IR 05000348/1993300
| ML20036A865 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/07/1993 |
| From: | Aiello R, Lawyer L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20036A851 | List: |
| References | |
| 50-348-93-300, NUDOCS 9305170107 | |
| Download: ML20036A865 (100) | |
Text
{{#Wiki_filter:#"4Q UNIT ED STATES [g jo,, NUCLEAR REGULATORY COMMISSION n REGION 81
fy 101 MARIETTA STREET,N W,
't AT LANT A, GE ORGI A 30323
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%, ,o'g ..... ENCLOSURE 1 Report No.: 50-348/93-300 Licensee: Southern Nuclear Operating Company, Inc.
P. O. Box 1295 Birmingham, AL 35201 Facility Docket No.
50-348 Facility License No. NPF-2 Facility Name: Joseph M. Farley Nuclear Plant Examination Conducted: April 5.15, 1993 2? .. b +C - NI Chief Examine. - Ronald F. Aiello Datedigned Examiners: S. Cahill, NRC, Region 11 F. Jaggar, INEL Approved By: . 3 7 f)' Lawre'nce L. Lawyer, Chief Dat6 ' Signed f [ Operator Licensing Section 1 r Operations Branch ! f Division of Reactor Safety ' SUMMARY I i Scope: { i NRC examiners conducted regular, announced operator licensing requalification i examinations and associated inspection activities during the_ period of April 5-15, 1993.
Examiners administered examinations under the guidelines of the Examiner Standards (ES), NUREG-1021, Revision 7.
Twelve Senior Reactor ' , Operators (SR0s) and four Reactor Operators (R0s) received written and i operating examinations'. For the simulator portion of the examination,
operators comprised four crews. The examiners also conducted licensed j operator interviews in accordance with NRC Inspection Procedure 41500, , Training and Qualification Effectiveness, f l
i 9305170107 930507 < PDR ADOCK 05000348 , V PDR ! i
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l Enclosure 1
l l , Results: j Operator Pass / Fail: SRO R0 Total Percent Crews Percent l
Pass
4
100
100
! Fail
0
0
0
l Examiners judged that the Joseph M. Farley Nuclear Plant requalification l program was satisfactory based on the results of the examinations.
j
Examiners identified a weakness in operator knowledge (paragraph 2.i).
, No violations or deviations were identified.
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, L I { REPORT DETAILS ! ! t 1.
Persons Contacted
! Licensee Employees
- W. Bayne, Safety Analysis and Engineering Review (SAER) Supervisor l
p
- P. Crone, Operations Superintendent
!
- J.
Deavers, Senior Plant Instructor ! S. Freeman, SAER Representative
- R. Hill, General Manager Nuclear Plant
- D. Martz, SAER Representative l
C. McLean, Senior Plant Instructor
- C. Nesbitt, Manager Operations
J. Osterholts, Assistant General Manager Support ! '
- L. Stinson, Assistant General Manager Operations
- W. Vanlandingham, Supervisor Operations Training
- L. Williams, Manager Training NRC Personnel l
- M. Morgan, Resident Inspector
!
- Attended exit 2.
Discussion , i a.
Scope ! i NRC examiners conducted regular, announced operator licensing i requalification examinations and associated inspection activities j during the period of April 5-15, 1993.
Examiners administered examin- ' ations under the guidelines of the Examiner Standards, NUREG-1021,
Revision 7.
Twelve SR0s and four R0s received written and operating
examinations.
For the simulator portion of the examination, operators i comprised four_ crews. The examiners also conducted licensed operator ! interviews in accordance with NRC Inspection Procedure 41500, Training ! and Qualification Effectiveness.
! b.
Reference Material The examination team compared the utility's reference material to the
recommendations in NUREG-1021, ES-602, and determined that while the ! reference material was adequate to support the examination, some . improvements were appropriate. The inspectors reviewed the licensee's j 1992 Licensed Operator Requalification Program sample plan.
The } sample plan was compared to NUREG-1021, ES-601, Attachment 2, and i NUREG/BR-0122, Revision 5.
The sample plan contained the items listed ! in ES-601, Attachment 2, but did not describe a procedure for ! selecting Knowledges and Abilities (K/As) from the PWR or plant - specific K/A catalog to develop a test outline as recommended in j BR-0122, Re' vision 5, Chapter 2.
The utility's reference material did ! not give explicit guidance for developing 'a sample plan as suggested
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Report Details
l l NUREG 1021, Attachment 2, page 29. The verbal description of the ! selection process was obtained from the facility training staff during l the onsite preparation week.
The examiners found the sample plan to-
be difficult to interpret due to the use of undefined terms and cross- ! reference numbers. The examination team discussed enhancements with t the facility, such as including a short guide for using the sample ! plan and simplifying some sections to improve future submittals.
c.
Examination Development
i The examination team conducted a comparison of the facility's proposed ! written, walk-through, and dynamic simulator examinations to the i guidance of NUREG 1021, ES-602.
The NRC substituted new material for i about 10 percent of each section of the examination. The team .! approved.the remainder of the examination with the following minor l changes.
l i The team noted that most of the questions were still lacking direct { references which was also identified in last year's requalification ! examination report 50-348/92-300. The facility responded that they , j had agreed to incorporate references for each question as part of j their yearly review of the examination bank.
Each annual review '
encompasses approximately 150 questions out of the 850 questions in ' the examination bank. At this rate it would take over four years to i ' incorporate references throughout the bank. The facility reviewed ! many other questions outside the scope of the yearly review. The l facility is considering adding references during these other reviews ! ]_ to increase the progress being made.
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Examination Administration } The licensee's administration of the examinations was well planned and ! coordinated.
The examination administration satisfactorily met all ! the recommendations delineated in NUREG 1021,-ES-601 and ES-604, ! Paragraph D, respectively.
The team determined that all facility i , evaluators were satisfactory.
[ ~ i e.
Operator Performance { Each licensed operator passed a written examination and an operating i test consisting of a walk-through examination and a dynamic simulator i examination, developed and administered in accordance with NUREG 1021,
ES-602, ES-603, and ES-604, respectively l > >
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j i (1) Written . Operator performance was satisfactory on four questions in the-Part B examination that were inserted by the examination team to
test previously identified facility knowledge deficiencies, j (2) Job Performance Measure (JPM) Performance i Several operators had difficulty performing JPM CRO-0658 (Perform an ! Emergency Boration).
FI-110A is the flow indicator for the normal '; emergency boration flow path. When the alternate manual path is.
j used via valve FCV-113A and local valve V185, FI-Il0A will not .! indicate any flow. An operator must look at boric acid blender ' i FR-113 to verify boric acid flow is occurring when using manual emergency boration. Many operators were unfamiliar with this and continued to check F1-110A for flow indication once alternate manual emergency boration was established.
Most of the operators did not '{ verify flow on FR-ll3 until directed in the text of A0P-27.0. This l was not critical, but was an indication of a system knowledge i s deficiency.
' The first step of JPM CRO-333D, Lineup for Cold Leg Recirculation (ESP 1.3, Step 6.1), tasked the operator to verify that the
recirculation valve disconnects were closed using an attachment.
Several of the operators were confused on how to complete this step.
They couldn't decide whether to locally reperform the already completed actions of the attachment or to verify it via main control _ board indications to confirm that the disconnects were closed. This ! ' confusion stemmed from the fact that at Farley the term " verify" may i include performance if necessary.
Some of the operators completed _- this step satisfactorily while others either dispatched someone else ! to do it, said it could not be done, or didn't know how to do it.
l This verification must be completed to ensure train-separation in ] the event of a passive failure on one of the trains. This problem j , was also identified during the simulator portion of the examination < (see paragraph 2.e.(3), below). The intent of the procedure was to , " verify" that the disconnects were closed.via main control board [ indications. Overall, operator performance was adequate.
, ! (3) Simulator Crew performance in the simulator part of the examination was i ? satisfactory.
On two occasions, the board operators neglected to use rod control in addition to boron addition to reduce power.. This resulted in an axial flux difference in excess of the Technical ' j Specification (TS) Limiting Condition for Operation (LCO) thus .! requiring the operators to enter the action step of T.S. 3.2.1.
j The lack of definition of " verify" that was identified in paragraph 2.e(2) above by the examination team during JPM CRO-3330 concerning.
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the recirculation valve disconnects, was also encountered in the simulator during scenario 92-8A, event 4 (Large Break LOCA).
Overall, operator performance was satisfactory.
f.
Program Evaluation Based on the examination results, the Joseph M. Farley Nuclear Plant Requalification Program meets the criterion established in NUREG-1021, ES-601. The examiners judged that the Joseph M. Farley Nuclear Plant requalification program was satisfactory.
g.
Simulator Facility NRC examiners reviewed the licensee's record of simulator usage during calendar year 1992.
The inspectors found that the simulator was available for a total of 6,240 hours based on a Monday through Friday usage.
During these hours of availability, the simulator was used for . operator training related functions 42 percent of the time.
It was used for non-operator training functions 1.9 percent of the time, and it was idle 56.1 percent of the time. The examiners concluded that the simulator availability for operator training usage was satisfactory.
The examination team identified no simulator facility problems.
h.
General Observations The examiners identified on JPM CRO-365C, " Perform Actions at the Hot Shutdown Panel (HSP)", that the procedure used for the administration of the JPM listed the control for FCV-122 as HIK-122. The JPM document-ation also had the same information.
The tag on the HSP listed it as FCV-122.
The examiner informed the appropriate plant personnel.
i. Training and Qualification Effectiveness (41500) In order to assure public health and safety, facility licensees are required to maintain a continuous training program for NRC licensed individuals and operating crews.
Each facility must have a program that meets the requirements specified in 10 CFR 55.59.
This regulation requires licensed. individuals to pass an annual operating test and a periodic comprehensive written examination. The Commission has specified that facility licensees may utilize a Systems Approach to Training (SAT) for developing and implementing this training, in lieu of adhering to some of the specific guidance in 10 CFR 55.59.
The inspector identified a weakness in operator knowledge.
The inspectors conducted technical interviews with licensed operators in accordance with NRC inspection procedure 41500, to determine that personnel have qualifications commensurate with the performance requirements of their jobs and to ensure training improvement programs were effective. During the interviews and performance observations, the inspectors determined that the overall quality of work was consistently _- _-_-__ -___- __ __
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! meeting job performance requirements. However, many operators displayed i knowledge weaknesses in the following: knowing the difference between an Anticipated Transient Without Trip (ATWT) and a failure of the.
! Reactor Protection System (RPS), the ATWT Mitigating System Actuation Circuitry (AMSAC) arming and actuation circuity, the loop flow detection
system, and the relationship between Permissives P-10, P-13, and P-7.
! j, Procedures l Title 10 CFR Part 50, Appendix B, requires that activities affecting i quality shall be prescribed by documented instructions, procedures, or ' drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
The inspector examined the following E0Ps for quality and usefulness and found them to be satisfactory: ECP-1.1, " Loss of Emergency Coolant Recirculation", Revision 11 EEP-0, " Reactor Trip or Safety Injection", Revision 15 EEP-1, " Loss of Reactor or Secondary Ccalant", Revision 13 EEP-3, " Steam Generator Tube Rupture", Revision 11 ESP 1.1, "SI Termination", Revision 9 ESP 1.2, " Post LOCA Cooldown and Depressurization", Revision 10 ESP 1.3, " Transfer to Cold Leg Recirculation", Revision 9 FRP-P.1, " Response to PTS", Revision 8 FRP-H.1, " Response to Loss of Secondary Heat Sink", Revision 13 5.
Exit Interview At the conclusion of the site visit, the examiners met with the represent-atives of the plant staff indicated in paragraph I to discuss the results of the examinations and inspection findings. The facility licensee did not identify as proprietary any material provided to or reviewed by the examiners. Dissenting comments were not' received from the licensee.
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ENCLOSURE 2 '
, ! SIMULATOR FACILITY REPORT i i Facility Licensee: Joseph M. Farley Nuclear Plant ! Facility Docket Nos.: 50-348 and 50-364 ! Operating Tests Administered During: The weeks of April 5 and 12,1993 ! l This form is used only 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 i 10 CFR 55.45(b).
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 i response to these observations.
l ' ! The examination team identified no simulator facility problems.
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RTYPE: K2,04 (Individual) - _ RTYPE: K2.07 ! (KEY) i l !
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TRAINING DEPARTMENT EXAMINATION , i NAME(*RCVR): CROUP: '
- DATE: 04/05/93 EXAM NUMBER: A93C5W1R EXAM TITLE: LRP-93 RO CY-5 WK-1 PART-A TOTAL POINTS:
13.00 , (*XREF) NRC INSTRUCTIONS , ?
1.
This is a 1.0 hour examination.
2.
Point value for each question is indicated in the ques-tion header.
3.
Answer all questions: [[] On a separate paper.
[[] On the answer sheet by circling or marking the cor-l rect response or filling in the blanks.
[X] On the same page as the question..If extra room is ! needed, use the reverse side of the previous page j ' or use extra paper.
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CHEATING OF ANY KIND IS STRICTLY FORBIDDEN. ANY INDI-VIDUAL CAUGHT CHEATING WILL AUTOMATICALLY FAIL THE
EXAMINATION AND DISCIPLINARY ACTION WILL BE TAKEN.
l i 5.
ALL WORK DONE ON THIS EXAMINATION IS MY OWN.
TO MY , KNOWLEDGE, I HAVE NEITHER GIVEN NOR RECEIVED AID.
] FURTHERMORE, I WILL NOT DIVULGE THE CONTENTS OF THIS j l EXAMINATION TO ANYONE ELSE VHO MAY TAKE IT.
' EXAMINEE' S SIGNATURE
i l'f (i LJA yl 'I EXAM GRADED BY: PREPARED BY: p dA GRADING / MATH REVIEL: BY: APPROVED BY: / Training Manag(r/ Supervisor
- lNDEXING INFORMATION
! 2/24/89 1 of 2 -.-
l .. PIET A (STATIC SIMULATOR) AND PART (OPEN REFERENCE) , . < EXAMINATION GUIDELINES The procedures, drawings, Tech Specs, and other material ,
provided may be used as references while taking this examina-
tion.
If this is a " Static Simulator-Part A" exam, the simu 1ator may be used as a reference to gather data for answering q the questions.
If this is an "Open Reference-Part B" exam, i the simulator may be used as a reference but no si.mulator ' data should be used to answer the questions.
The following guidelines must be followed while using , these references: < - The exam may require all examinees to refer to the same
control board indications Care must be taken to main- ! tain exam security and avoid any possibility of compro-l mise.
d - Do not leave pencil or pen marks in the reference mate-
rials.
i L' hen you are finished with reference materials, ensure
j that the materials are closed and/or returned to their l original location.
I ! Keep your exam aaterials together_ k'hile at the control l board or procedures, take your exam with you and keep your ' answers covered.
k" hen you have finished and turned in your exam, you may j leave the exam area and DO NOT discuss the exam with any one ' who has not taken it.
i Do not forget to follow the basic rules of exam taking: l - Static Simulator-Part A questions are syst+ m based and j apply to the static sirrulator conditions unless otherwise i specified.
- Opcn Reference-Part B questions are procedure based and are
not based on static simulator conditions.
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- Answer all questions independently of each other unless i spccified by the question.
> i ' - Answer all parts of each question; do not leave any answers blank
- If a question is unclear or you are uncertain as to the
intent -- ask ONLY the proctor for help prior to stating
.
any assumptions.
< i - Show all work and state any assunptions.
