IR 05000289/1989019
| ML20247M936 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 09/14/1989 |
| From: | Eselgroth P, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20247M905 | List: |
| References | |
| 50-289-89-19OL, NUDOCS 8909260085 | |
| Download: ML20247M936 (104) | |
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U. S. NUCLEAR. REGULATORY COMMISSION, REGION I OPERATOR LICENSING EXAMINATION REPORT .
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' EXAMINAi' ION REPORT N /89-19(OL);
o.- cFACILITY. DOCKET N FACILITYLLICENSE N D?R-50 LICENSEE: GPU Nuclear Corporation P. O. Box 480 Middletown, PA. 17057
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FACILITY: Three Mile Island, Unit No. 1
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EXAMINATION'DATE: August 10, 1989 CHIEF EXAMINER: N-> CMF9
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Bar p f. Norris Date Senior Operations Engineer APPROVED BY: . /// b ~
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[fyPetefW. EseJgftoth, Chief Da'te
/ PWR Section, Operations Branch SUMMARY: A written examination was administered in the Region I Office to a Reactor Operator candidate (RO) who had previously
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failed ~that portion of the examination. The candidate passed the L-~
examination and was issued a license.
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TRC/71')20f7
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e U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 1 FACILITY: Three Mile Island 1 REACTOR TYPE: PWR-B&W177 DATE ADMINISTERED: 89/08/10 CANDIDATE: ad /SM '/
INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write answers on one side only. S le question sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 25.00 25.00 88/100 88.0 % 1. REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
27.00 27.00 % EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
48.00 48.00 % PLANT SYSTEMS (38%) AND PLANT-W1DE GENERIC RESPONSIBILITIES (10%)
100.00 % TOTALS I'INAL GRADE All work done on this examination is my own. I have neither given nor received ai Candidate's Signature
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS
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During the administration of this examination the following rules apply: !
1. Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . After the examination has been completed, you must sign the statement on the cover sheet ind1cating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examinatio . Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil only to facilitate legible reproduction .
l 5. Print your name in the blank provided in the upper right-hand corner of the examination cover shee . Write your answers on the examination question page. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAG . Print your name in the upper right-hand corner of the first page of each section of your examination question pages. Initial each pag . The point value for each question is 1.00 point . NOTE: Partial credit will NOT be given on multiple choice question .If the intent of a question is unclear, ask questions of the examiner onl i 11. When turning in your examination, assemble the completed examination with examination questions, examination aids and all scrap pape .To pass the examination, you must achieve an overall grade of 80% or greater and at least 70% in each categor . There is a time limit of 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for completion of the examinatio ... t '**
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3 SECTION IS INTENTIONALLY MISSING
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CANDIDATE PASSED TIE FUNDAMENTAL EXA!1INATION l
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. 4 DERGENCY AND ABNORMAL PIANT EVOLUTIONS (27%)
. QUESTION 2.01 (1.00) i
'Which one of the following correctly describes the behavior of RCS pressure during a Small Break LOCA occurrence, WITHOUT feedwater available? Assume ESAS does NOT actuat Pressure decreases slowly, then drops very rapidly when the OTSGs have boiled dr b. . Pressure initially decreases, then rapidly increases when the OTSGs have boiled dr Pressure initially decreases, then continues to decrease, but at a much slower rate, when the OTSGs have boiled dr Pressure decreases slowly until it levels off somewhere above
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ESAS actuation pressur J
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5- EMERGENCY- AND ABNORHE PLANT EVOLUTIONS (27%)
. QUESTION -2.02 '(1.00)
Which one of the following'is correct regarding the HPI. Throttling Criteria,' which are found in Abnormal Transient Procedure 1210-10,
" Abnormal Transients Rules, Guides, and Graphs"? The throttling criterion.to prevent pump runout includes injection line flow AND seal injection flow, HPI must be throttled if LPI flow has been greater than 100 GPM in each line and stable for'15 minutes, HU-V-36 and HU-V-37 must be opened before HPI flow drops below 500 gpm/ pum Pressurizer level must be at least 80 inches and stable (or 4 increasing) prior to throttling HP l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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.. 6 1 EHERGENCY AND ABNORMAL PIANT EVOLUTIONS (27%)
QUESTION 2.03 (1.00)
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.According to AP 1203-15, " Loss of R.C. Makeup," if letdown flow has l- been : isolated, it must be restored GRADUALLY, to minimize the possibility ofs: Flow oscillations in the letdown coole . Pressure surges in the letdown coole Thermal shock to the letdown coole Water hammer in the letdown coole (***** CATEGORY 2 CONTINUED ON NEXT PAGE "*")
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QUESTION 2.04 (1.00)
Assume the' unit is at full load. RC-RV-2 (pressurizer pilot operated relief valve).has OPENED for ten seconds and subsequently shu Proper reseating.of the valve (with no leakage) can'be MOST POSITIVELY
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verified by observation of: Control room position' indicating lights for.RC-RV-2, immediately after the even The behavior of pressurizer level for approximately ten
-minutes after the event, c. 'The behavior of RCDT temperature for approximately one hour after the even d. .The' behavior of tailpipe. differential temperature approximately two hours after the even l
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QUESTION- 2.05 (1.00)-
Which one of the below-listed radiation monitor instruments is ,
required by the technical specifications to be operable during refueling operations? RM-A2 (RB Atmosphere) RM-G7'(Fuel Handling Bridge) RM-G5 (RB Personnel Access Door)
l RM-G8 (RB High Range)
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' QUESTION 2.06- (1.00)
Select the BEST answers from the choices listed belo I The reason for the Two-Hour Backup Instrument Air System (Bottled
" Air) is to provide dry compressed air for operation of components within th (1) system and the (2) system,.
in'the event both the Instrument Air and Backup Instrument Air systems become unavailabl CHOICES: ANSWERS: I Decay Heat Removal Emergency Feedwater Intermediate Closed Cooling Main Teedwater Main Steam Makeup & Purification Nuclear Service closed Cooling (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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QUESTION 2.07 (1.00)
If any personnel are working in the overhead of the relay room, then another person must be continuously stationed on the floor to Provide communications to'the control room, in case of an emergency involving one or more of the worker Act'as a fire watch, since the CO2 fire suppression system must be disabled if workers are in the overhea Cause injection of CO2 into the room to be delayed, if an automatic actuation of the system occur Warn personnel entering the room of the potential hazards which exist due to workers overhea (***** ChTEGORY 2 CONTINUED ON NEXT PAGE *****)
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11-A DERGENCY AND' ABNORMAL PLANT EVOLUTIONS (27%)-
QUESTION- 2.08 (1.00)-
According to ATP 1210-5, "OTSG Tube Leak / Rupture," the' fuel pin compression' limits (fuel-pin-in-compression curve) must be adhered to
.UNLESS the tube' leak is greater thans gp b. -30 gp gp gp i
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~~ 12 DiERGENCY AND ABNOPEAL PIANT EVOLUTIONS (27%)
QUESTION 2.09 (1.00)
If RM-L7 reaches its high-level setpoint during a routine radioactive liquid release from Waste Evaporator Condensate Storage Tank (WECST)
11A, then Liquid Waste Discharge Isolation Valve WDL-257 wills Automatically throttle back to a position which allows a lower discharge flow, until flow is low enough that the PM-L7 alarm clear Automatically shut, completely shutting off the discharge flow from the WECST, and will reopen automatically when the RM-L7 alarm clear Automatically shut, completely shutting off.the discharge flow from the WECST, and will remain shut until reset by the
! operator, after the R:1-L7 alarm clears, Remain unaffected by the Ril-L7 alarm, because RM-L7 is not a Technical Specification-required instrumen i i
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QUESTION- 2.10 (1.00)
According to EP'1202-29, " Pressurizer System Failure," if no_ _
pressurizer heaters are available, then the spray block valve RC-V-3
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-must be shut'to Prevent thermal shock to the spray lin ' b' . Ensure the Boron concentration in the pressurizer does not change during the plant. shutdow , Maintain spray line temperature within 250F of pressurizer temperatur ~
d. -Preserve the mass of hot water stored in the pressurize (" * " CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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- EMERGENCY AND ABNOR1%L PLANT EVOLUTIONS-(27%).
