action steps from memory as contained in the Emergency Operating Procedures 1
(E0Ps) was an apparent weakness.
During the dynamic simulator scenarios, there were a couple of incidents when the Reactor Operator failed to perform all immediate action steps.
The steps were subsequently completed when the DOS asked for verification of immediate action steps while reading from the procedure.
The immediate action steps of the E0Ps must be committed to memory by the operators and performed as such.
In addition, during execution of one Job Performance Measure (JPM) which required the operator to respond to an Anticipated Transient Without Scrams (ATWS),
condition, the operator failed to complete all immediate action steps from memory while executing Critical Safety Procedure q
(CSP) S.1, " Response to Nuclear Power Generation /ATWS." The k
facility evaluator passed the operator on this particular JPM while the NRC concluded his performance to be unsatisfactory.
The Duty Shift Supervisors (DSS) ability to correctly transition thru the E0Ps while performing as the DOS was an apparent weakness.
All of the E0P incorrect transitions as described in Paragraph 4 of this report occurred when the DSS was placed in the DOS position on i
shift. The DSS is a licensed SRO, and therefore must be able to i
satisfactorily perform the duties of the DOS in his absence which include correct timely execution of the E0Ps.
l 7.
Exit Meeting l
An informal meeting was held on March 2, 1989 between the facility training management and the NRC to discuss all of the observed requalification program and operator strengths, deficiencies, and concerns including all examples as contained in this report.
In addition, an exit meeting was held on March 3, 1989 to summarize the observed requalification program and operator strengths, deficiencies, and concerns with facility management and training staff representatives.
6 i
NRC representatives in attendance were:
J. Lennartz, Examiner J. Hopkins, Examiner D. Shepard, Examiner R. Leemon, Resident Inspector Facility representatives in attendance were:
J. Zach, Manager, PBNP R.-Bruno, Superintendent, Training _
J. Knorr, Regulatory Engineer, EQRS J. Reisenbuechler, Superintendent, Operations W. Baines, Training Coordinator M. Mervine, Training Coordinator F.
Flentje, Administrative Specialist, EQRS The facility management acknowledged the examiners observations discussed in Section 2-6 of this report.
l i
i s
7
I Facility:
Point Beach Examiners:
Shepard, Hopkins, Guilfoil, Weale, Lennartz Dates of Evaluation:
Areas Evaluated:
Written X
Oral X
Simulator X
Examination Results:
R0 SR0 Total Evaluation Pass / Fail Pass / Fail Pass / Fail (5, M, or U)
Written Examination 3/3 4/2 7/5 U
Operating Examination Oral 6/0 6/0 12/0 S
Simulator 6/0 6/0 12/0 S
Evaluation of facility written examination grading S
Overall Program Evaluation Satisfactory Marginal Unsatisfactory X
(List major deficiency areas with brief descriptive comments)
Less than 75% passed written examination.
Major area of weakness was the ability of the operators to predict how Rod Control System will respond to plant transients as well as ability to explain overall plant transient response to normal / abnormal rod motion.
Submitted:
Forwarded: g Approved:
(AroU Q
b l
S ction Chief Branch Chief J. Lennartz T. Burdick G. Wright
.;)
Name AJ A t*, t' A (Kev')
y
.Date T89-008:
LIMITS AND CONTROLS 89B (RO)
(FOR APPROVAL)
(TITLE)
Instructions:
1.
Answer all questions on enclosed pages and show all calculations.
2.
Do not discuss the questions or answers with anyone.
3.
' Passing grades are 80% overall; 70% individual section grade.
Section 1
Points Received Section Point Value" 4
~
I I' # r e.
Percentage Grade Overall Graded by Date Reviewed by Examinee Date g
Prepared by
/
[
/f/#c-Date A R/ pre Reviewed by 1
Date
? - / /- r 9 Tec%calReview AhV b
N,,
L.
n)
Date Curricu um-evelopment k,
Approved by 6( %,
Date TR-8.6.1
.(10-87)
7,
(;
Exam Ouestion' Number Ouestion Number 1-01 055-01-028A.
1-02 043-03-010A 1-03 031-03-110A 1-04 1051-03-022AJ 1-05 052-02-011A 1-06 052-05-013A 1-07 054-01-006A 1-08 054-02-008A l
1 055-01-030A 1-10 053-01-027A 1-11 055-01-031A 1-12 031-01-005A 1-13 031-03-005A 1-14 051-04-001A l
1-15 052-01-006A 1-16 057-02-003A 1-17 057-02-017A 1-18 057-02-023A
-(
l
~ ~ _ - - _ _ - _ - -. _
i
\\
Question Number:
055-01-028A Point Value:
0.8 Revision Number:
0 Approval Date:
02/22/89
)
Question Format:
W Question Type:
C
{
Subject Area:
CHEMICAL AND VOLUME CONTROL SYSTEM Task Number:
C0426 COT Terminal Learnina Obiective:
C0426 COT During a normal plant startup and given a copy of OP-1A i
assess charging, letdown and pressurizer pressure when drawing a bubble in the pressurizer in accordance with OP-1A, " Cold Shutdown to Low Power Operation".
1 Question:
Instructor Use Only You are in the process of drawing a pressurizer steam bubble during a plant startup.
RCS pressure is 400 psig, RCP B is in operation, all pressurizer heaters are on and the pressurizer is at saturation temperature for 390 psig. To facilitate drawing a PZR bubble you should:
a.
slowly increase charging pump speed manually.
b.
slowly increase spray flow manually.
c.
slowly decrease letdown flow manually.
d.
slowly decrease the letdown pressure setpoint manually.
Points Earned
__m
_____m__
___________,_m_.__
Question No.:
055-01-028A Page 2 Answer:
Instructor Use Only d.
(.8 pts.)
Additional Information:
1 Technical
References:
OP-1A Items to be Included with Ouestion:
None Time Validation:
2.50 Reaual Cycle:
N/A K/A
Reference:
System:
002 Mode:
000 Number:
K1.06 Ratings:
RO:
3.7 SRO:
4.0
Question Number:
043-03-010A Point Value:
0.6 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
S Subject Area:
RESIDUAL HEAT REMOVAL SYSTEM Task Number:
C0511 COT, C0907 COT Terminal Learnina Obiective:
C0511 COT
'During plant cooldown to cold shutdown conditions the operator must predict core reactivity affects of placing RHR in service in terms of potential dilution effects on the RCS.
C0907 COT Using available control room indications RECOGNIZE the effect of a loss of RCS flow on the pressurizer pressure control system without error to determine the status of the l
RCS and the ability to control pressure.
.i 1
Question:
Instructor Use Only 1
.During a cooldown to cold shutdown in preparation for refueling, an RCS boron sample was taken 1/2 hour after placing RHR in service. RCS boron concentration had increased 50 ppm from the previous sample, which was taken just prior to placing RHR in service. The CVCS was not used to borate the RCS during this time period. Explain why RCS boron concentration increased.
)
i t
I l
I Points Earned
i Question No.: '043-03-010A Page 2 I:
Answer:
Instructor Use Only The RHR system boron concentration is greater than RCS boron concentration (because the RHR system is borated to the RWST boron concentration by recirculation with the RWST prior to securing RHR during.a heatup) during a cooldown to-refueling and boration of the RCS when placing RHR in service is expected. (.6 pts.)
' Additional Information:
Technical
References:
OP-7A OP-7B Items to be Included with Ouestion:
None Time Validation:
3.20 Reaual Cycle:
N/A K/A
Reference:
System:
005 Mode:
000 Number:
K5.03
)
i Ratings:
RO:
0.0 SRO:
3.1 l
i 1
1 l
)
1 I
I 1
Question Number:
031-03'110A Point Value:
0.5 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question. Type:
S Subject. Area: -RESIDUAL HEAT REMOVAL SYSTEM Task Number:
C0514 COT, C2416 COT Terminal Learnina Obiectivg:
C0514 COT During an accident condition the operators must be able to diagnose inadequate suction for the RHR pu*ps from the RCS hot leg, RWST or containment recirculation sump.
C2416 COT.
During emergency operation the operator must analyze.the effect of the MSIV closure on the steam geiiarator in relation to steam generators level, pressure and heat removal capability.
Question:
'Instrr tor Use Only A large break LOCA has occurred.
Operation is proceeding according to EOP-1.3, where preparation is being made to switchover to containment sump recirculation.
The RHR pumps are still aligned for suction from the RWST when the RWST low-low level alarm (6%) is received. The DSS says that the RHR pumps should now be secured.
a.
What is the procedural basis for his statement?
l l
ll.
1 i
i ll Points Earned I
t
.v
.1 Question No.:
031-03-110A
.Page 2
' Answer:
Instructor Use Only i
l' a.
Caution orlor to sten 10 of EOP-1.3 or i
the RWST level may.be to low to provide i
adequate suction for the RHR pumps. The RHR oumos should be secured to orevent damaae due to a loss of suction.
(.5 pts.)
(Either l
answer is acceptable.)
299 Additional Information:
Technical
References:
I EOP-1.3 EOP-1.'3 BG Items to be Included with Ouestion:
None I
Time Validation:
5.90 Recual Cycle:
N/A i
K/A
Reference:
System:
006 Mode:
020 Number:
A4.02 Ratings:
RO:
'3. 9 SRO:
3.8 i
i I
l l
1
Question Number:
051-03-022A Point Value:
1.0 Revision Number:
0 Approval Date:
02/20/89 Question Format:
W Question Type:
S Subject Area:
SAFETY INJECTION SYSTEM Task Number:
C0607 COT Terminal Learnino Obiective:
C0607 COT During all modes of operation and given a copy of EOP-0 apply Technical Specifications and procedural requirements for the SI system operation in accordance with EOP-0,
" Reactor Trip or Safety Injection".
Question:
Instructor Use Only You are in EOP-0 " Reactor Trip or Safety Injection" at step 30 during a Safety Injection situation, the following data were observed:
Rx Core Secondarv Vessel Level: >29 feet SG Pressure: 1100 psig Thermocouple: 510*F SG Level (A and B): 20%
RCS Containment PZR Level:
0%
Pressure: 11.5 psig RCS Pressure:
1125 psig TCWR:
520*F SI Pumps:
On i
a.
Based upon the above data, what action is i
required?
i i
b.
Justify your answer.
\\
l l
Points Earned l
l
l
-i Question No.:.
051-03-022A Page'2 l
' Answer:
Instructor Use Only
)
~
a.
. Secure both RCP's (.5 pts.)
b.
RCS subcooling is < 60*F for an adverse containment and at least one SI pump is I
running. (.5 pts.)
f Additional Information:
Technical-
References:
EOP-0 Items to be Included with Ouestion:
None Time Validation:
10.50 Reaual-Cycle:
N/A K/A
Reference:
System:
000 Mode:
011 Number:
EK3.14' Ratings:
RO:
4.1 SRO:
4.2 l
I
~.
l l
1 l
Question Number:
052-02-011A Point Value:
0.6 Revision Number:
0 Approval Date:
02/22/89 I
Question Format:
W Question Type:
E Subject Area:
MAIN STEAM SYSTEM Task Number:
C2603 COT, C2702 COT Terminal Learnina Obiective:
C2603 COT Concerning the automatic operation of the steam generator blowdown system, IDENTIFY causes of interlocks, permissives and automatic functions associated with the steam generator blowdown system as identified in LP0037.
l C2702 COT During startup, shutdown and normal power operation apply TS and procedural requirements associated with operation of the MS system without error.
i Question:
Instructor Use Only While heating up Unit 1 for a startup from a refueling outage, at 250*F RCS temperature it is discovered that one of the steam generator safety valves on SG 1A is continuously weeping.
The safety valve is subsequently gagged to stop the weeping.
a.
Can the reactor be made critical?
b.
Explain.
Points Earned
b_'
1 1:
Question No.':-
052-02-011A.
Page 2 t..
v JAnswer:-
Instructor'Use Only-
'a.'
No.
TS 15.3.4.A.1
(.2(pts.)
b.
Violates T.S.-to conduct critical Loperations above 350*F without 8 operable steam reliefs.
- (.'4 pts. ) '
037 Additional Information:
Technical
References:
OP-1A (CL-13A)
OP-1B-(CL-1A)
T.S.
15.3 Items to be Included'with Ouestion:
None Time Validation:~
'3.80 Recual Cycle:
N/A' K/A
Reference:
System:
039 Mode:
000 Number:
Gil Ratings-RO:
0.0 SRO:
3.1
Question Number:
052-05-013A Point Value:
1.0 Revision Number:
.0 Approval Date:
02/20/89 Question Format:
W Question Type:
S Subject' Area:
AUXILIARY FEEDWATER SYSTEM Task Number:
C4210 COT Terminal Learnina Obiective:
C4210 COT During all modes of operation analyze causes of interlocks, permissives, and automatic functions associated with operation of the AFW system without error.
Question:
Instructor Use Only A loss of off site power occurs-during a severe thunderstorm.
All systems are operating as designed.
The condensate storage tank high/ low level alarm annunciated.
Both' CST levels are observed to be decreasing at a rate of one foot per minute.
a.
From the time of the alarm how soon must actions be taken?
b.
What specific actions must be taken-(and from which control board)?
i Points Earned
y R
I
!ol'.
Question No.:
052-05-013A Page 2
, Answer:
Instructor Use Only
'l l
l a.
Action must be taken 5.5 minutes from receipt of the CST low level alarm.
(.4 pts.)
b.
Manually open 1 and 2 MOV-4006 on C03 i
(.3 pts. ). (SW supply to the turbine AFW '
i 9
pumps).
I Manually open MO"-4009 and 4016 on C01
(.3 pts.)
(SW supply to P38A and P38B.
117 l
Additional Information:
Technical
References:
EOP-0 ARB C01 A2-9 M-217 Items to be Included with Ouestion:
Underlined the word each in response to a comment from shift.
Time Validation:
5.30 1
Recual Cycle:
N/A K/A
Reference:
System:
061 Mode:
000 Number:
K4.01 Ratings:
RO:
3.9 SRO:
4.2 l
l l
)
l.O
. Question Number:
054-01-006A Point Value:
L.6 Revis!.2n Number:
0 Approval Date:
02/22/89 Questivu Format:
W Question Type:
S Subject Area.
AC ELECTRICAL DISTRIBUTION Task Number:
C4301 COT Terminal Learnina Obiective:
C4301 COT During all modes of operation and given TS 15.3.7, apply TS and procedural requirements associated with the AC electrical distribution system in accordance with TS 15.3.7, " Auxiliary Electrical System."
Question:
Instructor Use Only While operating both units at 100% power with Station Auxiliary Transformer 2X03 out-of-service and the gas turbine G05 operating, Station Auxiliary Transformer 1X03 locks out due to a sudden pressure condition.
Unit 1 operator recommends that'both units be shutdown, Unit 2 operator disagrees.
a.
Which operator is correct?
b.
Justify your answer.
l L
I I
l i
l l
Points Earned E___________________
Question No.:
054-01-006A Page 2 Answer:
Instructor Use Only-
. 2, a.
Unit 2 operator is correct.
(.% pts.)
b.
With both station auxiliary transformer out-of-service and G05 operating, one unit must be placed in hot shutdown; the second unit can remain operating, but must be limited to 50% power.
( M pts.)
161 Additional Information:
Technical
References:
T.S.
15.3.7.B.1.b Items to be Included with Ouestion:
None Time Validation:
2.70 Recual Cycle:
N/A K/A Referer;ce:
System:
062 Mode:
000 Number:
G01 Ratings:
RO:
3.3 SRO:
3.4 i
l Question Number:
054-02-008A Point Value:
0.6 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
S Subject Area:
DC ELECTRICAL DISTRIBUTION SYSTEM Task Number:
C4402 COT, C4403 COT Terminal Learnina Obiective:
C4402 COT During all modes of operation, assess causes of interlocks permissives, and automatic functions associated with operation of the DC electrical distribution s," stem without error.