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- _uestion Number:
052102F10003 Points: 1.00 Q j i i f Service water valves MOV-514 and MOV-516 are out of position j , , on MLB-2 indication. All MLB-2 lights have been tested to be i
working properly.
Bas,cd on current static plant conditions, -! ! ' j select the correct response from below: (circle the correct ^ response.)
A.
The valves are in the process of stroking and should j continue to stroke until they are closed.
i B.
Flow to the turbine building can only be isolated by l local valve operation.
l ! C.
The valves will not continue to stroke due to loss of B 'I train 4160V power.
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D.
This lineup is robbing iIow from safety-related equip i b l ment.
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! i ANSWER: C.
Toint Value: 1.0 Answer Time: 4.0 Mins. Part A.
! ' I l Static Sim Scenario Nos. 14E - l l S&K No.
247613023320
K/A No.
076000K1,16 .076000K2.08 ! { RO/SRO Impf.
3.6 /3.8 3.1 /3.3 / ,i
Obj ective 052102F10 052530A13 l j Reference 052102F, Service Vater ! j Rev. Date 3/22/93-l Rev. Date 3/24/93 j l . ! > L l
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O O .. . . . ] OS2102G20007 Points: 1.00 Question Number:
! ! Prior to the reactor trip, the "A" train of CCW was desig i nated as the "on-service" train, and the B compor.ent cooling ! ! water (CCW) pump was the running CCW pump.
Based on current ! I
plant conditions, which of the following pump (s) should be running now, assuming no operator action was taken? (Circle the correct response.)
A.
A & C CCW pumps
B.
B & C CCW pumps , C.
B CCW pump - -1 D.
C CCW pump l l F i ! ANSWER: C.
Point Value: 1,0 Answer Time.
3.0 Mins. Part A.
Static Sim Scenario Nos.14E - ~ ~ i S&K No.
240411030320 K/A No.
008030A3.04 008010A3.01 RO/SRO Impf, 3.6 /3.7 3.2 /3.2 , Objective 052102G20 052520101 , Reference 052102G. CCW j Rev. Date 3/22/93 , i , I i k ! ! !
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i L, - - O O i - . 052102H15007 Points: 1.00 Question Number:
_ i i J d Smoke has been reported and verified coming from 1A MDAFV i e l i pump.
The shift supervisor has determined the pump must be
a l l stopped.
Based on static plant conditions, which of the l i l following actions would heer -' "mFW pump stopped? (Circle- ! d I ! the correct response.)
A.
Place the 1A MDAFW s nandswitch on MCB to stop , and release.
.i
l B.
The 1A MDAFW pump cannot be secured from the MCB unless l
the SI is reset first Operation of the 1A MDAFV i l start /stop handswitch on the MCB to stop and release is [ j then required.
!
, ' C.
Placu _he A train Auto / Defeat switch in DEFEAT and place ! the 1A MDAFW pump start /stop handswitch to STOP.
l r L.
The 1A MDAFU pump cannot be secured from the MCB.
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Operation at the HSDP is required to secure the pump.
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f ANSWER: D.
Point Value: 1.0 Answer Time: 3 0 Mins. Part A.
Static Sim Scenario Nos. 14E ! ! S&K No.
24111020515 246111020956 ! l K/A No.
061000K4.06 061 GEN 10 ( I I RO/TRO Impf.
4.0 /4.2 3.5 /3.6 / , Objective 052102H15 .
Reference 052102H, AFW 052202D, HSPs ! l Rev. Date 2/3/93 ! f Rev. Date 3/22/93 { l Rev. Dr.te 3/24/93 j ! r f ! , l l ! ! ! I i I i l
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052103D20008 Points: 1.00 Question Number:
i
Annunciators for instrument inverters IC, ID. and 1G are presently in alarm.
How is plant operation affected by these
inverter faults? (Circle the correct response.)
' A.
120V AC vital panels 1C and ID are deenergized j B.
120V AC vital panels 1C and ID will be deenergized in approximately two (2) hours.
C.
Loss of power to protection cabinet IV has occurred.
l D.
120V AC vital panels 1C and ID are on alternate supply.
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ANSWER: B.
Point Value: 1.0 Answer Time: 4.0 Mins. Part A.
f Static Sim Scenario Nos. 14E
I S&K No.
246208026000 246236026200 K/A No.
000057-KO.05G 000057-AO 12G 000057EA0.12G f RO/SRO Impf.. 3.4 /3.6 3.3 /3.4 3.3 /3.4 Obj ec tive 052103D20 052103C10 Reference 052103D, 120V AC Distribution f FNP-0-ARP-2.1 LOC VD1 ! Rev, Date 2/3/93 { l -; i ! ! t ^* ) I !
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O & C/ w 052103F04003 Points: 1.00 Question Number: S t Based on present static plant conditions, which one of the following actions taken at the EPB, by itself, will start the IB emergency diesel generator assuming all support systems are aligned for normal operation? (Circle the correct response.)
A.
Place the IB D/G unit selector switch to the Unit 1 position.
B.
Place the IB D/G mode selector switch to mode 2 posi tion.
C.
Press the IB D/G ettergency start reset pushbutton, D.
Reset the SI. then press the EPB IB D/C start pushbutton.
ANSk'ER : B.
Point Value 1.0 Answer Time' 4.0 Mins. Part A.
Static Sim Scenario Nos. 14E S&K No.
246426022250 246408022710 K/A No.
000056A2.14 064000A3.09 RO/SRO 1mpf.
4.6 /4.6 4.0 /4.0 / Objective 052103F04 052531r05 Reference 052103F, DG Sequcneers Rev. Date 2/3/93 Rev Date 3/24/93 , f t i
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- _. _ _ _ . ~_ _ _.. _ l l O O - t a 052105C27001 Points: 1.00 Question Number:
I
! Based on static plant conditions, which of the following j statements is correct concerning the main generator hydrogen
! seals? (Circle the correct response.)
[
A.
The seal oil backup pump should have already automati cally started and be maintaining seal oil pressure'at H2 pressure + 8 psig.
i l B.
The air side emergency DC seal oil pump should have j started and should be maintaining seal oil pressure at
H2 pressure + 8 psig.
C.
The H2 side seal oil pump will maintain seal oil i pressure at H -pressure + 8 psig.
4 i
l t l D.
The seal oil backup pump will automatically start-l J when bearing oil pressure drops to 12 psig and maintain j seal oil pressure at H2 Pressure + 8 psig.
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! AN5k'ER: D.
Point Value: 1.0 Answer Time: 4.0 Mins. Part A.
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Static Sim Scenario Nos. 14r S&K No.
245011022020 l
K/A No.
045 GEN 07 045010K4.23 ! RO/SRO Impf.
2.6 /2.8 3.4 /3.6 /___ i
Obj ective 052105C27
Reference 052105C, Main Generator and Auxiliaries
Rev. Date 3/19/91
Rev. Date 2/4/93 l l Rev. Date 3/22/93 '
Rev. Date 3/24/93 l l
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- _ _ _ _. - ___ -. O O . . 052201F06001 Points: 1.00 Question Number:
Based on static plant conditions, DRPI indication can be-restored by: (Circle the correct response.)
A.
Selecting NORMAL on the DRPI power supply bus transfer switch.
B.
Selecting ALTERNATE on the DRPI power supply bus trans fer switch.
C.
Selecting EMERGENCY on the DRPI power supply bus trans fer switch.
D.
Indication cannot be restored.
ANSWER: A.
Point Value: 1.0 Answer Time: 3.0 Mins. Part A.
Static Sim Scenario Nos. 14E 24A S&K No.
241403000130 K/A No.
014000K406 014000A2.02 RO/SRO Impf.
3.4 /3.7 3.1 /3.6 / Objective OS2201F06 Reference 052201F, DRPI Rev. Date 11/2/91 Rev. Date 2/5/93 Rev. Date 3/22/93
..... . .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ - - - - _ - _ _ _ _ _ _ _. - - - -. _ _ - - o o .. . ... 052521K02003 Points: 1.00 Question Number:
Radiation monitor R-14 has a high alarm and yet it indicates 10 cpm.
The reason for this is: (Circle the correct response.)
A.
The alarm may be valid. With containment purge. iso lated, the indication is reading normal pre-event readings.
B.
The alarm may be valid. The low reading is caused by the loss of B train power.
C.
The alarm is invalid.
The alarm failed on when the power supply auto shifted to A train.
D.
The alarm is invalid.
No other indication verifies.an alarm could have occurred.
ANSWER: B.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos. 14E S&K No.
2473090200500 247256020150 K/A No.
072 GEN 13 072 GEN 13 RO/SRO Impf, 3.0 /3.1 3.0 /3.1 / Rev. Date 2/26/91 Rev. Date 3/22/93 Rev. Date 3/24/93 <
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& u W i 052530A13009 Points: 1.00 Question Number:
Prior to the reactor trip and safety injection, the 1A, 1B, 1D, and IE service water pumps were running.
During the immediate operator action steps of EEP-0, Reactor Trip or Safety Inj ection, the operator finds only the IB SW pump running.
Which ONE of the following would have been the expected service water system response to the plant transient? (Circle the correct response.)
A.
The IC SW pu:r.p should have auto started l>ecause the spare pump selector switch is normally in the 1A position.
E.
The 1C SW pu:rp should have auto started because the ESF sequencer was activated.
C.
The ID and 1E pumps tripped because of the safety inj ection but are available to be started if needed.
D.
The lA and 1B SW pumps should both be running because the spare pu:np selector switch is normally in the IC position.
ANSWER: D.
Point Value: 1.0 Answer TIrne : 3.0 Mins.
' Stat.ic Sim Scenario Nos. 14 E SLK No.
300903110215 K/A No.
000007A202 RO/SRO Impf.
4.3 /4.6 / _/ Rev Date 3/19/91 Rev. Date 2/8/93 Rev Date 3/22/93 Rev. Date 3/25/93 . l ! t !
. _ _ _ _ -.. _ _ -.___. . ._ ___ _.... _. _. _... _. -...m---_._m.
... _. _. _... _.,
. - O O
. . 052531F07016 Points: 1.00 Question Number: 10 'i I I
Concerning the 2C DG: (Circle the correct response.)
)
A.
It should be secured due to lack of service water flow, ' i B.
It can be procedurally aligned to supply power to the 1G 4160V bus, allowing the BIG ESS sequencer to run.
C.
The B1J and B2J LOSP sequencers should have aligned the , 2C diesel to Unit 1 and Unit 2.
D.
It can be procedurally aligned to supply power to the IG i 4-4160V bus to allow manually starting B train components.
l i
ANSk'ER : D.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos. 27E r S&K No.
246402000200 i K/A No.
064000A4.06 -! ' j RO/SRO Impf.
3.9 /3.9 / / l Revised 1/16/92 l ' Rev. Date 3/23/93 ' Rev. Date 3/24/93 ' . i . t
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- . -! ' 052531F09015 Points: 1.00 Question Number: 11 Based on current static plant conditions, which of the following statements is correct? (Circle the correct , ! , response.)
! ! A.
Opening the RCS PRZR aux spray valve HV-8145 will cause . J an RCS pressure reduction.
j i B.
No means of operator initiated RCS pressure reduction is f available at this time.
j i C.
lA loop spray valve PCV-444C can not be used for RCS f L pressure reduction.
l D.
Opening PRZR PORV PCV-445A will cause an RCS pressure f reduction.
! ! ! , ANSVER: D.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos.-14E S&K No.
240235020380 t K/A No.
000009EA1.01 ! RO/SRO Impf.
4.4 /4.3 / / l Rev. Date 2/5/92 i ,
1 ! !
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l 052520D04011 Points: 1.00 Question Number: 12 l 'i ! CAUTION: THIS QUESTION IS EDT RELATED TO THE STATIC l l SIMULATOR CONDITIONS.
! During a loss of reactor coolant flow recovery due to .
l the 1B RCP tripping, the operator fails to place the "B" l ! loop pressurizer spray valve in manual and fully close the j valve. All other actions of the loss of reactor coolant flow procedure have been taken. A short time later, the
annunciator HAS, "PRZR PORV TEMP HI," comes in.
The i f temperature indicators read as follow: - j TI463 200* TI467 125' i TI465 125" TI469 125' i I , This alarm was received due to: (Assume all controls are !, fully operational with A & E BU HIR groups in "0N.") (Circle l r the correct response.)
A.
An obvious pressurizer power-operated relief valve I temperature indicator error.
i B.
"A" loop spray flow is bypassing the PRZR, allowing j pressure to increase, j ! ! C.
"B" loop spray flow is bypassing the PRZR, allowing . l pressure to increase.
! D.
The "B" spray valve controller feedback to PK-444A is . ! ' causing controller windup, resulting in unnecessary PORV l operation.
l , ! !
ANSWER: B.
Point Value: 1.0 Answer Time: 4.0 Mins. Part A.
{ ! Static Sim Scenario Nos.
~ i S&K No.
241013020720 K/A No.
000015A0.06G i RO/SRO Impf.
3.1 /3.2 / / ! Rev. Date 10/8/91
Rev. Date 2/5/93 ' Rev. Date 3/24/93 i i
f
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1 052531C09005 Points: l'.00 Question Number.: 13 ) - - l.
l
l ' 'l l CAUTION: THIS QUESTION IS NOT RELATED TO THE STATIC i
- i
SIMULATOR CONDITIONS.
j l I [ Which one of the following conditions would NOT be expected l
i " to occur during a natural circulation cooldown? (Circle your l i j choice.)
f i A.
A steadily decreasing cold leg temperature with a . '.. constant steam pressure i t B.
A steadily decreasing steam pressure while maintaining a = , l steadily increasing or constant RCS subcooling i
! i-C.
Steam pressure and hot leg temperature steadily decreas i ! ing ] l
] D A steadily decreasing core t2T with a decreasing cooldown-
rate ! ! ANSk'ER : A.
Point Value: 1.0 Answer Time; 2,0 Mins.
Static Sim Scenario Nos
- '
S&K No.
240206023570
K/A No.
000017EA1.21 002020A403
RO/SRO Impf.
4.4 /4.5 4.3 /4.4 /___ j Rev. Date 2/8/93 e t I l
I I e . I
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(3 m . 03/31/93 ALABAMA POWER COMPANY * . EXNi GRADING SilEET EXAM NAME: A93C5W1R CLASS NAME: LRP-93 TOTAL POINTS: 13 DATE GIVEN: 04/05/93 STUDENT ID / NAME: / QUESTION POINT POINTS
VALUE MISSED 1 - 052102F10003 1.00 2 - 052102G20007 1.00 3 - 052102H15007 1.00 4 - 052103D20008 1.00 5 - 052103F04003 1.00 6 - 052105C27001 1.00 7 - 052201F06001 1.00 8 - 052521K02003 1.00 9 - 052530A13009 1.00 , 10 - 052531F07016 1.00 11 - 052531F09015 1.00 12 - 052520D04011 1.00 13 - 052531009005 1.00 TOTAL POINTS MISSED: FINAL SCORE: _ % ,
> O A f., /chr. 9J-J oo/<p g '
W Na '
RTYPE: K2.04 (Individual) T PE: K2.07 (KEY) ~ o TRAINING DEPARTMENT EXAMINATION NAME(*RCVR): GROUP:
- DATE: 04/05/93 EXA'i NUMBER : A93C5W1S EXAM TITLE: LRP-93 SRO CY-5 WK-1 PART-A TOTAL POINTS:
13.00 (*XREF) NRC INSTRUCTIONS 1.
This is a 1.0 hour examination.
2.
