ML14174B015
| ML14174B015 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 02/09/1993 |
| From: | Ernstes M, Mcwhorter R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14174B016 | List: |
| References | |
| 50-261-93-300, NUDOCS 9303020433 | |
| Download: ML14174B015 (77) | |
See also: IR 05000261/1993300
Text
UNITED STATES
o
NUCLEAR REGULATORY COMMISSION
REGION lI
101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30323
ENCLOSURE 1
EXAMINATION REPORT -
50-261/93-300
Facility Licensee:
Carolina Power and Light Company
Facility Name: H. B. Robinson Steam Electric Plant
Facility Docket No.:
50-261
Facility License No.:
Examinations were administered at the H. B. Robinson Steam Electric Plant near
Hartsville, South Carolina.
Chief Examiner:
4/C
Kj
Richard D. McWhorter, Jr.
D ate Signed
Examiners:
E. Lea, NRC
B. Holbrook, NRC
A. Lopez, Battelle Pacific Northwest Laboratories
Approved By:
o4X'1,A
J6
L-/
_
/7 /73
Michael E. Ernstes, Chief
Date Signed
Operator Licensing Section 2
Operations Branch
Division of Reactor Safety
SUMMARY
Scope:
Regular, announced requalification examinations and associated
inspection activities were conducted during the week of January 25,
1993. The examinations were administered under the guidelines of the
Examiner Standards (ES), NUREG-1021, Revision 7. Written and
operating examinations were administered to nine Senior Reactor
Operators (SROs) and three Reactor Operators (ROs).
Results: Nine SROs and three ROs passed the examination for a 100% pass rate.
Three of three crews evaluated passed the simulator portion of the
examination. Based on the results of the examinations, the
H. B. Robinson Requalification Program has been determined to be
satisfactory.
9303020433 930211
ADOCK 05000261
V
Enclosure 1
2
Minor weaknesses were identified in operator performance and in the
quality of the licensee-proposed examination (paragraphs 2.c and
2.e).
Two inspector follow-up items were identified regarding inadequate
guidance contained in procedural steps (paragraph 2.f).
No violations or deviations were identified.
REPORT DETAILS
1. Persons Contacted
Licensee Employees
C. Dietz, Vice President - Robinson Nuclear Project
J. Allen, Project Specialist - Operator Training
- R. Allen, Manager -
License Training
- C. Bethea, Manager - Training
H. Carter, Project Specialist - Operator Training
R. Chambers, Plant General Manager
- W. Flannagan, Manager - Operations
J. Jones, Senior Specialist - Operator Training
G. Levy, Contractor to Licensee
W. Mahalovits, Senior Specialist - Operator Training
A. McGilvray, Senior Specialist -
Operator Training
D. Neal, Senior Specialist - Operator Training
- C. Olexik, Manager - Robinson Assessment Section
W. Stover, Shift Supervisor - Operations
- A. Wallace, Manager - Shift Operations
NRC Employees
- H. Christensen, Section Chief
- L. Garner, Senior Resident Inspector
- C. Ogle, Resident Inspector
- Attended exit meeting
Other licensee employees contacted included instructors, operators,
engineers and office personnel.
2. Discussion
a. Results and Program Evaluation
This examination was administered under the guidelines of the
Examiner Standards, NUREG-1021, Revision 7. Nine SROs and three ROs
passed the examination for a 100% pass rate. Three of three crews
passed the simulator portion of the examination. Based on the
examination results, the H. B. Robinson Requalification Program meets
the criteria established in NUREG-1021, ES-601.D.2, and has been
determined to be satisfactory.
b. Reference Material
The licensee supplied reference material to support examination
preparation. Procedures and lesson plans were adequate. The
scenario, written examination, and Job Performance Measure (JPM)
banks met the minimum guidelines of NUREG-1021 for quantity and
quality.
Report Details
2
The licensee supplied a sample plan describing the requalification
cycle. The plan and its test item selection process met the
guidelines for NRC administered examinations, and supported testing
both knowledge gained during the requalification program and other
general areas.
c. Examination Development
The licensee supplied the NRC with proposed examinations. NRC
examiners reviewed the examinations and found them consistent with
the guidelines of NUREG-1021. As detailed below, several changes to
the examination were required due to problems discovered during
examination validation. NRC examiners judged that most of these
problems should have been discovered and resolved by the licensee
prior to submission of the proposed examination to the NRC.
(1) Written Examination
The Part A (static simulator) examination submitted by the
licensee was based on a loss of shutdown cooling event. NRC
examiners considered this examination (SSS-8) to be an excellent
choice for testing important operator knowledge of shutdown
evolutions and hazards. However, during validation, the
licensee was unable to exactly repeat the simulator setup called
for by the examination, which made several questions invalid.
Although the attempt to include a shutdown scenario in the
proposed examination was commendable, NRC examiners believed
that the problem with duplicating the scenario setup should have
been identified before its inclusion as a part of the proposed
examination. A replacement Part A examination was validated
without major problems. One procedure problem noted during the
validation of the Part A examination is discussed in paragraph
2.f.
The Part B examination submitted by the licensee was reviewed by
NRC examiners, and minor problems were noted. Specifically, two
pairs of questions were found to be repetitive in the topics
examined. The licensee and the NRC examiners each selected one
substitute question from licensee banks to correct this problem.
Twelve other questions required modifications to improve
multiple choice distractors, to incorporate recent procedure
changes, or to improve stem wording. NRC examiners considered
that several of these problems should also have been resolved
prior to inclusion of these questions into the proposed
examination.
Additionally, NRC examiners found that although the written
examination met NRC guidelines, it examined at a low level of
difficulty. NRC examiners expressed concern that such an
examination may not be useful for identifying areas where
Report Details
3
retraining is needed for upgrading knowledge as required by
(2) Dynamic Simulator Scenarios
Licensee-submitted dynamic simulator scenarios met the
guidelines of NUREG-1021, for scenario attributes without NRC
modification. During scenario validations, it was discovered
that one scenario (DSS-3) resulted in an unanticipated entry
into a Functional Restoration Procedure. As a result, the
licensee proposed, and the NRC agreed, to substitute another
scenario (DSS-11) from the licensee bank. NRC examiners
considered that this was another example of a problem that
should have been detected and resolved prior to inclusion as a
part of the proposed examination. Additionally, one procedure
problem noted during scenario validation is discussed in
paragraph 2.f.
JPMs submitted for the examination were generally good in
content. One proposed JPM (IP-004) was judged by NRC examiners
to be at too low a level of knowledge for the examination
because it required only one step for task completion. NRC
examiners proposed, and the licensee concurred to substitute a
d. Examination Administration
(1) Scheduling and Conduct of Examinations
The administration of examinations was generally well conducted
and was free from major problems. At the start of the
examination week, the licensee informed NRC examiners that the
area for the conduct of one JPM (IP-032) was in a contamination
control area and recommended replacing the JPM. NRC examiners
agreed and selected a substitute JPM (IP-020).
(2) Licensee Evaluators
Licensee evaluators in the operating portions of the examination
were able to administer the examinations competently and provide
accurate and unbiased evaluations of operator performance. NRC
examiners observed minor examples of a lack of formality or
attention to detail, and provided this feedback to the
individual evaluators. These areas included failures to shield
examination notes from operators, and failures to require
operators to describe actions in detail.
NRC examiners noted that at the start of each JPM, evaluators
routinely told operators the task standard for completion and
Report Details
4
the terminating cue for the JPM. NRC examiners considered that
this practice did not meet the intent of NUREG-1021, ES-603,
with respect to guidelines for information to be given to
operators at the start of a task. The licensee staff agreed to
evaluate this practice.
e. Operator Performance
As evidenced by the high percentage of operators and crews passing
the examination (paragraph 2.a), operator overall performance was
good.
Crews displayed similar problems in two areas. First, board
operators were observed to ignore a caution marker placed on the
controller for valve PCV-145. The caution stated that the controller
should be taken to manual whenever letdown orifices were manipulated.
More than half of the operators in the simulator portion of the
examination left the controller in automatic when placing additional
letdown orifices in service. Additionally, during JPMs, the majority
of operators failed to address a caution cap on valve SI-863B.
Examiners concluded that operators examined displayed a lack of
proper concern for caution tags placed on control room equipment.
Second, three operators (25%) failed to properly complete a JPM to
transfer to long term recirculation following a loss of coolant
accident. NRC examiners expressed concern to the licensee that the
inability of a large portion of operators to successfully complete
the task demonstrated a need for the licensee to provide additional
training on the task and the procedure.
One crew made a serious error in procedure use during a small break
Loss of Coolant Accident (LOCA) scenario. The Senior Control
Operator (SCO) and Shift Supervisor (SS) chose to use EPP-8, "Post
LOCA Cooldown and Depressurization," instead of following the
established emergency path to use EPP-15, "Loss of Emergency Coolant
Recirculation."
Post-scenario questioning revealed that the senior
control operator made this decision because he believed that EPP-8
was better since it would not reduce safety injection flow and that
the EPP-15 purpose of conserving water was not a concern.
Post-scenario questioning of the SS revealed that he incorrectly
believed that for the situation in the scenario, EPP-15 could not be
accomplished.
After analyzing the scenario, licensee evaluators concluded that
although operators did not follow approved emergency procedures, the
impact on the plant in this instance was not significant. The
licensee believed that SCO was correct in that either procedure
EPP-15 or EPP-8 would effectively mitigate the accident and take
essentially the same actions. Accordingly, the licensee concluded
that the crew passed the examination, however both the SS and SCO
Report Details
5
demonstrated significant weaknesses in procedure usage that would
require individual remediation.
NRC examiners also reviewed the impact of.the SCO's decision, and the
actions taken by the licensee. Examiners judged that the licensee's
conclusions were proper for the situation. NRC examiners also
reviewed the licensee's individual evaluation results for the
operators and concluded that the licensee had properly identified
appropriate areas for remediation.
f. Licensee Procedures
During the validation of simulator scenarios, licensee training staff
pointed out to examiners that several Operations Work Procedures
(OWPs) required functional tests to verify bistables are properly
tripped when a safety-related instrument is taken out of service.
However, in many situations, a proper functional test was not
possible, since bistable indications were already lit. In those
cases, the licensee stated that operators were expected to initiate a
temporary procedure change to complete the OWP. Examiners inquired
about how long this situation had existed, and licensee personnel
indicated that the situation was identified to operators in December
1991.
Examiners expressed concern that the time the problem had been
known to exist without correction was excessive for a Technical
Specification-related procedure. The licensee agreed to evaluate the
priority of completing a procedure revision.
During JPM validation, it was found that procedure FRP-H.1, "Response
to Loss of Secondary Heat Sink," was inadequate in the direction
given for operators to accomplish the response not obtained for step
13.a. The step required operators to align any available low
pressure water source to a depressurized steam generator. However,
the step failed to give any guidance for accomplishment, and licensee
training staff could not identify any methods for step accomplishment
readily available to operators. A review by NRC examiners of generic
emergency procedure guidelines revealed that the guidelines
recommended that the licensee provide facility-specific information
in the step on how to accomplish the task. The licensee failed to
write the procedure to meet that guideline. In response to NRC
concerns, the licensee agreed to evaluate the adequacy of the step.
