IR 05000369/1997300
| ML20217R350 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/29/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20217R215 | List: |
| References | |
| 50-369-97-300, 50-370-97-300, NUDOCS 9709050085 | |
| Download: ML20217R350 (100) | |
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EXECUTIVE SUMMARY
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McGuire Nuclear Station, Units 1 & 2 NRC Examination Report Nos. 50 369/97 300,50-370/97 300 l
During the period July 28 31,1997, NRC examiners conducted an announced operator l
licensing initial examination in accordance with the guidance of Examiner Standards, NUREG 1021, Revision 7 Supplement 1, and as modified by the pilot program guidance of l
NRC Generic Letter 95 06, " Changes in the Operator Licensing Program". This examination l
implemented the operator licensing requirements of 10 CFR $55.41, $55.43, and $55.45.
l Qoerations l
Control room activities were observed during the examination validation week and
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examination administration week. The operators were found to be attentive and
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professional in their duties (Section 01.1).
Six Senior Reactor Operator (SRO) candidates and one Reactor Operator (RO)
candidate received written examinations and operating tests. The licensee administered the.wntien examination on July 28, and the NRC administered the operating tests July 28 31,1997 (Section 05.1),
in general, the examiners found that ths as-submitted examination was good. The-
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examiners identified the following areas as requiring staff attention or improvement:
facility review of the draft examination for technical accuracy, plausibility of the third incorrect distractor, and sample plan development (Section 05.2).
Six of seven candidates passed the examination. Three candidates were graded as a
marginal pass on the written examination and four candidates _were graded as a marginal pass on the operating test (Section 05.3).
Candidale Pass / Fall
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SRO'
RO Total Percent Pass
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86 %
Fall
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14 %
- The examiners identified a generic performance weakness in the area of McGuire
administrative requirements on the SRO written examination (Section 05.3).
The examiners identified one simulator fidelity discrepancy. The licensee's simulator
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support staff corrected the error prior to completion of the site visit (Section 05.4).-
The examiners concluded that the UFSAR wording discussed in section 08 was not
consistent with the current plant operating practices and procedures. These
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discrepancies are collectively identified as additional examples of URI 96-04-02.
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No violations or deviations were identified.
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9709050005 970829 Enclosure 1 PDR ADOCK 050 369-
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Bgoort Details Summarv of Plant Status During the period of the examinations the Unit 1 was at 100 percent power and Unit 2 was at 100 percent power.
l. Operations
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Conduct of Operations 01.1 Control Room Observation During validation and administration of the examination, the examiners observed the conduct of operations by currently licensed operators in the control room. The Reactor Operators (ROs) were attentive to the evolutions in progress. The Senior Reactor l
Operators (SROs) limited personnel access for official businass only, which contributed
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to a quiet, professional atmosphere.
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Operator Training and Qualifications 05.1 General Comments NRC examiners conducted regular, announced operator licensing initial examinations during the period July 28 31,1997. NRC examiners administered examinations developed by members of the McGuire training staff and a contractor, under the I
requirements of an NRC security agreement, in accordance with the guidelines of the f
Examiner Standards (ES), NUREG 1021, Revision 7, Supplement 1 as modified by the pilot program guidance of NRC Generic Letter 95-06, " Changes in the Operator Licensing Program". Six SRO and one RO license applicants received written examinations and operating tests.
05.2 E[gfxamination Activitieg This examination represented the licensee's second participation in the NRC's new process of the facility developing written examinations and operating tests for the NRC's operator licensing process. In general, the examiners found that the as.
submitted examination was good. Licensee response to examiner changes and comments was prompt and accurate. The operating tests and written examinations were validated during the week of July 14,1997.
The majority of comments on the draft written exam concerned format and style changes. Tne examiners identified the following areas as requiring staff attention or improvement: facility review of the draft examination for technical accuracy, p'ausibility of the third incorrert distractor, and sample plan development. The examiners identified several examples of questions that were technically inaccurate despite three or more independent reviews by staff members. The NRC expectation is that the as-submitted draft examination will not contain any technicalinaccuracies. While it is recognized that developing three good, plausible but incorrect distractors is difficult, a question submitted with one or more poor distractors will not be accepted.
Enclosure 1
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The as submitted sample plan met the minimum requirements of the Examiner Standards. However, the examiners later identified that the facility test developers had deleted from consideration any knowledge and ability (K/A) items that did not possess a facility learning objective, in the future, the substitution of K/As from the randomly generated sample plan will be considered only if that knowledge or ability is technically or physically inappropriate for the facility. Any substitution must be discussed and concurred with by the Chief Examiner.
The examiners considered the simulator tests to be very good. Only minor changes to enhance the test items of each scenario. The walkthrough examinations sets submitted by the licensee exam team contained Job Performance Measures (JPMs)
that met the guidelines of the ES and were of the appropriate level of difficulty. Many JPM follow up questions were rather simplistic and not very challenging. Improvement in this area would be warranted on future licensing examination submittals.
05.3 Examination Results and Related Findinas. Observations. and Conclusions Six of seven candidates passed the examination. Three candidates were graded as a marginal pass on the written examination and four candidates were graded as a marginal pass on the operating test. Detailed candidate performance comments have been transmitted under separato cover for management review and to allow appropriate candidate remediation.
During development of the written examination, one question was modified and included rearranging the order of the distractors and correct answer. However, this rearrangement was not properly reflected on the answer key. This oversight was identified by the licensee, during licensee grading of the written examination. A pen and ink change was made to the answer key to correct this error. No post.
examination comments were submitted by the licensee on the written test. Post-examination grading item analysis identified a generic weakness by the SRO
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candidates in the area of facility administrative requirements.
Poor candidate communications during the simulator test were noted as a weakness during the last NRC licensing examination (NRC Examination Report 50-369,50-370/06-300). The examiners did not note any significant improvement in this area. The candidates spoke quietly, did not always use 3-way communications, and occasionally made announcements or reports without addressing it to another specific crew member. The latter often resulted in missed commu,1l cations due to the other crew members being involved in separate conversations or concentrating on responding to the plant transient that was in progress. Additionally, periodic crew briefings on the status of plant conditions and progress in mitigating the casualty by the SRO were rare. The few briefings that were made did not provide useful information to the crew.
The examiners noted that Emergency Operating Procedure (EOP) implementation by the candidates was very slow. During one Steam Generator Tube Rupture (SGTR)
scenario, ruptured SG isolation was not accomplished before the power operated relief valve opened due to overfilling. In another scenario with a loss of coolant accident (LOCA), the candidates executed EOP E-0, Reactor Trip or Safety injection" (SI) so Enclosure 1
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slowly that the Refueling Water Storage Tank (RWST) automatically swapped to the emergency sump before a transition to EOP E-1, " Loss of Reactor or Secondary Coolani", was reached. In yet another scenario while transferring from hot leg to cold leg recirculction, the candidates questioned the validity of the valve manipulations listed in the EOP. One candidate pulled the plant drawings to confirm that the valves specified by the EOP would actually achieve the desired plant lineup. While self-checking is generally a good practice to implement during control board operations, stopping performance of a facility validated and approved EOP to confirm proper valve lineups on plant prints is not appropriate.
During the plant walkthrough examinations, two of the seven candidates began performance of one JPM on Unit 1 despite cues at the beginning of the task that the JPM was to be conducted on Unit 2. In both cases, the candidate self-identified his mistake prior to performing any manipulations on the wrong unit.
05.4 Simulator Fidelity During performance of an electrical system JPM on the simulator, one candidate verified the performance of auxiliary operator manipulations in the plant on the Operator Aid Computer (OAC). The candidate noted that solocted breakers had not been closed despite software commands to the contrary by the simulator operator, investigation by the simulator staff determined that the OAC software had been
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recently upgraded to match that of the actual plant. However, simula:or modeling of ceitain plant breakerc was not consistent with the level of detail provided by the new OAC software and thus when observed by the candidate showed indications l
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inconsistent with the verbal reports provided. The simulator support ctaff corrected this l
problem before the end of the test week and the examiner verified completion. The f
examiners did not note any other simulator fidelity discrepancies.
Of Miscellaneous Operations issues 08.1 Special Review of UFSAR Comm.'tments a.
Scop _q A recent discovery of a licensee operating its facility in a manner contrary to the Updated Final Safety Analysis Report (UFSAR) description highlighted the need for a special focused review that compares plant practices, procedures and/or parameters to the UFSAR descriptions. While performing the examinations discussed in this report, the examiners reviewed the appiicable portions of the UFSAR that Nated to the area that were being tested. The examiners intent was to verify that the UFSAR wording was consistent with the observed plant practices, procedures and/or parameters.
h Observations The examiners reviewed the sections describing the Emergency Core Cooling Systems (ECCS). The examiner noted that operators were required to close 1(2)NV-1508 and c
1(2)NV-151A (charging pump recirculation valves) following a reactor trip and safety injection if NC pressure was less than 1500 psig in accordance with Enclosure 1 of Enclosure 1
4 EOP E-0. The original design of the system had these valves automatically close on an SI signal; however, both units were licensed with a modification which removed the automatic closure signal to these two valves. Operator action was relied upon to poaltion the valves per the steps in the EOPs. The examiner identified the following discrepancies in the McGuire UFSAR:
Section 7.4.1.6.1 - Safety injection System Description, page 7-69. The last paragraph on the page describes the electrical interlocks of the system and incorrectly states that the valves on the miniflow line [1(2)NV 150 B and 1(2)NV-151A) automatically close (on an SI signal). Actual closure of these valves relies upon operator action at 1500 psig NC pressure.
Section 6.3.2.2.2 - ECCS System Operation, page 6-147. The last paragraph states," Operation of the Emergency Core Cooling System during injection mode is completely automatic." This is not completely accurate since operator action is necessary to reposition the recirculation line valves when proper plant conditions occur.
Section 6.3.2.16 - Motor Operated Valves and Controls, page 6-159. The table at the top of the page incorrectly lists valve 1NI-162A as a " Hot Leg Recirc Valve".
This is actually a " Cold Leg injection Valve",
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Conclusion l
The examiners concluded that the UFSAR wording in the sections discussed above was not consistent with the current plant operating practices and procedures. These
' discrepancies are collectively identified as additional examples of URI 96-04-02, which was identified in the Resident inspectors' earlier report.
V. Manaaement Meetiagg X1. Exit Meeting Summary _
At the conclusion of the site visit, the examiners met with representatives of the plant staff listed on the following page to discuss the results of the examinations. The licensee's management representatives provided no dissenting comments. No proprietary information l
was identified.
Enclosure 1
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i PARTIAL LIST OF PERSONS CONTACTED Licensee -
H. Barron, Vice President D. BaA'.cr, Shift Operations Manager A. Bhatnagar,- Superintendent of Operations -
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M. Cash, Compliance Manager
__ K. Crane; Compliance R. Cross, Compliance B. Dola1, Safety Assurance Manager l
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S. Het r ;,- Operations Training
' A. Lindsey, Operations Training Manager L. Massey, Operations R. Penson, Operations T. Rhodes, Operations C. Sawyer, Operations Training R. White, Training Manager NRC M. Sykes, Acting Senior Resident inspector M. Franovich, Resident inspector ITEMS OPENED, u.OSED, AND DISCUSSED Opened NONE Closed NONE'
Discussed URI 50-369,370/96-04-02 UFSAR Discrepancies Added examiner identified discrepancies from Sections 6.3.2.2.2, 6.3.2.16 & 7.4.1.6.1 of the UFSAR to this open URI.
(Section 08.1)
Enclosure 1
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LIST OF ACRONYMS USED CFR Code of Federal Regulations
'ECCS-Emergency Core Cooling System EOP Emergency Operating Procedure ES Examiner Standards (NUREG-1021)
JPM Job Performance Measure K/A.
Knowledge and Ability.
LOCA Loss of Coolant Accident NRC-Nuclear Regulatory Commission OAC.
. Operator Aid Computer.
RO Reactor Operator
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RWST Refueling Water Storage Tank SG Steam Generator SGTR
.Stearn Generator Tube Rupture SI Safety injection-
-SRO Senior Reactor Operator STA Shift Technical Advisor-TS-Technical Specifications UFSAR Updated Final Safety Analysis Report URI.
Unresolved item
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SIMULATION FACILITY REPORT
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Facility Licensee: McGuire Nuclear Station f
Facility Docket Nos.: 50 369 and 50-370
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l Operating Tests Administered on: July 28 - 31,1997
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This form is to be used only to report observations. These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of -
noncompliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information that may be used in future evaluations. No licensee action is required in response to these observations.
- While conducting the simulator portion of the operating tests, the following items were
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observed (if none, so state):
l IIEM DESCRIPTION
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NONE L
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NRC Official Use Only
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Nuclear Regulatory Commission Reactor Operator Licensing Examination This document is removed from Official Use Only category on date of examination NRC Official Use Only
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- ES-401 Site specific Written Examination Form ES-401-1 Cover Sheet U. S. NUCLEAR REGULATORY COMMISSION SITE-SPECIFIC WRITTEN EXAMINATION APPLICANT INFORMATION Name:
Region:
I /ilij/ Ill / IV / V Date:
Facility / Unit:
McGuiro License Level:
[RO] / SRO Reactor Type.
[W[/ CE / BW / GE INSTRUCTIONS
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Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires a final grade of at least 80 percent. Examination papers will be picked up 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the examination starts.
All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature RESULTS
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Examination Value 100 Points Applicant's Score Points Applicant's Grade Percent j
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ES-402 Policies and Guidelines Attachment 2 for Taking NRC Written Examinations 1.
Cheating on the examination will result in a denial of your application and could result in more severe penalties.
2.
After you complete the examination, sign the statement on the cover sheet indicating that
-_ths work is your own and you have not received or given assistance in completing the examination.
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To pass the examination, you must achieve a grade of 80 percent or greater.
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The point value for each question is indicated in parentheses after the question number.
5.
.There is a time limit of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for completing the examination.
6.
Use only black ink or dark pencil to ensure legible copies.
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Print your name in the blank provided on the examination cover sheet and the answer sheet.
8.
Mark your answers on the answer sheet provided and do not leave any question blank.
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If the intent of a question is unclear, as questions of the examiner only.
10.
Restroom trips are permitted, but only one applicant at a time will be allowed to leave.
Avold all contact with anyone outside the examination room to eliminate even the appearance or possibility of cheating.
11.
When you complete the examination, assemble a package including the examination questions, examination aids, and answer sheets and give it to the examiner or proctor.
Remember to sign the statement on the examination cover sheet.
12.
After you have turned in your examination, lehve the examination area as defined by the examiner.
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Questi:n 01 McGuire Nuclear Station RO Ex:m 1997
Bank Question: 2 Answer: C 1Pt(s)
Given the following conditions:
The Volume Control Tank (VCT) is at 42%.
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Automatic make-up is in progress.
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A leak develops in the common reference leg associated with the
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VCT level controller.
Assume no operator action.
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Which one (1) of the following describes the FIRST system response?
A.
NC Filter Outlet 3-way control valve begins modulating letdown flow.
B.
Indicated VCT level will decrease.
C.
Automatic makeup to the VCT will stop.
D.
NV pump suction switches to the FWST.
MISCINFO:
RO&SRO SOURCE:
RO 96 REFERENCES:
OP-MC-PS-NV page.18,19 LESSON:
OP-MC-PS-NV TASK:
- OBJECTIVES:
LPRO 3E,6 TIME:
KA:004010A211 (3.1/3.1)
DATE:
4//7/97 Confidential Ques _02e July 28,1997 a
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Question #2 McGuire Nuclear Station RO Exam 1997 Bank Question: 36 Answer: D 1 Pt(s)
After responding to a large break LOCA into containment, NS actuation logic fails to reset when required by procedure.