QUESTION -2.11 (1.00)
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Assuming all other conditions are normal, the radiation monitoring equipment most likely to provide the earliest indication of a failed '
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fuel element ist- RM-A2 RB Atmosphere Monitor- RM-G19 RCP Seal Return Monitor RM-L1 RCS. Letdown Monitor RM-G21 RB' Sump Monitor 1-l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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QUESTION 2.12' (1.00).
Using the preferred emergency boration path per OP 1103-4, " Soluble Poison
. Concentration Control,". Sect. 3.10, " Emergency Boration Frotn Boric Acid Hix Tank CA-T1," confirmation that boric acid solution is being injected at approximately 20 gpm is made by checking then a. Rate of rise of' liquid level in the makeup tank, and verifying CA-T1 liquid level decreas ' b. Total flow indicated on batch controller HU-FT 12, and verifying CA-T1 liquid level decreas c. M al flow indicated'on makeup flow indicator MU-F7 24, and verifying makeup tank liquid level decreas d. Fotal flou indicated on makeup flow indicater HU-TT 24, and the total flow indicated on batch controller HU-TT 1 ( * * " * CATEGORY 2 CONTINUED ON NEXT PAGE **"* )
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. 2. ' DERGENCY AND ABN6AHAL PLANT EVOLUTIONS-(27%)
QUESTION 2.13 (1.00)
According to EP 1202-08, "CRD Equipment Failures - CRD Malfunction-Action," Sect. C, " Stuck Rod," the operator should immediately attempt to move the stuck rod by:
l a. first INSERTING the rod a short distance, and then WITHDRAWING L it.
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- c. inserting the rod ONLY.
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' QUESTION 2.14 (1.00)
Assume the unit is at 67% power with THREE reactor coolant pumps in operation and the diamond station in HAND, when a single control rod drops to its full insertion positio According to EP 1202-08, "CRD Equipment Failures - CRD Malfunction Action,"
Sect. B, " Dropped Rod," the ICS wills
. Automatically run the plant back to 478 HWe, and no further action is require Automatically run the plant back to 360 MWe, and no further l- action is required, Automatically run the plent back to 478 HWe, and then the operator must manually reduce load to below 360 MW Not respond to reduce power, and the operator must immediately run power back to below 360 HWe.
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. EMERGENCY AND ABNORMAL PIANT EVOLUTR'N_S ( 27%,) :
QUESTION 2.15 (1.00)
According to EP 1202-08, "CRD Equipment Failures - CRD Malfunction Action," Sect. D, " Motor Fault," 'thich one of the following 'is an ,
immediate manual action required to be_taken in the event of an uncontrolled withdrawal of a group of rods, with no demand for out motion present? Verify that the CRD operators console is'in automati b. ' Select run spee c. Attempt to transfer the affected group to the auxiliary power suppl Select sequence. overrid .
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QUESTION.- -2.16L (1.00)-
.According to ATP 1210-10, " Abnormal Transient Rules, Guides, &
~ Graphs," Sect 2.8, "RCS Natural Circulation Verification," which one of the choices below IS NOT indicative of proper natural circulation, 30 minutes after loss of all reactor coolant pumps (RCPs)?- Assume that prior to. loss of the RCPs, the reactor had been operating at full power for 3 month a. _RCS Delta-T increases to approximately 12F to 15F, and
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b. .Incore thermocouple. temperatures stabilize, and are tracking T Cold leg temperatures approach saturation for secondary side pressur .
! Steam flow and feed flow indications demonstrate that heat is-being removed from the OTSG j
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QUESTION' ~2.17 (1.00)
According to ATP 1210-10, " Abnormal Transients Rules, Guides, &
Graphs," Sect. 2.10, " Feeding a Dry OTSG," which one of the following-OTSG pressures would indicate that the OTSG is dry, assuming that its h startup range level is zero, and its associated loop Tc temperature is 540F, psi psig, psig, psi ,
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.GZl QUESTION 2.18 (1.00)
Which one of the belDH systems Will NOT automatically actuate in the event of a fire in the Air Intake Tunnel? Fire pumps start Sprinkler system actuates Fire dampers close
'. d . Deluge sump pump starts (+++++ CATEGORY 2 CONTINUED ON NEXT PAGE ***++)
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[- -QUESTION 2.1'9 (l'00)'
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LThe. vital batteries are capable of sustaining design a load for-approximately -
- - .5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
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6 1 .5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> d. ,13.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> ,
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L2. ' DERGENCY AND ABNORMAL PIANT EVOLUTIONS (27%).
' QUESTION 2.20' (1.00)
Assume normal full power operation with no known malfunctions or abnormalitie In accordance with AP 1203-16, Section 4.0, " Reactor Coolant Pump and Motor Malfunction Pump and Motor Vibration," if excessive RCP shaft vibration is detected, then the affected RCP must be tripped immediately after reducing reactor power to:
. percen percen percen d .' 75 percen t (***** CATEGORY 2 CONTINUED ON NEXT PAGE **"* )
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QUESTION 2.21 (1.00)
Assume the unit is at 65% load with 4 RCPs operating, ICS in full'
automatic, with no abnormalities known.to exist, when symptoms become evident which indicate the occurrence of a total loss of ICS Hand and Auto power. As soon as the problem is identified (diagnosed), why does EP 1202-40, " Loss of ICS Hand & Auto Power," caution the operator to NOT select alternate ICS/NNI Power or otherwise attempt to restore power? The excessive current drawn by the individual controllers, all of which are in an imbalance condition, will cause further loss of control powe The OTSGs will experience an overfeed condition, because the main and startup feedwater valves will stroke fully ope An uncontrolled rod withdrawal or insertion transient will result from the large neutron error signal which will be presen The letdown heat exchanger will experience an excessive thermal transient, as the letdown system unisolate '
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QUESTION 2.22 (1.00)
Which one of the follow!ng describes the automatic action which should occur upon the receipt of a "HIGH" alarm on Control Room Air' Monitor (gas channel), M-A1, assuming normal operation of all systems
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and components prior to the RM-Al alarm? Centrolled Access Area Damper AH-D-28 closes, and Outside Air Relief Damper AH-D-39 open b' . Crintrolled Access Area Damper AH-D-28 opens, and Outside Air Relief Damper AH-D-39 closes, Return Air Damper AH-D-36 opens, and Controlled Access Area Damper AH-D-28 close Return Air Damper AH-D-36 closes, and Controlled Access Area Damper AH-D-28 Damper open .
