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| issue date = 10/07/1993
| issue date = 10/07/1993
| title = Forwards Comments on Written Part of Operator Licensing Exams Administered During Wk of 930927
| title = Forwards Comments on Written Part of Operator Licensing Exams Administered During Wk of 930927
| author name = ZERINGUE O J
| author name = Zeringue O
| author affiliation = TENNESSEE VALLEY AUTHORITY
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:ENCLOSURE 3 Tennessee Valley Authority.
{{#Wiki_filter:ENCLOSURE 3 Tennessee Valley Authority. Post Office Box 2000, Decatur. Alabama 35609.2000 O. J. "Ike Zeringue Vice President, Browns Ferry Nuclear Plant OCT       07   19%
Post Office Box 2000, Decatur.Alabama 35609.2000 O.J."Ike Zeringue Vice President, Browns Ferry Nuclear Plant OCT 07 19%Mr.Stewart D.Ebneter Regional Administrator ATTH: Branch Chief, Operator Licensing U.S.Huclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323  
Mr. Stewart D. Ebneter Regional Administrator ATTH: Branch Chief, Operator Licensing U.S. Huclear Regulatory Commission Region         II,   Suite 2900 101     Marietta Street, NW Atlanta, Georgia 30323


==Dear Sir:==
==Dear     Sir:==
In the Matter of Tennessee Valley Authority Docket Hos.50-259 50-260 50-296 BROWHS FERRY NUCLEAR PLANT (BFH)-REACTOR OPERATOR (RO)AHD SEHIOR REACTOR OPERATOR (SRO)LICENSING EXAMIHATIOH COMMENTS In accordance with the requirements of the HUREG 1021,"Operator Licensing Examiner Standard," Section ES-402, TVA is providing the enclosed comments on the written part of the Operator Licensing Examinations.
The examinations were administered at BFN during the week of September 27, 1993.A copy of the enclosed examination comments was given to the lead examiner on September 30, 1993.9312130396 931D28 pre roach osoooa59 V PDR


Mr.Stewart D.Ebneter Page 2 cc~ov~>>If you have any questions, please telephone Terry Dexter at (205)?29-3470.Sincerely, O.J.Zeringue Enclosure cc (Enclosure):
In the Matter of                                                                Docket Hos. 50-259 Tennessee         Valley Authority                                                         50-260 50-296 BROWHS FERRY NUCLEAR PLANT                          (BFH) REACTOR OPERATOR (RO) AHD SEHIOR REACTOR OPERATOR (SRO) LICENSING EXAMIHATIOH COMMENTS In accordance with the requirements of the HUREG 1021, "Operator Licensing Examiner Standard," Section ES-402, TVA is providing the enclosed comments on the written part of the Operator Licensing Examinations. The examinations were administered at BFN during the week of    September 27, 1993.
Mr.Robert M.Gallo Chief, Operator Licensing Branch, DLPQ U.S.Nuclear Regulatory Commission MS OWFN 10D-22 Washington, D.C.20555 Mr.M.E.Ernstes Chief, Operator Licensing Section 2 U.S.Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, HW Atlanta, Georgia 30323 Mr.R.V.Crlenjak, Project Chief U.S.Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, HW Atlanta, Georgia 30323 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 HRC Resident Inspector Browns Ferry Huclear Plant Route 12 Box 637 Athens, Alabama 35611 EHCLOSURE Tennessee Valley Authority (TVA)Browns Ferry Huclear Plant (BFH)s 0 e ato e s a o 0
A copy        of the enclosed examination comments was given to the lead examiner on September 30, 1993.
HLT 9208 written examination post examination comments RO question 01;SRO question 01 Question: The reactor is being restarted near the end of core life following a one day outage.Reactor power is at 32%.Control rods 34-23 and 58-23 have been isolated at position 00.When rod 42-43 is withdrawn, alarm 2-XA-55-5A-29, CRD ACCUM PRESS LOW LEVEL HIGH, actuates on panel 9-5.WHICH ONE (1)of the following requirements is in effect under current plant con ditionsV a.Exercise control rod 42-43 at least one notch at least once each day.b.Clear the accumulator trouble alarm on rod 42-43 prior to moving to the next control rod.c.Control rod 42-43 must be fully inserted and electrically disarmed.d.Observe nuclear instrumentation for response each time rod 42-43 is moved.Answer key answer: D Comment: For any event that can directly affect reactivity, it is considered to be of a critical nature and strict procedural compliance along with conservative actions must be followed.This caution is prevalent throughout BFNP procedures such as: SSP 12.17 2-0I-85 2-GOI 100-1A 2-Gol 100-1B 2-GOI 100-1C Reactivity Management, page 9 Control Rod Drive system Precaution and Limitations 3.1.13, page 8, 10, 11[INPO SOER 84-002]Unit Startup From Cold Conditions section 3.12 page 12[INPO SOER 89-006, SOER 88-002]Unit Startup From Cold Shutdown to Hot Standby section 3.11 page 12;[INPO SOER 89-006, SOER 88-002]Unit Startup from Hot Standby page 9 section 3.10.[INPO SOER 89-006, SOER 88-002]During the situation described in the stem of this question, rod 42-43 is potentially inoperable if the accumulator alarm is valid.This would make answer B also correct since during a reactor startup, it would be assumed that the next control rod movement would be a rod withdrawal, it would not be conservative action to continue rod withdrawal with an potentially inoperable rod that is not fully inserted.Additionally, the alarm response procedure directs dispatching of personnel to determine if the alarm is valid and directs the use of 2-Ol-85 to clear the alarm.This would be the expected course of action should this event occur in the plant.Answer D is correct because this requirement is in place per Technical Specifications whether the rod is being inserted or withdrawn.
9312130396 931D28 pre roach osoooa59 V                          PDR
I Proposed resolution:
Accept either B or D as a correct answer


HLT 9208 written examination post examination comments RO question¹57;SRO question¹47 Question: WHICH ONE (1)of the following is an acceptable way to perform position verification on a throttled valve?(assume that the valve is installed in a system with local indication controlled by the valve, and the valve has a rising stem)a.observe the initial valve operator's action in positioning the throttled valve b.perform an independent visual check of the valve position by observing the valve stem c.independently verify the valve position by a second valve operation d.by observing flow indication through the throttled valve's system Answer key answer: A Comment: SSP 12.6 (Verification program)page 7, states that throttled valves are normally verified using second party verification.
Mr. Stewart D. Ebneter Page 2 cc~  ov ~>>
However, section 3.3.3 (also on page 7)states that alternate verification methods may be used at the discretion of shift supervisory personnel.
If you have  any questions, please telephone Terry Dexter at (205) ?29-3470.
One of these alternate verification techniques is the use of process parameters.
Sincerely, O. J. Zeringue Enclosure cc (Enclosure):
Since the question stem asks for thief lygp D is also correct.Proposed resolution:
Mr. Robert M. Gallo Chief, Operator Licensing Branch, DLPQ U.S. Nuclear Regulatory Commission MS OWFN  10D-22 Washington, D.C. 20555 Mr. M. E. Ernstes Chief, Operator Licensing Section 2 U.S. Nuclear Regulatory Commission Region  II, Suite 2900 101 Marietta Street, HW Atlanta, Georgia 30323 Mr. R. V. Crlenjak, Project Chief U.S. Nuclear Regulatory Commission Region II,  Suite 2900 101 Marietta Street, HW Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission ATTN: Document  Control Desk Washington, D.C. 20555 HRC Resident Inspector Browns Ferry Huclear Plant Route 12 Box 637 Athens, Alabama 35611
Accept either A or D as the correct answer HLT 920B written examination post examination comments RO question 061;SRO question 053 Question: Four licensed UOs attended a fellow employee's birthday party the last night of their vacation and alcohol was served to all.Below shows when each UO stopped drinking alcoholic beverages.
UO A1:05 am UO B2:05 am UO C 3:05 am UO D 4:05 am From the four UOs listed above, WHICH ONE (1)of the following states the number available for NRC licensed work the same morning at 7:00 am?(Assume that all the UOs have blood alcohol levels within SSP 1.6 guidelines) a.ONE b.TWO c.THREE d.FOUR Answer key answer: B Comment: SSP 1.6 (Fitness for duty)states on page 6, section 3.1.4 that a person covered by the scope of the procedure shall abstain from the consumption of alcohol for at least 5 hours preceding any scheduled work.Therefore, to be available for work at 7:00 am, an individual would have to stop drinking prior to 2:00 am.Since only UO A had stopped drinking prior to 2:00 am, he or she would be the only one available to work at 7:00 am.Answer B is not correct.Proposed resolution:
Accept A as the correct answer


HLT 9208 written examination post examination comments SRO question¹62 Question: The control room was evacuated due to a fire 5 minutes ago.Atl the immediate actions for"Control Room Abandonment" were performed.
EHCLOSURE Tennessee  Valley Authority (TVA)
Current plant conditions are: The reactor has been verified to be shutdown.RPV level is>+60 inches.RPY pressure is 700 psig and decreasing slowly.The MSIVs are open and cannot be closed, The turbine bypass valves appear to functioning normally.An operator is stationed to control RPY level and pressure with HPCI as necessary WHICH ONE (1)of the following is the appropriate emergency action level for this situation?
Browns Ferry Huclear Plant (BFH) s     0 e  ato    e s          a o
a.Unusual Event b.Alert c.Site Area Emergency d.General Emergency Answer key answer: C Comment: The stem of the question states that the control room was evacuated due to a fire, but does not state the location of the fire.Due to the proximity of some offices to the control room, it is conceivable that a fire in those offices could result in enough smoke in the control room to warrant evacuation without an actual fire in the control room.With this limited information, it is merely a judgment call by the SOS as to whether the fire is in i I (alert)or actually ff i vi I r (site area emergency).
Additionally some of the information given in the stem is confusing:
(1)HPCI is being used to control level and pressure, but in 2-AOI-100-2, step 4.2.10, HPCI would be disabled (2)The MSIVs are stuck open, reactor pressure is dropping, but the bypass valves are functioning normally.There is no available indication of bypass valve position at the backup control panel.The pressure decrease could be considered to be normal (depending on recent power history)with reactor water level at+60 and normal auxiliary steam loads in service and without supporting indications (radiation or temperature alarms, or reports from the plant)the slow pressure decrease would not necessarily be indicative of a leak during the first 5 minutes of the event.With no data on radiation levels in the plant or coolant activity levels, reference to the general descriptions of the emergency classifications on pages 1 and 2 of EPIP-1 could lead to alert as the appropriate classification.