Point value for each question is indicated in the ques-tion header.
3.
Answer all questions: [[] On a separate paper.
[] On the answer sheet by circling or marking the cor-rect response or filling in the blanks.
[5] On the same page as the question.
If extra room is needed, use the reverse side of the previous page or use extra paper.
4.
CHEATING OF ANY KIND IS STRICTLY FORBIDDEN. ANY INDI-VIDUAL CAUGHT CHEATING WILL AUTOMATICALLY FAIL THE EXAMINATION AND DISCIPLINARY ACTION WILL EE TAKEN.
5.
ALL WORK DONE ON THIS EXAMINATION IS MY OWN.
TO MY KNOWLEDGE, I HAVE NEITHER GIVEN NOR RECEIVED AID.
FURTHERMORE, I VILL NOT DIVULGE THE CONTENTS OF THIS EXAMINATION TO ANYONE ELSE WHO MAY TAKE IT.
EXM41 NEE'S SIGNATURE < ' / EXAM CRADED BY PREPARED BY: /4 A4 _,. r CRADING/ MATH REVIEW BY: APPROVED BY: I g o- / 1rainingManagr/ Supervisor kINDEXING INFORMATION 2/24/89 i l of 2 i
- AEh
PAi A (STATIC SIMULATOR) AND PART !'(OPEN REFERENCE)
EXAMINATION GUIDELINES The procedures, drawings, Tech Specs, and other material provided may be used as references while taking this examina-tion.
If this is a " Static Simulator-Part A" exam, the simu lator may be used as a reference to gather data for answering the questions.
If this is an *Open Reference-Part B" exam, the simulator may be used as a reference but no simulator data should be used to answer the questions.
The following guidelines must be followed while using these references: - The exam may require all examinees to refer to the same control board indications.
Care must be taken to main-tain exam security and avoid any possibility of compro-mise - Do not leave pencil or pen marks in the reference mate-rials.
- When you are finished with reference materials, ensure that the materials are closed and/or returned to their original location.
Keep your exam materials together.
While at the control board or procedures, take your exam with you and keep your answers covered.
When you have finished and turned in your exam, you may leave the exam area and DO NOT discuss the exam with any one who has not t ake n it.
Do not forget to follow the basic rules of exam taking: - Static Simulator-Part A questions are system based and apply to the static simulator conditions unless otherwise specified.
- Open Reference-Part B questions are procedure based and are not based on static simulator conditions.
- Answer all questions independently of each other unless specified by the question.
- Answer all parts of each question; do not leave any answers blank - If a question is unclear or you are uncertain =is to the intent -- ask 0:;LY the proctor for help prior to stating any assumptions.
- Show all work and state any assumptions.
2 of 2 -
.. _ _.. _ - - _, - _ - _ -. - ~ - ~ . - __ _ _ _.. _. - _. _.. _ - - _ _ _. _ ___.
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l O o ! - . i 052102F10003' Points: 1.00 Question Number:
l
- t ' l Service water valves MOV-514 and MOV-516 are out of position i
I on MLS-2 indication. All MLB-2 lights have been tested to be working properly.
Based on current static plant conditions, select the correct response from below: (Circle the correct l l response.)
! !
I A.
The valves are in the process of stroking and should ! continue to stroke until they are closed.
l
B.
Flow to the turbine building can only be isolated by i local valve operation.
{ ! C.
The valves will not continue to stroke due to loss of B < I train 4160V power.
a !
' D.
This lineup is robbing flow from safety-related equip l ment.
l , i
ANSWER: C.
Point Value: 1.0 Answer Time: 4.0 Mins. Part A.
Static Sim Scenario Nos. 14E S&K No.
247613023320 K/A No.
076000K1.16 076000K2.08
4 RO/SRO Impf.
3.6 /3.8 3.1 /3.3 __ _ / i Objective 052102F10 052530A13
Reference 052102F, Service Water
Rev. Date 3/22/93 i Rev. Date 3/24/93 l l l
4
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- [D A, . v 052102G20007 Points: 1.00 Question Nu:tber :
1 Prior to the reactor trip, the "A" train of CCW was desig nated as the "on-service" train, and the B corrponent cooling water (CCW) pump was the running CCW pump.
Based on current plant conditions, which of the following pump (s) should be running now, assuming no operator action was taken? (Circle the correct response.)
A.
A 6 C CCW pumps B.
B & C CCW pu:rps i C.
B CCW punp D.
C CCW pun:p A' SWER : C.
Point. Value 1.0 Answer Time: 3.0 Mins. Part A.
Static Si:n Scenario Nos.14E __ S&K No.
240411030320 K/A No.
008030A3.04 008010A3.01 RO/SRO Impf.
3.6 /3.7 3.2 /3.2 Objective 052102G20 052520101 Reference 052102G, CCW Re, Date 3/22/93 <
I < ' l
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O & - - . 052102H15007 Points: 1.00 Question Number:
Smoke has been reported and verified coming from lA MDAF"w' { pump.
The shift supervisor has determined the pump must be , . stopped.
Based on static plant conditions, which of the
following actions would keep the MDAFW pump stopped? (Circle the correct respense.)
i ' A.
Place the 1A MDAFW start /stop handsvitch on MCB to stop and release.
, B.
The 1A MDAFW pump cannot be secured from the MCB unless the SI is rese first.
Operation of the 1A MDAFW , start /stop handswitch on the MCB to stop and release is then required.
C.
Place the A train Auto / Defeat switch in DEFEAT and place the 1A MDAFW pump start /stop handswitch to STOP.
' D.
The lA MDAFW pump cannot be secured from the MCB.
! Operation at the HSDP is required to secure the pump.
! ANSk'ER : D.
Point Value 1.0 Answer Time: 3.0 Mins. Part A.
Static Sim Scenario Nos. 14E l S&K No.
24111020515 246111020956 ' K/A No.
061000V.4.06 06] GEN 10 l RO/SRO Impf.
6.0 /4.2 3.5 /3.6 ___ / i Objective 052102H15 Peterence 052102H, AFW 052202D, HSPs j Rev Date 2/3/93
, Rev Date 3/22/93 f Rev. Date 3/24/93 .
i i J i i l
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. 052103D20008-Points: 1.00 Question Number: 4 Annunciators for instrument inverters IC. 1D, and 1G are presently in alarm. How is plant operation affected by these inverter faults? (Circle the correct response.') A.
120V AC vital panels 1C and ID are deenergized.
B.
120V AC vital panels 1C and ID will be deenergized in approximately two (2) hours.
C.
loss of power to protection cabinet IV has occurred.
D.
120V AC vital panels 1C and ID are on alternate supply, j . !, ANSk'ER : B.
Point Value: 1.0 Answer Time: 4.0 Mins. Part A.
Static Sim Scenario Nos. 14E i S&K No.
246208026000 246236026200 .l K/A No.
000057+KO.05G 000057-AO.12G 000057EA0.12G j
RO/SRO Impf.
3.4 /3.6 3.3 /3.4 3.3 /3.4 Obj ective 052103D20 052103C10 Reference 052103D, 120V AC Distribution FNP-0-ARP-2.1 LOC VDl.
, Rev. Date 2/3/93
- !
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- .-. . _. _ ... .-. - -- . . .. . - -..t i . O O l - 052103F04003 Points: 1.00 Question Number: .5-Based on present static plant conditions, which one of the ! following actions taken at the EPB, by itself, will start the [ ' 1B emergency diesel generator assuming all support systems i are aligned for normal operation? (Circle the correct response.)
l i A.
Place the 1B D/G unit selector switch to the Unit 1 l position.
.; B.
Place the IB D/G mode selector switch to mode 2 posi
tion.
[ t C.
Press the 1B D/G emergency start reset pu eN.u t t on.-
! D.
Reset the SI, then press the EFB 1B D/G start ! , l pushbutton.
I i
! ANSWER: B.
Point Value: 1.0 Answer Time: 4.0 Mins. Part A.
! Static Sim Scenario Kos. 14E f' S&K No.
246426022250 246408022710 , K/A No.
000056A2.14 064000A3.09 i RO/SRO Impf.
4.6 /4.6 4.0 /4.0 / l Objective 052103F04 052531F05 l Reference 052103F, DG Sequencers . Rev. Date 2/3/93 ! Rev. Date 3/24/93 .; i .. . !
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- O O l i ! 052105C27001 Points: 1.00 Question Number: 6- '.[ i l-i l Based on static plant conditions, which of the following ! statements is correct concerning the main generator hydrogen '- seals? (Circle the correct response.)
l l A.
The seal oil backup pump should have already automati I cally started and be maintaining seal oil pressure at H2 pressure + 8 psig.
I j B.
The air side emergency DC seal oil pump should have I started and should be maintaining seal oil pressure at
L H2 Pressure 4 8 psig.
l C.
The H2 side seal oil pump will maintain seal oil pressare at H2 pressure + 8 psig.
D.
The seal oil backup pump will automatically start - when bearing oil pressure drops to 12 psig and maintain seal oil pressure at H2 pressure + B psig.
i l l ANSk'ER : D.
Point Value: 1.0 Answer Time: 4.0 Mins. Part A.
l_ Static Sim Scenario Nos. 14E
- .
S6K No.
245011022020 K/A No.
045CEN07 045010K4.23_ RO/SRO Impf.
2.6 /2.8 3.4 /3.6 / ! Objective 052105C27 l Reference 052105C, Main Genera er and Auxiliaries
Rev. Date 3/19/91 Rev. Date 2/4/93 Rev. Date 3/22/93 Rev. Date 3/24/93
O O - . ~ t i OS2201F06001 Points: 1.00 Question Nuniber.: 7'
Based on static plant conditions, DRPI indication can be l restored by: (Circle the correct response.)
A.
Selecting NORMAL on the DRPI power supply bus transfer '! switch.
l i B.
Selecting ALTERNATE on the DRPI power supply bus trans j fer switch.
! r i C.
Selecting EMERGENCY on the DRPI power supply bus trans c ' fer switch.
D.
Indication cannot be restored.
' ! ! ! ! ANSWER: A.
Point Value: 1.0 Answer Time: 3.0 Mins. Part A.
Static Sim Scenario Nos. 14E 24A S&K No.
241403000130 K/A No.
014000R406 014000A2.02
RO/SRO Impf.
3.4 /3.7 3.1 /3.6 / t Obj ec tive 052201r06 Reference 052201F DRPI Rev. Date 11/2/91 ! Rev. Date 2/5/93 ! Rev. Date 3/22/93 ] ! -l ! i ! f i i , I , ! h ! i k
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l t t ? ! h ._ . . i
_____ - -. _ - _ - _ - _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ - - O O - . 052521K02003 Points: 1.00 Question Number:
Radiation monitor R-14 has a high alarm and yet it indicates 10 cpm.
The reason for this is: (Circle the correct response.)
A., The alarm may be valid. With containment purge iso ) lated, the indication is reading normal pre-event readings.
B.
The alarm may be valid. The low reading is caused by the loss of B train power.
C.
The alarm is invalid.
The alarm failed on when the power supply auto shifted to A train.
D.
The alarm is invalid.
No other indication verifies an alarm could have occurred.
ANSWER: B.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos. 14E 56X No.
2473090200500 247256020150 K/A No.
072 GEN 13 072 GEN 13 RO/SRO Impf.
3.0 /3.1 3.0 /3.1 / Rev. Date 2/26/91 Rev. Date 3/22/93 , i Rev. Date 3/24/93 l- ,
__.
_ _ _ _. _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _. _. _ _ _ _ _ _ _. _ _ _ _ _ _ _ _. _. _. _. _ _ _. _ _ _. _. _ _ _ _. _.. _ _ _. _ _
I I . b) & e w 052530A13009 Points: 1.00 Question Number:
i Prior to the reactor trip and safety injection, the 1A. I P>, 1D, and 1E service water pumps were running.
During the
immediate operator action steps of EEP-0, Reactor Trip or Safety Injection, the operator finds only the IB SW pump running. Which O_NE of the following would have been t.he expected service water system response to the plant transient? (Circle the correct response.)
A.
The 1C SW pu:rp should have auto started because the spare pump selector switch is normally in the 1A position.
B.
The 1C SW pump should have auto started because the ESP sequencer was activated.
C.
The ID and 1E purrps trippcd because of the safety inj ection but are available to be started if needed.
D.
The 1A and 13 SW pumps should both be running because the spare pun p selector switch is normally in the 1C position.
- l ANSWER: D.
Point Value 1.0 Ans.,er Time: 3.0 Mins.
Static Sim Scenario Nos. 14E _ S6E No.
300903110215 R/A No.
00000/i202 P0/SRO Impf.
4.3 /4.6 / _/ Rev. Date 3/19/91 Rev Date 2/8/93 Rev Date 3/22/93 Rev Date 3/25/93 ! i
l l
. . _ _ O o - . . 052531F07016 Points: .1.00 Question Number: 10 , i l Concerning the 2C DG: (Circle the correct response.)
l ! A.
It should be secured due to lack of service water flow.
l l B.
It can be procedurally aligned to supply power to the 1G
4160V bus, allowing the BIG ESS sequencer to run.
l I C.
The BlJ and B2J LOSP sequencers should have aligned the i 2C diesel to Unit I and Unit 2.
i !i D.
It can be procedurally aligned to supply power to the IG l 4160V bus to allow nianually starting B train components.
{, i ) + i ANSk'ER : D.
Point Value: 1.0 Answer Time: 4.0 Mins.
l
S&K No.
246402000200 ~~~ ~~~ l Static Sim Scenario Nos. 27E ! ] K/A No.
064000A4.06 __ /__ l RO/SRO Impf.
3.9 /3.9 _/ i Revised 1/16/92 l ' Rev. Date 3/23/93 ' Rev. Date 3/24/93
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( -) AEL - v y 052531T09015 Points: 1.00 Question Number: 11 l
j Based on current static plant conditions, which of the - j following stateaents is correct? (Circle the correct . response.)
j i ' i A.
Opening the RCS PRZR aux spray valve HV-8145 will cause , l an RCS pressure reduction.
! , i B.
No n.eans of operator initiated RCS pressure reduction is J available at this time ! l C.
lA loop spray valve PCV-444C can not be used for RCS pressure redaction.
- l i
i
D.
Opening PRZR PCRV PCV-445A will cause an RCS pressure j reduction.
- l
i ANS'n'ER : D.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos. 14E ! S&K No.
240235020380 ] K/A No.
000009EA1.01
RO/SRO Impf.
4.a /4.3 ___ / / l Rev. Date 2/5/92
1
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v . I i ! 053002J15007 Points: 1.00 Question Number: 12 Based on current static plant conditions, state the MINIMUM notification / classification required: (Circle the correct response.)
A.
1 hour non-erergency report B.
NOUE C.
Alert D.
Site Area Drergency ANSVER: C.
Point Value' 1.0 Answer Time 3.0 Mins.
Static Sim Scenario Nos. 14E SLK No.
311934020536 K/A No.
194001A1.16 RO/SRO Impf.
3.1 /4.4 / /___ Rev Date 2/26/91 Rev. Date 1/9/92 Rev. Date 2/6/93 c
. _.. _ -. _... _. - _ _ _ _... _ - -. _._.._ _. _... _ _ _ _ _ __... __.. -. _.. _ __ 's E.
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j-052201G17001 Points: 1.00 Question Number: 13 ! a CAUTION: THIS QUESTION IS NOT RELATED TO THE STATIC SIMULA ! TOR CONDITIONS.
! j The plant !.s at 100% steady-state when turbine impulse .i
! f.. pressure channel 447 fails high.