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i QUESTION.- 2.23 (1.00) l According to EP 1202-12, " Excessive Radiation Levels,"~which one of
' the following will NOT cause the Panalam window labeled " Radiation Level Hi" to annunciate? Assume any annunciator alarms received are immediately acknowledged and reset as appropriat . An " ALERT" alarm on Fuel Handling Building Ventilation Duct Monitor RH-A4, with no_other alarms occurrin An " ALERT" alarm on Control Room Air Honitor RM-Al 30 seconds after a previous " ALERT" alarm on the same channel (RM-A1).
c. ~A "HIGH" alarm on Control Room Air Honitor RH-Al 30 seconds after an " ALERT" alarm on the same' channel (RH-A1). An " ALERT" alarm on Fuel Handling Building Ventilation Duct Monitor RM-A4 30 seconds after an " ALERT" alarm on Reactor Building Purge Duct monitor RM-A .
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- ( 27*5 )
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l QUESTION 2.24 (1.00).
.While performing ATP 1210-5, "OTSG Tube Leak / Rupture," the Subcooling l- Margin of the RCS is minimized in order to reduce the Differential pressure across the leaking / ruptured tube, Affected OTSG's shell-to-tube differential temperatur c. : Possibility of lifting main steam safety valve Time which is required for cooldown of the RC .
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. QUESTION 2.25 (1.00) l
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Assuming initial operation at 100%, which one of the following is an action required.to be immediately performed by the operator in-accordance with EP 1202-9A, " Loss of.'A' DC Distribution System"? Close the DC tie switches to provide an alternate source of DC powe Manually trip the generator exciter breake Transfer the A, C, and E Inverter loads to the regulating transforme Reduce power to within the reduced capacity of the condensate system.
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- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (2M)..
.p QUESTION 2.26 (1.00)-
According to EP 1202-35, " Loss of Decay Heat Removal System," th operator must immediately ensure valves DH-V-1, DH-V-2, and DH-V-3 (suction line valves from Loop B Hot Leg) are SHUT if RCS pressure increases to psig, b .- 350 psig.- psi d.. 450 psig.
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QUESTION 2.27 (1.00)
According to ATP 1210-1, " Reactor Trip," after attempting to mar.ually trip the reactor, if none of Groups 1 through 7 tripped, then the FIRST thing the operator is required to do is Emergency borat :' b.- Trip IG-02 and IL-0 Commence manual insertion of control rod Initiate HPI and maximize letdow .e i
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' PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC'
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QUESTION 3.0 (1.00).
-Which one of the following statements is accurate concerning the OTSG's? Primary and secondary side blowdown (during plant heatup) is accomplished by means of drain connections near the lower tubeshee l The operating range instruments will provide indication that the aspirating ports are floode The auxiliary feedwater header penetrates near the top of the.OTSG shell and sprays the feedwater on the upper cylindrical baffl d. The full range level instruments are compensated for containment temperature change (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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QUESTION, 3.02 (1.00)
Which one of the following is correct concerning the Reactor Coolant Pump (RCP) seal water syste Seal water is forced between a rubbing face seal and a' runne on the number one seal.- Seal' water enters the seal package between the thermal barrier heat exchanger and the lower radial bearin The seal water pressure differential ensures.the faces of the number 2 seal do not ru ' Seal differential pressure across number 2 seal is a result of the number-1 seal leakoff pressure and containment atmospheri pressure.
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- 33 PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC-
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' QUESTION '3.03 (1.00)
Which one of the following would be the RCS flow response in the 'A'
loop following the stopping of RC-P-1A? The measured loop 'A' flow is 50% of the previous loop flow rat The measured loop flow rate decreases to 44% of the previous loop flow rat The actual flow rate of the remaining pump is equal to its previous flow rat I The actual flow rate from the remaining pump increases to twice its previous flow rate.
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QUESTION- 3 . 04 ,- (1.00)
Upon a loss of all Reactor Coolant Pumps,'the Emergency Feedwater System will control at which one of the following operating levels?
a. 25%
b. 450 c. 501 d. 95%
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QUESTIO .05 ~(1.00)
Which set of valves below,. associated with the Emergency Feedwater
. System, fails _OPEN upon a loss of 120 vdc power?
a. -MS-V-13 A/B EFW pump steam inlet valv EF-V-1 A/B EFW pump suction cross-ti '
c._ HS-V-2 A/B HS stop valves to Turbine EFW pump from OTSGs MS-V-10 A/B lts bypass for HS-13 A/B I
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-L . QUESTION 3.06 (l.00)
Plant' Conditions:
Total loss of Reactor Coolant Pumps.with a Reactor Trip. OTSGs are
~being feed by ErW but have not reached the proper level setpoint. OTSG pressure is 800 psig pressure and slowly decreasing. All remaining systems are in automatic control and responding normally with reactor core temperatures decreasing as expecte Which one of the following is the correct Emergency Feedwater throttling criteria for the condition described above?-
a.. EFW flow should be throttled as needed to raise OTSG to pressure within 100 psig of the turbine bypass setpoint regardless of the level setpoin ErW flow should be maintained at > 450 gpm until'the proper OTSG level is achieved, then throttled to a minimum of 100 gp EFW flow is maintained at the maximum attainable rate until the proper level is attained, then throttled to a minimum of 200 gpm I ErW flow is to be no greater than 225 gpm total until proper level setpoints are established, then throttled to maintain OTSG pressure at 900 psi ( * " * * CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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QUESTION .3.07 ( l .00 )'
Following a 1600#.esas actuation, which one of the following is the proper Makeup System response?
a. . Makeup ~is-isolated and all' flow goes to the injection nozzle Makeup and' seal injection are-isolate . Makeup flow is reduced to only the amount needed to prevent thermal: shock'to the normal makeup nozzles, Makeup continues to operate.at an increased flow to regain pressurizer-level.
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l - PIANT SYSTEMS (38%)'AND PLANT-WIDE GENERI RESPONSIBILITIES (10%)
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QUESTION 3.081 (1.00)
Which one of the following chemicals is'added directly to the Make-up Tank (HU-T-1)? Hydrogen Hydrazine Lithium Hydroxide d.- Boric acid
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[ QUESTION- 3.09 ~(1.00)-
Which one of the following valves is NOT affected by the Reactor Trip-Isolation (RTI) portion ofa the ESAS system?
1 MU-V-3 Letdown isolation outside Reactor Bld WDG-V-4 . Waste Gas line isolation outside' Reactor Bld CA-V-l' Steam Space' sample inside Reactor Bldg isolatio AH-V-1A, Purge' exhaust isolation outside Reactor Bld (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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QUESTION- 3.10 (1.00)-
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Using the following scenario, determine which one of the choices below is the sequence for ES system actuatio ES initiates block loading, the Diesel Generator starts but does not load, W trips all equipment except block 1 and Non-ES equipment is locked out. Diesel generator breaker closing reinitiates block loading, after 2.5 second timer times'out.
l Undervoltage followed by E ES simultaneous with undervoltag c. 'Homentary undervoltage followed by E ES followed by undervoltag .