Proposed resolution:
Accept either B or C as the correct answer HLT 9208 written examination post examination comments RO question&#xb9;97;SRO question&#xb9;96 Question: RHR loop I is in shutdown cooling taking suction through Shutdown Cooling suction valves 74<7 and 74-48.Loop II of RHR remains in the LPCI standby lineup.Due to misoperation of ventilation systems, drywell pressure increases to 2.5 psig.WHICH ONE (1)of the following describes the response of the RHR system?a.Valves 74-47 and 74-48 close, Loop I suppression pool suction valves auto and BOTH RHR loops inject to the vessel.b.Valves 74-47 and 74-48 close, Loop I RHR pumps trip, suppression pool suction valves auto open but only Loop II injects.c.Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression suction valves remain closed and only Loop II injects.d.Valves 74-47 and 74-48 close, Loop I RHR pump trip, Loop I suppression pool suction valves remain closed and NEITHER Loop injects.Answer key answer: C Comment: 2-0I-74 page 69 of 202, and Lesson Plan OPL171.044 page 24 states the actions that occur on a group 2 isolation when the RHR system is operating in the shutdown cooling mode.On the isolation signal, both of the Loop I and II inboard injection valves would receive a close signaI and would not automatically reopen until the group 2 isolation signal was reset on panel 9-3.Therefore, neither loop of RHR would inject without some form of operator manual action.Since this action was not listed in the stem of the question, answer C could not be correct.Proposed resolution:
Accept D as the correct answer 0 0 ENCLOSURE 4 RESOLUTION OF FACILITY COMMENTS ON WRITTEN EXAM 1.SRO Question 1 (RO Question 1)Facility comment accepted.2.SRO Question 47 (RO Question 57)Facility comment accepted.3.SRO Question 53 (RO Question 61)Facility comment accepted.4.SRO Question 62 (No RO question)Facility comment accepted.5.SRO Question 96 (RO Question 97)Facility comment accepted.
U.S.NUCLEAR REGULATORY
'OMMISSION SITE SPECIFIC EXAMINATION REACTOR OPERATOR LICENSE REGION 2 Afas 4~CANDIDATE~S NAME: FACILITY: Browns Ferry 1, 2,&3 REACTOR TYPE: BWR-GE4 DATE ADMINISTERED:
93/09/27 INSTRUCTIONS TO CANDIDATE:
Use the answer sheets provided to document your answers.Staple this cover sheet on top of the answer sheets.Points for each question are indicated in parentheses after the question.The passing grade requires a final grade of at least 804.Examination papers will be picked up four (4)hours after the~~'nation starts.TEST VALUE CANDIDATE'S SCORE 100.00 TOTALS FINAL GRADE All work done on this examination is my own.I have neither given nor received aid.Candidate's Signature REACTOR OPERATOR ANSWER SHEET Page 2 I Multiple Choice (Circle or X your choice)If you change your answer, write your selection in the blank.MULTIPLE CHOICE 001 a b c d 002 a b c d 003 a h c d 004 a b c d QQ5 a b c d 006 a h c d 007 a b c d 008 a b c d 0 a b c d a b c d a b c d 017 018 019 020 a h c d b c d b c d b c d 021 a b c d a b c d 012 a h c d 013 a b c d 014 a b c d 015 a b c d 016 a b c d 023 a b c d Q24 a b c d 025 a b c~d 026 a b c d 027 a b c d 028 a h c d 029 a b c d 030 a b c d 031 a b c d 032 a b c d 033 a b c d 034 a h c d 035 a b c d 036 a b c d 037 a b c d 038 a b c d 039 a b c d 040 a b c d 041 a b,.c d 042 a h c d 043 a b c d 044 a h c d 045 a b c d


REACTOR OPERATOR Page 3 AN'SWER SHEET~~Multiple Choice (Circle or X your choice)Zf you change your answer, write your selection in the blank.a b c d a b c d a b c d 058 a b c 059 a b c 060 a b c d d d 061 a b c d 062 a b c 063 a b c I 064 a b c d d d 065 a b c d 046 a b c d 047'b c d 048 a b c d 049 a b c d 050 a b c d 051 a b c d 052 a b c d 053 a b c d 054 a b c d 069 a b c, d 070 a b c d 071 a b c d 072 a b c d 073 a b c d 074 a b c d 075 a b c d 076 a b c d 077 a b c d 078 a b c d 079 a b c d 080 a b c d Q81 a b c d 082 a b c d Q83 a b c d 084 a b c d 085 a b c d 086 a b c d 087 a b.c d 088 a b c-d 066 a b c d 067 a b c d a b c d 089 a b c d 090 a b c d 091 a b c d REACTOR OPERATOR d,i A N S N E R S H E E T Page 4~~~~Multiple Choice (Circle or X your choice)If you change your answer, write your selection in the blank.092 a b c d 093'b c d 094 a b 095 a b 096 a b 097 a b 098 a b 099 a b 100 a b c d c d c d c d c d c d c d 0 (**********
0 HLT 9208 written examination post examination comments RO question 01; SRO question 01 Question: The reactor is being restarted near the end of core life following a one day outage. Reactor power is at 32%. Control rods 34-23 and 58-23 have been isolated at position 00. When rod 42-43 is withdrawn, alarm 2-XA-55-5A-29, CRD ACCUM PRESS LOW LEVEL HIGH, actuates on panel 9-5. WHICH ONE (1) of the following requirements is in effect under current plant con ditionsV
END OF EXAMINATION
: a.     Exercise control rod 42-43 at least one notch at least once each day.
**********)
: b.     Clear the accumulator trouble alarm on rod 42-43 prior to moving to the next control rod.
0 Page 5 RC RULES AND GUIDE IN S FOR L CENSE EXAMINATIONS 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 penalties.
: c.     Control rod 42-43 must be fully inserted and electrically disarmed.
2.3.After the examination has been completed, you must sign the~statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination.
: d.     Observe nuclear instrumentation for response each time rod 42-43 is moved.
This must be done after you complete the exam-ination.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, cheating.4.Use black ink or dark pencil only to facilitate legible repro-ductions.5.6.Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.Fill in the date on the cover sheet of the examination (if necessary).
Answer key answer: D Comment: For any event that can directly affect reactivity, it is considered to be of a critical nature and strict procedural compliance along with conservative actions must be followed. This caution is prevalent throughout BFNP procedures such as:
7.Print your name in the upper right-hand corner of the first page of each section of your answer sheets.8.Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.9.The point value for each question is indicated in parentheses after the question.10.Partial credit will NOT be given.ll.If the intent of a question is unclear, ask questions of the examiner only.12.When you are done and have turned in your examination, leave the examination area as defined by the examiner.If you are found in this area while the examination is still in progress, your license may be denied or revoked.
SSP 12.17              Reactivity Management, page 9 2-0I-85                Control Rod Drive system Precaution and Limitations 3.1.13, page 8, 10, 11 [ INPO SOER 84-002 ]
Page 6 Blank Page REACTOR OPERATOR C%.Page 7 TION: 001 (1.00)The reactor is being restarted near the end of core life following a one day outage.Reactor power is at 324.Control rods 34-23 and 58-23 have been isolated at position 00.When rod 42-43 is withdrawn, alarm 2-XA-55-5A-29, CRD ACCUM PRESS LOW LEVEL HIGH, actuates on panel 9-5.WHICH ONE (1)of the following requirements is in effect under the current plant conditions?
2-GOI 100-1A            Unit Startup From Cold Conditions section 3.12 page 12 [INPO SOER 89-006, SOER 88-002]
a.Exercise control rod 42-43 at least one notch at least once each day.b.Clear the accumulator trouble alarm on rod 42-43 prior to moving the next control rod.c.Control rod 42-43 must be fully inserted and electrically disarmed.d.Observe nuclear instrumentation for response each time rod 42-43 is moved.ION: 002 (1.QO)Control Rod 38-23 has been selected for a single notch withdrawal from position 02 to position Q4.The following response from the CRD system was observed: Insert light illuminates and goes out.Withdrawal light illuminates and goes out.Settle light illuminates and goes out.The operator also observes and reports that the selected rod is now at position 06 and is continuing to drift out.A Rod Drift alarm is also present.WHICH ONE (1)of the following has caused the conditions?
2-Gol 100-1B            Unit Startup From Cold Shutdown to Hot Standby section 3.11 page 12; [INPO SOER 89-006, SOER 88-002]
a.the automatic sequence timer has failed b.stuck open.,collet fingers c.excessive HCU cooling water pressure d.leaking scram inlet valve 0
2-GOI 100-1C            Unit Startup from Hot Standby page 9 section 3.10.
REACTOR OPERATOR Page 8 STION: 003 (1.00)WHICH ONE (1)of the following states the condition identified by an illuminated blue scram light for each control rod on the Full Core Display?a.Both inlet and outlet scram valves for that rod are open.b.Both inlet and outlet scram valves for that rod are closed.c.Both scram pilot air valves for that rod are energized.
[INPO SOER 89-006, SOER 88-002]
d.Both scram pilot air valves for that.rod are deenergized.
During the situation described in the stem of this question, rod 42-43 is potentially inoperable if the accumulator alarm is valid. This would make answer B also correct since during a reactor startup, it would be assumed that the next control rod movement would be a rod withdrawal, it would not be conservative action to continue rod withdrawal with an potentially inoperable rod that is not fully inserted. Additionally, the alarm response procedure directs dispatching of personnel to determine if the alarm is valid and directs the use of 2-Ol-85 to clear the alarm. This would be the expected course of action should this event occur in the plant. Answer D is correct because this requirement is in place per Technical Specifications whether the rod is being inserted or withdrawn.
QUESTION: 004 (1.00)Following performance of a torus-drywell vacuum breaker operability surveillance instruction, the vacuum breaker has the following indications:
I Proposed resolution: Accept either B or D as a correct answer
Check light-OFF~~Green light-ON Red light-OFF WHICH ONE (1)of the following states the position of the vacuum breaker'?a.fully closed b.cracked open (less than 3 degrees open)c.partially open (between 3 degrees and 80 degrees open)d.fully open (greater than 80 degrees open)
REACTOR OPERATOR Page 9 STION: 005 (1.00)While a control rod is being inserted using the EMERGENCY IN contxol switch, rod motion stops.WHICH ONE (1)of the following could have terminated rod insertion?
a.the automatic sequence timer deenergizes b.loss of power to the Rod Position 1'nformation System c.a RWM select block d.a RWM insert block QUESTION: 006 (1.00)WHICH ONE (1)of the following will result in a control rod block on input from IRM B?a.Mode switch is in REFUEL, IRM B is downscale on range 1.is in STARTUP, IRM B indicates 30 on range 3.c.Mode switch is in STARTUP, IRM B downscale on range 5.d.Mode switch is in RUN, IRM B indicates 105 on range 8.