C4403 COT During all modes of operation, assess the effect of malfunctions of the DC system on plant operation without error.
Question:
Instructor Use Only Both units are operating normally at 100% power. SI and a loss of AC power occur on Unit 1.
The control operator attempts to restore a battery charger to service by closing the control switch on the ASIP 2C20. Assuming the charger has been lined up for recovery per the applicable OI, what must be done to allow closure of the charger contactors?
Points Earned
1 I
?
I Question No.:'
054-02-008A
~ Page 2
,l',
L Answer:
Instructcr Use Only j
l 9
l SI must be reggt (.3 pts.) or normal oower aust be restored (.3 pts.)
i Additional ~Information:
1 Technical
References:
TRHB 12.7
-Elementary wiring' diagram 499B466 sheets 554,555, 556 and 557 Items to be Included with Ouestion:
None Time Validation:
6.10 Recual Cycle:
N/A K/A
Reference:
System:
063 Mode:
000 Number:
K1.03 Ratings:
RO:
0.0 SRO:
3.5 l
I
Question Number:
055-01-030A Point Value:
1.0 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
E
. Subject Area:
ROD CONTROL SYSTEM Task Number:
C0104 COT, C1308 COT Terminal Learnina Obiective:
C0104 COT During all modes of operation and given a copy of OP-3B Appendix "A",
predict the effect of changing plant conditions on SDM in accordance with OP-3B Appendix "A",
" Shutdown Margin Calculation."
C1308 COT During a reactor startup, predict the effect of subcritical multiplication when changing core reactivity.
Question:
Instructor Use Only Unit 1 is operating at 100% power, equilibrium xenon conditions. Boron concentration is 780 ppm,.
Tavg = 570*F and Control Bank D rods are at 225 steps. If Unit 1 tripped from its current conditions, calculate the amount shutdown for Unit 1 thirty-two hours later with the shutdown banks withdrawn? Boron concentration and Tavg have not changed. (burnup = 1000 MWD /MTU) (Show all work.)
Points Earned
l i
I l
-Question No.:
055-01-030A Page 2 l
1 l
1 Answer:
Instructor.Use Only l
Power defect (from
+1375 pcm (.25 pts.)
( d ir,,)
s*
100% power) a n ? rm ? -t- - 3 v o y.)
Rods i-d'?'
p"= - O pcm)
-4726 pcm (.25 pts.)
- y v24 as -
Xenon t 2037 pc=
7*
M 'pcm (.25 pts.).
- 3a i t -l-2ny)
- ? ?lg? ?,T")
q
-2009 pcmA % r M rw(.25 pts.)
Amount Shutdown
( (5 pcm) due to i
Power Defect used, i
Additional Information:
)
Technical
References:
OP-3B App. A rev. 1 ROD book Items tg'be Included with Ouestion:
None Time Validation:
7.10 Recual Cycle:
N/A K/A
Reference:
System:
001 Mode:
010 Number:
A4.04 Ratings:
RO:
3.5 SRO:
4.1 1
q es bn N#-
.f Unit OP-3B, Appendix "A" Date a rG -cyl-d3Y MINOR DSS Revision 1 10-29-84 SHUTDOWN MARGIN CALCULATION 1.0 PURPOSE To determine the shutdown margin of the reactor when at power and when subcritical.
2.0 PRECAUTIONS & LIMITATIONS 2.1 After shutdown from an at-power condition, the xenon concentration will eventually start to decrease, adding positive reactivity. This positive reactivity addition must not reduce the shutdown margin below that required by the Technical Specifications.
2.2 All reactivity data will be obtained from the appropriate unit's Reactor Operating Data Book and Xenon Tables.
2.3 Power defect will encompass the reactivity insertion from an at-power condition to no-load Tavg. If the reactor is shutdown from a no-load condition, power defect will be o pcm.
2.4 Depending on the change in a given variable, the reactivity effect may be positive or negative, therefore ensure the correct sign (i) is circled to avoid confusion.
2.5 Control roil reactivity will be considered negative as rods are stepped inward from the all rods out position.
2.6 If the reactor is suberitical with any number of rods fully or partially withdrawn; the most reactive stuck rod worth must be considered in the shutdown margin calculation. The most reactive stuck rod worth is used even if that particular rod is not withdrawn.
This is done for conservatism and due to a lack of individual rod worth data. If the reactor is suberitical with all rods in the most reactive stuck rod worth is not applicable.
3.0 SHUTDOWN MARGIN CALCULATION FROM AN AT POWER CONDITION 3.1 Rod worth from present rod position to all rods in.
pcm 3.2 Most reactive stuck rod worth
+
pcm 3.3 Power defect for
% power
+
pcm 3.4 Shutdown margin (sum of Steps 3.1, 3.2 and 3.3) pcm l
s
- c N OP-3B
.)
Appendix "A" Page 2 4.0 AMOUNT SHUTDOWN & SHUTDOWN MARGIN CALCULATION WHEN SUBCRITICAL 4.1 Last Critical Condition Data 4.1.1 Time O
hours 4.1.2 Date 4.1.3 Power level
/00 4.1.4 Power defect
+ / 3 7 5-pcm f/ E 4.1.5 Rod position D
bank 2av step 4.1.6 Rod worth from all rods out to position in Step 4.1.5 O
pcm 4.1.7 I number ir e 4.1.8 X number
' /'d 4.1.9 Xenon reactivity
- lo / //
pcm 4.1.10 Boron concentration 7IO ppm 4.1.11 Temperature T 'l 7
- F (Insert no-load temperature if the reactor was tripped from an at-power condition.)
4.2 Conditions at Time of calculations 4.2.1 Time V3 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 4.2.2 Date f
4.2.ge Rod position A
bank a
step 4.2.4 Rod worth from all rods out to position l
in Step 4.2.3
- 4 7 2_ [
j pcm l
4.2.5 X number 4.2.6 Xenon reactivity
- 20 RI pcm d
t 1
OP-3B Appendix "A" Page 3 4.2.7 Boron concentration 7 T#'
ppm 4.2.8 Temperature i t/ 7
'F 4.2.9 Rod worth from all rods out to all rods in pcm 4.3 Araount Shutdown Calculation 4.3.1 Power defect (from Step 4.1.4)
+ /37F pcm 1 / $
l 4.3.2 Rods (Step 4.2.4 minus Step 4.1.6) 1"97d pcm 4.3.3 Xenon (Step 4.2.6 minus Step 4.1.9) i + i l.d pcm 4.3.4 Boron Boron worth coefficient (BWC) pcm/ ppm
((Step 4.2.7 minus Step 4.1.10) x BWC) i O
pc..
l 4.3.5 Temperature
')'
T (Step 4.2.8)
- F ITC1 pcm/ F i
j T (Step 4.1.11)
'F ITC2-pcm/ F 2
ITCt + ITC2 AT = Ti-T2 ITC,yg =
2 Reactivity from temperature change i
pcm (AT x ITC,yg)
I 4.3.6 Amount Shutdown (Sum of Steps 4.3.1
.through Step 4.3.5) 14 > s' pcm + if~
,3.,,,,
4.4 Shn f5IrginCalculation 4'
,, Amount shutdown (from Step 4.3.6) pcm
%g
+
4.4.2 ' ' Reactivity available from rods withdrawn (Step 4.2.9 minus Step 4.2.4) pcm 4.4.3 Most reactive stuck rod worth (zero if all rods are actually inserted)
+
pcm 4.4.4 Shutdown Margin (Sum of Steps 4.4.1 through Step 4.4.3) pcm
(<
l OP-3B Appendix "A" Page 4 5.0 CALCULATION OF THE TIME AT WHICH XENON DECAY ADDS SUFFICIENT
' REACTIVITY TO ACHIEVE CRITICALITY AT 40 STEPS ABOVE THE ZERO POWER INSERTION LIMIT NOTE: THIS CALCULATION ASSUMES THAT THE DECAY OF XENON IS THE ONLY REACTIVITY CHANGE TAKING PLACE AND THE SHUTDOWN MARGIN CALCULATION HAS BEEN COMPLETED.
5.1 Present Reactivity Data 5.1.1 Amount shutdown (from Step 4.3.6) pcm 5.1.2 Rod position bank step 5.1.3 Rod worth from all rods out to position in Step 5.1.2 pcm 5.1.4 Rod worth from all rods out to 40 steps above the zero power insertion limit pcm 5.1.5 Rod worth change (" " " ' 4 minus Step 5.1.3)
+
pcm 5.1.6 I number 5.1.7 X number 5.1.8 Xenon reactivity pcm 5.2 Xenon Data at the Time of criticality 5.2.1 Xenon reactivity change necessary to achieve criticality at 40 steps above the insertion limit.. -(sum of Step 5.1.1 and Step 5.1.5)
+
pcm
.y 5.Q4' Xenon reactivity (sum of Step 5.1.8 and V ^.
Step 5.2.1) pcm 5.2.3 X number for Step 5.2.2 5.2.4 Time and date at which xenon reaches the X number in Step 5.2.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> date Calculation Perfonned By
,{
Question Number:
053-01-027A Point Value:-
0.7 Revision' Number:
0 Approval Date:
02/22/89 1
Question Format:
W Question Type:
E
' 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 l
in accordance with REI #7.
Question:
Instructor Use Only A startup is in-progress and Control Bank B is Lcurrently in motion.
The operator notes that the l
position. indicator for rod F6 has not moved from 45 l
inches in the last 10 rod steps on bank demand. The control operator' attempts to determine whether the j
rod is stuck or the position indicator is i
I malfunctioning by checking to see if a quadrant tilt exists and by evaluating the symmetry of the f
incore thermocouple.
a.
Do you concur with the evaluation method?
b.
Explain why or.why not.
d 1
I l
i l
l l
l l
Points Earned
e t '-
Question-No.:
053-01-027A Page 2 Instructor Use Only Answer:--
- 'j _.
a.
No.
(.'2 pts.)
b.
During a startup, power-(neutron flux) is too low-to give meaningful indication of a misaligned rod using quadrant tilt or thermocouple. (.5 pts.)
Additional Information:
Technical
References:
.T.S.
15.3.10 Items to be Included with Ouestion:
None Time Validation:
10.70 Recual Cycle:
N/A K/A
Reference:
System:
001 Mode:
000 Number:
A2.03 Ratings:
RO:
3.5 SRO:
4.2
)
1
Question Number:
055-01-031A Point Value:
0.6 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
S Subject Area:
PRESSURIZER PRESSURE CONTROL SYSTEM i
i Task Number:
C0906 COT
. Terminal Learnina Obiective:
C0906 COT During a normal plant heatup/cooldown analyze the effect on the pressurizer pressure control system caused by a temperature change during solid plant operations to avert a pressure transient on the RCS.
Question:
Instructor Use Only The plant is shutdown and for the last two hours RCS temperature has been 360*F, with pressure at 450 psig. When the cooldown is resumed on the condenser steam dumps, temperature drops rapidly to 340'F before the operator can regain control. After evaluating the situation, the operator decides to continue the cooldown without any other action.
Do you agree or disagree with this action?
a.
b.
Explain.
l l
l Points Earned l
J
1 Question No.:-
055-01-031A Page 2 Answer:
Instructor Use Only a.
Disagree (.2 pts.)
b.
Technical Specification 15.3.15.A.1 (LTOP operation).was violated. (.4 pts.)
Additional Information:
Technical
References:
T.S.
15.3.15.A.1 Items to be Included with Ouestion:
None Time Validation:
13.80 Reaual Cycle:
N/A K/A
Reference:
System:
010 Mode:
000 Number:
A1.04 Ratings:
RO:
3.6 SRO:
3.8 i
i s
Question Number:
031-01-005A Point Value:
0.7 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
S Subject Area:
EMERGENCY TASKS Task Number:
C7024 COT, C7025 COT 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.
C7025 COT Given a set of Emergency Operating Procedures analyze the format and organization of the EOPs by identifying the various transition paths between procedures and the established priorities of various groups of procedures.
Question:
Instructor Use only The unit has suffered a total loss of all AC from an initial condition of 100% power.
Indicated SG wide range levels are 190" and 195", for "A" and "B" SG, respectively.
The turbine-driven AFW can only feed each SG at 75 gpm.
The DSS decides to make a transition to CSP H-1 " Response to Loss of Secondary Heat Sink."
a.
Do you AGREE / DISAGREE with this transition?
b.
Explain.
Points Earned
?.<
Que'stionLNo.:. 031-01-005A-Page 2.
]
a
- Answer:
Instructor Use Only 1
a.
~ Disagree (0.2. pts.)
b.
During a loss. of ~al). AC, ST's are. to be monitored for information only; CSP's are not to be performed.
(.5 pts.)
Alternate answer:.Should be in ECA 0.0,
" Loss of All-AC" 080 Additional Information:
Technical-
References:
- ECA-0, cautions Items to be Included with Ouestion:
Added alternate answer to cover.the procedure where the note is listed
. based on comments from a practice exam.
Time' Validation:
3.50 Reaual Cycle:
N/A K/A
Reference:
System:
000 Mode:
055
-Number:
G12
_---_l_______-_-_-_______
i
9 Question' Number:
031-03-005A Point Value:
0.6 Revision Number:
0 Approval Date:
02/22/89 Question Format:
-W' Question Type:
S Subject Area:
EMERGENCY TASKS Task Number:
C7009 COT, C7028 COT Terminal Learnina Obiective:
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 satisfied in accordance with the critical safety function status trees.
C7028 COT During an accident or emergency condition involving a steam generator recognize multiple casualties so they may be identified and their priorities established according to EOP, Emergency Contingency Actions.
Question:
Instructor Use Only Unit 2 was operating at 100% power, when a reactor trip and safety injection occurred and the immediate actions of EOP-0 " Reactor trip or Safety Injection" are complete. During the accident, the two steam generators have the following conditions:
A B
Units WR Level 465 210 Inches Pressure 1010 600 Psig Steam Flow 0
0 Lb/Hr RE-231/232 SE-02
-6.03E-05 uci/cc a.
Which SG is ruptured?
b.
Which SG is faulted?
c.
Which condition should be addressed first?
i l
l Points Earned l
w_____
4 Question No.:
031-03-005A Page.2 Answer:'
Instructor Use Only a..
A.
(.'2 pts.)
- b.
B.
(.2 pts.)
c.
B. (faulted).
(.2 pts.).
163 Additional Information:
Technical
References:
.EOP-O' l
Items to be Included with Ouestion:
None Time Validation:
1.40 Recual Cycle:. II/A K/A Referengg:
System:
000 Mode:
038 Number:
EA2.03 Ratings:
RO:
4.4 SRO:
4.6 i
l f
l i
1 i
l Question Number:
051-04-001A Point Value:
0.7 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
S Subject Area:
LIQUID RADWASTE SYSTEM Task Number:
C4801 COT Terminal Learnina Obiective:
C4801 COT During all modes of operation and given a copy of OP-9A apply TS and procedural requirements associated with the liquid waste system in accordance with OP-9A, " Liquid Waste Process System Operation".
-Question:
Instructor Use Only A liquid release from "A" waste distillate tank is in progress, and throttled to 35 gpm.
An auxiliary operator is monitoring the release by periodically checking tank level.
The following information is noted:
i Time Tank Level 1205 74%.
1220 67%
1230 62.5%
1 1245 55.5%
1250 54%
a.
Does the indicated flow rate agree with the observed change in level?
b.
Show any calculations required to support your answer.