Which one (1) of the following describes the NS system response to an increase in containment pressure.
A.
NS pumps will start and discharge valves will open after containment pressure reaches.35 psig.
B.
NS pumps will start and discharge valves will open after containment pressure exceeds 0.8 psig.
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C.
NS pumps will start when containment pressure reaches.35 psig and
discharge valves will open when containment pressure exceeds 0.8 psig.
D.
Discharge valves will open when containment pressure exceeds.35 psig and NS pumps will start when containment pressure exceeds 0.8 psig.
MISCINFO:
RO ONLY SOURCE:
RO96 REFERENCES:
OP-MC-ECC-NS 3.2 page 31 LESSON:
OP-MC-ECC-NS TASK:
OBJECTIVE:
-LPRO 6 TIME:
K/A: 013000K405(3.8/4.2)
DATE:
4/7/97 Confidential QUES _36E July 28,1997 l
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Question #3 McGuire Nuclear Station RO Exam 1997 Bank Question: 38 Answer: B 1Pt(s)
A small break LOCA has occurred. Attempts to mitigate the event have been unsuccessful. Approximately one hour aller the break first occurred, the operators notice that the Subcooling Margin Monitor alarms.
Given the following conditions on the Inadequate Core Cooling Monitor plasma display:
1)
- Subcooling Margin indicates -35 degrees, trend is not changing 2)
T/C indicates 740 degrees, trend is increasing slowly 3)
Highest T, temperature indicates 535 degrees, trend is not changing 4)
Wide range loop pressure indicates 2420 psig, trend is not changing
/nd given the following plant conditions:
1)
Containment pressure steady at 2.5 psig t
2)
All NC pumps have been stopped for one hour Which one (1) of the following statements best describes the thermal hydraulic state of the core?
A.
Superheated steam at +35 degrees F -
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Superheated steam at +76 degrees F C.
Saturated steam D.
Subcooled steam at -35 degrees F MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
OP-MC-IC-ICM 1.4.E page 26-27; Steam Tables-Provided to students LESSON:
OP-MC-IC-ICM TASK:
OBJECTIVE:
LPRO10/LPSO10 TIME:
K/A: 017020K503 (3.7/4.1)
DATE:
11/29/95 Confidential QUES _38E July 28,1997
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Question #4 McGuire Nuclear Station RO Exam 1997 Bank Question: 49 Answer: C
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Which one (1) of the following abnormal transients will cause a C-5 rod stop signal to actuate during the plant transient from 100% power?
A.
Illgh failure of channel I turbine impulse pressure B.
liigh failure of channel 11 turbine impulse pressure C.
Low failure of channelI turbine impulse pressure D.
Low failure of channel 11 turbine impulse pressure MISClNFO:
RO&SRO SOURCE:
RO96 i
REFERENCES:
OP-MC-IC IPE page 25 OP-MC-TA-AT page 23,24 LESSON:
1) OP-MC-IC-IPE TASK:
2) OP-MC-TA AT OBJECTIVE:
1) LPRO 1.G / LSRO 1.G TIME:
2) LPRO 7 / LPSO 7 K/A: 014000K405 (3.1/3.3)
DATE:
4/7/97 Confidential QUES _49E July 28,1997
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Question #5 McGuire Nuclear Station RO Exam 1997 Bank Question: 57 Answer: D 1Pt(s)
Given the following conditions on Unit 1:
A loss of all AC power has occurred
The 1B DG started up in automatic mode and tripped
Upon arriving inside the Emergency Diesel Generator room, the Operators observe that two alarms are locked in. The operators then depress the local emergency stop reset push button to clear the alarms and restart the diesel generator.
Which one (1) of the following alarm pairs represent conditions that will nrevent a standby diesel generator from imilating a restart sequence in the automatic mode?
A.
Illgh lube oil temperature Low lube oil pressure B.
Fire shutdown Overspeed C.
Illgh Jacket water temperature Low lube oil pressure D.
Low crankcase vacuum 86D lockout relay MISCINFO:
RO&SRO-SOURCE:
RO96 REFERENCES:
OP-MC-DG-DG page 21,41 1.ESSON:
OP-MC-DG-DG TASK:
OBJECTIVE:
LPRO 5/6 TIME:
N/A:064000K402 (3.9/4.2)
DATE:
4/7/97 Confidential QUES _57E July 28,1997 m
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i Question #6 McGuire Nuclear Station RO Exam 1997 Bank Question: 63 Answer: D i
1 Pt(s)
Unit 1 is at 12% power with 4 NCPs running during a plant startup when an electrical transient occurs on the 6.9KV busses.
Given th: following transient conditions:
Electrical Bus Parameter TA TB TC TD Frequency (Hz)
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60 Voltage (Volts AC)
6800 6900 6800 6900 Offsite bus-line l A is supplying TA and TC Offsite bus-line IB is supplying TB and TD Which one (1) of the following sequences describes the immediate plant response to this transient with no operator action?
A.
No NCP pumps trip and the reactor does NOT trip l
B.
The 1 "A "and 1 "C" NCPs trip and the reactor trips
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C.
All four NCPs trip but the reactor does NOT trip D.
All four NCPs trip and the reactor trips MISCINFO:
RO&SRO SOURCE:
RO96 MOD REFERENCES:
OP-MC-PS-NCP pages 27,29 OP-MC-EL-EP pages 37,39 LESSON:
1. OP-MC-PS-NCP TASK:
2. OP-MC-EL-EP OBJECTIVE:
1. LPRO 8 TIME:
2. LPRO 24,25 K/A: 003000K304 (3.9/4.2)
DATE:
7/21/97 Confidential QUES _63E July 28,1997
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Question #7'
McGuire Nuclear Station RO Exam 1997 Bank Question: 64 Answer; B 1Pt(s)
Unit 1 is operating at 100% power.
Given the following conditions:
1)
A Inlal loss of instrument air (VI) occurs at 2:00 AM 2)
A reactor trip occurs on Lo-Lo S/G level at 2:05 AM Assuming no operator actions, what will be the sequence of events for the CA system?
A.
Motor driven and turbine driven CA pumps will start at 2:00 AM
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The turbine drive CA pump will start at 2:00 AM Motor driven CA pumps will start at 2:05 AM C.
Motor driven and turbine drive CA pumps will start at 2:05 AM D.
Turbine driven CA pump will NOT start.
Motor driven CA pumps will start at 2:05 AM MISCINFO:
RO ONLY SOURCE:
RO96 REFERENCES:
OP-MC-CF-CA pages 10,11 LESSON:
1) OP-MC-CF-CA TASK:
OBJECTIVE:
1) LPRO 5 TIME K/A:061000A207(3,4/3.5)
DATE:
4/7/97 Confidential.
QUES _64E July 28,1997 l
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Question #8 McGuire Nuclear Station RO Exam 1997 Bank Questlom 70
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1 Pt(s)
Which one of the following accurately describes how the combined error signal is
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developed by the reactor control system during rapid power transients?
A.
The power mismatch signallnitially dominates the temperature mismatch signal until after the rate of change of power has subsided.
B.
The temperature mismatch signalinitially dominates the power mismatch signal until after the rate of change of temperature has subsided.
C.
The difference in temperature (T,,,- T,,,) is amplified by the non-linear gain amplifier and compared to the difference in power (autioneered
high nuclear power-turbine power)in the summer unit. The greater signal is dominant.
D.
The power mismatch signalis delayed in a rate-lag unit derivative circuit so temperature mismatch is dominant until after the lag time has elapsed.
MISCINFO:
RO ONLY SOURCE:
RO96 REFERENCES:
OP-MC-IC-IRX 2.5 2.7 page 17-23 LESSON:
OP-MC-IC-IRX TASK:
OBJECTIVE:
LPRO 5,6,7 TIME:
K/A:001000A106 (4.1/4.4)
DATE:
4/7/97
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Question #9 McGuire Nuclear Station RO Exam 1997 Bank Question: 71 Answer: 0 1Pt(s)
While shilling to cold leg recire during a LOCA, N1 136B ( B N1 PUMP SUCTION FROM ND) will not open. What is a possible cause of this problem?
A.
ND-19A (A ND PUMP SUCT FROM FWST OR NC) must be closed.
H.
ND-58A (TRAIN A ND TO NV & NI PUMPS) must first be open.
C.
N1 184H (RH SUMP TO TRAIN H ND & NS) must first be open.
D.
ND-4B (H HD PUMP SUCT FROM FWST OR NC) must be closed.
I MISCINFO:
RO ONLY SOURCE:
RO96 REFERENCES:
OP MC-ECC-NI 1.5 C.3 page 14,15 i
MC-ECC N15 LESSON:
OP-MC-ECC-NI TASK:
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OBJECTIVE:
LPRO 9 TIME:
K/A:006000K409 (3.8/4.1)
DATE:
4/7/97
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Question #10 McGuire Nuclear Station RO Exam 1997 Bank Question: 78 Answer: C 1 Pt(s)
Unit 1 is operating at 100% power with the pressure control selector switch in the l-2 position.
Given the following conditions:
PORY NC-34 is tagged out ofservice
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Channel 2 pressurizer pressure fails high
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Assuming no operator action, what is the expected plant automatic response?
A.
Pressure will gradually decrease until a reactor trip occurs at 1945 psig and safety injection occurs at 1845 psig.
B.
Pressure will gradually increase up to 2335 psig then will cycle between 2335 psig and 2315 psig.
C.
Pressure will rapidly decrease until 2185 psig and then will cycle
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around 2185 psig.
D.
Pressure will not change.
MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
OP-MC-PS IPE page 35 LESSON:
OP-MC-PS-IPE TASK OBJECTIVE:
LPRO 12 TIME:
K/A: 000027EK303 (3.7/4.1)
DATE:
4/7/97 Confidential QUES _78E July 28,1997
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__-
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Question #11 McGuire Nuclear Station RO Exam 1997 Bank Question: 82 Answer: D
.
1Pt(s)
Unit 1 is recovering from a loss of 120 VAC instrument bus l EKVA due to the loss of the IEVIA static inverter. IEKVA has been reenergized from the alternate supply. After repairs to inverter 1EVIA are completed, the operator is directed to restore the 1EKVA bus to the normal line up.
Which one (1) of the fo.. wing actions is necessary to restore the electrical line up to a normal operating configuration per OP/0/A/6350/01 A aller tags are cleared.
A.
Manually transfer bus power from static inverter IEVIB back to static inverter IEVIA.
B.
Enable the automatic transfer of power from static inverter IEVIB back to IEVI A.
C.
Enable the automatic transfer of power from regulated power center iKRP back to static inverter IEVIA.
D.
Manually transfer power from regulated load center IKRP back to static inverter IEVI A.
MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
OP-MC-EL-EPL page 25,27 LESSON:
OP-MC-EL-EPL TASK:
OBJECTIVE:
LPRO 17 TIME:
K/A: 000057EK301(4.1/4/4)
DATE:
4/7/97 Confidential QUES _82E July 28,1997
.
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- - -
-
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Question #12 McGuire Nuclear Station RO Exam 1997 Bank Question: 84-Answer: D 1 (Pt(s)
Unit 1 is operating at 52% power with NCP Loop "A" Channel 1 flow instrument in test with the bistables tripped.
Given the following conditions:
120 VAC vital instrument bus EKVC was deenergized due to a bus fault
.
The reactor trip breakers have failed in the closed position due to improper
.
maintenance and retesting (unknown to the coerators)
Control switches are in the 1-2 position.
e Which one (1) of the following sequences accurately describes the plant response?
.
A.
The reactor protection system will NOT generate a trip signal with the loss of CII III loop flow instrument B.
The reactor protection system will NOT generate a trip signal because the plant is below P-8 C.
The reactor protection system will generate a trip signal under these conditions and an ATWS would occur.
D.
The reactor protection system will generate a trip signal under these conditions and a failure of RPS would occur.
MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
OP MC-PS-IPE pages 32,33 LESSON:
1) OP-MC-PS-IPE TASK:
2) OP-MC-EL-EPL
' OBJECTWE:
1) LPRO 1.F,3,4 TIME:
2) LPRO 6 -
K/A: 000057EA203(3.7/3.9)
DATE:
4/7/97 Confidential QUES._84E July 28,1997
_
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,
Question #13 McGuire Nuclear Station RO Exam 1997 Bank Question: 88 Answer: D 1 Pt(s)
Unit 1 is responding to a LOCA following an earthquake which has caused substantial damage throughout the station.
Given the following conditions:
1)
All sources of feedwater have been lost 2)
NCPs are secured 3)
The operators have implemented FR-C.1, " inadequate Core Cooling" 4)
Attempts to initiate SI have been unsuccessful 5)
S/G depressurization has not been successful in restoring adequate core cooling.
6)
Core exit T/Cs exceed 1200 'F 7)
NCP support requirements are NOT met What are the maior actions required by FR-C.1 under these conditions?
A.
Do NOT restart NCPs, open all vent paths to containment and depressurize NCS to inject cold leg accumulators.
B.
Restart NCPs and restore secondary heat sink in FR-H.1 before proceeding in FR-C.1.
C.
Do NOT restart NCPs and initiate feed and bleed of the NCS to restore core cooling.
D.
Restart NCPs and open all vent paths to containment.
MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
OP-MC-EP-FRC pages 23,43 FR C.1 step 21 page 15 LESSON:
OP-MC-EP-FRC TASK:
OBJECTIVE:
FR-C. obj 3 and FR-C.1 obj 15 TIME:
K/A:000074EK311(4.0/4.4)
DATE:
4/7/97 Confidential-QUES._88E July 28,1997 f
i
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Question #14 McGuire Nuclear Station RO Exam 1997 Bank Question: 92 Answer: D 1 Pt(s)
What is the expected temperature downstream of a leaking pressurizer PORY (very small leak rate) relative to T,, following a reactor trip.
A.
At pressurizer steam space temperature.
H.
Midway between pressurizer steam space temperature and T.,,.
'
C.
At no-load T.,,
D.
Below T REFERENCES PROVIDED
,
MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
OP-MC-TA Il pages 7,9,12 Steam Tables /Mollier Diagram - PROVIDED LESSON:
OP-MC-THF-STM TASK:
OILIECTIVE:
LPRO 6,7 TIME:
K/A:000008EK302(3.6/4.1)
DATE:
4/7/97 Confidential QUES _92E July 28,1997
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Question #15 McGuire Nuclear Station RO Exam 1997 Bank Question: 93 Answer: B 1Pt(s)
Unit I was operating at 100% when an electrical fault in the "D" NCP stator windings caused an electrical transient that tripped all 4 NCPs. The resulting thermal hydraulic transient caused a reactor trip and a small break LOCA. The operators have reached step 6 of E-1.
Given the following parameters at the indicated times:
Time Interval Parameter 2:00 2;Q3 2:06 1)
Pressurizer pressure (psig)
1305 1350 1395 2)
Core exit T/C temp ('F)
581 583 586 3)
T.,,('F)
575 576 577 4)
Tw (*F)
577 578 580
!
5)
T,a('F)
573 574 575 i
l If other requirements to terminate SI are satisfied, what is the earliest time that the operators have the necessary conditions to terminate Sl?
REFERENCES PROVIDED A.
Si flow may be terminated at 2:00 B.
Si flow may be terminated at 2:03 C.
SI flow may be terminated at 2:05 D.