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QUESTION .3.11 (1.00)
Using the'following plant conditions, which one of the ESAS levels has actuated?
RCS pressure at 750 psig, containment pressure at 2.0 psig, pressurizer level at 5 inche Reactor Building isolation and coolin High pressure injection, Low pressure injectio Partial Containment Isolation and Building spra (*"" CATEGORY 3 CONTINUED ON NEXT PAGE ""* )
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. QUESTION ' 3.12 (1.00)
Which one.of the following conditions would result in an Auto-Inhibit actuation being generated in the Rod Control Logic?
a. Safety Rod Groups at the out limi b. Asymmetric fault with power level at'50%,.
I c. A startup rate of 2.0 DPH in the Source rang 'd. High neutron error signal (2.5%).
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QUESTION 3.13 (1.00)
The Technical Specificationallowable RCS pressL;a and temperature limit for control rod drive operation is based one Brittle fracture considerations for the drive mechanism Assuring a hy;draulic buffer action during a reactor tri Fuel pin-in-compression limitation Electro-magnetic coupling of the drive motor to the segment arms.
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QUESTION 3.14 (1.00)
Which one of the speeds listed below is provided by the jog speed-motor of the Rod Control System? inches / mi i s inches / mi l- inches / mi g inches / min.
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QUESTIO .15 .(1.00)
Multiple Choice The source range (NI-1 and NI-2)' backup high voltage cutoff is actuated bys Power range channels NI-5 and NI-6 OR power range channels NI-7 and NI-8 greater than or equal to 10% full powe Power range channel NI-5 or NI-6 AND power range channels NI-7 or NI-8 greater than or equal to 10% full powe Power range channels NI-5 and NI-6 OR power range channels NI-7 and NI-B greater than or equal to 3% full powe Power range channel NI-5 or NI-6 AND power range channels NI-7 or NI-8 greater than or equal to St. full powe .
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. .. 46 EW9fT simir,G (38%) AND PLANT-WIDE GENERIC RF5runmitsILITIES (10%)
QUESTION 3.16 (1.99)
Which one of the following groups of indications or conditions would be used by the reactor operator to DECIARE the reactor critical -
during a startup? - Positive SUR, stable source range count rate, no positive reactivity additio Zero SUR, increasing source range count rate, positive reactivity additio Zero SUR, decreasing source range count rate, no positive reactivity additio Positive SUR, increasing source range count rate, no positive reactivity additio ~ *
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QUESTION 3.17 (1.00)
Which one of the Nuclear Instrumentation outputs below is NOT used to generate control functions within the ICS?
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i QUESTIOtt: 3.18 (1.00) 3 Which one of the following interlocks associated with the Makeup and l Purification system PERMITS positioning of the Three-way Valve, MLi-V-8,"
to the bleed position and opening of the flow control valve, MLi-V-10,'
simultaneously?
a. Control Rod group 6 is 95% withdraw b. Low level alarm (66") for the make-up' tan c. Low pressure alarm (18 psig) for the make-up tan d. Pushing the batch controller START pushbutto Yq
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l QUESTION 3.19- (1.00)
Which one of the following will automatically terminate a radioactive gaseous release? Waste' gas compressor tri Low pressure in the waste gas decay tan High radiation level on the ventilation stac Low vent header pressur .
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QUESTION 3.20 (1.00)
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If Reactor Coolant Temperature is lowered below 275 F, the ,
pressure in the Core Flood Tanks is allowed to remain at 600 psig providing which of the following is done?
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' High pressure injection valves arti shut and deenergized! Set the PORV, RC-RV-2, setpoint to 485 psi Reduce Core Flood Tank N2 pressure to 485 psig, Lower Core Flood Tank temperature to below 200 .:
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QUESTION 3.21 (2.00)
Which one of the following is the proper control sequence for the RAeactor Building Spray system? Spray pumps are given a signal to start at 4 psig, and the valves open et 30 psig, The spray valves open at 4 spig, and the pumps get a signal to start at 30 psi The spray valves open at 4 psig, with the pumps getting a permissive signal at 30 psig and start one minute late . Spray pumps are given a start permissive at 4 psig, and the valves open and pump start occurs at 30 psi ,
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QUESTION 3.22 (1.00)
Which one of the following statements correctly describes plant
,W behavior during a reactor startup, where power is being raised above the point of adding heat? Assume a linear reactor power increase to about 3% power with initial Tave value of 525 F?
e a. Tave will not rise above 525 deg ..i b. Tave will rise and the steam te:aperature will tend to remain constant at the zero power valu c. The OTSGs will remain at saturated conditions and no superheat will be adde d. The OTSGs will be superheated at 3% power and superheat will rise proportionally with powe .
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QUESTION 3.23 (1.00)
Which one of the following is correct concerning the Main Steam ;
Isolation Valves-(MSIV)?:
" Local operation of the valve can be controlled by a jog open/ closed pushbutton controlle Valve operation from the control room is limited to the open, close,
' test, and stop mode Valve main' disk opening is motor controlled with the disk being held open by steam flo ~ d. . Equalization of pressure across the HSIVs is accomplished by the opening of. internal ports during the first several inches of operator movement toward ope .
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QUESTION 3.24 (1.00)
Which one of the following times represents the closest approximate amount of time it would take for the Spent Fuel Pools -
temperatures to increase to 180 F from the normal control value of 135 F after failure of both trains of cooling? Assume the maximum
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fuel heat load is in the poo . a. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> c. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> d. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
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QUESTION 3.25 (1.00)
Nhich one of the following is NOT a method used to prevent inadvertent draining of Spent Fuel Pool "A".
a. Discharge piping termination at or above the level of the ,
fuel grid b. Suction piping termination at or above the level of the fuel grids, c. Syphon break valve on the drain line to limit draining to le feet above the fuel grid d. Automatic pressure release valve on the pool separation gate seals to allow cross-connection to maintain inventor ,
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QUESTION- 3.26 (1.00) fj- g Which one of the following is the indication of an' input mismatch on
. the Smart Auto Signal Selector (SASS)? Y Computer alarm #2278, " SASS actuation". The green " SASS ON" IED will be off on the SASS module._ _ The red " SASS TRIP" LEDs are lit on the SASS module, Console pushbutton is locked ou .
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QUESTION 3.27 (1.00)
Which one.of the following is the correct method to verify, from the Control Room, Emergency Feedwater system flow when low in the indicating range? Monitor all channels of control room indication and use the average flow, Add let of control room meter full scale reading to obtain proper indicatio Read control roem Emergency Feedwater flow directly and control accordingl Use control room OTSG pressure and level to verify flo .
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side DC distribution system? The engine would not star .[ The engine would start and come up to speed, but the generator would not energiz , The engine would start and come up to speed and voltage, but not tie to the AC bu The engine would start but trip on overspee i a
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QUESTION 3.29 (1.00) ;
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Which one of the.following is the function of the key locked "69' '~
Bypass switches" when placed in the "Deergency" position? Enable both local and control room operation of the control .; Transfer control functions to the Remote Shutdown Pane , Prevent restarting of equipment'after an undervoltage . @
conditio Auto start features and ES interlocks are made inoperabl ' .
