ML19325D339
| ML19325D339 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/16/1989 |
| From: | Pellet J, Whittemore J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19325D336 | List: |
| References | |
| 50-298-OL-89-02, 50-298-OL-89-2, NUDOCS 8910230110 | |
| Download: ML19325D339 (52) | |
Text
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APPENDIX i
U.S. NUCLEAR REGULATORY COW.15510N REGION !Y NRC Operater Licensing Examination Report:
50-298/0L 89-0?
l License No.: DPR-46 l
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Doclet: 50 298 Licensee: Nebraska Public Power District (NPPD) 1 Facility Nane: Cooper Nuclear Station i
Examination at:
CooperNuclearStation(CNS)
P.O. Fox 98 Brownville, Nebraska I
Examination conducted: Weeks of July 24 and September 11, 1989 i
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Chief Examiner:
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- 9. E. Whittemore, Examiner Date Operator Licensing Section Division of Reactor Safety i
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//1!//g Approved:
J.'L. Pellet, Chief Date
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i Operator Licensing Section Division of Reactor Safety Inspection Summary NRC Administered Examinations Conducted Durino The Weeks of July 24 and l
Teptember 11. 1989 (Report 50-29h/0L 89-02)
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NRC administered written, simulator, and walk-through requalification exan.inations 6
to two unit crews consisting of two reactor operators (R0s) plus six senior reactor operators (SR0s) and a staff crew consisting of three SR0s and one RO. 'All crews passed the examinations. One SRO failed the written examination.
NRC also administered a retake written examination to one R0 candidate who passed the examination and has been issued the appropriate license, j
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DETAILS l
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Persons Examined j
l Requalification Examinations:
CREW SRO g
TOTAL.
l Pass.
3 8
3 11 i
Fail-0 1
0 1
l RO, TOTAL O
Replacement Exemination:
l Pass-.
I 1
fail-0 0
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Examiners' 1
D. N. Graves J. M. Keeton L. R. Miller i
l J. L. Pellet J. E. Whittetaore, Chief Examiner 3.
Requalification and Replacement Fxenination Report
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Perfomance results for individual examinees are not included in this report as it will be piaced in the NRC Public Document Room and these l
results are not subject to public disclosure, a.
Examination Material Development The licensee examination material development effort connenced 1
late in 1988. The Chief Examiner traveled to the facility in January 1989 for the purpose of reviewing initially developed material. The simulator scenarios were being developed by a contractor and were not available for review at this time. Several problems were discovered with new written and walk-through examination ittns.
(1) The facility licensee did not fully understand what would be appropriate for Section "A" or "B" of the written examination.
Several questions designated for Section."A" required the examinee to use' procedures related to the emergency plan or to interpret Technical Specification LCOs and detemine operability.
~ The f acility licensee was infonned that since the written examination Section "A" was intended to be a common examination t
for licensed R0s as well as SR0s, it was improper for the Section "A" examination to focus on these areas. The Chief Examiner offered interpretation of Section ES-601 in an effort to resolve this problem.
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(2) There were several " Double Jeoparcy" items in the initial written item material submission. Many of these items required j
a yes/no or true/f01st answer and then required an explanation to support the iitial answer with partial credit being allowed for each corret partial answer. The disadvantage of the f
examinee being unable to correctly support a wrong initial answer was pointed out to the developers. The licensee was
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inforwed that NRC woL !d not use items considered to be " double jeopardy" or items re3uiring a yes/no or true/ false answer.
(3) A large portion of the written examination items reviewed did not require the operutor to synthesize or analyze conditions i
i or events to arrive at the correct answer.
It was only necessary to look up a correct answer. Many items were not at e
'the "look up" perfon,.ance level, but were better classified as nere recall knowledge. The licensee oevelopers were inforned i
that the requalification examination should evaluate the decision making capabilities of the operators as well as their l
j aptitude for using plant procedures and other documents.
(4) Several of the written examination items referenced K/A importance factors that were less than the value.cf 3.0 required,
by Section ES-601.
(5) Conpleted written examination items were not assigned point values.
(0) There was no scheme or methodology for distributing partial credit for answers graded to be at least partially correct on any of
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the written items.
(7) The forwat used for job performanel measures (JPMs) was cumbersone i
i ard difficult to use. The Chief Examiner suggested a columnar
' i format with the performance' elements and standards side by side, I
with cues in the standard column. The licensee adopted this suggestion.
(B) The standards Yor JPM steps were often inadequate because of overuse of the phrase "Same as Element." There was a lengthy I
discussion about the level of detail required in the performance standard. The licensee was informed that a perforn.ance measure element should merely state what the step or subtask is, while the standard should provide the evaluator with a detailed description of how the step is to be accomplished for a passing evaluation.
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(9) JPM evaluator cues were missing or inadequate, and in some cases, r
in the wrong place. -1.icensee developers were informed that the most successful methodology used recently for detemining the adequacy'of cues was to thoroughly walkdown a JPM with two l
indiv Wuals role' playing as evaluator and examinee.
(10) A majority of the questions at the end of each JPM were simple lookup or recall, and required'no analysis or synthesis on the part of the examinee to answer the question. The facility
-licensee was informed that questions used with the JPHs are subject to the same content and construction requirements as those submitted for written items.
The Chief Examiner was onsite again during the latter part of February 1989 for the purpose-of administering replacement operator licensing examinations. At the conclusion of these examinations, 1
meetings were held with licensee personnel to interpret NUREG 1021, t
Section ES-601 requirements, and to determine, discuss, and resolve any logistical problems relating to requalification examination preparation and administration.
The. prepared scenarios arrived in the Region IV office approximately six weeks prior to the' administration of the simulator examinations '
that were scheduled to occur at the GE training facility.in Morris, Illinois. After review in the office, a Region IV examiner traveled to the site with the results of this review. The major issue to be resolved was to better define and identify individual simulator.
critical tasks (ISCTs), crew tine critical behaviors, and crew team dependent behaviors. The two parties agreed on changes that.needed-l to be implemented and the scenarios were' considered to be in final form for use during the simulator examination.
The entire data bank of the finalized written items as well as JPMs was received in the NRC Region IV office approximately 60 days prior to the examination week. The Chief Examiner' performed an extensive review of all the material. During this review comments were made.
l on nearly every item in the package submitted. Some of the problems noted after the initial review were still fully evident and in some areas there.had been only marginal improvement. At the completion' i
of'the review, the entire package with review consents was mailed l
back to the facility for the licensee to resolve NRC concerns. The generic problems uncovered during this review were the following.
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o There were no point values assigned to the written items.
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o There was no methodology for partial credit grading of the wr.itten l
items.
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Several of the questions on the written items were open-ended I
as it was unclear what information being solicited, o-Written item key answers contained infonnation required for full credit that had not been solicited in the question, o
There were several written examination items, which had been previously noted, unsuitable for use on an NRC examination.
o Many of'the'JPM questions were of poor quality and often nondiscriminating, o
There were JPM individual step performance standards that were inadequate for. objective evaluation.
o JPM cues were inadequate or nonexistent in some cases. A thorough walkdown validation.should have prevented this problem c
on all submitted JPMs.-
b.
Examination Development During the week of August 28, 1989, the Chief Examiner traveled to the CNS site. The Chief Examiner and one CNS instructor who had signed an ES-601 security agreement form assembled Saction "A" and "B" written examinations considered to be satisfactory by both parties. These exaninations were time validated by having the designated facility representatives take the examinations. The I
representatives completed the examinations within the allowable time.