SI flow may be not terminated MISCINFO:
RO&SRO SOURCE:
RO96 MOD REFERENCES:
Steam Tables-PROVIDED OP-MC-EP-INTRO page 53 EP/1/A/5000/E-1 step 6 page 6 PROVIDED LESSON:
OP-MC-EP-El TASK:
OBJECTIVE:
LPRO/LPSO 4,7.b TIME:
K/A:000009EK324 (4.1/4.6)
DATE:
4/7/97 Confidential QUES._93E July 28,1997 ___ -
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Question #16 McGuire Nuclear Station RO Exam 1997 Bank Question: 94 Answer: B 1Pt(s)
Unit 1 is recovering from a LOCA and the operators have reached step 14 of E-lat 2:00 AM. NC pumps have been tripped. Given the following indications at the following times:
Parameter 1 00 2$5 211D 1 15 1)
RVLIS (% LR lvl)
39
67 2)
NC pressure (psig)
280 285 290 295 3)
ND Flow 1000 1025 1075 1085 4)
Core exit T/Cs (*F)
690 702 695 685 5)
FWST level (inches)
159 149 139 129 6)
Containment Pressure (psig) 2.5 2.3 2.2 2.1 What is the earliest time that the operators can transition to ES-1,3, transfer to cold leg recirculation.
A.
2:00 AM
,
l B.
2:05 A M I
C.
2:10 AM D.
2:15 AM MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
EP/l'A/5000/E-1 page 2 OP MC-EP-El page 53,167 LESSON:
OP-MC-EP-El TASK:
OBJECTIVE:
E-1 Objective 7.f TIME:
K/A:000011EK315(4.3/4.4)
DATE:
4/7/97 Confidential QUES _94E July 28,1997
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,-
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Question #17 McGuire Nuclear Station RO Exam 1997 Bank Question: 97 Answer: A 1 Pt(s)
Unit 1 is in the process of preparing to conduct a plant cooldown in mode 3 in preptration for a refueling period. The OSM denied a request from maintenance to tag shut IND 15B (TRAIN B ND TO IlOT LEG ISOL) for valve stroke time testing.
What is the reason for his decision?
A.
This action would isolate the cross tie between the ND trains which is assumed to be open in the FSAR to ensure one ND pump can inject into all four NC loops.
B.
Although this would be permitted in mode 3, closing IND-ISB would cause one ND train to be inoperable and is prohibited in mode 4.
C.
IND-15B is interlocked with INI-136B (B NI PUMP SUCTION FROM j
ND) and this will defeat interlock and prevent IND-58A (TRAIN A ND
'
TO NV & NI PUMPS) from opening and establishing an alternate horation path from the NV system D.
IND-15B is interlocked with IND-58A and this will defeat interlock and prevent IND-58A from opening and establishing an alternate horation i
path from the NV system MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
OP-MC-PS-ND page 13,23 Tech Specs 3,4.1.2; 3.4.1. 3; 3.5.2 LESSON:
OP-MC-PS-ND TASK:
OBJECTIVE:
LPRO 3,7,9 TIME:
K/A:000025G004(2.6/3.8)
DATE:
4/7/97 Confidential Ques _97e July 28,1997
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Question #18 McGuire Nuclear Station RO Exam 1997 Bank Question: 101 Answer: C 1 Pt(s)
Unit I has a liquid radioactive waste release in progress from the Waste Monitoring Tank (WMT) through the RC system. The LWR document requires 3 RC pumps to be operating. All lineups and authorizations have been properly made in accordance with OP/0/B/6200/35 using the normal path.
Given the following initial conditions:
3 RC pumps running
1 EMF-49 correctly set for trip 1 and trip 2 activity limits
MRIRR = 75 GPM based on boron concentration
if one RC pump trips during the release, what automatic actions will occur to terminate the telease?
A.
WM-46 will close automatically (interlocked with pumps),
i B.
WM-46 will close automatically when EMF-44 reaches the trip 2
'
setpoint.
C.
WP-37 and WP-35 will close automatically (interlocked with pumps).
D.
WP-37 and WP-35 will close automatically when EMF-49 reaches the trip 1_ setpolnt.
,
MISCINFO:
RO&SRO-SOURCE:
RO96 i
REFERENCES:
OP-MC-WE RLR pages 19,21,23,29,33 LESSON:
OP-MC-WE-RLR TASK:
OBJECTIVE:
LPRO 4. 5 TIME:
K/A:000059EA205(3.6/3.9)
DATE:
4/7/97 Confidential QUES 101E July 28,1997
)
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Question #19 McGuire Nuclear Station RO Exam 1997 Bank Question: 102 Answer: A 1 Pt(s)
What automatic protective signal (s) will shut down both the Auxiliary Building unfiltered exhaust fans and sunoly fans?
A.
Blackout signal, or Eh1F-37 (trip 2)
H.
Eh1F-41 (trip 2)
C.
EMF-53 (trip 2)
D.
Aux Bld exhaust hi temperature alarm, or freeze protection thermostat MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
OP MC PSS-VA page 10,15 17 LESSON:
OP MC-PSS VA TASK:
!
OBJECTIVE:
LPRO!LPSO 3,4,8 TIME:
l K/A: 000060EA205(3.7/4.2)
DATE:
4/7/97
I Confidential QUES 102E July 28,1997
.
,.
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Question #20 McGuire Nuclear Station RO Exam 1997 Bank Question: 104 Answer: D 1 Pt(s)
Unit 1 is operating at 100% p6werin a 1-2 lineup.
Given the following indications:
. Letdown isolates All pressurizer heaters deenergize
.
Pressurizer levelincreases
.
Charging flow decreases e
What is the cause of these indications?
A.
Pressurizer level channel I falls high B.
Pressurizer level channel I falls low
C.
Pressurizer level channel 11 fails high D.
Pressurizer level channel II falls low MISCINFO:
RO&SRO SOURCE:
RO96 MOD REFERENCES:
OP-MC-TA-AT page 28,29,30 LESSON:
OP-MC-TA-AT TASK:
OBJECTIVE:
LPRO/LPSO 7 TIME:
K/A:000028EA101(3.8*/3.9*)
DATE:
4/7/97 Confidential QUES 104E July 28,1997
_J
._
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,
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Question #21 McGuire Nuclear Station RO Exam 1997 Bank Question: 106 Answer: B 1 Pt(s)
Unit 1 is operating at 100%. A T,,, channel fails high (full scale). Which one of the following selections describes the response of the reac'ar control system with rods in automatic?
A.
Temperature mismatch overrides power misnatch
'
Heactor Control System demands that rods drive OUT at 72 steps / min Control rod outward movement is blocked by C 5 rod stop 11.
Temperature mismatch overrides power mismatch Reactor Control System drives rods IN Rods step IN at 72 steps / min
,
C.
Power mismatch overrides temperature udsmatch
>
Reactor Control System drives rods OUT Rods step OUT at 48 steps / min until blocked by C 11 rod diop D.
Power mism.atch overrides temperature mismatch Reactor Control System drives rods IN Rods step IN at 72 steps / min MISCINFO:
RO&SRO SOURCE:
RO96
REFERENCES:
OP-MC IC lox page 39 LESSON:
OP MC-lC-IP.X TASK:
OBJECTIVE:
LPRO11 TIME:
K/A:0000001EK105(3.5/3.8)
DATE:
4/7/97
.
Confidential QUES 106F.
July 28,1997
_ *
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Question #22 McGuire Nuclear Station RO Exam 1997 Bank Question: 108 Answer: B 1Pt(s)
The immediate action steps of AP/1/A/S$00/14 Case 111 (Dropped Control Rod)
require operator actions associated with rod control and temperature restoration, i
Why are these actions required rather than simply allowing the reactor control system to respond in automatic to recover power?
A.
If the reactor is operating at or near 100% power, automatic rod withdrawal will cause the power mismatch signal to over compensate and a generate a rod stop.
H.
Allowing automatic rod withdrawal willincrease the severity of flux tilt and the core will be closer to DNHR limits.
C.
Allowing the rod control system to respond automatically causes a reduction in shutdown margin D.
If the control bank is close to the top of the core, the rods will drive out until they reach the full out position. This action could cause the RCC drive shaft to jam against the mechanical stop causing the rods to become stuck when temperature changes cause thermal expansion of the RCC.
MISCINFO:
RO ONLY SOURCE:
RO96 REFERENCES:
OP MC IC lRE page 35 LESSON:
OP-MC IC IRE TASK:
OBJECTIVE:
LPPO 16 TIME:
!
K/A:000003EK103(3.5/3.8)
DATE:
4/7/97
-
i i
i j _
Confidential QUES 108E July 28,1997
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,.
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Question #23 McGuire Nuclear Station RO Exam 1997 Bank Question' 120 Answen C
1Pt(s)
Given curve 8.5 of enclosure 4.3 to OP/1/A/6100/22, which one (1) of the following sets of pump operating parameters is indicative of pump cavitation conditions?
IEFEIGNCES PROVIDED A.
discharge pressure = 91 PSIG suction pressure =
7.7 PSIG pump flow rate = 3250 GPM 11.
dischurge pressure = 87 PSIG suction pressure =
8.6 PSIG pump flow rate = 3500 GPM C.
discharge pressure = 80 PSIG suction pressure =
7.7 PSIG pump flow rate =
3750 GPM D.
discharge pressure = 82 PSIG suction pressure = 12.0 PSIG pump flow rate = 4000 GPM MISCINFO:
RO&SRO SOURCE:
RO96 REFERENCES:
OP/1/A/6100/22 enci 4,3 curve 8.5 KC Pumps PROVIDED LESSON:
OP-MC THF FF TASK:
OBJECTIVE:
LPRO 6e TIME:
K/A 194001 A108(2.6/3.1)
DATE:
4/7/97 Confidential QUES 120F July 28,1997
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Question #24 McGuire Nuclear Station RO Exam 1997 l
Bank Question: 122 Answer: A l
l 1Pt(s)
After realigning the NV system for stanup, a valve located in an high radiation area
!
requires independent verification.
Given the following conditions:
General area radiation levels are 120 mrem /hr e
Estimated time to independently verify the position is 15 minutes
.
There are no known hot spots in the area e
There is no airborne activity in this room e
The room has no surface contamination areas
.
What are the ALARA requirements (if any) for waiving the independent verification of this valve?
A.
Independent verification may be walved because the exposure to the operatorexceeds Al. ARA guidelines.
H.
Independent verification is walved for all valves in high radiation areas until after shutdown.
C.
Independent verification may be walved after an evalue:lon by the NLO.
D.
Independent verification may not he waived for ALARA considerations under these conditions.
MISCINFO:
RO ONLY SOURCE:
RO96 MOD REFERENCES:
OMP 8-2 page 16-17
- LESSON:
OP MC ADM OMP TASK:
OBJECTIVE:
LPRO 16 TIME:
K/A:19400lK104(3,3/3.5)
DATE:
4/7/97 Confidential QUES 122E July 28,1997 -
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Question 025 McGuire Nuclear Station R9 Ex:m 1997 Bank Question: 126 Answer: A j
1 Pt(s)
Which ONE (1) of the following represents the expected leakoff flow rates associated with NORMAL OPERATION of the Reactor Coolant Pump (NCP) Seals?
- 1 Seal
- 2 Seal
- 3_ Scal A.
3 gpm 3 gph 100 cc/hr B.
6 gpm 3 gpm 300 cc/hr C.
6 gpm 3 gph 100 cc/hr D.
3gpm 3 gpm 300 cc/hr MISCINFO:
RO ONLY SOURCE:
Bank PSNCP021 REFERENCES:
OP MC PS NCP page 19,21 LESSON:
OP MC PS NCP TASK:
OHJECTIVE:
LPRO 12 TIME:
KA: 003000A109(2.8/2.8)
DATE:
S/21/97 Confidential QUES 126a July 28,1997
.
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Question 026 McGuire Nuclear Station R3 Ex:m 1997 Bank Question:127 Answer:A 1 Pt(s) Given the following plant conditions:
An inadvertent Safety injection occurred on Unit 1.
- Plant and operator response was appropriate and Safety injection Termination
l is being perfonned.
in accordance with Safety injection Tennination Procedure EP/l/A/5000/ES.
I e
1.1 Enclosure 3 Plant Realignment After S/l Termination; Containment
!
Ventilation Systems are being returned to normal per OP/1/A/6450/01 Enclosure 4.9, Realignment of Contairmient Ventilation Systems Following a Sl.
Which ONE (1) of the following Containment Ventilation System (VU,VL,VR,VT) components will require RESET / RETRANSFER 7 A.
Lower Containment Ventilation Units.
H.
YL and VU AIIU's with their associated Return Air Fans.
C.
VU Al!U's and their associated Return Air Fans.
D.
Steam Generator Hooster Fans.
MISCINFO:
RO ONLY SOURCE: Bank CNTVUL017 REFERENCES:
OP MC CNT VUL pages 27,35,37 LESSON:
OP MC CNT VUL TASK:
OBJECTIVE:
LPRO 6 TIME: -
KA: 022000K403 (3.6*/4.0*)
DATE:
5/21/97 Confidential QUES 127a July 28,1997-
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...
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Question 027 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 128 Answer: B 1 Pt(s)
Given the following plant conditions:
Unit 2 Reactor Startup in progress (withdrawing Control Bank A rods).
.
Pressurizer Level Master Controller fails to 100% output.
.
Pressurizer Level increases resulting in a PZR 111 LEVEL
ALERT condition on all three channels.
Which ONE (1) of the following describes the expected protective action (if any)?
A.
Reactor Trip H.
None C.
Letdown isolation D.
All Pressurizer heaters deenergized MISCINFO:
RO ONLY SOURCE:
Bank PSILE 020 REFERENCES:
OP MC PS ILE page 19 LESSON:
OP-MC-PS ILE TASK:
OBJECTIVE:
LPRO 9 TIME:
KA: 011000K513(3.2*/3.4)
DATE:
5/21/97
.
Confidential QUES 128a July 28,1997
.
.
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Question 028 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 129 Answer: B 1 Pt(s)
Given the following plant conditions:
Loose Parts hionitoring System is aligned for normal operation with the
.
following switch positions at the Alann Rack:
Alami Calibration Unit Selector Switch in the VIEW position.
- Alami hionitor Unit Selector Switch in the PRihiARY position.
- Alann Control Unit is ENABLED with both the Event Alami and
.
the System Failure Alami Switches in the NORhiAL position.
Alann inhibit Unit Selector Switch in the NORhiAL position.
- Backup Alann Unit has detected an EVENT which has not been
.
detected by the circuitry associated with the Transient Recorder.
Which ONE (1) of the following describes the LPMS indication for this event?
A.
"LPS1S Hackup Alarm" Annunciator Alarm on the hialn Control Board.
H.
Event Reset LED is illuminated on the Alarm Calibration Unit of the Alarm Rack.
C.
Backup LED is illuminated on the Alarm Monitor Unit of the Alarm Rack.
D.
" Loose Parts Panel Trouble" Annunciator Alarm on the Main Control Board without Transient Recorder operation.
MISCINFO:
RO ONLY SOURCE:
Bank !CEMD007 REFERENCES: -
OP-hic-IC-EMD page 35 LESSON:
OP htC-IC EhiD TASK:
OBJECTIVE:
LPRO 3 TIME:
KA:
016000A401(2.9*/2.8*) _
DATE:
5/21/97 Confidential QUES 129a July 28,1997
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2
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,.
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Question 029 McGuire Nuclear Station R3 Exam 1997
,
Bank Question: 130 Answer: B
'
1 Pt(s)
Which ONE (1) of the following describes how spray flow is first provided l
through the ND Spray llenders?
.
A.
Supplied by the NS Spray Pumps but can also be aligned to the ND Pumps after switchover to the containment sumps.
11.
Supplied by the ND Pumps after switchover to cold leg recirculation operation has been completed.
C.
Supplied by the ND pumps after switchover to hot leg recirculation. ND spray is not available in cold leg recirculation.