NRC examiners identified this item for follow up as Inspector
Follow-up Item (IFI) 93-300-01, procedure FRP-H.1 contains inadequate
guidance for accomplishment of step 13.a, response not obtained.
A similar problem was observed in AOP-020, "Loss of Residual Heat
Removal (Shutdown Cooling)." During static simulator validations, it
was noted that step 55 directed operators to align alternate cooling
to the Residual Heat Removal pumps from fire water. However, the
procedure gave no guidance on how this was to be accomplished, and
licensee training staff could not identify any other procedure that
described a method for accomplishment. In response to NRC concerns,
Report Details
6
the licensee agreed to evaluate the adequacy of the step. NRC
examiners identified this item for follow up as IFI 93-300-02,
procedure AOP-020 contains inadequate guidance for accomplishment of
step 55.
g. Simulator Fidelity
Five items identified in the NRC Simulation Facility Report included
in the last requalification examination report were reviewed for the
status of resolution. Examiners found that the simulator had been
modified to resolve simulator to plant differences in radiation
monitor type and in the location of several control board meters.
Also, the simulator core model had been upgraded, resolving
previously identified core modeling problems. Examiners concluded
that the licensee was effective in working to resolve simulator
fidelity problems. No new simulator fidelity problems were
identified.
Examiners also requested that the licensee provide information on the
use of the simulator for items other than operator training and
evaluation. The licensee reported that of the time the simulator was
actually in use, 87% was for operator training, and 13% was for uses
other than operator training.
h. Training Program Reviews
(1) Non-NRC Requalification Examinations
NRC examiners selected and reviewed written and simulator
examinations given in the first and last weeks of the 1992
requalification examination cycle. Examiners compared them to
the guidelines of NUREG-1021 for complexity and level of
knowledge evaluated. Examinations were found to be of
comparable quality to NRC administered examinations.
Additionally, examiners reviewed the results of examinations
given during the two weeks and found that the results were
generally comparable to NRC administered examinations in grade
averages and ranges. Examiners concluded that the examination
program conducted in 1992 was administered consistent with NRC
examination guidelines and practices.
Licensee simulator examination results for the 1992 examination
cycle were reviewed, along with remediation and retest programs
identified for deficient operator performance. Examiners
reviewed all unsatisfactory evaluations, and licensee corrective
action to remediate and retest operators in accordance with
10 CFR 50.59 requirements. Some inconsistencies were noted in
how different evaluators completed administrative records, but
all remediation and retests were properly documented as being
satisfactorily completed. Examiners judged that the licensee's
program for remediation and retest met NRC requirements.
Report Details
7
(2) Requalification Program Procedures
Examiners reviewed procedures TUI-21, "Development and
Administration of Annual License Operator Requalification Exam,"
Revision 1, and TI-200, "Robinson Plant Operator Requalification
Program," Revision 2. The procedures outlined a requalification
program and examination process that met the requirements of
10 CFR 55.59, and was patterned according to the guidelines of
Examiners judged the procedures to be adequate for
program administration.
(3) Staffing Review
NRC examiners also reviewed the requirements for licensee
staffing in comparison to crew composition for training and
examination. Examiners found that the licensee's Technical
Specifications and administrative procedures required the same
number of licensed operators as were used in training and for
this examination (two senior operators and two reactor operators
per shift).
Examiners concluded that the licensee examined with
the same crew composition required for use in the plant.
Within the areas inspected, no violations or deviations were identified.
3. Exit Interview
The examination scope and findings were summarized on January 29, 1993,
with those persons indicated in paragraph 1. The inspectors described the
areas inspected and discussed in detail the inspection results.
Additionally, the licensee was informed by telephone following the
interview of the specific items listed below. Dissenting comments were
not received from the licensee. Proprietary information is not contained
in this report.
Item Number
Description and Reference
50-261/93-300-01
Inspector follow-up item regarding procedure
FRP-H.1, inadequate guidance for the
accomplishment of step 13.a, response not
obtained (paragraph 2.f).
50-261/93-300-02
Inspector follow-up item regarding procedure
AOP-020, inadequate guidance for the
accomplishment of step 55 (paragraph 2.f).
ENCLOSURE 2
SIMULATOR FIDELITY REPORT
Facility Licensee:
Carolina Power and Light Company
Facility Docket No.:
50-261
Operating Tests Administered On:
January 26 - 28, 1993
This form is used to report observations. These observations do not
constitute, in and of themselves, audit or inspection findings and are not,
without further verification and review, indicative of noncompliance with
These observations do not affect NRC certification or
approval of the simulation facility other than to provide information which
may be used in future evaluations. No licensee action is required solely in
response to these observations.
During the conduct of the simulator portion of the operating tests, the
following items were observed:
ITEM
DESCRIPTION
None
& Llp,,
6~
9%q2 - 3O "
NAME:
DATE:
CLASS:
H.B. ROBINSON LOR
EXAM:
ANNUAL LOR EXAM -
SRO WRITTEN
PREPARED BY: GUY LEVY
GRADED
BY:
ALTERNATE GRADER:
(if required)
TOTAL POINTS:
29.6
POINTS MISSED:
1. EXAM TIME LIMIT IS 2 HRS
2. DO NOT write on back of pages.
3. A score of 80% is required for passing.
4. Use only black ink on this exam. Cross out all
errors with a single line initial and date.
I have neither given nor received help on this exam.
All work is my own.
Signature
PAGE 23
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
1
ITEM ID: B-005
POINT VALUE:
1.2
LESSON PLAN: PLR-LP-58
OBJECTIVE:
4
LESSON PLAN: PROC-LP-39
OBJECTIVE:
1
LESSON PLAN: RCS-LP-009
OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-015 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-035 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-035 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-035 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 4
LESSON PLAN: SR-SE-004
OBJECTIVE: 3
LESSON PLAN: SR-SE-028
OBJECTIVE: 4.A
PLANT REFERENCE: AOP-016
PLANT REFERENCE: T/S 3.1.5.3
During normal full power operation, radiation monitors for SG
blowdown and condenser-vacuum pump effluent were observed to be
increasing.
OST-051 "RCS Leakage Evaluation" was performed and
results were 0.6 gpm.
SG chemistry samples identify a primary
to secondary leak on "C" SG of 0.4 gpm.
. Based on this information, which of the following actions is
correct?
a. Power operation can continue. Continue to monitor RCS
leakage.
b. Place the reactor in a hot shutdown condition within 12
hours.
c. Place the reactor in a cold shutdown condition within 30
hours.
d. Place the reactor in a cold shutdown condition within 36
hours.
ANSWER
1
C.
PAGE 24
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
2
ITEM ID: B-009
POINT VALUE:
1.4
LESSON PLAN: PROC-LP-38 OBJECTIVE: 1.D
LESSON PLAN: RO-SE-059
OBJECTIVE:
3
LESSON PLAN: RO/SRO-SE-034
OBJECTIVE: 3
PLANT REFERENCE: AOP-001
PLANT REFERENCE: OMM-024
PLANT REFERENCE: SD-007
PLANT REFERENCE: T/S 3.10.1.5
HBR Unit 12 is at 90% power with all controls in automatic. D
Control Bank group step counters indicate 196 steps. ERFIS is
operable. A check of the rod position indications for D Control
Bank show that:
a. Rod DS:
124 inches
b. Rod MS:
116 inches
c. Rod H4:
120 inches
d.
Rod H8:
121 inches
e. Rod H12: 131 inches
Are the control rods in D control bank properly aligned? Justify
your answer by explaining how any limits are or are not met.
ANSWER
2
No. (0.4) H12-deviates > 7.5 inches from the average of the
RPIs (122.4 in.) (1.0)
Mob.
'd -hL
PAGE 25
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
3
ITEM ID: B-020
POINT VALUE:
1.2
LESSON PLAN: EOP-LP-17
OBJECTIVE: 3
LESSON PLAN: MDTA-LP-08
OBJECTIVE: 3
LESSON PLAN: RO-SE-069
OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-009 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-026 OBJECTIVE: 4
LESSON PLAN: SR-SE-010 OBJECTIVE: 2.B
PLANT REFERENCE: ERG-FR-H.1
PLANT REFERENCE: FRP-H.1
FRP-H.1 (Response to Loss of Secondary Heat Sink) requires
tripping of the RCPs and the immediate initiation of RCS bleed
and feed, if ANY SG wide range level decreases to less than 60%
[63%].
Choose the statement that correctly explains why the
RCPs are required to be tripped.
a. Delays loss of RCS inventory
b. Allows presure reduction to below SI shutoff head
c. Prevents uncovering the core after subcooling is lost
d. Reduces RCS heat input and extends time to S/G dryout
ANSWER 3
d.
PAGE 26
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
4
ITEM ID: B-033
POINT VALUE:
1.7
LESSON PLAN: AOP-LP-05 OBJECTIVE: 3
LESSON PLAN: PLR-LP-60
OBJECTIVE:
3
LESSON PLAN: PROC-LP-32
OBJECTIVE: 2.E
LESSON PLAN: RO/SRO-SE-018 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-033
OBJECTIVE: 3
PLANT REFERENCE: AP-030
PLANT REFERENCE: T/S 3.3.3
The plant is at 100% power with "B" Component Cooling Pump
declared inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago. While attempting to
perform an operability demonstration, "C" Component Cooling
Pump tripped twice and has just been declared inoperable.
With these conditions, the NRC must be notified within
a. 15 minutes
b. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
c. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
d. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
ANSWER 4
b. [1nCFR5O.72(b)(1)(ii)(A) notification)
PAGE 27
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
5
ITEM ID: B-043
POINT VALUE:
1.7
LESSON PLAN: FUEL-LP-004
OBJECTIVE:
3
LESSON PLAN: PROC-LP-47
OBJECTIVE:
3
LESSON PLAN: PLR-LP-59
OBJECTIVE: 6
PLANT REFERENCE: T/S 3.10.2.5
PLANT REFERENCE: FMP-009
The plant is
at 89% power with a power escalation in progress.
PDC target values (100% power) are as follows:
- N-41:
-2.674
- N-43:
-1.431
- N-42:
-1.896
- N-44:
-2.494
Target Band:
+ or -
5%, APL=103% power
Current Delta Flux meter readings are as follows:
- N-41:
1.6
- N-43:
2.8
- N-42:
0.7
- N-44:
2.2
Based on the above information, which of the following
actions is correct ?
. a. Power must be maintained < 90%
b. Power must be reduced to < 50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
c. Power must be reduced to < 50% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
d. Power escalation may continue to 100%
ANSWER
5
d.
PAGE 28
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
6
ITEM ID: B-051
POINT VALUE:
1.20
LESSON PLAN: RO-SE-028
OBJECTIVE: 2
LESSON PLAN: RO-SE-028
OBJECTIVE: 3
LESSON PLAN: RO-SE-031 OBJECTIVE: 2
LESSON PLAN: RO-SE-045 OBJECTIVE: 2
LESSON PLAN: SR-SE-028 OBJECTIVE: 1.B
LESSON PLAN: RO/SRO-SE-027
OBJECTIVE: 4.A
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 4
PLANT REFERENCE: CURVE 8.23
PLANT REFERENCE: OST-051
With the plant operating at 100% power, a pressurizer safety
valve begins to leak.
