IR 05000423/1989005
| ML20246M874 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/03/1989 |
| From: | Eselgroth P, Yachimiak E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20246M862 | List: |
| References | |
| 50-423-89-05OL, 50-423-89-5OL, NUDOCS 8905190287 | |
| Download: ML20246M874 (198) | |
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{{#Wiki_filter:_- - _ _ _ _ . I-p !- U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT
l EXAMINATION REPORT NO.: 5C-423/89-05 (OL) FACILITY DOCKET NO.: 50-423 FACILITY LICENSE NO.: NPF-49 LICENSEE: Northeast Nuclear Energy Company Hartford, Connecticut 06141-0270 FACILITY: Millstone Nuclear Power Station, Unit 3 EXAMINATION DATES: March 21-23, 1989 CHIEF EXAMINER: 4h b d b9 EdwardYachimiak,OpergonsEngineer /Date APPROVED BY: ////' [ Md [[S/89 Date
[ft/ Peter W. Eselgrotft/
Division Chief PWR Section of Reactor Safety SUMMARY: Two (2) Senior Reactor Operator (SRO) and two (2) Reactor Operator (RO) license examinations were administered. All candidates successfully completed both the written and operating parts of their respective examina-tions, with the exception of one (1) R0 applicant who failed section 1 of his written examination. Two (2) SR0 licenses and one (1) R0 license were grante pjg5 87 89050s V CM 0 200423 PNV l _ _ _ _ _ _ _ _ - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ __ i
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I l DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS: l R0 l SR0 l l Pass / Fail l Pass / Fail l l l l l l 1 l l Written l 1/1 1 2/0 l 1 L_ l l I I I I l Operating l 2/0 l 2/0 l l l l 1 I I I I l Overall l 1/1 1 2/0 l l 1 I I I I I I 1. CHIEF EXAMINER AT SITE: E. Yachimiak (NRC) 2. OTHER EXAMINERS: B. Dean (NRC) J. Prell (NRC) J. Nickolaus (PNL) T. Bardell (PNL) 3. Pre-Examination Review: Prior to the administration of the Senior Reactor Operator (SRO) and the Reactor Operator (RO) written examinations, two (2) Millstone Station staff members, both under security agreement, reviewed the examinations at our offices in King of Prussia, Pennsylvania on March 15 and 16, 1989. This review resulted in a content valid performance based examinatio All simulator scenarios were reviewed and exercised by the NRC on the Mills +.one simulator prior to their use with the assistance of one (1) facility instructor under security agreement.
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i 4. Simulator Operation During the administration of one operating test, the simulator appeared to behave in a manner not expected by the operating crew being examine Specifically, the main electrical generator turbine controls for load set and standby load set could not be transferred between each other in accordance with the approved plant procedure. This problem was reviewed I after the operating test and was diagnosed as a apparent simulator modelling ; deficiency. The Training Supervisor stated that this problem would be ; reviewed in greater detail and corrected. Other than this minor problem, the simulator's performance throughout both days of operating tests was excellen This problem did not affect the ability of the examiners to evaluate the candidate . Exit Meeting Summary: The following comments were presented and discussed with the personnel listed in Section 6 presen Key control of Remote / Local switches required for auxiliary (local) shutdown /startup of diesel generators is not addressed in either administrative procedures or applicable emergency procedures. This lack of information could result in the dispatching of an operator to the diesel generators without the prerequisite keys needed for local starting, thus causing a significant delay in the restoration of an emergency power source.
l The Operations Supervisor stated that he would review this finding and take appropriate corrective action Specific diesel generator (D/G) operating parameters which are to be locally checked by the auxiliary operator are not specified in E0P-3503, Appendix The Operations Supervisor stated that the procedure would be reviewed and specific D/G operating parameters would incorporated, as necessar Efficient use of NRC resources necessitates the current policy regarding the administration of operator licensing examinations. This can only be accomplished by scheduling a maximum of two (2) license classes a year with a minimum of six (6) license candidates in each. The Ooerations Training Supervisor acknowledged this information and had no commen __- -
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! 6. Personnel Present at Exit Meeting: 1 L NRC Personnel Bardell,T.,-Examiner (PNL) Dean, B.,-Examiner Kolonauski, L., Resident Inspector (MP1) ! Nickolaus, J., Examiner (PNL) Prell, J.,' Senior Operations Engineer Yachimiak, E., Operations Engineer Facility Personnel Coven,.K., Operations Assistant Gentry, M., Operations Supervisor - Parrish, B., Simulator' Instructor Ruth, B., NU Manager, Operator Training
;Stotts, R., Operations Training Supervisor
Attachments:
R0 MASTER Written Examination and Answer Key SR0 MASTER Written Examination and Answer Key l .. _ ___w------_.----_-_-_---_--.._.-----,__--------_---..---w-
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0FFitlAt. cop)/ Attachment-1 U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION REGION 1 FACILITY: Millstone 3 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 89/03/21 INSTRUCTIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one side onl Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of a 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 24.75 24.63 REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 32.7S 32.59 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS-(33%) A YS.95 4. 0L 42.79 PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC g RESPONSIBILITIES (13%) M % TOTALS 1 FINAL GRADE All work done on this examination is my ow I have neither given nor received ai M Candidate's Signature + c4 daa 6 defa c y w>fs, 6.05,pcxf % l
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS l During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . 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 . Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each section of the answer shee . Consecutively number each answer sheet, write "End of Category _" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer shee . Number each answer as to category and number, for example,1.4, . Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literature, , 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer require . Show all calculations, methods, or assumptions used to obtain an answer I to mathematical problems whether indicated in the question or no . Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner onl . You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
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- _-_ _ _ _ . . _ _ - - - _ _ - _ _ _ _ _ _ - _ _ _ _ _ - - __ _ __ _ .__ ___ ___ _ __ ___ 18. When you complete your examination, you shall: Assemble your examination as follows:
(1) Exam questions on to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are part of the answe Turn in your copy of the examination and all pages used to answer ,
the examination questions, i Turn in all scrap paper and the balance of the paper that you did not use for answering the questions, Leave the examination area, as defined by the examine If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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. _ _ _ _ - _ . .EACTOR PRINCIPLES (7's) THERMODYNAMICS Page 4 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
QUESTION ~4.01 (1.50) WHAT are THREE (3) types of a
REGION 1 FACILITY: Millstone 3 REACTOR TYPE: PWR-WEC4 OATE ADMINISTERED: 89/03/21 INSTRUCTIONS TO CANDIDATE: Use. separate paper for the answers. Write answers on one side onl Staple question' sheet on top of the answer sheet Points for each question are indicated in parentheses after the cuestion. The passing grade requires at least 70% in each category anc 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 24.75 - 24.75 1. REACTOR PRINCIPLES (7%) THERM 0 DYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) 27.25 27.25 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%) 48.00 48.00 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%) 10 % TOTALS FINAL GRADE All work done on this examination is my ow I have neither g ven nor received ai . - l Candidate's Signature
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- _ - _ - _ . - _ - _ . .- NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: q Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . 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 . Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each section of the answer shee . Consecutively number each answer sheet, write "End of Category ,_" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet, Number each answer as to category and number, for example,1.4, . Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no . Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner only.