D.
Aligned so that ND Spray licader flow will begin whenever the NS pumps respond to a Containment Spray Actuation Signal MISCINFO:
RO ONLY SOURCE:
Bank ECCNS004 REFERENCES:
OP MC-ECC-NS pagel1,13 1.ESSON:
OP MC ECC NS TASK:
OBJECTIVE:
LPRO 8 TIME:
KA: 026000K401(4.2/4.3)
DATE:
5/22/97
'
Confidential QUES 130a July 28,1997
- Question 030 McGuire Nuclear Station R3 Ex:m 1997 Bank Question:131 Answer: O 1 Pt(s)
Given the following plant conditions:
Unit 1 in hiode 6.
- Reactor hiissile Shield removed.
l
" Norm Refuel" Selector Switch in the REFUEL position.
.
Fan hiode Selector Switch in the 100% position.
- 1EhiF-38 trip 2 alarm.
- l Which ONE (1) of the following describes the COhiPLETE l
system response by the Containment Purge System?
A. Supply Fan (lH) will STOP.
Supply Damper will CLOSE.
Exhaust Fan (IB) will STOP.
Exhaust Damper will CLOSE.
Upper Containment Inside Isolation Valves will CLOSE.
Upper Containment Outside Isolation Valves will CLOSE.
Lower Containment Inside Isolation Valves will CLOSE.
Lower Containment Outside Isolation Valves will CLOSE.
H. Supply Fans (I A & 1B) will STOP.
Exhaust Fan (l A & 1B) will STOP.
Upper Containment luside Isolation Valves will CLOSE.
Upper Containment Outside Isolation Valves will CLOSE.
C. Supply Fan (IB) will STOP.
Exhaust Fan (1B) will STOP.
Lower Containment Inside Isolation Valves will CLOSE.
Lower Containment Outside Isolation Valves will CLOSE.
D. Supply Fans (1 A & lH) will STOP.
Supply Damper will CLOSE.
Exhaust Fan (I A & lH) will STOP.
Exhaust Damper will CLOSE.
Upper Containment Inside Isolation Valves will CLOSE.
Upper Containment Outside Isolation Valves will CLOSE.
Lower Containment inside Isolation Valves will CLOSE.
Lower Containment Outside Isolation Valves will CLOSE.
MISCINFO:
RO ONLY SOURCE:
Bank CNTVP009hiOD Confidential
_.
QUES 131a July 28,1997
.
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_ _. -. _
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Question 030 McGuire Nuclear Station RD Ex:m 1997 l
REFERENCES:
OP MC-CNT VP LESSON:
OP MC-CNT VP TASK:
OBJECTIVE:
LPRO 3 TIME:
KA: 029000A301(3.8/4.0)
DATE:
S/22/97 i
Confidential QUES 131a July 28,1997-
.
Question 031 McGuire Nuclear Station R3 Exam 1997 Bank Question: 134 Answer: D 1 Pt(s)
Unit 2 is operating at 55% rated thennal power with all systems in normal alignment for this condition. Given the following events:
T.,, = 574'F
A Turbine Trip occurs due to low condenser vacuum e
A Reactor Trip occurs due to the Turbine Trip
.
Which ONE (1) of the following statements explains the EXPECTED i
" INITIAL" RESPONSE of the Steam Dump System?
A.
Atmospheric Dump Valves will TRIP OPEN and discharge to
.
the atmosphere.
B.
llanks 3 and 4 will TRIP OPEN while Hanks 1 and 2 will modulate to control T,,, within 3'F of Tu,e C.
Bank I will receive a TRIP OPEN signal but wili he HLOCKED from discharging to the Condenser, and Bank 2 will be modulating with discharge to the atmosphere.
D.
Condeuser Dump Valves will receive a TRIP OPEN signal but will be blocked from discharging to the Condenser, hilSCINFO:
RO&SRO SOURCE:
Bank SThilDE14 REFERENCES:
OP-hic-SThi IDE page 25 LESSON:
OP-hic-SThi IDE TASK:
OBJECTIVE:
LPRO 9 TIhlE:
KA:041020K603(2.7/2.9)
DATE:
5/22/97 Confidential QUES 134a
_ July 28,1997
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Question 032 McGuire Nuclear Station R3 Ex:m 1997 i
Bank Question: 135 Answer: A i
1Pt(s)
Which ONE (1) of the following statements best describe the operation of the Lill Coil Disconnect Switches?
A.
The switches are in the circuit for the lift coil multiplexing thyristors. When the switch is open, the rod cannot be stepped.
B.
The switches are in the circuit for the slave cyclers. When the switch is closed, the rod bank cannot he stepped.
C.
The switches are in the circuit for the lift coll multiplexlnit thyristors. When the switch is open, the rod bank cannot he stepped.
i D.
The switches are ir. the circuit for the slave cyclers. When the switch is open, ti.e rod cannot be stepped.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP MC IC-IRE pages 15,61 LESSON:-
OP MC-1C IRE TASK:
OBJECTIVE:
LPRO 8 TIME:
KA: 000005EK202(2.5/2.6)
DATE:
5/22/97 i
Confidential QUES 135a July 28,1997
.
y
~
,n, a-
-, - - +
--r
_
_.
_
_
.__
. _ _ _ _. -
_
_ - _ _ _ _ _ _ _ _ _ _ - _ _.
.
.
,.
.
Question 033 McGuire Nuclear Stai; ion R3 Ex:m 1997
Bank Question: 136 Answer: B 1 Its)
Given the following plant conditions:
Increasing NCP Stator Winding temperature
liigh NCP Motor Amps.
e Which ONE (1) of the following (if any) is the applicable CASE for implementation, associated with AP/1/A/5500/08, Malfunction of NC Pump Procedure?
A. NC Pump Seal or Pump Lower Bearing Malfunction.
i B. NC Pump Motor or Motor Bearing Malfunction.
C. Excessive Vibration D. The above symptoms DO NOT meet the entry conditions for the NCP Malfunction Abnormal Procedure MISCINFO:
RO ONLY SOURCE:
Bank PSNCP026 REFERENCES:
OP MC PS NCP page 45 LESSON:
OP MC PS NCP TASK:
- OBJECTIVE:
LPRO 16 TIME:
KA: 00001 SEA 208(3.4/3.5)
DATE:
5/22/97 Confidential QUES 136a July 28,1997 E
.
.
.
. _,..
. _.
_ _ - -
________ ____ ___ _-___ - - - -
-
.
.
.
Question 034 McGuire Nuclear Station R'S Ex:m 1997 Bank Question: 137 Answer: B 1Pt(s)
Unit I refueling is in progress.
Given the following plant conditions:
1 Eh1F.39, Containment Gas hionitor "lii Rad" alarm.
e I EhiF-40, Containment lodine hionitor "lii Rad" alarm.
e IEhtF 16, Containment Refueling Bridge hionitor alarm.
e l
Which ONE (1) of the following Abnomial Operating Procedures should be implemented?
l A. AP-18,liigh Activity in Reactor Coolant.
H. AP 25, Spent Fuel Damage.
C. AP-40, Loss of Refueling Canal Level.
D. AP-41. Loss of Spent Fuel Pool Cooling or Level MISCINFO:
RO&SRO SOURCE:
Bank FilFC011 REFERENCES:
OP htC FH FC page 21,23,25,27 LESSON:
OP-h1C-Fil FC TASK:
OH.IECTIVE:
LPRO 6 TIME:
KA: 000036ER301(3.1/3.7)
DATE:
5/23/97 Confidential QUES 137a July 28,1997
_
-___
. _ _ _ _..
_ _. _ _ _ _ _ _._ _.. _ _ _
____
__
,
.
.
'
Question 035 McGuire Nuclear Station R3 Exam 1997 Bank Question: 138 Answer: D i
"
1Pt(s)
A KC system valve is listed on a valve checklist for full system valve alignment reverification following an outage. The following conditions
,
exist:
The control room has indication of flow through the valve.
.
The required valve position valve for the reverification is OPEN.
- Which ONE (1) of the following statements is correct in accordance with OhtP 417 A.
Rucrification may be walved by the OSM because there is reasonable assurance that the valve is open.
H.
Reverification may be walved by the OSh1 if access to the valve would result in personnel receiving an estimated dose of to mrem.
C.
Reverification may be walved by a licensed Operations Supervisor if the valve is in a liigh Radiation Area.
D.
Reverification may not be waived because the observation of flow through the valve is not a suiticient condition for a walver.
511SCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OPhi 4-1 section 10,4 LESSON:
OP-hic-ADhi-OP TASK:
OBJECTIVE:
LPRO 23 Tin 1E:
KA:194001K101 (3.6/3.7)
DATE:
5/23/97 Confidential
_
QUES 138a July 28,1997
-
c-gi
-
---a-rm--
- -
i-ewi--'-----w
-<-
r-r'mmr---
---m-
-- -
-
.
-
'
'
Question 036 McGuire Nuclear Station RC Exam 1997 Bank Question: 139 Answer: B 1 Pt(9 Which ONE (1) of the following list the Emergency Exposure TEDE Dose Limit for the protection of valuable property?
A. 5 rem.
II.10 rem.
C. 25 rem.
D. 50 rem.
MISCINFO:
RO&SRD SOURCE:
Bank RADPROO75 REFERENCES:
10CFR20. OP MC RAD-PR page 71 LESSON:
OP MC RAD PR TASK:
OBJECTIVE:
LPRO 131 TIME:
KA:19400lR103(2.8/3.4)
DATE:
5/23/97 Confidential
_
_
QUES 139a July 28,1997 -
_
_
-
..
(
'
Question 037 McGuire Nuclear Station R9 Ex:m 1997 Bank Question: 140 Answer: C 1 Pt(s)
An operator and a maintenance mechanic must enter an emergency diesel generato: room to perform a surveillance.
Given the following conditions:
The maintenance mechanic has a security badge for Area 1
The operator has a security badge for Area 1, Area 2 and Area 3 e
Area 1 is the protected area of the plant Area 2 is the vital area with the exception of the control room.
Area 3 is the control room
Which ONE (1) of the following statements is correct?
A.
The mechanic can enter the diesel generator room using his
'
badge, 11.
The operator can escort the mechanic into the room without obtaining further permission.
C.
The operator and the mechanic can enter the diesel generator room if permission is obtained from the shift supervisor.
i D.
The mechanic cannot enter the diesel generator room without first obtaining the correct badge from security. No exceptions may be made this polley.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
NSD 217.5 page 217 9 LESSON:
GET TASK:
OllJECTIVE:
GET TIME:
KA:194001K105(3.1/3.4*)
DATE:
5/23/97 Confidential QUES 140a July 28,1997
_ _.
-.
_ _
-..
--
.
-..
.
._
. _.
- -.-..-. - -___.-- - -
'
'
Question 038 McGuire Nuclear Station R3 Ex:m 1997 l
Bank Question: 141 Answer: B
'
J lPt(s)
Which ONE (1) of the following circumstances would an individual, who
!
had been authorized access to the control room, be allowed to enter the gray l
carpet area without prior approval by an on-duty reactor operator?
A.
The NRC regionalinspectors can enter the gray carpeted area at any time to observe control board operations.
H.
All personnel who have been granted access to the control room
may cross over the gray-carpeted area between the control boards, for entry only.
C.
An) person who had been granted prior access to the gray
,
carpeted area during the day can reenter that area during the
'
shift as long as the on-duty reactor operator who granted permission is present.
D.
Maintenance Supervisors may enter the gray carpeted area if they have an approved work order that requires work in the gray carpeted area and if they have OSM approval to enter the Controlled Access Area.
i MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
MSD 580.5 page 580-11 LESSON:
OP-MC ADM DIR TASK:
- OBJECTIVE:
LPRO 3 TIME:
KA:194001 A109(2.7/3.9*)
DATE:
5/24/97
.
- Confidential
___.
_ QUES 141a
. July 28,1997 WN w
w u c'-r- - ~
-m ww--M-T--mg----pw e a-'
= = -
m-
+-- +
- + + -
.
'
Question 039 McGuire Nuclear Station R3 Exam 1997 Bank Question: 142 Answer: A 1Pt(s)
A maintenance worker reported that a fire door was darnaged while removing a piece of heavy equipment from a room. The door will no longer close.
Which ONE (1) of the following actions are required by McGuire Station Directives.
A.
Within one hour, station a passive fire watch and initiate a " Fire l
Watch" tag.
B.
Report this event under 10CFR50.72 to the NRC (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> l
reportable event) and station a security guard at the door C.
Within one hour, notify the Security Shift SupenIsor and initiate a " Fire Watch" tag.
D.
Within one hour, notify the Fire Protection Engineer and take whatever actions are specified by him/her.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
MSD 460 pages 10,11 LESSON:
OP MC-SS RFY TASK:
OILIECTIVE:
LPRO 28 TIME:
KA:19400lR116(1.5/4.2*)
DATE:
5/23/97 l
Corst,dential QUES 142a July 28,1997 -
.;
.
'
Question C40 McGuire Nuclear Station R9 Ex:m 1997 Bank Question: 143 Answer: A 1 Pt(s)
Which ONE (1) of the following requirements is required by OMP 41 for verification of a working copy of a procedure?
A.
All permanent changes must he verified to be entered but restricted changes are only entered if the reason for the change still applies.
H.
All permanent changes and restricted changes must he verified
to be entered prior to use.
C.
Permanent changes need not he verilled as they are already entered into the control copy. Only restricted changes need to be verified.
D.
Only permanent changes need to be verilled to be entered.
Restricted changes are not required to be entered.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OMP 4-1 pages 9,10 LESSON:
OP MC ADM.OP TASK:
OBJECTIVE:
LPRO 5 TIME:
KA:194001 A101(3.3/3.4)
DATE:
5/23/97
_
Confidential _ -_
-
_
QUES 143a
--
. -
--
July 28,1997-
-
_-
j
.
Question C41 McGuire Nuclear Station R9 Exam 1997-l Bank Question: 144 Answer: 0
'
1 Pt(s)
Which ONE (1) of the following statements describes the requirements for a reference use procedure?
A.
Shall he performed using step by step adherence unless
,
flexibility is allowed by the procedure or other criteria in the
,
i OMP, A copy shall be in the possession of the performer (s) at i
the job site.
!
H.
May be performed by periodically referring to the procedure to ensure procedural adherence and appropriate steps are being i
performed. Written sign off steps will be signed off prior to proceeding to the next step. A copy shall be at the job site.
l
C.
May he performed by periodically referring to the procedure to
'
ensure procedural adherence and appropriate steps are being
performed. Written sign off steps will be signed off as frequently
as practical. A copy shall he at the job site.
?
D.
May be performed by periodically referring to the procedure to ensure procedural adherence and appropriate steps are being performed. Written sign off steps will be signed off as frequently
'
l as practical. A copy is not required at the job site.
.
t MISCINFO:
RO&SRO SOURCE:
NEW
.
'
REFERENCES:
OMP 41 page 5 and 6 LESSON:
OP-MC ADM OP TASK:
' OBJECTIVE:
LPRO 6 TIME:
.
'
KA:194001 A102(4.l*/3,9)
DATE:
5/24/97 i-
<
. Confidential QUES 144a July 28,1997
- _ _.
.--
-
..
. - _ _ -.
.. - -.
..
- -
- -
.
_.
.
_ _.
-
.. -
. -
_ _
.
- _.
.
.
'
Question C42 MtCulre Nuclear Station R3 Ex:m 1997 Bank Question: 146 Answer: D 1 h(s)
" Condition with fuel in the reactor vessel and level is lower than 3 feet below the reactor vessel flange."
Which ONE (1) of the following terms matches the definition provided above?