I Points Earned
I, l.
l..
l*
' Question No.:
051-04-001A Page 2 Answer:
Instructor'Use Only Note:
Also accept calculations if thumbrule of
%o 07.25 ga1/% used. o e isoy,/,Ho ars use d.
a.
No.
(.2 pts.)
b.
97.25 cal /% x % chance (chosen by operator) time (chosen by operator)
(.5 pts.)
Te-Llew 77' 127 Additional Information:
Technical
References:
OP-9A pg. 3 Tank Book TLB-23 Items to be Included with Ouestion:
None 1
Time Validation:
2.90
-Recual Cvele:
N/A K/A
Reference:
System:
068 Mode:
000 Number:
G01 Ratings:
RO:
0.0 SRO:
3.1
%diu /*s :
A, r.y f,n 1
f 3d./- d3sdy /
. y 3,3
@ '!E o.//-4 L 7L/ 4,4 (0
v laes f,., % 1 Bad 9
p l
" ~ ' ' "
7 9 '4 = P2 W y./,
95:o,,//,4 x y g =- 4nyp 67'I*
7 tse y, /,
y 5,.
I ya /,
O. ci'/o
= 1too D I"y //"5 6""' N"4 D'l rr, reg a S yys y, j,
% f ru /a.
r9 <4
- ( y>o y /.
' a'l reac44s 2 Wyl
- ] = / / 'A
- d = y y, yy.
l 4rp
Question Number:
052-01-006A Point Value:
1.8 Revision Number:
0 Approval Date:
02/22/89 Question' Format:
W Question Type:
S Subject Area:
FIRE PROTECTION SYSTEM Task Number:
C5203 COT,.C6101 COT Terminal Learnina Obiective:
C5203 COT During the process of simulation or evaluation identify causes of interlocks, permissive and' automatic functions j
associated with the circulating water system to maintain plant efficiency and condenser vacuum.
C6101 COT As required by periodic TS testing; as part of the watch standing duties and, as directed by shift supervision, 1
apply TS and procedural requirements associated with operation of the fire protection system as measured by TS compliance.
Question:
Instructor Use Only Since P35B, the diesel-driven fire pump is inoperable, daily surveillance are being performed on pump P35A, the electric motor-driven fire pump.
Today's surveillance has been completed, and returned to the Dt.ty Shift Superintendent.
All steps have been initialed and the recorded discharge pressures are:
PI-3706, fire header pressure (C01): 149 psig PI-3719, P35A motor driven fire pump discharge pressure:
152 psig a.
After verification of readings, what actions are required?
b.
Explain.
l l
l f
l l
l Points Earned
(
l.
1 s
]
Question No.:'
052-01-006A Page 21
}
Answer:
Instructor Use Only-j i
i a.
'A backup fire suppression water' system must be established within 24-hours.
(.5 pts.)
Also prompt. notification to the NRC must be-d made (.3 pts.)
b.
Since the' pumps discharge pressure.is inadequate, the pump is inoperable.
Both fire l
pumps being inoperable require these actions.
(1.0 pts.)
)
4 142 Additional Information:
i Technical
References:
TS-71 T.S.
15.3.14.A.3 Items to~be Included with Ouestion:
None Time Validation:
6.40 Recual Cycle:
N/A-K/A
Reference:
System:
086 Mode:
000 Number:
GOS Ratings:
RO:
3.0 SRO:
3.6
=
I.O l
Question Number:
057-02-003A Point Value:
978 i
Revision Number:
0 Approval Date:
02/22/89 l
Question Format:
W Question Type:
S l
Subject Area:
ADMINISTRATIVE SYSTEMS
' 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.
With Unit 1 at 100%, the following data is observed:
Channel 1
2 3
4 TH 599 598 598 600 TAVG 571 570 570 571 TC 543 542 542 543 Delta-T 56 56 55.9 57 NIS 100 99.5 99.8 100
-Calculate reactor thermal output.
Assume 100%
average delta-T is 56.4 Deg.
F.
b.
With pressurizer pressure normal, what value of Tavg would violate the safety limits?
i Points Earned i
L L
R Question No.:
057-02-003A Page 2 i
4 Answer:
Instructor Use.Only l
lj j
'a.
RTO,= (56 + 56 + 55.9 + 57) x 100% / 56.4 f
4 99.69%
.2%
(.5 pts) u i
b.
609'F (i 5'F)
(.*% pts.)
j
.6 J
121 j
i t
Additional Information:
Technical
References:
I REI-1.0 Section 5<.2 T.S.15.2 l
l.
Items to be Included with Ouestion:
None l
Time Validation:
6.10 I
Recual' Cycle:
N/A K/A
Reference:
' System:
015 l
Mode:
000 j
Number:
A1.01 i
Ratings:
RO:
3.5 SRO:
3.8 f
{
Question-Number:
057-02-017A Point Value:
1.0 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
E Subject Area:
TECHNICAL SPECIFICATIONS Task Number:
C6501 COT, P6511 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.
P6511 COT During any mode of plant operation, apply Technical Specification requirements in accordance with all action statements associated with the applicable Technical Specification.
Question:
Instructor Use Only The "A" condesate storage tank has to be removed from service due to chemistry results indicating high levels of sodium.
The "B" condensate storage tank has 8000 gallons of " good" water in it. Assume Unit 1 is shutdown for refueling.
a.
What must be done to the "B" tank prior to removing the "A" tank from service?
b.
Why?
I Points Earned j
l 4
Question No.: '057-02-017A Page 2 i
Answer:
Instructor Use:Only a.-
Lineup verified to the auxiliary feed water pumps (.33 pts.) and filled greater than 10,000 gal. (.33 pts) b.
Meets the operability requirements per Tech Specs
(.33 pts.)
Additional Information:
Technical
References:
Tech Specs section 15.3.4.A.2 LP 618 Limiting Conditions for Operation Items to be' Included with Ouestion:
None Time Validation:
2.00 Recual Cycle:
N/A K/A
Reference:
System:
061 Mode:
000 Number:
A1.04 Ratings:
RO:
3.9 SRO:
3.9
t 1
Question Number:
057-02-023A Point Value:
1.0 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
S l
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
)
You have just relieved the watch with a plant heatup in progress. While taking logs the operator notes the following data on the trend recorder; Time Temo.
0630 350*F 0640 372*F 0650 388'F 0700 410'F a.
What actions, if any, should be taken by the reactor operator?
b.
Explain.
1 h
l Points Earned i
1
-; Question No.:
057-02-023A Page 2
' Answer:
Instructor Use Only.
-i
- a.. Reduce the heatupLrate
.2 pts.
b.
Maximum heatup rate is 100*F/Hr.
- 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 Reaual Cycle:
N/A E/A
Reference:
System:
002 Mode:
020 Number:
GO5
i U
'.].;
I e-Name
///$(
- Ces, fp.,
l
//
1 Date T89-OO7:
LIMITS AND CONTROLS R99-(Mun (PhD EDDDotMT 4 (TITLE) l Instructions:
1.
Answer all questions on enclosed pages and show all calculations 2.
Do not discuss the questions or answers with anyone.
3.
Parsing grades are 80% overall;-70% individual section. grade.
l Section 1
Points Received-Section Point Value 17.9 17.9 Percentage Grade Overall Gradud by Date Reviewed by Examinee Date Prepared by Wm /A//f Date
.7-3 1.29 Reviewed by
?_
Date f - f /- f ?
Tec 1 Review w
- hN Date c)/2 3/fi Cu,r,rfculum D elopment r
Approved by 7/h m Date f
c/
/
7,-
TR-8.6.1
, (10-87)
__._____._.____m.
..e
. Exam Ouestion Number Question Number 1-01 051-01-049A 1-02 051-03-017A 1-03 043-03-010A 1-04 051-03-022A 1-05 055-02-060A 1-06 052-05-013A 1-07 051-06-002A 1-08 054-01-008A 1-09 055-01-029A 1-10 055-02-098A 1-11 031-03-001A 1-12 031-03-004A 1-13 051-02-040A 1-14 051-04-003A 1-15 052-01-011A 1-16 086-05-008A 1-17 086-01-006A 1-18 057-02-016A i
i 1
___z-__---
Question Number:
051-01-049A Point Value:
0.6 Revision Number:
0 Approval Date:
02/20/89 Question Format:
W Question Type:
S Subject Area:
REACTOR COOLANT SYSTEM Task Number:
CO230 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.
Question:
Instructor Use Only Unit 1 is shutdown; RCS temperature is 345'F and pressure is 380 psig; cooldown for repair of a crack downstream of 1CS-466BB (loop A main feedline-check valve first off) is in progress. RHR pump 1B is out of service for maintenance, t
a.
Is it permissible for the Maintenance Department to take RCP 1B out of service?
b.
Explain your answer.
i Points Earned l
I
Question No.:
051-01-049A Page 2 Answer:
Instructor Use only a.
Lyes.
(.2 pts.)
b.
Tech' Spec requirement 15.3.1.A.3'can be satisfied by the following 2 cooling loops:-
u 1.
RHR train A numo ind,EX
(.2 pts.)
2.
RCS loon B, its SG (1B), and RCP 1A.
(.2 pts.)
Additional Information:
Technical
References:
T.S' 15.3.1.A.
OP-4B OI-1 M202, Sh. 2 Items to be Included with Ouestion:
None Time Validation:
9.70 Recual Cvele:.N/A K/A
Reference:
System:
003 Mode:
000 Number:
G05 Ratings:
RO:
3.4 SRO:
3.8 1
-Question Number: '051-03-017A Point Value:
0.8
~ Revision Number:
0 Approval Date:
02/20/89 Question Format:
W Question Type:
C Subject Area:
RESIDUAL HEAT REMOVAL SYSTEM i
Task Number:
C0505 COT, C0509 COT i
Terminal Learnina Obiective:
'C0505 COT With the RWST no longer supporting the Containment Spray System, assess the effect of a loss of RHR on the Containment Spray System prior to losing NPSH to the 1
containment spray pumps.
C0509 COT During all modes of operation identify causes of interlocks, permissives, automatic functions associated with the RHR system without error.
Question:
Instructor Use Only A large break LOCA has occurred.
The RHR pumps, safety injection pumps, and' containment spray pumps have been aligned for recirculation from containment sump B.
Suddenly, RHR pump P10A trips due to a fault in its power supply breaker.
Which of the following actions should be taken by.the operator with respect to the containment spray system?
a.
Trip containment spray' pump P14A because it has the same power supply, b.
Allow containment spray pump P14A to take suction from the spray additive tank until it is empty, and then secure the pump.
c.
Stop containment spray pump P14A because suction from RHR pump P10A discharge is no longer available.
d.
Crosstie containment spray pump P14A suction to RHR pump P10B discharge.
1 Points Earned
Qusction No.
051-03-017A Page 2 Answer:
Instructor Use Only c.
(.8 pts.)
- 268, i
Additional Information:
Technical
References:
EOP-1.3 Items to be Included with Ouestion:
Nor.e Time Validation:
0.70 Recual Cvele:
N/A K/A
Reference:
System:
005 Mode:
000 Number:
K4.12 Ratings:
RO:
3.1 SRO:
3.7 l
I L
i l
Question Number:
043-03-010A Point Value:
0.6 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
S Subject Area:
RESIDUAL HEAT REMOVAL SYSTEM Task Number:
C0511 COT, C0907 COT Terminal Learninc Obiective:
C0511 COT During plant cooldown to cold shutdown conditions the operator must predict core reactivity affects of placing RHR in service in terms of potential dilution effects on i
the RCS.
C0907 COT Using available control room indications RECOGNIZE the effect of a loss of RCS flow on the pressurizer pressure control system without error to determine the status of the RCS and the ability to control pressure.
Question:
Instructor Use Only Dur3ng a cooldown to cold shutdown in preparation fo. v4 fueling, an RCS boron sample was taken 1/2 hour after placing RHR in service. RCS boron concentration had increased 50 ppm from the previous sample, which was taken just prior to placing RHR in service. The CVCS was not used to borate the RCS during this time period. Explain why RCS boron concentration increased.
Points Earned u_____________________________
1 Question No.: - 043-03-010A Page 2 Answer:
Instructor Use Only-The-RHR system boron concentration is greater.than RCS boron concentration (because the RHR system is borated to the RWST boron concentration by recirculation with the RWST prior to' securing RHR during a-heatup) during a cooldown to refueling and boration of the RCS when placing RHR.in service is expected. (.6 pts.)
Additional Information:
Technical
References:
OP-7A OP-7B
'ltems to be Included with Ouestion:
None Time Validation:
3.20 Resual cycle:
N/A K/A Referenet:
System:
005 Mode:
000 Number:
K5.03 Ratings:
RO:
0.0 SRO:
3.1
L Question Number:
051-03-022A Point Value:
1.0 Revision Number:
0 Approval Date:
02/20/89 Question Format:
W Question Type:- S Subject Area:
SAFETY INJECTION SYSTEM Task Number:
C0607 COT Terminal Learnina Obiective:
4
]
C0607 COT During all modes of operation and given a copy of EOP-0
)
apply Technical' Specifications and procedural requirements
]
for the SI system operation in accordance with EOP-0,
" Reactor Trip or Safety Injection".
Question:
Instructor Use Only You are in EOP-0 " Reactor Trip or Safety Injection" at step 30 during a Safety Injection situation, the following data were observed:-
Rx Core Secondarv Vessel Level: >29 feet SG Pressure: 1100 psig Thermocouple: 510*F SG I4 vel (A and B): 20%
ECs Containment PZR Level:
0%
Pressure: 11.5 psig RCS Pressure:
1125 psig TCWR:
520*F SI Pumps:
On a.
Based upon the above data, what action is required?.
-b.
Justify your answer.
Points Earned
i
~
1 Question No.:
051-03-022A Page 2 Answer:
Instructor Use Only a.
Secure both RCP's (.5 pts.)
b.
RCS subcooling is < 60*F for an adverse containment and at least one SI pump is running. (.5 pts.)
Additional Information:
Technical
References:
EOP-0 Items to be Included with Ouestion:
None Time Validation:
10.50 Recrual Cycle:
N/A K/A
Reference:
System:
000 Mode:
011 Number:
EK3.14 Ratings:
RO:
4.1 SRO:
4.2 1
Question Number:
055-02-060A Point Value:
4,4- /. 0 Revision Number:
0 Approval Date:
02/20/89 Question Format:
W Question Type:
S Subject Area:
STEAM GENERATOR SYSTEM Task Number:
C1314 COT, C2402 COT Terminal Learnina Obiective:
C1314 COT Durang all modes of operation, apply TS and procedure requirements associated with operation of the NIS in accordance with Technical Specification limits 15.3.5,
" Instrumentation System".
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 operating at 100% and the P-38B electric auxiliary feed pump out-of-service, Unit 2 trips.
Three hours later, the post-trip review is complete; and the Duty and call Superintendent (DCS) recommends to the Duty Shift Superintendent (DSS) to restart Unit 2.
All equipment operated properly during the trip.
I The DSS informs the DCS that since P-38B is out-of-service, Unit 2 cannot be started up.
The DCS states that a 7-day clock exists and the pump has only been out-of-service for 2 days, so the restart is authorized.
a.
Can Unit 2 be started up?
b.
Explain.
Points Earned l
' Question No.:
005-02-060A Page 2 Answer:
Instructor Use Only a.
No Unit 2 cannot be started up.
(.2 pts.)
I b.
Unit 2 cannot be taken critical unless all four auxiliary feedwater pumps are operable.