If PRT level increases from 71% to 76% (as indicated on LI-470)
over a one hour period, the RCS leakage rate through the safety
valve would be closest to:
a. 2 gpm
b. 5 gpm
c. 10 gpm
O
d. 20 gpm
ANSWER
6
c.
PAGE 29
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
7
ITEM ID: B-058
POINT VALUE:
1.2
LESSON PLAN: EOP-LP-03
OBJECTIVE:
1
LESSON PLAN: EOP-LP-03
OBJECTIVE: 4
LESSON PLAN: MDTA-LP-07
OBJECTIVE:
1
LESSON PLAN: RO-SE-034
OBJECTIVE: 4
LESSON PLAN: RO-SE-074
OBJECTIVE:
6
LESSON PLAN: RO/SRO-SE-016 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-023
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-031
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-033 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-037 OBJECTIVE: 6
LESSON PLAN: SR-SE-Oil OBJECTIVE: 2
LESSON PLAN: SR-SE-014
OBJECTIVE: 2.C
PLANT REFERENCE: PATH 1
Assume that the "B" steam generator main steam line completely
shears inside containment.
Assuming that all Reactor-Protection
and Engineered Safeguards Features equipment operate as designed
and that all actions are taken as required by plant procedures,
what procedure will be used to secure safety injection?
a. EPP-OC8
Sb.
Path-2
c. EPP-7
d. EPP-11
ANSWER
7
C.
01
PAGE 30
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
8
ITEM ID: B-099
POINT VALUE:
2.00
LESSON PLAN: FUEL-LP-002 OBJECTIVE: 3
LESSON PLAN: PLR-LP-59
OBJECTIVE: 6
LESSON PLAN: PROC-LP-38
OBJECTIVE: 1.E
LESSON PLAN: RO-SE-039 OBJECTIVE: 2
LESSON PLAN: RO-SE-043 OBJECTIVE: 1
LESSON PLAN: RO-SE-052 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-004 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-015 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 4
LESSON PLAN: SR-SE-003 OBJECTIVE: 3
LESSON PLAN: SR-SE-006 OBJECTIVE: 1.B
LESSON PLAN: SR-SE-008 OBJECTIVE: 1.C
LESSON PLAN: SR-SE-010 OBJECTIVE: 1.C
LESSON PLAN: SR-SE-011
OBJECTIVE:
1
LESSON PLAN: SR-SE-013
OBJECTIVE: 1
LESSON PLAN: SR-SE-014 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-019 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-030 OBJECTIVE: 1.A
PLANT REFERENCE: GP-005
PLANT REFERENCE: T/S 3.10.7
Following a refueling outage, the reactor was operated at full
power for 118 days and then shutdown for 35 days for required
maintenance. A plant startup has just been performed to 20%
power. What RATE LIMITS, if any, apply to the REACTOR POWER
INCREASE from 20% to full power?
a. 5%/minute
b. 3%/minute
c. 10%/hour
d. 3%/hour
ANSWER
8
A.
[Normal design limits of GP-005 apply (5% min or 10% step
increase). 35 days shutdown does not apply toward 30 days
of cumulative reactor power operation, so Tech. Spec.
restrictions do not apply.1
PAGE 31
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
9
ITEM ID: B-141
POINT VALUE:
1.6
LESSON PLAN: NI-LP-004 OBJECTIVE: 5
LESSON PLAN: PLR-LP-38
OBJECTIVE:
3
LESSON PLAN: PROC-LP-29
OBJECTIVE: 1
LESSON PLAN: RO-SE-034
OBJECTIVE: 1
LESSON PLAN: RO-SE-039
OBJECTIVE: 1
LESSON PLAN: RO-SE-041
OBJECTIVE: 2
LESSON PLAN: RO-SE-044 OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-013
OBJECTIVE: 6
LESSON PLAN: SR-SE-003
OBJECTIVE: 2
LESSON PLAN: SR-SE-006 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-008 OBJECTIVE: 1.B
LESSON PLAN: SR-SE-010 OBJECTIVE: 1.B
PLANT REFERENCE: GP-005
PLANT REFERENCE: OP-002
During plant startup with power at 5%, N-35 detector fails low.
Determine the most appropriate response:
a. Hot shutdown must be established since power is less than P-10.
b. Startup may continue since only (1) IR channel is required to
W
be operable.
c. N-35 trips must be inserted prior to continuing the startup.
d. Hot shutdown must be established since the minimum degree of
redundancy cannot be met.
ANSWER
9
b.
PAGE 32
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 10
ITEM ID: B-178
POINT VALUE:
1.6
LESSON PLAN: ESF-LP-3
OBJECTIVE: 1
LESSON PLAN: PROC-LP-31 OBJECTIVE: 1.A
LESSON PLAN: PROC-LP-31
OBJECTIVE: 2.A
LESSON PLAN: RO/SRO-SE-024 OBJECTIVE: 1
PLANT REFERENCE: GP-002
A RCS heatup is in progress in accordance with GP-002 (cold solid
to hot subcritical at no-load Tavg).
RCS temperature is 198
degrees with an established heatup rate of approximately 25
degrees/hr. The RO notices that BOTH level channels on "A" SI
accumulator indicate 58% and BOTH pressure channels indicate 580
psig.
Select the most appropriate course of action:
a. Continue the -heatup-and fill/pressurize the accumulator when RCS
temperature is 350 dejF and prior to exceeding 1000 PSIG.
b. Stop the heatup and fill/pressurize the accumulator.
c. Continue the heatup, but fill/pressurize the accumulator prior
to reaching RCS temperature of 350 degF and exceeding 1000 psig.
d. Stop the heatup, vent the RCS and fill/pressurize the
ANSWER 10
a.
PAGE 33
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
11
ITEM ID: B-183
POINT VALUE:
1.7
LESSON PLAN: EOP-LP-04
OBJECTIVE: 3
LESSON PLAN: EOP-LP-12
OBJECTIVE: 1
LESSON PLAN: RO-SE-068
OBJECTIVE: 1
LESSON PLAN: RO-SE-070
OBJECTIVE: 1
LESSON PLAN: RO-SE-070 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-015 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-015 OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-028 OBJECTIVE: 4
LESSON PLAN: SR-SE-019 OBJECTIVE: 2.A
LESSON PLAN: SR-SE-023 OBJECTIVE: 3
PLANT REFERENCE: PATH 2
Concerning a Steam Generator Tube Rupture (SGTR) accident, if ALL
three SGs were ruptured, Path-2 would direct you to:
a. EPP-16 (Uncontrolled Depressurization of all Steam
Generators)
b. EPP-17 (SGTR with Loss of Reactor Coolant:
Subcooled
Recovery)
c. EPP-18 (SGTR with Loss of Reactor Coolant:
Saturated
Recovery)
d. EPP-019 (SGTR Without Pressurizer Pressure Control)
ANSWER 11
b.
PAGE 34
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 12
ITEM ID: B-211
POINT VALUE:
1.6
LESSON PLAN: EOP-LP-12 OBJECTIVE: 2
LESSON PLAN: RO-SE-032 OBJECTIVE: 1
LESSON PLAN: RO-SE-068 OBJECTIVE: 1
LESSON PLAN: RO-SE-068 OBJECTIVE: 2
LESSON PLAN: RO-SE-070 OBJECTIVE: 1
LESSON PLAN: RO-SE-070 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-015 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-015 OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-028 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-032 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-037 OBJECTIVE: 7
LESSON PLAN: SR-SE-004
OBJECTIVE: 4
LESSON PLAN: SR-SE-019 OBJECTIVE: 2.A
LESSON PLAN: SR-SE-019 OBJECTIVE: 2.B
PLANT REFERENCE: EPP-017
The Operating Shift is performing Step 19 of EPP-017 (SGTR With
Loss Of Reactor Coolant: Subcooled Recovery).
The following
conditions exist:
- No RCPs running
- RCS hot leg temp:
370 degrees
- 2 SI pumps running
- RCS subcooling: 85 degrees
- 1 charging pump running
- CV pressure: 5 psig
- 1 RHR pump running
- PZR level: 52%
The Operating Shift should:
a. Stop 1 SI pump AND determine if the other SI pump should be
stopped.
b. Stop 1 SI pump AND check if normal charging should be
established.
c. Leave SI pumps running then go to Step 24.
d. Leave SI pumps running AND depressurize to refill pressurizer.
ANSWER 12
a.
PAGE 35
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 13
ITEM ID: B-230
POINT VALUE:
1.30
LESSON PLAN: CVC-LP-005
OBJECTIVE: 4
LESSON PLAN: PLR-LP-37
OBJECTIVE:
1
LESSON PLAN: RCS-LP-006A
OBJECTIVE:
2
LESSON PLAN: RO-SE-027
OBJECTIVE:
5
LESSON PLAN: RO-SE-044 OBJECTIVE: 3
LESSON PLAN: RO-SE-054
OBJECTIVE:
1
LESSON PLAN: RO/SRO-SE-003
OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-017 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-026 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-029 OBJECTIVE: 4
LESSON PLAN: SR-SE-012 OBJECTIVE: 1
LESSON PLAN: SR-SE-012
OBJECTIVE: 2
LESSON PLAN: SR-SE-027
OBJECTIVE: 1
PLANT REFERENCE: AOP-018
PLANT REFERENCE: APP-0O1
With the plant at 100% power and all systems in the
normal/automatic mode you get the following annunciators and
indications:
- RC PMPS SHFT #1 SEAL LEAK HI TEMP
RC
PMPS SEAL LEAKOFF HI FLOW
OC
PMPS SEAL LEA/OFF LO FLOW
- RC PMPS SHFT SEAL WTR LO DELTA-P
- #1 Seal leakoff for "B" RCP is pegged high
- #1 Seal leakoff for "All & "C" RCP's are pegged low
What IMMEDIATE operator actions are required (if any)?
a. AOP-O18, Section A
b. AOP-018, Section B
c. AOP-014O Section B
d. AOP-014, Section c
ANSWER 13
b .
LESN0LN
PAGE 36
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 14
ITEM ID: B-236
POINT VALUE:
1.6
LESSON PLAN: AOP-LP-04 OBJECTIVE: 3
LESSON PLAN: RO-SE-044 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-013 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-013 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-013 OBJECTIVE: 4
LESSON PLAN: RXTH-LP-51 OBJECTIVE: 3
LESSON PLAN: SR-SE-003
OBJECTIVE: 1
LESSON PLAN: SR-SE-008
OBJECTIVE: 1.A
LESSON PLAN: SR-SE-010 OBJECTIVE: 1.A
PLANT REFERENCE: CURVE 1.8
PLANT REFERENCE: GP-003
At 9000 MWD/MT, in Cycle 15 a reactor startup is in progress. The ECP is
calculated for criticality at 130 steps on D bank. The Reactor
Operator declares the reactor critical at 40 steps on D bank.
Which one of the following is the required operator action?
a. The reactor must be shutdown, applicable portions of GP-006
must be completed, the condition must be evaluated, and a new
startup number assigned for the subsequent startup.