17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been complete _--_ _ _ _ _ _____ _
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- 18. When you complete your examination, you shall:
.a. . Assemble your examination as follows:
(1) , Exam questionsLon to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are part of.'the answe Turn in your copy of.the examination and all pages used to answe :: the examination question Turn in all scrap paper and the balance of the paper that you did
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not use for answering the question Leave the examination area, as defined by the examine If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoke ' I
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QUESTION 1.01 (1.50) WHAT are THREE (3) types of accidental events that could lead to Pressurized Thermal Shock of the reactor vessel? (1.5)
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t REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 5 l (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) QUESTION 1.02 (2.50) ! Assume the plant is stable on natural circulation with the following conditions: That - Tcold = 30 degrees F Thot subcooled margin = 35 degrees F subcooled Steam Generator pressure = 650 psia CALCULATE the RCS pressure and STATE ALL assumptions mad (2.5) l i
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, REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 6 (7%) AND COMP 0NENTS (11%) (FUNDAMENTALS EXAM)
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QUESTION 1.03 (3.00) WHAT effect (Increase, Decrease, Remain the Same) will the following parameter changes have on the DNBR7 JUSTIFY your answer'for each. Assume all other parameters remain constant, Decrease in core inlet temperature (0.75) AFD changes from 0% to +3% (0.75) Increase in reactor coolant flow (0.75) Control rod dropped near the core center (0.75) ! I l
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' REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 7 (7%)~AND COMPONENTS (11%) (FUNDAMENTALS EXAM) > '
QUESTION 1.04 (3.00) ' The control of flow rate in a system is usually controlled by valve operation.rather than pump operation. MATCH those valves listed below.with the BEST operational characteristic under'which they.are most often use (3.0) VALVE TYPE OPERATIONAL CHARACTERISTICS Globe 1. Good flow control in high flow, low pressure application Can cause waterhamme Gate 2. Used to. prevent high system pressur Problems include leakage, incorrect lifting pressure, and failure to sea Butterfly 3. Used most often for throttling flo Capable of handling large pressure differentials and can tightly shutoff flow Check 4. Generally used as on-off valves, small delta pressure when fully open, may need equalizing line Relief 5. Generally used in low pressure and temperature applications, not normally used for throttlin Diaphragm 6. Allows flow in only one direction, self opening and closin (***** CATEGORY 1CONTINUEDONNEXTPAGE*****) _ _ _ _ _ _ _ ._ __- _ _ _ . _ = _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ - - -
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_ 1. cREdCTOR PRINCIPLES (7%) THERMODYNAMIC Page 8:
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QUESTION 1.05 (3.00) Refer to the attached Figure DETERMINE the resultant SYSTEM flow AND pressure for EACH of the TWO (2) combinations of centrifugal pumps listed belo You may write on the figure and attach it to your answer shee Figure 4.1.a: a second aump, identical to the first,
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.is added in PARALLEL wit 1 the firs (1.5) Figure 4.1.b: pump #1 is put in SERIES with pump #. (1.5)
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l REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 9 l (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) ! QUESTION 1.06 (1.50) Controllers often use circuit devices to modify their input signals in order to account for process delays or anticipate system response. For the THREE (3) types of controllers listed below, identify HOW a step input signal to that controller would be modified: Proportional controller (0.5) Integral controller (0.5) Derivative controller (0.5)
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QUESTION 1.07 .(1.25) Assume Unit 3 is c6oling down from 100% power to Cold Shutdown conditions. WHAT long term effect will the cooling of containment ,. have.on Pressurizer level readings for those THREE.(3) level detectors which are~" hot" calibrated? EXPLAIN your answe (l'.25)
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. ' REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 11 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
QUESTION '1.08 (2.00) Millstone Unit 3 is originally operated at 100% power with RCS Tavg at 586 F. and steam pressure at 1185 psig. During a maintenance period,10 percent of the tubes in EACH steam generator..(all 4 steam generators) are plugged. CALCULATE what the new temperature for Tavg must be in order to maintain a steam pressure of 1185 psig at 100% power with 10 percent of-the total SG tubes plugge . STATE ALL ASSUMPTIONS / EQUATIONS USED and SHOW ALL WORK. ASSUME
:that RCS specific heat and mass flow rate through the SGs are .
unchanged by the tube plugging (i.e., remain constant at the original 100 percent value). (2.0)
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_ - _ - _ _ _ _ _ - _ _ - _ - _ _ _ - _ - _ _ _ - - REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 12 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) QUESTION 1.09 (3.00) With an initial count rate of 20 cps, reactivity is added to increase the count rate to 40 cps. WHAT would the effect be on the CRITICALITY fdNDITION (subcritical, critical, supercritical) if the same amount of reactivity was added again? EXPLAIN your answer. A mathematical proof is not required but is acceptabl (1.5) With an initial power level of 10%, reactivity is added to raise power to 20%. What would the effect be on the CRITICALITY CONDITION (subcritical, critical, supercritical) AND what would the resultant power level be if the same amount of reactivity was added again? EXPLAIN your answer. ASSUME that secondary power is changed to maintain normal plant parameter (1.5) ,
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(7%) AND COMPONENTS (11%) (FUNDAMENTALS-EXAM)
r QUESTION 1.10' (3.00) .. Millstone Unit 3 is in Mode-3, BOL, following a reactor trip 20 hours earlier from 70 percent power. Boron concentration is 1000 ppm, all shutdown banks are withdrawn, and the control banks are withdrawn to 50 steps on bank C. The core is shutdown by 400 pcm.. A dilution of the boron concentration, which takes about 1 hour, increases source range counts from 100 cps to 196 cps. CALCULATE the final' boron concentration. STATE all assumptions and SHOW all work. ASSUME xenon changes by 100 pcm during the 1 hour dilutio (3.0)
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QUESTION 1.11 (1.00) What are TWO (2) reasons WHY the probability that delayed neutrons will cause fission is different as compared to prompt neutrons? (1.0)
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t i: EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 15 (27%) I
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- _ _ - _ _ - _ MERGENCY AND ABNORMAL PLANT EVOLUTIONS-- Page 16 QUESTION 2.01 (1.00) WHEN, if at all, is it permissible to establish feed flow to a faulted steam generator? (1.0) l
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QUESTION' 2.02- '(2.00) l E0P 35 FR-S.I', ~ " Response to Nuclear Power Generation /ATWS," i . Step 2 has you verify that the turbine has tripped. . WHAT actions
"should be carried out by the operator if the turbine-has not tripped? INCLUDE all contingency sub-steps contained in the-response not obtained column in you answe (2.0)
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"RCP Tri failure,p-WHAT or SealTWO Failure," in related (2) RCP the event of an actions must RCP be taken? #1 seal INCLUDE the respective maximum allowable time limit (1.0)
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-QUESTION 2.04 (1.50)
-You are given the following summary of Critical Safety Function Status Trees while performing .E0P-2, " Faulted Steam Generator Isolation." If ALL procedures were to be used, PROVIDE the order of priority. - (1.5)- Heat Sink Red Core Cooling Yellow Subcriticality Orange
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_ _ _ _ _ - _ _ - _ _ _ _ _ _ _ - _ _ i EMERGENCY AND ABNORMAL FLANT EVOLUTIONS Page 20 (27%) QUESTION 2.05 (1.00) As a result of a small break loss of coolant accident, adverse containment conditions have been declare ASSUMING adverse containment was declared due to containment radiation, WHAT conditions must be satisfied prior to using the normal instrument setpoints? (0.5) ASSUMING adverse containment was declared due to containment temperature, WHAT conditions must be satisfied prior to using the normal instrument setpoints? (0.5) i f I (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) _ - _ _ _ _ - _ _ _
_ _ _ _ _ _ _ _ . I l EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 21 (27%) I QUESTION 2.06 (1.00) WHICH ONE (1) of the following is NOT an immediate operator action for E0P 35 ECA-0.0, " Loss of All AC Power"?
(1.0) (a.) Verify AFW flow to all intact SG (b.) Verify reactor tri (c.) Check if RCS is Isolate (d.) Restore power to any AC emergency bu !