These examinations were graded by-NRC and the licensee representative.
Both individuals passed the written examinations. At this tima, the licensee was informed'that these examinations could be counted as 1
their annual requalification examinatiorss if the CNS program permitted this. Also at this time, security agreements were acknowledged and signed by.the designated facility representatives. After some modification of the examinations, the facility representatives and 1
the Chief Examiner agreed on the final written examination versions.
After finalizing the written examinations, JPMs were selected and assembled into walk-through examinations. This task required i
considerable effort as examinees could not be examined on JPMs to which they had already been exposed either for validation or practice. The team wes able to assemble examinations meeting this requirement because, licensee training department personnel had developed and instituted a trscking system..which would indicate i
which individuals had been exposed to specific JPMs.
When all examinations had been assembled, the Chief Examiner initiated a detteiled team review of all items selected for written and walk-through examinations. All deficiencies identified were corrected to the satisfaction of the Chief Examiner. The corrective actions taken j
were mainly in the following areas..
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Written examination items were assigned point values with instructions for partial credit grading. The facility licensee had taken no action to correct this problem, which had been pointed out in January 1989.
o Specific question answer keys were corrected to eliminate infomation not solicited by the question.
o Written examination items were corrected so that item construction format was consistent among the various types of' questions, i.e., multiple choice, matching, short answer, etc.
o Some JPM questions were eliminated and replaced with questions i
that were more discriminating for the purpose of performance.
evaluation.
o It was necessary to correct the misidentification of critical steps within the JPMs. The major corrective action required redesignating previously-designated critical steps as noncritical.
o Approximately 25 percent of the JPMs selected for the examination required corrective action to. improve individual step standards.
i When examination assembly was complete, the Chief Examiner met with the designated facility evaluators. The three evaluators. signed preexamination security agreements. The evaluators were signed on~
as soon as possible to allow them sufficient time to become familiar i
l with the JPMs they would be administering. At the request Pf the-facility licensee, the Chief Examiner observed each of the waluators s
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administer at least one practice JPM in the control room or plant.
The JPMs utilized.were outside the. bank designated for.NRC use. At l
the conclusion of this observation, the evaluators were infomed of all problems noted either in technique or procedure.
It was
.noted during this evolution that a communication problem existed between the evaluator and examinee in the method the facility licensee -
had chosen to initially cue the examinee. The Chief Examiner recommended a substitute method, which was adopted for use during the.
r examinations.
,c.
Examination Administration The CNS requalificatico examinations were administered during.two different widely separated weeks in July and September to accomodate the licensee's previously purchased and scheduled time on the Morris i
l facility simulator ar.d to work around the scheduled refueling outage j
that concluded in the late sumer time frane.
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(1) During the week of July 24, 1989, the three crews were administered simulator examinations at the GE Morris, Illinois facility.' The a
particular scenarios to be utilized were selected af ter the designated facility evaluators signed preexamination security agreements and the facility evaluators had no prior knowledge of which scenarios would be used.
Prior to examination administration, minor adjustments were made to the scenarios to correct deficiencies.
These corrections mainly defined critical tasks and behaviors required for a passing evaluation of crews as well as individuals.
i At the conclusion of simulator examination, NRC met with the facility licensee to inform them of the following items that had l
been observed during the preparation and administration. phases of the examination, o
More effort is needed in determining more objective evaluation' criteria for ISCT's and time critical-i behaviors.
o The scenarios are inconsistent in the level of detail required for evaluation of performance of various steps.
Some are very detailed wiole some are generalized.
o Normal evolutions, i'.e., power' change are not required for requalification simulator examinations.
o All crews experienced mihar problems in executing shift command / control.during off-normal events.-
o Overall crew performance on the non plant specific simulator was fully satisfactory.
(2) During the week of September 'll,1989, the written and walk-through examinations were administered at the site. The written examinations I
were administered starting at approximately noon on September 11.
This occurred simultaneously with the administration of a replacement retake written examination'given to one individual who had failed'a previous examination. The replacement examination i
candidate was kept separate from requalification examinees. The requalification written examinations were administered to two different groups of six examinees simultaneously in two 4.
different rooms. Compromise was prevented by having both groups take Section "A" first and then giving a short unescorted break before starting both groups on Section'"B".
NRC examiners provided full time proctoring for all three examination group sessions. At the conclusion of the replacement examination, the NRC provided the facility with a review copy of the examination as administered. Licensee-personnel were informed that comments were due in the ' regional 9
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, i office within five working days and that examination grading j
would not begin until f acility licensee comments were received i
by NRC. The licensee's training personnel copied the completed 3
recualification examinations'and provided the NRC with copies t
in order that parallel grading could be accomplished.
(3) Walk-through examinations were conducted on September 12 and 13, 1989, for all 12 examirees. The examinations consisting of five consnon and five diverse JPMs and were administered to six examinees each day. Precautions were taken so that individual canaidates who would be exposed to identical material were separated and monitored to preclude any chance of 3
compromise.
The 12 individuals were administered walk-through examinations by 3 facility evaluators and co-evaluated by NRC examiners.
(4) The morning of September 14, 1989, was set aside for the facility.
licensee and the NRC to grade written examinations and finalize grading of,the walk-through examinations. During that afternoon, comparison of grading results between the two parties revealed that there was 100 percent agreement on pass / fail results.
Both NRC and the facility had failed the same licensed individual on the examination.
d._
Examination Results l
All examinees passed the simulator and walk-through examinations
'as evaluated by the facility licensee evaluators and the NRC, All crews' passed the simulator examinations. One SR0 failed the written examination as graded by the facility and the NRC.
A total of nine examinees failed eleven individual JPMs. with two individuals failing two JPMs each. One JPM, injecting service water into the reactor vessel, was missed by two examinees. A total,of 229 JPM followup questions out of a possible 250 or 92 percent were answered correctly.
One individual answered 74 percent of the. followup questions. All others performed better. The NRC met with the facility licensee training staff to discuss preliminary results and findings. At this time all significant weaknesses were noted to the licensee.
The weaknesses noted were both in development and examinee performance.
Throughout the process, problems relating to specific material had been relayed to the facility evaluators and designated technical representatives. The training staff was informed of the requalification examination generic item development problems' below.
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-g-o Point values need to be assigned to all written items in the data base. The licensee had not done this so that a question f
could be assigned a relative value depending on the questions it i
was being used with. Question worth should stand alone regardless of the test environment. Time was not utilized effectively during.the preparation week because of the need to assign point
- values, o.
Questions were often open-ended in what they solicited or the answer required by the key was not asked for in the question.
o Questions in the~ examination format were sometimes j
different from those on the key, o
There is no partial credit breakdown for short answer questions presently in the data base. This leads either to overly severe grading if no partial credit is given, or to subjective grading if each grader determines.the worth of partial answers.
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The process set up by the facility licensee does not clearly communicate the task required by the'JPM to the examinee. There were numerous instances where exaninees had to ask for restatement
- of conditions and requirements before.or during task performance.
o Several JPMs require examinees to ascertain what task is to be performed, but the existing cues do not lead the examinee in the proper direction to determine the task.
o Several JPM standards. are sufficiently vague as to make objective evaluation impossible. Complicated steps, which have been designated critical, often have standards that are "Same as Element;"
o A thorough walkdown review was not evident for all of the JPMs used for the examination. There were cases where specifically cited instrumentation did not exist and procedure steps performed by examinees were not included in the JPM.
o There were numerous cases where a step was designated critical, but was not, and some steps not designated critical, should have been.
o JPM questions are vague and nondiscriminatory. The licensee was reminded that JPM questions are subject to the same review criteria as written items.