A. h11d Loop H. Dralned Loop C.111 Decay llent Condition D. Reduced Inventory hilSCINFO:
RO&SRO SOURCE:
Bank ADhiDIR06 REFERENCES:
MSD 403, Shutdown Risk Management Guidelines LESSON:
OP MC ADM DIR TASK:
OBJECTIVE:
LPRO 2 TIME:
KA:194001A108(2.6/3.1)
DATE:
5/24/97 Confidential.
QUES 146a July 28,1997
_-.
--
.
-_ -
_
.
.
Question C43 McGuire Nuclear S'. : tion R3 Ex:m 1997 Bank Question: 148 Answer: C j
1 Pt(s)
What is the reason for the bank overlap function of the rod control system and in what control modes does this function operate?
A.
The bank overlap function provides a more uniform reactivity addition rate and is only active in the automatic control mode.
H.
The bank overlap function prevents axial flux tilt and is active in both the automatic and manual control modes.
C.
The bank overlap function provides a more uniform reactivity addition rate and is active in both the automatic and manual control modes.
D.
The bank overlap function prevents excessive axial flux tilt and is active only in the automatic control mode.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP MC-lC lRE page 13 LESSON:
OP MC-IC IRE TASK:
OBJECTIVE:
LPRO5 TIME:
KA:001010K501(2.7/3.4)
DATE:
5/25/97
<
Confidential QUES 148a July 28,1997
-
-
-
.
.
__--.
_ -.
.
,.
.
Question C44 McGuire Nuclean Station R9 Exam 1997 Bank Question:149 Answen A 1Pt(s)
A Unit I control room evacuation has occurred and the operators have transferred control to the ASP.
Given the following plant conditions:
The reactor has been tripped.
.
i e Pzrlevelis 40%
Phase A isolation (S)did NOT occur e
Control has been transferred to the ASP.
e The following valves were open when the operators left the Control
.
Room:
INV 457A (45 gpm UD ORIFICE OUTLET CONT ISOL)
INV 458A (75 gpm UD ORIFICE OUTLET CONT ISOL)
INV 35A (VARIABLE UD ORIFICE OUTLET CONT ISOL)
.
Which ONE (1) of the following statements correctly describes the status of the letdown orifice isolation valves NV-457, NV-458 and NV-357 A.
All three valves will remain open until the operators take manual action and shut them from the ASP 11.
Only INV-457A will close automatically C.
Only INY-457A and INV-458A will close automatically D.
INY-457A INV-458A and INY 35A will close automatically MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP MC PS NV page 44 LESSON:
OP-MC PS NV TASK:
OBJECTIVE:
LPR0 6 TIME:
KA:004000A207(3.4/3.7)
DATE:
5/25/97
,
Confidential QUES 149a July 28,1997
..
-.
...
.--..
-
--
_
,.
.
Question C45 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 150 Answer: A 1Pt(s)
Unit 1 is responding to a reactor trip from 100% power. A main feedwater isolation occurred at 0200 due to P-4 and low T,,,
Given the following plant conditions at the following times:
Time 0200 0201 0205 0210 T.,,
552 551 554 555 R, Trip Breakers open open open shut A SG NR level 81 %
80 %
75 %
70%
B SG NR level 79 %
81 %
76 %
72 %
l C SG NR level 80%
79 %
75 %
71 %
l D SG NR Level 82 %
80 %
75 %
71 %
When is the earliest time that the FW1 reset pushbutton can be depressed and allow the operators to regain control of main feedwater components?
A.
0200 B.
0201 C.
0205 D.
0210 MISCINFO:
RO ONLY SOURCE:
NEW REFERENCES:
OP MC-ECC ISE pages 23,24,25,26 OP MC lC IPE page 24 LESSON:
OP-MC ECC-ISE TASK:
OBJECTIVE:
LPRO IN TIME:
KA:013000K413(3.7/3.9)
DATE:
5/25/97 Confidential QUES 150a July 28,1997
i i
.
,.
.
Question C46 McGuire Nuclear Station R9 Ex m 1997 Bank Question: 151 Answer: C 1 Pt(s)
The operators are at 85% power steady state when the reactor operator observes the following parameters on the nuclear instruments:
Time 0200 0205 0210 0215 N141 85 %
84 %
84 %
86 %
NI42 85 %
85 %
86 %
87%
N143 84 %
84 %
B6%
87 %
N144 84 %
83 %
83 %
85 %
Calorimetric power 84 %
83 %
83 %
84 %
What is the earliest time that the operators MUST declare the excore Nis inoperable and enter Tech Spec 3.0.3 A.
0200 H.
0205 C,
0210 D.
0215 i
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP MC-lC-ENB pages 37,38 LESSON:
OP MC-lC END TASK:
OBJECTIVE:
LPRO 14B TIME:
KA:015000A101(3.5/3.8*)
DATE:
5/25/97 Confidential QUES 151a July 28,1997-
_ _a
.
Question C47 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 152 Answer: B 1 Pt(s)
The operators are conducting a reactor startup.
Given the following indications on the source range (SR) and intermediate range (IR) excore nuclear instruments:
Time 0200 020$
0210 0215 SR "A"(eps)
1.5x10*
2.5x10*
2.8x10'
l.1 x10'
SR "B" (eps)
1Ax10 2.3x10 2.7x10 9.8x10
4
4 l
1R "A" (amps)
7.6x 10'"
9.8x 10
1.1 x 10
7.0x 10
'
1R "B" (amps)
7.9x 10-"
1.2x 10'"
1.5x 10
7.5 x 10
l What is the earliest time that the P 6 status lights are lit and the operators should block the source range high flux trip?
A.
0200 H.
i)205 C.
0210 D.
0215 MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP.MC-lC ENB pages 22,23 MC.lC END 2
' ESSON:
OP MC-IC ENB TASK:
JECTIVE:
LPRO 12 TIME:
KA:015000K401(3.1/3.3)
DATE:
5/25/97 Confidential
-
QUES 152a July 28,1997
.
'
. Question C48 McGuire Nuclear Station RD Ex:m 1997 Bank Question: 153 Answer: A 1 Pt(s)
Which ONE (1) of the following statements correctly describes the operation of the Containment Ventilation Cooling System (RV) valves, 1RN 301 A,C and RN-302B (RV SU"?LY FROM LLl).
A.
These valves will automatically close to isolate the non essential header on a 111-111 Containment Pressure (S,) signal.
H.
These valves will automatically close to isolate the non-essential header on a Safety Injection (S ) signal.
l C.
Valves RN 301 A, C will automatically open while RN-302B will close to maintain the cooling water flow path in response to a III.
111 Containment Pressure (S,) signal.
D.
These Valves will automatically open to swap the eaoling water flow path to.the Low Level lutake in response to a 11!-l{!
Containment Pressure (S,) signal.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP MC-CNT-RV page 6 LESSON:
- OP-MC-CNT-RV TASK:
OBJECTWE:
LPRO 12 TIME:
KA:022000A404(3 l*/3.2)
DATE:
5/26/97 Confidential QUES 153a July 28,1997
"
,
.
.
-
..
- _ _
.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _.
..
'
Question C49 McGuire Nuclear Station R3 Ex m 1997 Bank Question: 154 Answer: O 1 Pt(s)
Which ONE (1) of the following conditions will cause a Containment Ice Condenser (NF) lce Machine to shutdown?
A.
Low o'l pressure B.
Glycol expansion tank Lo-Lo level
,
C.
Compressor high pressure D.
Low feed solution temperature
,
I MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-CN -NF page 35 LESSON:
OP MC-CNT-NF TASK:
OBJECTIVE:
LPRO 2 TIME:
KA:025000K402(2.8*/3.0*)
DATE:
5/26/97 Confidential QUES 154a July 28,1997 l
_J
.
Question C50 McGuire Nuclear Station R9 Ex:m 1997 Bank Question:- 155 -
Answer: D 1 Pt(s)
The plant is at 95% power in the process ofincreasing to 100% power with the following sequence of events:
A and C Hotwell Pumps (HWPs) in operation with the B HWP in
" auto",
A and C Condensate Booster Pumps (CBPs) in operation with B CDP in
" auto".
A feedwater system transient causes the CDP Lo-Lo suction header
pressure alarm to activate.
The B HWP fails to auto-start.
- After restoring condensate system pressure, the operators commence troubleshooting the cause of the B HWP auto-start problem.
,
Which ONE (1) of the following potential malfunctions would NOT cause
,
'
the auto-start problem?
A.
1he suction valve to llWP "B" was partially shut.
B.
The discharge valve to HWP "B" was not fully open.
C.
Loss of 125 VDC control power to the DC interlocks circuitry D.
ICM-976 (CONDENSATE FILL ISOL)- to the polishing
- demineralizers was fully open.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-CF-CM page 26,29,30,31 LESSON:
OP-MC-CF-CM TASK:
OBJECTIVE:
LPRO 7 TIME:
KA:056000A204(2.6/2.8*)
DATE:
5/26/97 Confidential QUE5155a July 28,1997 l
l]
.
Question 051 McGuire Nuclear Station R@ Ex_m 1997 Bank Question: 156 Answer: D 1 Pt(s)
The plant is at 50% power increasing to 100%. Given the following events:
1.
Closure of CF-32 (A S/G CF CNTRL VALVE) at 20% open with CF-104 (A S/G CF CNTRL VLV BYPASS) fully open 2.
Closure of CF 23 (B S/G CF CNTRL VALVE) at 10% open with CF-105 (B S/G CNTRL VLV BYPASS) shut.
3.
Closure of CF 28 (C S/G CF CONT OUTSIDE ISOL)
4.
Closure of CF-26 (D S/G CF CONT OUTSIDE ISOL)
Which ONE (1) of the following combination of events will cause AMSAC to activate?
A.
1,2,3 B.
1,2,4
!
C.
1,3,4 D.
2,3,4 I
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-CF-CF pages 17,17,18,19,20
'
PID # MC-CF-CF-3 LESSON:
OP-MC-CF-CF TASK:
OBJECTIVE:
LPROISB TIME:
KA:059000K303(3.5/3.7)
DATE:
5/26/97
'
Confidential QUES 156a July 28,1997
__-__-
_________- _ __--__ _ ______
Question 052 McGuire Nuclear Station R9 Ex"_m 1997 Bank Question: 157 Answer: C 1 Pt(s)
The operators are performing a plant startup.
Two feedwater pumps (FWPT) arein operation.
Given the following conditions:
Powerlevelis 50%
The "B" FWPT trips on a loss of control oil pressure
The"A"FWPT continues to operate
.
Control oil pressure is restored to the "B"FWPT e
Which ONE (1) of the following statements describe the correct operator
,
response for restoring the "B" FWPT to operation?
A.
Immediately RESET the feedwater pump recire valve to prevent
'
the recire valve from opening.
- H.
Ensure that the manual loader for the recire valve is set to 50%
and RESET the recire valve.
C.
Ensure that the manual loade. for the recire valve is set to 0%
and RESET the rectre valve.
D.
No action is necessary as the recire valve will be prevented from l
opening.
MISCINFO:
RO ONLY SOURCE:
NEW REFERENCES:
OP-MC-CF-CF page 13 LESSON:
OP-MC-CF-CF TASK:
OBJECYIVE:
LPRO 7 TIME:
KA:059000K416(3.l */3.2*) -
DATE:
5/26/97 Confidential QUES 157a July 28,1997
)
_..
.
Question C53 -
McGuire Nuclear Station RD Ex:m 1997 Bank Question: 158 Answer: A 1 Pt(s)
What design features protect the turbine driven auxiliary feedwater (CA)
pump against minimum flow conditions and runout?
A.
Minimum now protection provided by recirc valves, runout protection provided by max flow travel stops on discharge control valves.
B.
Minimum flow protection provided by recire valves, runout protection provided by flow restricting orifices in feedwater lines.
C.
Minimum flow protection provided by governor control settings, runout' protection provided by max flow travel stops on I
discharge control valves.
,
D.
Minimum flow protection provided by, governor control settings runout protection provided by flow restricting orifices in feedwater lines, l
- MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-CF-CA page 24 LESSON:
OP-MC-CF-CA -
TASK:
OBJECTIVE:
LPRO 7 TIME:
KA:061000K404(3.1/3.4)
DATE:
5/26/97
,
Confidential QUES 158a July 28,1997
.
--_______J
.
Question #54 McGuire Nuclear Station RD Ex:m 1997 Bank Question: 159 Answer: C 1 Pt(s)
The plant is operating at 100% power. Given the following conditions:
An IAE technician reported that the auto start signal of a CA pump
from the "A" main feedwater pump has failed its surveillance test due to a calibration problem on the oil pressure switch.
Which ONE (1) of the following responses is correct by tech specs?
REFERENCES PROVIDED
A.
No tech spec action is required as the main feedwater pump trip is not covered under tech specs.
B.
Operation may continue for up 10 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while repairs may be effected, or a shutdown must be started.
C.
Operation may continue provided that the histables are tripped within one hour.
D.
Immediately enter tech spec 3.0.3 and commence a plant shutdown within one hour.
MISCINFO:
RO ONLY SOURCE:
NEW REFERENCES:
OP-MC-CF-CA page 10,29 Tech Specs Table 3.3-3 PROVIDED LESSON:
OP-MC-CF-CA TASK:
OBJECTIVE:
LPRO 9B TIME:
KA:061000G006(2.7/3.8)
DATE:
5/26/97 l
l Confidential QUES 159a July 28,1997
_A
. _ _ _ -. _ _ _ _
__
,
'
- Question 055 McGuire Nuclear Station RD Exam 1997 Bank Question: 161 Answer: A
.,
1 Pt(s)
Which ONE (1) of the following signals will automatically trip the Waste Gas Flow Controller IWG-160, during a release from the Waste Gas Decay Tanks?
A.
Un!t vent gas 1 EMF 36(L) trip 2 B.
Waste Gas Compressor Suction Pressure Low C.
111111 Oxygen concentration (>4%)
,
D.
Waste Gas Moisture Separator Level-111 l
MISCINFO:
RO&SRO
- SOURCE:
NEW REFERENCES:
OP-MC-WE-WG pages 27,31,35 LESSON:
OP-MC-WE-WG TASK:
OBJECTIVE:
LPRO 5 TIME:
,
KA:071000A303(3.6/3.8)
DATE:
5/26/97 Confidential QUES 161a July 28,1997 l
.
Question C56 McGuire Nuclear Station R9 Ex:m 1997 Bank Question: 162 Answer: C 1 Pt(s)
Which ONE (1) of the following Containment Radiation Monitors will initiate containment ventilation isolation as indicated by the corresponding sequence of actions?
A.
EMF-38(II) trip-1-will secure VP and VQ, and shutoff containment sump pumps and incore sump pumps.
B.
EMF-39(L) trip-1 will sound the containment evacuation alarm, and secures VP and VQ.
C.
EMF-40 trip-2 will secure VP and VQ, and shutoff containment sump pumps and incore sump pumps.
D.
EMF-41 trip-2 will secure VP and VQ, and shutoff containment sump pumps and incore sump pumps.
l MISCINFO:
RO ONLY SOURCE:
NEW REFERENCES:
OP-MCAVE-EMF pages 15,16,17 LESSON:
OP-MC-WE-EMF TASK:
OBJECTIVE:
LPRO 3 TIME:
KA:072000K401(3.3*/3.6*)
DATE:
5/26/1997 Confidential QUES 162a July 28,1997
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Question 057 McGuire Nuclear Station RG Ex:m 1997 a
Bank Question: 164 Answer: D 1 Pt(s)-
The plant was operating at 100% when an "A" SG steam header rupture caused the operators to implement E-0, E-1 and E 2.