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r 1 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 22 (27%) QUESTION 2.07 (1.00) Per A0P 3559, " Loss of Condenser Vacuum", WHAT are TWO (2) possible indications of a loss of condenser vacuu (1.0)
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QUESTION 2.09 (2.00) In accordance with A0P 3566, "Immediate Boration," WHAT are FOUR (4) i conditions that would require IMMEDIATE B0 RATION? (2.0) ,
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-QUESTION 2.10 (1.00)
WHICH ONE (1) of the following statements describes the response of the Emergency Generator Load Sequencer (EGLS) when a Safety Injection Signal (SIS) occurs 20 seconds following a Loss of Power (LOP)? (1.0)
(a.) All LOP loads will be stripped and the EGLS will start the LOP /SI sequenc (b.) The EGLS will stop the LOP load sequence and the EGLS !
will start the LOP /SI sequenc J (c.) The EGLS will stop the LOP load sequence, loads which are not required by SI will be stripped, and the EGLS will start the SI sequenc (d.) The EGLS will stop the LOP load sequence, the LOP loads on-line will remain so, and the EGLS will start the
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l l l EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 26 (27%) I l l QUESTION 2.11 (1.00) l ' The first action step of the SGTR procedure (E0P 35 E-3, " Steam Generator Tube Rupture") requires the operator to check if the RCPs are required to be stopped. STATE the reason for this ste (1.0) i (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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l EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 28 (27%) QUESTION 2.13 (2.00) In procedure E0P 35 FR-S.1, " Response to Nuclear Power Generation / ATWS," one of the sub-steps has the operators check if PZR pressure is less than 2350 psi WHAT is the basis of this sub-step? (1.0) I WHAT operator actions are required if PZR pressure is greater than 2350 psia? (1.0)
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i EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 29 I (27%) j l QUESTION 2.14 (1.00)
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WHAT are FOUR (4) indications / annunciators associated with a loss of Reactor Plant Component Cooling _ Water (RPCCW). (1.0) l l l l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) _________ _ -____ -_ - _ _ _ _ _ - _ - _ - ,
__ __ ._ - _ _ _ _ . f I 1 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 30 (27%) QUESTION 2.15 (1.50) Per A0P 3505, " Loss of Shutdown Cooling (RHR)," ASSUME the unit is in cold shutdown, the RPV head is NOT removed and the RCS level is at the center line of the hot leg HOW will RHR pump air binding be detected? (0.5) If both trains of RHR are ai,a bound, normal charging from the RWST is to be used to remave RCS decay heat. WHAT are TWO (2) alternate means of make-up to restore decay heat removal? (1.0) j (***** CATEGORY 2 CONTINDED ON NEXT PAGE *****) { _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ - - - - - -
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QUESTION 2.16 (1.50) In accordance with FR-1.3, " Response to Voids in Reactor Vessel," WHAT are the THREE (3) possible methods of collapsing a void in the reactor vessel? SPECIFY WHICH method is used to collapse a non-condensible voi (1.5)
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_ - _ _ _ - _ _ _ - _ _ _ _ - l' [- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 32 (27%) QUESTION 2.17 (1.25) The following refer.to E0P 35 E- When the operator is instructed to " check for faulted S/G " l WHAT indication is observed? (0.25) WHAT are the TWO (2) parameters and setpoints that determine if main steam lines should be isolated? (1.0)
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l l EMERGENCY AND ABNORMAL PLANT EV0LUTIONS Page 33 (27%) ! , ! QUESTION 2.18 (1.50) A0P 3563, " Loss of a DC Bus," states that letdown isolates with l the loss of either Battery Bus 1 or Battery Bus HOW are letdown and charging established following loss of either bus? INCLUDE charging sources AND letdown flowpaths AND destination (1.5)
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_ _ _ _ EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 34 (27%) QUESTION 2.19 (2.00) What are FOUR (4) indications of a dropped rod? (2.0)
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3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 35 RESPONSIBILITIES (10%) l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) \ - _ _ _ _ _ _ _ _ - - _ _ - - - _ _ _ _ _ _ _ _ _ - -
- - _ _ - _ _ _ - _ _ _ _ _ . _ _ _ . _ . _ _ . _ _ - _ _ _ _ _ _ _ - _ _ - _ _ . PLANT SYSTEMS (38%) AND PLANT-W10E GENERIC Page 36 RESPONSIBILITIES (10%) QUESTION 3.01 (1.50) WHY is sodium hydroxide (NA0H) used in the Quench Spray System? (0.5) WHY are limits placed on this chemical's volume and concentration which assure a pH value of between 7.0 and 7.5 for the solution recirculated within containment after a LOCA7 (1.0)
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QUESTION 3.02 (1.50) WHAT are TWO (2) . reasons for maintaining a minimum pressurizer spray line flow during normal "at power" operations? (1.0) WHAT indication or annunciation is available to alert the operator that minimum spray flow is not being maintained? (0.5) l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) ! l l
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QUESTION 3.03 (1.50) j WHAT are TWO (2) indications which provide an operator prompt indication that a pressurizer safety valve has lifted? (1.0) WHAT system provides spray to cool the Pressurizer Relief Tank (PRT)? (0.5)
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, - - _ _ - _ _ _ _ _ - _ _ - - - - PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 39 RESPONSIBILITIES (10%) QUESTION 3.04 (1.00) The Containment Spray system is designed to reduce containment pressure after a DB WHAT signal (s) is (are) necessary for a full automatic actuation of the containment spray system? (0.5)- During the normal sequence of a LOCA, WHEN will the Quench spray pumps trip? (setpoints are NOT required) (0.5) i i i (***** CATEGORY 3CONTINUEDONNEXTPAGE*****) l _ _ _ _ _ _ ._- __-_- --
7__-_-- . I l \ PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 40 RESPONSIBILITIES (10%) J QUESTION 3.05 (1.50) WHAT'are the THREE (3) load transients for which the pressurizer is designed to satisfactorily operate during normal operations (with automatic rod control)? (1.5) l l
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_ _ _ . . _ _ _ _ _ _ _ _ - - _ _ - PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 41 RESPONSIBILITIES (10%) l QUESTION 3.06 (3.00) The diesel generators have been automatically started by a l SIS / LOP /CD WHAT are the THREE (3) Shutdown Relay (SDR) signals that will trip the diesel generator? (1.5) WHAT 'are FOUR (4) of the mechanical SDR diesel engine trips that are defeated during an automatic start of the diesel generator? (1.0) WHAT are TWO (2) of the SDR electrical (generator) trips that are defeated during an automatic start of the diesel generator? (0.5)
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I . QUESTION 3.0 (2.00) WHAT are the THREE (3) arming signals for the steam dump-control syste (1.5) I The Interlock Select Switch must be in the ON position, in conjunction with the arming ~ signals, to allow control of:ALL steam dump valves. WHAT is the other interlock which must be satisfie (0.5) I , L
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_ _ _ _ _ - - _ _ - _ _ _ - _ _ _ i i i PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 43 RESPONSIBILITIES (10%) QUESTION 3.08 (1.00) Describe TWO (2) means of interconnecting the Instrument Air (IA) system with backup sources of air pressur (1.0)
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- _ ____-_ PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 44 RESPONSIBILITIES (10%) QUESTION 3.09 (1.00) WHY does OP 3201, " Plant Heatup" request extreme care be exercised when operating the contrcls for the Atmospheric Steam Dump Valves?