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The training staff was further informed of the following generic perfomance problems. detected on the written and walk-through-examinations for multiple examinees.
o Examinees experienced difficulty in recalling setpoints, which by itself, is not noteworthy. This minor finding was amplified when candidates could not locate setpoints they could not recall.
o Examinees had difficulty locating locally posted operating procedures, o
Examinees could not set the control rod drive (CRD) hydraulic control unit (HCU) accumulator pressure regulator according to the procedure.
o Two individuals could not use the jet pump operability test curves properly, o
The safety system status panel usage was inconsistent among the examinees.
o The thumb rule being used for vessel fill rate is erroneous, o
Examinees could not explain CRD mechanism internal design.
features that allowed the use of reactor pressure to scram.
o Examinees did.not demonstrate an understanding of reactor equipment coolant (REC) system response to electrical system transients.
o Examinees demonstrated weaknesses in predicting plant response to instrument failure and making a determination of which instrumentation is valid during abnormal or deteriorating conditions.
o Examinees elected to attempt an increase power to clear a RSCS Technical Specification LCO when a shutdown was required.
o Examinees did not recognize a safety limit being' violated and subsequently failed to demonstrate the knowledge.that NRC concurrence is required for startup after a shutdown due to a safety limit violation.
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Replacement Examination Review Coment and Resolution ~
k In general, editorial coments or changes made during the examination, or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of substantive coments
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l made by CNS staff. The only coments normally addressed in this section are those which are not accepted for incorporation into the examination answer key. Those comments accepted are incorporated into the master examination key. The facility made coments on two questions, both of which were accepted and incorporated into the final examination key. The full text of the comments and the final corrected examination key are attached.
f.
Site Visit Sumary An exit meeting was held at the CNS site at the conclusion of the examinations. The following person 6c' vere present:
l NRC NPPD J. M. Keeton R. D. Black L. R. Miller R. Brungardt J. L. Pellet J. W. Dutton J. E. Whittemore C. M..Estes
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i G. R. Horn J. M. Meacham D. Shellenberger V. W. Stairs G.'A. Trevors NRC opened the meeting by thanking the facility licensee operations and training personnel for the cooperation received during the onsite examination process. The licens'ee was informed that the CNS requali -
fication program meets the requirements of NUREG 1021, Section ES-601 to be evaluated satisfactorily, and is evaluated as such pending concurrence of Region IV upper managenent. During this meeting, licensee personnel e,tpressed concern about the length of the written examination. NRC responded by explaining the written examination time validation process that had been used and pointed out that written examinations were normally designed to take l'.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per section while candidates were allowed two hours to complete the examination section. The following' items were comunicated to the 7
facility licensee representatives as consents, observations, or deficiencies.
(1) All 12 operators and all 3 crews passed the simulator and walk-through examinations. One licensed SRO failed the written examinations as graded by NRC and licensee personnel.
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(2) The satisfactory rating is by a narrow nargin. Several licensed
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personnel were very close to feiling the written or walk-through
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examination.
(3) All. parts of the examination process demonstrated a lack of attention to detail as there was insufficient review or validation to assure that objective performance measures were used. Also, it was frequently difficult for the examinees to determine exactly what was expected of them. This applies to both written and walk-through examination format.
(4) The same level of performance on the next audit will very likely result in an unsatisfactory program evaluation.
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(5) The examination material must be' improved. Specific problems have been discussed with the training department. This required improvement will take even more resources than used'to
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date.
(6) The addition of the plant specific simulator will place a major burden on resources for development because it mandates major I
revision.to material already developed.
(7) The new process lends itself to finding problems.with plant procedures.. The NRC has pointed out,to training personnel that correcting these problems and updating existing material for changes to procedures will also claim substantial resources.
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(8) NRC understands that'a reason for some of the problems noted on this examination may be because of the. limited tine the program I
has been-in effect. Therefore, the Operator Licensing Section in Region IV will provide additional guidance at the facility licensee's request.
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NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 4
FACILITY:
09221E 115112D____..______
REACTOR TYPE:
BWB:QEe__________________
DATE ADMINSTERED:
124Q2411_________________
CANDIDATE:
luSIBUSIIQUS_ID_DeUDIDeIEi i
Use separate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each Question are indicated in parentheses after the question.
The passing grade requires at least 70% in each category and a final grade of at least 80%.
Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY
__VeLUE_ _IDIeL
___SDDBE___
_VeLUE__ ______________DeIEQDBY
_2520D__.25100 1.
REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
_2ZiDD__ _2ZzGD
________ 2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
_3gigg__ _30200 3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
10010D__
TOTALS i
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FINAL GRADE l
All work done on this examination is my own.
I have neither given nor received aid.
Candidate's signature e
DRAFT COPY
'81.E$EBGENQ1.eNQ8BNQBdeL_ELaNI_EVQLVIION1 Page 3
12Z11 QUESTION 2.01 (2.50)
MATCH the action in COLUMN A with its appropriate vacuum setpoint in COLUMN B.
(NOTE: Items in COLUMN B may be used more than once or not et all.)
COLUMN A COLUMN B a.
MSIVs close.
1.
7" Hg b.
Main Turbine pre-trip 2._
10" Hg actuates.
3.
19" Hg c.
RFP turbines trip.
4.
23" Hg-d.
Main Turbine trips.
5.
25" Hg e.
Reactor Scram.
6.
28" Hg 7.
No trip point exists.
ANSWER 2.01 (2.50) i, c.
1 b.-
5 c.
1 d.
3 e
7 (0.5 pts each) i REFERENCE
'1.
CNS: OSTM, COR001-14 L.O.
8.
TABLE 1, pg. 27.
2.
CNS: Procedure 2.4.9.3.5.
3.
CNS: OSTM. COR002-03, L.O.
5, TABLE 2.
'i 295002K203 295002K205 295002K202
..(KA's) i l
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CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2t.EbEBGEUQ1eUD_eEUQBdeL_EleUI_EVQLWIl001 Page 4
12Z11 QUESTION 2.02 (1.00)
SELECT the Digital Electrohydraulic (DEH) system failure that would rcsult in a high pressure transient (i.e..
bypass valves and governor volves close).
s.
Pressure controller
'A' fails high.
b.
Pressure setpoint fails high with NO manual transfer, c.
Pressure controller
'A' fails low.
d.
Pressure setpoint fails low with NO manual transfer.
ANSWER 2.02 (1.00) b.
REFERENCE 1.
CNS:
OSTM COR002-09:
L.O.7.
295025K208
..(KA's)
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i
- 2t. EdEBGEUGl_6BD_eBUQBdeL_ ELAN 1.EYGLVI1ONS Page 5
LZZ12 QUESTION 2.03 (1.00) t CNS is operating at 60% power when a failure in the Reactor Recirculation Flow Control system causes a reduction in flow.
The reactor operator places both flow controllers in manual and verifies power oscillations of about 10% peak to peak are occurring.
In accordance with procedure 2 4.1.6,
" Abnormal Neutron Flux Oscillations," CHOOSE the PREFERRED method for reducing power oscillations, s.
Withdraw control rods.
b.
Decreece recirculation flow.
c.
Insert control rods.
d.
Increase recirculation flow.
ANSWER 2.03 (1.00) d.
REFERENCE 1.
CNS: Procedure 2.4.1.6, page 1, step IV.B.1.