REACTOR OPERATOR B.Page 10~~~~~STION: 007 (1.00), WHICH ONE (1)of the following sets of conditions would result in the Unit 2 Automatic Depressurization system 95 second timer starting?Assume all sensors, power supplies, and interlocks are operating properly.a~b.co d.RPV level remains at-125" for 4 minutes and 30 seconds, Drywell pressure peaks at 2.10 psig,>>A>>Core Spray pump discharge pressure is 190 psig,"C>>Core Spray pump discharge pressure is 195 psig, no other ECCS pumps are running.RPV level remains at-125>>for 4 minutes and 30 seconds, Drywell pressure peaks at 2.10 psig,>>A>>Core Spray pump discharge pressure is 175 psig,>>C>>Core Spray pump discharge pressure is 195 psig, no other ECCS pumps are running.RPV level remains at-135>>for 3 minutes and 25 seconds, Drywell pressure peaks at 2.50 psig,>>A>>Core Spray pump discharge pressure is 190 psig,>>B>>Core Spray pump discharge pressure is 195 psig, no other ECCS pumps are running.RPV level remains at-135>>for 3 minutes and 25 seconds, Drywell pressure peaks at 2.50 psig,>>B>>Core Spray pump discharge pressure is 190 psig,>>D>>Core Spray pump discharge pressure is 175 psig, no other ECCS pumps are running.QUESTION: 008 (1.00)A Main Steam Relief Valve (MSRV)lifts due to high reactor pressure.WHICH ONE (1)of the following could cause a significant DECREASE in the MSRV's lift pressure if it subsequently lifts a second time?a.tailpipe vacuum breaker failed CLOSED b.tailpipe vacuum breaker failed OPEN.c.high drywell pressure d.high suppression pool level REACTOR OPERATOR Page 11~~STION: 009 (1.00)Control rod drive mechanism 25-24 has exceeded 350 degrees F, alarm TA-85-7, CONTROL ROD DRIVE UNIT TEMP HIGH annunciator (2-XA-55-5A, Window 17)is alarming.WHICH ONE (1)of the following describes the correct response to this hot CRD mechanism'?
HLT 9208 written examination post examination comments RO question    &#xb9;57;  SRO question &#xb9;47 Question: WHICH ONE (1) of the following is an acceptable way to perform position verification on a throttled valve? (assume that the valve is installed in a system with local indication controlled by the valve, and the valve has a rising stem)
a.Check for scram discharge valve leakage, leave the drive hot.b.Check for scram discharge valve leakage, cool the drive by giving it repeated drive signals.c.Check for scram inlet valve leakage, leave the drive hot.d.Check for scram inlet valve leakage, cool the drive by giving it repeated drive signals.QUESTION: 010 (1.00)WHICH ONE (1)of the following signals from the Post-Treatment Radiation Monitoring System will initiate an AUTOMATIC ISOLATION of the Off gas charge to the main stack (FCV-66-28)?
: a. observe the initial valve operator's action in positioning the throttled valve
a.High-High-High trip in Channel A;Channel B is clear b.High trip in Channel A;downscale trip in Channel B c.High trip in Channel A;XNOP trip in Channel B.d.Downscale trip in Channel A;INOP trip'in Channel B.
: b. perform an independent visual check of the valve position by observing the valve stem
REACTOR OPERATOR dS., Page 12 STXON: 011 (1.00)During a LOCA, the SRO directs you to initiate drywell sprays.The RHR SYS I CTMT VLV SELECT switch is in SELECT and the 2/3 Core coverage keylock switch is in OVERRIDE.RHR SYS I DW SPRAY INBD VLV (2-FCV 61)cannot be opened.WHICH ONE (1)of the following interlocks is preventing valve operation?
: c. independently verify the valve position by a second valve operation
a.RPV level less than-122 inches b.RPV level less than-183 inches c.LPCI initiation signal NOT present d.Drywell pressure less than 1.96 psig QUESTION: 012 (1.00)An earthquake has resulted in a complete loss of off-site power and LOCA on Unit 2.Drywell pressure has increased to 5 psig on Unit 2.rgency Diesel Generator"C" has failed to start.All other emergency nt equipment is functioning normally.EXCH ONE (1)of the following ntifies the Core Spray pumps that will respond to the automatic start signal?a.2A, 28 b.2A, 2B, 2D c.2A, 2C d 2Ar 2Ct 2D
: d. by observing flow indication through the throttled valve's system Answer key answer: A Comment: SSP 12.6 (Verification program) page 7, states that throttled valves are normally verified using second party verification. However, section 3.3.3 (also on page 7) states that alternate verification methods may be used at the D is also correct.
thief discretion of shift supervisory personnel. One of these alternate verification techniques is the use of process parameters. Since the question stem asks for lygp Proposed resolution: Accept either A or D as the correct answer


REACTOR OPERATOR d5.Page 13 The Control Room has been evacuated.
HLT 920B written examination post examination comments RO question 061; SRO question 053 Question: Four licensed UOs attended a fellow employee's birthday party the last night of their vacation and alcohol was served to all. Below shows when each UO stopped drinking alcoholic beverages.
RHR pump 2C is required for operation in the shutdown cooling mode and the SDC suction valve is OPEN.RHR pump breaker power has been transferred to the local Emergency position.WHICH ONE (1)of the following will prevent the pump from starting?a.Shutdown Cooling Supply valve, 74-47, is CLOSED.b.RHR Drain pump suction valve, 74-104, is OPEN.c.A Unit 2 Accident Signal is present.d.Undervoltage on Shutdown Board C.QUESTION: 014 (1.00)~~Condxtzons have been met to start the Automatic Depressurization System (ADS)95 second timers.WHICH ONE (1)of the following identifies the initiation signals that will NOT automatically reset if conditions ar?a.95 second TIMER and Low Reactor Water Level TIMER b.95 second TIMER and Low Reactor Water Level signal c.High Drywell pressure signal and Low Reactor Water Level TIMER d.High Drywell pressure signal and Low Reactor Water Level signal
UO A1:05 am UO B2:05 am UO C 3:05 am UO D 4:05 am From the four UOs listed above, WHICH ONE (1) of the following states the number available for NRC licensed work the same morning at 7:00 am?
(Assume that all the UOs have blood alcohol levels within SSP 1.6 guidelines)
: a. ONE
: b. TWO
: c. THREE
: d. FOUR Answer key answer: B Comment: SSP 1.6 (Fitness for duty) states on page 6, section 3.1.4 that a person covered by the scope of the procedure shall abstain from the consumption of alcohol for at least 5 hours preceding any scheduled work.
Therefore, to be available for work at 7:00 am, an individual would have to stop drinking prior to 2:00 am. Since only UO A had stopped drinking prior to 2:00 am, he or she would be the only one available to work at 7:00 am. Answer B is not correct.
Proposed resolution: Accept A as the correct answer


REACTOR OPERATOR C5.Page 14 STION: 015 (1.00)Reactor Recirculation pump"A" is operating at 1310 RPM and is providing 40,000 gpm flow.Reactor Recirculation pump"B" is operating at 1325 RPM.WHICH ONE (1)of the following states the LOWEST flow for Reactor Recirculation pump"B" that would indicate possible jet pump failure7%~a.44,000 gpm b.44,600 gpm c.46,000 gpm d.46,600 gpm QUESTION: 016 (1.00)Reactor Recirculation pumps are not operated below 204 speed.WHICH ONE (1)of the following states the basis for this limit?a.Ensures adequate Net Positive Suction Head.b;Prevents thermal stress in the vessel lower head region.c.Prevents unstable fluid coupler operation.
HLT 9208 written examination post examination comments SRO question &#xb9;62 Question: The control room was evacuated due to a fire 5 minutes ago. Atl the immediate actions for "Control Room Abandonment" were performed. Current plant conditions are:
d.Limits harmonic vibration of the jet pumps.
The reactor has been verified to be shutdown.
RPV level is >+60 inches.
RPY pressure is 700 psig and decreasing slowly.
The MSIVs are open and cannot be closed, The turbine bypass valves appear to functioning normally.
An operator is stationed to control RPY level and pressure with HPCI as necessary WHICH ONE (1) of the following is the appropriate emergency action level for this situation?
: a. Unusual Event
: b. Alert
: c. Site Area Emergency
: d. General Emergency Answer key answer: C Comment: The stem of the question states that the control room was evacuated due to a fire, but does not state the location of the fire. Due to the proximity of some offices to the control room, it is conceivable that a fire in those offices could result in enough smoke in the control room to warrant evacuation without an actual fire in the control room. With this limited information, it is merely a judgment call by the SOS as to whether the fire is            in      i I      (alert) or actually ff i        vi I r (site area emergency). Additionally some of the information given in the stem is confusing: (1) HPCI is being used to control level and pressure, but in 2-AOI-100-2, step 4.2.10, HPCI would be disabled (2) The MSIVs are stuck open, reactor pressure is dropping, but the bypass valves are functioning normally. There is no available indication of bypass valve position at the backup control panel. The pressure decrease could be considered to be normal (depending on recent power history) with reactor water level at+60 and normal auxiliary steam loads in service and without supporting indications (radiation or temperature alarms, or reports from the plant) the slow pressure decrease would not necessarily be indicative of a leak during the first 5 minutes of the event. With no data on radiation levels in the plant or coolant activity levels, reference to the general descriptions of the emergency classifications on pages 1 and 2 of EPIP-1 could lead to alert as the appropriate classification.
Proposed resolution: Accept either B or C as the correct answer


REACTOR OPERATOR Page 15 I~~~~STION: 017 (1.00)The plant is operating at full power when the"B" Reactor Recirculation pump's suction valve drifts to 884 open.WHICH ONE (1)of the following states the expected response?a.Pump speed decreases to 284.b.Pump speed decreases to 454.c.Pump speed decreases to 754.d.Pump trips.QUESTION: 018 (1.00)While Reactor Recirculation pump"A" is operating at.804, a failure in pump's individual M/A station occurs and a signal is sent to the Bailey Positioner calling for a pump speed of zero.WHICH ONE (1)of the following states the expected response of the pump?a.Scoop tubes will lock and speed will remain at 804.b.Speed decreases to 284.c.Speed decreases to 204.4 d.Speed decreases to zero.