If a manual reactor trip / i I turbine trip was initiated from this condition: (Circle'the ' L l correct response.)
! A.
The steam dumps would operate normally to lower Tavg to no-load conditions.
! B.
The impulse pressure channel failure that occurred would
prevent the steam dumps from arming.
j ' l i C.
The steam dumps would be armed but would not have a ! demand signal to lower Tavg.
! D.
The steam dumps would be - armed with a maximum demand signal causing all steam dumps to remain open until Tavg decreases to 543*F.
! ! ANSWER: A.
Point Value: 1.0 Answer Time: 4,0 Mins. Part A, Static Sim Scenario Nos.
~~~ S&K No.
244101000120 K/A No.
041020A408 RO/SRO Impf.
3.0 /3.1 ___ / / Obj ective 052201C17 Reference 052201G, Steam Dumps ! Rev. Date 11/12/91 !- Rev. Date 2/5/93 Rev. Date 3/24/93 ! i L
s ! '
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'03/31/93: ALABAMA POWER COMPANY EXAM GRADING SHEET EXAM NAME: A93C5WIS CLASS NAME: LRP-93 TOTA!. POINTS: 13 DATE GIVEN: 04/05/93 , STUDENT ID / NAME: / ! i QUESTION POINT POINTS j
VALUE MISSED
i 1 - 052102F10003 1.00 .) 2 - 052102G20007 1.00
3 - 052102H15007 1.00 I 4 - 052103D20008 1.00 5 - 052103F04003 1.00 i 6 - 052105C27001 1.00 j 7 - 052201F06001 1.00 i 8 - 052521K02003 1.00 9 - 052530A13009 1.00 10 - 052531F07016 1.00 j 11 - 052531F09015 1.00 l 12 - 053002J15007 1.00 13 - 052201G17001 1.00 i ! ! i'l i i ! ! ! , . - ? ' TOTAL POINTS MISSED: FINAL SCORE: t , b
! ! i ' . -. ---
e fa /cy 9J -J ee . b Atar % &* p af <. . RTYPE: K2.04 ! (Individual) j R -- RTYPE: K2,07 (KEY) - ! TRAINING DEPARTMENT EXAMINATION i r ' NAME(*RCVR): GROUP: i
- DATE: 04/06/93 EXAM NUMBER: B93C5W1R i
! EXAM TITLE: LRP-93 RO CY-5 WK-1 PART-B TOTAL POINTS: 27.00 i (*XREF) NRC
, ! INSTRUCTIONS ' . 1.
This is a 1.0 hour excuination.
! 2.
Point value for each question is indicated in the ques-tion header.
3.
Answer all questions:
[[] On a separate paper.
f (_]] On the answer sheet by circling or marking the cor-rect response or filling in the blanks.
!X) On the same page as the question.
If extra room is , a needed, use the reverse side of the previous page j or use extra paper.
> ) 4.
CHEATING OF ANY KIND IS STRICTLY FORBIDDEN. ANY INDI-
- '
VIDUAL CAUGHT CHEATING WILL AUTOMATICALLY FAIL THE " EXAMINATION AND DISCIPLINARY ACTION WILL BE TAKEN.
J ! 5.
ALL WORK DONE ON THIS EXAMINATION IS MY OWN.
TO MY y KNOWLEDGE, I HAVE NEITHER GIVEN NOR RECEIVED AID.
! FURTHERMORE, I WILL NOT DIVULGE THE CONTENTS OF THIS
, ' EXAMINATION TO ANYONE ELSE WHO MAY TAKE IT.
EXAMINEE'S SIGNATURE
! i.
- , ) 1{ / - ?
_ l EXAM GRADED BY: PREPARED BY:
i jkh V CRADING/ MATH REVIEW BY: APPROVED BY: Training Managerf l ' Supervisor / l
- INDEXING INFORMATION I
2/24/89 . I of 2
i l ! ! , .
_ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - ) . Ib A (STATIC SIMULATOR) AND PAR (OFEN REFERENCE)
EXAMINATION GUIDELINES The procedures, drawings, Tech Specs, and other material provided may be used as references while taking this examina-tion.
If this is a " Static Simulator-Part A exam, the simu lator may be used as a reference to gather data for answering the questions.
If this is an "Open Reference-Part B" exam, the simulator may be used as a reference but no simulator data should be used to answer the questions.
The following guidelines must be followed while using these references: - The exam may require all examinees to refer to the same control board indications.
Care must be taken to main-tain exam security and avoid any possibility of compro-mise - Do not leave pencil or pen marks in the reference mat - rials.
- Vhen you are finished with reference materials, ensuri that the materials are closed and/or returned to their original location.
Keep your exam materials together.
While at the control board or procedures, take your exam with you and keep your answers covered.
When ycu have finished and turned in your exam, you may leave the exam area and DO N0f discuss the exam with any one who ha: not taken it.
Do not forger to follow the basic rules oi exam taking: - Static Simulator-Part A questions are system based and apply to the static simulator conditions unless otherwise specified.
- Open Reference-Part B questions are procedure based and are not based on static sir.ulator conditions.
- Ansu r all questions independently of each other unless specified by the question.
- Answer all parts of each question; do not leave any answers blank - If a question is unclear or you are uncertain as to the int (nt -- ask ONLY the proctor for help prior to stating , any assumptions.
- Show all work and state any assumptions.
, l I i l 2 of 2 l , l
i L______--_-__________________-____-_- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - - - -
. _ _ _ _ ._ .. -. ._ -. = .. _, _ l O O - . ! l 052102H06012 Points: 1.00 Question Number:
Unit I has experienced a large break LOCA.
While performing , the required actions for a loss of reactor or secondary f coolant, the CST LEVEL LO-LO alarms are received with con i firmed level on L1-4132A & B. Which of the following is the j l . correct action to be taken for these conditions? (Circle the i
i correct response.)
l t i A.
Maintain AFJ flow from CST as long as cavitation of APW I pumps is not indicated.
B.
Secure all AFW pumps and proceed to FNP-i-FRP-H.l.
, C.
Shift AFV suction to SW per FNP-1-SOP-22.0.
l ! D.
Verify at least one intact SC narrow range level greater
than 6% and secure all APW pumps.
I
ANSWER: C.
Point Value: 1.0 Answer Time: 2.0 Mins. Part B.
!
Static Sim Scenario Nos.
' S&K No.
24561602250 t K/A No.
061000K4.01A !
R0/SRO Impf.
3.9 /4.2 ___ / / l Obj ective 052102H06 052530A13 j
Reference 052102H, AFU FNP-1-EEP-0.0 i Rev. Date 12/14/92 ! Rev. Date 1/18/93 f
. i . . I ! ! -i . I i % . i ! t + + r ! I t < ! < _ ___ .1
, ' ! - (~ ash % sur ! i - i,
1 052105C27006 Points: 1.00 Question Number:
i ! k'ith the Unit 1 main turbine on the turning gear, annuncia j
! i tors LF4 " AIR SIDE SEAL OIL PUMP OFF" and LF5 " SEAL OIL ! ' l PRESS LO" are energized.
Subsequent investigation deter ' ! mines the breaker EQ08 (air side seal oil pump supply I
breaker) has tripped on overload.
The DC air side emergency l ,
seal oil pump has started.
L'ha t action should be taken in - , response to this event? (Circle the correct response.)
A Nothing necds to be done since a backup HP seal source is established in this present condition.
i S.
Reduce hydrogen pressure within the generator to 2 psig j or less since no backup HP seal oil source exists.
{ C.
Start the AC bearing oil pump and reduce hydrogen
pressure within the generator to 2 psig or less.
_ . i
' D.
Start the seal oil backup pump and return the seal oil j system to normal as soon as possible ! l ANSk'ER : D.
Poirt alue ' 1.0 Answer Time: 4.0 Mins.
. j Static Sim Scenario Nos.
l ! SLK No.
245002000100 245006001000 245006001100
. i K/A No.
j j RO/SRO Impf.
/ /___ / l Rev Date 11/7/91 i Rev Date 1/1S/93 Res Date 3/24/93 .
1 l J j
J d Y $
! !
1 ' I l l I
i
$ l
,
$
i
,. ._ _ _.... _. _. _ _ _ _.. _ _ _ _.... _.. ~ _. _ _ _.. - _.. ._ .. _ _ _. _ _. _. _ _ _, - . O O o . i i ) ' i . OS2108A12003 Points: 1.00 Question Number:
. I l ' ! If instrument air header pressure decreases to zero psig, , g which one of the following sets of steps will open the 1A j '
atmospheric relief valve once the emergency air compressor is j running per.the procedure? (Circle the correct response.)
, i A.
Open N1P18V073A, then adjust the MCB M/A station to full i , open in MANUAL.
! ' t t B.
Open N1P18V074A, place the lisp L/R switch for the 1A
atmospheric relief to LOCAL and adjust pot to full open.
f ! C.
Place local handswitch 1-MS-HS-3371AB in the lower
equipment room in OPEN.
l i D.
Place local handswitch 1-MS-HS-3371AB in lower equipment room in CLOSE, override solenoid valve 1-MS-SV-3371AB open, then open N1P18V073A.
, t ! ANSk?ER : D.
Point Value: 1.0 Answer Time: 3.0 Mins.
_.
Static Sim Scenario Nos.
! S&K No.
253913025503 ) K/A No.
078000K302 078000K402 { RO/SRO Impf.
3.4 /3.6 3.2 /3.5 / nor Date 3/24/93 i
I i . I ! i
! . ! I i
7 .
l l . .. _ _ _,. - . . . . . - -. ... . ..
_.._ _ ... - - _ ._ _ _ _ -. -. ~. _ _ _ . . ... _ _ _ _ -.. _-. _ _ _... __w_ _ _. _. . - I I i O O- - - i " . 052201D00000 Points: 1.00 Question Number:
i ! f
Which ONE of the following describes the operation of the l i power range nuclear instrumentation channel current l , l 'I {, comparator? (Circle the correct response.)
~ A.
Compares total power from each channel to average power , and generates an alarm when any one is greater than 2% . ! of the average power l !
B.
Compares total power from the highest value channel to l l the lowest value of the other channel signals and - l l generates an alarm at 2% difference.
i i ! l C.
Compares each lower detector to the average of the lower l l.
detectors and each upper detector to the average of the l l upper detectors and generates an alarm at greater than ' 24 difference D.
Compares upper detector A normalized signal to lower detector B normalized signal and generates an alarm at greater.than 21 difference ANSVER: B.
Point Value: 1.0 Answer Time: 3.0 min.
Static Sim Scenario Nos.
S&K No.
~-~ K/A No.
015000K601 RO/SRO Impf.
2.9/3.2 / Reference 052201D, Excore Nuclear Instrumentation Rev. Date 3/24/93 - 1 , I e wa m .w%rese-w- - p---:e,w-.- _--a---g-w- -,x a .- iw .-
fl & . v w 052202E23004 Points: 1.00 Question Number:
While monitoring the Subcooled Margin Monitor, the OATC observes that the digital display on channel 1 is flashing.
Error code E9 is determined to be the error. Which of the following is the cause of the alarm? (Circle the correct response.)
A.
HJTC input 9 open or shorted B.
Pressurizer pressure low out of range C.
CETC input 9 shorted or open D.
Subcooled margin exceeding alarm setpoint ANSWER: B.
Point Value: 1.0 Answer Time: 3.0 Mins.
Static Sim Scenario Nos S&K No.
241705022050 241705023010 241706000200 K/A No.
017000AO.13G 000074EA1.16 017000KO.0SG RO/SRO 1rpf.
2.7 /2.9 4.4 /4.6 3.1 /3.2 ) l l
- O O
- .
052303G09010 Points: _1.00 Question Number:
A caution' tag should be used: (Circle the correct response.)
A.
k' hen special instructions are required due to an abnor mal condition B.
In place of procedure changes for long-term conditions C.
In place of red tag if no personnel injury or equipment damage can result D.
In place of a red tag for components in a work request that will need to be unisolated later during the , maintenance activity ! \\ l t ANSWER: A.
Point Value: 1.0 Answer Time: 3.0 Mins.
I Static Sim Scenario Nos.
l S&K No.
311903024000 l K/A No.
194001K102A RO/SRO Impf.
3.7 /4.1 / / Rev. Date 3/24/93 i f ! I i
, ! +.f
- .- -- c
__ __. . . . . _-. -._ _ . . - _ _ _ _ _ f O O - . ! If
052303H11020 Points: 1.00 Question Number:
i e ! s } - The only people, other than active RO or SRO license j ! holders, alleeed to manipulate any control that directly
! -. affects reactivity or power level are those who are: ! , ! . A.
in a training status to qualify for a reactor l or senior reactor operating license, IN AN ABNORMAL OR l EMERGENCY CONDITION ONLY ! ! B.
. non-licensed personnel specifically directed in an i approved surveillance test procedure or Work Request-l and under direct supervision of a licensed operator i C.
management or technical non-licensed persons pro-i , viding plant support functions in their field of ! expertise, with RO/SRO approval !
i D.
In a training status to qualify for a reactor or ! < senior reactor operating license and trained.to perform j the manipulation - and in the presence of and under i
a direct supervision of a licensed operator !
! ! i . '
ANSWER: D.
Point Value: 1.0 Answer Time: 4.0 Mins.
l
Static Sim Scenario Nos.
' S&K No.
! i K/A No.
GENA 1.03 [ d RO/SRO Impf.
2.5 /3.4 ___ / / j Rev. Date 1/18/93
Rev. Date 3/24/93
l' !
! , t I
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_,.. . - _. .. _
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] 052520A06006 Points: 1.00 Question Number:
i ' ]
i The plant is operating at 100% steady state power.
The i ' ! .1 following alarms are received: j . i f' MCB Annunciators - PRZR LVL DEV LO (HB2) i
VCT LVL HI-LD (DF3) Pressurizer level is falling rapidly.
The control room operator takes manual control of charging and raises !
1 .) charging flow to maximum. He secures letdown by closing i !
letdown orifice isolation valves and LCV-459 and LCV-460, -{ l I { verifies reactor makeup in automatic, and notes that pressur j ! . j iner level is continuing to fall. All charging pumps are L l started. A few minutes later, the annunciator alarm, PRZR ' e.
! LVL LO B/U HTRS OFF LTDN SEC (HA3), comes in.
What action must be taken next? (Circle the correct response.)
, i A.
Attempt to identify the location of the leakage and isolate it.
! B.
Manually initiate a reactor trip, then a safety injec tion; refer to EEP-0, Reactor Trip or Safety Injection.
i
C.
Manually initiate a safety injection, then verify ', !' reactor tripped; refer to EEP-0, Reactor Trip or Safety
l Injection.
j i j D.
Perform a CVCS flow balance; determine the RCS leak rate; determine if a rampdown to minimum load is required by Technical Specifications.
! !- }
! I ANSWER: B.
Point Value: 1.0 Answer Time: 4.0 Mins.
' i Static Sim Scenario Nos.
i S&K No.
240203001095 241103000135-K/A No.
002000A3.01A 000009EK3.28A j.
RO/SRO Impf.
3.7 /3.9 4.5 /4.5 /-
Rev-Date 2/26/91 [ Rev. Date 1/15/92 Rev, Date 1/18/93 , l Rev. Date 3/24/93 i.
i l e - I k l..
! . , d i .. - - , .-. . . - - -. . - - - - - -.. -. .
.. _ _ _. _.