)
b. The reactor must be shutdown, via reactor trip,
the condition must be evaluated, and the same startup
number will be used.
c. The startup may continue provided the Reactor Engineer and the
Operations Manager are informed and with the Plant General Manager's
permission.
d. The startup may continue provided the Reactor Engineer and the
Operations Manager are informed and that the disagreement
between the actual critical position and the ECP are noted in
the RO's AND the SF's logs.
ANSWER 14
a.
PAGE 37
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 15
ITEM ID: B-245
POINT VALUE:
1.00
LESSON PLAN: EP-LP-06 OBJECTIVE: 3
LESSON PLAN: EP-LP-07
OBJECTIVE: 3
LESSON PLAN: RO-SE-034 OBJECTIVE: 3
LESSON PLAN: RO-SE-034
OBJECTIVE: 4
LESSON PLAN: RO-SE-039
OBJECTIVE:
3
LESSON PLAN: RO-SE-039
OBJECTIVE: 4
LESSON PLAN: RO-SE-043
OBJECTIVE: 5
LESSON PLAN: RO-SE-052 OBJECTIVE: 3
LESSON PLAN: RO-SE-057 OBJECTIVE: 4
LESSON PLAN: RO-SE-068 OBJECTIVE: 2
LESSON PLAN: RO-SE-070 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-009 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-009 OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-009 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-009
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-015
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-015
OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-016 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-016 OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-01B OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-018 OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-021 OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-023
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-027
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-027
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-028
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-029 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-030 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-031 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-032 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-033
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-033
OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-034
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-034
OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-035
OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-037 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-037 OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-037 OBJECTIVE: 8
LESSON PLAN: RO/SRO-SE-038
OBJECTIVE: 5
LESSON PLAN: SR-SE-004
OBJECTIVE: 4
LESSON PLAN: SR-SE-00S
OBJECTIVE: 2.A
LESSON PLAN: SR-SE-005 OBJECTIVE: 2.B
LESSON PLAN: SR-SE-008
OBJECTIVE: 2.C
LESSON PLAN: SR-SE-008 OBJECTIVE: 2.C
LESSON PLAN: SR-SE-010 OBJECTIVE: 2.A
LESSON PLAN: SR-SE-010 OBJECTIVE: 2.B
LESSON PLAN: SR-SE-Oil
OBJECTIVE: 2
LESSON PLAN: SR-SE-Oil
OBJECTIVE: 3
LESSON PLAN: SR-SE-012
OBJECTIVE: 3
LESSON PLAN: SR-SE-012
OBJECTIVE: 7
LESSON PLAN: SR-SE-013
OBJECTIVE: 2.A
LESSON PLAN: SR-SE-014
OBJECTIVE: 2.C
LESSON PLAN: SR-SE-016 OBJECTIVE: 1.B
LESSON PLAN: SR-SE-019 OBJECTIVE: 2.B
LESSON PLAN: SR-SE-022
OBJECTIVE: 3
PAGE 38
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
LESSON PLAN: SR-SE-022 OBJECTIVE: 4
LESSON PLAN: SR-SE-023 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-025 OBJECTIVE: 2.A
LESSON PLAN: SR-SE-025
OBJECTIVE: 2.B
LESSON PLAN: SR-SE-025
OBJECTIVE: 2.C
LESSON PLAN: SR-SE-028
OBJECTIVE: 1.A
LESSON PLAN: SR-SE-028
OBJECTIVE: 1.B
LESSON PLAN: SR-SE-028 OBJECTIVE: 1.C
LESSON PLAN: SR-SE-030
OBJECTIVE: 2.C
PLANT REFERENCE: PEP-171
The plant has experienced a small break LOCA. The Shift Supervisor
has assumed the Site Emergency Coordinator position and declared
a Site Emergency.
You have been designated to be the Emergency
Communicator. Which one of the following phone numbers should be
used to notify the NRC?
a.
(404)
331-5085
b.
(301)
951-6000
c.
(301) 951-1212
d.
(301) 951-0550
. ANSWER 15
d.
PAGE 39
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION
16
ITEM ID: B-322
POINT VALUE:
1.1
LESSON PLAN: EOP-LP-03
OBJECTIVE: 3
LESSON PLAN: EOP-LP-11 OBJECTIVE: 2
LESSON PLAN: EOP-LP-11 OBJECTIVE: 4
LESSON PLAN: MDTA-LP-07
OBJECTIVE: 1
LESSON PLAN: RO-SE-034 OBJECTIVE: 4
LESSON PLAN: RO-SE-051 OBJECTIVE: 3
LESSON PLAN: RO-SE-056 OBJECTIVE: 2
LESSON PLAN: RO-SE-074 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-016 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-023 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-031 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-033 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-037
OBJECTIVE: 6
LESSON PLAN: SR-SE-011 OBJECTIVE: 2
LESSON PLAN: SR-SE-014
OBJECTIVE: 2.C
PLANT REFERENCE: EPP-011
Following a reactor trip from 100% power, a main steam safety
valve on the "A" steam generator (SG) lifts and fails to reseat.
During recovery actions that follow, feedwater flow to the "A" SG
should be
. a. Controlled to maintain a minimum level of 10%.
b. Controlled to maintain a minimum level of 25%.
c. Maintained at 25 gpm.
d. Isolated.
ANSWER 16
d.
PAGE 40
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 17
ITEM ID: B-342
POINT VALUE:
1.1
LESSON PLAN: RHR-LP-003 OBJECTIVE: 4.A
LESSON PLAN: RHR-LP-003
OBJECTIVE: 4.B
LESSON PLAN: PLR-LP-25 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-016 OBJECTIVE: 1.A
LESSON PLAN: RHR-LP-003 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-020 OBJECTIVE: 1
PLANT REFERENCE: AOP-020
PLANT REFERENCE: AOP-014
PLANT REFERENCE: OP-201
PLANT REFERENCE: APP-001
The following conditions exist with the plant in Cold Shutdown
and drained for removal of "B" steam generator manways.
RCS level
= approximately -72
inches, stable
"A" RHR pump running light = ON
RHR flow (FI-605)
= erratic, 1000 to 3000 gpm
RCS temperature
= 95 degrees, increasing
CV sump level
= none
= none
. The event that is the most likely cause of these conditions is
a. Cavitation due to vortex formation at the RHR hot leg suction
b. RHR system leak
c. Loss of running CCW pump
d. RHR-FCV-605 (RHR heat exchanger bypass flow control
valve) is failed closed.
ANSWER 17
a.
PAGE 41
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 18
ITEM ID: B-447
POINT VALUE:
1.20
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 1
LESSON PLAN: SR-SE-011 OBJECTIVE: 2
PLANT REFERENCE: CURVE 7.3
The plant is operating at 750 MWe gross, and 100 MVAR
positive reactive when a leak occurs on the Generator
Hydrogen system. Generator Hydrogen pressure drops to
50 psig. Concerning generator load, what action should
the Operator perform?
a. The Operator must reduce load to < app. 700 MWe gross
b. The Operator must reduce load to < app. 590 MWe gross
c. The Operator must reduce load to < app. 450 MWe gross
d. The Operator must reduce reactive load to zero (0).
ANSWER 18
a.
PAGE 42
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 19
ITEM ID: B-455
POINT VALUE:
1.6
LESSON PLAN: ARP-LP-05
OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-019 OBJECTIVE: 3
PLANT REFERENCE: DSP-003
The crew is operating IAW DSP-003 due to a fire in the charging
pump room. RCS inventory is being maintained using a safety
injection pump. You are not intentionally depressurizing the RCS,
but when a pressure decrease causes subcooling to decrease to 35 degrees
F, you are directed to secure the SI pump. Why?
a. THE INSURGE OF SI FLOW IS GREATER THAN THE PZR HEATERS CAN
HANDLE
b. TO BRING PZR LEVEL BELOW 70%.
c. PREVENT THERMAL SHOCK TO PZR SURGE LINE.
d. TO PREVENT LOSS OF RCP'S
(TRIP CRITERIA; 25 DEGREES F.)
ANSWER 19
a.
PAGE 43
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 20
ITEM ID: B-475
POINT VALUE:
1.6
LESSON PLAN: RO/SRO-SE-005 OBJECTIVE: 1
LESSON PLAN: SR-SE-025
OBJECTIVE: 1.A
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-036
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-037
OBJECTIVE: 4
PLANT REFERENCE: GP-006
While removing the unit from the line, the Operator
closed the MSR shutoff valves at 5% power/turbine
load. A steam flow spike occurred which resulted in
a reactor trip and SI. Choose the statement below
that best describes why this event may have occurred.
a. A S/G Safety opened on closing the MSR shutoff valves.
b. The turbine momentarily attempted overspeed as the MSR's
became more efficient.
c. Power level was too low to perform this evolution since
the MSR timer valves will all momentarily open when a
shutoff valve is closed.
d. There is NO logical reason for this to have occurred.
ANSWER 20
c.
PAGE 44
TEST ANSWERS
TEST ID: WEEK 3-93 SRO
ANNUAL LOR EXAM -
SRO WRITTEN
QUESTION 21
ITEM ID: B-498
POINT VALUE:
1.0
PLANT REFERENCE: 10CFR20
PLANT REFERENCE: HPP-001
What is the minimum radiation level required to post an area
"GRAVE DANGER VERY HIGH RADIATION AREA"?
a. 100 Rad/hr
b. 300 Rad/hr
c.
500 Rad/hr
d. 1000 Rad/hr
ANSWER 21
C.
- E***** **
END OF EXAM
NAME:
DATE:
CLASS: H.B. ROBINSON LOR
EXAM:
ANNUAL LOR EXAM -
RO WRITTEN
PREPARED BY: GUY LEVY
GRADED
BY:
ALTERNATE GRADER:
(if required)
TOTAL POINTS:
29.7
POINTS MISSED:
1. EXAM TIME LIMIT IS 2 HRS
2. DO NOT write on back of pages.
3. A score of 80% is required for passing.
4. Use only black ink on this exam. Cross out all
errors with a single line initial and date.
I have neither given nor received help on this exam.
All work is my own.
Signature
PAGE 24
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
1
ITEM ID: B-005
POINT VALUE:
1.2
LESSON PLAN: PLR-LP-58 OBJECTIVE: 4
LESSON PLAN: PROC-LP-39
OBJECTIVE: 1
LESSON PLAN: RCS-LP-009
OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-015
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-034
OBJECTIVE:
6
LESSON PLAN: RO/SRO-SE-035 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-035 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-035 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 4
LESSON PLAN: SR-SE-004
OBJECTIVE: 3
LESSON PLAN: SR-SE-028 OBJECTIVE: 1.A
PLANT REFERENCE: AOP-016
PLANT REFERENCE: T/S 3.1.5.3
During normal full power operation, radiation monitors for SG
blowdown and condenser-vacuum pump effluent were observed to be
increasing.
OST-051 "RCS Leakage Evaluation" was performed and
results were 0.6 gpm. SG chemistry samples identify a primary
to secondary leak on "C" SG of 0.4 gpm.
. Based on this information, which of the following actions is
correct?
a. Power operation can continue. Continue to monitor RCS
leakage.
b. Place the reactor in a hot shutdown condition within 12
hours.
c. Place the reactor in a cold shutdown condition within 30
hours.
d. Place the reactor in a cold shutdown condition within 36
hours.
ANSWER
1
C.