(bea pts) o%
Alternate answer: LCO only applies if the unit is already at power.
i 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 Cycle:
N/A K/A
Reference:
System:
061 Mode:
000 Number:
GOS Ratings:
RO:
3.3 SRO:
4.0 4
i f
I
Question Number:
052-05-013A Point Value:
1.0 e
Revision Number:
0 Approval Date:
02/20/89 Question Format:
-W Question Type:
S Subject Area:
AUXILIARY FEEDWATER SYSTEM
)
Task Number:
C4210 COT Terminal Learnina Obiective:
C4210 COT During all modes of operation analyze causes of interlocks, permissives, and automatic functions associated with operation of the AFW system without error.
Question:
Instructor Use Only i
A loss of off site power occurs during a severe 1
thunderstorm.
All systems are operating as designed.
The condensate storage tank high/ low level alarm annunciated.
Both CST levels are observed to be decreasing at a rate of one foot per minute.
a.
From the time of the alarm how soon must actions be taken?
b.
What soecific actions must be taken (and from which control board)?
Points Earned
7_
L-i i
. t
,(
. i f'
-Question No.:
052-05-013A-Page 2 a
Answer:
Instructor Use Only a.
Action must be taken 5.5 minutes from receipt of the: CST low level alarm.
(.4 pts.)
b.
Manually open.1 and 2.MOV-4006 on CO3
(.3 pts.) (SW supply to-the turbine AFW pumps).
Manually open MOV-4009 and 4016 on C01
(.3 pts.)
(SW supply to P38A and P38B.
117 Additional'Information:
Technical
References:
'M-217l Items to be Included with Ouestion:
Underlined the word each in response to a comment from shift.
Time Validation:
5.30 Reaual Cvele: =N/A K/A
Reference:
System:
061 Mode:
000 Number:
K4.01 Ratings:
RO:
3.9 SRO:
4.2
__L__A-__---_2
f 1
Question Number:
051-06-002A Point Value:
&,3 4 0 Revision Number:
0 Approval Date:
02/21/89 Question Format:
W Question Type:
S Subject Area:
SERVICE WATER SYSTEM Task Number:
C5302 COT l
l Igrminal Learninc Obiectly_g:
l C5302 COT During all modes of operation and given a copy of OI-70 l
apply TS and procedural requirements associated with the l
operation of the service water system in accordance with OI-70, " Service Water System Operation".
Question:
Instructor Use Only Both units are operating at 100% power with Service Water Pumps 32A and 32F out-of-service. The Duty Shift Superintendent instructs the Unit 1 RO to take Service Water Pump 32B out-of-service for routine maintenance, a.
Should service water pump 32B be taken out-of-service?
b.
Explain.
I Points Eayned 4
k
,y.
-Question No.:. 051-06-002A Page 2 Answer:
Instructors se~Only U
l a.
No.
'(.2 pts) b.-
Although Tech._ Specs. allow. continued 1 operation.for us to 24. hours with 3, service water pumps, OI-70 states.that at no-time.should all 3 pumps in a.given train be intentionally made inoperable. Pumps 32A, B
nd F are all powered from the same. train.
(
pts)
Alternate answer: This condition is not
. allowed by the!DCS' Handbook'.
160 Additional'Information:
Technical
References:
T.S.15.3.3.D.2.a OI-7 0 --
M-207 Sh.1 Items to be Included with Ouestion:
None
' Time Validation:
3.50 Recual Cvele:
N/A K/A
Reference:
System:
076 Mode:
000 Number:
G01 Ratings:
RO:
2.9 SRO:
3.1 i
_______________________m.
i l
l Question-Number:
054-01-008A Point Value:
1.5 Revision Number:
0 Approval Date:
02/21/89 Question Format:
W Question Type:
S Subject Area:
AC ELECTRICAL DISTRIBUTION i
Task Number:
C4301 COT, C4603 COT t
Terminal Learnina Obirigj;.iy_g:
-C4301 COT During all modes of operation and given TS 15.3.7, apply TS and procedural requirements associated with the AC electrical distribution system in accordance with TS 15.3.7, " Auxiliary Electrical System."
C4603 COT During all modes of operation, identify'causes of interlocks, permissives and automatic functions associated with SC without error.
Question:
Instructor Use Only Both units are operating at 100% power.
RHR pump 1P10B has been out-of-service for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Diesel Generator G01 auto starts due to a degraded voltage condition on 4.16 kv bus 1A05, but trips, and locks out due to an overcurrent condition. Assume no reactor trip and units stablized with bus 1A05 deenergized.
a.
What actions are required?
b.
Explain why these actions are required.
I J
I l
Points Earned
Question No.:
054-01-008A Page 2 3
l 1
Answer:
Instructor Use Only i
l a.
Unit 1 must be in Hot Shutdown within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
(0.5 pts) b.
Since G01 is inoperable operation can continue l
for 7 days if G02, and all safeguards equipment fed by G02, are operable.
RHR pump J
1P10B being out-of-service requires a shutdown and T.S.
15.3.0.A applies.
(1.0 pts) 159 Additional Information:
i l
Technical
References:
l T.S.
15.3.7.B.1.e T.S.
15.3.0.A Items to be Included with ouestion:
None Time Validation:
4.60 Recual Cycle:
N/A K/A
Reference:
System:
062 Mode:
000 Number:
A2.01 Ratings:
RO:
3.4 SRO:
3.9 1
4
_an-- _ - _ _ _ _ _ _
W.
Question Number:
055-01-029A Point Value:
1.0 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
E Subject Area:
ROD CONTROL SYSTEM Task Number:
C0104 COT, C1308 COT Terminal Learnina Obiective:
C0104 COT During all modes of operation and given a copy of OP-3B Appendix "A",
predict the effect of changing plant conditions on SDM in accordance with OP-3B Appendix "A",
" Shutdown Margin Calculation."
C1308 COT During a reactor startup, predict the effect of subcritical multiplication when changing core reactivity.
Question:
Instructor Use Only Unit 1 is operating at 100% power, equilibrium xenon conditions. Boron concentration is 780 ppm, Tavg = 570'F and Control Bank D rods are at 225 steps. Calculate the shutdown margin. (burnup =
1000 MWD /MTU)- (Show all work.)
i i
l Points Earned j
Question No.:
,055-01-029A Page 2 Answer:
Instructor Use Only Note: These calculations t:se.UIC16 data. Values may change with subsequent cycle data.
' Rod worth from present
-7977 pcm (.25 pts.)
rod position to all rods in position Most reactive stuck rod
+760 pcm (.25 pts.)
worth Power defect for 100%
+1375 pcm (.25 pts.)
yv ( I5 pcm)
-5842 pcm (.25 pts.)
( l5 pcm)-due to Power Defect used.
yg Additional Information:
Technical
References:
OP-3B App. A rev. 1 ROD book Items to be Included with Ouestion:
None Time Validation:
7.10 Recual Cycle:
N/A K/A
Reference:
System:
001 Mode:
010 Number:
A4.04 Ratings:
RO:
3.5 SRO:
4.1 i
OS E C PSA ygS es Unit OP-3B, Appendix "A" Date MINOR DSS Revision 1 10-29-84 SHUTDOWN MARGIN CALCULATION l
1.0 PURPOSE To determine the shutdown margin of the reactor when at power and when suberitical.
I 2.0 PRECAUTIONS & LIMITATIONS l
l 2.1 After shutdown from an at-power condition, the xenon concentration will eventually start to decrease, adding positive reactivity. This l
positive reactivity addition must not reduce the shutdown margin below that required by the Technical Specifications.
2.2 All reactivity data will be obtained from the appropriate unit's Reactor Operating Data Book and Xenon Tables.
2.3 Power defect will encompass the reactivity insertion from an at-power condition to no-load Tavg.
If the reactor is shutdown from a no-load j
),
condition, power defect will be O pcm.
2.4 Depending on the change in a given variable, the reactivity effect l
may be positive or negative, therefore ensure the correct sign (i) is circled to avoid confusion.
2.5 Control rod reactivity will be considered negative as rods are stepped inward from the all rods out position.
2.6 If the reactor is subcritical with any number of rods fully or partially withdrawn; the most reactive stuca rod worth must be considered in the shutdown margin calculation. The most reactive stuck rod worth is used even if that particular rod is not withdrawn.
This is done for conservatism and due to a lack of individual rod worth data. If the reactor is suberitical with all rods in the most reactive stuck rod worth is not applicable.
3.0 SHUTDOWN MARGIN CALCULATION FROM AN AT POWER CONDITION 3.1 Rod worth from present rod position to all rods in.
- 7#/7 7 pcm 3.2 Most reactive stuck rod worth
+
74 6 pcm 3.3 Power defect for
/66
% power
+ / 3 ~7 7 pcm 1/f T $' V2 pcm _t / [
j 3.4 Shutdown margin (sum of Steps 3.1, 3.2 and 3.3)
______.-________S.___
)
Question Number:
055-02-098A Point Value:
1.0
-Revision Number:
0 Approval Date:
02/21/89
. Question Format:
W Question Type:
C Subject Area:
REACTOR PROTECTION SYSTEM Task Number:.
C1106 COT
)
4 l
Terminal Learnina Obiective:
C1106 COT During all modes of operation, analyze the effect of a malfunction in the reactor protection system prior to violating Technical Specification 15.3.5, " Instrumentation
]
System".
Question:
' Instructor Use Only
. Unit 1 is at 100% steady state power.
TE 401A for channel 405' fails low.
The appropriate actions are taken.
Five hours later, power range channel N43 fails low.
The appropriate action the operator must now take is to; I
a.
put the appropriate bistables in trip per
[
ICP 10.2, then proceed to HSD within three j
hours.-
b.
enter into EOP-0 since the reactor has just tripped.
c.
put the appropriate bistables in trip per ICP 10.2 and continue operating.
d.
recover from the turbine runback; put the appropriate bistables in trip per ICP 10.2; then, proceed to HSD within three hours.
e.
stabilize after the turbine runback; then, proceed to HSD within three hours.
Points Earned
' Question No.:
-055-02-098A Page 2 Answer:
Instructor Use Only e.
(1.0; pts.)
l
. Additional Information:
Technical
References:
T.S.
15.3.5 ICP 10.2 Logic Sheets 15,16 T.S.
15.2.3 Items to be Included with Ouestion:
None Time Validation:
7.20 Recual Cycle:
N/A K/A
Reference:
System:
012 Mode:
000 Number:
K4.01 Ratings:
RO:
3.7 SRO:
4.0 l
LL______.
i Qusstion'Numbar:
031-03-001A Point Valus:
ev6 0.1 i
Revision Number:
O' Approval Date:
02/21/89 Question Format:
W Question Type:
S o.
l Subject Area:
EMERGENCY TASKS Task Number:
CO225 COT, C7028 COT Terminal Learnina Obiective:
CO225 COT During an emergency involving a reactor trip from power operation recognize the need to maintain subcooling margin on natural circulation in terms of its effect on core
. cooling and in terms of procedure applicability.
C7028 COT During an accident or emergency condition involving a steam generator recognize multiple casualties so they may be identified and their priorities established according to EOP, Emergency Contingency Actions.
Question:
Instructor Use Only With Unit 2 at 75% power, a safety injection and reactor trip. occurred and the immediate actions of l
EOP-0 " Reactor Trip or Safety Injection," are completed. The following statements summarize key indications-that have been noted:
1.
The RCS is losing. inventory, > 200 gpm.
2.
One steam generator is depressurizing uncontrollably.
3.
Air ejector radiation alarms indicate a tube rupture.
4.
DTA notifies you the critical safety functions status trees indicate at transition to H-5
" Response to Steam Generator Low Level," a yellow condition.
Which statement (1, 2,
3, or 4) must be given first priority for remedial actions?
Points Earned i
i l
1
Question No.:-
031-03-001A Page 2 Answer:
Instructor Use Only.
.8 Statement 2.
(sF pts.)
078 Additional Information:-
Technical
References:
EOP-0, Reactor Trip or SI EOP-2'" Symptoms or Entry Conditions" Items to be Included with-Question:
None Time Validation:
3.20 Recual Cvele:
N/A K/A
Reference:
System:
000 Mode:
040 Number:
Gil l'
1,
' Question Number:
031-03-004A Point Value:
1.8 Revision Number:. O Approval Date:
02/21/89
' Question Format:
-W Question Type:
C Subject Area:
EMERGENCY TASKS Task Number:
C4306 COT, C7032 COT Terminal Learnina Obiective:
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.
C7032 COT Recognize the purpose and applicability of each EOP.
Question:
Instructor Use Only From 100% power, the' reactor has suffered a trip, safety injection and a loss of offsite AC power.
The immediate actions are completed and prior to transitioning out of EOP-0, the operator notes these indications:
Parameter H
Units TH(WR) 528 538 Dag F TC(WR) 510 538 Deg F Core T/C's 538 Deg F RCP's Off Off Pzr Pressure 1600 Psig Pzr Level 10 SG Level 85 330 Inch AFW Flow 120 90 GPM SI Pumps On RHR Pumps On "A" SG Pressure 450 psig and decreasing "B" SG Pressure 850 psig and stable 1.) The transition to be made is to a.
continue into EOP-2, " Faulted Steam Generator Isolation."
b.
continue into ECA-2.1, " Uncontrolled Depressurization of Both Steam Generators."
c.
continue into CSP-H.1, " Response to Loss of Secondary Heat Sink."
.d.
continue into EOP-1.1, "SI Termination."
e.
continue into EOP-3, " Steam Generator Tube Points Earned Rupture."
___m_______.____.m_____
____.______m.-
-Question No;:~ 031-03 004A Page 2-
': Question:.(continued)'
Instructor Use Only 2.' ) Explain your cho' ice.
V
L. '
. Question No.:
.031-03-004A.
-Page 3
.<t Answer:
Instructor Use Only an. '
(1.0 pts.).
b.
With'"A" S/G pressure decreasing and below-saturation for-"A" loop T (indication e,
- requires transition to EOP-2).
' Alternate answer: "A"'S/G pressure decreases uncontrollably (requires transition to EOP-2).
(0.8 pts.)
094 l
Additional Information:
Technical
References:
EOP-0 EOP-2 Items to be Included with ouestion:
None Time Validation:
4.20 Reaual cvele:
N/A
- K/A
Reference:
System:
000 Mode:
040 Number:
EK3.04 Ratings:
RO:
4.5 SRO:
4.7 i
i Question Number:
051-02-040A Point Value:
0.6 Revision Number:
0:
Approval Date:
02/21/89
{
. Question Format:
W Question Type:
E j
Subject Area:. HEAT TRACING SYSTEMS l
l Task Number:-
C0424 COT, C4702 COT 1
1 Terminal Learnina'Obiective:
C0424 COT During all modes of operation apply TS and procedural requirements for CVCS operation without error.
C4702 COT During all modes of operation apply-Technical Specifications and procedural requirements associated with the heat tracing system without error.
-Question:
Instructor Use Only While operating Unit 1 at 100% power, alarm B4-11, on panel C01, " Boric Acid Heat Tracing" comes in.
An auxiliary. operator reports that the Boric Acid Heat Tracing Recorder (TR-4177) shows circuits 93, Boric acid line to Unit 1 blender including FT-110 and FCV-110A (boric acid to blender), and 135, emergency borate to VCT outlet, are both low.
l Further' investigation shows that both trains have shorted out on both circuits.
i What' limitations are placed on continued operation of the plant and why?
Be specific.
i l
Points Earned b
4 Question No.:
051-02-040A Page 2 Instructor Use Only Apswer:
we b re-u/re / O ve /i/
\\
- e. a u f s.re -l (13 C l3Y) l3s H e f._j of be f frecakj
- n.I S/ O wi u.