.,. _ _ -. _ _ _ _. _ _ _. -. _. _. .. _... -.. - ~ _ _ _ _ _ _ _ _... _ _ _ _... _. . O O
~
? - i I , l 052520A11015 Points: 1.00 Question Number:
j !
I ' I Evaluate the following plant conditions to answer the ques j , i ,. U t tion below: -i
i i s
- 854 power for governor valve testing, power stable for ! ~ 15 minutes.
l - Charging flow 55 gpm in auto.
l l - Letdown flow 65 gpm.
j - A VCT auto makeup occurred 15 minutes ago.
! - VCT level is 35% and slowly dropping.
l - Seal injection 8 gpm/ pump.
- Seal return 3 gpm/ pump.
- Pressurizer pressure and level on program.
! - Rad monitors R2.7,11,12 all trending up.
.; ! - Rad monitors on plant vent stack trending up until mini l j purge was manually isolated, then they returned to-j normal values, j "-
Which one of the following actions would be procedurally l , t i required for existing plant conditions? (Circle the correct '!
i
l
response.)
! l A.
De te rmine leak rate using CVCS flow balance.
B.
Manually trip the reactor and go to EEP-0.- f ! ] C.
Start an additional charging pump.
D.
Determine leak rate using STP-9.
l i !~ ] ANSWER: A.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos.
l S&K No-. 240203001098
i K/A No.
004000AO.13G . RO/SRO Impf.
3.6 /3.5 ___ / / ! Rev. Date 3/21/91
i Rev. Date 3/24/93 l 1-i d
! - ! - . Y . .
l '
..: , " , i i . . . . . - - , ,.
. O O - 052520C05002 Points: 1.00 Question Number: 10 Unit 1 is presently at 28% power and ramping up at 2 MW/ min per UOP-1.2.
Annunicator KK1 "TURE COND VAC LO" alarm .] comes in.
The operator notes the following indications: l l - MCB condenser vacuum recorder (PR-4029) indicates 4.5 psia , - DEHC point CNDPl displays 4.6 psia (point detail dis plays 9.4 in Hga) i Based on the above information what should the plant operator j i do next? (Circle the correct response,) A.
Reduce turbine load until vacuum stabilizes B.
Have the turbine building 50 check SJAE and gland seal , steam operation i C.
Verify turbine trip D.
Verify auto start of MDAFW pumps due to both SGFPs-tripped ANSWER: C.
Point Value: 1.0 Answer Time: 3.0 Mins.
j Static Sim Scenario Nos.
j S&K No.
300903113210 300903113710 j K/A No.
001000AD.13G _ _ _ / ! i RO/SRO Impf.
3.7 /3.6 / R ev.. Date 10/8/91 i l i i l ! -l t
I -
l
. l'- I l
i ! -k i j
, , ! ! u- ! , -,, -,, -- -- -,,. .,,. - - ,.. - -,. - - - - - .. - - - - - - - - - -, -
I
i I JEb iur ' , 052520C08004 Points: 1.00 Question Number: 11 , I The plant is at 331 power and ramping up.
All systems are in ! automatic and controlling properly.
As a result of a DEH control system malfunction, the main turbine trips.
The OATC and UO acknowledge all im:rediate actions are completed.
Approximately 45 seconds after the turbine trip, the shift supervisor notes the generator output breaker indicating lights still indicate closed.
L' hat action is required?
(Cire'e the correct response.)
i
A.
Manually open the el breaker.
. B.
Manually open the generator output breakers.
, i C.
Place the reverse power switch to " BYPASS" and manually open the 41 breaker.
D.
Place the reverse pover switch to "EYPASS" and manually open the generator output breakers.
. ANSk'ER - D.
Point Value: 1.0 Answer Time: 3.0 Mins, Static Sim Scenario Nos.
S&E No.
244527020820 244547020123 K/A No.
045050A1.02A 045050A4.01A ' RO/SRO Impf.
3.3 /3.7 2.4 /2.3 / Rev, Date 1/18/93
Rev. Date 3/24/93 I i i I .
i . - .. . -
. -- .- - F.
O O <
052520D01001 Points: 1.00-Question Number. 12 j
1 ] At 20% reactor power while ramping up following a refueling I j outage, the IC reactor coolant pump (RCP) trips. The opera
i tor must perform whicip'of the following: (Circle the correct l , ., / s~
) response.)
j
- ^' d
, i U A.
Place the affected loop pressurizer spray valve in i i manual and close.
- j B.
Manually trip tlie reactor.
,! i . C.
Shut down the plant prior to attempting a restart of the
RCP.
. D.
Continue operation with an upper limit of 35% reactor j power to prevent an automatic reactor trip.
! I i l .) l
ANSk'ER : C.
Point Value: 1.0 Answer Time: 3.0 Mins.
j j Static Sim Scenario Nos.
l S&R No.
300707080240 300903113710 K/A No.
003000A0.13G 001000AO.13G ! RO/SRO Impf.
3.6 /3.7 3.7 /3.6 / Rev. Date 3/24/93 ! , ! ! i i I
4 i '
. ' ' l !
i . l I I i I I
t
5 l
l < a I i i ' I . ., , , ! , . ._ ......,_-,._,_._. _.___.__._--... . _, _ _ _, _. _. _ _ _.., _. . .. - - _. _ _ _,
l ^ o o - . i 052520108004 Points: 1.00 Question Number: 13' ! I I
Evaluate the following plant conditions that apply to the question that follows: ' I ) - The plant is at 100% steady-state power with all systems operating properly.
' I - C CCW pump is running through the C CCW Hx, supplying the miscellaneous header.
, - r - B CCW pump is out of service for maintenance.
l - A leak in the miscellaneous header causes level in the on-service train surge tank to drop to the Lo-Lo level ! alarm; all automatic actions occur.
. : - CCW surge tank level stops decreasing and stabilizes at = ! 15 inches.
Which of the following is a correct operator response? . ; e (Circle the correct response.)
j ! A.
Trip the reactor and RCPs; transfer the miscellaneous { header to the opposite train to allow immediate restart ing of the RCPs.
- B.
Cross-connect A train and B train'to allow continued l' plant operation while trying to isolate the leak.
O.
Trip the reactor and RCPs do not cross-connect CCW , " trains or transfer the miscellaneous header to the other l train, s i D.
Transfer the miscellaneous header to the opposite train l to allow continued operation while trying to isolate the l 1eak.
j . I r ! ANSWER: C.
Point Value: _ 1.0 Answer Time: 4.0 Mins.
j Static Sim Scenario Nos.
' ! S&K No.
300903113710 ' j K/A No.
001000A013G.
- j RO/SRO Impf.
/___ 3.7 /3.6 / - ' ! l .
,
< , - i l , ' i , y , - se e en-c =m-w-w ,--nc z-i-sr , . - n - m o - - -- - ~ -" e
.. _ _ _ _ . _. -
O - , 052520LO5006 Points: 1.00 Question Number: 14 t
l
The plant is operating with the RCS at mid-loop.
Which one i d ! l of the following is true with regards to the reactor vessel l
i ) tygon tube level indicator? (Circle the correct response.)
~ A.
It must be continuously monitored and checked for f proper opera +1on at least once every 12 hours.
t . . ! B.
It is only required to be monitored when RCS level is ! being lowered.
f '
C.
It is to be recorded once per hour and continuously I monitored any time level is being lowered.
' i D.
It is to be recorded every 4 hours and checked for
j proper operation every 24 hours unless any level changes
are being made.
!
i i l ANSWER: A.
Point Value: 1.0 Answer Time: 3.0 Mins.
l Static Sim scenario Nos.
S&K No.
i K/A No.
002000K4.02 002020SG1 i RO/SRO Impf.
3.5 /3.8 3.8 /3.9 /___ l Rev. Date 2/27/91
!' i l t j l
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' ! v ' l -
i 1.
A l- \\ - i ! ,
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f) & v w 052520L19016 Points 1.00 Question Number: 15 CTMT closure is being established per SOP-14.1 due to loss of both trains of RER 1A SG (E and C unavailable) is intact and has 72% wide range level.
lA SG has been established as a heat sink per AOP-12 and a secondary bleed and feed is in progress to reduce the RCS pressurination rate.
When the plant operator is directed to isolate containment, which of the following actions nust be taken? (Circle the correct response.)
A.
Open AFJ to SG 15 stop v1v AFJ-MOV-3350B if closed.
B.
Close SG blowdown line iso vlv ED-HV-7614A if open.
C.
Close /.FJ t o SG 1 A stop vi-AFJ-MOV-3350A if open.
. D.
Close M'; Fi t o SG 1/ stop vlv CFJ-MOV-32 3 2 A if open.
A';SWER : D.
Point Value' l.0 Answer Tiae: 4.0 Mins.
Static Sim Scenario Nos.
S&K No.
24 3501C'00100 K/A ';o. 035010K1.01 035010K1.09 RO/SRO 1rpi.
4.2 /4.5 3.8 /4.0 / Rev Datt 5/9/91 Rev Date 11/13/91 Rev Date 3/24/93 -- -
- O O
.
.i I 052520M04005 Points: 1.00 Question Number: 16 l i !
If the only running SCFP trips at 40% power, which of the j i following statements is correct concerning Rx trip? (Circle the correct response.)
{ ! A.
The reactor should be manually tripped to conserve S/G inventory for adequate secondary heat sink and decay heat removal.
B.
The reactor should not be manually tripped until the main turbine is tripped in order to minimize the RCS j cooldown.
' C.
Reactor power should be reduced to < 35%, then trip the main turbine.
l ! I D.
The main turbine should be tripped manually; the reactor j will not trip. automatically.
) i ANSWER: A.
Point Value: 1.0 Answer Time: 3.0 Mins. Part B.
i Static Sim Scenario-Nos. ___ S&K No.
240201022000 K/A No.. 000054K304 RO/SRO Impf.
4.4 /4.6 / / . Rev. Date 10/16/91 l Rev. Date 12/15/92 j Rev. Date 3/24/93 l J
- l i ! r l '
.. . _ _ _j
a ,O 052520505001 Points: 1.00 Question Number: 17 __.
An air line break has caused a high penetration room pressure.
k'hich one of the following methods should be used to reduce the pressure in the penetration room? (circle the correct response.)
A.
Allow pressure to slowl:, bleed off naturally.
B.
Slowly and carefully open penetration room doors.
C.
Align one train of the penetration room filtration system.
D.
Align both trains of the penetration room filtration , system.
. ItNS'.'ER : C.
Point Value 1.0 Answer Time 3.0 Mins. Part E.
Static Sim Scenario Nos.
S&s No.
250102000160 K/A No.
103000SG15 ' RO/SRO Impf.
3.8 /4.1 / / Rev. Date 12/15/92 r , s
' d J
- O O
.
052520Y08005 Points: 1.00 Question Number: 18 I i f L l The chemistry group reports cation conductivity of 38 pmho/cm l .i confirmed on latest SGBD sample due to-a condenser tube leak.
'I i
Why does the applicable procedure recommend proceeding to
! COLD SHUTDOWN? (Circle the correct response.)
f A.
Lower temperature results in lower corrosion rates.
! B.
SGBD flow increases proportionally as SG pressure-l* decreases during the cooldown, resulting in improved sodium removal, [ C.
To prevent component damage from carryover that would ! result from the foaming action of impurities in a steam } generator.
D.
To increase the recirculation ratio of the steam l " generators.
, ! ! ANSVER: A.
Point Value; 1.0 Answer Time: 3.0 Mins. Part B.
f l Static Sim Scenario Nos.
--- ,i S&K No.
240201002000 K/A No.
001000SG13 { RO/SRO Impf.
3.7 /3.6 ___ / / j Rev. Date 12/15/92
Rev. Date 1/18/93 i Rev. Date 3/24/93 , i .i
I-i i ! > I h ~I . i a i l
'I ! i 'I ' . -. . -,. -.. _ .. -. -, -
. _.. _ _ _ _ _. _. _ _. i - O O.
.
052521A01006-Points: 1.00 Question Number: 19 l .Which one of th. following situations requires that an emergency boration be performed? (Circle the correct ! response.)
) ! A.
CONTROL ROD BANK POSITION LO alarm is received.
i B.
An increase in source range counts while diluting to the l calculated estimated critical tod position.
l va ! C.
RCS Tavg falls below 521*F for 2 minutes following a i reactor trip, then recovers and stabilizes at 532*F.
!
- '
D.
32 hours after a reactor trip from 100% power, equili- _ l brium conditions, the SDM is determined to be 1.9% delta K/K.
- !
l l t I ANSWER: C.
Point Value: 1.0 Answer Time: 3.0 Mins.
' Static Sim Scenario Nos.
.i S&K No.
240410020295
K/A No.
000024EK3.01A 'l RO/SRO Impf.
4.1 /4.4 / / i Rev. Date 1/18/93 l Rev. Date 3/24/93 l j i
i t ! ! ! t l i ! t .! i ! i
.. l
' . i ,I i !
... -... ... _.. - - -... ... - -.. -..... -. - - -.. -. _ -.. ~. -.. _. , L.
O O , l e!; .! i i ' 052521H04004 Points: 1.00 Question Number: 20 i s i , A lowering refueling cavity level has resulted from damage to.
l
- .
I the refueling cavity seal ring. Because of the lowering l cavity level: (Circle the, correct response.)
A.
The RHR pump (s) should be. stopped immediately to ensure . pump cavitation does not occur.
, B.
Both RHR loops should be aligned to the RWST with j only 1 RHR pump running.
j , C.
One RHR loop should be in operation and aligned to the l , !L RCS; the other RHR loop should be aligned to fill the i refueling cavity from the RUST.
l , . D.
One RHR loop should be aligned to the RCS with its l ! respective pump secured.
The other RHR loop should be i j aligned to drain the refueling cavity to minimize { inventory loss to the containment floor.
i i t-l .
i
! ANSWER: C.
Point Value: 1.0 Answer Time: 4.0 Mins.
I Static Sim Scenario Nos.
S&R No.
240511020560 K/A No.
033000A2.03A RO/SRO Impf.
3.1 /3.5 / / Rev. Date 1/18/93 - i !
!
i ) J l
t ! [
l a ~f !
t J .I
r i t k i.
I i i
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'l
O O -
OS2521K03004 Points: 1.00 Question Number: 21 l l , If during refueling operations a valid high alarm is received j ! on a containment area radiation monitor, the control room j i ) operators: (Circle the correct response..) j A.
Do not have to announce an evacuation because the - containment evacuation alarm will sound.
, I B.
Do not have to announce an evacuation because HP cover i ! age is already on the scene.
-r C.
Should announce the affected area, but no evacuation is ' 1 t required because everyone in containment is wearing j dosimetry and will be investigating the cause while [ stowing fuel and verifying ventilation isolation.
, ! D.
Should announce the affected area and have the affected ! area evacuated.
l i i !
ANSWER: D.
Point Value: 1.0 Answer Time: 3.0 Mins.
Static Sim Scenario Nos.
l S&K No.
24709020330 t ' K/A No.
000061EA2.05A RO/SRO Impf.
3.5 /4.2 ___ / / Rev. Date 3/24/93
I I - j l
I i $ a' ! ] , - - - - - -, w ..., e & - - - - - -- - - ---*--- 'w---* - --
. .. - - . . - -. ... .. _ -. _, - -. .. . _ .. .- _ i . O O
- ! , ! 052531G09004 Points: 1.00 Question Number: 22 l i l
i A LOCA has occurred, resulting in actuation of the contain
ment spray system. Once the containment spray pumps are aligned for recirculation, they: (circle the correct ! . response.)
i , l A.
Should be secured as long as containment pressure is ! l less than 16 psig
B.