The following sequence ofevents occurred:
Reactor trip and safety injection
Isolation of the "A" SG
.
Restoration of Pzr level to 20%
e Si has not been reset
What is the correct sequence for the restoration of power to Pzr back-up heater bank A7 i
A.
Power will be restored automatically when Pzr level is restored above 17%.
B.
Select "ON" on the back-up heater control switch on IMC10.
C.
-Select MANUAL on the "A" PZR IITR MODE SELECT switch on 1MC10,
-Close the back-up heater breaker on IMCCS,
-Select "ON" on the back-up heater control switch on IMC10.
D.
-Reset Safety Injection-Select MANUAL on the "A" PZR llTR MODE SELECT switch on IMC10,
-Close the back-up heater breaker on 1MCC5,
-Select "ON" on the back-up heater control switch on IMC10.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-PS-IPE pages 23,59, 71 LESSON:
OP-MC-PS-IPE TASK:
- OBJECTIVE:
LPRO 10 TIME:
KA:010000K402(3.0/3.4)
DATE:
5/26/1997
~ Confidential QUES 164a July 28,1997
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Question C58 McGuire Nuclear Station RD Ex;m 1997 Bank Question: 165 Answer: B 1 Pt(s)
Which ONE (1) of the following statements describes the effects of a loss of a 120 VAC Vital Bus to SSPS while at 100% power?
A.
All histables in affected channel wil! deenergize All 2/4 logie becomes 1/3 All 2/3 logic becomes 1/2 The reactor WILL trip since the RTB UV coils will deenergize
'
B.
All bistables in affected channel will deenergize
!
All 2/4 logic becomes 1/3 All 2/3 logic becomes 1/2 The reactor will NOT trip since the RTB UV coils will remain energized l
'
C.
Only bistables powered from input cabinet will deenergize NC pump trips go to 1/3 Turbine trip logic goes to 2/3 Stop valves closed logic goes to 1/3 The reactor will NOT trip D.
Only histables powered from input cabinet will deenergize NC pump trips go to 1/3 Turbine trip logic goes to 2/2 Stop valves closed logic goes to 3/3 The reactor will NOT trip MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-IC-IPE page 33,34 LESSON:
OP-MC-IC-IPE TASK:
OBJECTIVE:
LPRO 8 TIME:
KA:012000K101(3.4/3.7)
DATE:
5/27/97 Confidential QUES 165a July 28,1997 i
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Question 059 McGuire Nuclear Station RD Ex:m 1997 Bank Question: 106 Answer: B 1 Pt(s)
Given the following initial conditions:
"A" KF pump running
"B" KF pump stopped e
"A" and "B" KF Air Handler Unit (AHU) in auto
What is the condition of the KF System 10 minutes after a safety injection assuming no operatoraction?
A.
"A" KF pump running
"A" AHU running
"B" KF pump running
"B" AHU running
___.-
-B. ~ ~"A" KF pump running
"A" AHU running
"B" KF pump stopped
"B" AHU running C.
"A" KF pump running
"A" AHU running
"B" KF pump stopped
"B" AHU stopped D.
"A" KF pump running
"A" AHU stopped
,
"B" KF pump stopped
"B" AHU stopped MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-FH-KF pages 13,14 LESSON:
OP-MC-FH-KF TASK:
OBJECTIVE:
LPRO 9 TIME:
KA:033000A202(2.7/3.0)
DATE:
5/27/97 Confidential QUES 166a July 28,1997
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _
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Question #60 McGuire Nuclear Stati2n R9 Ex:m 1997 Bank Question: 167 Answer: B 1 Pt(s)
During a plant cooldown when T.,, is 400'F, which ONE of the following statements is correct regarding Wide Range (WR) and Narrow Range (NR)
indicated SG level?
A.
NR dG indicated level is higher than actual level WR SG indicated levelis higher thkn actual level B.
NR SG indicated level is higher than actual level WR SG indicated level is lower than actual level C.
NR SG Indicated level is lower than actual level WR SG indicated levelis higher than actual level D.
NR SG indicated level is lower than actual level l
WR SG indicated level is lower than actual level MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-STM-SG LESSON:
OP-MC-STM-SG page 23 TASK:
,
OBJECTWE:
LPRO5
= TIME:
'
KA:035010K603(2.6/3.0)
DATE:
5/27/97 Confidential QUES 167a July 28,1997 I
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^
Question C61 McGuire Nuclear Stati:n RO Ex:m 1997 Bank Question: 168 Answer: D
1 Pt(s)
In order to assure that moisture canyover in a SG will not exceed the design specification of 0.25% by weight, what operating limits are places on the SG7 A.
Steady state operation up to 100% of full steam load Loading or unloading rate of 10% full power How per minute Step load change of10% of full power B.
Steady state operation up to 102% of full steam load i.
Loading or unloading rate of10% full power Dow per minute Step load change of 10% of full power
'
C.
Steady state operation up to 102% of full steam load Loading or unloading rate of 5% full power How per minute Step load change of10% of full power D.
Steady state operation up to 100% of full steam load Loading or unloading rate of 5% full power Gow per minute Step load change of10% of full power MISCINFO:
RO ONLY SOURCE:
NEW REFERENCES:
OP-MC-STM-SG page 19 LESSON:
OP-MC-STM-SG TASK:
OBJECTIVE:
LPRO 4 TIME:
KA:035010G10(3.2/3.4)
DATE:
5/27/96 Confidential QUES 168a July 28,1997
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Question C62 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 169 Answer: D 1 Pt(s)
Which ONE (1) of the following protective actions will initiate an automatic fast transfer of the TA 6900V bus ?
A.
Degraded vonge relay actuation B.
Under-voltage condition relay actuation C.
Under-frequency condition relay actuation D.
Generator-switchyard protective lockout MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-EL-EP pages37,39 l
LESSON:
OP-MC-EL-EP TASK:
OBJECTIVE:
LPRO 24 TIME:
KA:062000A216(2.5/2,9)
DATE:
5/27/97
,
l
Confidential QUES 169a July 28,1997
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Question C63 McGuire Nuclear Station RD Ex';m 1997 Bank Question: 170 Answer: C 1 Pt(s)
Which ONE (1) of the following loads is powered from 250 VDC auxiliary power system?
A.
Control Room Annunciators B.
Reactor Trip Breaker under-voltage coils C.
Turbine Emergency Bearing Oil Pump D.
Switchgear protective relays MISCINFO:
RO ONLY SOURCE:
NEW
!
REFERENCES:
OP-MC-EL-EPJ page 10 LESSON:
OP-MC-EL-EPJ TASK:
OBJECTIVE:
LPRO11 TIME:
i L
KA:063000K201(2.9*/3.1*)
DATE:
5/27/9/
t
Confidential QUES 170a July 28,1997
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Question C64 McGuire Nuclear Station RD Ex:m 1997 Bank Question: 171 Answer: C 1 Pt(s)
What is the purpose of the IEMF-34 process monitor and what automatic actions (if any) are controlled by 1 EMF-347 A.
hionitors S/G blowdown demineralizer outlet Closes BB 101 (S/G blowdown IIX inlet Closes BB-83 (S/G demineralizer outlet)
B.
51onitors activity from the condenser air ejector No automatic actions C.
hionitors S/G sample line for non volatile contamination Closes NM 267(EMFinlet)
Closes BB-119, BB-120, BB-121, BB-122 (secures blowdown)
Closes NM-269, NM-270, NM-271, NM-272 (secures sampling)
D.
Monitors steam line radiation levels for tube leak No automatic actions I
l MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-WE EMF pages 12,13 PID MC-WE-EMF-11 PID MC-WE-EMF-01 LESSON:
OP-MC-WE-EMF TASK:
OBJECTIVE:
LPRO 3 TIME:
KA:073000K401(4.0/4.3)
DATE:
5/27/97 Confidential QUES 171a July 28,1997 l
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Question C65 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 172 Answer: A 1 Pt(s)
Which ONE (1) of the following statements describes the design feature which protects the Instrument Air Header from a rupture and depressurization of the Low Pressure Station Air Header.
A.
A cross-connect valve automatically closes on low header pressure.
B.
A cross-connect check valve closes on reverse flow from VI to VS.
C.
The VI air compressor automatically starts to repressurize the header.
D.
A cress-connect valve automatically closes on high header flow.
'
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-SS VS page 10 PID MC-SS-VS-2 LESSON:
OP-MC-SS-VS TASK:
OBJECTIVE:
LPRO 1 TIME:
KA:079000K401(2.9/3.2)
DATE:
5/27/97 Confidential QUES 172a July 28,1997
,
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.,
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Question C66 McGuire Nuclear Station RD Ex m 1997 Bank Question: 173 Answer: B
.
1 Pt(s)
l't the event of a fire which activates the fire protection system, which ONE (1) of the following sequence of events is the nonnat starting sequence for
,
the fire pumps?
A.
The "A" Jockey Pump starts at 31" level in the pressurizer tank The "B" Jockey Pump starts at 29" level in the pressurizer tank
'
The "A" Fire Pump starts at 27"levelin the prmuri:e Nnk The "B" Fire Pump starts at 25" level in the pressur'
cak The "C" Fire Pump starts at 23" level in the pressurizer tank B.
The "A" Jockey Pump starts at 31" level in the pressurizer tank The "B" Jockey Pump starts at 29" level in the pressurizer tank l
The "A" Fire Pump starts at 81 psig system pressure l
The "B" Fire Pump s#. arts at 76 psig system pressure The "C" Fire Purry starts at 71 psig system pressure C.
The "A" Jockey Pump starts at 85 psig system pressure The "B" Jockey Pump starts at 83 psig syrtem pressure The "A" Fire Pump starts at 81 psig system pressure The "B" Fire Pump starts at 76 psig system pressure The "C" Fire Pump starts at 71 psig systein pressure D.
The "A" Jockey Pump starts at 85 psig system pressure The "B" Jockey Pump starts at 83 psig system pressure The "A" Fire Pump starts at 81 psig system pressure The "D" Fire Pump starts by operator action The "C" Fire Pump starts by operator action MISCINFO:
RO ONLY SOURCE:
NEW REFERENCES:
OP-MC-SS-RFY pages 23,25,27 LESSON:
OP-MC-SS-RFY TASK:
OBJECTIVE:
LPRO 5 TIME:
KA:086000A301(2.9/3.3)
DATE:
5/27/97 Confidential QUES 173a July 28,1997
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Question C67 McGuire Nuclear Station RD Ex2m 1997 Bank Question: 174 Answer: C 1 Pt(s)
Which ONE (1) of the following design characteristics will prevent the Residual Heat Removal System (ND) from being over-pressurized by the Reactor Coolant System (NCS) when ND is staned.
A.
The ND system relief valves are capable of maintaining system pressure below design pressure.
B.
Operator procedures and a warning annunciator prevent inadvertent pressurization of the ND system from the NCS.
C.
Valve open permissive interlocks on ND to NC loop isolation valves prevent opening these valves against pressures over 385.5 psig.
D.
LTOPs protection of the NCS prevents over pressurization of
,
j the ND system.
i
,
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-PS-ND pages 18,19,20,21,22 LESSON:
OP-MC-PS-ND TASK:
OBJECTIVE:
LPRO 6 TIME:
KA.005000K401(3.0/3.2)
DATE:
5/27/97 Confidential QUES 174a July 28,1997 l
.
- .
.
Question C68 McGuire Nuclear Station RD Ex:m 1997
' Bank Question: 175 Answer: B 1Pt(s)
Unit 1 is operating at 100% power when the following indications are noted by the operators in the control room for the "A" NCP:
KC-345(Thermal Barrier Isolation Valw) shuts automatically
.
Pump lower bearing temprature slow'.y increasing
.
Pump seal water return temperature slowly increasing
What event caused the above indications on the "A" NCP?
A.
Loss of sealinjection l
B.
Ruptured NCP thermal barrier C.
Loss KC flow to BOTII the thermal barrier and to sealinjection -
D.
Failure of the I" stage mechanical seal MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-PS-NCP page 15 OP-MC-PSS-KC pages 19,23 LESSON:
OP-MC-PSS-KC TASK:
OBJECTIVE:
LPRO5 TIME:
KA:008010A302(3.0/3.1)
DATE:
5/27/97
.
Confidential QUES 175a July 28,1997
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Question C69 McGuire Nuclear Station RO Ex m 1997 Bank Question: 176 Answer: C 1 Pt(s) -
Which ONE (1) of the following sets of Hydrogen concentrations is correct for % by weight of Hydrogen in dry air?
A.
1. Hydrogen Analyzer Annunciator setpoint = 1.5% -
2. Hydrogen is flammable above 2%
3. Hydrogen is explosive above 4%
B.
1. Ilydrogen Analyzer Annunciator setpoint = 3.5%
2. Hydrogen is flammable above 4%
,
'
3. Hydrogen is explosive above 10%
C.
1. Hydrogen Analyzer Annunciator setpoint = 3.5%
i 2. Hydrogen is flammable above 4%
3. Hydrogen is explosive above 17%
D.
1. Hydrogen Analyzer Annunciator setpoint = 4%
2. Hydrogen is flammable above 5%
3. Hydrogen is explosive above 17%
MISCINFO:
RO&SRO SOURCE:
NEW
- REFERENCES:
OP-MC-CNT.VX pages 19,29
- LESSON:
OP-MC-CNT-VX TASK:
'
OBJECTIVE:
LPRO 3 TIME:
KA:028000K502(3.4/3.9)
DATE:
5/27/97 Confidential QUES 176a July 28,1997
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Question 070 McGuire Nuclear Stati:n RD Ex:m 1997 Bank Question:- 177 Answer: D 1 Pt(s)
Which ONE (1) of the following main turbine overspeed protective devices / features will be the FIRST to actuate to prevent a turbine overspeed condition during a loss of offsite power event?
A.
The OPC circuit willlimit speed without tripping the turbine B.
The mechanical trip device will trip the turbine i
C.
The 20-1 AST device will trip the turbine D.
The GBX relay willlimit speed without tripping the turbine -
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-MT-MT pages 24,25,38,39,59 OP-MC-MT-LH pages LESSON:
1. OP-MC-MT-MT TASK:
2. OP-MC-MT-LH OBJECTIVE:
1. LPRO 3C TIME:
2. LRPO 10 KA:045000K413(2.6*/2.S*)
DATE:
5/27/97 Confidential QUES 177a July 28,1997
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Question 071 -
McGuire Nuclear Station RO Extm 1997 Bank Question: 178 Answer: D 1 Pt(s)
Unit 1 is shutdown in mode 5 when a loss ofInstmment Air (VI) occurs.
Given the following plant conditions:
A rupture on the VI common discharge line for the A, B, and C air
.
compressors has been isolated.
The operator is directed to restart the D centrifugal air compressor to
.
restore the VI header.
- Which ONE (1) of the following sequences will provide for a successful restart of the D VI compressor in the absence of VI air pressure?
A.
Control air is supplied internally from the compressor output stage upon restart of the D VI compressor. The compressor may be restarted immediately.
B.-
Cross connect _ the VB air system to the VI air system and repressurize the VI air header. Restart the D compressor when VI header pressure is above 80 psig.
L C.
Cross connect the VS air system to the VI air system and repressurize the VI air header. Restart the D compressor when VI header pressure is above 80 psig.
D.
Isolate the normal VI control air supply and connect the VB air system to provide control air for the D compressor. The compressor may be restarted once control air is supplied from VB.
MISCINFO:
RO ONLY SOURCE:
NEW REFERENCES:
OP MC-SS-VI page 23,24 LESSON:
OP-MC-SS-VI TASK:
OBJECTIVE:
LPRO TIME:
KA:078000K302(3.4/3.6)
DATE:
5/28/96 Confidential QUES 178a July 28,1997
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Question #72 McGuire Nuclear Station RD Ex:m 1997 Bank Question - 179 Answer: C 1 Pt(s)-
Which ONE (1) of the following statements describes the design feature that protects against large negative pressure from building up in the containment annulus?