PAGE 25
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
2
ITEM ID: B-006
POINT VALUE:
1.1
LESSON PLAN: PROC-LP-38 OBJECTIVE: 1.D
LESSON PLAN: RDCNT-LP-004 OBJECTIVE: 1
LESSON PLAN: RO-SE-021 OBJECTIVE: 2
LESSON PLAN: RO-SE-057 OBJECTIVE: 3
LESSON PLAN: RO-SE-066 OBJECTIVE: 2
LESSON PLAN: SR-SE-006 OBJECTIVE: 2.D
LESSON PLAN: RO/SRO-SE-021 OBJECTIVE: 1
PLANT REFERENCE: T/S 3.10.6.2
PLANT REFERENCE: T/S 3.0
AOP-001, Section 4.0 (Dropped rod) immediate actions state that
"if two or more control rods have been dropped, then proceed with
an orderly shutdown to the hot shutdown condition."
What time limits, if any, apply to establishing hot shutdown
conditions.
a. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
d. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
ANSWER
2
d.
PAGE 26
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
3
ITEM ID: B-009
POINT VALUE:
1.4
LESSON PLAN: PROC-LP-38 OBJECTIVE: 1.D
LESSON PLAN: RO-SE-059 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 3
PLANT REFERENCE: AOP-001
PLANT REFERENCE: OMM-024
PLANT REFERENCE: SD-007
PLANT REFERENCE: T/S 3.10.1.5
HBR Unit #2 is at 90% power with all controls in automatic. D
Control Bank group step counters indicate 196 steps. ERFIS is
operable. A check of the rod position indications for D Control
Bank show that:
a. Rod D8:
124 inches
b. Rod M8:
116 inches
c.
Rod H4:
120 inches
d. Rod H8:
121 inches
e. Rod H12: 131 inches
Are the control rods in D control bank properly aligned? Justify
. your answer by explaining how any limits are or are not met.
ANSWER
3
No. (0.4) H12 deviates > 7.5 inches from the average of the
RPIs (122.4 in.) (1.0)
PAGE 27
TEST ANSWERS
)
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
4
ITEM ID: B-020
POINT VALUE:
1.2
LESSON PLAN: EOP-LP-17
OBJECTIVE: 3
LESSON PLAN: MDTA-LP-08
OBJECTIVE: 3
LESSON PLAN: RO-SE-069
OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-009 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-026 OBJECTIVE: 4
LESSON PLAN: SR-SE-010 OBJECTIVE: 2.B
PLANT REFERENCE: ERG-FR-H.1
PLANT REFERENCE: FRP-H.1
FRP-H.1 (Response to Loss of Secondary Heat Sink) requires
tripping of the RCPs and the immediate initiation of RCS bleed
and feed, if
ANY SG wide range level decreases to less than 60%
[63%).
Choose the statement that correctly explains why the
RCPs are required to be tripped.
a. Delays loss of RCS inventory
b. Allows presure reduction to below SI shutoff head
c. Prevents uncovering the core after subcooling is lost
d. Reduces RCS heat input and extends time to S/G dryout
ANSWER
4
d.
PAGE 28
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
5
ITEM ID: B-051
POINT VALUE:
1.20
LESSON PLAN: RO-SE-028
OBJECTIVE: 2
LESSON PLAN: RO-SE-028
OBJECTIVE: 3
LESSON PLAN: RO-SE-031
OBJECTIVE: 2
LESSON PLAN: RO-SE-045
OBJECTIVE: 2
LESSON PLAN: SR-SE-028
OBJECTIVE: 1.B
LESSON PLAN: RO/SRO-SE-027 OBJECTIVE: 4.A
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 4
PLANT REFERENCE: CURVE 8.23
PLANT REFERENCE: OST-051
With the plant operating at 100% power, a pressurizer safety
valve begins to leak.
If PRT level increases from 71% to 76% (as indicated on LI-470)
over a one hour-period-, the RCS leakage rate through the safety
valve would be closest to:
a. 2 gpm
b. 5 gpm
c.
10 gpm
d. 20 gpm
ANSWER
5
c.
PAGE 29
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL
LOR EXAM
-
RO WRITTEN
QUESTION
6
ITEM ID: B-058
POINT VALUE:
1.2
LESSON PLAN: EOP-LP-03 OBJECTIVE: 1
LESSON PLAN: EOP-LP-03
OBJECTIVE: 4
LESSON PLAN: MDTA-LP-07
OBJECTIVE: 1
LESSON PLAN: RO-SE-034
OBJECTIVE: 4
LESSON PLAN: RO-SE-074
OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-016
OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-023
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-031 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-033
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-037 OBJECTIVE: 6
LESSON PLAN: SR-SE-Oil OBJECTIVE: 2
LESSON PLAN: SR-SE-014
OBJECTIVE: 2.C
PLANT REFERENCE: PATH 1
Assume that the "B" steam generator main steam line completely
shears inside containment.
Assuming that all Reactor Protection
and Engineered Safeguards Features equipment operate as designed
and that all actions are taken as required by plant procedures,
what procedure will be used to secure safety injection?
-a.
EPP-008
b. Path-2
c. EPP-7
d. EPP-11
ANSWER
6
C.
PAGE 30
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
7
ITEM ID: B-099
POINT VALUE:
2.00
LESSON PLAN: FUEL-LP-002
OBJECTIVE: 3
LESSON PLAN: PLR-LP-59
OBJECTIVE: 6
LESSON PLAN: PROC-LP-38
OBJECTIVE: 1.E
LESSON PLAN: RO-SE-039
OBJECTIVE: 2
LESSON PLAN: RO-SE-043 OBJECTIVE: 1
LESSON PLAN: RO-SE-052 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-004 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-015 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 4
LESSON PLAN: SR-SE-003
OBJECTIVE: 3
LESSON PLAN: SR-SE-006
OBJECTIVE:
1.B
LESSON PLAN: SR-SE-008 OBJECTIVE: 1.C
LESSON PLAN: SR-SE-010
OBJECTIVE: 1.C
LESSON PLAN: SR-SE-011 OBJECTIVE: 1
LESSON PLAN: SR-SE-013 OBJECTIVE: 1
LESSON PLAN: SR-SE-014 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-019 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-030 OBJECTIVE: 1.A
PLANT REFERENCE: GP-005
PLANT REFERENCE: T/S 3.10.7
Following a refueling outage, the reactor was operated at full
power for 118 days and then shutdown for 35 days for required
maintenance. A plant startup has just been performed to 20%
power. What RATE LIMITS, if any, apply to the REACTOR POWER
INCREASE from 20% to full power?
a. 5%/minute
b. 3%/minute
c. 10%/hour
d. 3%/hour
ANSWER
7
A.
[Normal design limits of GP-005 apply (5% min or 10% step
increase). 35 days shutdown does not apply toward 30 days
of cumulative reactor power operation, so Tech. Spec.
restrictions do not apply.)
PAGE 31
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
8
ITEM ID: B-121
POINT VALUE:
1.20
LESSON PLAN: AOP-LP-11
OBJECTIVE: 3
PLANT REFERENCE: OMM-001
PLANT REFERENCE: OP-101
PLANT REFERENCE: OP-305
PLANT REFERENCE: OP-301
After reviewing the tasks listed below, select the ONE that would
NOT require documentation by the completion of a procedure.
a. Filling "B" RCP standpipe with primary water in response to a
low level alarm
b.
Starting "C" RCP during RCS fill and vent operations
c. Placing "C" CVCS hold-up tank on recirculation for sampling
d. Blending make-up to the RWST to establish required Tech.
Spec. level
ANSWER
8
a.
PAGE 32
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
9
ITEM ID: B-141
POINT VALUE:
1.6
LESSON PLAN: NI-LP-004
OBJECTIVE: 5
LESSON PLAN: PLR-LP-38
OBJECTIVE: 3
LESSON PLAN: PROC-LP-29
OBJECTIVE: 1
LESSON PLAN: RO-SE-034
OBJECTIVE: 1
LESSON PLAN: RO-SE-039
OBJECTIVE: 1
LESSON PLAN: RO-SE-041
OBJECTIVE: 2
LESSON PLAN: RO-SE-044
OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-013
OBJECTIVE: 6
LESSON PLAN: SR-SE-003
OBJECTIVE: 2
LESSON PLAN: SR-SE-006
OBJECTIVE: 1.A
LESSON PLAN: SR-SE-008 OBJECTIVE: 1.B
LESSON PLAN: SR-SE-010 OBJECTIVE: 1.B
PLANT REFERENCE: GP-005
PLANT REFERENCE: OP-002
During plant startup with power at 5%, N-35 detector fails low.
Determine the most appropriate response:
a. Hot shutdown must be established since power is less than P-10.
. b. Startup may continue since only (1) IR channel is required to
be operable.
c. N-35 trips must be inserted prior to continuing the startup.
d. Hot shutdown must be established since the minimum degree of
redundancy cannot be met.
ANSWER
9
b.
PAGE 33
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
---
QUESTION 10
ITEM ID: B-178
POINT VALUE:
1.6
LESSON PLAN: ESF-LP-3
OBJECTIVE: 1
LESSON PLAN: PROC-LP-31 OBJECTIVE: 1.A
LESSON PLAN: PROC-LP-31 OBJECTIVE: 2.A
LESSON PLAN: RO/SRO-SE-024 OBJECTIVE: 1
PLANT REFERENCE: GP-002
A RCS heatup is in progress in accordance with GP-002 (cold solid
to hot subcritical at no-load Tavg).
RCS temperature is 198
degrees with an established heatup rate of approximately 25
degrees/hr. The RO notices that BOTH level channels on "A" SI
accumulator indicate 58% and BOTH pressure channels indicate 580
psig.
Select the most appropriate course of action:
a. Continue the heatup-and fill/pressurize the accumulator when RCS
temperature is 350 deqF and prior to exceeding 1000 PSIG.
b. Stop the heatup and fill/pressurize the accumulator.
c. Continue the heatup, but fill/pressurize the accumulator prior
to reaching RCS temperature of 350 degF and exceeding 1000 psig.
d. Stop the heatup, vent the RCS and fill/pressurize the
ANSWER 10
a.
PAGE 34
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION 11
ITEM ID: B-183
POINT VALUE:
1.7
LESSON PLAN: EOP-LP-04 OBJECTIVE: 3
LESSON PLAN: EOP-LP-12 OBJECTIVE: 1
LESSON PLAN: RO-SE-068 OBJECTIVE: 1
LESSON PLAN: RO-SE-070 OBJECTIVE: 1
LESSON PLAN: RO-SE-070 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-015
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-015
OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-028
OBJECTIVE: 4
LESSON PLAN: SR-SE-019 OBJECTIVE: 2.A
LESSON PLAN: SR-SE-023 OBJECTIVE: 3
PLANT REFERENCE: PATH 2
Concerning a Steam Generator Tube Rupture (SGTR) accident, if ALL
three SGs were ruptured, Path-2 would direct you to:
a. EPP-16 (Uncontrolled Depressurization of all Steam
Generators)
b. EPP-17 (SGTR with Loss of Reactor Coolant:
Subcooled
Recovery)
c. EPP-18 (SGTR with Loss of Reactor Coolant:
Saturated
.
Recovery)
d. EPP-019 (SGTR Without Pressurizer Pressure Control)
ANSWER 11
b.