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295014K211
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CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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- 2t__EbEBGEUQ1.6U0_eBUQBdeL_EleUI.EVQLul10S$
Page 6
L2Z12 QUESTION 2.04 (2.00)
MATCH the expected action or response in COLUMN A with the Plant Air system pressure settings in COLUMN 8.
COLUMN A COLUMN B t
a.
Tendematic Sequence Control 1.
40 psig System starts standby compressor 2.
50 psig b.
Low Control air pressure 3.
65 psig clarm actuates 4.
70 psig c.
Service Air isolation valve (PCV-609) closes 5.
75 psig d.
Manuel Scram required 6.
85 psig 7.
95 psig l
8.
105 psig l
1 ANSWER 2.04 (2.00) l l
G.
7 1
b.
5 c.
4 L
d.
4 (0.5 pts each)
REFERENCE OSTM COR001-17, PAGES 22, L.O.
6.
and CNS Proc.
5.2.8, P.
2 295019A104 295019G009 295019A104 295019G009 295019K214 295019K214
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- 2t_EbEBGEUQ1_eUQ_eBUQBdeLEL6UIEVQLVIl003 Page 7
L2Z11 QUESTION 2.05 (3.00) 1 MATCH the component or system in t:0LUMN A with its associated rGdioactivity release trip or isolation setpoint in COLUMN 8.
(NOTE:
Answers in COLUMN B may he used more than once or not at all.)
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COLUMN A COLUMN 8 1
a.
Control room ventilation 1.
3 X Normal Full Power
Background
b.
Main condenser outlet valves 2.
7.0 X 10E4 CPS c.
Reactor building ventilation 3.
3.5 x 10E4 CPS d.
Mechanical vacuum pump 4,
Off-gas isolation valves 5.
100 MR/HR f.
Stand-by gas treatment 6.
No setpoint exists ANSWER 2.05 (3.00) l
- e. 4 b.
1 l
c.
5 d.
1 o.
2 l
f.
6 i
(0.5 pts each)
REFERENCE 1.
CNS: OSTM, COR001-16, L.O.
6 pg.
i 2.
CNS: OSTM, COR001-08, L.O.
8 pg. 56 8 57.
(
295017G009 295017G010 295017K301
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- 2t__EbEBGEUQ1_eUQ_etuDBdeL_EL6UIEVQLVIIQUS Page 8
L2Z12 QUESTION 2.06 (1.00)
Upon a loss of all site AC power, according to Procedure 5.2.5.1,
" Loss of All AC Power Station Blackout":
a.
Which reactor water level indication (s) are available in the control room?
(0,5) b.
Which reactor water level indication (s) are available outside the control room? (0.5)
ANSWER 2.06 (1.00) c.
The 3 GEMACs (0.25) and associated recorder (0.25) b.
The Yarways (in the Reactor Building).
(0.5)
REFERENCE 1.
CNS: EOP 5.2.5.1, Loss of All Site AC Power Station Blackout, Rev 4, 99 3.
2.
CNS: AP 2.4.8.4.2, Rev 11, pg.
2.
295003G006 295003G006 295003A202 295003A202
..(KA's)
QUESTION 2.07 (3.00)
In accordance with procedure 5.2.1,
" Shutdown'from Outside.the Control Room," STATE six (6) of the immediate operator actions or verifications that must be performed.
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i
2x__EdEEGEUCl eUD eEUQBdeL_EleUI.EVQLVIIQU$
Page. 9 L2Z11 ANSWER 2.07 (3.00) a.
Scram the reactor.
b.
Leave the mode switch in the RUN position.
c.
Verify all control rods are inserted.
d.
Trip the main turbine generator.
c.
Trip ONE feed pump, f.
Trip TWO condensate booster pumps.
9 Trip TWO condensate pumps.
h.
Ensure 90TH RFD turning gear motors are.in AUTO.
(Any 6 8 0.5 pts each)
REFERENCE l
1.
CNS: Procedure 5.2.1 " Shutdown From Outside the Control Room" 295016G010
..(KA's)
QUESTION 2.08 (1.00) i Loss of normal power to the No-Oreak Power Panel results in the system i
automatically transferring from:
I a.
Inverter 1A to inverter 18.
f b.
c.
MCC-R (115 V) to inverter 1A.
c.
MCC-R (115 V) 'o selected Critical Distribution Panel.
i l
ANSWER 2.08 (1.00)
\\
b.
l 1
i
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i h
2&__EdEBGEUQ1 eUQ_eBUQBdeL_EL6UI_EVQLUI1QUE Page 10 L2Zil i
REFERENCE 1.
CNS: OSTM, COR001-01, L.O.4, pg. 25.
295003A204
..(KA's)
QUESTION 2.09 (1.50)
With normal make-up unavailable, STATE three.(3) systems that can be uOed in an emergency to provide make-up to the fuel pool during a loss of level.
ANSWER 2.09 (1.50) 1)
RHR f
2)
RHR. Service Water 3)
Condensate Transfer 4)
Fire System (via fire hoses) 5)
Skimmer Surge Tk. Make Up (Any 3 0 0.5 pts each)
REFERENCE OSTM, COR001-06 pg. 23 & 24.
295023G010 295023G010 295023A102 295023A102
..(KA's)
QUESTION 2.10 (1.50)
If an area temperature exceeds its maximum normal operating limit. E0P-3 directs the operator to isolate any system breakc that are leaking into the area, unless the system is required for une of three reasons.
STATE the three (3) exceptions.
i i
I
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i
o 25._EMEBGEUQ1_eUQ_eHUQBdeL_ELeUI_EVQLVIl00$
Page 11
'L2Z11 ANSWER 2.10 (1.50)
If the system (s) is required to:
1.
Shutdown the reactor 2.
Assure adequate core cooling 3.
Suppress a working fire (0.5 pts each)
REFERENCE 1.
CNS: E0P-3, pg.
4.
295033A105
..(KA's)
QUESTION 2.11 (2.00)
The reactor is operating near full power when the following indications are received:
A turbine building high radiation alarm, A reactor building high radiation alarm, i
Generator output has dropped several MWe, Steam pressure has dropped to 830 psig, Tunnel area on main steam line
'A' (panel 9-21) reads 200 deg F.
In accordance with 5.3.4,
" Pipe Break Inside the Turbine ?uilding,"
STATE the immediate operator actions or verfications that must be Dorformed.
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4
.i&__EDEBGEUQ1.8WQ_eBWQBdeL ELebl EYQLWIlQU1 Page 12 12Z12 ANSWER 2.11 (2.00)
.a.
Verify MSIV closure.
b.
Verify condensate pump or feedwater pump trip.
c.
Monitor reactor water level, pressure and power, d.
Enter appropriate E0Ps if entry conditions exist.
s (0.5 pts each) l REFERENCE
-l 1.
CNS: Procedure 5.3.4 " Pipe Break Inside Turbine Building."
2.
l 3.
CNS: E0P-3, " Secondary Containment Control."
295033G011 295033G010 295033A203 295032G011
..(KA's)
QUESTION 2.12 (1.50)
STATE three (3) of the plant conditions that require the-use of alternate shutdown cooling as specified in the RPV pressure control coction of E0P-1.
r ANSWER 2.12 (1.50) a.
All RHR shutdown cooling interlocks clear (>75 psig,
>12.5"
- level,
.r and <2 psig D/W),
b.
RHR shutdown cooling not available, c.
All control rods are inserted to or beyond position 02, d.
Further cooldown is required.