HLT 9208 written examination post examination comments RO question    &#xb9;97; SRO question &#xb9;96 Question: RHR loop I is in shutdown cooling taking suction through Shutdown Cooling suction valves 74<7 and 74-48. Loop II of RHR remains in the LPCI standby lineup. Due to misoperation of ventilation systems, drywell pressure increases to 2.5 psig. WHICH ONE (1) of the following describes the response of the RHR system?
1 REACTOR OPERATOR dS., Page 16 STION: 019 (1.00)WHICH ONE (1)of the following sets of cavity pressures indicate a failure of the&#xb9;2 (outer)Reactor Recirculation pump seals?a 0 b.C~d.&#xb9;1 CAUITY PRESSURE 1000 psig 1000 psig 500 psig 1000 psig&#xb9;2 CAVITY PRESSURE 100 psig 1000 psig 500 psig 500 psig QUESTION: 020 (1.00)During an accident on Unit 2, power is lost from the Division II ECCS inverter.WHICH ONE (1)of the following HPCI system capabilities is lost'l a.Flow control b.Automatic initiation c.Automatic isolation d.Automatic trip REACTOR OPERATOR Page 17\~~~~STION: 021 (1.00)HPCI is in standby readiness.
: a. Valves 74-47 and 74-48 close, Loop I suppression pool suction valves auto and BOTH RHR loops inject to the vessel.
WHICH ONE (1)of the following states the HPCI pump suction status if Torus level is+5 inches and the Condensate Storage Tank volume is 9900 gallons.7 a'.Suction is from the CST but can be manually transferred to the Torus without bypassing interlocks.
: b. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, suppression pool suction valves auto open but only Loop II injects.
b.Suction is from the CST and CANNOT be transferred to the Torus without bypassing interlocks.
: c. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression suction valves remain closed and only Loop II injects.
c.Suction is from the Torus but can be manually transferred to the CST without bypassing interlocks.
: d. Valves 74-47 and 74-48 close, Loop I RHR pump trip, Loop I suppression pool suction valves remain closed and NEITHER Loop injects.
d.Suction is from the Torus and CANNOT be transferred to the CST without bypassing interlocks.
Answer key answer: C Comment: 2-0I-74 page 69 of 202, and Lesson Plan OPL171.044 page 24 states the actions that occur on a group 2 isolation when the RHR system is operating in the shutdown cooling mode. On the isolation signal, both of the Loop I and II inboard injection valves would receive a close signaI and would not automatically reopen until the group 2 isolation signal was reset on panel 9-
QUESTION: 022 (1.00)mode switch is in run and APRM B has failed downscale.
: 3. Therefore, neither loop of RHR would inject without some form of operator manual action. Since this action was not listed in the stem of the question, answer C could not be correct.
No operator ion is taken.WHICH ONE (1)of the following correctly describes the ected response if the stated IRM failures occur?a.IRM B Hi-Hi or ZRM G ZNOP will result in a half scram of RPS Channel A.b.IRM B Hi-Hi or ZRM G INOP will result in a half scram of RPS Channel B.c.IRM B ZNOP or ZRM H Hi-Hi will result in a half scram of RPS Channel A.d.ZRM B ZNOP or ZRM H Hi-Hi will result in a half scram of RPS Channel B.
Proposed resolution: Accept D as the correct answer
0 REACTOR OPERATOR Page 18 STION: 023 (F 00)With the plant operating at 100%power, Alarm XA-55-3F, window 31, CORE SPRAY SYS II SPARGER BREAK, actuates.WHICH ONE (1)of the following identifies the core spray line break location required to actuate the alarm?a.'nside of the reactor vessel shroud b.inside of the reactor vessel and outside of the shroud c.anywhere inside of the reactor vessel d.anywhere on the pressurized portion of the injection line QUESTION: 024 (F 00)During a LOCA, reactor water level is dropping at a rate of 20 inches per minute.RPV level is currently-132 inches.RPV pressure is 468 psig and Drywell pressure is 2.5 psig.WHICH ONE (1)of the following cribes the expected status of the Unit 2 Core Spray system?a.Core Spray system has NOT initiated.
b.Core, Spray pumps have started, injection valve is CLOSED.c.Core Spray pumps have started, injection valve is OPEN, but pump flow is deadheaded against the closed check valve.d.Core Spray pumps have started and are injecting into the vessel.I REACTOR OPERATOR d.Page 19 TION: 025 (1.00)The PSC pumps trip and cannot be restarted.
WHICH ONE (1)of the following conditions is a possible reason for this occurrence?
a.RPV level is-118 inches.b.RHR Room temperature is 182 degrees F.c.250U RMOV power is lost to Div I.d.Suppression pool level is-6.25 inches.QUESTION: 026 (1~00)During plant startup with reactor power on range 5 of the IRMs, an MSIV closure occurs.WHICH ONE (1)of the following conditions is a possible reason for this occurrence?
'a.Reactor water level is-83 inches.t b.MSL tunnel temperature is 210 degrees F.c.Reactor pressure is 840 psig.d.Drywell pressure is 2.6 psig.
0 0 REACTOR OPERATOR d.)Page 20 STION: 027 (1.00)During a plant transient, the Main Steam Isolation Valves isolated on a valid Group I isolation signal.All control rods inserted and immediate operator actions reguired by procedure have been taken.A decision has been made to unisolate MSL"D" (valves 1-51 and 1-52)to allow use of the main condenser.
Given the following plant conditions:
Reactor water level is-5 inches.Reactor pressure is 700 psig.Drywell pressure is 3.2 psig.MSL Area temperature is 185 degrees P.WHICH ONE (1)of the following states actions required to reset the Group 1 isolation?
a.The MSIV switches for ONLY valves 1-51 and 1-52 must be placed in the CLOSE position.b.A jumper must be installed AND the MSIV switches for ONLY valves 1-51 and 1-52 must be placed in the CLOSE position.c.The MSIV switches for ALL MSIUs must be placed in the CLOSE position.t d.A jumper must be installed AND the MSIV switches for ALL MSIVs must be placed in the CLOSE position.  
>l REACTOR OPERATOR Page 21~~~~~STION: 028 (1.00)'onditions exists on Unit 2 that require the initiation of Standby Liquid Control.WHICH ONE (1)of the following contains two indications that SLC is injectingi a.Explosive valve current flow indicator reads 0 milliamps AND the blue SQUIB VALVE CONTINUITY light is illuminated.
b.Explosive valve current flow indicator reads 4.milliamps AND the blue SQUIB VALVE CONTINUITY light is illuminated.
c.Explosive valve current flow indicator reads 0 milliamps AND the blue SQUIB VALVE CONTINUITY light is extinguished.
Explosive valve current flow indicator reads 4 milliamps AND the blue SQUIB VALVE CONTINUITY light is extinguished.
QUESTION: 029 (1 00)Off-Gas Pretreatment High Radiation alarm for Unit 2 has just ated.WHICH ONE (1)of the following conditions could have caused alarm?a.Failure of the on-line Catalytic Recombiner.
b.Failure of a condensate demineralizer resin trap.c.Trip of the operating Steam Jet Air Ejector.d.Increased steam content of off-gas exhaust flow.
0 REACTOR OPERATOR d.)Page 22 STION: 03 0 (1 00)A TIP trace is being run in the automatic mode using TIP Channel A.While the TIP is at the top of core limit, the reactor scrams on low water level after a loss of electrical power.120VAC power is lost to the TIP system.RPV level reaches+10 inches minimum.WHICH ONE (1)of the following describes the response of the TIP System following the scram?a.The TIP channel will shift to manual reverse mode withdraw to the in shield limit and the ball valve will close.b.The TIP channel will shift to manual reverse mode, withdraw to the in shield limit and the ball valve will fail to close.The Shear valve can be fired if isolation is required.c.The TIP channel will remain at it's present position.The Shear valve can be fired if isolation is required.d.The TIP channel will remain at it's present position.The Shear valve will be incapable of firing if isolation is required.TION: 031 (1.00)Given that the following conditions exist during refueling on Unit 3: Bridge is directly over the core Main hoist is loaded to 550 lbs, in the full up position Aux hoist is loaded to 350 lbs, in the full up position Rod 03-17 is at position 02 Mode Switch is in STARTUP WHICH ONE (1)of the following responses would indicate normal interlock functioning on the refuel bridge?(FORWARD means away from the core, REVERSE means toward the core.)a.Bridge will move in the forward AND reverse directions.
b.Bridge will move in the forward direction BUT NOT reverse direction.
c.Bridge will move in the reverse direction BUT NOT forward direction.
d.Bridge will NOT move in either direction.
o REACTOR OPERATOR B.Page 23 STION: 032 (1.00)WHICH ONE (1)of the following describes the trip logic for the Reactor Building Ventilation Radiation Monitors (Reactor Zone Ventilation Radiation Monitors and Refuel Floor Radiation Monitors)a.Two Hi levels in 1 division OR one downscale in 2 divisions b.Two Hi levels in 1 division OR two downscales in 1 division c.One Hi level in 2 divisions d.One Hi level in 2 divisions OR one downscale in 2 divisions OR two downscales in 1 divisions QUESTION: 033 (1.00)WHICH ONE (1)of the following describes how the RWCU system is connected to the RPV in each of the three units?a.Suction is from the>>A>>Recirc line on all units, return the>>B>>feed line for Units 1 and 2, and the>>A>>and>>B>>lines for Unit 3.is via feed b.Suction is from the>>A>>Recirc line on all units, return the>>B>>feed line for Units 1 and 3, and the>>A>>and>>B>>lines for Unit 2.is via feed c.Suction is from the>>B>>Recirc line on all units, return is via the>>B>>feed line for Units 1 and 3, and the>>A>>and>>B>>feed lines for Unit 2.d.Suction is from the>>B>>Recirc line on all units, return is via the>>B>>feed line for Units 1 and 2, and the>>A>>and>>B>>feed lines for Unit 3.