PAGE 35
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION 12
ITEM ID: B-211
POINT VALUE:
1.6
LESSON PLAN: EOP-LP-12
OBJECTIVE: 2
LESSON PLAN: RO-SE-032
OBJECTIVE: 1
LESSON PLAN: RO-SE-068 OBJECTIVE: 1.
LESSON PLAN: RO-SE-068 OBJECTIVE: 2
LESSON PLAN: RO-SE-070 OBJECTIVE: 1
LESSON PLAN: RO-SE-070 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-015 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-015 OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-028 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-032 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-037 OBJECTIVE: 7
LESSON PLAN: SR-SE-004 OBJECTIVE: 4
LESSON PLAN: SR-SE-019 OBJECTIVE: 2.A
LESSON PLAN: SR-SE-019 OBJECTIVE: 2.B
PLANT REFERENCE: EPP-017
The Operating Shift is performing Step 19 of EPP-017 (SGTR With
Loss Of Reactor Coolant: Subcooled Recovery).
The following
conditions exist:
- No RCPs running
- RCS hot leg temp:
370 degrees
- 2 SI pumps running
- RCS subcooling: 85 degrees
- 1 charging pump running
- CV pressure: 5 psig
- 1 RHR pump running
- PZR level: 52%
The Operating Shift should:
a. Stop 1 SI pump AND determine if the other SI pump should be
stopped.
b. Stop 1 SI pump AND check if normal charging should be
established.
c. Leave SI pumps running then go to Step 24.
d. Leave SI pumps running AND depressurize to refill pressurizer.
ANSWER
12
a.
PAGE 36
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL
LOR EXAM -
RO WRITTEN
QUESTION
13
ITEM ID: B-230
POINT VALUE:
1.30
LESSON PLAN: CVC-LP-005
OBJECTIVE: 4
LESSON PLAN: PLR-LP-37
OBJECTIVE:
1
LESSON PLAN: RCS-LP-006A
OBJECTIVE: 2
LESSON PLAN: RO-SE-027
OBJECTIVE: 5
LESSON PLAN: RO-SE-044
OBJECTIVE: 3
LESSON PLAN: RO-SE-054
OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-003
OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-017
OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-026
OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-029 OBJECTIVE: 4
LESSON PLAN: SR-SE-012 OBJECTIVE: 1
LESSON PLAN: SR-SE-012 OBJECTIVE: 2
LESSON PLAN: SR-SE-027 OBJECTIVE: 1
PLANT REFERENCE: AOP-018
PLANT REFERENCE: APP-001
With the plant at 100% power and all systems in the
normal/automatic mode you get the following annunciators and
indications:
- RC PMPS SHFT #1 SEAL LEAK HI TEMP
- RC PMPS SEAL LEAKOFF HI FLOW
- RC PMPS SEAL LEAKOFF LO FLOW
- RC PMPS SHFT SEAL WTR LO DELTA-P
- #1 Seal leakoff for "B" RCP is pegged high
- #1 Seal leakoff for "A" & "C" RCP's are pegged low
What IMMEDIATE operator actions are required (if any)?
a. AOP-018, Section A
b. AOP-018, Section B
c. AOP-014, Section B
d. AOP-014, Section c
ANSWER 13
b.
PAGE 37
TEST ANSWERS
)
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION 14
ITEM ID: B-236
POINT VALUE:
1.6
LESSON PLAN: AOP-LP-04 OBJECTIVE: 3
LESSON PLAN: RO-SE-044 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-013
OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-013
OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-013 OBJECTIVE: 4
LESSON PLAN: RXTH-LP-51 OBJECTIVE: 3
LESSON PLAN: SR-SE-003 OBJECTIVE: 1
LESSON PLAN: SR-SE-008 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-010 OBJECTIVE: 1.A
PLANT REFERENCE: CURVE 1.8
PLANT REFERENCE: GP-003
At 9000 MWD/MT, in Cycle 15 a reactor startup is in progress. The ECP is
calculated for criticality at 130 steps on D bank. The Reactor
Operator declares the reactor critical at 40 steps on D bank.
Which one of the following is the required operator action?
a. The reactor must be shutdown, applicable portions of GP-006
must be completed, the condition must be evaluated, and a new
startup number assigned for the subsequent startup.
b. The reactor must be shutdown, via reactor trip,
the condition must be evaluated, and the same startup
number will be used.
c. The startup may continue provided the Reactor Engineer and the
Operations Manager are informed and with the Plant General Manager's
permission.
d. The startup may continue provided the Reactor Engineer and the
Operations Manager are informed and that the disagreement
between the actual critical position and the ECP are noted in
the RO's AND the SF's logs.
ANSWER 14
a.
PAGE 38
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION 15
ITEM ID: B-245
POINT VALUE:
1.00
LESSON PLAN: EP-LP-06 OBJECTIVE: 3
LESSON PLAN: EP-LP-07
OBJECTIVE:
3
LESSON PLAN: RO-SE-034
OBJECTIVE:
3
LESSON PLAN: RO-SE-034
OBJECTIVE: 4
LESSON PLAN: RO-SE-039
OBJECTIVE:
3
LESSON PLAN: RO-SE-039 OBJECTIVE: 4
LESSON PLAN: RO-SE-043
OBJECTIVE: 5
LESSON PLAN: RO-SE-052
OBJECTIVE: 3
LESSON PLAN: RO-SE-057
OBJECTIVE: 4
LESSON PLAN: RO-SE-068 OBJECTIVE: 2
LESSON PLAN: RO-SE-070 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-009 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-009 OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-009 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-009
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-015
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-015
OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-016
OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-016
OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-018 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-018 OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-021 OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-023 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-027 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-027 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-028 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-029 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-030
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-031
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-032
OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-033 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-033 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-035 OBJECTIVE: 2
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-037
OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-037
OBJECTIVE: 7
LESSON PLAN: RO/SRO-SE-037
OBJECTIVE: 8
LESSON PLAN: RO/SRO-SE-038 OBJECTIVE: 5
LESSON PLAN: SR-SE-004 OBJECTIVE: 4
LESSON PLAN: SR-SE-005 OBJECTIVE: 2.A
LESSON PLAN: SR-SE-005 OBJECTIVE: 2.B
LESSON PLAN: SR-SE-008 OBJECTIVE: 2.C
LESSON PLAN: SR-SE-008 OBJECTIVE: 2.C
LESSON PLAN: SR-SE-010 OBJECTIVE: 2.A
LESSON PLAN: SR-SE-010 OBJECTIVE: 2.B
LESSON PLAN: SR-SE-Oil OBJECTIVE: 2
LESSON PLAN: SR-SE-034
OBJECTIVE: 3
LESSON PLAN: SR-SE-012
OBJECTIVE: 3
PAGE 39
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
LESSON PLAN: SR-SE-012
OBJECTIVE: 7
LESSON PLAN: SR-SE-013
OBJECTIVE:
2.A
LESSON PLAN: SR-SE-014 OBJECTIVE: 2.C
LESSON PLAN: SR-SE-016
OBJECTIVE: 1.B
LESSON PLAN: SR-SE-019
OBJECTIVE: 2.B
LESSON PLAN: SR-SE-022
OBJECTIVE: 3
LESSON PLAN: SR-SE-022 OBJECTIVE: 4
LESSON PLAN: SR-SE-023 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-025 OBJECTIVE: 2.A
LESSON PLAN: SR-SE-025 OBJECTIVE: 2.B
LESSON PLAN: SR-SE-025 OBJECTIVE: 2.C
LESSON PLAN: SR-SE-028 OBJECTIVE: 1.A
LESSON PLAN: SR-SE-028 OBJECTIVE: 1.B
LESSON PLAN: SR-SE-028 OBJECTIVE: 1.C
LESSON PLAN: SR-SE-030 OBJECTIVE: 2.C
PLANT REFERENCE: PEP-171
The plant has experienced a small break LOCA. The Shift Supervisor
has assumed the Site Emergency Coordinator position and declared
a Site Emergency. You have been designated to be the Emergency
Communicator. Which one of the following phone numbers should be
used to notify the NRC?
. a. (404) 331-5085
b. (301) 951-6000
c. (301) 951-1212
d.
(301)
951-0550
ANSWER
15
d.
PAGE 40
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
16
ITEM ID: B-322
POINT VALUE:
1.1
LESSON PLAN: EOP-LP-03 OBJECTIVE: 3
LESSON PLAN: EOP-LP-11 OBJECTIVE: 2
LESSON PLAN: EOP-LP-11 OBJECTIVE: 4
LESSON PLAN: MDTA-LP-07 OBJECTIVE: 1
LESSON PLAN: RO-SE-034
OBJECTIVE: 4
LESSON PLAN: RO-SE-051
OBJECTIVE: 3
LESSON PLAN: RO-SE-056 OBJECTIVE: 2
LESSON PLAN: RO-SE-074
OBJECTIVE: 6
LESSON PLAN: RO/SRO-SE-016
OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-023
OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-031 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-033 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-037 OBJECTIVE: 6
LESSON PLAN: SR-SE-011 OBJECTIVE: 2
LESSON PLAN: SR-SE-014 OBJECTIVE: 2.C
PLANT REFERENCE: EPP-011
Following a reactor trip from 100% power, a main steam safety
valve on the "A" steam generator (SG) lifts and fails to reseat.
During recovery actions that follow, feedwater flow to the "A" SG
. should be
a. Controlled to maintain a minimum level of 10%.
b. Controlled to maintain a minimum level of 25%.
c. Maintained at 25 gpm.
d. Isolated.
ANSWER 16
d.
PAGE 41
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION 17
ITEM ID: B-342
POINT VALUE:
1.1
LESSON PLAN: RHR-LP-003 OBJECTIVE: 4.A
LESSON PLAN: RHR-LP-003 OBJECTIVE: 4.B
LESSON PLAN: PLR-LP-25
OBJECTIVE: 1.A
LESSON PLAN: SR-SE-016
OBJECTIVE:
1.A
LESSON PLAN: RHR-LP-003
OBJECTIVE:
5
LESSON PLAN: RO/SRO-SE-020
OBJECTIVE:
1
PLANT REFERENCE: AOP-020
PLANT REFERENCE: AOP-014
PLANT REFERENCE: OP-201
PLANT REFERENCE: APP-001
The following conditions exist with the plant in Cold Shutdown
and drained for removal of "B" steam generator manways.
RCS level
= approximately -72 inches, stable
"A" RHR pump running light = ON
RHR flow (FI-605)
= erratic, 1000 to 3000 gpm
RCS temperature
= 95 degrees, increasing
CV sump level
= none
= none
The event that is the most likely cause of these conditions is
a. Cavitation due to vortex formation at the RHR hot leg suction
b. RHR system leak
c. Loss of running CCW- pump
d. RHR-FCV-605 (RHR heat exchanger bypass flow control
valve) is failed closed.
ANSWER 17
a.