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l PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 45 RESPONSIBILITIES (10%) l l QUESTION 3.10 (1.50) ANSWER the following questions concerning the 125 VDC Power System: WHAT are FOUR (4) conditions that will cau:e the 125 VDC (MB8) " BATTERY 1 TROUBLE" annunciator to alarm? (Annunciator test is not considered a valid condition.) (1.0) HOW long can a fully charged battery maintain full bus loads? (0.5)
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I i PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 46 ' RESPONSIBILITIES (10%) l OUESTION 3.11 (1.00) WHAT are FOUR (4) items that the Rod Control System Startup switch will rese (1,0) i l i l
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QUESTION 3.12 (1.00) WHICH ONE (1) of the following is a purpose of the Chemical and Volume Control System mixed bed demineralizers? (1.0)
(a.) remove ALL chemicals from the RC (b.) remove ionized coolant impurities and fission products from the RC (c.) replace insoluble material with soluble ion (d.) provide a method of boron control during reactor operation l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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_ _ _ _ __ _ _ PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 48 RESPONSIBILITIES (10%) QUESTION 3.13 (1.00) WHAT are FOUR (4) conditions / signals which will actuate a CBI (Control BuildingIsolation). (Setpoints and coincidence not required.) (1.0)
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! l l ' PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 49 RESPONSIBILITIES (10%) QUESTION 3.14 (1.50) WHAT are the THREE (3) signals which will initiate a Feedwater Isolation (FWI). (1.5)
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_ _ - _ _ _ _ _ - _ _ _ - _ - _ _ _ _ _ _ _ _ _ - - - _ _ _ b l L ! I 1 PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 50 i RESPONSIBILITIES (10%) QUESTION 3.15 (1.00) With regard to the chemical and volume control system, WHICH ONE (1) of the following is the CORRECT failure mode when valves fail on a loss of power or air? (1.0)
(a.) Letdown isolation valves (LCV 459/460) fail ope (b.) Letdown Orifice Isolation Valves (CHS 8149 A/B/C) fail ope (c.) Low Pressure Letdown Control Valve (PCV-131) fails as i (d.) Charging Pump Suction Valves (LCV-1128/C) fail as i ,
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_ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - , PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 51 RESPONSIBILITIES (10%) QUESTION 3.16 (1.50) EXPLAIN HOW gross overcompensation of both intermediate range I nuclear instrumer.tation channels can cause an early, premature reactor trip during a normal plant shutdow (1.5)
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_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ ) l l PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Pa9e 52 RESPONSIBILITIES (10%) l QUESTION 3.17 (1.00) The t e of detector used for the Gamma-Metrics system is which ONE ( of the following?
(1.0) (a.) G-M tube (b.) BF3 proportional counter (c.) fission chamber (d.) uncompensated ion chamber (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) - - _ - _ - _ _ _ - _
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QUESTION 3.18 (1.00) WHICH ONE (1) of the following statements is CORRECT concerning the intermediate range compensated ionization chambers? (1.0) l (a.) The boron lined chamber is sensitive to neutron and gamma radiation, while the unlined chamber is sensitive only to gamma ray (b.) The compensated ion chamber is designed to remove the gamma signal only at high reactor power level (c.) Undercompensation will cause loss of some neutron current as well as blocking gamma curren (d.) Gammas which penetrate the detector's lead shielding will cause ionization which results in a voltage puls (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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i l l PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 54 RESPONSIBILITIES (10%) QUESTION 3.19 (1.00) WHAT is the purpose of the auxiliary feedwater cavitating venturis? (1.0) i
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b; ! Pl. ANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 55 RESPONSIBILITIES (10%) , QUESTION '3.20 (2.50) WHAT are the FOUR (4) signals that will automatically start the Motor Driven Auxiliary Feedwater Pumps? INCLUDE logic,.
.when applicable.'(setpoints are NOT required). (1.0). ~ WHAT signal will automatically start the Turbine Driven Auxiliary Feedwater Pump. INCLUDE-logic. (setpoints are NOT required).
(0.5) WHAT is the.0NE (1) normal and THREE-(3) alternate sources of make-up to auxiliary feedwate (1.0) l l
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_ - _ _ _ _ _ _ _ _ _ j i PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 56 RESPONSIBILITIES (10%) QUESTION 3.21 (1.00) FILL in the blanks for the following statements regarding the CVCS system, The CVCS mixed beds and cation demineralizers are protected from high (1) by diverting flow from the demineralizers to the (2) .
(0.5) The letdown orifice isolation valves (CHS 8149-A/8/C) are interlocked so they can.be opened only if pressurizer level is (1) and both letdown isolation valves are (2) .
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_ _ _ - _ _ - _ _ - __ l PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 57 RESPONSIBILITIES (10%) l l QUESTION 3.22 (1.50) WHAT are six (6). conditions which would require an operator to manually trip an RCP7 (1.5) I i
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Page 58 RESPONSIBILITIES (10%) QUESTIO!1 3.23 (1.50) MATCH the following equipment with their respective power source (answers may be used more than once or not at all). (1.5) TPCCW Pumps Buses 35A/B/C/D Safety Related MCCs Buses 34A/B , RCPs Busses 32 A through G RPCCW Pumps Busses 32-2T,R,U,W, & 32-3T SI Pumps Buses 32R through Y Battery Chargers Buses 34C/D l l l !
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QUESTION 3.24 (1.50) WHAT are the AUTOMATIC signals which will generate a Main Steam Isolation Signal. (INCLUDE setpoints and coincidence). (1.5)
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3& PLANT SYSTEMS (38%)' AND PLANT-WIDE GENERIC Page 60 RESPONSIBILITIES (10%) QUESTION 3.25 (1.50) WHAT are THREE (3) signals that will cause a turbine runbac (1.5)
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_ _ _ PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 62 RESPONSIBILITIES (10%) QUESTION 3.27 (1.50) MATCH the protective interlocks in column "A" with the respective function in column "B".
(1.5) A B P-14 1. blocks auto rod withdrawal on rod drop signal P-6 2. unblocks single loop low flow Rx trip P-8 3. permits block of IR hi flux trip and rod stop and PR hi flux low setpoint RX trip P-10 4. permits manual block of SR trip and hi volt P-11 unblocks the RCP low speed trip P-7 unblocks Rx trip on turbine trip permits block of PZR pressure and steam pressure SI SG HI level, trips feed pumps, closes FWIVs
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_ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - _ .- . PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 63 RESPONSIBILITIES (10%) QUESTION 3.28 (1.00) If you are in a 100 mrad / hour gamma field (Quality Factor = 1) for 45 minutes, WHAT is your dose in MREM after 45 minutes? (1.0)
(a.) 45 (b.) 75 (c.) 450 (d.) 750 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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RESPONSIBILITIES (10%) QUESTION 3.29 (2.00) SHP 4912, " Radiation Work Permit Completion and Flow Control," General Instructions, requires your initials on the exposure control sheet. Your initials signify understand work conditions as well as,you are aware radiation and of and contamination controls prior to entry into a RWP are PROVIDE FOUR (4) of these FIVE (5) conditions / control (2.0)
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QUESTION 3.30 (1.00) Per ACP-QA-2.06A, " Station Tagging," MATCH the tag function /use with the tag typ (1,0) Tags: Panel Tags Red Tag Blue Tag Green Striped Hold Tag Yellow Caution Tag Lifted Tag Tagged equipment is not to be operated under any ci rcumstances . Placed on equipment to prevent re-energizing if the equipment trips, Placed on equipment to indicate the equipment is only to be energized by order of the individual issuing the ta If operated would endanger personnel and/or equipment.
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. QUESTION 3.31 (1.00) Concerning OP. 3260, " Conduct of Operations," SELECT the ONE (1) CORRECT statement in regards to positioning of category 1 valve '(1.0)
(a.)- Operators performing verification checks can realign valves.
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(b.) Flow path verification will be performed after any action that realigns valves _ during the performance of maintenanc (c.)' Retests of. systems where valves have been repositioned wil require an independ:nt verificatio (d.) If a' system is in an off-normal condition for periods exceeding ONE shift, then the components should be-red tagge j (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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- _ - _ . _ .-. PLANT SYSTEMS (38%) AND PLANT-WIDE SENERIC Page 67 RESPONSIBILITIES (10%) QUESTION 3.32 (1.00) WHY, when containment is at atmospheric conditions (supplemental breathing apparatus not required), are personnel restricted from low confined spaces? (Chemistry Department clearance has not been obtained.) (1.0)
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DURING reactor power operation, WHICH ONE (1) of the following may grant permission to enter containmen (1.0)
(a.) Operations Supervisor (b.) Shift Supervisor (c.) Unit Superintendent (d.) Supervising Control Operator (***** CATEGORY 3CONTINUEDONNEXTPAGE*****)
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_ PLANT SYSTEMS (38%) AND PtANT-WIDE GENERIC Page 69 RESPONSIBILITIES (10%) < QUESTION 3.34 (1.50) Per ACP-QA-2.06A, " Station Tagging,": WHAT are the TWO (2) " Operator in Attendance" responsibilities?