A.
The primary containment shell is designed to withstand the largest negative pressure that could be created by the VE exhaust fans operating continuously in the exhaust mode.
B.
The containment vacuum breaker will open at -7" of water allowing the annulus area to be vented to containment.
C.
. The VE exhaust fans will trip on Low-Low pressure at -7" of water.
D.
'
The VE exhaust fans will shift from the exhah.t mode to the recirc mode at-7" of water.
MISCINFO:
RO ONIX SOURCE:
NEW REFERENCES:
OP-MC-CNT-VE pages 13,15,17 LESSON:
OP-MC-CNT-VE TASK:
OBJECTIVE:
LPRO 9 TIME:
KA:103000K401(3.0*/3.7*)
DATE:
5/28/97
Confidential QUES 179a July 28,1997
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Question 073 McGuire Nuclear Station RO Ex:m 1997 Bank Question: 180 Answer: C 1Pt(s)-
What is the basis for tripping NC pumps in FR-H,1 just prior to attempting to reestablish feedwater flow to the S/Gs?
A.
To prevent damaging the pump during bleed and feed actions.
This maintains the integrity of the NCPs for forced circulation recovery in later stages.
B.
To reduce SG tube sheet temperatures below dryout limits.
Shifting to natural circulation flow will incrcase the temperature i
difference across the core and thereby lower temperatures at the SG tube sheet region.
C.
To extend the effectiveness of the remaining water inventory by reducing the heat input to the NCS. This extends the time at which operatcr action to initiate feed and bleed must occur.
l D.
To increase the cooldown rate of the steam generators by reducing the heat transfer rate between the NCS and the S/Gs.
This improves the chances for recovery of a S/G using a low pressure source of water because the S/Gs will depressurize more rapidly.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-EP-FRH page 41 LESSON:
OP-MC-EP-FRH TASK:
OBJECrlVE:
FR-H.1 Obj 9 TIME:
KA:002000A204(43/4.6)
DATE:
5/28/97 Confidential QUES 180a July 28,1997
.
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- Question 074 McGuire Nuclear Station R3 Ex m 1997 Bank Question: 181 Answer: B 1 Pt(s)
Step 4d of FR S.1 requires the operators to check Pzr pressure less than 2335 psig immediately after initiating emergency boration flow to the l
reactor, If pressure exceeds 2335 psig, the contingency action is to open a l
PORV and rapidly depressurize to 2135 psig. What is the basis for this step?
A.
To maintain pressure below the PORY setpoint to prevent cycling the PORVs.
B.
To ensure that the borallon flow rate is sufficient for emergency
'
boration.
C.
To maintain positive control of NC pressure to prevent lifting a code safety relief valve.
D.
To reduce NC pressure to allow closing of NV pump recire valves to maximize emergency boration flow.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
. OP-MC-EP-FRS page 25,27 FR-S.1 pages 2,3,4,5
.
LESSON:
OP-MC-EP-FRS TASK:
OBJECTIVE:
FR-S.1 Obj: 6 TIME:
KA:000024EK302(4.2/4,4)
DATE:
5/28/97
b Confidential QUES 181a July 28,1997
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Question 075 McGuire Nuclear Station R9 Ex:m 1997 Bank Question: 182 Answer: C 1 Pt(s)
Which ONE (1) of the folloxing protective actions will cause 1KC-338B (NC PUMP SUP HDR CONT OUTSIDE ISOL) to close automatically?
A.
Phase A isolation B.
Safety Injection C.
111-111 Containment Pressure D.
Station Blackout
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-PSS-KC page 32,33 LESSON:
OP-MC-PSS-KC TASK:
OBJECTIVE:
LPRO 4 TIME:
KA:000026EK302(3.6/3.9)
DATE:
5/28/97
,
Confidential QUES 182a July 28,1997
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Question 076 McGuire Nuclear Station R3 Exam 1997 Bank QuesGot.' 183 Answer: D 1 Pt(s)
Unit I was opera'ing at power when the operators detennine that there is a steam leak. They enter AP/1/A/5500/01 (Steam Leak) and immediately reduce turbine load.
Upon reaching step 8, they note the following conditions:
T,,, is stable
.
Condenser dump valves indicate closed
.
Turbine impulse pressure is 277 psig e
Reactor poweris $$%
e The Turbine 13uilding Operator reports that there is steam blowing out of
a turbine casing drain Which ONE (1) of the following sequence of actions is concet to complete steps 8 and 9 of AP/l/A/5500/01 (Steam Leak)?
REFERENCES PROVIDED A.
Walt for stable plant conditions
,
H.
Trip the turbine C.
Trip the reactor D.
Go to step 10 MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
AP/1/A15500/01 step 8 page 7 LEESON:
OBJECTIVE:
LPRO 12 TIME:
s KA:000040EA202(4.6/4.7)
DATE:
5/28/97-Confidential QUES 183a July 28,1997
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Quesilon 077 McGuire Nuclear Station R3 Exam 1997
'
Bank Question: 184 Answer: C 1Pt(s)
Unit 1 is operating at 100% power when a vacuum leak causes a slow but steady degradation of condenser vacuum.
Which ONE (1) of the following conditions requires the operators to
'
manually trip the reactor while perfonning AP/1/A/5500/23 (LOSS OF CONDENSER VACUUhi)?
A.
Condenser low vacuum (pre-trip) alarm
.
H.
Condenser vacuum decreases to 24"lig C.
Turbine exhaust hood hi hl temperature alarm D.
Turbine Ell fluid emergency low level alarm
AllSCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP hic-hit hit pages 56,57 AP/1/A/5500/23 pages 2,3
,
LES$f'N:
OP htC hit hit TASK OBJECTIVE:
LPRO 21 TIME:
KA:000051EA202(3.9/4.1)
DATE:
6/11/97
.
Confidential-QUES 184a July 28,1997
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Question 078 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 185 Answer: C
1 Pt(s)
Unit I was operating at 100% power when a steam line rupture occurred inside containment. The operators responded by entering:
E-0,"Reactot Trip or Safety injection", followed by
E 2," Faulted Steam Generator isolation" where they isolated the rupture e
and then transitioned to E 1," Loss of Reactor or Secondary Coolant".
e Given and the following conditions at the following times:
Time 0200 0205 0210 0215 Subcooling ['F]
+3
+2
+1
S/G A (NR)[%)
7
11 S/G B (NR)[%)
6
9 S/G C (NR)[%)
7
12 S/G D ('NR)[%)
10
13 Feed Flow A S/G [GPM]
135 135 145 145 Feed Flow B S/G [GPM]
150 130 160 165 Feed Flow C S/G [GPM]
O
0
Feed Flow D S/G [GPM]
160 180 150 160 NC pressure [psig)
1710 1725 1750 1765 Pzr Level [%)
25
32 Containment pressure [psig) 3.2 2.9 2.5 2.4 At 0200, the operators are at step 12 of E-1.
What is the earliest time that the operators can transition to ES 1.1," Safety hijection Termination"?
REFERENCES PROVIDED
..
A.
0200 H.
0205
.
C.
0210 D.
0215 MISCINF9:
RO&SRO SOURCE:
NEW Confidential-QUES 185a July 28,1997
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Question 078 McGuire Nuclear Station RD Exam 1997 REFERENCES:
OP MC-EP El page 43 EP/1/A/5000/E 1 page 6 LESSON:
OP MC EP El TASK:
.,
,
OHJECTIVE:
E 1 series objective 7b TIME:
KA:000040EA205(4.1/4.5)
DATE:
6/3/97
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,
Confidential QUES 185a July 28,1997
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Question 079 PicGuire Nuclear Station R3 Ex:m 1997 94pW1 Bank Question: 186 Answer:f D 1Pt(s)
Unit I was operating at 100% when a loss of offsite power occurs and both DGs fail to start. The operators have entered the appropriate EOPs.
Given the following critical safety function status indications:
- Containment-GREEN inventory. GREEN e
Integrity-GREEN e
Suberiticallity-ORANGE e
llent Sink-RED e
Core Cooling-RED e
j Which ONE (1) of the following actions are required by EOPs.
A.
Immediately transition to FRC-0.1 H.
Immediately transition to FRil-0.1 C.
Immediately transition to FRS-0.1 D.
Remain in ECA-0.0 l
l MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP MC-EP-ECAO pages 9, i1 OP MC-EP INTRO pages 29,31,33 LESSON:
OP MC-EP ECAO TASK:
OBJECTIVE:
Objective 6 TIME:
KA:000055G011(4.1*/4.1*)
DATE:
6/3/97
- Confidential-
- QUES 186a July 28,1997
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Question C80 McGuire Nuclear Station RD Ex:m 1997 Bank Question: 187 Answer: D 1 Pt(s)
Which ONE (1) of the following statements describes the basis for manually
'
actuating Safety injection (SI) if the D/Gs fail to start at step 7.c (RNO) of
ECA 0.0?
A.
To align ESF valves and isolate letdown to maintain NCS Inventory H.
To generate a phase "A" Isolation signal to isolate containment to assure NCP sealisolation C.
To assure the SI sequencer will strip off all loads prior to starting the D/Gs D.
To generate a start signal to the D/Gs MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP MC EP ECAO page 29,31 LESSON:
OP-MC EP ECA0 TASK:
OBJECTIVE:
Objective 7 TIME:
KA:000055EK302(4.3/4.6)
DATE:
6/4/97 L
Confidential QUES 187a July 28,1997
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Question C81 McGuire Nuclear Station RD Ex7.m 1997
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Bank Question: 188 Answer: A 1Pt(s)
Unit 1 is operating at 100% power when a fire in a room in the Auxiliarv Building causes the room heat detector to actuate and the nearby sprinkla valve to open. Which ONE (1) of the following statements describes the correct sequence of events that would occur to provide a flow of water to the sprinkler valve?
A.
Water would immediately flow to the sprinkler valve under the normal configuration of the fire header without any further action.
H.
Deluge valves 1RY ll3 and IRY Il4 would open automatically when the thermostatle detector was actuated and provide water to the fire header.
C.
Deluge valves IRY ll3 and IRY-ll4 would first need to be opened by operator action in the control room to provide water to the sprinkler system.
D.
Deluge valves IRY-ll3 and IRY-ll4 would first need to be opened by operator action at the local breakglass stations in the Auxillary Hullding to provide water to the sprinkler systemi MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC SS RFY pages 41,43 LESSON:
OP MC-SS RFY TASK:
OBJECTIVE:
LPRO 18 TIME:
i KA:000067EK304(3.3/4.1)
DATE:
6/4/97 l
Confidential QUES 188a July 28,1997
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Question C82 McGuire Nuclear Station RO Ex:m 1997 Bank Question:189 Answer: A 1Pt(s)
Unit I was operating at 100% power when a toxic gas accident caused the operators to transfer control to the Auxiliary Shutdown Panel (ASP) and evacuate the control room.
Given the following conditions:
Reactor trip occurred and all rods inserted
Safety injection occurred
Core bumup is 343 EFPD e
Ta = 302 'F e
llow much boric acid must be added in accordance with step 18 of AP/1/A/5500/17 to maintain shutdown margin?
REFERENCES PROVIDED A.
O gallons H.
60 gallons C.
120 gallons D.
I80 gallons MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
AP/1/A/5500/17 page 14 OP MC-CP-SS page 19 UNIT 1 DATABOOK CURVE 1.14 (PROVIDED)
LESSON:
OP-MC-CP-SS TASK:
OBJECTIVE:
LPRO 3 TIME:
KA:000068EK311(3.2/3,6)
DATE:
6/4/97 Confidential QUES 189a July 28,1997
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Question C83 McGuire Nuclear Station RD Ex:m 1997 i
Bank Question:190 Answer: C 1 Pt(s)
Unit 1 is in a refueling outage with the following plant conditions:
'
NC system is mid. loop
ND is in operation e
Which ONE (1) of the following statements correctly describes the status of the containment equipment hatch?
A.
Must be kept closed at all times while the NC system is mid loop.
B.
May he open provided a Watch is stationed to immediately close
-
the hatch in the event of a loss of ND
.
C.
May be open provided contingency plans are in place and equipment is staged to close the hatch prior to core bolling in
the event of a loss of ND.
d D.
May he open as long as the hatch is considered to be operable.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP MC-CP PRO page 45 AP/1/A/5500/19 page 25 LESSON:
OP-MC CP-PRO TASK:
OBJECTIVE:
LPRO 19 TIME:
KA:000069EA202(3.9/4.4)
DATE:
6/4/97 j
Confidential-QUES 190a July 28,19D
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Question #84 McGuire Nuclear Station RD Ex:m 1997 Bank Question: 191 Answer: C 1Pt(s)
Unit I was operating at 100% power when a total loss of feedwater occurred. The Operators reached step 33 of FR H.lwhere they evaluate the requirement to restrict the feedwater flow rate to a hot, dry steam generator upon restoration of fetxlwater.
Given the following conditions:
Loop A Loop B Loop C Loon D S/G(WR)[%) 10
9
NC T u [*Fj* 545 542 549 555 i
'NC T u temperatures were the values recorded in step 27 of FR H.1 i
Core exit T/Cs are trending UP
Containment pressure is 0.4 psig e
VI pressure is 120 psig e
Assuming the conditions above do not change, which ONE (1) of the following statements correctly describes the initial restrictions for restoring feedwater flow following bleed and feed in FR H.l.
REFERENCES PROVIDED A.
Feedwater may he restored to all four S/Gs but limited to 100 GPh1 flow rate.
H.
Feedwater may be restored to any one SG hut limited to 100 GPh1 flow rate C.
Feedwater may be restored to any one S/G hut limited to a feed rate required to lower core exit T/Cs D.
Feedwater may be restored to the A, B or C S/G only and limited to 100 GPh1 511SCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
FR H.1 page 28 PROVIDED FR-H.1 enclosure 7 pages 1-7 PROVIDED LESSON:
OP-MC-EP-FRH TASK:
l Confidential QUES 191a July 28,1997 m
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Question C84 McGuire Nuclear Station RD Ex:m 1997
'
OBJECTIVE:
FR il.1 Objective 10 TIME:
j KA:000054EA104(4,4/4,5)
DATE:
6/4/97 i
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,
.
t
- Confidential-
-
QUES 191a
-
July 28,1997
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Question C85 McGuire Nuclear Station R3 Ex:m 1997
-
Bank Question: 192 Answer: D 1Pt(s)
Which ONE (1) of the following S/G sample results exceeds the Technical l
Specification limits.
A.
gross specific activity > 0.01 pel per gram H.
gross specific activity > 0.1 pel per gram C.
gross specific activity > 0.01 pel per gram dose equivalent l
D.
gross specific activity > 0.1 pel per gram dose equivalent 1"'
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
Tech Spec 3.7.1.3 LESSON:
OP MC Cil SC TASK:
OBJECTIVE:
LPRO 13 TIME:
KA:000037G003(3.2/3.9)
DATE:
6/4/97
- - - -
- Confidential-QUES 192a -
~
July 28,1997
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Question C86 McGuire Nuclear Station R9 Ex:m 1997 Bank Question: 193 Answer: A 1 Pt(s)
The Steam Generator Tube Rupture EOP, E 3, enclosure 6 (NC Pressure and Charging Control) directs operators to energize pressurizer heaters if the ruptured S/G level is decreasing and pressurizer level is greater than 25%
throughout the event (unless otherwise directed by ES 3.1). What is the basis for this action in E-37 A.