REACTOR OPERATOR d5.Page 24 STION: 034 (1.00)Shutdown Bus 1 was initially being supplied by Unit Board 2B when Shutdown Board B bus transfer switch (43)transfers to MANUAL.WHICH ONE (1)of the following is a possible reason for this occurrence?
4 a.Shutdown Board B Normal Feeder Breaker (1616)Emergency Control Power Transfer Switch has been placed in the Emergency position.b.The alternate power supply to Shutdown Bus 1 has sensed a high load differential condition across the 87Uxz breaker.c.A phase or ground overcurrent condition has been sensed by the NORMAL shutdown bus power supply.d.The residual voltage relay has shut in the close circuit of the alternate power supply to Shutdown Bus 1.QUESTION: 035 (1.00)cerning the Diesel Generator Mode Switch, WHICH ONE (1)of the lowing modes of operation is used when the diesel generator is in allel with off-site power?a.Test b.Single Unit c.Units In Parallel d.Parallel With System 0 0 REACTOR OPERATOR d5.Page 25 STION: 036 (1 00}A LOCA has occurred.Drywell pressure is 3 psig and no off-site power is available.
WHICH ONE (1)of the following is the only load allowed to be sequenced onto its associated shutdown board before forty (40)seconds have elapsed'a.RHRSW pumps b.A and D Control Air Compressors c.Drywell blowers d.RBCCW pumps QUESTION: 037 (1.00)V WHICH ONE (1)of the following would be affected if the+/-24 VDC system was totally lost'a.Neutron Monitoring Instrumentation b.Control Room Annunciators c.Diesel Control and Logic power d.480V Shutdown Board Control Power REACTOR OPERATOR d5.Page 26 STION: 038 (1.00)Normal and alternate supply breakers to unit boards 3A and 3B have tripped and the Unit 3 Shutdown Board 43 auto transfer switches have transferred to MANUAI.WHICH ONE (1)of the following describes what has happened?a.An automatic shutdown bus transfer has taken place.b.The associated 4 kV shutdown board has failed to transfer to the alternate power supply.c.The associated backfeed switch has been placed in the BACKFEED position.d.A manual U3 Unit Board high-speed transfer to the alternate power supply failed.QUESTION: 039 (1.00)zng full power operation on Unit 2, the mechanical spaces exhaust fan ls.WHICH ONE (1)of the following is a possible consequence of this lure?a.Buildup of contaminants in the Radwaste building atmosphere b.Development of an explosive atmosphere in battery rooms c.Main steamline isolation d.Unreliable Emergency Range level indication REACTOR OPERATOR dS.Page 27 STION: 040 (1.00)A fire pump has automatically started.could have caused the initiation?
WHICH ONE (1)of the following a.A fog water system was manually started at the Main turbine oil tanks.b.Turbine building area temperatures have steadily risen 40 degrees in the last five minutes.c.Main Transformer temperature has increased to 190 degrees F.d.Unit 2 HPCI room temperature has increased from 100 to 212 degrees F over the last 30 minutes.QUESTION: 041 (1.00)An RSW pump has started to automatically increase level in the RSW storage tank when a fire pump receives an automatic start signal.WHICH (1)of the following describes the response of the RSW storage tank lation valves and the RSW pump?a.The RSW pump immediately trips.The isolation valves CLOSE but will AUTOMATICALLY reopen when the fire pump stops.b.The RSW pump immediately trips.The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire pump stops.c.The RSW pump continues running in support of the fire pump.The isolation valves CLOSE but will AUTOMATICALLY reopen when the fire pump stops.d.The RSW pump continues running in support of the fire pump.The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire pump stops.
REACTOR OPERATOR d%.Page 28~~STION: 042 (1 00)The plant is being shutdown and reactor power is stable at 254 when annunciator"OFFGAS HOLDUP TEMPERATURE HIGH" actuates due to low flow through the SZAE condensers.
WHICH ONE (1)of the following could have caused the event'?a.In-leakage of noncondensible gases into the main condenser.
b.SPE Heat Exchanger Balancing valve (FCV 2-190)open.c.Condensate demineralizer bypass valve (FCV 2-130)open.d.Only two condensate pumps running.QUESTION: 043 (1.00)The Condensate system is aligned for short cycle cleanup.WHICH ONE (1)of the following describes the flowpath?a.Flow returns to the condenser from the outlet of the SJAE condensers.
b.Flow returns to the condenser from the condensate booster pump discharge header.c.Flow returns to the CST from the outlet of the SZAE condensers.
d.Flow returns to the CST from the condensate booster pump discharge header.
REACTOR OPERATOR Page 29 STION: 044 (1." 00)RHR loop 1 is in standby when electrical power is lost to 480 volt RMOV board 2D.WHICH ONE (1)of the following RHR flowpaths is NOT available?
a.torus cooling b.drywell spray c.LPCI injection d.pump minimum flow QUESTION: 045 (1.00)WHICH ONE (1)of the following RPS trip signals can be bypassed from the Control Room?a.Scram Air Header low pressure~~~~b.Loss of RPS power c.Hi RPV pressure d.Hi MSL radiation QUESTION: 046 (1.00)WHICH ONE (1)of the following describes the expected DIRECT response t ne Main Steam Line radiation monitor reaching it's high trip setpoint?.a.Full scram and full Group 1 Isolation b.Full scram and half Group 1 Isolation c.Half scram and full Group 1 Isolation d.Half scram and half Group 1 Isolation REACTOR OPERATOR d5.Page 30 STION: 047 (1.00)WHICH ONE (1)of the following states when the Rod Block Monitor system initiates a null sequence?a.reference APRM fails upscale b;reference APRM is changed to alternate c.recirculation flow changes by 10%d.reactor power drops below 30%QUESTION: 048 (1.00)Unit 2 is operating at 100%power with FWLC in automatic three element control when the"A" steam flow transmitter fails downscale.
WHICH ONE (1)of the following describes the expected control room INDICATIONS after conditions stabilize?(Assume no operator action is taken)a.Feed Flow 100%, Steam Flow 75%, Reactor Level 18 inches b.Feed Flow 75%, Steam Flow 75%, Reactor level 18 inches c.Feed Flow 100%, Steam Flow 75%, Reactor Level 33 inches d.Feed Flow 75%, Steam Flow 75%, Reactor Level 33 inches I.ld REACTOR OPERATOR dS.Page 31 I STION: 049 (1.00)Unit 2 is operating at 1004 power with the master feedwater controller is in 3 element when the FWLC system experiences one of the two feedwater flow inputs.WHICH ONE (1)of the describes the expected plant response?(Assume no operator taken)level a loss of following action is a.Reactor level will stabilize at normal with.FWLC remaining in 3 element control.b.Reactor level will stabilize at normal with FWLC in single element.c.Reactor level will stabilize about 15 inches below normal with FWLC remaining in 3 element control.d.Reactor level will stabilize about 15 inches below normal with FWLC in single element.QUESTION: 050 (1.00)~~~~~H ONE (1)of the following conditions will result in a RFPT trip?a.RFPT"B" suction pressure 95 psig for 25 seconds.b.Condenser low vacuum 10" Hg.c.RFP (pump)low oil pressure 6 psig.d.RPV level 52" for 10 seconds.
0 0 REACTOR OPERATOR Page 32 STION: 051 (1.00)Unit 2 has just experienced a small LOCA and Drywell pressure has increased to 3 psig.Reactor pressure is SQQ psig and steady.The increase in Drywell temperature causes reliability concerns for WHICH ONE (1)of the following level instruments' a.Emergency Range indicators, b.Normal Range indicators c..Post Accident indicators d.Shutdown Floodup indicators QUESTION: 052 (1.00)WHICH ONE (1)of the following describes.how an electrical drawing is verified as being the current revised copy'P t a.Refer to the Controlled Drawing Holders list of drawings that contains only the latest revised drawings.b.Refer to the Shift Operations Supervisor/Assistant Shift Operations Shift log book.c.Refer to the Lead Unit Operators log book.d.Refer to Document Control for assistance.
0 REACTOR OPERATOR Page 33 STION: 053 (1.00)A surveillance is in progress, with the SOS (initials O.H.)direct'ing the actions of the"UO" (initials S.L.)i.n the plant.The procedure is in the possession of the"UO".WHICH ONE (1)of the following describes the initials that the"UO" is to place on the surveillance step?a;OH/SL b.SL/OH c.OH d.SL QUESTION: 054 (1.00)WHICH ONE (1)of the following statements DEFINES a radiation area?a.An area where an individual can be exposed to dose rates exceeding 5 mrem/hr or receive up to 40 mrem total exposure in any eight (8)hour period.b.An area where an individual can be exposed to dose rates exceeding 100 mrem/hr or receive up to 3 REM total exposure in any five (5)consecutive days.c.An area where an individual can be exposed to dose rates exceeding 5 mrem/hr or receive up to 1QQ mrem in any five (5)consecutive days.d.An area where an individual can be exposed to dose rates exceeding 10 mrem/hr or receive up to 8Q mrem in any eight (8)hour period.
REACTOR OPERATOR Page 34 STION: 055 (1 00)During a Site Area Emergency, the Site Emergency Director is informed'that the UO on building rounds did not report to the Control Room and does not respond to the plant paging system.WHICH ONE (1)of the following is the maximum exposure allowed to an individual in order to search for the unaccounted for operator?a.BFNP administrative limits b.10CFR20 non-emergency limits c.25 REM d.75 REM QUESTION: 056 (1.00)WHICH ONE (1)of the following is the maximum length of time a confined space entry permit is valid without an extension?
b.12 hours c.24 hours d.72 hours REACTOR OPERATOR B.'>Page 35 STION: 057 (1.00)WHICH ONE (1)of the following is an acceptable way to perform position verification on a throttled valve?(assume that the valve is installed in a system with a local flow indication controlled by the valve, and the valve has a rising stem)a.observe the initial valve operator's action in positioning the throttled valve b.perform an independent visual check of the valve position by observing the valve stem c.independently verify the valve position by a second valve operation d.by observing flow indication through the throttled valve's system QUESTION: 058 (1.00)event occurs that, is required to be logged in the Operating Lo NE (1)of the following states ALL the Operations Narrative Logs gs~the event would be required to be recorded in according to SSP-12.1,"Conduct of Operations".
a.SOS b.SOS, ASOS c.SOS, ASOS, UO d SOS J ASOS g UO~STA REACTOR OPERATOR Page 36~~STION: 059 (1.00)A valve will be manipulated at rated power that may influence RPV level.WHICH ONE (1)of the following forms of verification would ensure the correct valve is manipulated?
a.Supervisor Verification b.Second Party Verification c.Independent Verification d.Responsible Manager Verification QUESTION: 060 (1.00)The plant is operating at 80%power with three (3)hours remaining on a 24 hour LCO.The Wilson Load Dispatcher requests the base load to be increased 25 MWE for the remainder of the operating run.WHICH ONE (1)of the following actions should be taken?t a.Before increasing the electrical load, the request must be approved by EITHER the SOS or the ASOS.b.Before increasing the electrical load, the, request must be approved by BOTH the SOS and the ASOS.c.Before increasing the electrical load, the request must be approved by any licensed individual.
d.The request for a load increase cannot be approved at this time.