(1.0) WHEN do " Operator in Attendance" responsibilities terminate? (0.5)
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QUESTION 3.35 (1.50) ACP 7.05A, " Vital Area Access Control," REQUIRES that-prior to restoring an t.rea to a vital status and rearming vital dc> ors, a thorough inspection must be performed. WHAT TWO (2) people perform this inspection AND for what purpose? (1.5)
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.I REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 71 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
, l ANSWE .01 (1.50) 1. Small break LOCA '+ .5 V 2. Excessive feedwater 3. Excessive steam flow l+0 0l
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' & ptcl & & a n toI+i\ ;2p>owtigilten REFERENCE V 1. LP-RVC-01-C p - 37,38 EO - 11 K/A 193010K107 3.8/ ANSWER 1.02 '(2.50)
S/G press. = 650 psia = 495 degrees F sa ;+0.50 Tc will' follow S/G temp.,thus Tc ='495 degrees F ,+ 0.50; Th = Tc + 30 = 525 degrees F +0.50, PZR temp.'= Th + 35 = 525 + 35 = 560 degrees F l+0.50 PZR press. = sat. press. for 560 degrees F = 1133.4 (1130-1140) psia
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REFERENCE 1. LP-HFC-01-C p - 13 through 17 K/A 193003K125 3.3/ K117 3.0/ (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) _ _ _ _ . . _ _ _ _ _ _ . - _ _ _ __ . - .
_ . _ _ _ _ _ _ _ _ _ _ _ i REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 72
' (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
ANSWER 1.03 (3.00) Increase DNBR [+0.25] lowering inlet temp. lowers all core related temps, which increases the margin to DNB [+0.50] Decrease DNBR ;+0.25; power peaked to the top of core puts that region closer to DNB +0.50, Increase DNBR [+0.25] raising flow increases heat transfer which increases margin to DNB [+0.50] Decrease DNBR [+0.25] distortions in the radial shape will cause some fuel assemblies to be hotter than average, which is closer to DNB
[+0.50]
REFERENCE 1. LP-HFI-01-C p - 24,25,26 E0 - 1,4 K/A 193008K105 3.4/3.6 ANSWER 1.04 (3.00) a. 3 b. 4 I d. 6 e. 2 f. 5 [+0.5each] REFERENCE 1. LP-HFE-01-C p - 43 through 51 EO - 3 K/A 193006K115 3.1/ K108 3.4/ (***** CATEGORY 1 CONTINUED ON NLXT PAGE *= '*) _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ - _ -
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I i REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 73 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) i ANSWER 1.05 (3.00) Flow = 2300 gpm (+/-150) Pressure = 175 psig (+/-10) Flow = 25,500 gpm (+/-750) Pressure = 825 psig (+/-50) [+0.75each] REFERENCE 1. LP-HFE-01-C p - 32 through 34 EO - 6 K/A 191004K109 2.4/ K110 2.4/ K114 2.4/ ANSWER 1.06 (1.50) a. output = K X (magnitude of input signal) b. output = (magnitude of input signal) X (time of input error signal) c. output =(magnitude of rate of change) = high initial value decreasing to zero for step input [+0.5each] REFERENCE LP-ICT-01-C p - 39 through 46 EO - 10 K/A 191003K109 2.4/ ANSWER 1.07 (1.25) Lower level reading [+0.50]. Lowering the temperature in containment lowers the temp. in the reference leg of the D/P cell used to measure level [+0.25]. This increases the density of the water [+0.25] which causes the delta pressure across the D/P cell to increase [+0.25].
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i: REACTORPRINCIPLES(7%NTHERM0 DYNAMICS Page 74
, (7%) AND COMPONENTS (13%) (FUNDAMENTALS EXAM)
REFERENCE-e .
.
! 1.~ LP-PPL-02-C p - 27 EO -6
,
K/A'.191002K108 2.8/ . ANSWER 1.08 (2.00)
'SG heat transfer = Q = UA(Tavg - Tstm) ;+0.50'
Q,U and Tstm remain constant '+0. 25, A1 * (Tavgl - Tstm) = A2 * (Tavg2 - Tstm) +0.25' Given A2 = 0.9 * Al '+0.25'
From steam tables: Tsat for 1200 psia = 567 F '+0.25' A1 * (586 - 567) = 0.9 * A1 * (Tavg2 - 567) +0.25' Tavg2 = 588.1 F.(+ or. ,D,3-f acceptable) ;HO.25 05' REFERENCE 1. LP-HFB-01-C .p - 20 EO - 8 2. CE Steam Tables K/A 191006K113 2.8/2.9
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_ _ __ - - _ __ - - --. _ _ - - _ _ _ _ . _ - - . ___ . _ _ . .___ _ - _ _ - _ _ REACTOR PRINCIPLES (7%) THERM 0 DYNAMICS Page 75 (7%) AND-COMP 0NENTS (11%) (FUNDAMENTALS EXAM) ANSWER 1.09 (3.00) Reactor would go slightly supercritical [+0.50]. By doubling the count rate 1 - Keff. is halved. By adding the same amount of reactivity again, Keff become greater than one. [+1.00] OR 2 Reactor would go supercritical [+0.50]. delta rho = rho 2 - rhol = (K2 - K1) / K1K2 '+0.20 CR1 / CR2 = (1 - K2) / (1 - K1) l+0.20' eg. K1 = 0.90 '+0.10., Assume any(value for K1 20 / 40 = 1 - K2) / (1 - 0.90) K2 = 0.95 [+0.10] delta rho = (0.95-0.90) / (0.9) (0.95) = 0.0585 delta k/k '+0.10' add an additional 0.0585 delta k/k = (K3-0.95) / 0.95K3 l+0.10' K3 = 1.0063 > 1.0 therefore Rx. supercritical [+0.20' ]
(For all assumed K1 values K3 > 1.0) , None (OR the Rx. would return to a critical condition) [+0.50]
Since the power coefficient of reactivity is linear, the reactor power would increase approximately another 10% . [+1.0] REFERENCE LP-RTL-02-C p - 20 EO - 3 OPS Form 3209-3 p-1 LP-RTG-02-C p - 27 through 32 K/A 192008K120 3.8/ .
'
ANSWER 1.10 (3.00)
,
rho 1 = (k1 - 1) / kl = -0.004 [+0.50] kl = 1 / (1 - (-0.004)) = 0.996 [+0.25 100 (1 - 0.996) = 196 (1 - k2) [+0.25]] k2 = 0.998 [+0.25] rho 2 = (0.998 - 1) / 0.998 = -0.002 = - 200pcm [+0.25] rho 2 - rho 1 = -200 - (-400) = 200pcm [+0.25] approx.100 pcm is due to Xenon per Ops Form 3209-6, therefore remaining 100 pcm is due to boron [+0.50] Assume a differential boron worth = -10 pcm/ ppm [+0.25 100 pcm = (100 pcm) / (-10 pcm / ppm) = -10 ppm [+0.25]] 1000 ppm - 10 ppm = 990 ppm the new boron concentration [+0.25]
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e , , REACTOR PRINCIPLES(7%) THERMODYNAMICS Page 76 (7%) AND COMPONENTS (11%)-(FUNDAMENTALS EXAM) L 4
[ . . REFERENCE .I 1. LP-RTL-02-C p - 14.through 18 .