Should be secured as long as containment pressure is ) less than 16 psig and spray add tank level < 104.
' C.
Should remain operating for 2 hours regardless of I containment pressure to ensure addition of the entire ! contents of the spray add tank (spray add tank level i < 10%). ! l ' D.
Should remain operating for 2 hours regardless of I containment pressure to ensure proper mixing of the I spray add tank volume with the ECCS sump contents.
ANSk'ER : D.
Point Value: 1.0 Answer Time: 3.0 Mins.
Static Sim Scenario Nos.
S&K No.
300903110710 ) K/A No.
000011K312 RO/SRO Impf.
4.4 /4.6 / / j Rev. Date 3/22/91 i Rev. Date 3/24/93 { -I i ! , .. _ - _ ,,. - _. _.. _. _.., -
O & . v w i 052531LO6002 Points: 1.00 Question Number: 23 During performance of ESP-0.3, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (with , RVLIS), off-site power becones available during performance of step 7.
Which of the following actions should be taken by
the operator? (Circle the correct response.)
A.
Continue with procedure ESP-0.3.
B.
Go to ESP-0.2 step 1 to attempt to start a reactor coolant punp.
C.
Return to step 1 of ESP-0.3.
D.
Return to step 2 of ESP-0.3 to attempt to start a reactor coolant pu:rp. ANSWER: C.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos.
S&R No.
K/A No.
002000A2.03 RO/SRO Iepf.
4.1 /4.3 ___ / /
.. - _ . _. - - .- - _ -.. . - . _ _.. -. _. - --. I i . O O f ! 052533C04007 Points: 1.00 Question Number: 24 l
You have been directed to enter FRP-C.1, Response to i ! I Inadequate Core Cooling, due to a red condition on j l the critical safety function status tree.
RCS pressure is
'I approximately 1900 psig.
One RCP is in operation with 7 gpm i I seal injection flow.
Component cooling water (CCW) flow has i >
been lost to the containment.
In step 4 of FRP-C.1, it is _f f noted that no CCW is availabic to the RCPs.
Choose the - l l action below that is most appropriate for the control room staff to undertake. (Circle the correct response.)
! A.
Stop the running RCP when indications of seal failure occur.
i B.
Stop the running RCP as directed by AOP-9.0, Loss of l Component Cooling Vater, and then proceed with FRP-C.1.
j I C.
Continue with FRP-C.1 while attempting to reestablish j CCW flow-to the RCPs as personnel resources permit.
! .! D.
Continue with FRP-C.1 and complete actions to depres-
' surire the SGs to 100 psig, and then attempt to reestablish CCW flow to he RCPs in accordance with all applicable abnormal operating procedures.
i > ! l ANSWER: C.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos.
S&K No.
240311021187 240311021193 K/A No.
000074EKl.03 000074EK3,07 j RO/SRO 1mpf.
4.5 /4 9 4 0 /4.4 ___ / ! Rev. Date 11/9/91 j Rev. Date 1/18/93 j Rev. Date 3/24/93 i.!
-i .. r . ! .I l ! % $ , i- . -- - .. . - -
.. . - _. _ _ _ _ ~...... _ - - - _..._ _-.._._._._._.. ... _ _ _ _ _. _ _ _ _ _ _ _. _ L l l-O O - . . I I r I i l-052533F09009 Points: 1.00 Question _ Number: 25 l l ! '
l.- - i l-The plant is in an emergency condition, and the control' room ' operators are responding to a loss of secondary heat sink.
, i Attempts to restore feed flow to the SGs have been unsuc I cessful, so the operators are attempting to establish RCS j i bleed-and-feed.
The need to locally align a valve has
i delayed the establishment of an RCS feed path for a few l , l minutes. The STA suggests commencing the RCS bleed immedi
[ ! , l ately while waiting for the RCS feed path to be established, i l a Do you agree or disagree with the STA's recommendation? Why? j (Circle the correct response.)
A.
Agree. Under these conditions, the bleed-then-feed
method of RCS beat removal is an acceptable alternative ! ' to the feed-then-bleed method B.
Agree.
A procedure caution directs that RCS heat t removal by bleed-and-feed be established quickly.
. I i ! C.
Disagree. The correct course of action is to discontinue attempts to align an RCS feed path and continue attempts to establish AFW flow.
I D.
Disagree.
Opening a PORV before RCS feed is established could result in severe core uncovery.
, I
l i ANSWER: D.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos.
. L S&K No.
240606001900 l K/A No.
002000A204 000054K305
RO/SRO Impf.
4.3 /4.6 4.6 /4.7 /___ l .
4 ,
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I o a l l l ' i !
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i t t
}::
. -. . -... -. -.. . -. - . - - .. .
O O - . 052533K03007 Points: 1.00 Question Number: 26 )
Due to an excessive RCS cooldown following a main steam line break outside containment, the operating crew ! transitions to FRP-P.1, " Response to Imminent Pressurized ! Thermal Shock Condition." An RCS pressure reduction is
i in progress using a single pressurizer PORV.
While ! ! performing step 14, the RO observes that RCS subcooling is l
44' F.
Choose the action that should be implemented by the' i crew: (Circle the correct response.)
[ ! ) A.
Cool down the RCS to increase subcooling by dumping ! steam from the intact SG to obtain an RCS cooldown rate i ' of < 50*F in any 60 minute period.
B.
Start an additional charging pump to raise subcooling.
t C.
Terminate the depressurization of the RCS by closing the .l pressurizer PORV.
j l D.
Continue with the depressurization of the RCS l t
ii ANSWER: D.
Point Value: 1.0 Answer Time: 4.0 Mins.
[ Static Sim Scenario Nos.
___ l S&K No.
240206023860 ' K/A No.
194001A102 , _, / RO/SRO Impf.
4.1 /3.9 / , Rev. Date 3/20/91 i Rev. Date 11/7/91 [ Rev. Date 1/18/93 l Rev. Date 3/24/93 .! I ! -! ! I i L !
i
- .
! ' !
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- O O
. 052533M01001 Points: 1.00 Question Number: 27 , A LOCA has occurred.
While the operators are performing i l EEP-1, Loss or Reactor or Secondary Coolant, an orange priority is received on the containment status tree.
The I control room operators enter FRP-2.1, Response to High I i Containment Pressure.
They successfully complete all of'the-l actions of FRP-2.1 and return to EEP-1.
When they return to f EEP-1, they observe that the containment critical safety I i, function has not been restored.
The containment status tree i a t i I continues to display an orange priority. With these condi i l tions, the operators should: (Circle the correct response.)
k j A.
Continue with the action.< r EEP-1 with no need t( re-perform the steps of 1.1-Z-1.
< l B.
Implement FRP-Z.1 again, and repeat the actions to clear the orange priority.
C.
Return to the last step of FRP-Z.1 and hold until the j orange priority is cleared.
i l D.
Stay on the step-in-effect in EEP-1 until the emergency director determines if FRP-Z.1 should be performed again.
t I i ANSWER: A.
Point Value: 1.0 Answer Time: 2.0 Mins.
Static Sim Scenario Nos.
j S&K No.
311939021020 K/A No.
000069EK3.01A l RO/SRO Impf.
3.8 /4.2 / / .
. i ! ! L i-i ,
, i j
r' O ^ f ALABAMA POWER COMPANY'EP 03/31/93 - EXAM GRADING SHEET EXAM NAME: E93C5V1R CLASS NAME: IRP-93 TOTAL POINTS: 27 DATE GIVEN: 04/06/93 STUDENT ID / NAME: ** DRAFT ** / *************** DRAFT *************** QUESTION POINT POINTS
VALUE MISSED 1 - 052102H06012 1.00 2 - 052105C27006 1.00 3 - 052108A12003 1.00 4 - 052201D00000 1.00 5 - 052202E23004 1.00 6 - 052303G09010 1.00 7 - 052303H11020 1.00 8 - 052520A06006 1,00 9 - 052520A11015 1.00 10 - 052520C05002 1.00 11 - 052520C08004 1.00 12 - 052520D01001 1.00 13 - 052520I0S004 1.00 14 - 052520LO5006 1.00 15 - 052520L19016 1.00 16 - 052520M04005 1.00 17 - 052520N05001 1.00 18 - 052520Yo8005 1.00 19 - 052521A01006 1.00 20 - 052521H04004 1.00 j 21 - 052521M0300G 1.00 j 22 - 052531GO9004 1.00 23 - 052531LO6002 1.00 24 - 052533C04007 1.00 l 25 - 052533F09009 1.00 ~ 26 - 052533M03007 1.00 27 - 052533M01001 1.00 ) j ! ! ! j l
I TOTAL POINTS MISSED: FINAL SCORE:
1
1 i
I , .,
E 9.3-200 O O J a / pe
.. m a.
..
RTYPE: K2.04 i (Individual) !
RTYPE: K2.07 l (KEY) l ~ i TRAINING DEPARTMENT EXAMINATION j
! l '
NAME(*RCVR): GROUP: ! ' !
- DATE: 04/06/93 EXAM NUMBEP,: B93C5W1S j
I EXAM TITLE: LRP-93 SRO CY-5 VK-1 PART-B TOTAL POINTS: 27.00 (*XREF) NRC i INSTRUCTIONS 1.
This is a I.0 hour examination.
l alue for each question is indicated in the ques-l 2.
Poi
tio: oder.
' 3.
Answer aII questions: ,
[[] On a separate paper.
[ ! , I ",_ ] On the answer sheet by circling or marking the cor- - l ' rect response or filling in the blanks.
, i [X) On the same page as the question.
If extra room is ! needed, use the reverse side of the previous page ! or use extra paper.
f
CHEATING OF ANY KIND IS STRivTLY FORBIDDEN. ANY INDI-VIDUAL CAUGHT CHEATING WILL AUTOMATICALLY FAIL THE
EXAMINATION AND DISCIPLINARY ACTION WILL BE TAKEN.
! , 5.
ALL WORK DONE ON THIS EXAMINATION IS MY OWN.
TO MY j KNOWLEDGE, I HAVE NEITHER GIVEN NOR RECEIVED AID.
e FURTHERMORE, I WILL NOT DIVULGE THE CONTENTS OF THIS i EXAMINATION TO ANYONE ELSE WHO MAY TAKE IT.
I ! ! Dud 4INEE' S SIGNATURE ! ! ,' G r f [.
EXAM GRADED BY: PREPARED BY: ' ho i ph GRADING / MATH REVIEW BY: APPROVED BY: , TrainingManag/ { Supervisor - ,
- INDEXING INFORMATION
! 2/24/89
{ I of 2 ! I a
. . ' pad A (STATIC SIMULATOR) AND PAR (OPEN REFERENCE)- EXAMINATION GUIDELINES '! The procedures, drawings, Tech Specs, and other material
provided may be used as references while taking this examina-
tion.
If this is a " Static Simulator +Part A" exam, the simu l lator may be used as a reference to gather data for answering j the questions.
If this is an "Open Reference-Part B" exam, .j the simulator may be used as a reference but no simulator data should be used to answer the questions.
I The following guidelines must be followed while using-these references:
I - The exam may require all examinees to refer to the same l control board indications.
Care must be taken to main-tain exam security and avoid any possibility of compro-mise.
{ ! - Do not leave pencil or pen marks in the reference mate- ! rials.
! - When you are finished with reference materials, ensure ! that the materials are closed and/or returned to their ! original location.
Keep your exam materials together. While at the control
board or procedures, take your exam with you and keep your
answers covered.
When you have finished and turned in your exam, you may , leave the exam area and DO NOT discuss the exam with any one , who has not taken it.
, , Do not forget to follow the basic rules of exam taking: . ! - Static Simulator-Part A questions are system based and apply to the static simulator conditions unless otherwise , specified.
j > - Open Reference-Part B questions are procedure based and are ! not based on static simulator conditions.
'! ! - Answer all questions independently of each other unless i specified by the question.
{ ! - Answer all parts of each question; do not leave any answers j ' blank r
- If a question is unclear or you are uncertain as to the , ' intent -- ask ONLY the procter for help prior to stating any assumptions.
I' - Show all work and state any assumptions.
, i 2 of 2 l l
l
b t i f
. _. _.
_. _ _ _ _, _ _ _ _ _ _ _ o o - . .
052101K00000-Points: 1.00 Question Number:
. RHR pump 1A was started for testing at 0752 and stopped at 0800.
It was then restarted at 0835 and run until 0840 when it was stopped. Which ONE of the following is the earliest time that RHR pump 1A may be restarted? (Circle the correct .. response.)
{ ' l i A.
0840 e ' I t' i B.
0845 ' C.
0855
J
D.
0925 . I ] ANSER : D.
Point Value: 1.0 Answer Time: 3.0 Mins.
! l Static Sim Scenario Nos. ~~~ -- i S&K No.
'. K/A No.
005000G010 j RO/SRO Impf.
3.3 /3.5 ___ /___ / q Reference SOP-7.0, p.
J Rev. Date 3/24/93 l " . >
! .! . ! i I
I.
i l
1 L i , .
' , / l t- ! . I v
i n ' a
d .n . n -,,. . -.. - -..., - -
_ i ' , - b3 &w I \\ i 052106D08010 Points: 1.00 Question Number:
A HICH radiation alarm is received from the control room air intake monitor used to rnonitor the computer room outside air intake.
Which ONE of the following is ILOI an expected action G as a result of this radiation monitor alarm? (Circle your choice.)
A.
Utility exhaust fan suction dampers close.
B.
Filtration exhaust and recirculation fans start.
C.
TSC ventilation shifts into recirculation mode D.
Control room supply and return from computer room is isolated.
ItNSWER : B.
Point Value 1.0 Answer Time: 4.0 Mins.
Static Sirn Scenario I os.
S&K No.
_072000K104 K//t No.
RO/SRO Impf.
/ /_ / Reference ARP-3.1 - LD4 (R-35A HI Alarm) OPS-52106D, Radiation Monitoring Rev Date 3/24/93
F O O . . I ! ~! 052108A12003 Points: 1.00 Question Number:
l ! i ! If instrument air header pressure decreases to zero psig, _{ which one of the following sets of steps will open the lA atmospheric relief valve once the emergency air compressor is running per the procedure? (Circle the correct response.)
l l A.
Open N1P18V073A, then adjust the MCB M/A station to full e open in MANUAL.
j -! B.
Open N1P18V074A, place the HSP L/R switch for the 1A l atmospheric relief to LOCAL and adjust pot to full open.
! l C.
Place local handswitch 1-MS-HS-3371AB in the lower i equipment room in OPEN.
D.
Place local handswitch 1-MS-HS-3371AB in lower equipment
room in CLOSE, override solenoid valve 1-MS-SV-3371AB l open, then open N1P1BV073A.
! ANSWER: D.
Point Value: 1.0 Answer Time: 3.0 Mins.
Static Sim-Scenario Nos. ___ S&K No.
243913025503 K/A No.
078000K302 078000K402 l RO/SRO.1mpf.
3.4 /3.6 3.2 /3.5 / j Rev. Date 3/24/93 j ! I '!
! ! , i l . ,
- ! -
!
i ! . ! i l \\ ' l -
d i
4 --. . . .. . .. . . . - -
..m... ..,-....._...--,,. -m .
9 - 052201D00000 _ Points: 1.00 Question Number: 4-Which ONE of the following describes the operation of the power range nuclear instrumentation channel current comparator? (Circle the correct response.)
A.
Compares total power from each channel to average power and generates an alarm when any one is greater than 2% of the average power j l B.