REACTOR OPERATOR Page 37~~~STION: 061 (1.00)Four licensed UOs attended a fellow employee's birthday party the last night of their vacation and alcohol was served to all.Below shows when each UO stopped drinking alcoholic beverages.
UO'A':05 am UO'B':05 am UO'C':05 am UO'D':05 am From the four UOs listed above, WHICH ONE (1)of the following states the number available for NRC licensed work the same morning at 7:00 am?(Assume that all the UOs have blood alcohol levels within SSP 1.6 guidelines).
a.ONE b.TWO t c.THREE d.FOUR 0
REACTOR OPERATOR Page 38 STION: 062 (1 00)Six operators enter the RCA.Upon exiting, the following measurements were observed using the frisker: Operator 1 Operator 2 Operator 3 Operator 4 Operator 5 Operator 6 200 cpm above background skin contamination.
85 cpm above background skin contamination.
50 cpm above background personal clothing contamination.
150 cpm above background personal clothing contamination.
250 cpm above background personal clothing contamination.
125 cpm above background personal clothing contamination.
WHICH ONE (1)of the following indicates the number of operators that ,are considered contaminated in accordance with procedure SSP 5.1,"Radiation Protection Plan"?a.Four b.Three co Two d.One QUESTION: 063 (1.00)Units 1 and 3 are defueld.Unit 2 is at 1004 power.A transient on Unit 2 results in declaring a Site Area Emergency and activation of the accountability siren.WHICH ONE (1)of the following describes the expected response of the Unit 1 and Unit 3 operators?
a.Remain at their respective units and wait for further direction.
~b.Report to Unit 2 and assist as directed by the SOS.c.Unit 1 UOs report to the Unit 2 control room and Unit 3 Uos remain at their station.d.Unit 3 Uos report to the Unit 2 control room and Unit 1 Uos remain at their station.
REACTOR OPERATOR C3.Page 39 TION: 064 (1.00)WHICH ONE (1)of the following conditions requires entry into an EOI'?a.Reactor Building floor drain sump level at 69 inches.b,.Drywell temperature at 146 degrees F.c.Secondary Containment dp is-0.19 inches H20.d.Reactor zone ventilation exhaust radiation level at 68 mR/hr.QUESTION: 065 (1 00)During an ATWS with the reactor at high power, EOI-1, step RC/Q-7, directs that recirculation be run back to minimum prior to tripping the Reactor recirculation pumps.WHICH ONE (1)of the following is the basis for this action?a.Prevent MSIU closure on high flow.b.Promote boron mixing.c.Prevent Main Generator reverse power trip.d.Prevent Main Turbine high RPU water level trip.


REACTOR OPERATOR CS.Page 40 STION: 066 (1.00)Given the following plant conditions:
0 0
Reactor pressure is 930 psig RPV level is+28 inches RCIC is injecting Twenty control rods are at position 48 Reactor power is 9000 cps on the SRMs and decreasing A 90 degree F/hr cooldown is in progress WHICH ONE (1)of the following would require termination of cooldown?a.RPV level lowers to+15 inches.b.SRM count rate increases to 10000 cps.c.Main turbine bypass valves fail closed.d.Drywell pressure begins to increase.ION: 067 (1.00)WHICH ONE (1)of the following responses will be noted on Unit 2 during a complete loss of Unit 2 I&C Bus during reactor operation?
a.Unit 2 reactor water level increase b.Unit 1 Loop A recirculation pump speed increase c.Unit 3 SJAE flow to offgas system increase d.Unit 2 main steam tunnel temperature increase
.REACTOR OPERATOR Page 41 STION: 068 (1.00)During a plant transient on Unit 2, a Group I isolation is caused by high radiation.
Five control rods fail to insert.Suppression pool level is 12 feet and pool temperature is 94 degrees F.WHICH ONE (1)of the following identifies the systems available to help maintain pressure below 1040 psig'?a.HPCI, RCIC b.RCIC, RWCU'.RWCU, MSL drains d.MSL drains, HPCI QUESTION: 069 (1.00)During an ATWS, EOIs direct the operator to inhibit ADS automatic~~~~wdown when Standby Liquid Control is injected.WHICH ONE (1)of the lowing states the basis for this requirement'?
a.ADS actuation would impose a severe pressure and temperature transient on the vessel.b.ADS would result in the removal of boron after it has been injected.c.Core damage could result from a large power excursion if low pressure ECCS systems were to inject.d.ADS/MSRV system flow rate is incapable of assuring fuel cooling through steaming above 54 reactor power.
REACTOR OPERATOR d%.Page 42 STION: 070 (1.00)While the reactor is operating at 90%power, reactor pressure is observed decreasing at an approximate rate of 200 psig per minute.WHICH ONE (1)of the following is the expected immediate operator action'?a.Scram the reactor and place the pressure control unit in manual.b.Scram the reactor and close the MSIVs.c.Take manual control of the reactor pressure control unit.d.Manually transfer to the backup pressure control unit.QUESTION: 071 (1.00)A failure of Drywell Control Air has resulted in Drywell control air being supplied by the Plant Control Air header.WHICH ONE (1)of the following is a concern during the malfunction?
~~~~a.Moisture in the air may cause critical valves to fail.b.Torus temperature may increase.c.Drywell oxygen level may increase.d.Breathing air is unavailable.
.REACTOR OPERATOR Page 43 STION: 072 (1.00)WHICH ONE (1)of the following systems is used to inject Alternate Standby Liquid Control (SLC)boron into the reactor?a.Suppression Chamber Head Tank system I b.Control Rod Drive system c.RHR Standby Coolant system d.Condensate and Feedwater system QUESTION: 073 (1.00)The reactor has experienced an incomplete scram.WHICH ONE (1)of the following methods of rod insertion requires first resetting the SCRAM?a.De-energization of scram solenoids t b.Venting of the scram air header c.Scraming individual control rods using test switches d.Venting the Control Rod Drive over piston volume QUESTION: 074 (1~00)WHICH ONE (1)of the following constitutes a loss of Secondary containment?
a.The Reactor Building normal HVAC is inoperable and isolated.b.Both Reactor Building ventilation radiation.
monitors are INOP.c.The Reactor Building/Suppression Chamber vacuum breaker is open.d.The Standby Gas Treatment system is inoperable.
REACTOR OPERATOR dS, Page 44~~~~STION: 075 (1.00)EOI-2, Primary Containment Control, requires emergency depressurisation if suppression pool level cannot be maintained within the safe region of curve 4,"SRV Tail Pipe Level Limit".WHICH ONE (1)of the following identifies the plant changes which both drive the plant toward the UNSAFE portion of the curve and an INCREASED possibility of SRV tail pipe failure?a.decreasing suppression pool water level, decreasing reactor pressure b.decreasing suppression pool water level, increasing reactor pressure c.increasing suppression pool water level, decreasing reactor pressure d.increasing suppression pool water level, increasing reactor pressure ION: 076 (1~00)Within two minutes after a loss of Reactor Building Closed Cooling Water, AOI 70-1,"Loss of RBCCW", directs that the reactor be scrammed and both recirculation pumps be tripped.WHICH ONE (1)of the following is the basis for this action?a.Loss of cooling will lead to filter demin inlet temperature increase and auto isolation of RWCU.b.Loss of flow to RHR pump coolers will prevent the RHR system from meeting design criteria.c.Loss of cooling to the Recirculation pump seals will lead to a primary coolant leak.d.Loss of Drywell cooling will lead to an increase in Drywell pressure, actuating safety related equipment.
0 REACTOR OPERATOR Page 45 STION: 077 (1 00)While the plant is operating at full power, a complete loss of Control Air is experienced.
WHICH ONE (1)of the following containment isolation valves is designed to fail open under these circumstances?
a.Suppression Chamber vacuum relief valves b.Main Steam Isolation Valve c.Refuel zone ventilation dampers d.RHR process water sampling valve QUESTION: 078 (1.00)A pipe shear has resulted in Control Air pressure immediately decreasing to 0 psig.WHICH ONE (1)of the following will remain available?
a.Off Gas t b.Stator Cooling Water c.Reactor Water Cleanup d.Raw Service Water supply to fire systems QUESTION: 079 (1.00)WHICH ONE (1)'f the following plant changes will result in the indication from LI 3-52, Post Accident Range Level instrumentation, becoming more accurate?a.Reactor pressure increases from 900 to 1125.psig.b.Drywell temperature increases from 100 to 212 degrees.c.Reactor building temperature increases from 100 to 130 degrees.d.Reactor recirculation pumps are manually tripped.


REACTOR OPERATOR d%.Page 46~~TION: 080 (1.00)The reactor is shutdown with Recirculation pumps off.WHICH ONE (1)of the following indicates reactor coolant stratification?
ENCLOSURE 4 RESOLUTION OF FACILITY COMMENTS ON WRITTEN EXAM
a.Shutdown Cooling is out of service, RPV pressure is 5 psig, RX VESSEL FLANGE DR LINE temperature is 170 degrees F, and RX VESSEL FN NOZZLE N4B END temperature is 205 degrees F.b.Shutdown Cooling is in service, RPV pressure is 5 psig, RX VESSEL BOTTOM HEAD temperature is 215 degrees F, and RX VESSEL FW NOZZLE N4B END temperature is 260 degrees F.c.Shutdown Cooling is out of service, RPV pressure is 0 psig, RX VESSEL FLANGE DR LINE temperature is 130, and feedwater sparger temperature is 170.d.Shutdown Cooling is in service, RPV pressure is 0 psig, RX VESSEL BOTTOM HEAD temperature is 140, and feedwater sparger temperature is 195.