(Any 30 0.5 pts each)
-t REFERENCE 1.
CNS: INT 008-04-10, L.O.1, pg.
1, 2'
295021K101
..(KA's)
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I
t 25 _EMEBQEUQ1_600 eBUQBdeL EleUI EVQLUIl0NS Page 13 12Z12 i
QUESTION 2.13 (3.00)
For each plant condition in COLUMN A, MATCH the Emergency Procedure (s)
(EOP) in COLUMN B, that are reoutred to be entered. (NOTE: Each plant condition in COLUMN A may require more than one answer.)
COLUMN A COLUMN B t
a.
RPV water level 12 inches 1.
Drywell pressure 2.2 psig 2.
E0P-2 Primary Containment Control c.
Radiation release resulting in en ALERT classification 3.
E0P-4 Radiation Release Control d.
Suppression pool level +2.5 inches 4.
No E0P entry required e.
Suppression pool temperature 90 deg F.
ANSWER 2.13 (3.00) e.
1 b.
1,2 i
c.
3 d.
2 o.
4
[0.5 pts each)
REFERENCE 1.
CNS:
Introduction to E0Ps INT 008-04 01 Rev. O p.
35.
2.
CNS:
3.
CNS:
E0P-2 " Primary Containment Control."
4 CNS:
E0P-4 " Radiation Release Control."
295024G011
..(KA's)
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Zu EdEBGEupl_6UD_eBUQBdeL_ELeUI.EVQLVIlD01 Page 14 12Z11 i
l QUESTION 2.14 (3.00)
For EACH parameter listed in COLUMN A, MATCH the group (s) from COLUMN B that use this paramettr to generato en isolation signal.
(NOTE:
Each parameter may have more than one group listed.)
COLUMN A COLUMN B a.
Low reactor water level 1.
(+12.5 inches) 2.
Group II - RHR', ACAD, A0G and TIP b.
Main steam line high rad (3 x Normal) 3.
Group III - RWCU r
c.
Low-low reactor water 4.
Group IV - HPCI T
level (-145.5 inches) 5.
Group V - RCIC d.
High drywell pressure
(+2 psig) 6.
Group VI - Reactor building vent, primary containment vent and e.
High reactor water level purge (58.5 inches) 7.
Group VII - Recirculation loop f.
High steam flow sample
(
C300 %)
8.
No Isolation required l
l ANSWER 2.14 (3.00) c.
2,6,3 b.
1,7 c.
1,7 d.
2,6 o.
8 f.
4,5 (0.25 pts each) l REFERENCE 1.
CNS: OSTM, COR002-03, Table 2.
295031K212 295024K207
..(KA's) 1 l
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l 2t_ ELa81_SX11EOS_L2011_eNQ_EleWI: WIDE _SEUEB1Q Page 15 BESEQN11BIL111E1.11012 i
I QUESTION 3.01 (2.00) i LIST the TWO (2) conditions necessary AND the TWO (2) operations rCQuired to reset a " scram."
i ANSWER 3.01 (2.00)
Conditions necessary:
a.
Scram signal cleared (0.5) b.
10 second timer timed out (0.5)
Oscretions:
a.
Bypass SDV high water level trip
[0.5) b.
Operate the Reactor Scram Reset Switch (0.5)
REFERENCE 1.
CNS: OSTM. COR002-21, pg. 35 212000A414
..(KA's) l QUESTION 3.02 (1.00) i A reactor scram should be reset as soon as practical to:
r a.
Prevent over pressurization of the scram discharge volume.
l l
b.
Prevent loss of air from scram air supply header.
1 c.
Prevent damage to RPS MG sets due to operating with no load.
I d.
Prevent damage to control rod drive mechanism seal due to high dp.
ANSWER 3.02 (1.00) 1 d.
i
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s i
$t.E'.881.11SIEdS_l2fil8ND.EL8Hl: WIDE _QEUE81Q Page 16 BESEQWSIBIL111ES.11012 REFERENCE 1.
CNS: OSTM, COR002-21, pg. 35.
212000K108 212000A414
..(KA's)
QUESTION 3.03 (3.00)
For esch of the plant areas listed in COLUMN A, MATCH the type (s) of fire protection system listed in COLUMN O that are available in that crea.
(NOTE:
Items in COLUMN B may be used more than once.)
COLUMN A COLUMN B a.
Reactor feed pump room 1.
Fire water system b.
Service water pump room 2.
Carbon. dioxide system c.
Diesel generator day tank rooms 3.
Halon 1300 system I
d.
Cable spreading room (918')
e.
Diesel fire pump room ANSWER 3.03 (3.00) a.
1 b.
3 c.
2 d.
1,2 c.
1 (0.5 pts each)
REFERENCE 1.
CNS: OSTM Vol VI, Fire protection System Description.
286000U503 286000K501 286000K502
..(KA's) i
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2&__EleNI 111IEdi_LIA11_aWQ_EleWI-WIDE _GENEB1Q Page 17 BESEQU11RILIIIES 11011 L
QUESTION 3.04 (1.00)
Which event causes the RWCU Blowdown Control Valve to isolate?
a.
Reactor water level decreases to 10 inches.
l l
b.
RWCU discharge line pressure increases to 143 psig.
1 c.
Non-regenerative heat exchanger's outlet temperature increases to 147 deg F.
d.
RWCU pump flow decreases to 35 gpm.
4 i
ANSWER 3.04 (1.00) 1 L
b.
REFERENCE 1.
CNS: OSTM, COR001-20, L.O.
5, pg. 19 l
204000K408
..(KA's) l QUESTION 3.05 (1.00) l Feilure of the #1 inboard seal on a recirculation pump would be l
indicated by:
a.
- 1 seal (inboard) cavity pressure decreases, pump seal l
leekoff flow High.
b.
- 1 seal (inboard) cavity pressure increases, pump seal leekoff flow Low.
c.
- 2 seal (outboard) cavity pressure decreases, pump seal leekoff flow Low, d.
- 2 seal (outboard) cavity pressure increases, pump seal leakoff flow High.
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' it__ EL 6NI_SISIE di_12012_6ND _ EL 6NI-W.'.D E.Q E NE B I Q Page 18 EEEEQN11EILII1E1_11012 ANSWER 3.05 (1.00) d.
' REFERENCE 1.
CNS:
OSTM. Vol II Rev 3.
Rx Recire. System og 14, L.O.
4.
202001A109
..(KA's)
QUESTION.
3.06 (2.00) o.
The plant is operating at 95% power when it becomes necessary to remove TWO (2) feedwater heaters from service.
PRIOR to removing the feedwater heaters from service, reactor power must be reduced by:
1.
3%
i 2.
5%
3.
7%
4.
10%
(1.0) b.
The reason for reducing reactor power prior to removing the feedwater heater is to compensate for:
1.
Reduced recirc pumps NPSH caused by feedwater temperature change.
2.
Positive reactivity addition caused by feedwater temperature change.
3.
Increased reactor power oscillations caused by heater temperature change.
4.
Decreased RFP suction pressure caused by feedwater temperature change.
(1.0)
I 1
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' Ix__EL&NI 1111Edi_llB11_&NQ.EL&WI-WIDE _QENEBIQ Page 19 i
BEEEQN11EILIIIEE 11D12 ANSWER 3.06 (2.00) a.
2.
b.
2.
(1.0 pts each)
REFERENCE 1.