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60 PLANT SYSTEMS (38%) A)O PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
QUESTION 3.30 (1.00)
Following an undervoltage condition, which one of the following will NOT prevent automatic closure of an Emergency Diesel Generator output breaker to a 4160 VAC ES bus? Breaker control switch in pull-to-loc Synchroscope switch of B/1D(1E) not rese Diesel ready matrix (81-59 matrix) not satisfied.
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\ PIANT SYSTEMS (38%) AND PIANT-WIDE GENERIC RESPONSIBILITIES I10%)
QUESTION 3.31 (1.00)
Which one of the following automatically occurs when the Reactor Protection System is placed in " Shutdown Bypass?" All trips on the affected channel are bypasse The nuclear overpower trip is reduced to 5% or les The high pressure setpoint is reduced to 1720 psig, The RCS Outlet Temperature setpoint is reduce to 585 F.
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62 PIANT SYSTEMS (38%) AND PLANTcWIDE GENERIC RESPONSIBILITIES (10%)
QUESTION 3.32 (1.00)
Which one of the following is a major source of Hydrogen release to the containment after a IDCA? Zirconium-water reactio Electrolytic decomposition of water during LPI recirculatio Release of dissolved hydrogen in the RCS during the LOC Decomposition of oil used for equipment lubricatio .'
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63 PLANT SYSTEMS (38%) AND PIANT-WIDE GENERIC RESPONSIBILITIES (10%)
QUESTION 3.33 (1.00)
Which one of the following describes the lineup used to inject cooling water into the RCS after the BNST has emptied, following a small-break IOCA. Assume RCS pressure is 300 psi The DHR pumps are lined up to draw a suction on the i RB Surp and discharge to the Reactor Coolant System via the
>
LPI injection nozzle RCS Hot Leg and discharge to the spray ring then the makeup (HPI) pumps get the water from the sump and dischage it to the RCS injection nozzle RB Sump and discharge to the suction of the makeup (HPI)
pumps, which then inject into the RC RCS Hot Leg and discharge to the RCS via the makeup pump suction and the in$ection nozzle ( * * * " CATEGORY 3 CONTINUED ON NEXT PAGE *"** )
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64 PIANT SYSTEMS (38%) AND PIANT-WIDE mm'RIC RESPOieIBILITIES (10%)
. i QUESTION 3.34 (1.00)
Which one of the following Decay Heat valves provides automatic overpressure '
protection for the Decay Heat System? DHV-2 Inside containment suction isolation valve DHV-3 Outside containment suction isolation valve DHV-4A Outside containment return isolation valve DHV-63 Inside containment auxiliary spray isolation valve
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' PLANT SYSTEMS (38%) AND PIANT-WIDE GENERIC RESPONSIBILITIES (10%)
QUESTION 3.35 (1.00)
Which one the following is correct concerning the Intermediate Closed Cooling system? Low level in the surge tank will trip the normal duty pump and initiate makeu A simultaneous ES and W condition on D and E bus locks out ICCW pump On an Emergency Safeguards signal, the cooling water supply valves to the Control Rod Drive Motors are closed and the booster pumps are stoppe The standby ICCW pump will automatically start based on low system pressur <
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66 PLANT BYsaariS (38%) AND PIANT-WIDE GDIERIC RESPONSIBILITIES (10%)
QUESTION 3.36 (1.00)
Which one of the following is the positive bias applied to the Turbine
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Bypass. Valves following a reactor trip? , psi i psi psi psi
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67 PIANT SYSTEMS (38%) AND PIANT-WIDE GENERIC RESPONSIBILITIES (10%)
QUESTION 3.37 (1.00)
Which one of the following is the correct response of the Turbine Bypass Valves to a reduction in the main condenser pressure from normal operating condenser pressure to 20" of vacuum?
, Valve capacity is reduced to 15% and the excess steam load is vented via the OSTG safetie Valves are latched closed and the atmospheric dusp valves operate to limit pressur Valve opening is NOT affected, but the turbine THROTTLE valves are limited in the amount of openin Valve operating setpoint is biased 50 psi above the atmospheric dump valves until the condenser is availabl <<
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68 PIANT SYSTEMS (38%i AND PIANT-WIDE GEIERIC RESPONSIBILITIES (10%)
QUESTION 3.38 (1.00)
For the following list (items 1 through 6), SEIECT the answer below (a., b., c., or d. ) which properly displays the correct order of donning a full face respirator mask as stated in 9100-ADH-4020.03
"THI Radiological Controls". NOTE: Every step is NOT liste . Loosen all head harness straps out to the end tab . Insert prescription respirator eyeglasses into facepiec . Hold breath for le second . Insert chin into facepiece and lay sealing surface against fac . Conduct a negative pressure tes . Adjust the headband straps for a snug, comfortable fi ,1,4,6,5,3 ,5,3,2,1,6 ,3,2,1,4,6 ,5,3,2,1,6
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69 PLANT SYSTEMS (38%) AND PIANT-WIDE CM5MIC RESPONSIBILITIES (10%)
QUESTION 3.39 (1.00)
Which one of the following does NOT meet the required conditions for when a Standing Radiation Work Permit may be used.? A manual isolation valve needs to be opened, taking 1-2 mi Venting the primary side of the letdown flow indicator aunt be don Job is not expected to cause any significant changes in the static radiological conditions of the area Approval of the Shift Foreman is granted.
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- 70 PLMIT SYSTEMS (38%) AND PIANT-WIDE GENERIC idiisham1mILITIES (10%)
QUESTION 3.40 (1.00) *
.
Which one of the following is the GPUN Administrative limit for WHOLE BODY exposure for.one Quarter?
a. '1.0 REM .0 PEM .0 RD( .0 REM
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. PIMT SYSTEMS (38%) AND PIMT-WIDE GENERIC RESPONSIBILITIES (10%)
.
I QUESTION 3.41 .(1.68)
l Which one of the following is the correct procedure'for adding tags to the Controlling Document w ording to Administrative Procedure 1902,
").ules for the Protection of Employees Working on Electrical and Mechanical Apparatus?" Department foreman is to provide tags and initial the Controlling Documen Obtain permission of Shift Supervisor / Shift Foreman and document with their initial When notified by the craftsman, make additional tags and give to the craft to han The Control Room Operator should initial the controlling Document and hang tags as needed by the craftsma (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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72 PIANT SYSTEMS (38%) AND PIANT-WIDE GENERIC RESPONSIBILITIES (101)
QUESTION 3.4 (1.00)
Which one of the following is a circumstance when the Shift Foreman or delegated Control Room Operator is allowed to issue the Control Room key for an individual to gain access to a Locked High Radiation Area. Assume Shift Supervisor permission has been grante The Radiological Controls personnel are not readily available to issue the normal ke Operations personnel need to access the High Radiation are The Radiological Controls key was taken home by the previous shift and is unavailabl Excessive time delay would be encountered while operations personnel are conducting ncrual plant procedure I I
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73 PLANT SYSTEMS (38%) AND PIANT-WIDE GENERIC RESPONSIBILITIES (10%)
i QUESTION 3.43 (1.00)
Which one of the following is the proper Control Room Operator action to be taken before conducting any ESAS testing according to Operations Department Memo 84-3? Notify System Load Dispatcher of testing in progres I Verify proper relay status prior to starting the tes Place the channel to be tested in bypass conditio Ensure double verification of steps are accomplishe s J
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74 PIANT sica,G (38%) AND PIANT-WIDE GENERIC RESPONSIBILITIES (10%)
QUESTION 3.44 (1.00)
Which one of the following is a valid method of performing an independent verification?