Maintain pressurizer saturation temperature equal to ruptured S/G pressure to minimize NC pressure transients.
H.
Maintain pressurizer saturation temperature equal to intact S/G pressure to minir..lze primary leakage into the S/G.
C.
Maintain pressurizer saturation temperature above ruptured S/G pressure to ensure S/G water does not flow into the NC system.
D.
Maintain pressurizer saturation temperature equal to intact S/G pressure to minimize NC pressure transients.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-EP E3 page 125 EP/1/A/5000/E 3 pages 40, SS LESSON:
OP-MC-EP-E3 TASK:
OBJECTIVE:
E 3 Objective 28 TIME:
KA:000038EA138(3.3*/3.3)
DATE:
6/5/97 Confidential QUES 193a July 28,1997
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l
Question C87 McGuire Nuclear Station R3 Ex:m 1997 i
Bank Question: 194 Answer: B
'
1 Pt(:i)
Unit 1 is operating at 100% power when the following indications are noted in the control room:
Pzr level = 23% and decreasing slowly
.
CHARGING LINE ABNORhtAL FLOW alarm
NC PUhiP SEALINJ LOW FLOW alann
.
"
REGEN llX LETDN 111 TEhiP alamt
LETDN HX OUTLET 111 TEhiP alarm
.
Which ONE (1) of the following abnormal procedures should be entered?
'
A.
AP/1/A5500/12 CASE I, " Loss of Letdown" B.
AP/1/A5500/12 CASE li," Loss of Charging" C.
AP/1/A5500/12 CASE III," Loss of Seal injection"
.
D.
AP/1/A5500/12 CASE IV " Charging Ileader Rupture" MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
AP/1/A/5500/12 pages 2,12,17 PID #htC-PS-NV 1 PID # hic PS-NV-5 LESSON:
OP-htC-PS NV TASK:
OBJECTIVE:
LPRO 10 TIME:
KA:000022EA201(3.2/3.8)
DATE:
6/5/97
Confidential QUES 194a July 28,1997
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Question C88 McGuire Nuclear Station R3 ECm 1997 Bank Question:196 Answer: B 1Pt(s)
Unit 1 is in the process of conducting a reactor startup. While withdrawin,
.
the control banks, SR NI channel N 31 fails. Which ONE (1) of tre
'
following actions is in accordance with Tech Specs requirements to proemi with the startup?
A.
Terminate the startup and insert all rods until N 31 is restored to operable status.
H.
Suspend all positive reactivity additions until d-31 is restored to operable status.
C.
Continue withdrawing shutdown hanks but do not proceed
'
beyond P-6 without resto*Ing N 31 to operable status.
,
,
D.
Continue the startup using an operable Wide Range Neutron
,
Flux Detector (Gamma-hietrics 51onitor) in place of the Inoperable SR channel.
.
h11SCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC IC-END pages 33,34
-
Tech Specs 3.3.1 Table 3.3.1 l
Tech Spec 3. 9.2
,.
Tech Spec Bases 3.9.2 LESSON:
OP-MC-IC-END TASK:
OBJECTIVE:
LPRO14B TIME:
KA:000032EK301(3.2/3.6) _
DATE:
6/5/97
-
Confidential QUES 196a July 28,1997 i.
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Question C89 McGuire Nuclear Station R9 Ex:m 1997 Bank Question: 198 Answer: A 1Pt(s)
The E 0, Reactor Trip or Safety injection, foldout page requires NCPs to be tripped if:
At least one NV or Ni pump is on, and
.
NC subcooling based on Core Exit T/Cs is less than or equal to 0*r
Which ONE (1) of the following statements is the EOP basis for the foldout page trquirement to trip NCPs A.
To prevent depleting NC Inventory and improve NC system depressurization.
H.
To prevent damage to NCPs due to two phase flow C.
To maintain NCPs for use in later EOPs when they are required to prevent inadequate core cooling.
D.
To minimize thermal shock to the pressurizer spray nozzle during depressurization.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP MC-EP-INTRO page 59 OP.MC EP-E0 page 47 -
LESSON:
OP MC-EP-E0 TASK:
OBJECTIVE:
E-0 Objective 11 TIME:
KA:000007EK301(4,0/4.6)
DATE:
6/5/97
-
Confidential QUES 198a July 28,1997
>
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Question C90 McGuire Nuclear Station R3 Ex:m 1997 Bank Question:199 Answer: B 1 Pt(s)
Which ONE (1) of the following descriptions is correct for the source of DC control power to the emergency diesel generators in the event of a station blackout?
A.
DC control power is supplied from the station 125 VDC vital instrument hus allowing the diesels to be started at any time.
B.
DC control power is supplied by dedicated 125 VDC hatteries which are only slied for a 30 minute duty cycle under load.
C.
DC control power is supplied from the 600/120 VAC auxillary power system through a rectifier.
D.
DC control power is not required to start the emergency diesel generators as the residual magnetism in the generator is suf11clent to provide field flashing.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC DG EPQ pages 8,9,10,11 LESSON:
OP.MC-DG EPQ TASK:
OBJECTIVE:
LPRO$
TIME:
KA:000058EK301(3.4a/3.7)
DATE:
6/5/97 f
Confidential QUES 199a July 28,1997
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Question C91 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 200 Answer: B 1Pt(s)
Unit 1 is shutdown in mode 4 with the following alignment of NCPs:
NCPs are powered from their nonnal sources
Buses TA amt TC are running off bus line 1 A
Buses TB and TD are running off bus line 1B e
Which ONE (1) of the following sequences describes status of the B NCP pump and bus TB when:
1. Power is lost to the nonnal 6900 V supply to bus TB due to a generator switchyard protective lockout.
2. Power is restored to the nomial 6900 V supply to bus TB aller the fault hn been cleared.
A.
1. NCP B continues to run as bus Til automatically fast transfers to the alternate power supply.
2. NCP B continues to run and bus Til automatically fast transfers back the normal power supply.
11.
1. NCP B continues to run as bus Til automatically fast transfei s to the alternate power supply.
2. Ilus Til does not automatically shift back to its normal supply.
C.
1. NCP B trips and bus Til automatically slow transfers to its alternate power supply.
2. Ilus TB does not automatically shift back to its normal power supply.
D.
1. NCP 11 continues to run as bus Til automatically fast transfers to the alternate power supply.
2. NCP 11 trips and bus TB automatically slow transfers back to the normal power supply.
MISCINF9:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC EL EP pages 37,39,123 LESSON:
OP-MC-El EP TASK:
OBJECTIVE:
LPRO 24 TIME:
KA:000056EA244(4.3/4.5)
DATE:
6/5/97 Confidential QUES 200a July 28,1997 e
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Question C92 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 222 Answer: B 1 Pt(s)
Which ONE (1) of the following is NOT a reliability classification of Diesel Generator "stan attempts" in accordance with Oh1P S-4, Diesel Generator Logbook?
A.
Valid start sueecss 11.
Invalid start failure C.
Valid start failure D.
luvalid start test MISCINFO:
RO ONLY SOURCE:
llank ADMOMPO4SMOD REFERENCES:
OMP S-4 pages 6,7 OMP S-4 Attachment i page 1
LESSON:
OP MC ADM OMP TASK:
'
OBJECTIVE:
LPSO 8 TIME:
KA:194001A106(3.4/3,4)
DATE:
6/11/97
.
Contidential QUES 222a July 28,1997
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Question C93 McGuire Nuclear Station R9 Ex:m 1997 Bank Question: 224 Answen B 1 Pt(s)
Which ONE (1) of the following Liquid Waste System tanks nonnally receive the melt water from the Containment Ice Condenser liaskets when in mode $7 A.
KCDT it.
VUCDT C.
NS and ND sumps D.
NCDT MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP hic-WE-WL page 19 LESSON:
OP hic-WE WL TASK:
OllJECTIVE:
LPRO 2 TIME:
KA:068000K107(2.7/2.9)
DATE:
6/12/97 Confidential QUES 224a July 28,1997
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Question C94 McGuire Nuclear Station R3 Ex:m 1997
,
Bank Question: 226 Answer: A 1Pt(s)
Unit 1 is operating in mode 4.
Given the following conditions:
1 A ND pump is operating
1NI.173A (Train A ND to A&D CL)is open
1NI 178B (Train B ND to C&D CL)is closed
What is the basis for the rertriction that total ND flow must be less than 2000 gpm?
A.
To ensure proper flow conL!tions through the Ni system check
<
'
valves.
B.
To prevent cavitation in the ND pumps due to vortex formation.
C.
To prevent draining the NC systn.i helow the reactor vessel nozzles and causing a loss of ND suction when dralning the NC system.
D.
To ensure that adequate NPSil is maintained to prevent vapor hinding of the pump.
MISClNFO:
RO ONLY SOURCE:
NEW
,
REFERENCES:
OP/1/A/6200/04 page 1 OP MC PS-NC paces 39.40
<
LESSON:
OP-MC PS-NC TASK:
OBJECTIVE:
LPRO 14 TIME:
KA:002000G010(3.4/3.9)
DATE:
6/12/97 Confidential QUES 226a July 28,1997
i
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)
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Question #95 McGuire Nuclear Station R9 Ex:m 1997 Bank Question: 228 Answer: B 1 Pt(s)
Unit 1 is in mode 6 and in the proecss of unlatching control rods. Which ONE (1) of the following limiting conditions requires the Operator at the Controls to immediately suspend all CORE ALTERATIONS in the Reactor Building in accordan:e with Tech Specs?
A.
Loss of one channel of SR Nis with both Gamma Metric SDMs in operation, 11.
Loss of direct communications hetween the control room and the refueling bridge (refueling station).
C.
Loss of the Fuelliandling Ventilation System.
D.
Time since entering mode 2 is 102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br />.
MISCINFO:
RO ONLY SOURCE:
NEW REFERENCES:
Tech Specs 3.9.5 OP MC Fil FC pages 29,31,33,35,37,39,4i LESSON:
OP MC-Fil FC TASK:
OllJECTIVE:
LPRO 7 TIMEt KA:034000G00$(2.6/3.5)
DATE:
6/12/97 Confidential QUES 228a July 28,1997 J
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.
)
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Question C96 McGuire Nuclear Station RD Ex:m 1997 Bank Question: 229 Answen A 1 Pt(s)
Which ONE (1) of the following statements describes LOCAL operation of the SM PORVs (S/G PORVs)?
j A.
Local operation of the SM PORVs is provided only for "A" and
"D" SM PORVs by isolating the VI supply from the Control Room Manual Loader and opening the supply from the Local Manual Loader, j
B.
Local operatio1 of the SM PORVs with the Local Manual Loader may be established by overriding the air pilot valve on each SM PORV.
C.
Local operation of the SM PORVs is provided by isolating the VI supply from the ' ontrol Room Manual Loader and opening the supply from the Local Manual Loader.
D.
Local operation of the "B" nnd "C" SM PORVs is provided by Local Valve Operator Extensions (reach rods) attached to the valve actuators in the Exterior Doghouse.
MISCINFO:
RO ONLY SOURCE:
STMSM047 MOD REFERENCES:
OP MC-STM SM page 17,18 LESSON:
OP MC STM-SM TASK:
OBJECTIVE:
LPRO 9 TIME:
KA:039000K102(3.3/3.3)
DATP.:
6/12/97
<
Confidential QUES 229a July 28,1997 L
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-)
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Question C97 McGuire Nuclear Station RD Exam 1997 Bank Question: 231 Answer: C 1Pt(s)
During perfonnance of PT/2/A/4200/31E, Upper Containment Personnel Airlock Leak Rate Test, by the Operation Test Group, two steps need to be perfonned out of sequence. After deliberation by the Test Team Supervisor and the Shift Supervisor, it is determined that this deviation frora the procedure sequence is needed and will not alter the intent of the procedure.
Which ONE (1) of the following statements describes the required action (s)
required for performing these procedural steps out of sequence in accordance with OMP 4-17
A.
OSM approval documented within the REMARKS SECTION of the Procedure Process Record.
B.
Test Team approval documented within the REMARKS SECTION of the procedure and a copy of the " SUBMITTED" procedure change attached.
C.
An explanation of the sequence deviation documented within the remarks section of the Procedure Process Record and initialed by the Test Team Supervisor and the Licensed Operator approving the change.
D.
An explanation of the sequence deviation documented within the procedure and initialed by the OSM approving the change, the Test Team Supervisor and the Shift Supervisor recommending the change.
MISCINFO:
RO&SRO SOURCE:
BANK ADMOMP028 REFERENCES:
OMP 4-1 page 13 LESSON:
OP-MC-ADM-OP TASK:
OBJECTIVE:
LPRO 4 TIME:
KA:194001 A102(4.l*/3.9)
DATE:
6/12/97 Confidential QUES 231a July 28,1997
]
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Question C98 McGuire Nuclear Station R3 Ex:m 1997 Bank Question: 232 Answer: A 1Pt(s)
Which ONE (1) of the following actions is the first action required per FR.
S.1, Response to Nuclear Power Generation /ATWS, if the main turbine will NOT trip?
A.
Place the turbine in manual and fast close the governor valves B.
Close the A1SIVs and htSIV bypass valves C.
Stop the EllC pumps-D.
hianually initiate a 51ain Steam Line isolation 511SCINFO:
RO&SRO SOURCE:
RO94 REFERENCES:
EP/l/N5000/FRS S.1 page 2 OP MC EP FRS page 23 LESSON:
OP-MC-EP-FR TASK:
OBJECTIVE:
FR-S.1 Objective 4 TihlE:
KA:000029G010(4.5*/4.5*)
DATE:
6/13/97 Confidential QUES 232a July 28,1997 m
II
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Question C99 McGuire Nuclear Station RJ Ex:m 1997 Bank Question: 234 Answor: A 1Pt(s)
Which ONE (1) of the following conditions could occur if compensating voltage was lost on Intermediate Range Ni channel N357 A.
May be unable to block P-6 prior to reaching SR high levcl trip due to lnsufficient overlap during a reactor startup.
II.
Permissive P-6 will be reccited earlier, et a lower SR level during a shutdown.
C.
Indicated N 35 SUR will be higher than N-36 SUR throughout the intermediate range during a reactor startup.
D.
Indicated N-35 SUR will be higher than source range SUlt during a reactor shutdown.
MISCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
OP-MC-IC-ENB page 25,27,51 LESSON:
OP-MC lC-END TASK:
OBJECTIVE:
LPRO 7 TIME:
KA: 000033EA211(3.1/3.4)
DATE:
7/22/97 Confidential Ques 234a July 28,1997
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%
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Question 0100 McGuire Nuclear Station RD Ex:m 1997 Bank Question: 239 Answer: C 1 Pt(s)
Unit 1 is operating at 100% power. IAE personnel are calibrating the l A
'
Channel 1 NCP flow meter which is generating numerous and frequent alarms in the control room.
Which ONE (1) of the following operator practices is in accordance with htSD 5897 A.
No communication of this alarm is required since it is related to
testing and the alarm is expected.
II.
The first time the annunciator alarms during the shift,it should be communicated to another assigned control room person. If agreed upon by two lleensed operators, no further communication of the alarm is required.
C.
The annunciator should be communicated to another assigned control room person.
With Control Room SRO approval, annunciators associated with a particular activity can be excepted from being announced.
D.
The annunciator must he communicated to another assigned control room person with no exception, hilSCINFO:
RO&SRO SOURCE:
NEW REFERENCES:
htSD 589 page 12 LESSON:
OP htC-ADhi DIR TASK:
OBJECTIVE:
LPRO 7 TIhlE:
KA: 194001 A105(3,6/3,8)
DATE:
7/23/97 Confidential Ques 239a July 28,1997