PAGE 42
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
18
ITEM ID: B-447
POINT VALUE:
1.20
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 1
LESSON PLAN: SR-SE-011 OBJECTIVE: 2
PLANT REFERENCE: CURVE 7.3
The plant is operating at 750 MWe gross, and 100 MVAR
positive reactive when a leak occurs on the Generator
Hydrogen system. Generator Hydrogen pressure drops to
50 psig. Concerning generator load, what action should
the Operator perform?
a. The Operator must reduce load to < app. 700 MWe gross
b. The Operator must reduce load to < app. 590 MWe gross
c. The Operator must reduce load to < app. 450 MWe gross
d. The Operator must reduce reactive load to zero (0).
ANSWER 18
a.
PAGE 43
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION 19
ITEM ID: B-455
POINT VALUE:
1.6
LESSON PLAN: ARP-LP-05 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-019
OBJECTIVE: 3
PLANT REFERENCE: DSP-003
The crew is operating IAW DSP-003 due to a fire in the charging
pump room. RCS inventory is being maintained using a safety
injection pump. You are not intentionally depressurizing the RCS,
but when a pressure decrease causes subcooling to decrease to 35 degrees
F, you are directed to secure the SI pump. Why?
a. THE INSURGE OF SI FLOW IS GREATER THAN THE PZR HEATERS CAN
HANDLE
b. TO BRING PZR LEVEL BELOW 70%.
c. PREVENT THERMAL SHOCK TO PZR SURGE LINE.
d. TO PREVENT LOSS OF RCP'S
(TRIP CRITERIA; 25 DEGREES F.)
ANSWER 19
a.
PAGE 44
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL
LOR EXAM -
RO WRITTEN
QUESTION 20
ITEM ID: B-475
POINT VALUE:
1.6
LESSON PLAN: RO/SRO-SE-005 OBJECTIVE: 1
LESSON PLAN: SR-SE-025 OBJECTIVE: 1.A
LESSON PLAN: RO/SRO-SE-034 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-037 OBJECTIVE: 4
PLANT REFERENCE: GP-006
While removing the unit from the line, the Operator
closed the MSR shutoff valves at 5% power/turbine
load. A steam flow spike occurred which resulted in
a reactor trip and SI. Choose the statement below
that best describes why this event may have occurred.
a. A S/G Safety opened on closing the MSR shutoff valves.
b. The turbine momentarily attempted overspeed as the MSR's
became more efficient.
c. Power level was too low to perform this evolution since
the MSR timer valves will all momentarily open when a
shutoff valve is closed.
d. There is NO logical reason for this to have occurred.
ANSWER
20
c.
PAGE 45
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
21
ITEM ID: B-480
POINT VALUE:
1.20
LESSON PLAN: SR-SE-005 OBJECTIVE: 1.C
LESSON PLAN: RO/SRO-SE-035 OBJECTIVE: 4
LESSON PLAN: RO/SRO-SE-035
OBJECTIVE: 5
LESSON PLAN: RO/SRO-SE-017
OBJECTIVE: 2
LESSON PLAN: SR-SE-005 OBJECTIVE: 1.A
PLANT REFERENCE: GP-007
When taking the PZR solid, indication that the PZR
is fully solid is provided by
a. An increase in letdown flow that exceeds
charging flow.
b. An increase in charging flow that exceeds
letdown flow.
c. PZR level channels LT-459, LT-460, & LT-461
indicating > 100%.
d. PZR level channel LT-462 (Cold Cal)
.
indicating > 100%.
ANSWER 21
a.
PAGE 46
TEST ANSWERS
TEST ID: WEEK 3-93 RO
ANNUAL LOR EXAM -
RO WRITTEN
QUESTION
22
ITEM ID: B-498
POINT VALUE:
1.0
PLANT REFERENCE: 10CFR20
PLANT REFERENCE: HPP-001
What is the minimum radiation level required to post an area
"GRAVE DANGER VERY HIGH RADIATION AREA"?
a. 100 Rad/hr
b. 300 Rad/hr
c.
500 Rad/hr
d. 1000 Rad/hr
ANSWER 22
C.
- ****
- ****
END OF EXAM
Attachment 6a
CAROLINA POWER & LIGHT COMPANY
3 -
o3
H.B. ROBINSON PLANT
STATIC SIMULATOR SCENARIO
MAIN FEEDWATER PUMP TRIP;
MANUAL RUNBACK
SSS-004
(Rev.4)
OPERATOR:
DATE:
TOTAL POINT VALUE (SRO):
14.4
TOTAL POINT VALUE
(RO):
14.4
TOTAL POINTS CORRECT:
SCENARIO QUESTIONS (Attached):
1. A-04-001
9. A-04-009
2. A-04-002
10. A-04-010
3. A-04-003
11. A-04-011
4. A-04-004
12. A-04-012
5. A-04-005
13. A-04-015
6. A-04-006
14. A-04-016
7. A-04-007
15. A-18-014
8. A-04-008
DEVELOPED BY:
DATE:
I 11z
REVIEWED BY:
______________
DATE:
Z/~
APPROVED
BY:
DATE:
'
Manager
-
License Training
SSS-004 (Rev.4)
Attachment 6b
SCENARIO SUMMARY SHEET
SCENARIO NO:
4
SCENARIO NAME: MAIN FEEDWATER PUMP TRIP/MANUAL RUNBACK
SCENARIO SUMMARY
The plant
is
operating at
100% power
(MOL)
with all
equipment operable.
A trip
of the "A" main feedwater pump occurs and the
operating shift
performs a runback to approximately 70% power
with the Main Turbine in turbine manual control.
are shifted to auto to allow rods to drive in to maintain Tag
approximately equal to Tref.
A loop
2
Thot instrument
has
failed low.
The steam dumps do not operate as required on the
runback.
SSS-004 (Rev.4)
Attachment 6c
SCENARIO SETUP CHECKLIST
SCENARIO NO.:
4
SCENARIO NAME: MAIN FEEDWATER PUMP TRIP/MANUAL RUNBACK
SCENARIO SETUP:
1.
Strip Charts
1.1
Turn off all strip charts.
1.2
Advance all strip charts.
2.
Run Scenario
2.1
Ensure ROD STEP COUNTER UNBLOCK is lit.
2.2
Run scenario per Attachment 6d.
2.3
Turn SPDS off
3.
ICCM
a.
Channel 1:
PT Curve (T/C Page 1)
b.
Channel 2:
Any channel.
4.
Mark First-Out Annunciator:
None.
5.
Position the following Switches:
None
6.
Clearance Tags:
None.
7.
Update status board information as follows:
a.
MWD/MTU:
6330
b.
RCS BORON: 507 ppm
c.
PRESSURIZER BORON:
507 ppm
d.
AXIAL OFFSET TARGET:
-0.5%
e.
AXIAL OFFSET TARGET BAND:
+ 5%
8.
Markup PATH-1 and/or PATH-2 if applicable: N/A
SSS-004 (Rev.4)
Attachment 6d
MANUAL SCENARIO SETUP SUMMARY
.
SCENARIO NO.:
4
SCENARIO NAME: MAIN FEEDWATER PUMP TRIP/MANUAL RUNBACK
1.
Initialize the simulator to IC-20.
Use prepared file
(FILE SSS4)
if
available,
and continue at
Step 3
2.
With the simulator frozen, insert the following:
COMMAND LINE
DESCRIPTION
a.
OVR CRF46C 2,1
Manual rod control off
b.
OVR CRF46D 1,1
Auto rod control on
c.
OVR TUR50D 3,1
VALVE POS LIMIT light as-is
d.
OVR TUR50Q 101,0,1
Valve position limit meter as-is
e.
MAL CFW15A ACT,300
MFW pump A trip
f.
MAL TUR21A ACT,1,303
Turbine limiter runback
g.
MAL TUR21B ACT,1,303
Turbine ref. runback
h.
OVR TUR41A-1,313
Turbine manual pushbutton ON
i.
XMT RCS55,510,2,1
Loop 2 Thot,TI-422B1 low
j.
OVR MSS20M 1,1
Steam Dump control OFF
3.
Verify proper simulator setup by using MAL STATUS,
OVR STATUS,
and LOA STATUS
4.
Ensure all strip chart recorders are running
5.
At the command line type:
RUN 430.
a.
Set NOISE SYN and AUDIBLE ANNUN off
b.
Acknowledge
all
2 seconds before the
simulator freeze (SIMTIME = 428).
6.
Immediately turn off all strip chart recorders
7.
Continue setup per Attachment 6c, Step 2.3
SSS-004 (Rev.4)
PAGE 17
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
1
ITEM ID: A-04-001
POINT VALUE:
0.70
LESSON PLAN: FW-LP-003 OBJECTIVE: 1
LESSON PLAN: FW-LP-003 OBJECTIVE: 4
LESSON PLAN: MS-LP-001 OBJECTIVE: 2
LESSON PLAN: PLR-LP-50 OBJECTIVE: 7
PLANT REFERENCE: SD-025
PLANT REFERENCE: SD-027
How would the steam driven AFW pump operation be affected if all
of the main steam isolation valves were shut?
a. Turbine warmup steam would be maintained and the pump
could still be operated.
b. Turbine warmup steam would be maintained but the pump
could NOT be operated
c. Turbine warmup steam would be lost but the pump could still
be operated.
d. Turbine warmup steam would be lost and the pump could not be
operated.
ANSWER
1
a.
PAGE 18
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
2
ITEM ID: A-04-002
POINT VALUE:
1.30
LESSON PLAN: ESF-LP-5 OBJECTIVE: 3
LESSON PLAN: FW-LP-003 OBJECTIVE: 2
LESSON PLAN: PLR-LP-50 OBJECTIVE: 8
LESSON PLAN: RO/SRO-SE-033
OBJECTIVE: 1
PLANT REFERENCE: SD-006
PLANT REFERENCE: SD-027
With current plant conditions, how would the plant be affected if
"A" steam generator level transmitter LT-474 suddenly failed LOW?
a. Both motor driven AFW pumps would automatically start.
b. Automatic reactor trip due to A steam generator LO-LO LEVEL.
c. "A" steam generator main feedwater regulating valve would
initially travel in the OPEN direction.
d. Only alarms/annnunciators would be received with no other
plant response.
ANSWER
2
d.
PAGE 19
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
3
ITEM ID: A-04-003
POINT VALUE:
0.80
LESSON PLAN: MS-LP-001 OBJECTIVE: 4
LESSON PLAN: PLR-LP-48 OBJECTIVE: 3
LESSON PLAN: RO-SE-041 OBJECTIVE: 3
LESSON PLAN: SR-SE-004 OBJECTIVE: 2
PLANT REFERENCE: SD-025
With present plant conditions, which statement below best
describes the proper operation of the steam dump system?
a. All steam dump valves are in proper position for plant
conditions.
b. The first bank of condenser dump valves should be partially open
c. Only five condenser dump valves should be fully (100%)
open.
d. In addition to all five condenser dump valves, the steam
generator power operated relief valves should be open.
ANSWER 3
b.
PAGE 20
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
4
ITEM ID: A-04-004
POINT VALUE:
1.10
LESSON PLAN: NI-LP-005 OBJECTIVE: 3
LESSON PLAN: PROC-LP-38
OBJECTIVE: 1.B
LESSON PLAN: RO-SE-025 OBJECTIVE: 2
LESSON PLAN: RO-SE-052
OBJECTIVE: 2
LESSON PLAN: RO-SE-063 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-021 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-024
OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-028 OBJECTIVE: 1.B
LESSON PLAN: RO/SRO-SE-036
OBJECTIVE: 2
PLANT REFERENCE: FMP-009
PLANT REFERENCE: T/S 3.10.2.8
Which statement is correct regarding the Power Distribution
Control (PDC) Program?
a. No penalty points are currently being assessed.
b. Penalty points are being assessed at the rate of one
per minute.
c. Penalty points are being assessed at the rate of one
every two minutes.
d. Penalty points are being assessed at the rate of two
per minute.