a. . Two individuals independently verifying valve position only from a i
remote direct component position indicato One individual actually placing a breaker in its required position, then the same individual verifying from a remote
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indicator that the breaker is in the correct positio One individual observing that a valve is in the correct position locally, and another individual independently using a remote position demand indicator to verify valve positio One individual checking a valve in the correct position, and then a second individual obtaining a report from the first individual that the position is correc i
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75 PLANT SYSTEMS (38%) AND PIANT-WIDE GENERIC RESPONSIBILITIES (10%)
QUESTION 3.45 (1.00)
Which one of the following methods of communicating information is NOT proper according to Operations Department Memo 88-02, " Plant Communications and Casualty Control Guidelines?" When asked to report the value of a parameter ensure the value is understood by pronouncing each number seperately (ex. the report "580 degrees" must be spoken as "five - eight - zero degrees"), Use noun names and numbers where appropriate and always emphasize the parts that make what you are describing uniqu (ex. "Open condensate pump discharge valve CO-V18 "A" five turns." When providing direction to change a parameter, use words such as
" increase" or " decrease". When asked to report the rate of change of a parameter, report the value and the parameter as well (i.e. RCS heatup of 90 degrees per hour and Tave is 553 degrees).
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76 PLANT SYSTEMS (38%) AND PLANT-WIDE GDERIC RESPONSIBILITIES (10%)
QUESTION. 3.46 (1.00)
Which one of the following is NOT an immediate action regarding the CRO Responsibilities and Authority according to Operations Department Memo 88-02, " Plant Communications and Casualty Control Guidelines?" Silence the alarms and perform the immediate action Perform alarm review, address abnormal alarms under Shift ,
Foreman directio . Secure major plant equipment su;ch as main feedwater pump Announce the casualty to the control room team (if known).
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77 PIANT SYSTEMS (38%) AND PIANT-WIDE GENERIC RESPONSIBILITIES (10%)
QUESTION 3.47 (1.00) j In the event of a fire in the Auxiliary Building, which one of the below is an acceptable combination for the Fire Brigade (;under noranal manning conditions)? Shift Forman, 2 Auxiliary Operators, Radiation Control Technician, Control Room Operator Maintenance: Foreman, 2 Auxiliary Operators, Radiation Control Technician, Control Room Operator Shift Forman, 2 Auxiliary Operators, 2 Maintenance Personnel; and a Radiation Control Technician as an advisor Maintenance Foreman, 2 Auxiliary Operators, 2 Maintenance Personnel; and a Control Room Operator as an advisor
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WUESTION 3.48 (2.00)
Select the answer below which correctly completes the following statement regarding the Reactor Building Spray system:
Following a IOCA, reactor building spray is designed limit post accident building pressure to -1- psig, and tehn reduce building pressure to approximately -2- psi / 25 / 25 / 1 / 1
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79 EMERGENCY AND ADNORMAL PIANT EVOLUTIONS (27%)
ANSWER 2.01 (1.00) ,
b REFERENCE s-
'tHI OPM, Vol. 7, Sect. N-2, pp. 142-146 No facility objective identifie '
(4.1/4. 7 )'
000074A207 ..(KA's)
ANSWER 2.02 (1.00)
a REFERENCE ATP 1210-10, pp. 4.0 - Lesson Plan-11.2.01.326, pp. 19.0 - 20.0, & Obj. 11. (4.0/4.6)
000007K301 ..(KA's)
.
ANSWER 2.03 (1.00)
e REFERENCE AP 1203-15, p. No facility objective identifie (3.5/3.8)
000022K302 ..(KA's) -
ANSWER 2.04 (1.00) ,
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.. EMERGENCY AND ABNORMAL PIANT EVOLUTIONS
.(27%)
REFERENCE EP 1202-29, pp. 3.0-4.0 and ES- ,
No' facility objective identifie .
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(4.0/4.2)
000008A107 ..(KA's)
ANSWER 2.05 (1.00)
b REFERENCE 1D IV.E.06.02, & IV.E.06.0 TS Sect. OPM F-7, pp. 48-50 (3.4/3.9)
000036K202 ..(KA's)
ANSWER 2.06 (1.00) b (Emergency Feedwater) e (Main Steam) NOTE: Order may be reverse REFERENCE No Facility Objective Identifie OPH H-2, p. 1 (3.0/3.2) ,
000065K304 ..(KA's) .
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ANSWER 2.07 (1.00) 4 e
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81 DERGENCY AND ABNORMAL PIANT EVOLUTIONS (27%)
i REFERENCE-OPH K-3, p. No facility objective identifie (3.4/3.9). -
900067G006 ..(KA's)
ANSWER 2.08 (1.00)
d REFERENCE ATP 1210-5, p. LO V.E.05.0 (4.2/4.4)
000037K307 ..(KA's)'
ANSWER 2.09 (1.00)
c REFERENCE OPH E-2, p. 2 ID IV.B.09.0 (3.6/3.9)
000059A205 ..(KA's)
ANSNER 2.10 (1.00)
d REFERENCE EP 1202-29, p. 1 No facility objective identifie (3.5/3.8)
000027K301 ..(KA's)
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i 82: BIERGENCY AND ABNORMAL PLMIT EVOLUTIONS (27%)-
AllSWER 2.11 (1.00) . REFERENCE -
EP 1202-11, p. OPH F-7, p. 4 [ .
No facility objective identifie ."'
(3.2/3.4)-
900076A104 ..(KA's)
ANSWER 2.12 (1.00)
a REFERENCE OP 1103-4,.p. 2 .
LO IV.A.09.2 (3.8/4.1)
000024A201 ..(KA's)
ANSWER 2.13 (1.00)
a REFERENCE
.EP.1202-08, p. 1 ID V.D.03.0 '
,
(3.9/4.2)
000005K306 ..(KA's)
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ANSWER 2.14 (1.00)
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83 DERGDICY AND ABNORMAL PIANT EVOLUTIONS (27%)
REFERENCE EP.1202-08, pp. 6.0- LO V.D.03.01.
(3.8/4.1) (3.2/3.6)
000003K113 000003K304 ..(KA's)
s ANSWER 2.15 (1.00) ~
,
d REFERENCE EP 1202-08, pp. 13.0-1 V.D.03.02 (3.9/4.0)
000001G010 ..(KA's)
ANSWER 2.16 (1.00)
a REFERENCE ATP 1210-10, p. 1 No facility objective identifie (4.4/4.5)
000015A121 ..(KA's)
.z -
ANSWER 2.17 (1.00)
a .