: 1. SRO Question  1 (RO  Question 1)
0 REACTOR OPERATOR d.)Page 47 STION: 081 (1.00)A Reactor startup is in progress on Unit 2 when the following annunciators actuate.Current readings are also given.CRD ACCUM CHG WTR HDR 1480 psig CRD DRIVE WTR FILTER DIFF PRESS HIGH 50 psid Given the following plant conditions:
Facility  comment accepted.
Rx Power is 5%Reactor Pressure is 550 psig Charging Water Pressure is 1480 psig~decreasing slowlyg 1 Accumulator is XNOP due to water level 1 CRD High Temperature alarm WHICH ONE (1)of the following would be the correct IMMEDIATE action to take in accordance with 2-AOI-85-3,<<CRD System Failure"?a.A Manual Scram is required under current conditions.
: 2. SRO Question 47  (RO  Question 57)
b.A Manual Scram is required if Temperature alarm is received t SUCTION PRESSURE alarm.c.A Manual Scram is required if received.another Control Rod High in conjunction with the LOW CRD a second Accumulator alarm is d.A Manual Scram is required if Charging Water Pressure decreases to 1400 psig.
Facility  comment accepted.
0 0 REACTOR OPERATOR 8.)Page 48 STION: Q82 (1.QQ)Unit 2 control room has been abandoned and reactor pressure is decreasing due to a controlled cooldown.Water level is being controlled with the RCIC system at remote shutdown panel 25-32, in accordance with 2-AOI-100-2,"Control Room Abandonment".
: 3. SRO Question 53  (RO  Question 61)
When reactor pressure decreases to 50 psi, WHICH ONE of the following describes the status of the RCIC system under these circumstances?
Facility  comment accepted.
a.tripped and isolated.b.tripped but not isolated;can be restarted from Control Room c.tripped but not isolated;can NOT be restarted from Control Room d.RCIC is running QUESTION: 083 (1.00)\Unit 2 is operating at 1004 rated power when the following indications are received:~~~~OG POST TREATMENT RADIATION HI-HI ALARM OG POST TREATMENT RADIATION HI-HI-HI/INOP ALARM OG PRETREATMENT RADIATION HI ALARM OG AVERAGE ANNUAL RELEASE LIMIT EXCEEDED ALARM WHICH ONE (1)of the following is the appropriate immediate operator action?a.Reduce reactor power to 604 using recirc flow;manually scram the reactor.b.Reduce reactor power to 604 using recirc flow;insert control rods in reverse order to shutdown the reactor.c.Reduce core flow to 60%;manually scram the reactor.d.Reduce core flow to 60%;insert control rods in reverse order to shutdown the reactor.
: 4. SRO Question 62 (No    RO question)
0 REACTOR OPERATOR Page 49~~~~TION: 0&4 (1.00)During operation at 1004 power, a turbine trip occurs, and subsequently a reactor scram signal is generated.
Facility comment accepted.
Mater level reaches-15 inches but is recovered by the operator using the feedwater system.Reactor pressure initially reaches 1105 psig, but is controlled normally thereafter by the turbine bypass valves.During response to the transient, the operator notes that neither recirculation pump is running.WHICH ONE (1)of the following is the basis for the recirculation pump trip?a.To prevent damage to the recirculation pump seals when reactor pressure exceeds 1100 psig.b.To add negative reactivity, counteracting the positive reactivity added due to the pressure increase which resulted from the turbine trip.c.To promote level swell in the vessel, counteracting the shrink effects caused by the turbine trip.d.To protect the recirculation pumps from loss of adequate NPSH caused by the vessel level shrink resulting from the turbine trip.
: 5. SRO Question 96  (RO  Question 97)
0 REACTOR OPERATOR B.i Page 50~~~STION: 085 (1.00)A loss of all off-site power has occurred at Unit 2.:You are directed to backfeed the Unit boards from the Diesel generators in order to start a CCW pump andestablish the Main Condenser as a heat sink for cooldown.WHICH ONE (1)of the following describes the effect of taking the 2 BACKPEED switches on the Unit Boards (Panels 9-23-7 and 9-23-8)to the BACKFEED position'?
Facility  comment accepted.
a.Automatically trip and lockout the normal and alternate supply breaker, automatically trip the 43 switch to MANUAL, and allow the Unit Board to Shutdown Bus supply breaker to be manually closed.b.Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to MANUAL, and allow the alternate supply to Unit Board breaker to be manually closed.c.Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to AUTO and allow the alternate supply to Unit Board breaker to be manually closed.d.Automatically trip and lockout the alternate supply breaker, automatically trip the 43 switch to AUTO and allow the normal supply to Unit Board breaker to be auto closed.QUESTION: 086 (1.00)Reactor power is 254, main turbine on line, when a small air leak into the condenser starts to reduce vacuum.After performing the subsequent actions of 2-AOI-47<<3,"Loss of Condenser Vacuum", condenser pressure stabilizes at 24" Hg vacuum.WHICH ONE of the following actions is appropriate?
a.If condenser vacuum later decreases, trip the main turbine before condenser pressure reaches 7" vacuum..b.Trip the main turbine.c.Start the mechanical vacuum pump.d.Increase SJAE steam inlet pressure to 225 psig.
0 REACTOR OPERATOR d5.Page 51 I STION: 087 (1.00)Control Room instrumentation and annunciation indicates that three turbine stop valves have drifted to 804 open.No rod movement has occurred.You observe that the individual blue lights for each control rod on the full-core display are illuminated.
Also, the eight scram solenoid group indicating lights are extinguished.
WHICH ONE (1)of the following is a possible cause for the failure to SCRAM'?a.Failure of scram pilot valves to open.b.Only one RPS bus is de-energized.
c.Failure of scram inlet and outlet valves to open.d-Hydraulic lock on the scram discharge volume.QUESTION: 088 (1.00)Unit 2 is operating at 25%power when a loss of I&C bus"A" occurs.RPV evel control is selected to Level"A".Recirc pumps are in individ l ua 1 control.WHICH ONE (1)of the following describes the"expected ua nt response and operator actions for this event?, a.Feed flow will increase until the turbine trips on high level.A manual SCRAM should be inserted.b.Recirc pump B will run back to minimum speed, Recirc pump A will experience a scoop tube lockup.Recirc pump A should be manually run back to minimum speed.c.Recirc flow will increase until the Reactor scrams on high flux.Both recirc pumps should be manually run back to minimum.d.Recirc pump A will run back to minimum speed, Recirc pump B will experience a scoop tube lockup.Recirc pump B should be, manually run back to minimum speed.  


~REACTOR OPERATOR Page 52 I TION: 089 (1.00)Given the following plant conditions:
U. S. NUCLEAR REGULATORY 'OMMISSION              Afas 4~
RPV level RPV pressure Drywell press.Torus level Rx zone vent rad Refuel zone vent rad+56 inches 1040 psig 2.40 psig+1 inch 75 mr/hr 62 mr/hr WHICH ONE (1)of the following EOI groups should be entered?a.EOI-1,"RPV Control" and EOI-2, and EOI-4, Radiation Release Control.b.EOI-1,"RPV Control" and EOI-2,"Primary Containment Control".c.EOI-2,"Primary Containment Control" and EOI-3,"Secondary Containment Control"..
SITE SPECIFIC EXAMINATION REACTOR OPERATOR LICENSE REGION  2 CANDIDATE~S NAME:
d.EOI-3,"Secondary Containment Control" and EOI-4, Radiation Release Control.QUESTION: 090 (1.00)Unxt 2 is operating at rated power when all RBCCW pumps trip and none can be restarted.
FACILITY:           Browns  Ferry 1, 2, & 3 REACTOR TYPE:        BWR-GE4 DATE ADMINISTERED:  93/09/27 INSTRUCTIONS TO CANDIDATE:
WHICH ONE (1)of the following describes the IMMEDIATE operator actions appropriate for this situation?
Use  the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets.     Points for each question are indicated in parentheses after the question. The passing grade requires a final grade of at least 804. Examination papers will be picked up four (4) hours after the
a.Reduce recirculation flow to minimum, if recirc pump seal cavity temperature exceeds 200 degrees F on BOTH pumps, TRIP both recirc pumps and SCRAM the reactor.b.If drywell temperature exceeds 145 degrees F, or drywell pressure exceeds 1.66 psig, insert a manual SCRAM, and trip both recirculation pumps.c.Run recirculation pumps to 454 speed, insert, a manual SCRAM, Trip both recirculation pumps, and initiate a cooldown of 90 degrees F/hour.d.IMMEDIATELY TRIP both recirc pumps and SCRAM the reactor.
    'nation starts.
0~I REACTOR OPERATOR Page 53 TION: 091 (1.00)While offloading fuel bundles from the reactor, fuel pool level begins to decrease uncontrollably.
    ~    ~
WHICH ONE (1)of the following describes a method available from the control room to add water to the fuel pool?a.Align fuel pool cooling and cleanup heat exchanger RBCCW supply to the fuel pool to maintain level.b.Start an RHR pump and inject to the reactor vessel to maintain fuel pool level.c.Open emergency makeup supply valve from EECW to the fuel pool to maintain level.~I d.Open the CST to Fuel Pool Gravity drain valves.QUESTION: 092 (1 00)WHICH ONE (1)of the following scram signals is effective ONLY when the mode switch is in RUN?i a.IRM hi-hi b.Turbine stop valve closure c.MSIV closure d.EHC low oil pressure QUESTION: 093 (1.00)Unit 2 is operating at 254 power.WHICH ONE (1)of the following combinations of events will NOT result in a half reactor scram?a.Both MSIV's in steam lines"A" and"B" isolate b.Both MSIV's in steam lines"A" c.APRM"E" and"C" trip on hi-hi and"D" isolate flux 0 d.APRM"E" and>>A" trip on hi-hi flux
CANDIDATE'S TEST VALUE        SCORE 100.00                                       TOTALS FINAL GRADE All work    done on this examination is   my own. I have neither given nor received aid.
Candidate's Signature


REACTOR OPERATOR Page 54 STION: 094 (1.00)WHICH ONE (1)of-the following conditions requires a manual reactor SCRAM?a.RBCCW pump suction header temperature of 102 degrees F b.Pre-treatment radiation HI-HI-Hi c.Both recirculation pumps trip with the mode switch in Startup d.Off-gas system Hydrogen concentration of 54 QUESTION: 095 (1.00)WHICH ONE (1)of the following conditions assures ADEQUATE CORE COOLING?a.All rods inserted, RPV level-200, MSRV's cycling on pressure, no injection flow.b.RPV level unknown, 6 MSRV's open, reactor pressure is 10 psig.c.Reactor power 3%, RPV level-210, one MSRV open, HPCI injecting at maximum flow.d.RPV level-230, RHR"B" and"D" injecting at maximum flow, suppression pool level at 15 feet.