K/A 192008K104 3.8/ K10 .0/ , ' ANSWER 1.11 (1.00)'
' 1.- Because they are born at lower energy levels ~ they do not cause as many . fast fissions as prompt neutrons 2. Delayed neutrons are less likely to leak from the core so they are more likely to thermalize-and cause a thermal' fissio . They spend less time in the resonance region so they are less likely to be absorbed'in the resonance regio .They are therefore more likely to -
thermalize and cause a thermal fis on [any 2 at 0.50 each,1 REFERENCE .O i A CDM u Gyt Q LP-RTH-02-C p - 13 fgt .y MMg(cyy f; K/A 192003K107 3.0/3.0 l t-(***** END OF CATEGORY 1*****) . .
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2. ; EMERGENCY AND' ABNORMAL' PLANT EVOLUTIONS' Page 77
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' ANSWER .'2.01 (1.00)
~
-If it is needed for RCS cooldow [+1.0J J I' REFERENCE MNPS-3: E0P 35 E-2, Cautio K304 ..(KA's)
ANSWER 2.02 (2.00) manually tr.ip turbine Co SQ)- 2.- manually runback turbine CCh)
' 3((, close main steamline isolation valves (65 FQ)
g closemainsteamlineisolationbypassvalves@.5Q)
[+0.5] each Ch
} q ad/ 3b c,p ab TW 7N b5 REFERENCE MNPS-3: Lesson Plan FSI-01-C, p. .- MNPS-3: E0P 35 FR-S.1, step K306 000029K308 ..(KA's)
ANSWER 2.03 (1.00) Close the seal leakoff isolation valve [+0.3] within five minutes. [+0.2] Stop the affected RCP [+0.3] within thirty minutes. [+0.2]
..
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___ ' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 78 (27%) REFERENCE MNPS-3: A0P 3554, p. 3, steps 2a,b_& A210 ..(KA's) ANSWER 2.04 (1.50) 1,5,3,6,2,4
: Deduct 0.3 for ea, perturbation required to establish correct order] :+1.5]
REFERENCE ERG Executive Volume, Users Guide, pp. 10-1 . MNPS-3: Lesson Plan E0il-01-C, pp. 6- G012 000074G012 000007G012 000011G012 ..(KA's) ANSWER 2.05 (1.00) Radiation > 10*5R/hr requires an Engineering evaluation prior to relaxing " Adverse CTMT". [+0.5] Relax " Adverse CTMT" when temperature less than 180 degrees [+0.5] REFERENCE MNPS-3: Lesson Plan EOU-01-C, pp. 12-1 . MNPS-3: Lesson Plan E00-01-C, p. 25 000011K312 000011A204 ..(KA's)
' ANSWER 2.06 (1.00)
(d.) [+1.0]
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_ - _ . l EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 79 (27%) REFERENCE MNPS-3: E0P 35 ECA-0.0, steps 1- G011 ..(KA's) ANSWER 2.07 (1.00) hotwell level low (hotwell level hi/ low alarm). condenser in-leakage (condenser A/B/C vacuum , alarm). exhaust hood A/8/C temp hi alar G J condenser vacuum meter or recorder indicates loss of vacuu ' decrease in electrical outpu Any two [+0.5] each REFERENCE MNPS-3: A0P 3559 B, Lesson Plan A59-01-C, p. G011 ..(KA's)
,
ANSWER 2.08 (1.50) > To accommodate for void collapse. [+0.5] Ch o QCCCntCctAv ' @ L'&!CV May result in additional void formation in loops OR RCS [+0.5] To provide normal pressurizer spray. [+0.5] REFERENCE MNPS-3: E0P 35 ES-0.3 note 2, step 2, caution p. . MNPS-3: Lesson Plan 503-01-C, pp. 5, 9, 1 K101 ..(KA's)
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p , t EMERGENCY AND ABNORMAL PLANT EVOLUTION Page~80 (27%) i ANSWER 2.09 (2.00)- . Control Rod bank height below the R00 BANK LOW-LOW limit-alarm set poin .- Failure of two or more control rod clusters to' fully insert following a reactor trip or shutdow . Unexplained or uncontrolled reactivity increas . Failure'of Reactor Makeup Control System. (i.e. Must be bypassed to borate the RCS) Uncontrolled ' Reactor cooldown (following a reactor' trip or shutdown).
Any FOUR [+0.5] each l REFERENCE MNPS-3: A0P 3566 G011 ..(KA's) ANSWER 2.10 (1.00)
(b.) [+1.0]
REFERENCE 1 '. MNPS-3: Lesson Plan EDS-01-C, p. 2 K301 ..(KA's) ANSWER 2.11 (1.00) Ensure core cooling [+0.5] in the event of an operator misdiagnosis [+0.5]. (Small LOCA vs SGTR, Executive document RCP Trip Criteria to prevent core uncovery.)
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EMERGENCY =AND ABNORMAL PLANT EVOLUTIONS- Page 81-(27%)
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REFERENCE MNPS-3: Lesson Plan E30-01-C, p. K308 ..(KA's)- ANSWER 2.12' (2.50) !' Reactor coolant system (RCS) is subcooled [+0.25] greater than
'30 degrees.F.[+0.25].
- RCS pressure (0.25) is stable or increasing [+0.25].
3 .' .(Adequate secondary heat sink exists) -- total AFW flow [+0.25] is greater than 525 gpm [+0.25] OR narrow range level . in at least-one steam generator [+0.25] is greater than 4 percent [+0.25]. Pressurizer level [+0.25] is greater than 7% [+0.25].
' REFERENCE MNPS-3: E0P 35 E-0, step 2 K309 000008K305 000009K324 ..(KA's).
ANSWER 2.13 (2.00) Alert operator to a condition where chargin RCS is reduced [+1.0]~(boration is reduced)g flow into the
.
) EnsureglockvalvesF0.00]-andPORVs[44r56}areope REFERENCE
{/.CO] MNPS-3: Lesson Plan FSI-01-C, pp. 7- . E0P 35 FR-5.1, Step 4 K312 000024K302 ..(KA's)
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ANSWER 2.14 (1.00) RPCCW surge tank A OR B level lo j l RPCCW containment supply and return division valves AUTO ' clos . RPCCW train A OR B non-safety header AUTO isolatio . RPCCW suction header A (B) press lo annunciator li . RPCCW header supply flow hi annunciator li . RPCCW pump AUT0 trip /overcurrent annunciator li . Loss of service water cooling to any on service RPCCW exchange . Any high temperature and/or low flow alarms on components l served by RPCC Any FOUR (4) [+0.25] each i
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REFERENCE
: MNP5-3: Lesson Plan A61-01-C, p. . MNPS-3: A0P 3561, G011 ..(KA's)
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-_ - . - - - . - -- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 83 (27%) . ANSWER 15 1.50)
dl$n(aEci , 'to ' differential pressure or lowVtOVf low with pumpCW Oy running and flow control valve open [+0.5] . charging pumps from th Rh'ST boric acid transfer pumps frem beric acid ta i safety injection pumps frca n'.lST containment recirculation spray pumps fr.c= th; "h'ST RWST gravity feed v-i; cl! chovc peths cacept r,seci Any two (2) [+0.5] each:: tive forcc [:0.3]; curcc [;0.2] REFERENCE HNPS-3: E0P 3505, Steps 2, 5, 9, and 1 A207 000025K301 ..(KA's) ANSWER 2.16 (1.50) collapse by increasing RCS pressure [+0.4] . collapse by starting [an RCP used [+0.4] on non-condensible voids+ ((0.3]venttocontainment}+0.4]:
' 3 $0T i REFERENCE l MNPS-3: Lesson Plan FI3-01-C, p. G012 ..(KA's)
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_ EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 84 (27%) ANSWER 2.17 (1.25) S/G pressure [+0.25] Containment pressure [+0.25] greater than 17.7 psia [+0.25], or steamline pressure [+0.25] less than 660 psig [+0.25]. REFERENCE MNPS-3: E0P 35 E-0, Step 23, 12 000009K321 000040K301 000040A201 ..(KA's) ANSWER 2.18 (1.50) Letdown via RV head vent 0.5] to PRT charging from RWST [+0.5][+(VCT outlet isolated).(or excess letdown )[+0.5]; REFERENCE MNPS-3: Lesson Plan A63-01-C, p. . MNPS-3: A0P 3563, A203 ..(KA's) ANSWER :.19 (2.00) a rod bottom light . decreasingTavg,[11RCSpressure) auto rod withdraw Power range channel deviation alarm Tavg-Tref deviation alarm Power range flux rate hi (one channel) PR upper / lower detector hi flux deviation Rod position deviation alarm One rod bottom alarm any four (4) [+0.5] each
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i REFERENCE MNPS-3: Lesson Plan A52-01-C _,
000005A201 ..(KA's) i
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i l
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ANSWER 3.01 (1.50) .