3 fn ap on s es. c,. ~ wt rs isu. a. o.y. rtuak 3. f. !C 3"A we 4he inocerability e f - both heat-treeinc-- circui-ts*' # #
d,gg,y [. 3 ) (75 / f Iv,ef-)
_(0.2 pt&.) Disces Uriit 1 in a ze hour LCC (0.2'
-- bil) 555
'3 5f 5 f_
"' F
- C,I/ S/C v//v N A" #[
-wy vuo.
sv.s
- p.. i disca+y. (. 3) ( 75,5,,,)/
098 Additional Information:
Technical
References:
T.S.
15.3.2.".5 T.S.
15.3.2.D.4 T.S.
15.3.0 ARBC01 Panel B4-11 STPD 7.3 40P-6E Rev. O TRHB 10.6 Items to be Included with Ouestion:
None Time v'alidation:
8.80 Recual Cycle:
N/A K/A
Reference:
System:
004 Mode:
010 Number:
K5.07 Ratings:
RO:
3.1 SRO:
3.4 1
i 1
1
Question Number:
051-04-003A Point Value:
1.0 Revision Number:
0 Approval Date:
02/21/89 Question Format:
W Question Type:
S Subject Area:
LIQUID RADWASTE SYSTEM Task Number:
C4801 COT
. Terminal Learnina Obiective:
C4301 COT During all modes of operation and given a copy of OP-9A apply TS and procedural requirements associated with the liquid waste system in accordance with OP-9A, " Liquid Waste Process System Operation".
Question:
Instructor Use Only Chemistry informs you that the "A" waste distillate tank (WDT) should be transfered to the "B" WDT via the polishing demineralized for further cleanup.
At 1315 you, inform chemistry that the transfer is complete and the transfer pump (P135) is secured.
At 1530 chemistry samples the "B" WDT and reports that it is below the acceptable liquid effluent discharge limit.
At 1600 chemistry brings you a discharge permit.
Should you authorize the discharge permit? Explain j
your answer.
Points Earned
Question-No.:
.051-04-003A Page 2 Answer:
Instructor Use only.
No.
(.5 pts.)
-Since it has been longer than 2-hours between completion of the transfer, the "B" waste distillate. tank must be recirculated prior to sampling.
(.5 pts.):
063 Additional Information:
Technical
References:
OP-9A pg. 2 & 4 TS Table 15.7.6-1 NOTE 2 Items to be Included with Ouestion:
None
' Time Validation:
5.40 Recual cyc1A:- N/A K/A
Reference:
Syst'em:
068 Mode:
000 Number:
'A2.02 f
\\
Question Number:
052-01-011A Point Value:
1.0 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
S Subject Area
, FIRE PROTECTION SYSTEM Task Number:
C6101 COT, C6103 COT Terminal Learninc Obiective:
C6101 COT As required by periodic TS testing; as part of the watch standing duties and, as directed by shift supervision, apply TS and procedural requirements associated with operation of the fire protection system as measured by TS compliance.
C6103 COT In an evaluation setting, given a plant location, relate the type of fire suppression used in a guven area without error.
Question:
Instructor Use Only 4
Following performance of Bi-Monthly Smoke Detection System Integrity Test TS-77, the following discrepancies are reported:
C901 South Wall Containment Spray Pump Room -
D2DA of the detectors operated; C903 North of Component Cooling Water Pumps -
XS-5045, XS-5049, XS-5050, and XS-5052 failed to operate; C907 East of Unit i Volume Control Tank - XS-5059 and XS-5063 failed to operate; and all other detectors operated properly.
The DSS directo that an hourly fire watch l
inspection be established in zone C901. Is the action recommended by the DSS adequate? Explain.
Points Earned L____
l 1
1 Question No.:
052-01-011A' Page 2 Answer:
Instructor Use Only No. (.2 pts.)
j r
Since more than 25% of the detectors in zone C903 i
are inopi.rable, an hourly fite watch must be established in this zone. (.8 pts.)
Additional Information:
Technical
References:
T.S.
15.3.14.D i
TS-77 rev. 5 Standing Order PBNP 4.12.7 rev. 1 Items to be Included with Ouestion:
None Time Validation:
11.50 Recrual cycle:
N/A K/A
Reference:
System:
086 Mode:
000 Number:
G05
.j Ratings:
RO:
3.0 SRO:
3.6 l
l l
l l
l
Question Number:' 086-05-008A Point'Value:
1.2 Revision Number:.
O Approval Date:
02/21/89 t
Question Format:
W Question' Type:
C
- Subject Area:~ SRO Task Number:
C1006SRO i
Terminal Learnina Obiective:
' C1006SRO During abnormal / emergency condition and given' CSP's recognize' critical safety functions in accordance with CSP's.
Question:
Instructor.Use Only I
Assume that a reactor trip and safety injection has progressed such that you have entered EOP-1, " Loss of Reactor or Secondary Coolant."
The DTA has just performed an evaluation of the critical safety function status trees.
The results of his evaluation are as follows:
Subcriticality - Green Path Core Cooling - Orange Path Heat Sink - Yellow Path Integrity - Green Path Containment - Orange Path Inventory - Yellow Path Which of the following procedures should you use to proceed with operation?
a.
EOP-1, " Loss of Reactor or Secondary Coolant" b.
CSP-C.1, "Responae to Inadequate Core Cooling" c.
CSP-H.5, " Response to Steam Generator Low 1
Level" d.
CSP-Z.1, " Response to High Containment Pressure" e.
CSP-C.2, " Response to Degraded Core Cooling" f.
CSP-I.3, " Response to Voids A:. 7eactor Vessel" l
l Points Earned I
l l
Question No.:
086-05-008A
_Page 2 Answer:
Instructor Use only e.
(1.2 pts.)
ST-88-15 719 Additional Information:
Technical
References:
STs 1, 2,
3, 4,
5,
& 6 Items to be Included with Ouestion:
None Time Validation:
1.00 Recual Cvele:
N/A K/A
Reference:
System:
000 Mode:
011 Number:
Gil l'
l l
_. _ _ _ _________________ _ J
j I
Question Number:
086-01-006A Point Value:
1.0 Revision Number:
0 Approval Date:
02/21/89 Question Format:
W Question Type:
E Subject Area:
TECHNICAL SPECIFICATIONS Task Number:
P0319 COT, P0319SRO Terminal Learnina obiective:
P0319 COT During all modes of operation and given Technical Specifications, apply Tech specs for safety limits, safety settings and limiting conditions for operation without arror.
P0319SRO During all modes of cparation and given Technical Specifications, apply Tech Specs for safety limits, safety settings and limiting conditions for operation without error.
Question:
Instructor Use Only A containment purge exhaust valve boot fails, resulting in a leak rate of 300,000 scem out of the containment. It will take approximately one week to fix the boot, and the leakage cannot be reduced.
Assuming the plant is operating at 100% power, what actions affecting plant operation, if any, must be taken?
i l
l Points Earned J
l I
l Question No.:
086-01-006A
.Page 2 Answer:
Instructor Use Only l
Hot shutdown within three hours (0.5 pts.) and cold shutdown within 48' hours (0.5 pts.)
q Additional Information:
l Technical
References:
)
Tech Specs sections 15.4.4.II.B.1, 15.3.6.C and 15.3.0.A TS-10 Hatch Test LP 692 Technical Specifications Items to be Included with Ouestion:
None Tine Validation:
5.80 Recrual Cycle:
N/A K/A
Reference:
System:
103 Mode:
000 Number:
K3.02 Ratings:
RO:
3.8 SRO:
4.2 l
Question Number:
057-02-016A-Point Value:
1.0 Revision Number:
0 Approval Date:
02/22/89 Question Format:
W Question Type:
S Subject Area:
TECHNICAL SPECIFICATIONS Task Number:
C6501 COT, P0319SRO 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.
P0319SRO During all modes of operation and given Technical Specifications, apply Tech Specs for safety limits, safety settings and limiting conditions for operation without i
error.
Question:
Instructor Use only A plant heatup is in progress in accordance with j
OP-1A " Cold Shutdown to Low Power Operation" step 4.8.
Everything is ready to exceed 350*F. At i
340*F, the "A" motor driven auxiliary feed pump is declared OOS due to water in the oil.
a.
Can this heatup exceed 350'F?
)
b.
Explain l
Points Earned L
R
[-
l Question'No.:
057-02-01oA Page 2 Answer:.
Instructor Use Only l
i a.
Yes
.2 pts.
b.
One steam generator must be operable prior to exceeding 350*F-(With one auxiliary feed pump q
available this is still met - optional)
.8 pts.
1 Additional Information:
Technical
References:
Tech specs section 15.3.1.A.2 and
. basis on page 15.3.1-3b LP 692 Technical Specifications Items to be Included with Ouestion:
None Time Validation:
9.00 Recual Cycle:
N/A K/A
Reference:
System:
039 Mode:
000 Number:
G06 l
Ratings:
RO:
0.0 SRO:
3.1 l
t)
L 1
l Name Date T89-009: M N.s49B (FOR' APPROVAL (TITLE) l Instructions:
1.
Answer all questions on enclosed pages and show all calculations.
2.
Do not discuss the questions or answers with anyone.
3.
Passing grades are 80% overall; XD0%2nddxmbdostosecedxurJgendec t
l 1
l 1
2 1
2 Section (RO)
(RO)
Points Received hg 10.0 10.J Section Point Valud j
Percentage Grade i
Overall Graded by Date Reviewed by Examinee Date Prepared by
/[/Zeh /d/M6 Date d2-prW/ff i
Reviewed by Date
?-av-st Te al Review
. Datie Ocf-fab b Curriculum
~velopment 4
Approved by The Dat N
'w-v(r-e.gwy p,
TR-8.6.1
.(10-87)
- {.
}
l
.. c m
Exam Ouestion Number Ouestion Number 6
1-01 052-03-011A 1-02 053-01-008A 1-03 053-01-005A 1-04 053-02-018A' i
1-05 055-01-011A l
1-06 053-01-009A 1-07 053-01-014A 08 053-01-006A 1-09 055-02-022A 1-10
'052-03-017A 1-11 031-03-140A 1-12 051-03-014A 1-13 031-03-094A 1-14 051-06-024A 1-15 055-02-059A i
1-16 053-06-009A
,2-01 055-02-030A 2-02 031-03-059A 2-03 055-02-020A 2-04 055-02-023A 2-05 053-02-013A 2-06 055-02-018A 2-07 031-03-066A 2-08 086-05-001A 2-09 043-02-004A 2-10 052-05-001A 2-11 031-03-064A 2'12 053-02-016A 2-13 053-02-014A 2-14 051-03-010A 2-15 031-03-147A i
4 k
i g; 3.
?
t-Ah 4,,
ft jf 1
..4.s..a..
.__,e-a-e a h.
(
b Section 1 I
s h.
- [.
f
-k_
f
]
- r[
1 i
1 1
1 J
1 s.
STUDENT REFERENCE Scenario - ST-88-12 Plant Historv Prior to Initietine Event Approximately 5 minutes ago, Unit I was operating at 100" power, beginning of life, steady state with the Gas Turbine out of service. Xenon was at equilibrium. All plant controls were in auto / normal for this plant condition.
I i
Initiating Event Several minutes ago, indicated on the bottom. turbine runback occurred. Control rod D-7.
a Ooerator Actions Taken i
Shortly after the turbine runback when plant conditions had stabilized, operators entered AOP-6A. Immediate actions - automatic have been verified. Immediate actions - manual have been completed l
to step 5.1.2.
'i Procedure and Steo in Affect Operators are entering step 5.2 of AOP-6A.
1 e
b
Question Number:
052-03-011A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89
)
~
Question Format:
W Question Type:
S Subject Area:
MAIN TURBINE GENERATOR Task Number:
C3118 COT, C3122 COT Terminal Learnino Obiective:
C3118 COT During conditions of turbine operation at power ASSESS between main turbine operation with " impulse in" and
" impulse out" in terms of turbine load control with varying steam conditions without error.
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.
Question:
Instructor Use Only a.
If a rod drop occurs at the current power level and conditions, what would final turbine load be (in %) when conditions stabilize?
b.
Explain why.
Points Earned e
.-. ::2.
--- z : - - - - -
Question No.: -052-03-011A Page 2 i
\\"
Answer:
Instructor Use Only a.
80%
(.4 pts.)
b.
The load reference runback would reduce l turbine reference to 80.0% due to the NIS Rod Drop Signal.
(.6 pts.)
ST-88-12 628 Additional Information:
i l
Technical
References:
Logic Sht. 16 TRHB 13.11 Items to be Included with Ouestion:
None i
Time Validation:
4.60 Recual Cycle:
N/A j
K/A
Reference:
System:
045 l
Mode:
000 Number:
K4.12 Ratings:
RO:
3.3 SRO:
3.6 I
, - *,. t N 3
4 p
+
?> A n,
1
q Question Number:
053-01-008A Point Value:
- 0. 4 '
Revision Number:
0 Approval Date:
02/23/89,
Question Format:
W Question Type:
S Subject Area:
ROD CONTROL SYSTEM Task Number:
C0121 COT, C0126 COT Terminal Learnina obiective:
~
C0121 COT During a sudden load decrease from 100% power, discriminate between plant responses when the rod control system is in
)
automatic and when the rod control system is in manual,
y without error.
C0126 COT During any plant operations involving rod laovement, diagnose a stuck rod or malfunctioning position indication in accordance with REI #7.
Question:
Instructor Use Only Explain whether a rod drop has or has or has not occurred.
gl~Y Points Earned 4
i
~
7:
- - - - ' = = - - - = = = = - = = - - - - - - - -
- Question'No.
~ 053-01-008A Page 2 l
l Answer:
Instructor Use only l
No alarms or~ indications present for an actual j
dropped rod.
(.4 pts.)
4 ST-88-12 640 Additional Information:
Technical
References:
TRHB 13.8 AOP-6A Logic Sht. 16 Items to be Included with Ouestion:. None Time Validation:
6.30 Recual Cycle:
N/A K/A
Reference:
System:
001 Mode:
000 Number:
K4.01 i
Ratings:
RO:
3.5 SRO:
3.8 I
L i
i
(
p
~
1 f?
i i
l Question Number:
053-01-005A Point Value:
0.8 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
ROD CONTROL SYSTEM Task Number:
C0102 COT, C0121 COT
{
Terminal Learnina Obiective:
i 4
C0102 COT While operating with rod motion possible from either manual I
or automatic means, assess causes of interlocks, f
permissives and automatic functions associated with the rod I
control system without error.
C0121 COT
.During a sudden load decrease from 100% power, discriminate between plant responses when the rod control system is in automatic and when-the rod control system is in manual, without error.
Question:
Instructor Use Only If this event had happened with control rods in manual, would the final values for the following parameters be GREATER THAN, LESS THAN, or EQUAL TO the final values with rods in auto?
a.
Tavg I
b.
Steam flow c.
Pressurizer level d.
Generator load (MWe) l
?'
Points Earned l
lv I!
1 i
Qusstion No.:
053-01-005A.
Page 2 l-l Answer:
Instructor Use Only a.
GREATER THAN (.2 pts.)-
b.
GREATER THAN (.2 pts.)
c.
GREATER THAN (.2 pts.)
d.
EQUAL TO
(.2 pts.)
ST-88-12 641 Additional Information:
Technical
References:
TRHB 13.8, 13.9 1
Items to be Included with Ouestion:
None Time Validation:
1.50 Recual Cycle:
N/A K/A
Reference:
System:
001 Mode:
000 Number:
K1.04 Ratings:
RO:
3.2 SRO:
3.4 2;.
-94,&
L Question Number:
053-02-018A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
REACTOR PROTECTION SYSTEM Task Number:
C1102 COT, P1103 COT Terminal' Learnina Obiective:
C1102 COT During all plant oper'ating 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, sithout error.