REFERENCE '
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ATP 1210-10, p. 1 LO V.E.10.04 (3.4/4.2)
000040K107 ..(KA's)
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2.- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 122 ANSWER 2.18' (1.88)
b
. REFERENCE EP 1282-31, p. LO IV.D.36.84 (3.1/3.3)
886888G814 ..(KA's)
ANSWER 2.1 (1.88)
b NOTE: References are confusing. The note on p. 6.8 of EP 1282-2A says "177.5 amps for B hours (1188 ampere hours)," which is self-contradictory. The revised text on p. 6 of OPM A-3 supports an B hour discharge at a 1428 ampere hour rate (177.5 amps). However, Figure 4 on p. 9 of OPM A-3 refers
.to an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> discharge at a 1288 ampere hour rate (158 amps). The litt ampere hour rate referred to in EP 1282-2A would indicate a continuous discharge of 13 amps. The utility needs to supply the correct battery load capacity to validate this question. ONLY ONE CORRECT ANSWER WILL BE ACCEPTE REFERENCE EP 1282-2A, p. OPM A-3, pp. 6, LO IV.6.18.1 (3.3/3.7)
888855K181 ..(KA's)
ANSNER 2.28 (1.88)
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85-l EHERGDICY AND ABNORMAL PIANT EVOLUTIONS l (27%) .
REFERENCE AP 1202-16, pp. 7.0- ID V.C 06.03 I
(2.9/3.2)
000015G012 ..(KA's)
ANSWEn 2.21 (1.00)
b REFERENCE EP 1202-40, p. ID V.D.20.0 (4.1/4.4)
000057K301 ..(KA's)
ANSWER 2.22 (1.00)
c REFERENCE EP 1202-12, p. El- *
ID IV.E.06.1 (3.6/3.6)
000061A101 ..(KA's)
.
ANSWER 2.23 (1.00)
b l REFERENCE EP 1202-12, p. No facility objective identifie (3.1/3.5)
000061A204 ..(KA's)
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86 IHERGENCY AND ABNORMAL PIANT EVOLUTIONS
<
(27%)
ANSWER 2.24 (1.00)
a REFEPJ33CE Lesson Plan 11.2.01.213, pp. 12.0-1 I4 V.E.05.05
.
(4.2/4.5)
000C 7K306 ..(KA's)
.
ANSWER 2.25- (1.00)
b REFERENCE
'EP 1202-9A, p. LO V.D.04.0 (4.0/4.2)
000058K302 ..(KA's)
ANSWER 2.26- (1.00)
e REFERENCE EP 1202-35, p. V.D.16.0 '
(3.9/4.1)
000025K303 ..(KA's)
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ANSWER 2.27 (1.00) '
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b
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87 EMERGENCY AND AIDIORMAL PLlulT EVOLUTIONS (27%).
l-
!* REFERENCE ATP 1210-1, p. I4 V.E.01.06.
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000029K312 ..(KA's)
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.I 11 ' PLANT dieir,G (38%) AND PLMrf-WIDE GENERIC
!
usrummusILITIES (10%)
l ANSWER 3.01 (1.00)
b REFERENC'i -
.
THI Operation Plant Manual, Section B-4, pp 20-22 -
,
(3.2/3.5)
035010K402 ..(KA's)
ANSWER 3.02 (1.00)
b REFERENCE THI Operations Plant Manual, RCP and motor, Section B-2, pp.7-10 Objective IV.A.06.01
.(2.7/3.1)
003000K602 ..(KA's)
ANSWER 3.03 (1.00)
b REFERENCE THI Operations Plant Manual, RCP and motor, Section B-2, fig. 14, p 44
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(2.8/3.0) ..
003000K505 ..(KA's) ,
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!4 PLANT srsusiS (38%) AND PIANT-WIDE GENERIC is5rOn=1mILITIES (10%)
ANSWER 3.04 (1.00) ,
c REFERENCE THI Operations Plant Manual, Section I-1, p. 6 (3.9/4.2)
061000A101 ..(KA's)
ANSWER 3.05 (1.00)
d REFERENCE THI Operations Plant Manual, Section I-1, p. 8 (3.2/3.3)
061000K201 ..(KA's)
ANSWER 3.06 (1.00)
a
.
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REFERENCE
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THI Operation Plant Manual, Section I-1, pp. 15-16 Objective IV.C.05.05
,
(4.0/4.0)
061000A302 ..(KA's)
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ANSWER 3.07 (1.00) .
a
..
REFERENCE /
THI Operation Plant Manual, Section B-5, p. 8 Objective IV.A.09.28
.
(3.3/3.2)
004000K405 ..(KA's)
ANSWER 3.08 -(1.00)
a REFERENCE
'IMI Operation Plant Manual, Section B-5, p. 7 (2.8/2.9)
004000K113 ..(KA's)
ANSWER 3.09 (1.00)
a
,
REFERENCE THI Operation Plant Manual, Section F-6, p.10 (3.3/3.7)
013000K410 ..(KA's)
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l PIANT siaar,G f 38%i AND PIANT-WIDE GEIERIC RESPONSIBILITIES (10%)
l ANSWER 3.10 (1.00)
d REFERENCE ,
THI Operation Plant Manual, Section F-6, pp 18-19 Objective IV.E.24.09 (4.1/4.2)
013000A302 ..(KA's)
ANSWER .3.11 (1.00)
b REFERENCE
?!I Operation Plant Manual, Section F-6, pp 9-15 Objective IV.E.24.06 (4.2/4.4)
~013000K101 ..(KA's)
' ANSWER 3.12 (1.00)
d
.
REFERENCE l
THI Operation Plant Manual, Section F-1, p. 64 Objective IV.E.13.22
. (3.7/3.8)
001000K407 ..(KA's)
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j PIANT SYSTEMS (38%) AND PIANT-WIDE GDERIC L is5r visIBILITIES (100 ANSWER 3.13 (1.00) ,.
b REFERENCE Technical Specifications, p. 3-1.10 (3.3/3.5)
001000G010 ..(KA's)
ANSWER 3.14 (1.00)
a
.
REFERENCE TMI Operation Plant Manual, Section F-1, p. 44 (2.6/2.8)
001000K404 ..(KA's)
ANSWER 3.15 (1.00)
b
,
REFERENCE BO IV.E.11.11 OPH F-4, p. 46 (3.1/3.2)
015000K604 ..(KA's)
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93 i l PIANT simirstS (38%) AND PLANT-WIDE GDERIC .
RESPONSIBILITIES (10%)
ANSNER 3.16 (1.00)
d' .
REFERENCE Terminal Objective Task No. 341801010 No facility reference identifie (4.1/4.4)
015000K505 ..(KA's)
ANSWER 3.17 (1.00)
a REFERENCE TMI Operation Plant Manual, Section F-3, p. 164 TMI Operation Plant Hanual, Section F-4, p. 36, fig Objective IV.E.11.07 (3.9/3.9)
015000K105 ..(KA's)
ANSWER 3.18 (1.00)
a REFERENCE THI Operation Plant Manual, Section B-5, p. 11
,:
(3.0/3.3)
004000K407 ..(KA's)
'
s ANSWER 3.19 (1.00)
e
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94 PLMIT SYSTEMS (38%) AND PIANT-WIDE GDIERIC RESPONSIBILITIES (10%)
REFERDICE THI Operation Plant Manual, Section F-7,.p. 48 -
(4.0/4.3)
073000K401 ..(KA's)
.