ANSWER
4
b.
PAGE 21
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
5
ITEM ID: A-04-005
POINT VALUE:
1.10
LESSON PLAN: PLR-LP-42 OBJECTIVE: 1
LESSON PLAN: PLR-LP-57 OBJECTIVE: 3
LESSON PLAN: RO-SE-025 OBJECTIVE: 2
LESSON PLAN: RO-SE-052 OBJECTIVE: 2
LESSON PLAN: RO-SE-063 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-028 OBJECTIVE: 1.B
LESSON PLAN: RO/SRO-SE-036 OBJECTIVE: 2
LESSON PLAN: RPS-LP-004
OBJECTIVE: 3
PLANT REFERENCE: APP-004
PLANT REFERENCE: SD-011
Which of the following is correct concerning RCS Loop-2
temperature instruments?
a.
T-hot failed low
b.
T-hot failed high
c.
T-cold failed low
d. T-cold failed high
ANSWER
5
a.
PAGE 22
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
6
ITEM ID: A-04-006
POINT VALUE:
1.10
LESSON PLAN: MDTA-LP-10 OBJECTIVE: 1.D
LESSON PLAN: RO-SE-021 OBJECTIVE: 2
LESSON PLAN: RO-SE-048 OBJECTIVE: 3
LESSON PLAN: RO-SE-057
OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-028 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-028 OBJECTIVE: 1.A
PLANT REFERENCE: AOP-001
With current plant conditions, if control rod K2 (Control Bank B)
suddenly dropped into the core, what type of runback would occur?
a. a turbine limiter runback of approximately 30%
b. a turbine reference runback of approximately 1 1/2%
c. a turbine limiter runback of approximately 1 1/2%.
d. a turbine reference runback of approximately 30%.
ANSWER
6
d.
PAGE 23
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
7
ITEM ID: A-04-007
POINT VALUE:
1.10
LESSON PLAN: PLR-LP-42
OBJECTIVE: 1
LESSON PLAN: PLR-LP-57
OBJECTIVE: 3
LESSON PLAN: RO-SE-039 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-015
OBJECTIVE: 2
LESSON PLAN: RPS-LP-005 OBJECTIVE: 3
LESSON PLAN: SR-SE-004 OBJECTIVE: 2
PLANT REFERENCE: SD-011
PLANT REFERENCE: SD-027
Predict the first reactor trip setpoint that would be exceeded if
main feedwater pump "B" was to suddenly trip with current plant
conditions.
a.
High pressurizer level.
b.
Steam flow/feed flow mismatch with low steam generator
level.
c. Turbine trip
d.
Low-low steam generator level
ANSWER
7
b.
PAGE 24
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
8
ITEM ID: A-04-008
POINT VALUE:
1.10
LESSON PLAN: FW-LP-002 OBJECTIVE: 2
LESSON PLAN: FW-LP-002
OBJECTIVE: 3
LESSON PLAN: RO-SE-041 OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-015
OBJECTIVE: 2
LESSON PLAN: SR-SE-004
OBJECTIVE: 2
PLANT REFERENCE: AOP-010
If the "A" main feedwater (MFW) pump cannot be restarted, the
plant can be reliably.operated at a maximum power of approximately:
a. 65%
b. 60%
c. 55%
d. 50%
ANSWER
8
0b
PAGE 25
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
9
ITEM ID: A-04-009
POINT VALUE:
0.70
LESSON PLAN: PLR-LP-37
OBJECTIVE: 2
LESSON PLAN: RCS-LP-003
OBJECTIVE: 4
LESSON PLAN: RCS-LP-004
OBJECTIVE: 1
LESSON PLAN: RCS-LP-005 OBJECTIVE: 2
LESSON PLAN: RO-SE-052
OBJECTIVE: 3
PLANT REFERENCE: OP-006
PLANT REFERENCE: SD-059
With current plant conditions, if PZR PORV PCV-456 overpressure protection
key switch was placed in the low pressure position:
a. Alarm APP-003-A3, PCV-456 LP PROT ACT/TROUB, would annunciate
and Pzr PORV PCV-456 would open
b. Alarm APP-003-C7, PZR PRESS CONTROLLER HI OUTPUT, would annunciate
c. Pzr PORV PCV-456 would not open due to current RCS temperature,
pressure relationship
d. Pzr PORV PCV-456 would not open due to RCS pressure less than
2000 psig
ANSWER
9
c.
PAGE 26
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
10
ITEM ID: A-04-010
POINT VALUE:
0.70
LESSON PLAN: ESF-LP-3 OBJECTIVE: 1
LESSON PLAN: RO-SE-010 OBJECTIVE: 1
LESSON PLAN: RO-SE-031 OBJECTIVE: 4.
PLANT REFERENCE: GP-002
PLANT REFERENCE: T/S 3.3.1.1.G
ASSUME FOR THIS QUESTION ONLY that it is desired to shut valve
SI-864B. Which statement correctly describes how this could be
accomplished?
a. Place SI-864B control switch to "close"
b. Shut SI-864B 480v breaker and place control switch to "close"
c. Restore SI-864B control power and place control switch to
"close"
d. Close SI-864B 480v breaker, restore control power and place
control switch to "close"
ANSWER 10
c.
PAGE 27
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
11
ITEM ID: A-04-011
POINT VALUE:
1.10
LESSON PLAN: CVC-LP-003 OBJECTIVE: 3
LESSON PLAN: CVC-LP-005 OBJECTIVE: 4
LESSON PLAN: SR-SE-012 OBJECTIVE: 1
PLANT REFERENCE: APP-001
PLANT REFERENCE: APP-003
PLANT REFERENCE: SD-021
Assume for this question only that a fault within charging pump
"C" motor causes the pump to trip with current plant conditions.
Prior to starting a standby charging pump, which alarm would
you expect to annunciate?
a. RCP SEAL WTR LO DELTA-P (APP-001-F2)
b. RC PMPS LABYRTH-SEAL LO DELTA-P (APP-001-B2)
c. RCP THERM BAR COOL WTR LO FLOW (APP-001-Dl)
d. RCP #1 SEAL LEAKOFF LO FLOW (APP-001-E2)
ANSWER 11
b.
PAGE 28
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
12
ITEM ID: A-04-012
POINT VALUE:
0.80
LESSON PLAN: PLR-LP-49 OBJECTIVE: 2
LESSON PLAN: RO-SE-044 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-013 OBJECTIVE: 1
LESSON PLAN: RO/SRO-SE-030 OBJECTIVE: 1
LESSON PLAN: SGLCS-LP-00
OBJECTIVE: 2
LESSON PLAN: SR-SE-003 OBJECTIVE: 1
LESSON PLAN: SR-SE-008
OBJECTIVE:
1.A
LESSON PLAN: SR-SE-010 OBJECTIVE: 1.A
PLANT REFERENCE: SD-027
THIS QUESTION DOES NOT REFER TO PRESENT PLANT CONDITIONS
FOR THIS QUESTION ONLY, assume that the plant is at full power
and that impulse pressure channel PT-446 is selected and fails
low.
Select the statement which correctly describes how the main
feedwater regulating valves would INITIALLY respond:
a. The valves would travel in the OPEN direction due to the loss
of pressure compensation to the controlling steam flow
channels.
b. The valves would travel in the SHUT direction due to loss of
pressure compensation to the controlling steam flow channels.
c. The valves would travel in the SHUT direction due to steam
generator reference level shifting to the no-load value.
d. The valves would travel in the OPEN direction due to steam
generator reference level shifting to the no-load value
ANSWER 12
C.
PAGE 29
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
13
ITEM ID: A-04-015
POINT VALUE:
0.70
LESSON PLAN: NI-LP-002
OBJECTIVE: 3
LESSON PLAN: RO/SRO-SE-030
OBJECTIVE: 1
PLANT REFERENCE: APP-005
PLANT REFERENCE: SD-010
THIS QUESTION DOES NOT REFER TO PRESENT PLANT CONDITIONS
What condition(s) will cause the CONTAINMENT EVACUATION alarm to
AUTOMATICALLY actuate?
a. Source range hi flux at shutdown alarm
b. Source range hi flux at shutdown alarm OR containment
radiation monitors RMS-32 A OR B high alarm
c. Source range hi-flux at shutdown alarm OR containment
radiation monitor RMS-11 and RMS-12 alarm
d. Containment radiation monitors RMS-11 OR RMS-12 alarm
ANSWER 13
a.
PAGE 30
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
14
ITEM ID: A-04-016
POINT VALUE:
1.3
LESSON PLAN: AC-LP-4
OBJECTIVE: 2
LESSON PLAN: SR-SE-011 OBJECTIVE: 4
PLANT REFERENCE: PATH 1
THIS QUESTION DOES NOT REFER TO PRESENT PLANT CONDITIONS.
A reactor trip without safety injection actuation occurs with the
plant initially at 100% power following a loss of offsite power.
Assuming that both emergency diesel generators (EDGs) operate as
designed, select the statement below that is correct:
a. "B" or "C" charging pump will have to be manually started
from the RTGB to restore RCP seal injection flow.
b. At least one Instrument Air Compressor will be running
following automatic emergency bus loading.
c. The "A" service water pump MUST be running for the "A"
service water booster pump to automatically start.
d. The EDG "A" supply fan (HVS-6) should not be running
following automatic emergency bus loading.
ANSWER 14
a.
PAGE 31
TEST ANSWERS
TEST ID: A-04-93
ANNUAL LOR EXAM -
STATIC SIM.
QUESTION
15
ITEM ID: A-18-014
POINT VALUE:
0.80
LESSON PLAN: EOP-LP-03
OBJECTIVE: 4
LESSON PLAN: DC-LP-1 OBJECTIVE: 2
LESSON PLAN: DC-LP-2 OBJECTIVE: 5
PLANT REFERENCE: OP-601
PLANT REFERENCE: SD-016
PLANT REFERENCE: PATH 1
THIS QUESTION DOES NOT REFER TO PRESENT PLANT CONDITIONS.
Path-1 Step B-6 directs the operating shift to "RESTART BATTERY
CHARGERS WITHIN 30 MIN OF POWER LOSS".
Failure to restart "A" (or "A-1") battery charger could lead to
the eventual loss of:
a. instrument bus 1
b. instrument buses 2 and 7
c. instrument buses 3 and 8
d.
instrument buses 4 and 9
ANSWER 15
b.
END OF EXAM
Attachment 6e
STATIC SIMULATOR SCENARIO
BRIEFING SHEET
SCENARIO NO.:
4
The Unit was
initially
at 100% power
(MOL)
with all
equipment operable.
Approximately 3 minutes ago, the "A" main feedwater (MFW)
pump tripped and the BOP Operator reduced turbine load in
turbine manual to its present value.
No other actions have been taken by the operating shift.
SSS-004 (Rev.4)