-
h CLCtC[
\ (Y C ,
l Iodinc scaveng4ag-[+0.5] 7d ' To minimize (the effect of chloride and caustic stress) corrosion on mechanical systems and components. [+1.0] REFERENCE l MNPS-3 FSAR Chapter 6.2, TSs 3/4.6. K402 026020K401 ..(KA's) l l ANSWER 3.02 (1.50) . To reduce thermal shock to the spray line and spray nozzl ! 2. To maintain Pzr. chemistry uniform with the RC !
[+0.5] each pressurizer spray line temperature low alarm. [+0.5]
;
REFERENCE i MNPS-3: Lesson Plan PZR-01-C, p. 1 < 010C'00K603 010000A102 010000A108 ..(KA's) ANSWER 3.03 (1.50) >
, . Temperature (in the discharge line of each valve)
(TI-464,465,466) .
"
2. Discharge flow Indicator (Thermal Flow Monitor on MB-4)
[+0.5] each primary makeup water [+0.5]
f
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REFERENCE MNPS-3: Lesson Plan PPT-01-C, p. 3 A410 007000K401 ..(KA's) l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) 1 PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 87 RESPONSIBILITIES ~(10%) ANSWER 3.04 (1.00) ;3 P'd Containment pressure (HI-3). [+0.5] RWST empty (RWST EMPTY QSS PP 0FF alarm) (<.M,725 gal.) [+0.5] REFERENCE FF,m MNPS-3: Tech Spec, Table 3.3-3, OP 330 K403 026000A301 ..(KA's) , l
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ANSWER 3.05 (1.50) Loading or unloading 5% of full power per minut . Step load changes of +/- 10% of full powe . Step load reduction of 50% of full power with steam dump [+0.5] each ; REFERENCE i MNPS-3: Lesson Plan RCS-01-C, p. 14, PPL-01-C, K602 ..(KA's) l l
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ANSWER 3.06 (3.00) . Engine overspeed (110%) [+0.5] Generator differential current (Primary Lockout Relay). [+0.5] Low Lube oil pressure (<50 psig) [+0.5] . Jacket water pressure LOW HIGH main bearing tem . Crankcase pressure HIGH Jacket water temperature HIGH Lube oil temperature HIGH Engine / turbo hi vibration High crankcase pres Any FOUR (4) [+0.25] each . Generator overcurrent Generator reverse power , i Loss of generator field Generator over voltage Neutral Any two (2) ground over current
[+0.25] each
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REFERENCE MNPS-3: Lesson Plan EGS-01-C, pp. 40-42, MNPS-3: OP 3346 K402 ..(KA's) ANSWER 3.07 (2.00) . P-4 (reactor trip) C-7 (load rejection) Steam pressure mode
[+0.5] each . C-9 (condenser available interlock) [+0.5]
REFERENCE e.NPS-3 : Lesson Plan SDS-01-C, pp. 18-1 K603 ..(KA's)
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ANSWER 3.08 (1.00) Cross-tie to Service air s g g'g Manual X-tie to Unit 2. E+yste ] P0.5] s 3 T&p:p Gli COmfLLB1 Ga k C.ii J ,'d k {{c.cddy
.
REFERENCE MNPS-3: A0P 3562 step 2c, OP 3332A K402 ..(KA's) ANSWER 3.09 (1.00) !- A rate compensated steamline low pressure SI can result [+0.75] from the valves . opening too quickly [+0.25]. REFERENCE MNPS-3: OP 3201, 4.2 G010 ..(KA's) ANSWER 3.10 (1.50) . Low DC Voltage (<125 volts) High DC Voltage (> 144 volts) Charger phase failure (loss of phase) High charger temperature (175F +/- 3F) No charge (low DC current) Battery bus ground Battery bus under voltage Any FOUR [+0.25] each hours minimum [+0.5] REFERENCE MNPS-3: Lesson Plan 125-01-C, p. 4-5, OP 3345 G008 ..(KA's) ) l
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I PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 90 RESPONSIBILITIES (10%) l ANSWER 3.11 (1.00) M84 group step counters master cycler counters slave cycler counters bank overlap counters internal memory and alarm pulse to analog converters for RPf Any FOUR [+0.25] each REFERENCE MNPS-3: Lesson Flan R00-01-C, p. 4 K402 ..(KA's) ANSWER 3.12 (1.00)
(b.) [+1.0]
i i REFERENCE HNPS-3: Lesson Plan CHS-01-C, p. 1 K602 ..(KA's) ANSWER 3.13 (1.00) Control Building Inlet Ventilation Radiation Containment Pressure (HI-1) SI Signal (manual p atc= tic) Manual
[+0.25] each REFERENCE MNPS-3: Tech Specs Table 3.3- K403 072000K104 ..(KA's) (***** CATEGORY 3 CONTINUE 0 ON NEXT PAGE *****)
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ANSWER' 3.14 (1.50) SG Hi-Hi Level (P-14) [+0.5] 2.- SIS.[+0.5] ' Low Tavg (564F) [+0.3] coincident with Reactor Trip (P-4)
[+0.2]
REFERENCE .. MNPS-3: Lesson Plan FWS-01-C, p. 4 K419_ ..(KA's) ANSWER: 3.15 (1.00)
(d.) [+1.'0]
REFERENCE MNPS-3: Lesson Plan CHS-01-C, pp'. 7-1 K405 004010A204 ..(KA's) ANSWER 3.16 (1.50)
: Gross overcompensation would cause an erroneously low indicate flux on the'IR channels [+0.5] which would cause premature
.
re-energizing of the source range detectors [+0.5] resulting in a [ reactor trip from SR high flux trip [+0.5]. REFERENCE MNPS-3: Lesson Plan, p. 2 K604 ..(KA's) L
. -ANSWER 3.17 (1.00) .(c.) [+1.0]
I' !:-
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_ PLANT SYSTEMS (38%) AND ply!T-WIDE GENERIC Page 92 RESPONSIBILITIES (10%) REFERENCE NNPS-3: Lesson Plan NIS-01-C, p. 2 K601 ..(KA's) ANSWER 3.18 (1.00)
(a.) [+1.0]
RUERENCE MNPS-3: Lesson Plan NIS-01-C, p. 1 K501 ..(KA's) ANSWER 3.19 (1.00) Limit AFW flow rate to one or two SGs [+0.5] following a SG or feed ruptw+ [+0 5] .