P1103 COT During normal operation with the reactor trip breakers closed, monitor this reactor protection system by recording all indicators, alarms, status switch positions, recorders and computer points related to parameters of the reactor protection system.
Question:
Instructor Use Only a.
What effect did the runback have on the OT deltaT setpoint?
i b.
Explain (include all parameters that changed the setpoint after the runback was completed).
l
?
Points Earned
=
T;
~~~-~~~
- = '
[.
l-1
. Question No.:
053-02-018A Page 2 1
Answer:
Instructor Use Only a.
Increased the setpoint.
(.2 pts.)
b.
Tava droceed which caused additional credits l
to the setpoint.
(.4. pts.)
1 f(deltas) cenalty chanced due to the large negative delta $ (added penalties).
(.4 pts.)
ST-88-12 633 Additional Information:
Technical
References:
TRHB 13.3 Items to be Included with Ouestion:
None Time Validation:
2.10 Recual, Cycle:
N/A K/A
Reference:
System:
012 Mode:
000 Number:
G10 Ratings:
RO:
3.7 SRO:
3.8 Nf E
l Question Number:
055-01-011,A Point Value:
0.5 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
ROD OONTROL SYSTEM i
Task Number:
P0103 COT, PO425 COT Terminal Learnina Obiective:
P0103 COT During all modes of operation and given OP-3B, Appendix "A", " Shutdown Margin Calculation", perform shutdown margin calculations without error.
PO425 COT During all modes of operation and given a copy of OI-1, control seal injection flows in accordance with OI-1,
" Reactor Coolant Pump Operation Guide".
Question:
Instructor Use Only What is the chance in shutdown margin immediately after this event?
Assume control bank D was initially at 213 steps at 100%, BOL (3000 MWD /MTU).
4 I
l 1 -
N i-Points Earned i.
h '.
l I
. Question No.:
055-01-011A Page 2 Answer:
Instructor Use Only No change,-the shutdown margin is the same
(.5 Pts)
Alternate answers:
1.
[ NOTE:
SDM = -(Rod worth from present to all i
rods in) + most reactive stuck rod worth +
l power defect deltaSDM = SDM (final) - SDM (initial)
=
0 pcm)
SDM initial:
(-8270 + 14) + 760 + 1460 =
-6036 pcm SDM final:
(-8270 + 209) + 760 + 1265 =
-6036 pcm deltaSDM = 0 pcm (
50 pcm) 1.
O pcm difference because the change in reactivity due to power defect was exactly offset by the change in reactivity due to change in rod height.)
ST-88-12 630 4
Additional Information:
Technical
References:
)
OP-3B, Appendix A ROD 4,5,7 Items to be Included with Ouestion:
None Time Validation:
4.30 Recual Cycle:
N/A K/A
Reference:
System:
001 Mode:
010
)
Number:
A4.04 Ratings:
RO:
3.5 SRO:
4.1 h
t L
j l~
Question Number.:.053-01-009A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
C Subject Area:
ROD CONTROL SYSTEM Task Number:
C0102 COT, C0126 COT I
Terminal Learnina 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.
C1126 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 When the operator first attempts to determine if the RPI channel is malfunctioning by moving the affected rod, Tavg will a.-
decrease, since the RPI channel is failed.
b.
increase, since the RPI channel is failed.
c.
not change, since the rod is on the bottom.
d.
not change, since the rod is stuck.
1 e.
not change until the urgent failure is reset.
1 i
l' 4 ',
fu Points Earned
- ..:. =
==.;==.=x-----====----
i Question No.:
053-01-009A Page 2 l
I
~
Answer:
Instructor Use'Only a.-
(1.0 pts.)
ST-88-12 632 Additional Information:
Technical
References:
AOP-6A, 6B Items to be Included with Ouestion:
None Time Validation:
2.40 Recual-Cycle:
N/A K/A
Reference:
System:
001 Mode:
000 Number:
A2.03 Ratings:
RO:
3.5 SRO:
4.2 g,;hff,
,.Y h.
itd%::
t 4
!.I '
i L
\\
4
~
Question Number:
053-01-014A Point Value:
0.6 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:l ROD CONTROL SYSTEM Task Number:
C0105 COT, C0120 COT 1
)
Terminal Learnina Obiective:
1 C0105 COT' During normal power operations with.the rod control system in automatic assess the response of the rod control system to change plant conditions. ' Assessment of expected rod speed and direction as the Tref - Tavg error exceeds 1.5 Deg F in either polarity is required, 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 a.-
If the scenario had continued and one of the steam dumps remained open, how would the RCS. temperature response have been different?
b.
Explain how the control rods respond to the continued steam demand from the steam dump valve.
.c 4
Points Earned l
Question No.:
053-01-014A Page 2 Answer:
Instructor Use Only I
1 a.
RCS temperature would degrease below Tref.
(.3 pts.)
.b.
Rods would not sten out to increase temperature to Tref due to the rod block in effect.
(.3 pts.).
ST-88-12 646 Additional Information:
1 Technical
References:
Logic Sht. 16 TRHB 13.8 TRHB 13.3 Items to be Included with Ouestion:
None Time Validation:
4.00 Recual Cycle:
N/A K/A Referenqg:
System:
001 l
Mode:
050 J
Number:
K4.01 Ratings:
RO:
3.4 SRO:
3.8 4
l
Question Number:
053-01-006A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
ROD CONTROL SYSTEM Task Number:
C0102 COT, P1201 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.
P1201 COT During all modes of operation and given T.S.
15.3.10, monitor the RPI system in accordance with T.S.
15.3.10,
" Control Rod & Power Distribution Limits".
Question:
Instructor Use Only.
Suppose an identical event, but with rod H-8, was now to occur from current conditions.
a.
What would be the final control Bank D rod height after conditions stabilize?
b.
(SRO only '89 requal exam) Explain whether sustained power operation would be or would not be allowed?
i 1
l g.
a l'
r 4
Points Earned l>
l
~
l Question No.:
053-01-006A Page 2 Answer:
Instructor Use Only l
a.
149 steps.
(.5 pts.)
(alternate answer:
same height as now) b.
Sustained power operation may continue per Tech Specs with 2 RPI channels failed as long i
as monitoring per Tech. Specs. 15.3.10.D.3 is satisfied.
(.5 pts.)
ST-88-12 649 Additional Information:
Technical
References:
Logic Sht. 16 Tech Specs 15.3.10 Items to be Included with Ouestion:
None Time Validation:
9.70 Reaual Cycle:
N/A K/A
Reference:
System:
014 i
Mode:
000 Number:
K1.01 Ratings:
RO:
3.2 SRO:
3.6
+
l
, ~
>F N
e
l
~
Question Number:
055-02-022A Point Value:
0.8 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
ROD CONTROL SYSTEM Task Number:
C0430 COT, P0105 COT Terminal Learnina Obiective:
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.
P0105 COT During normal power operations and given a copy of Technical Specifications, operate control rods to shape axial power without violating Technical Specification 15.3.10, " Control Rod and Power Distribution Limits".
Question:
Instructor Use Only (RO only) At the current conditions, it is determined that the axial. flux difference value is not acceptable at this power level.
a.
What is the minimum axial flux difference acceptable at this power level?
b.
What control board manipulations could be done in order to achieve an acceptable axial flux difference at this power level? (two required) l l
, ;f a
3
+, '
Points Earned
{L
... - -...,.. ~.
,,,4 LQuestion'No.:
055-02-022A Page 2 Answer:
Instructor Use.Only a.
-14 (i 1) at 86% power.
(.2 pts.)
b.
- 1. Control Rods must be withdrawn in manual..
- 2. Boration must be performed.
- 3. Reduce load.
Any two of these required for full credit, L
.(.3 points each)
ST-88-12 643 Additional Information:
Technical
References:
T.S.
15.3.10 TRHB 13.8 OP-3A-Items to be Included with Ouestion:
None Time Validation:
2.70 Recual Cycle:
K/A
Reference:
System:
001 Mode:
000 Number
- A4.02 Ratings:
RO:
4.1 SRO:
3.9 "A"
l
'l-?l h
m -
4
~
i The following questions DO NOT refer to.th's conditions of the scenario, but are only using the simulator for an additional reference.
1,
=
0 P
l
.+
D-g W
g
4 Question Number:
052-03-017A Point Value:
0.7 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
MAIN TURBINE GENELATOR Task Number:
C3108COr, C3405 COT 3 Terminal' Learnina Obiective:
C3108 COT During plant operating conditions that require a turbine trip DIAGNOSE a fai3ure of the turbine to trip when required without error using available control board indications.
C3405 COT During conditions of normal power operation with the EHC system operating in automatic mode ASSESS the cause of alarms, interlocks, and automatic functions of the EHC system without. error.
Question:
Instructor Use Only Unit 1 is shutting down for refueling and reactor power is at 6%.-
The main generator breaker is opened and turbine speed increases rapidly to 1893 rpm.
a.
Explain why the turbine should or should not trip (include applicable setpoints).
b.
Wh'at actions should be taken as turbine speed continues to increase?
.c.
i va a
Points Earned i
u b
Question No.:
052-03-017A Page 2 Answer:
Instructor Use Only b.
Should trip due to overspeed at 104% (1872 rpm). (0.45 pts.)
c.
Manually trip the turbine from the control board.
(0.25 pts.)
244 Additional Information:
Technical
References:
TRHB 13.11 PG 10 OP-3A Logic Sh. 3 Setpoint Documents 15.1 Items to be Included with Ouestion:
None Time Validation:
4.60 Recual Cvele:
N/A K/A Re'ference:
System:
045 Mode:
000 Number:
K4.11 Ratings:
RO:
3.6 SRO:
3.9 1,..
,t
Def Question Number:
031-03-140A Point Value:
977 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
C Subject Area:
REACTOR COOLANT SYSTEM Task Number:
CO229 COT Terminal ' Learnina Obiective:
CO229 COT Considering accident conditions in which primary inventory is lost, assess various means of core cooling as addressed in CSP-C.1, " Response to Inadequate Core Cooling" in terms of their effectiveness and potential hazards.
Question:
Instructor Use Only Following a transient in which PCV-430 stuck open, and MOV-516 failed to close, these readings are obtained in the Control Room:
Secondq;2 A.
3 Jnits SG Pressure 850 850 psig SG NR 55 50 AFW 10
'20 gpm E.QE Tavg
<530
<530 Deg F Pressure 850
'890 psig TCWR 526 525 Deg F Thermocouple 725 725 Deg /
RCP off off Vessel Level 18 17.5 Feet CTMT Pressure 4.0 psig Subcooling
>50 Superheat Deg F Meter 1.
Assuming none of these pumps are running, the best pump to start would be; a.
a second charging pump.
b.
a reactor coolant pump.
c.
a safety injection pump.
d.
a residual heat removal pump.
F yYF ~ g Y
1 Points Earned j
(
- J Question No.:
031-03-140A Page.2
.]
' Answer:
Instructor Use Only
.I
' 1.
c
(<F pts.)
j i
i Additional Information:
)
1 1
Technical'
References:
CSP-C.1 Items to be Included with Ouestion:
None Time Validation:
3.90 Recual Cycle:
N/A
' K/A
Reference:
System:
074 Mode:
074 Number:
EA2.01 4
t n'
s 4
Question Number:
051-03-014A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
C Subject Area:
CONTAINMENT SPRAY SYSTEM Task Number:
C1910 COT, C1911 COT Terminal Learnina Obiective:
C1910 COT
'During emergency operations and given a copy of EOP-0 apply TS and procedural requirements associated with the containment spray system in accordance with EOP-0,." Reactor Trip or Safety Injection".
C1911 COT During all modes of operation identify causes of interlocks, permissives, and automatic functions associated with operation of the containment spray system, without error.
Question:
Instructor Use Only A large LOCA occurs on Unit 1 during full power operation.
At time t=0, an SI signe.1 is generated; at time t=30 seconds, a containment spray signal is generated.
The containment spray system components will operate in the following sequence l
a.
t=0, spray pumps A and B start; t7 30sec, spray discharge valves 860A, B,
C, D open; t = 2 min, 30sec, NaOH addition valves 836A and B open.
b.
t = 30sec, spray discharge valves 860A, B,
C, D open; t = 40sec, spray pumps A and B start; t = 2 min, 30sec, NaOH addition valves 836A and B open.
c.
t=0, spray discharge valves 860A, B,
C, D
open; t = 20sec, spray pumps A and B start; t = 2 min, NaOH addition valves 836A and B open.
-d.
t = 30sec, spray pumps A and B start; t = 40sec, spray discharge valves 860A, B,
C, D open; my t = 2 min, 30sec, NaOH addition valves 836A and B open.
a-W e.
t = 10sec, spray pumps A and B start; gigp%
t = 30sec, spray discharge valves 860A,.B, C,
D open; Points Earned t = 2 min, 30sec, NaOH addition valves 836A and B open.
i
4 v.
' Question No :
051-03-Oi4A Page 2 Question:- (continued)
Instructor'Use Only.
>{.
' I 4
4 a
4 l
i e
h 'h
't y
. p<
r L----_-__:_______.
1
- Question No.:
051-03-014A Page 3 i
Answer:
Instructor Use Only.
1 LI b.
(1.0 pts.)
053 l
1
' Additional Information:
l Technical
References:
Logics Sht. 8,9 TRHB 10.12 Items to be Included with Ouestion:
None Time Validation:
2.10 Recual Cycle:
N/A K/A
Reference:
System:
026 l
Mode:
000 Number:
K4.04 Ratings:
RO:
3.7 SRO:
4.1 1
4 I
i O
~ ~. - - - - - - _ _ -... _ _ - _. - _ _ _. - - -. - _... -.. - - -
Question Number:
051-06-024A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
C Subject Area:
SERVICE WATER SYSTEM Task Number:
C5303 COT, C5307 COT l
Terninal Learninc Obiective:
C5303 COT During all modes of operation identify causes of interlocks, permissives and automatic functions associated with the service water system without error.
C5307 COT During all modes of operation and given a copy of AOP-9A diagnose the affect of a loss of service water on the EDG's in accordance with AOP-9A, " Service Water System Failure".
Question:
Instructor Use Only Units 1 and 2 are both operating at 100% steady state power.
Service water pumps P32B and E are in operation. Technical Specification Test TS-1, i
Emergency Diesel Generator G01 Bi-weekly, is conducted. After the diesel has been put on line, the service water pumps in operation are a.
- P32B, E,
and F.
b.
- P32A, B,
E, and F.
c.
- P3SA, B,
C, E, and F.
d.
- P32B, C,
D, and E.
e.
- P32A, B, and F.
1 i
t h
Points Earned
Question No.: '051-06-024A Page 2 Answer:
Instructor Use Only b.
(1.0 pt.)
074 Additional Information:-
Technical
References:
M-207 Sh 4
'TS-1 Logics Sh 8 Items to be Included with Ouestion:
None Time Validation:
1.90 Recual Cycle:
N/A
- l K/A
Reference:
System:
076 Mode:
000 Number:
K1.05 Ratings:
RO:
3.8 SRO:
4.0 4
i l
r' " 3 l-l
Question Number:
031-03-094A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
EMERGENCY TASKS Task Number:
C0705 COT, C7031 COT Terminal Learnina Obiective:
C0705 COT During an emergency or accident condition discriminate between a leaking PORV and pressurizer safety by analyzing tailpipe temperature indications and acoustic monitor response.
C7031 COT During an accident condition assess a failure of containment sump recirculation capability in terms of maintaining core cooling.
Question:
Instructor Use Only Your unit has been operating at 100% equilibrium when it suffers a small break LOCA.