Compares total power.from the highest value channel to j the lowest value of the other channel signals and ' generates an alarm at 2% difference ) ! C.
Compares each lower detector to the average of the lower ] detectors and each upper detector to the average of the ' upper detectors and generates an alarm at greater.than j 2% difference
i
D.
Compares upper detector A normalized signal.to lower j detector B normalized. signal and generates an alarm at l greater than 24 difference j
f -
ANSWER: B.
Point Value: 1.0 Answer Time: 3.0. min.
Static Sim Scenario Nos.
.] S&K No.
! K/A No.
015000K601 _ l RO/SRO Impf.
2.9/3.2 ___/ l Reference 052201D, Excore Nuclear Instrumentation l
Rev. Date 3/24/93 l l i I ' ! l l ' l )
! ! - 9 ! ! l ' ! s ! ! . I ' ! l - ti
l ,
n:
l .. o o - . 052202E23004 Points: 1.00 Question Number:
t .i While monitoring the Subcooled Margin Monitor, the OATC l i observes that the digital display on channel 1 is flashing.
l i' Error code E9 is determined to be the error. Which of the . l following is the cause of the alarm? (Circle the correct , i' response.)
i i A.
HJTC input 9 open or shorted I i B.
Pressurizer pressure low out of range l l ![ C.
CETC input 9 shorted or open -! 1-
D.
Subcooled margin exceeding alarm setpoint l l i ' ' j ANSWER: B.
Point Value: 1.0 Answer Time: 3.0 Mins.
y i Static Sim Scenario Nos.
j S&K No.
241705022050 241705023010 241706000200 K/A No.
017000AO.13G 000074 EA1.16 017000KO.08G RO/SRO Impf 2.7 /2,9 4.4 /4.6 3.1 /3.2 , ! i ! ! I b b ? ! ! t
4 !y i .
' ~ -l d
I i !.i i l - l ! ^ 'l j - I ,.. _,, . _ . .. >
, .. L ' O O > - 052302E02028 Points: 1.00 Question Number:
For each of the plant conditions listed below, which one is in violation of the shutdown margin requirements? All RCPs' are running in each case.
(Circle the correct response.)
l A.
The shutdown banks are withdrawn.
Shutdown margin ' calculation determines margin to be equal to 1.05% AM/K RCS Tave - 190*F.
B.
Shutdown margin is equal to 5.0% AK/K with reactor power at 2% and rods positioned at the RIL.
C.
Reactor power is 80% and control bank D rods are posi tioned at 140 steps.
D.
Reactor power is 100% and control bank D rods are positioned at 200 steps with axial flux difference reading -17% ANSWER: C.
Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos.
S&K No 300706060130 K/A No.
001000A0.11G RO/SRO Impf.
3.4 /3.9 / / Rev. Date 3/24/93 'lj
_._ _.. _._.._... _ _ _.... _ _ ~. - - _. -. - _ _ _ _. - _ _ .._..___..-___-_.._.._.._.y
e > . O O ~ -
! , o !
- l 052302E07013 Points:
1.00 Question Number:
! ! !
-l D ! L.
While operating at 100% power, with no other evolutions in j . j progress, the following indications occurred on DRPI panel
)- and MCB: ! s-f-. - General warning light above rod H-6 is flashing.
.l
6
- Rod bottom light for rod H-6 is lit..
' 3 urgent failure lights on DRPI are flashing.
Li - !
[ - 3 data A failure and 3 data B failure lights on DRPI are ! flashing.
j a i.
! - Tave and reactor power are stable, , ' j j - All other rods on DRPI indicate 228 steps with no j j: general warning alarms.
j j 'l Which of the following statements is correct? (Circle the j
i i i correct response.)
! i l A.
Rod H-6 has dropped; a mandatory LCO must be written on l [ movable control asoceblies.
! j.
l B.
Rod H-6 has dropped; and administrative LCO must be j ' ! written on movable control assemblies.
l.
! i-C.
Rod H-6 is stationary; a mandatory LCO must be written l l on DRPI.
! i , D.
Rod H-6 is stationary; an administrative LCO must be 'l , ! written on DRPI.
' l i . i-j ANSWER: C.
Point Value: 1., 0 Answer Time: 4.0 Mins.
. j Static Sim Scenario Nos, - i S&K No.
241404020030 l-K/A No:. 014000K4.05_ 014000AO.11G RO/SRO Impf.
3.1 /3.3 3.0 /3.9 i ___ /___ g i.
l ) I i !. i- < e ! s !-
l .i i ' l ! _ . . . ... .. . - l
. _ . - . 7 I . t . o-o
- i ! ! 052302MC6009 Points: 1.00-Question Number:
i
i Which of the following statements correctly describes proper status of containment building penetrations during refueling , ! operations? (Circle the correct response.)
[
A.
Both air lock doors can be open as long an an' individual j is stationed to shut one of the doors if conditions i require this action.
B.
Penetrations leading from the containment atmosphere to ! the outside atmosphere can be open as long as an oper able automatic isolation valve is in place.
l l C.
The equipment hatch is open but capable of being imme
diately shu ,
D.
The containment purge system is secured and all isola , tion valves shut.
j I ANSWER: D.
Point Value: 1.0 Answer Time: 3.0 Mins.
l Static Sim Scenario Nos-. ~ ! S&K No.
249704020110 > E/A No.
029000SGS 034000SG5 l RO/SRO Impf.
2.8 /3.4 .2.6 /3.5 /
Rev. Date 1/18/93
. .i ! ! ! I L I ! , ! ! ( I l . I ! '! ! l-i l !
] n;- o o - , I
052303G04001 Points: 1.00 Question Number:
i ,
During a unit refueling outage, a tag has been discovered j l missing on a clearance for a system that is currently being ] worked.
The shift supervisor should: (Circle the correct j i response.)
.l l
A.
Stop work on the system until the hold tag has been properly replaced with a new tag.
j 'i B.
Stop work on the system until the component is verified
in the required position, and an operator is stationed i' as a human red tag.
i C.
Stop work on the system until the missing tag is found, j and the effect on the system from the missing tag is j de te rmined..
i D.
Allow work to continue on the system as long as an J operator is stationed at the component as a human red j tag.
j .I i - I ANSWER: A.
Point Value: 1.0 Answer Time: 4.0 Mins.
! Static Sim Scenario Nos.
l S&K No.
311903024037 l K/A No.
194001Kl.02A ( ' RO/SRO Impf.
3.7 /4.1 /___ / Rev. Date 3/24/93 l
! ! > ! ! l i '. + ,
. ! i i f a
! , i i I ' l' ) !.
I l
'I-t - .. ._ - - - . . - -. -. - .
- _.. _ _. _.. _ _... _ _ _ _... _ _..... _ -. _. _.. _ -.. _... _ _. _ _. _... _. _. _ _ _ _ _ _. _. _ _ _ _.. _. _ _ _ _.. _ _.
' .
- .- i
- -
-052303H16027 Points: 1.00 Question Number: 10 ! l < ! ' i ! Who can authorize deviations from Technical Specifications ~ l-i- during an emergency condition if such actions are required to l immediately protect the safety and health of the public and ' insufficient time exists to obtain prior NRC approval? . I '- (Circle the correct response.)
, i A.
Reactor operator l l l ! B.
Any licensed SRO l C.
Emergency director l i D.
Reactor engineer i I l l ANSWER: C.
Point Value: 1.0 Answer Time: 2.0 Mins.
i ' Static Sim Scenario Nos. - - i S&K No.
j K/A No.
CENA1.03 i RO/SRO Impf.
2.5 /3.4 / / i > l t !
I i ! i l I L L i l I . . . . . . . . .. J
[l & i U y , 052520A11015 Points: 1.00 Question Number: 11 ? t Evaluate the following plant conditions to answer the ques tion below: - 854 power for governor valve testing, power stable for 15 minutes.
- Charging flow 55 gpm in auto.
- Letdown flow 65 gpm.
- A VCT auto makeup occurred 15 minutes ago.
- VCT level is 35% and slowly dropping.
- Seal inj ection 8 gpm/ pump.
- Seal return 3 gpm/ pump.
- Pressurizer pressure and level on program.
- Rad monitors R2.7,11,12 all trending up.
- Rad monitors on plant vent stack trending up until mini purge was manually isolated, then they returned to normal values Which one of the following actions would be procedurally required for existing plant conditions? (Circle the correct response.)
A.
Determine leak rate using CVCS flow balance B.
Manually trip the reactor and go to EEP-0.
, C.
Start an additional charging pump.
k D.
Determine leak rate using STP-9.
ANSWER: I'.. Point Value: 1.0 Answer Time: 4.0 Mins.
Static Sim Scenario Nos.
S&K No.
240203001098 , K/A No.
004000AO.13G l RO/SRO Impf.
3.6 /3.5 ___ / /___
, Rev. Date 3/21/91 Rev. Date 3/24/93 , !
i l
i l , ! i i !
_ . _ -, .- ! .O o ~ - s ! -1 ! 052520C05002 Points: 1.00-Question Number: 12 t i t i Unit 1 is presently at 28% power and ramping up at 2 MV/ min l per UDP-1.2.
Annunicator KK1 "TURB COND VAC LO" alarm !
comes in.
The operator notes the following indications: - MCB condenser vacuum recorder (FR-4029) indicates 4.5 psia { i - DEHC point CNDP1 displays 4.6 psia (point detail dis plays 9.4 in Hga) Based on the above information what should the plant operator , I do next? (Circle the correct response.)
-. i A.
Reduce turbine load until vacuum stabilizes l-i B.
Have the turbine building S0 check SJAE and gland seal I steam operation i ! C.
Verify turbine trip f i D.
Verify auto start of MDAFW pumps due to both SGFPs l tripped j i l f ANSWER: C.
Point Value: 1.0 Answer Time: 3.0 Mins.
Static Sim Scenario Nos.
S&K No.
300903113210- 300903113710 ! K/A No.
001000AO.13G -! RO/SRO Impf.
3.7 /3.6 / / { Rev. Date 10/8/91 .; , i ! ? t l !
! > > I ! ! - t I ! ! l l - - . - - .. . . , ...
._...._ _ _ _ _ _. _.. _._.__._ _.._. _ _ _ _ _ __ _ _ _ _. _. _.. _ __ _._._ _ _ _. _ _ _.~ _. _ _ _ _., [. o-o- - ! f.
052520C08004 Points: 1.00 Question Number: 13 1.
1' I i The plant is at 33% power and ramping up.
All systems are in ' - l-l automatic and controlling properly. As a result of a DEH l control system malfunction, the main turbine trips.
The OATC s j-and UO acknowledge all immediate actions are completed.
i a ' ' Approximately 45 seconds after the turbine trip, the shift j supervisor notes the generator output breaker indicating lights ! ' still indicate closed. What action is required?
' d (Circle the correct response.)
A.
Manually open the 41 breaker.
B.
Manually open the generator output breakers.
C.
Place the reverse power switch to " BYPASS" and manually ! open the 41 breaker.
I
D.
Place the reverse power switch to " BYPASS" and manually open the generator output breakers, i ANSWER: D.
Point Value: 1.0 Answer Time: 3.0 Mins.
l Static Sim Scenario Nos.
- 244547020123 S&K No.
244527020820 - l-K/A No.
045050A1.02A 045050A4.01A l RO/SRO Impf.
3.3 /3.7 2.4 /2.3 / Rev. Date 1/18/93 j , ! Rev. Date 3/24/93 l l
. I l.
, -
,
.'
I ) i ! \\ ! I . I
i ! t ! l i - , t, i i.,-------- I
. . . .- - _.. _.. _ _ _ . ! .O.
O ' - . 052520I08004-Points: 1.00 Question Number: 14 j
t Evaluate the following plant conditions that apply to the 'j ! question that follows: - The plant is at 100% steady-state power with all systems
' operating properly.
i - C CCW pump is running through the C CCW Hx, supplying the ! miscellaneous header, j ! - B CCW pump is out of service for maintenance.
i ! - A leak in the miscellaneous header causes level in the on-service train surge tank to drop to the Lo-Lo level j alarm; all automatic actions occur.
! ! - CCW surge tank level stops decreasing and stabilizes at = ! 15 inches.
!
' Which of the following is a corrent operator response? l .t (Circle the correct response.)
i . . A.
Trip the reactor and RCPs; transfer the miscellaneous I ! header to the opposite train to allow immediate restart ing of the-RCPs.
i i B.
Cross-connect A train and B train to allow continued
plant operation while trying to isolate the leak.
!
C.
Trip the reactor and RCPs; do not cross-connect CCW l trains or transfer the miscellaneous header to the other i
train.
D.
Transfer the miscellaneous header to the opposite train i . to allow continued operation while trying to isolate the leak.
l , ? ANSWER: C.
Point Value: 1.0 Answer Time: 4.0 Mins.
! Static Sim Scenario Nos.
- S&K No.
300903113710 , K/A No.
001000A013G ' RO/SRO Impf.
___ / 3.7 /5.6 / , !-i i
, ') D .! k
> . > t i ?-l
_ _. _ _ _ _ - -. - -. -. - -. -.. -... - -.. - - . - - - - ~. ~. _ -. - -. .. -., .-.a- _
l ~ O O -
< f 052520LO4005 Points: l'.00 Question Number: 15 I i
I RCS level is 123'3" and initial conditions are being estab j i i l lished to fill and vent the RCS per SOP 1.3.
It has been ! decided that an Mk'R must be completed on IB accumulator j..
discharge check valve Q1E21V032B (an SIS mid-loop check l [ valve) for seat leakage in excess of Tech Specs.
From the
i conditions listed below, choose the plant conditions that l must be established to perform the maintenance.
(Circle the
l correct response.)
l-A.
Verify open both PORVs and associated block valves.
I B.
Increase RCS level to > 126'6" . . , I l C.
Establish containment closure per SOP-14.1 and ensure l l hot leg injection available.
' D.
Verify one safety valve removed from the pressurizer.
l ! ' i ! I.
ANSWER: C.
Point Value: 1.0 Answer Time: 6.0 Mins.
I Static Sim Scenario Nos.
l i _ _ _ _ _ _ _ i S&K No.
K/A No.
002000Kl.08 - RO/SRO Impf.
4.5 /4.6 ___ / ,___ / i ' Rev Date 11/13/91 ' , . I i l - ! ! i i t ! I e !
i ! 'I i -
l r i l ! '
<
1 L
< ! I l r
i - i ,
i ~i i - l . .
bl & v w 052520M04005 Points: 1.00 Question Number: 16 If the only running SGTP trips at 40% power, which of the following statements is correct concerning Rx trip? (Circle the correct response.)
A.
The reactor should be manually tripped to conserve S/G inventory for adequate secondary heat sink and decay heat removal.
B.
The reactor should not be manually tripped until the main turbine is tripped in order to minimize the RCS cooldown.
C.
Reactor power should be reduced to < 351, then trip the main turbine D.
The main turbine should be tripped manually; the reactor will not trip automatically.
ANS'.'ER : A, Point Value: 1.0 Answer Time 3.0 Mins. Part B.
Static Sim Scenario Sos.
S&K No.
240201022000 K/A No.
000054K304 RO/SRO Impf.
4.4 /4.6 /___ ___ /___ Rev. Date 10/16/91 Rev Date 12/15/92 Rev Date 3/24/93
... . _ -. - _ __..-..... .- -. -.. - -... .-. - -.-. _-- ! O O l - ! t
052520N060ll Points: 1.00 Question Number: 17 i i i i I With Unit I at 100% power, a high penetration room pressure caused an isolation of the penetration room.