( ,'glC [f Va /
REFERENCE MNPS-3: Lesson Plan FWA-01-C, p. 1 G007 ..(KA's) ANSWER 3.20 (2.50) . lo-lo SG 1evel [+0.15] 1 of 4 SGs [+0.10] SIS '+0.25] CDA '+0.25' LOP '+0.25 lo-lo SG level [+0.3] 2 of 4 SGs [+0.2] normal - demin water storage tank (0WST) [+0.25] Alternates: service water (SWS) 2. condensate storage tank (CST) l 3. domestic water system (DMS) 4. water treating system (WTS) Any THREE (3) [+0.25] each (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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REFERENCE- MNPS-3: Lesson Plan FWA-01-C, pp. 18, 9, 6 &' K401 061000K406 ..(KA's) ANSWER 3.21 (1.00) Temperature VCT [+0.25] [+0.25] b. . > 17% ' 0.25'
+
open l+0.25 REFERENCE MNPS-3: Lesson Plan CHC-01-C, pp. 14 & 1 K403 004020K403- ..(KA's) ANSWER 3.22 (1.50) Post'SI, RCS pressure < 1435 psia with at least ONE SI or CHS pum ' RPCCW lost to.both containment header . Thermal barrier cooling lost and seal injection < 6 gp . RCS temperature > 400 degrees F and VCT temperature
> 135 degrees . RCS temperature < 400 degrees F and VCT temperature
> 150 degrees . Hi-Hi shaft / frame vibratio . Hi lower bearing water temperature.
' Hi bearing temperatur . Hi motor tem Any six (6) [+0.25]peratur each REFERENCE l MNPS-3: Lesson Plan RCP-01-C, p. 3 '
'003000A202 ..(KA's)
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ANSWER 3.23 (1.50). . I f. . 4
[+0.25] each REFERENCE MNPS-3: Lesson Plans 6Kv-01-C, p. 2; 4K-01-C, pp. 3 & 4; 480-01-C, p. 5; 125-01-C, p. K201 ..(KA's)
' ANSWER 3.24 (1.50) containment high pressure (HI-2), >or= 18.0 psia, 2/3 high steam pressure. rate, -100 psi /sec, 2/3 in 1/4 loops low steam line pressure, < 660 psig, 2/3 ir. 1/4 leaps
'
. [+0.5] each; signal [+0.2]; setpoint [+0.15]; coincidence [+0.15]
REFERENCE MNPS-3: Lesson Plan MSS-01-C, pp. 23 & 2 K405 ..(KA's) .
!
ANSWER 3.25 (1.50) OT delta-T (C-3) J '0P delta-T (C-4) l'+0.5'
+ > stator cooling runback [+0.5]
REFERENCE NNPS-3: 108D684, sheet . MNPS-3: Lesson Plan TRB-01-C, p. 3 K412 ..(KA's)
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1. - _ 3. ' PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 95 RESPONSIBILITIES (10%) ANSWER 3.26.'(1.50) 1. - RCP thernial barrier HX RCP (upper and lower) bearing oil coolers Excess letdown HX
[+0.5] each -
REFERENCE-1.- MNPS-3: Lesson Plan CCP-01-C, pp. 14-& 3 K102 ..(KA's) ANSWER 3.27 (1.50)
.
F '+0.25' '+0.25' . +0.25' =3' '+0.25' +0.25' l+0.25:
-REFERENCE MNPS-3: Lesson Plan RPS-02-C, pp. 42-4 K610 ..(KA's)
ANSWER 3.28 (1.00)
(b.) [+1.0]
REFERENCE CFR 2 . MNPS-3: Lesson Plan HPR-01-C, pp. 6 & 1 K103 ..(KA's)
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} (***** CATEGORY 3 CONTINVED ON NEXT PAGE *****) _ _ _ _ _ _ _ . _ _ - - - - _ _ _ _ _ _ a
_-_ _ - _ _ - _ _ _-_- - i ' 3. - PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 96 RESPONSIBILITIES-(10%) ANSWER 3.29 (2.00) are aware of how much radiation exposure you are allowed to receive for this job are aware of the. personnel monitoring devices you are required to carry 3
,_ . are aware of the radiation levels present in the work area ( ctcu T/r4J are aware of the protective clothing you are: required to f wear . areawareoftheotherinstructionsspecifiedonthisRWF/ -
Any FOUR (4) [+0.5] each ( 6% -
>7 -
REFERENCE N h l '. 'MNPS-3i SHP 4912, " General Instructions," p. 1 K103 ..(KA's) ANSWER 3.30 '(1.00) ~2 - Red Ta _ Green. Striped Hold Tag Blue Tag- Red Tag
[+0.25] each REFERENCE MNPS-3: ACP-QA-2.06A, K102 ..(KA's)
ANSWE .31 (1.00)
(c.) [+1.0]
REFERENCE MNPS-3: OP 3260, K101 ..(KA's)
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_ _ - _ - _ _ - _ - _ _ _ _ _ - - - _ _ _ _ _ _-_ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ l l PLANT SYSTEMS'(38%) AND PLANT-WIDE GENERIC Page 97 RESPONSIBILITIES (10%) ANSWER 3.32 (1.00) Heavy]gasec
[+0.3 and reduce present in containment oxygen content of the willair settle to low spaces
[+0.7].
REFERENCE MNPS-3: OP 3212, 3. K113 ..(KA's) ANSWER 3.33 (1.00)
(c.) [+1.0]
REFERENCE MNPS-3: OP 3212, K105 ..(KA's) ANSWER 3.34 (1.50) a.- To position valves and/or breakers as listed on the Tag Log Sheet (SF210). [+0. 5] l To assure the positions of valves and breakers remain , as listed on the Tag Log Sheet. [+0.5] When permission to CANCEL the CLEARANCE is obtained. [+0.5] REFERENCE MNPS-3: ACP-QA-2.06A, 6.8, K102 ..(KA's) ANSWER 3.35 (1.50) A plant operator [+0.5] and Security representative [+0.5] for explosives [+0.5] (or other abnormal conditions) Uh $hd bdAT) h O""
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) g g Mg w_-_- _ _ - - _ - -- . _ - .
_ _ - - _ -- - - - - - - - . . _ - - - - l- !. t PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 98 RESPONSIBILITIES (10%) REFERENC . MNPS-3: ACP 7.05A, 6. K105 ..(KA's)
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l TEST CROSS REFERENCE Page 1 QUESTION VALUE REFERENCE
, 1.01 1.50 90001 1.02 2.50 90002 1.03 3.00 90003 ,
1.04 3.00 90004 1.05 3.00 90005 1.06 1.50 90006 1.07 1.25 90007 1.08 2.00 90008 1.09 3.00 90009 1.10 '3.00 90010 1.11 1.00 90011
......
24.75 2.01 1.00 1275 2.02 2.00 5878 2.03 1.00 90012 i 2.04 1.50 90013 2.05 1.00 90014 2.06 1.00 90015 2.07 1.00 90016- < 2.08 1.50 90017 2.09 2.00 90018 2.10 1.00 90019 2.11 1.00 90020 2.12 2.50 90021 2.13 2.00 90022 2.14 1.00 90024 2.15 1.50 90025 2.16 1.50 90026 2.17 1.25 90027 ' 2.18 1.50 90028 2.19 2.00 90030 ___ .. 27.25 3.01 1.50 90046 3.02 1.50 90047 3.03 1.50 90050 3.04 1.00 90051 3.05 1.50 90052 i 3.06 3.00 90053 3.07 2.00 90054 3.08 1.00 90055 i 3.09 1.00 90064 3.10 1.50 90065 3.11 1.00 9000058 3.12 1.00 9000062 3.13 1.00 9000063 3.14 1.50 9000064 l i 3.15 1.00 9000072 3.16 1.50 90031 f 3.17 1.00 2337 3.18 1.00 3565 3.19 1.00 90034 i
,_ _ _ _ _ _ - _ _ _ _ _ - -_ - _ ,_ . TEST CROSS REFERENCE Page 2
! -0UESTIO VALUE REFERENCE i- ' 3.20 2.50 90035 3.21 1.00 10434 3.22 1.50 90037 3.23 1.50 90044 3.24 1.50 90045 3.25 1.50 90048 3.26 1.50 90049 3.27 1.50 90063 3.28 1.00 90043 3.29 2.00 90056 3.30 1.00 90057 3.31 1.00 90058 3.32 1.00 90059 3.33 1.00 90060 3.34 1.50 90061 - 3.35 1.50 90062 f ___... 48.00
......
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