CNS: OSTM, COR002 - 02, pg 57 259001K312
..(KA's)
QUESTION 3.07 (2.50)
Ucing the attached crewing (Fig. 2), MATCH the Standby Gas Treatment system purposts or function listed in COLUMN A with the valve (s) that provide that tunction listed in COLUMN B.
(NOTE:
Items in COLUMN A may have more than one correct response and items in COLUMN B may be used more than once.)
COLUMN A COLUMN B a.
Automatically maintains the 1.
AD-R-1C proper negative pressure in the Reector building.
2.
A0-255/256 b.
Opens automatically to align 3.
A0-251/252 proper suction path on a low reactor water level signal.
4.
A0-546ACB) c.
Opens au'omatically to align 5.
AD-R-1A proper cuction path on a high radiation 2n the reactor building 6.
A0-270/271 exhaust plenum.
7.
A0-249/250 d.
Opens to provide a metho-or removing decay heat ri f' t e t power 8.
AD-R-18 operation.
l l
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.. _. _. _ ~.
A0
L KEYLOCKE3
}--- TO SGT HE ATER CONTROL 3
g b-- TO SGT IF F AN CONTROL l
RELEASE pg P OIN T AO SGT FAN 1E 249 p
t v
FILTER TR AlH
~
I 29, E
_~
j y
1.1.0 LVORTEx AO g
s4eA
/
SGT IS2t AD-R-1C REACTOR
~~
L.O.[(4e)
SUILDING a
ROOM AIR EXHAUST
/
PLENUM
[f S T AD-R-1A AO AD-R-15 1
VORTEX a4en HEACTOR Ny 383-
~
BUILDING
~~
i l271 watt j
[
SGT2 FILTER TR AIN PRIM ARY CONTAINMENT
_AO SGT FAH 1F 250
--TO SGT HEATER CONTROL
~
KEYLOCKED b--TO SGT1E FAN CONTROL f
3-2TS A
d
.N l
HPCI TUR9edE I
GLAND STEAM CONDENSER STANDBY GAS TREATMENT (Basic Valve Lineup) 2 FIGIJRE 2 riev. 2
4
\\
. it _EL&WI_1111Eb1_L2112_aWD_EL&UI: WIDE SENEBIC Page 20 BEEEQWSIBILIIIE1_L1911 ANSWER 3.07 (2.50) s.
4 b.
1 c.
1.8 i
d.
6 (0.5 pts each)
REFERENCE I
1.
CNS: OSTM. COR002-28. pp 8-12.
261000G007
..(KA's)
QUESTION 3.08 (2.00) a.
The MSIVs are adj usted such that MAXIMUM automatic closure time is less than or equal to:
i 1.
3 seconds 2.
5 seconds 3.
7 seconds 4.
8 seconds (1.0) l b.
The basis for the MINIMUM allowable closing time is to:
l 1.
prevent core uncovery and minimize release of fission products.
2.
prevent valve damage due to mechanical stress on rapid closure.
3.
minimize reactivity addition rate due to subseouent void collapse.
4.
minimize reactor pressure transient following rapid MSTV closure.
(1.0) 1
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[
2&_.2LeWI 111IEbl.I2All.eWQ.2LeWI-WIDE.SENEBIC P89* 21 i
BEst0W1181L111E1.11013 1
l.
[
ANSWER 3.06 (2.00)
I a.
2.
b.
4 l
(1.0 pts each)
REFERENCE j
1.
CNS:
OSTM, COR002-14, p.
L.O.
4 i
239001K401
..(KA's)
[
i QUESTION 3.09 (1.00)
The Scram Air Supply Hender is malfunctioning causing the oressure to be I
at 90 psig.
If a reactor scram occurs with this condition:
j a.
Rod insertion speed may be excessive.
i b.
Scram pilot valves may fail to open.
c.
CRD mechanism components may be damaged.
[
t d.
$DV vent and drain valves would leak.
,i i
t ANSWER 3.09 (1.00) i c.
l REFERENCE i
i
- 1. CNS: OSTM, COR002-04, og 27.
l 201001K603
..(KA's) i t
i t
t I
i l
I I
l l.
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t i
25..ELeUI 111IEdi_L2A12_eUQ.ELeUI-WIDE _9EUEBIG Page 22 BESEQU11BILII1E1_L1012 i
i QUESTION 3.10 (1.00)
The plant is operating at 100% power when a loss of the operating dilution fan in the Off-gas system occurs and the standby dilution fan fails to start.
Assuming N0 ooerator action, the Off-ges:
a.
isolation valves will close after a 5 minute time delay.
b.
1 solation valves will close after a 15 minute time delay.
c.
system will continue operation because the SBGTS starts up.
d.
system will not respond until manual action is taken.
ANSWER 3.10 (1.00) a.
REFERENCE 1.
CNS: OSTM, COR002-05, pg. 13.
271000A301
..(KA's)
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n L
$5.2L8NI.ililE01.12Ill.8NDfL8Wl:WIQE.gggggIg Page 23 BE120W11RILillES.11011 QUESTION 3.11 (3.00)
O.
After initiation of Standby Liould Control ($LC), the MAXIMUM allowable injection time is:
1.
75 minutes 2.
125 minutes 3.
130 minutes 4
150 minutes (1.0) b.
The NINIMUM allowable injection time is:
1.
25 minutes 2.
50 minutes 3.
75 minutes 4.
125 minutes (1.0) c.
The basis for the MAXIMUM allowable SLC injection time is to overcome:
1.
reactivity added by void collapse.
2.
reactivity added by power chugging.
3.
reactivity added by cooldown.
4.
reactivity added by decreasing control rod worth.
(1.0)
ANSWER 3.11 (3.00) c.
2.
b.
2.
c.
3.
(1.0 pts each)
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S.
2L&W1.1111Edl.12Sil.!WD.ELAWl-WIDE.ggy[Elg Page 24 BE1EQWiltiLII1E1 11013 REFERENCE 1.
CNSt OSTM, COR002-?9, pg. 9 211000K503
..(KA's)
QUESTION 3.12 (2.00)
For each tituation listed in COLUMN A, MATCH the refueling interlock (s) frem COLUMN B that is (are) in effect.
(Note:
Each interlock in COLUMN B cay be used more than once or not at all.)
CCLUMN A COLUMN B a.
The service platform hoist is loaded, 1.
Rod block not all the rods are in, and the mode switch is in " refuel."
2.
Stops refuel platform travel b.
F r erne mounted hoist is loaded, not towards core all the rods are in, mode switch is in
" refuel," and the refueling platform 3.
Stops main fuel is near or over the core.
grapple operatien c.
The refueling platform is near or 4.
Stops service over the core when the mode switch platform hoist is placed in "startup."
operation 5.
Stops frame mounted hoist
-operation 6.
Stops trolley mounted hoist operation ANSWER 3.12 (2.00) c.
1,4 b.
1,2,3,5 c.
1,2 (0.25 pts each)
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9
$5..fL&W1.1111Edl.12All.8WQ.fL8dl-WIDE.igggBIQ Page 25 BElf0W11BILIIIES.11012 REFERENCE 1.
CNS: OSTM, COR001 21, Figure 39.
234000K502
..(KA's)
QUESTION 3.13 (1.00)
Those trips are associated with the Emergency Diesel Generators.
1.
2 Emergency shutdown switches 2.
Low lube oil pressure 3.
High vibration 4.
High jacketwater temperature 5.
Low turbocharger oil pressure 6.
Incomplete sequence 7.
Generator lockout 8.
Turbocharger thrust bearing failure 9.
Overspeed 10.