Offsite power is lost; bus A06 fails to energize; but bus A05 does energize from its EDG.
During the shift to containment sump recirculation, the auxiliary operator opens 1 SI-857B by mistake instead of 1 SI-857A (RHR to SI pump supply).
Assuming no other operator action other then the pumps have been t
started:
Pzr Pressure 850 psig Pressure 3.8 psig Pzr Level 0%
RE-126/127/128 3.5 EO R/hr TH(WR) 527 Deg F Sump "B"
Level > 11 inch TC(WR) 527 Deg F RCP's Off Core TC's 527 Deg F a.
What effect(s) will this have on expected core cooling flow?
b.
What effect(s) will this have on SI pump PISA?
Points Earned
., _. _ ~ _
h l i Question No.:
031-03-094A Page 2 Answer:
Instructor Use only l
a.
No core flow will be available from RHR or l
SI (.5 pts.)
RHR since pressure is > shutoff head SI since it will have no suction source b.
Cavitation / pump damage due to not having a suction source of water.
(.5 pts.)
l 065 Additional Information:
Technical
References:
2, 110E018 sht.1 Items to be Included with Ouestion:
Added pump syatus based on a comment from TGS.
Time Validation.:
6.30 Recual Cycle:
N/A K/A
Reference:
System:
000 Mode:
009 Number:
EK3.27 Ratings:
-RO:
3.6 SRO:
3.8 y.,
' I4 hhN4 c
- e
' {i
--- q Question Number:
055-02-059A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
STEAM GENERATOR SYSTEM Task Number:
C2402 COT, C7017 COT Terminal Learnina Obiective:
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."
C7017 COT During all modes of operation and given a copy of AOP-10A, diagnose control room inaccessibility in accordance with AOP-10A, " Control Room Inaccessibility".
Question:
Instructor Use Only Both units are operating at 100% power.
The P-38A electric auxiliary feed pump has been out-of-service for 3 days for motor repair. During routine surveillance on the 2-P29 steam driven auxiliary feed pump the reactor operator notes that discharge pressure and flow, after_ starting the pump, are both 0.
It has been locally verified that the suction and discharge flow paths are correc,tly aligned, and the pump casing is reported as being abnormally hot.
a.
What is the most likely cause of the c,onditions existing for pump 2-P29?
b.
What actions, if any, are required by Technical Specifications?
(Assume that 2-P29 cannot be proven operable).
i i
Points Earned
...x.
M.
(!
'n 4'
' Question.No.:
055-02-059A Page 2 j
l l;
Answer:
Instructor Use Only 1
l-a.
The pury has become steam bound due to leaking-check valves.
(.5 pts) b.
Unit 2 must be placed.in hot shutdown within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
(.5 pts) 155 i
Additional Information:
1 Technical
References:
AOP-2C T.S.
15.3.4.C.1 & 15.3.0.A Rev. O Items to be Included with Ouestion:
None Time Validation:
2.50 Recual CycLg:
N/A K/A Re'ference:
System:
061 Mode:
000 Number:
A2.04 Ratings:
RO:
3.4 SRO:
3.8 I
l
" j eg.#
L.
[6s
~
I 1
l Revision Number:
0 Approval Date:
02/23/89 Question Number:
053-06-009A Point Value:
0.5 l
l Question Format:
W Question Type:
S Subject Area:
SFAS Task Number:
C7304 COT, C7305 COT Terminal Learnina Obiective:
C7304 COT During all modes of operation with the safeguards actuation unblocked, assess causes of interlocks, permissives and automatic functions associated with the safeguards actuation signal including all parameters measured by safeguards instruments and their setpoint values, without error.
C7305 COT During transitions between low power operations and cold shutdown, analyze requirements which must be met prior to blocking or resetting (unblocking) a safeguards actuation signal in accordance with OP-1A and OP-3C.
Question:
Instructor Use Only Unit 1 is in the process of cooling down to cold shutdown to comply with a Tech Spec LCO when a Safety Injection occurs. Analyzing the following data, explain why the safety injection occurred.
TIME RCS TEMP.
PRESSURIZER PRESS.
BORON CON.
1400 547'F 1985 psig 244 ppm 1500 547'F 1985 psig 392 ppm 1630 470*F 1850 psig 392 ppm Points Earned
.QusstionNo.:
053-06-009A Page 2 Answer:
Instructor Use Only The cooldown to < 490*F caused SG pressure to be reduced to less than its SI setpoint (530 psig) (.5 pts.)
137
)
Additional Information:
Technical
References:
OP-3C pg. 9,10 Items to be Included with Ouestion:
None Time Validation:
1.90 l
Recual Cvele:
N/A K/A
Reference:
System:
000 Mode:
040 Number:
EA2.05 1
Ratings:
RO:
4.1 SRO:
4.5
~
l I
l l
10 d
', +i1@f
)
e 4
I e
1 Section 2 d
S O
'J d h'
'9' '. 'g-r. i t
.g -
^,,
- ' ?.(
'F 1
9.
.r.M.s. i n
,,4.u' i
l I
i l
a
.a :....-.:. =:.. - - - - - - - - - - - - - - -
i STUDENT REFERENCE Scenario - ST-88-13 Plant History Prior to Initiatine Event Approximately 15 minutes ago, Unit I was operating at 100% power, beginning of life, steady state with the Gas Turbine out of service. Xenon was at equilibrium. All controls were in auto / normal,
for this plant condition.
Initiating Event I
~About five minutes ago, a dacreasing pressurizer pressure was i
identified by the " Low Pressure /Htrs on" annunciator.
The "A" pressurizer spray valve controller indicated open. In.the next 90 i
seconds, the following occurred:
power with control rods stepping in,OT delta T turbine runback to 95%
low pressure alarm, and then a reactor trip. About 2 minutes ago, a Safety Injection Signal occurred.
Ooerator Actions Taken Shortly after identifying the open spray valve, operators t'ook manual control of the spray valve and placed the valve in the closed position. Plant response was being verified during the turbine runbacks. When the reactor trip occurred, the operators entered EOP-0 and had completed the first two steps when the SI occurred.
Procedure and'Steo in Affect E0P-0 step 1.
I i
i A
T
.u.;
egan.
]
i*.
s
n.-
- - - - - x. m-----
4 Question Number:
055-02-030A Point Value:
1.4 Revision Number:
1 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
Task Number:
C0902 COT, C4510 COT
,+
Terminal Learnina Obiective:
C0902 COT During all modes of operation,. diagnose malfunctions of the pressurizer pressure control system prior to causing a reactor trip.
C4510 COT During all modes of operation, diagnose malfunctions of the EDG without compromising the operability of the EDG.
Question:
Instructor Use Only Assume that this event is happening on Unit 1. Also assume that a loss of off-site AC has occurred on Unit 1 only, and the emergency diesels are supplying the safeguards busses.
Suddenly emergency diesel G01 (3D) trips.
Will the safeguards equipment listed below stop? (Check YES or NO for each item)
YES/NO a.
RHR pump (P10A)
/
b.
RHR pump (P10B)
/
c.
AFW pump (P38A)
/
d.
AFW pump (P38B)
/
e.
SW pump (P32A)
/
f.
SW pump (P32B)
/
g.
SW pump (P32C)
/
h.
SW pump (P32D)
/
i.
SW pump (P32E)
/
j.
SW pump (P32F)
/
k.
Cont. Vent Fan (1W1A1)
/
1.
' Cont'. Vent Fan (1W1B1)
/
m.
Cont. Vent Fan (1W1C1)
/
n.
Cont. Vent Fan (1WlD1)
/
$r.; Q Y
d kql},
OWGQ
}RD Points Earned E
c'
Question No.:
055-02-030A Page 2 Answer:
Instructor Use Only 4
a.
YES
(.1 pts.)
h.
NO
(.1 pts.)
b.
NO
(.1 pts.)
1.
NO
(.1 pts.)
c.
YES
(.1 pts.)
j.
NO
(.1 pts.)
d.
NO
(.1 pts.)
k.
YES (.1 pts.)
e.
YES
(.3 pts.)
1.
YES (.1 pts.)
f.
YES
(.1 pts.)
m.
NO
(.1 pts.)
g.
NO
(.1 pts.)
n.
NO
(.1 pts.)
ST-88-09 562 Additional Information:
Technical
References:
Logic Sht. 8 TRHB 12.5 TRHB 12.6 TRHB 12.8 Items to be Included with Ouestion:
None Time Validation:
4.30 Recual Cycle:
N/A K/A
Reference:
System:
064 Mode:
000 Number:
K3.02 1
f Ratings:
RO:
4.2 SRO:
4.4 1
Y dv s,
' fi-g.
Question Number:
031-03-059A Point Value:
0.5 Revision Number:
0 Approval Date:
02/23/89 Question Format:
.W Question Type:
S Subject Area:. SAFETY INJECTION SYSTEM Task Number:
CO217 COT, C0602 COT Terminal Learnina Obiective:
CO217 COT During an accident condition the operator must be able to analyze,the effect of a LOCA on RCP operation in terms of RCP operating criteria and the effect of continued RCP operation.
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.
Question:
Instructor Use Only Explain why the present SI flow is appropriate or is not appropriate for the present plant conditions?
~
wh Points Earned i
r.
g
- lg... Question No.:
031-03-059A Page 2-c Answer:
Instructor Use Only b
RCS oressure~is the SI ouir.o's shutoff head..(.5 pts.)
~ ST-88 533 Additional Information:
Technical Refereng_gg:
TRHB 10.8
~ EOP-0 Items to be Included with Ouestion:
None Time Validation:
1.70 Recual Cvele:
N/A-K/A
Reference:
~ System:.006 Mode:
000 Number:
K5.06 Ratings:
RO:
3.5 SRO:
3.9 0 +
I i
4 r;4-J If.
~
.','[r, p 3 pap;3..
.4.-
WS
- e lTp 4
1:
irYp s
L:_:___.-_--____-----__--_.--
=-
z-:----------
I Quest' ion Number:
055-02-020A Point Value:
0.6 l
Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
REACTOR COOLANT PUMP Task Number:
CO213 COT, C0313 COT i
i i
Terminal Learnina Obiectivg:
]
1 CO213 COT During all modes of operation, diagnose an RTD failure prior to reacter trip.
C0313 COT During all modes of operation, and given.a copy of_OI-1 l
diagnose conditions requiring RCP tripping in accordance l
with OI-1, " Reactor Coolant Pump Operation Guide".
Question:
Instructor Use Only Assume that prior to reaching EOP-0, " Reactor Trip or Safety Injection", step 25 " Check if RCPs should be stopped," RCS pressure has' dropped to a pressure l
corresponding to the SI pumps shutoff head and RCS temperature has not decreased any further.
i a.
Determine if the RCPs should be tripped based on the RCP trip criteria.
b.
Include in answer all parameters /setpoints that are used for this evaluation.
SY.iNNE' l
~
s:3
.'p
-],
gi[
'N fr
.i;6th.%
bP '
' Points Earned Ly hsL__--____--____--_-.
)
1 Question No.:
055-02-020A' Page 2 q
l Answer:
Instructor Use Only a.
No.-
(.2 pts.)
b.
At least one SI pump is running (.2 pts.) and 0
RCS subcooling is [ 30 F.
(.2 pts.)
ST-88-13 563 Additional Information:
i Technical
References:
1 EOP-0 3
Steam Tables 1
Items to be Included with Ouestion:
None Time Validation:
6.50 Recual Cycle:
N/A K/A
Reference:
System:
003 Mode:
000 Number:
A2.02 Ratings:
RO:
3.7 SRO:
3.9 l-r -
N* ' '
)
1 e
1
Question Number:
055-02-023A Point Value:
0.8
' Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
REACTOR COOLANT PUMP Task Number:
CO309 COT, C4207 COT Terminal Learnina Obiective:
C0309 COT-During all modes of operation, assess the effect of a loss i
of RCP on pressurizer pressure control prior to losing pressurizer spray.
C4207 COT During abnormal operating conditions, diagnose conditions requiring AFW automatic actuation without error.
l Question:
Instructor Use'Only I
a.
How can this pressure drop be stopped?
b.
How will this affect pressurizer pressure control?
4 l
L Points Earned l
l
)_
Question No.:
055-02-023A Page 2 Answar:
Instructor Use Only a.
Stop RCP "A' to stop flow to the failed spray valve.
(.4 pts.)
b.
Spray flowrate will be reduced but pressure i
control will still be available with the spray valve from RCP "B" and pressurizer heaters.
(.4 pts.)
ST-88-13 659 Additional Information:
Technical
References:
l TRHB 10.3 i
EOP-0 Items to be Included with Ouestion:
None Time Validation:
2.40 Recual Cycle:
N/A K/A
Reference:
System:
010 4
Mode:
000 Number:
K6.03 Ratings:
RO:
3.2 SRO:
3.6
.vg.
l-1L_-__--_.__-____--_-__
~
l 1
Question Number:
053-02-013A Point Value:
0.4 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
REACTOR PROTECTION SYSTEM Task Number:
C1102 COT i
Terminal Learninc Obiective:
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 The scenario states that an OT deltaT turbine runback to 95% power occurred prior to receiving the reactor trip.
During normal full power operations, the OP deltaT setpoint is closer to'the actual deltaT than the OT deltaT setpoint. Why then, did an OT deltaT runback occur vice an OP deltaT runback?
l I
I T
4 '
-\\ g '
- r
- N'
.; s s?( ~
i 74 7,8 b)Ju.
I Points Earned hi I
9
?
Question No.:
053-02-013A Page 2 Answer:
Instructor Use Only The cause of the OT deltaT turbine runback was decreasing pressurizer pressure.
(.4 pts.)
ST-88-13 660 Additional Information:
- Technical
References:
STPT 1. 2, ' :L. 3, 4.2 T.S.
15.2.3 Items to be Included with Ouestion:
None Time Validation:
2.80 Recual Cycle:
N/A K/A
Reference:
System:
012 Mode:
000 Number:
K4.02 Ratings:
RO:
3.9 SRO:
4.3 i
4, I
0 l
d m
duestionNumber:
055-02-018A Point ifalue:
0.7 Revision Number:
0 Approval Date:
02/23/89
]
Question Format:
W-Question Type:
S Subject Area:.
PRESSURIZER PRESSURE CONTROL SYSTEM Task Number:
C0902 COT Terminal Learnina Obiective:
C0902 COT During all modes of operation, diagnose malfunctions of the pressurizer pressure control system prior to causing a reactor trip.
Question:
Instructor Use Only When the "A" PZR spray valve was manually closed, the reading on PC-431C ("A" spray valve controller) indicated closed, a.
Explain what this indicatidn on the controller means related to valve position?
I L
l
's
.#~
's u
+
N
-Ja %.,.,
D i
Points Earned i
f if W-____--__-___________
. 1 o
= Question No.:-
055-02-018A' Page 2 l
Answer:
Instructor Use.Only l
The' indication on the controller is controller i
output' signal and'not actual valve position.
I
(.7 pts.)-
ST-88-13 661-Additional Information:
Technical
References:
lTRHB 13.5 i
Items'to be Included with Ouestion:
None
- Time ValidatiRD:
2.30 l
Recual Cycle:
N/A K/A
Reference:
System:
000 Mode:
027 Number:
EA1.01 Ratings:
RO:
4.0 SRO:
3.9 m
8 I
b I
<Jd
.kg(%)h.
4'
.r l * ~
t l
l
Question Number:
031-03-066A Point Value:
0.6 Revision Number:
0-Approval Date:
02/23/89 Question Format:
W Question Type:
E Subject Area:
SAFETY INJECTION SYSTEM Task Number:
C0608 COT, C0617 COT Terminal Learnina Obiective:
C0608 COT During a small or large brec% LOCA assess SI system response by verifying all automatic safeguards components actuate as required and that system parameters such as flow, temperature and pressure follow expected system I
characteristics.