Annunciators ! BK1 and BK2, PENE RM TO ATMOS A(B) TRN AP HI-LO, are ! ,_ i l alarming. Annunciator ED3, AUX BLDC RM PRESS HI, 'l -
' has remained clear. With no operator action taken: (Circle the correct response.)
A.
Pressurizer level will decrease to 15%, at which time letdown isolates and backup. heaters turn off.
_ C B.
Pressurizer level control will not be affected.
j ! ) C.
Pressurizer pressure will increase until the PORVs lift, l
D Pressurizer pressure will increase until a high pressure j i reactor trip occurs, ! ! !
i . ANSWER: D.
Point Value: 1.0 Answer Time: 3.0 Mins.
'; ' ! Static Sim Scenario Nos.
' ! S&K No.
240402000730 240402001000 240403000190 l K/A No.
103000-A0.15G 103000-A0.15G 103000-A0.15C ! - RO/SRO Impf.
3.8 /4.1 /___ / ! i Rev. Date 1/18/93 l
i > , ! l
- -
l
h .l ' ! i -
1. l ' . l- < . j .- ,
b n - , . . - .-=c - .m -
'l l O O ' - ! i 052520R11033 Points: 1.00 Question Number: 18
-; i Given the following conditions on Unit 1: - Refueling operations are in progress, fuel movement is in
progress l - SR N-31 and 32 read 10 cps
- Both IR NIs off-scale LOW ! - PR N-41 is 00S, all appropriate bistables are tripped , - PR N-42, 43, and 44 read 0% -
> An apparent failure has just occurred on PR N-44, causing it to upscale to 25% power.
Which ONE of the following actions , is required? (Circle the correct response.)
{ A.
Immediately terminate all fuel movement in progress and , determine the boron concentration of the RCS at least ' once per 12 hours.
! ! B.
Notify I&C to investigate the power range instrument ' failure and continue with the refueling.
i C.
Ensure NR-45 recorder is selected to the intermediate ' range channels and continue with the refueling.
, ! k D.
Immediately terminate all fuel movement in progress and ! j emergency borate per AOP-27.0.
i-
,
ANSWER: A.
Point Value: 1.0 Answer Tin.e: 4.0 Mins.
i Static Sim Scenario Nos. ~ ~ i ' S&K No.
K/A No.
000032G0ll ! RO/SRO Impf.
3,1 /3.4 / /___ i A Reference 052201D, Excore N1 T.S.
3.9.2 ! l Rev. Date 3/24/93
t [ ' , l h
I ! i i f i , , l , , y--- _ - - - -.,
& a i W W i
j 052520T01002 Points: 1.00 Question Number: 19 ' I steady-state power, and the " SEISMIC The plant is at 100's I PANEL AIARM" (MK5) actuates.
The peak-shock annunciator has - several red lights lit and surveillance test data confirms the peak-shoch unnunciat or indication The event has been verified with off-site agencies.
L'h i ch o f the ac tions be' ow should be taken? (Circle the correct response.)
A.
Continue POWER OPERATIONS.
i B.
Shut down to liOT STANDBY, and notify the NRC.
C.
Continue POWER OPERATIONS, and notify the I;RC.
D, Continue POWER OPERAT]ONS; notify the NRC; and channel
calibrate all seismic i ns t ru:re nt s. l ANSWER: B.
Point Value: 1.0 Answe r Titre 3.0 Mins Static Sim Scenario ';os. SM: No.
245402000100 248406000200 - R/A No.
N/A 194001A1.02A , RO/SRO In:pf. / 4.1 /3.9 _/ Rev Date 2/22/92
I
y
a
. . . - - - -.. - -.. _.. - - - -. . _ , . s-l !
. .O O'
- . l ,
- 1-j.
052520YO3008 Points: 1.00 Question Number: 20
- -
, 4-p Unit 1 is operating at 100% power when the shift supervisor
is notified by the chemistry group that a possible condenser 4.-
tube' leak exists.
Steam generator blowdown parameters are as ,. [ follows:
- Cation conductivity 1.5 pmho/cm j - Sodium 60 ppb - Chloride 200 ppb
1 - Sulfate 100 ppb i k"hich of the following is the proper response to these plant ,
1-j conditions? (Circle the correct response.)
l ' .) A.
. Reduce power to f 354 within 100 hours, must commence , ' l within 24 hours.
B.
Reduce power to 600 MW, but power reduction may be i
. delayed for up to 7 days to meet load demands.
' I ! C.
Reduce power to 5 354 within 4 hours.
l ' D.
Commence shutdown at the maximum rate (be in HOT STANDBY l vithin 30 minutes).
! > i
ANSWER: C.
Point Value: 1.0 Answer Time: 4.0 Mins.
[ Static Sim Scenario Nos.
j-S&K No.
243806000150 ! l K/A No.
056000A2.05A 'r RO/SRO Impf.
2.1 /2.5 ___ / / ) Rev. Date 3/24/93 i'
! i 1 - !
I i
l t d I.
'
. i !
!.o l l i L rm. -.~. . . . . .'
h O O ~ 052521H04001 Points: 1.00 Question Number: 21 The fuel assembly in core location J-7 has just been lif ted . I into the manipulator crane mast during a core unload. The } l SRO in charge of refueling recognizes that refueling cavity l i level is dropping. He determines that. the rate of level j i decrease is not severe and that radiation levels will allow t further corrective actions.
It is reported that the leakage is resulting from the C loop hot leg nozzle dam and it cannot be stopped. Which of the following is F_01 an action which should be performed under those conditions, assuming cavity Icvel continues to drop? (Circle your choice.)
_; ! A.
Place the J-7 fuel assembly in the upender and lower the upender t o t he horizontal position.
B.
Close the fuel transfer tube gate valve.
C.
Direct chemistry to sample refueling cavity and SFP for activity.
D.
Verify only one RER pump running with its suction aligned to the RCS loops.
ANSWER: C.
Point Value: 1.0 Answer Time: 3.0 Mins.
Static Sim Scenario Nos.
S&K No.
243406000175 243406000200 243406000250 ! K/A No.
034000A2.01A 034000AO.09G 034000KO.01G , RO/SRO Impf.
3.6 /4.4 3.0 /3.0-2.3 /2-.9 l l Rev. Date 3/24/93 'l [ ! I I i ! !
.! l t .. i ! 'l
i $ i
, ,- . _. -. _ -,.. -. _... -,._ - _.. _ _..,. - -. _ - - - - - _. . _. - -, * -
.. ,. . - _., _ - - . .. - ! @ e
' - i 052521J01002 Points: 1.00 Question Number: 22 l l .l . ! ' The plant has been ramped down to 85% power in order to I perform required maintenance on the IC condensate pump.
The
GFFD alarm was received 15 minutes ago.
The GFFD indication .l
. has upscaled from the = 1000 cpm it has been over several j !
weeks to its current reading of 9.0 e cpm in the last 15 l . c I l minutes.
The power reduction is(commenced at the shift j r supervisor's discretion.
L'hich of the below should be the l ! resultant power level after completing the required actions ! l of the procedure? (Circle the correct response.)
! A.
754 i B.
60%
I C.
254
'
D.
No power reduction necessary f ! ANSk'ER : D.
Point Value: 1.0 Answer Time: 3.0 Mins.
i
Static Sim Scenario Nos.
- S&K No.
242010020252___ ___
K/A No.
000076AO.11G l RO/SRO Impf.
3.4 /3.6 ___ / ___ / i Rev. Date 2/22/92 , Rev Date 3/7/92 I " l Rev. Date 3/24/93 i f ,
,
J ! ! i {
i O f
! ll - ! b A
i ! [
! t t-i r . = , ,,,., . _ _.. -
., _._,. _ _. _.. _ .~._ _. _. _ -_. _ _. _ _ _... _. _ __. - . _. _ _ _. _ _ _ _ _. _. _ _... _ _ J .o o .
052531C09004 Points: 1.00 Question Number: 23 i )
A LOCA has occurred, resulting in actuation of the contain ~ l J [ ment spray system.
Once the containment spray pumps are i ! i aligned for recirculation, they: (Circle the correct l ~
i response.)
j i ! $ A.
Should be secured as long as containment pressure is j less than 16 psig j B.
Should be secured as long as containment pressure is - ' less than 16 psig and spray add tank level < 10%.
C.
Should remain operating for 2 hours regardless of l containment pressure to ensure addition of the entire ! contents of the spray add tank (spray rdd tank level
< 10%) , d ! D.
Should remain operating for 2 hours regardless of
d containment pressure to ensure proper mixing of the , !] spray add tank volume with the ECCS sump contents.
! + ) l .
ANSWER: D.
Point Value' 1.0 Answer Time: 3.0 Mins.
.' $ Static Sim Scenario Nos.
56K No.
300903110710 K/A No.
000011K312 t ,
RO/SRO Impf.
4.4 /4.6 / / l j Rev. Date 3/22/91 ! Rev. Date 3/24/93 i ' i i i.
> ! ! l- -I
! I i
!
- ..
< < r I ! L
, l ! ! .
, , ' .i h ~ a ! t ,, .,,.., -.,,..., _., _..., .. _.,.... ... ..... .. , _.. - I
. . _._.m , -. ~... _ =.. - _ _ _. - - _ - _. _. - _ _ _... _. - - _. _ _ _, ._..-.__.-..____._____y -
. .o o -
052531LO6002 Points: 1.00 Question Number: 24 , , i' During performance of ESP-0.3, Natural Circulation Cooldown i j with Allowance for Reactor Vessel Head Steam Voiding (with l RVLIS), off-site power becomes available during performance , ' of step 7.
Which of the following actions should be taken by i i the operator? (Circle the correct response.)
I f A.
Continue with procedure ESP-0.3.
l B.
Go to ESP-0.2 step I to attempt to start a reactor.
!
coolant pump.
i
C.
Return to step 1 of ESP-0.3.
l.
D.
Return to step 2 of ESP 0.3 to attempt to start a reactor coolant pump.
l ' , .l i l ANSWER: C.
Point Value: 1.0 Answer Time: '4.0 Mins.
Static Sim Scenario Nos.
- S&K No.
K/A No.
002000A2.03 RO/SRO Impf.
4.1 /4.3 /___ / l . !-
4
. _ _ _ - ,-.. - -. .-. .- .-. .. _, - -.. .- . ..... ! l O O i
- l .l > r 052533K03009 Points: 1.00 Question Nuniber: 25 l , . i t ' > I I
The plant has experienced a steam break, which caused an SI.
! .
i ] EEP-0, Rc actor Trip or Safety Injection, was exited, and
l q FRP-P.I, Response to Imminent Pressurized Thermal shock { i t j Condition, was entered on an orange path.
S1 flow was still l . i in progress with FI-943 indicating approximately 200 gpm.
f '
! ! The operators have reachef. step 3 of FRP F.1.
The STA reports ! ' i'
that the cooldown ha s r.oppi 1, containment pressure is now { 55 psig and increasing slowly, and RCPs are tripped. The i I
required action per FRP-P.1 at this time is to: (Circle the
$ i
correct response.)
l l <
i l A.
Proceed to step 10 of FRP-P.1.
l e - l-B.
Continue to the next step of FRP-P.l.
i a i i ! C.
Leave this procedure and go to FRP-Z.1.
l E l l D.
Leave this procedure and go to rediagnosis.
l ! ! , > , ANSWER: B Point Value: 1.0 Answer Time: 4.0 Mins.
l
/
f.Static Sim Scenario Nos.
--- ~~~ i ' S&K No.
240201021400 { y ! K/A no.
002000A0.10G
RO/SRO lapf.
3.4 /3.9 / / I ' l Rev, Date 3/22/91 l i Rev. Date 1/18/93 i l Rev. Date 3/24/93
..
! !
i ,
i i ! i , .I !
i !
l- ! i i
.l i.
$ ' , - - i .
. -. i O O " - , t l ' 052533M01001 Points: 1.00 Question Number: 26 t i f A LOCA has occurred. While the operators are' performing ! ! EEP-1. Loss or Reactor or Secondary Coolant, an orange .! I priority is received on the containment status tree.
The .j
control room operators enter FRP-Z.1, Response to High .' , containment Pressure. They successfully complete all of the l ! actions of FRP-Z 1 and return to EEP-1.
When they return to
i EEP-1, they observe that the containment critical safety - function has not been restored.
The containment status tree l continues to display an orange priority. With these condi f tions, the operators should: (Circle the correct response.)
l A.
Continue with the actions of EEP-1 with no need to i re-perform the steps of FRP-2-1.
I B.
Implement FRP-Z.1 again, and repeat the actions to clear i the orange priority.
! C.
Return to the last step of FRP-Z.1 and hold until the j orange priority is cleared.
[ ! D.
Stay on the step-in-effect in EEP-1 until the emergency ! director determines if FRP-Z.1 should be performed l again.
i ! , . l ANSWER: A.
Point Value: 1.0 Answer Time: 2.0 Mins.
! Static Sim Scenario Nos.
- ! S&K No.
311939021020 l K/A No.
000059EK3.01A [ RO/SRO Impi.
3.8 /4.2 /___ / ' .: ! , -
i i ! i i ! ! .' !
O @ - . 053002WO3004 Points: 1.00 Question Number: 27 Eight hours after a reactor trip /SI due to a LOCA, R-27A and B are indicating 100R/hr.
The core damage state is: (Circle the correct response.)
A.
No clad damage B.
0-20% clad damage C.
20-50% clad damage D.
50-100% clad damage i
I ANSWER: C.
Point Value: 1.0 Answer Time: 4.0 Mins.
-l Static Sim Scenario Nos.
f S&K No.
311934020832 l K/A No.
194001Al.16 - RO/SRO Impf.
3,1 /4.4 __ /_ / j Rev. Date 3/24/93 . I ! l ! . i ! ' ,
l l i ! I i ! !
i i ! ! ! i I i t i L
! - . o ALABAMAPOWERCOMPANYo 03/31/93 i i ! l EXAM GRADING SHEET -
! EXAM NAME: B93C5W1S CLASS NAME: LRP-93 l } TOTAL POINTS: 27 DATE GIVEN: 04/06/93 .j i STUDENT ID / NAME: ** DRAFT ** / *************** DRAFT *************** l } . I QUESTION POINT POINTS
VALUE MISSED l 'i 1 - 052101K00000 1.00
2 - 052106D08010 1.00 l 3 - 052108A12003 1.00 i 4 - 052201D00000 1.00 , 5 - 052202E23004 1.00 l 6 - 052302E02028 1.00 l 7 - 052302E07013 1.00 i 8 - 052302M06009 1.00 i 9 - 052303G04001 1.00 ! 10 - 052303H16027 1.00 l 11 - 052520A11015 1.00
12 - 052520C05002 1.00 ! 13 - 052520C08004 1.00 't 14 - 052520108004 1.00 ! 15 - 052520LO4005 1.00 i 16 - 052520M04005-1.00 l 17 - 052520N06011 1.00 i 18 - 052520R11033 1.00 l 19 - 052520T01002-1.00 ! 20 - 052520YO3008 1.00 ( 21 - 052521H04001 1.00 ) 22 - 052521J01002 1.00-l 23 - 052531G09004 1.00 l 24 - 052531LO6002 1.00
25 - 052533K03009 1,00 i 26 - 052533M01001 1-.00 l 27 - 053002WO3004 1.00 { ! ! l t ! > I ! !l ! TOTAL POINTS MISSED: FINAL SCORE: % I r ., l ! ! !-r ... _.., . - _ .,. _ - ,_., ! }}