Main and connecting rod bearing high temperature Tho ONLY trips that remain in effect when the Diesel Generators automatically start on a high drywell pressure signal are:
a.
1, 2,
5, 7
b.
2, 3,
5, 9 c.
1, 6,
7, 9
d.
2.
6, 7,
9
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2a. 2L8HI.1111Edl [2 Nil 8WQ.fk8Wl-WIDE.gggggig Page 26 BEEEQuilBILIIIE1.fl012 ANSWER 3.13 (1.00)
C.
REFERENCE 1.
CNS: OSTM, COR002-08, pg 39.
264000K402
..(KA's)
QUESTION 3.14 (3.00)
For each load listed in COLUMN A, MATCH its power supply listed in COLUMN B.
(NOTE: Each power supply in COLUMN B may be used more than once or not at all).
COLUMN A COLUMN B a.
Recirculation MG set 1B 1.
Bus 1A b.
Condensate pump 1C 2.
Bus 1B
- c. Core spray pump 1A 3.
Bus 10 d.
Circulating water pump 10 4.
Bus 1D e.
Station service water pump 1C 5.
Bus 1E f.
Condensate booster pump 1A 6.
Bus 1F 7.
Bus 1G l
l l
l
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4 2t__EleWI 11SIEdi_L2911_eUQ_ELAUI: WIDE _QENEBIC Page 27 BEiEQUSIBILIIIES 1101)
ANSWER 3.14 (3.00) s.
4 b.
5 c.
6 d.
2 r
e.
5 i
f.
1 (0.5 pts each)
REFERENCE l
1.
CNS: OSTM, COR001-01, Tables 1,2,3.
262001K301
..(KA's)
QUESTION 3.15 (3.00)
P a.
STATE the FOUR (4) conditions necessary for an ADS automatic depressuri stion to occur.
(2.0) b.
With an ADS automatic depressurization in progress, STATE the pressure at which the low pressure CSCS pumps begin to inject into the vessel.
(1.0)
ANSWER 3.15 (3.00) a.
1.
Low reactor water level +12.5" 2.
Low reactor water level -145.5" 3.
Discharge pressure of any low pressure CSCS pumps > 100 psig 4.
120 secend timer timed out (0.5 ots each) b.
300 (+/-25)
(1.0)
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s
$t..EL881.1111Edl.12All86D.EL8dl:W10E.ggugB1C Page 28 BEEEQN11tIL111E1.11Q13 REFERENCE
[
1, CNS: OSTM, COR002-16, pg. 13, 23.
218000K501
..(KA's)
QUESTION 3.16 (2.00) a.
The flPCI pump suction will shift from its PREFERRED source to its ALTERNATE source upon a:
1.
Iow HPCI suction pressure.
2.
high ECST temperature.
t 3.
high suppression pool level, t
4.
LOCA signal.
(1.0) b.
The purpose of the vacuum breakers in the HPCI system are to:
1.
prevent overpressure in the gland seal condenser after HPCI is secured.
2.
prevent water from being siphoned into exhaust line after HPCI is secured.
3.
provide vacuum protection for the turbine steam supply header I
after HPCI is secured.
4.
provide overpressure protection if the rupture discs fail after HPCI is secured.
(1.0) t ANSWER 3.16 (2.00) a.
3.
b.
2.
(1.0 pts each)
REFERENCE CNS: OSTM, COR002-11, L.O.
2 & 7, pgs. 11 &'20 206000K508 206000K508 206000K419 206000K419
..(KA's)
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j i
J
$t..EL8NI.il11Edi.12B13.600EL&UI-WIDE.QEUEBig Page 29 BESEQuilEILIIIES.11013 QUESTION 3.17 (1.50) a.
The RCIC system automatically initiates at........... inches reactor water level.
(0.5) b.
The RCIC turbine will automatically shutdown at...
1....
inches reactor water level, and provides an injection rate of... 2..._
spm into the reactor vessel during operation.
(1.0)
ANSWER 3.17 (1.50) a.
-37"
[0.5]
b.
1.
+ 58.5 2
400 spm (0.5 pts each)
REFERENCE 1.
CNS: OSTM, COR002-18, pp.
7, 28, 37, 38.
217000A101 217000A108 217000K402
..(KA's)
QUESTION 3.18 (1.00)
Upon a LOSS of tachometer signal, RCIC turbine speed will:
a.
decrease to its minimum speed setting of 2200 RPM.
b.
increase until en overspeed trip occurs.
c.
decrease until speed drops to zero, d.
increase to its maximum speed setting of 3600 RPM.
ANSWER 3.18 (1.00) b.
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25..EleWI 1111Edi_12511_eUD_EleUI-WIDE _SEUEB1Q Page 30 i
BESEQuilBILIIIES 11012 REFERENCE 1.
CNS OSTM - COR002-18, pg. 41, L.O.
116.
QUESTION 3.19 (3.00) 031ng the attached " Power to Flow Map" (Fig. 19), MATCH the description in COLUMN A with lines 1 through 7 in COLUMN B.
COLUMN A COLUMN D a.
Represents reactor power 1
changes using rod movement in the absence of recirculation 2
pump operation.
3 b.
Represents the jet pump not positive suction head limit.
4 c.
Represents the low feedwater 5
runbeck limit.
6 d.
Represents conditions et which a flow-biased, high neutron 7
flux rod block will occur.
l e.
Repesents reactor power changes using rod movement with recirculation pumps at minimum speed.
f.
Represents the recirculation pump administrative net positive Suction head limit.
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BE1EQuilRIL111E1_L1712 ANSWER 3.19 (3.00) c.
3 b.
6 j
c.
2 d.
1 o.
5 f.
4 (0.5 pts each) i REFERENCE 1.
CNS: OSTM, Course # COR002-22, pp 47, 48, 49.
I 202001K403 202001K412
..(KA's)
QUESTION 3.20 (1.00)
The Reactor Building HVAC System maint ains a slightly negative pressure in secondary containment by the; a.
supply fan maintaining a constant air flow, while speed of the exhaust fan is varied.
b.
exhaust fan maintaining a constant air flow, while speed of the supply fan is varied.
c.
supply f an maint aining a constant air flow, while damper position of the exhaust fan is varied.
d.
exhaust fan maintaining a constant air flow, while damper position of the supply fan is varied.
ANSWER 3.20 (1.00) c.
i
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2t__tLeWI_111IEdi_12A11_eWQ.ELeWI-WIDE _GENEBig Page 32-BE1EQWilBIL111E1.11011 I
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REFERENCE F
i 1.
CNS: 0$TM, COR001 08, pg. 15.
288000K502
..(KA's)
I I
i QUESTION 3.21 (1.00)
In the Digatel Electro-Hydraulic Control (DEH) system, if the Governor
[
Velve control signal is in menuel, then the automatic control signal cill track the manuel signal in all modes EXCEPT:
[
l Mode 1
?
l b.
Mode 2 h
i c.
Mode 3 d.
Mode 4 I
)
i ANSWER 3.21 (1.00) i d.
.i REFERENCE 6
1.
CNS: OSTM, COR002-09, pg. 37.
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241000K308
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$$__EL&N1_11SIEdi_l2013.6NQELAN1-WIDE _ggugB1Q Page 33 BE1E0NSIBIL111EE.11011 QUESTION 3.22 (1.50)
In accordance with CNS Procedure 0.6.
" Personnel Safety,"
MATCH the f
type of breathing apparatus listed under COLUMN A with its designated use under COLUMN B.
(NOTE: Items listed under COLUMN B may or may not OOtch with items listed under COLUMN A.)