ANSNER 3.20 (1.00) ,
b REFERENCE THI Operation Plant Manual, Section B-8, p. 7 (2.9/3.1)
006000K504 ..(KA's)
ANSWER 3.21 (2.00)
b REFERENCE THI Operation Plant Manual, Section B-9, p. 5 (3.5/3.7)
026000G007 ..(KA's)
ANSNER 3.22 (1.00)
d ( * " * * CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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.l PIANT SYSTEMS (38%) AND PIANT-WIDE GDIERIC RESPONSIBILITIES (10%)
REFERENCE THI Operation Plant Manual, Section B-4, pp 1-15 (3.8/4.0)
035010K199 ..(KA's)
.
ANSWER 3.23 (1.00)
e REFERENCE TMI Operation Plant Manual, Section G-3, pp 9-18 (3.2/3.6)
035010K601 ..(KA's)
ANSWER 3.24 (1.00)
b REFERENCE TMI Operation Plant Manual, Section C-1, p. 11 Objective IV.B.10.09
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(3.0/3.3)
033000K303 ..(KA's)
ANSWER 3.25 (1.00)
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d .. -
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96 PIANT SYSTEMS (38%) AND PLMIT-WIDE GEIERIC mimivneusILITIES (10%)
REFERENCE TNI Operation Plant Manual, Section C-1, pp 11-12 Objective IV.B.10.05 (2.6/2.9) K403 ..(KA's)
1'
,-
l ANSWER 3.26 (1.00)
b REFERENCE THI Operation Plant Manual, Section F-5, pp 12-13 Objective IV.E.09.07 (2.9/2.9)
016000A301 ..(KA's)
ANSWER 3.27 (1.00)
d REFERENCE
'INI Operation Plant Manual, Section F-5, p.12 (3.6/3.5)
016000K106 ..(KA's)
ANSWER 3.28 (1.00)
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97 l PIANT sieaz,13 (38%) AND PIANT-WIDE GENERIC l
RE.5 POSSIBILITIES (10%)
l REFERENCE THE FACILITY TRAINING STAFF IS TO PROVIDE THE CORRECR ANmfER AFTER THE EKAMINE HAS BEEN ADMINISTERED 1 THI Operation Plant Manual, Section A-4, pp 25, 29-36, Figs. 14-21 and Figs. 32 and 3 (3.7/4.1) (3.2/3.6) (3.4/3.9)
064000K105 064000K203 063000K301 ..(KA's)
.
ANSWER 3.29 (1.00)
d REFERENCE TMI Operation Plant Manual, Section A-1, p. 18 Objective IV.G.03.05 (3.2/3.3) (3.0/3.2)
062000G007 062000G009 ..(KA's)
ANSWER 3.30 (1.00)
b REFERENCE THI Operation Plant Manual, Section A-4, p. 36 Objective IV.G.08.07 (d.1/4.0)
064000A301 ..(KA's)
ANSWER 3.31 (1.00)
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'A PIAL SYSTEMS (380 AND PIANT-WIDE GENERIC BESPONSIILgggis._,Lig1L REFERENCE THI Operation Plant Manual, Section F-2, p.13
Objective IV.E.14.13 ,
I (3.3/3.6)
..(KA's)-
'
012000K604 *
ANSWER 3.32 (1.00)
a REFERENCE THI-Operation Plant Manual, Section C-8, p. 10 Objective IV.B.12.03 (2.9/3.6)
028000K503 ..(KA's)
ANSWER 3.33 (1.00)'
c REFERENCE-TMI Operation Plant Manual, Section B-6, p. 8 Objective IV.A.11.03 (3.1/3.5) ,
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005000K408 ..(KA's)
ANSWER 3.34 (1.00)
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99 PLANT smir,G (380 AND PUWT-WIDE GENERIC RESPONSIBILITIES (10%)
REFERENCE l'
TkI Operation Plant Manual, Section B-6,- p. 7 Objective IV.A.11.06 ,
(3.0/3.2) ,.
005000K401 ..(KA's) .
.
ANSWER 3.35 (1.00)
a REFERENCE THI Operaticn Plant Manual, Section B-10, p. 8 Objective IV.B.03.06 (3.2/3.0)
008000A301 ..(KA's)
~ ANSWER 3.36 (1.00)
e
,
REFERENCE THI Operation Plant knual, Section F-3, p. 39 Objective IV.E.27.17 (2.8/2.9)
041000G004 ..(KA's)
.
ANSWER 3.37 (1.00)
b
%
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100 PLANT SYSTEMS (38%).. AND. PLMtT-WIDE..GDFJtIC
-
RESPONSIBILITIES (10%)
REFERENCE THI Operation Plant Manual, Section F-3, p. 39 -
Objective IV.E.27.20 (2.6/2.9)
041020K196 ..(KA's)-
~
-s ANSWER 3.38 (1.00)
a REFERENCE .
THI Radiological Controls Procedure, 9100-ADH-4020.03, pp 4-5 (3.3/3.6) (3.3/3.6) (2.8/3.4)
194001K103 194001K114 194001K113 ..(KA's)
ANSWER 3.39 (1.00)
d REFERENCE THI Radiological Controls Procedure, 9100-ADH-4110.04, pp 4-5 (2.8/3.4)
194001K103 ..(KA's)
,
ANSWER 3.40 (1.00)
1'
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101 PLANT SYSTEMS (38%) AND PIANT-WIDE GENERIC is iv k wILITIES (10%)
REFERENCE GPU Nuclear G.E.T. Radiation Worker Training (Cat II - Radiation Worker) lesson Plan, p. 5 THI Radiological Controls Procedure, 9100-ADH-4000.01, p. 1 ,
(2.8/3.4) i 194001K103 ..(KA's)
.
ANSWER 3.41 (1.00)
b REFERENCE THI Administrative Procedure, 1002, p. 19 (3.7/4.1)
194001K102 ..(KA's)
ANSWER 3.42 (1.00)
e REFERENCE TMI Administrative Procedure, 1011, p. 5 Objectives V.A.05.0 '
(3.1/3.4) ..,
'
194001K105 ..(KA's) ,,
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,
f ANSWER 3.43 (1.00) ..t
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b , z. .
I i
l l
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' 102 ELMrl_ElfS1EME61&lf-MIDK_M RESPONSIBILITIES (100 REFERENCE
~TMI Operations Department Memo 84-3 (4.3/4.1) .
l 194001A114 ..(KA's) ,
i SL
- ANSWER 3.44 (1.00) .
a-REFERENCE EO V.J.01.01, .02, .04, and .09 AP 1967, pp. 5.0- ,
(3.6/3.7)
194001K101 ..(KA's)
ANSWER 3.45 (1.00)
e REFERENCE
.
THI Operations Department Memo 88-02, p. 4
<s (3.6/3.8) ,.
<
194001A195 ..(KA's) .
<,
ANSWER 3.46 (1.99)
c ,.
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103 PLMIT SYSTEMS (38%) AND PIANT-WIDE GDERIC RESPONSIBILITIra.(10%)_
REFERENCE
THI Operations Department Heno 88-02, p. 6 (4.1/3.9)
..(KA's)
'- ~
194001A102 .
R',
s
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ANSWER 3.47 (1.00) 1
? dy; d
REFERENCE Technical Specifications, p. 6-la Administrative procedure 1038, p. 5 (3.5/4.2)
194001K116 ..(KA's)
.
ANSWER 3.48 (1.00)
d REFERENCE THI Operation Plant Manual, Section B-9, p. 1
' "
(3.6/3.9)
"
026000G004 ..(KA's) >
r*
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