C0617 COT Using ciatrol board indication and the ASIP panel assess the response of pressurizer level, pressure and subcooling margin after SI actuation.
These parameters should be maintained within the li.its identified on the foldout page.
i Question:
Instructor Use Only Assuming no operator action is taken to mitigate this event, describe the response of pressurizer pressure as the event progresses.
l 4
f A
Points Earned
4 I
Quest!on No.:
031-03-066A Page 2 l-Answer:
Instructor Use Only l
Pressurizer pressure continues to decrease below the SI pump shutoff head.
At this point, the SI i
pumps begin to inject water into the RCS, resulting l
in an increase in pressurizer level.-Pressure continues to decrease until the pressurizer is filled solid.
(.3 pts.)
At this point, spray flow no longer has an effect on pressure.
Iniection flow from the'SI pumps (when pressure is below shutoff head) and charging flow will cause'a nressure increase to the PORV setDoint.
Pressure will be maintained at_2I below the PORV setooint
(.3 pts.) by operation of the PORVs.
ST-88-13 662 Additional Information:
Technical
References:
TRHB 10.3, 10.8 Items to be Included with Ouestiqn:
None Time Validation:
2.30 Recual Cycle:
N/A K/A
Reference:
System:
000 Mode:
027 Number:
EA2.11 Ratings:
RO:
4.0 SRO:
4.1 I
t L
s
- 2 r-2 ;---- = - ---
Question Number:
086-05-001A Point Value:
1.5 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
SRO Task Number:
C0702SRO Terminal Learnina Obiective:
1 C0702SRO Following plant trips and given PBNP 3.4.10 synthesize information during post trip reviews in accordance with PBNP 3.4.10, " Post Trip Review".
Question:
6Ad dMLp' Instructor Use Only Given current plant conditions a.
Complete section 4.7,
" Trip Assessment" of ECL-5, " Post-Trip Reviews" (Circle YES or No for each item).
1.
If any safeguards or protection system setpoints were reached, did actuation occur?
YES NO 2.
RCS pressure remained below setpoint for pressurizer PORV or safety valve actuation?
YES NO 3.
RCS temperature decrease
< 100*F/hr?
YES NO 4.
Reactor Coolant system intact?
YES NO 5.
Pressurizer level remained on sca'le?
YES NO 1
6.
Steam generator NR level remained on scale?
YES NO b.
Categorize the trip in accordance with ECL-5,
" Post Trip Reviews" and PBNP 3.4.10, j
" Post-Trip. Review".
(Circle the correct category.)
CATEGORY 1
2 3
.gp f (pr 32 Li i,i%
),
skdF Points Earned t?
l
Question No.:
086-05-001A Page 2
]
1 Answer:
Instructor Use Only 4
l c-a.
1.
YES
-(.2 pts.)-
2.
.YES
(.2 pts.)
3.
YES
(.2 pts.)
4.
YES
(. 2 pt.s. )
5.
YES
(.2 pts.)
6.
rg (.2 pts.)
b.
3
(.3 pts.)
ST-88-13 656 Additional Information:
Technical References;-
ECL-5 PBNP 3.4.10 Items to be Included with ouestion:
None Time Validation:
11.40 Recual Cycle:
N/A K/A
Reference:
System:
000 Mode:
007 Number:
EA2.06 Ratings:
RO:
4.3 SRO:
4.5 I
kN-jfpit c
g 4
.gf ;
' 9L
~
fs,.s J W;l
?, $j;fSh hy7 e
I rl
- r
___,______,_a____-----.--__--------a-
--~--
'4-J i-1 The following questions DO NOT refer to the conditions-of the scenario, but are.only using the simulator for an additional reference.
I 1
l 1
Sy u.i o; >
i s,
.,h, :g);,\\
,y.
h.-
+*~s
.E'
[hk'I
<an h',
l
- g..
- 6 L
e Question Number:
043-02-004A Point Value:
.0.6 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
CHEMICAL & VOLUME CONTROL SYSTEM Task Number:
CO223 COT, PO435 COT Terminal Learnino 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.
PO435 COT During conditions of normal full power operation respond to a reactivity transient at high power in terms of its effect on power level and RCS parameters such as pressure and temperature, without error.
Question:
Instructor Use Only If the control rods were in manual during a runback, explain whether pressurizer level would be HIGHER or LOWER than if the rods had been in automatic?
,1 4 L
T.
- pqqy Points Earned
+
_._-..m-Question No.:
043-02-004A Page 2 Answer:
Instructor'Use Only Pressurizer level'would have been higher due to the pressurizer level program being higher. (.6 pts.)
ST-88-03 427 Additional Information:
Technical
References:
TRHB 13.5, 13.6 Items to be Included with Ouest.i2D:
None Time Validation:
3.40 Recual Cycle:
N/A K/A
Reference:
System:
000 Mode:
003 Number:
EA1.06 Ratings:
RO:
4.0 SRO:
4.1 0
Y
s'f 'i _
l4 E 4,][ - if l-
>[h, []
g (n s -,.p. A A
- (
t';
G
.t.
p I ?....
A Question Number:
052-05-001A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89 1
Question Format:
W Question Type:
'S I
Subject Area:
MAIN FEEDWATER SYSTEM Task Number:
P3907 COT, P4008 COT Terminal Learnina obiectiva:
1 r
P3907 COT During all modes of operation and given OP-2A monitor the condensate system in different combinations in accordance with OP-2A, " Normal Power Operations".
.P4008 COT-During power operation, when the automatic SG water level control does not respond properly, the operator will detect this problem and take action prior to plant trip.
Question:
Instructor Use Only The annunciators " Steam Generator B Feedwater Flow 1
High" and " Steam Generator B Feedwater Flow Channel Alert" are both actuated as a result of the failure of feed flow FT-476 detector low.
i 5xplain how the bistable setpoints for these I
annunciators were exceeded due to this failure:
i a.
" Steam Generator B Feedwater Flow High" I
(E2 2-5) b.
" Steam Generator B Feedwater Flow Channel Alert" (E2 3-5) 3
^.
i Y,
WM,.
N*
Points Earned 5V l
Question No.:
052-05-001A Page 2 Answer:
Instructor Use Only a.
Since FT-476 was a controlling channel for 1B steam generator level control, its failure caused feed reg valve 1CV-476A to open, resulting in actual feedwater flow as measured on FT-477 being greater than steam flow for the associated channel in excess of the alarm setpoint.
(.5 pts.)
This actuated the " Steam Generator B Feedwater Flow High" alarm.
b.
The failure of.the feedwater flow loop B transmitter FT-476 low resulted in steam flow being greater than feedwater flow for the associated channel in excess of the alarm setpoint, (.5 pts.) which actuated the " Steam Generator B Feedwater Flow Channel Alert" alarm.
ST-88-02 404 Additional Information:
Technical
References:
TRHB 13.7 Logic sheet 10 STPT 1.6 and 6.3 1CO3/2CO3 ARB Items to be Included with Ouestion:
None Time Validation:
3.90 Recual Cycle:
N/A K/A
Reference:
System:
059 i
l Mode:
000 Number:
K1.04
' Ratings:
RO:
3.4 SRO:
3.4 t
w
'~n
~ = ~ - - ~ - - -
~
~ ~ ~ ~ ~ '
t Question Number:
031-03-064A Point Value:
0.8 Revision Number:
0 Approval.Date:
02/23/89 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 I
response of the diesel generators to an undervoltage condition on a safeguards bus in.that the DG must function to provide electrical power to its associated safeguards loads.
Question:
Instructor Use Only Assume that prior to this event on' Unit 1, a normal surveillance was being conducted on emergency i
diesel 3D.
The diesel had just been started and was idling with the governor at the minimum setting. Emergency diesel 4D is not running.
Then f
the reactor trip and SI occur.
How should the emergency diesels respond to the Unit 1 SI signal?
a.
3D continues to idle at minimum governor setting.
4D does not start.
b.
3D, receives a fast' start signal and the g
governor depositions to the full load setting.
j 4D fast starts.
c.
3D continues to idle at minimum governor setting.
4D fast starts.
3 d.
3D receives a fast start signal and the governor depositions to the full load position.
4D does not start.
l l
i k
.rd f's =
jj
- .~
{gl( <f I
Points Earned 4
.7,3'x,.
3 ;...
4 4
, p.
y,
'Que'stion No.:'. 031-03-064A Page 2 Answer:
Instructor Use'Only-
[.
.J r
i c.
.(.8 pts.)
.i ST-88-09 539
. Additional Information:
Technical Referenegg:
TRfiB 12.8 OP-11A Jtems to be Included with ouestion:
None Time Validation:
1.50 Recual Cvele:
N/A K/A'
Reference:
' System:
013 Mode:
000
' Number:
K1.12 Ratin'gs:
RO:
4.1 SRO:
4.4 i
i i
i j
l n.
g 4#L7
- (;I) p.,.
pd. :?
%g s.
4,.
l
.~l\\
M 1-I l'.
j-
. = = =. =. - = - -.
t Question Number:
053-02-016A Point Value:
1.0 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
C Subject Area:
ROD CONTROL SYSTEM Task Number:
C0112 COT, P2801 COT 1
Terminal Learnina Obiective:
i 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.
P2801 COT During header pressure, load rejection and turbine trip modes of control, monitor the condenser steam dump control system in accordance with OP-1A and OP-3C.
Question:
Instructor Use Only Assume the plant is still operating at 1000 power with the failed pressurizer pressure channel PT-430 bistables tripped.
If THOT instrument, TE-403A, were to fail low, a.
the reactor would immediately trip on OPgT with 2/4 channels tripped.
b.
the reactor would not trip when the THOT instrument failed, but would if the bistables are tripped.
c.
the reactor would not trip with the THOT bistables tripped.
d.
power operation would be allowed to continue providing the THOT bistables are tripped, e.
power operation would be allowed to continue providing the OTgT setpoint is adjusted to compensate for the failed THOT input.
4 y@
hd i
Points Earned h
v l
~
l
' Question No.:
053-02-016A Page 2-l Answer:
Instructor Use Only b.
(l'. 0 ' pts. )
ST-88-14 677 Additional Information:
4 Technical
References:
TRHB 13.3 Logic Sht.
2, 15 Items to be Included'with Ouestiom:
None Time Validation:
5.70 Recual cycle:
N/A I
K/A
Reference:
System:
012 Mode:
000 Number:
A3.06 Ratings:
RO:
3.7 SRO:
3.7 i
e k
c.:,
5
. [;~;;p.
s,.
l tp" k
L___----_-_--_--_______
.~
Question Numbart. 053-02-014A Point Value:
0.6 Revision-Number:
0 Approval Date:
02/23/89 Question Format:
W.
Question Type:
S Subject Area:
REACTOR PROTECTION SYSTEM Task Number:
C0112 COT, P1101 COT x
Terminal Learnina 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.
P1C01 COT With a protection instrument declared inoperable, place the channel in the tripped condition to meet the minimum degree of redundancy requirement of the Technical Specifications, in accordance with ICP-10.2 Question:
[C QMjl Instructor Use Only According to ICP-10.2, when pressurizer pressure I
transmitter PT-430'is rer.oved from service, several bistables are tripped. Which of the following annunciators will indicate in the control room that the appropriate bistables have been tripped?
a.
Pressurizer. Low Pressure SI Channel Alert (1C01 1B1-7)
Yes/No b.
Pressurizer High Pressure Reactor Trip-(1C041B2-4)
Yes/No c.
Auto Turbine Runback Overpower QT (1C04 1A4-7)
Yes/No d.
Reactor Coolant Overtemperature gT (1C041A3-9) Channel Alert Yes/No e.
Auto Turbine Runback Overtemperature QT (IC041A4-8)
Yes/No f.
Pressurizer Low Pressure SI (1C04 1B3-3)
Yes/No
$rQ[-
NE h$;:[5 ge Points Earned
.t.
o Question No.:
053-02-014A Page 2 l
n s
I' Answer:
Instructor.Use Only a.
Yes b.
No c.
No d.
Yes e.
Yes f.
No ST-88-14 694 i
Additional Information:
l Technical
References:
i ARB Logic Sht. 13, 15, 18 i
t Items to be Included with Ouestion:
None Time Validation:
4.50 Recual Cycle:
N/A K/A
Reference:
System:
012 4
Mode:
000 1
Number:
A4.04 t
Ratings:
RO:
3.3 SRO:
3.3
{
-.s g.
3.'g
.t, j 1
.. f t hY's 's ;v
(,c fg
,t I
a I
I l
Question Number:-
051-03-010A Point Value:
0.6 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
SAFETY INJECTION SYSTEM j
l Task Number:
C0603 COT, P0501 COT l
Terminal Learnino Obiective:
l l
C0603 COT During all modes of operation identify causes of interlocks, permissives, and automatic functions associated with the SI system without error.
P0501 COT During a normal plant startup and given CL-7A perform lineups of the RHR system in accordance with CL-7A,." Safety Injection System Checklist".
Question:
g gg[f instructor Use Only Unit 1 was operating at 100% power when it suffered a loss of offsite power and safety injection.
One bus undervoltage device, 1-271X4/B03, fails to reset.
Will the below-listed loads auto start?
a.
RHR pump 1P10A b.
SI pump 1P15A c.
SW pump P32B l
1 I
a w,
- w
.p y
Points Earned lI l
1' l
J
- =..--..
-. =... - -
- + --- -
a-
')
g7+
,,t
-l g. Question No.:.
051-03-010A Page'.2
. Answer:
Instructor.Use Only-a.
No.
(. 2: pts. ):
D b.-
Yes.
'(.2-pts.)
c.
No.
(.2 pts.)
076 Additional'Information:
' Technical
References:
1
~ Logic 883D195
, Sht. 5, 8-Items to be Included with ouestion:
None Time Validation:
4.60 Recual Cvele:
N/A K/A
Reference:
System:
013 Mode:
000 Number:
K4.07 Ratings:-
RO:
3.7 SRO:
4.1 thhlnlYh4 or ut
"., p i
- r. w tj (s."
[~'
y
>:ax.
+
L w
fb kdb.
7 s
l I
(
Qucation Number:
031-03-147A Point Value:
0.4 Revision Number:
0 Approval Date:
02/23/89 Question Format:
W Question Type:
S Subject Area:
EMERGENCY CORE COOLING SYSTEM Task Number:
C0615 COT, C7032 COT Terminal Learnina obiective:
C0615 COT During emergency or accident conditions the operator must be able to recognize conditions for terminating or resetting SI as identified in the Emergency Operating Procedures.
C7032 COT Recognize the purpose and applicability of each EOP.
Question:
Instructor Use Only Following an SI reset, an undervoltage on safeguards busses 1-AOS and 1-A06 will cause the logic reset loop to drop out. With the SI signal still present, explain if SI will or will not reinitiate when power is restored.
e h
S
- c..
$Ntftlj:,y[?
[
Points Earned O
$V
/
- ' Question No.:
031-03-147A Page 2 Answer:
Instructor Use Only When the reset loop drops out the logic is realigned to provide a normal SI signal to the components. (.4 pts.)
Additional Information:
Technical
References:
I Logic sheets 7, 8,
and 9 j
i
- l Items to be Included with Ouestion:. None Time Validation:
2.70 Recual Cvele:
N/A i;
K/A
Reference:
System:
000 Mode:
040 Number:
EK3.02 Ratings:
RO:
4.4 SRO:
4.4 of
',W p%
1
[4, y
t'.