COLUMN A COLUMN B
- a. Self Conteined ____
1.
Removes radioactive contaminants from the atmosphere.
Not for use b.
Full Face in non-life supporting atmosphere.
I c.
Oro/Nasel
- 2. May be used in non-life supporting Respirator atmosphere, but time limited.
3.
Used for dust or paint laden atmospheres. Not for use in the presence of airborne radioactive contaminants.
4 May not be used in non-life supporting atmosphere, hose length limits effectiveness.
5.
Removes contaminants from the atmosphere.
Used in non-life supporting atmosphere.
ANSWER 3.22 (1.50) a.
2 b.
1 c.
3 (0.5 pts each)
REFERENCE 1.
CNS: Procedure 0.6, Pg 8 294001K113
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BESEQU11ElkillE1.1101) r i
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QUESTION 3.23 (1.00)
In accordance with procedure 9.1.2.1,
" Radiation, Contamination, f
Cnd Airborne Radioactivity Limits,"
exposure of the whole body and critical orgens of an individual shall be administratively limited to ___
a.... mrem / day and
....b.... mrem / week.
j ANSWER 3.23 (1.00) s.
150 mrem / day t.
300 mrem / week (0.5 pts each)
REFERENCE 1.
CNS:
Health Physics Procedure 9.1.2.1, Pg.
6.
i 29400lK104
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QUESTION 3.24 (1.00)
According to procedure 0.9,
" Equipment Clearance and Release Orders,"
i the correct sequence for isolating a pump is to:
a.
rock out the breaker, tag the control switch to a lockout or off position, close the vent or drain valve, close the suction isolation valve, then close the discharge isolation valve, b.
tag the control switch to a lockout or off position, rack out the breaker, close the discharge isolation valve, close the suction isolation valve, then close the vent or drain valve.
c.
tag the control switch to a lockout or off position, rack out the breaker, close the suction isolation valve, close the discharge isolation valve, then close the vent or drain valve.
d.
rack out the breaker, tag the control switch to a lockout or off position, close the suction isolation valve, close the vent or drain valve, then close the discharge isolation valve.
l
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21..EleUI 1111Edi_L2111_eNQ.EL6HI: WIDE _GEUEBig Page 35 BESEQN11tlLII1El_L1012 ANSWER 3.24 (1.00) b.
REFERENCE 1.
CNS: Procedure 0.9, Pg 3.
294001K101
..(KA's)
QUESTION 3.25 (1.50)
Fill in the blanks to complete the statements concerning
" Fire Door Watch":
Category 1 doors do not require a fire watch if obstructed and are d0signated by a _____e ____ colored dot.
Category 2 doors require a security watch who can act as a fire watch when they are open and are designated by a _____b_____ colored dot.
Category 3 doors require a fire watch unless they are equipped with an automatic closure device.
This category also includes doors within fire area barriers or safety related areas that are not common to the SOcurity system and they are designated by a _____c_____
colored dot.
ANSWER 3.25 (1.50) a.
green b.
yellow c.
red (0.5 pts each)
REFERENCE CNS Procedure 0.16, Pg 1.
294001K116
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2t__ELeNI_1111Edi_12A11.eND_EleUI:W10E_GENEBIQ Page 36 BESEQU11BILillE1_Il011 QUESTION 3.26 (1.00) l Procedure 0.25, " Surveillance Program," outlines the responsibilities cnd controls for the procedures used to verify that the facility is cperated in accordance with CNS Technical Specifications.
STATE the TWO (2) requirements that make up the acceptance criteria that a surveillance test must meet.
t
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ANSWER 3.26 (1.00) 1.
That there be no unexplained discrepancies for the test.
[+0.5) 2.
That the Technical Specifications (or applicable limits) are met.
(+0.5)
REFERENCE 1.
CNS:
Procedure 0.26, Pg 7.
294001A106
..(KA's)
QUESTION 3.27 (1.00)
Tho Plant Services Procedure 1.15, " Visitor / Tour Station Access,"
l governing access to protected and vital areas at CNS require that:
a.
Individuals under 15 years of age will not be allowed access to protected or vital areas of the plant.
b.
Individuals under 20 years of age will not be allowed access to any vital areas of the plant.
c.
Escort to visitor ratios will be one to five for the protected area.
d.
Escorts must card in and enter the turnstiles before the visitor and must card out after the visitor when exiting.
F T
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BE1EQU11RILIIIE1_11012 l
f ANSWER 3.27 (1.00) t d.
k REFERENCE 1.
CNS: Plant Services Procedure 1.15, pg. 1 & 2.
i 294001K105
..(KA's)
QUESTION 3.28 (2.00) i In accordance with procedure 9.1.2.1,
" Radiation, Contamination, and r
Airborne Radioactivity Limits,"
MATCH the eres of the body exposed, i
110ted in COLUMN A, with the quarterly exposure limit listed in
[
COLUMN B.
(NOTE:
Items listed in COLUMN 8 may match with more than ono item listed in COLUMN A.)
i COLUMN A COLUMN 8 e.
Whole Body 1.
1.25 REM t
b.
Skin of Whole Body 2.
18.75 REM c.
Hand and Forearms 3.
7.5 REM i
d.
Active Blood Forming Organs t
ANSWER 3.28 (2.00) a.
1 b.
3 t
c.
2 d.
1 (0.5 pts each]
I
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i dt EL&NI_1111Edi_L2A12 eND.ELeNI: WIDE.GENEBIQ Page 38
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BESEQW11BILIIIE1_L1012 i
l REFERENCE i
i 1.
CNS: Health Physics Procedure 9.1.2.1, pg.
5.
i r
294001K103
..(KA's) f f
QUESTION 3.29 (1.00)
According to procedure 2.0.3,
" Control Room /.ccess, Conduct. and Manning Requirements," instrument indicators that are placed in an Cbnormal state shall be designated by placement of a _____..__....
unless identified under en Equipment Clearance Order, t
t i
ANSWER 3.29 (1.00)
Rod Arrow REFERENCE 1.
CNS: Procedure 2.0.3.,
section 8.2.8.5, pg.
6.
294001A113
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EQUATIONS, C03STMTS, MD COHVERSIONS i
I 1
l 4'=m*C*deltai 6=U*A*deltai p
t I
P = Po*10sur*(t) p,p,t/T SUR = 26/T
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1 1
T = 1*/p + (p-p)/I p T=1/(p-$)
T=($-p)/Xp p = (Keff-1)/Keff
- deltaKeff/Keff p = 1*/TKeff + jeff/(1+ XT)
A = In2/tg = 0.693/tg X = 0.1 seconds-I I = to*e-ux CR=S/(1-Keff) 2 R/hr = 6*CE/d feet l
Water Parameters 1 ga;lon = 8.345 lbm = 3.87 liters i
1 ftJ = 7.48 gallons Density 9 STP = 62.4 lb /ft3 = 1 gm/cm3 m
Heat of vaporization = 970 Btu /lbm Heat of fusion = 144 Btu /lbm l
1 atmosphere = 14.7 psia = 29.9 inches Hg.
Miscellaneous Conversions I curie = 3.7 x 102U disintegrations per second i
1 kilogram = 2.21 lbm I horsepower = 2 54 x 103 Stu/hr 1 mw = 3.41 x 108 8tu/hr 1 inch = 2.54 centimeters degrees F = 9/5 degrees C + 32 degrees C = 5/9 (degrees F - 32) 1 Stu = 778 f t-lbf
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