REACTOR OPERATOR                                                   Page 2 ANSWER        SHEET I
, REACTOR OPERATOR 1 d5.Page 55 TION: 096 (1.00)The Control Room has been abandoned.
Multiple Choice    (Circle or X your choice)
All MSRV transfer switches at panel 25-32 have been placed in EMERGENCY.
If you  change your answer, write your selection in the blank.
All MSRV control switches at panel 25-32 are in CLOSE.WHICH ONE (1)of the following states the opening capability of the MSRUs?a.ONLY manually by placing the panel 25-32 control switches in~OPEN b.ONLY manually OR upon receipt of an ADS initiation signal c.ONLY manually OR when their respective pressure relief setpoint is reached d.EITHER manually OR on an ADS initiation signal OR when their respective pressure relief setpoint is reached QUESTION: 097 (1 00)loop I is in shutdown cooling taking suction through Shutdown ing suction valves 74-47 and 74-4&.Loop II of RHR remains in the I standby lineup.Due to misoperation of ventilation systems, Drywell pressure increases to 2.5 psig.WHICH ONE (1)of the following'escribes the response of the RHR system?a.Valves 74-47 and 74-48 close, Loop I suppression pool suction valves auto open and BOTH RHR loops inject to the vessel.b.Valves 74-47 and 74<<48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves auto open but only Loop II injects.c.Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and only Loop II injects.d.Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and NEITHER Loop injects.
MULTIPLE CHOICE                      023    a   b  c  d 001    a   b   c   d                     Q24  a   b c   d 002    a   b   c   d                     025  a   b c ~ d 003    a  h    c   d                     026  a   b c   d 004    a   b   c   d                     027  a  b  c  d QQ5    a   b   c  d                    028  a  h  c   d 006    a  h    c  d                     029  a   b   c   d 007   a   b    c  d                    030  a   b  c  d 008    a   b    c  d                     031  a  b  c   d a  b   c   d                    032  a  b  c   d 0      a a
0 REACTOR OPERATOR dS.i Page 56~~STION: 098 (F 00)An emergency exists which requires addition of water to the suppression pool.Your supervisor directs use of Appendix 18 of the Emergency Procedures.
b b
Using Appendix 18, WHICH ONE (1)of the following describes the availability of HPCI and RCIC'?a.Neither HPCI nor RCIC are available if they have isolated.b.Both HPCI and RCIC are available even if they have isolated.c.HPCI is available unless it has isolated;RCIC is available even if isolated.d.RCIC is available unless it has isolated;HPCI is available even if isolated.QUESTION: 099 (1.00)WHICH ONE (1)of the following is the Technical Specification safety it for reactor pressure?a.1120 psig b.1125 psig c.1250 psig d.1375 psig REACTOR OPERATOR d%.Page 57 STION: 100 (1~00)Unit 3 fuel loading is in progress.WHICH ONE (1)of the following lists the two required communication links between the Unit operator and the refuel bridge?a.PAX phone and radio b.PAX phone and Paging system c.Sound Powered phone and radio d.Sound Powered phone and Paging system (**********
c c
END OF EXAMINATION
d d
**********)
033 034 a
0 REACTOR OPERATOR ANSWER K E Y Page 1 MULTIPLE CHOICE 001: d ar 002 b 003 a 004 b 005 6 006 c 007 a ooe a 009 a d 011 cj 012 c 013 b 014 c 015 c 016 c 017 018 c 019 a 020 a 021 a'23 b 024 b m 025 a 026 b 027 c 028 c 029 b 030 c 031 b 032 a 033 a 034 a 035 d 036 a 037 a 038 c 039 c O4O a 041 b 042 b 043 b 044 c O45 a REACTOR OPERATOR A N S W E R K E Y Page 2 046 cj 047'048 c 049 b 050 c 051 052 d 053 d 054 c 055 057 a or d 058 c 059 b 060 061 P'062 a 063 a O64 a 065 6 066 b 067 8b 069 c 070 b 071 c 072 b 073 c 074 6 075 076 6 077 a 078 b 079 6 080 a 081 082 6 083 a 084 b OS5 a 086'b 087 088 b 089 c 090 c 091 b REACTOR OPERATOR B.i ANSWER K E Y Page 3 092 c 093: b 094 6 095 a 096 c 097~J 098 c 099 6 100 c 0 (**********
a b
END OF EXAMINATION
h c
**********)
c d
d 012    a  h    c   d                    035  a  b   c   d 013    a  b   c  d                    036  a   b  c  d 014    a   b    c  d                     037   a   b  c   d 015    a  b    c   d                    038  a   b   c  d 016    a  b   c   d                    039  a   b   c   d 017        h    c  d                     040  a  b  c   d 018    a   b   c   d                    041  a  b,. c   d 019        b   c   d                    042  a   h  c  d 020        b   c  d                    043  a   b   c  d 021    a   b   c   d                    044  a  h  c   d a  b   c   d                    045  a  b   c   d


REACTOR OPERATOR Page 58 WER 001 (1.00)a.g b  
REACTOR OPERATOR                                                 Page 3 AN'SWER        SHEET Multiple Choice
          ~      ~
(Circle or X your choice)
Zf you change your answer, write your selection in the blank.
046    a  b c    d                    069    a  b  c,  d 047        b c    d                    070    a  b  c  d 048    a  b c    d                    071    a  b  c  d 049    a  b c    d                    072  a    b  c  d 050    a  b c    d                    073  a    b  c  d 051    a  b c    d                    074  a  b    c  d 052    a  b c    d                    075  a  b    c  d 053    a  b c    d                    076  a  b    c  d 054    a  b c    d                    077  a  b    c  d a  b c    d                    078  a  b    c  d a  b c    d                    079  a  b    c  d a  b c    d                    080  a  b    c  d 058    a  b c    d                    Q81  a  b    c  d 059    a  b c    d                    082  a  b    c  d 060    a  b c    d                    Q83  a  b    c  d 061    a  b c    d                    084  a  b    c  d 062    a  b c    d                    085  a  b    c  d 063    a  b c    d                    086  a  b    c  d I
064    a  b c    d                    087  a   b  . c  d 065    a  b c    d                    088  a  b    c  -d 066    a  b c    d                    089  a  b    c  d 067    a  b c    d                    090  a  b    c  d a  b c    d                    091  a  b   c  d


==REFERENCE:==
d,i REACTOR OPERATOR                                                      Page 4 A N S N E R  S H E E T Multiple Choice
          ~        ~
(Circle or X your choice)
                            ~
If you  change  your answer, write your selection in the blank.
                                      ~
092    a  b    c    d 093        b    c    d 094    a  b    c    d 095    a  b    c    d 096    a    b    c    d 097    a    b    c    d 098    a    b    c    d 099    a    b    c    d 100    a    b    c    d 0
(********** END  OF EXAMINATION **********)
 
0 Page 5 RC RULES AND  GUIDE IN S FOR L CENSE EXAMINATIONS 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 penalties.
: 2. After the examination      has been completed, you must sign the        ~
statement on the cover sheet indicating 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 exam-ination.
: 3. 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, cheating.
: 4. Use  black ink or dark pencil only to    facilitate legible repro-ductions.
: 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
: 6. Fill in the date    on  the cover sheet of the examination  (if necessary).
: 7. Print your name in the upper right-hand corner of the      first  page of each section of your answer sheets.
: 8. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
: 9. The  point value for    each question  is indicated in parentheses after the question.
: 10. Partial credit will    NOT be  given.
ll. If the  intent of  a  question is unclear, ask questions of the examiner only.
: 12. When  you are done and have turned in your examination, leave the examination area as defined by the examiner.      If you are found in this area while the examination is still in progress, your license may be denied or revoked.
 
Page 6 Blank Page
 
C%.
REACTOR OPERATOR                                                            Page 7 TION: 001    (1. 00)
The  reactor is being restarted near the    end of core  life following a  one day outage. Reactor power is  at  324. Control rods 34-23 and 58-23 have been isolated at position 00.      When rod 42-43 is withdrawn, alarm 2-XA-55-5A-29, CRD ACCUM PRESS LOW LEVEL HIGH, actuates on panel 9-5.
WHICH ONE (1) of the following requirements is in effect under the current plant conditions?
: a. Exercise control rod 42-43 at least one notch at least once each day.
: b. Clear the accumulator trouble alarm on rod 42-43 prior to moving the next control rod.
: c. Control rod 42-43 must be fully inserted and electrically disarmed.
: d. Observe nuclear instrumentation    for  response each time rod 42-43 is  moved.
ION: 002    (1. QO)
Control  Rod 38-23 has been selected for a single notch withdrawal from position  02 to position Q4. The following response from the CRD system was  observed:
Insert light illuminates and    goes out.
Withdrawal  light illuminates  and goes out.
Settle light illuminates and    goes out.
The  operator also observes and reports that the selected rod is now at position  06 and is continuing to drift out. A Rod Drift alarm is also present. WHICH ONE (1) of the following has caused the conditions?
: a. the automatic sequence timer has failed
: b. stuck open .,collet fingers
: c. excessive HCU cooling water pressure
: d. leaking scram inlet valve
 
0 REACTOR OPERATOR                                                            Page 8 STION: 003      (1.00)
WHICH ONE      (1) of the following states the condition identified by an illuminated blue scram light for each control rod on the Full Core Display?
: a. Both      inlet  and outlet  scram valves  for that rod are open.
: b. Both    inlet  and outlet  scram valves for that rod are closed.
: c. Both scram      pilot air valves for that rod are energized.
: d. Both scram      pilot air valves for that. rod are deenergized.
QUESTION: 004        (1.00)
Following performance of a torus-drywell vacuum breaker operability surveillance instruction, the vacuum breaker has the following indications:
Check    light - OFF Green    light ON Red  light - OFF
              ~
WHICH ONE    (1)    of the following states the position of the    vacuum breaker'?
: a. fully closed
: b. cracked open (less than        3  degrees open)
: c. partially    open (between  3  degrees and 80 degrees open)
: d. fully open      (greater than  80 degrees  open)
 
REACTOR OPERATOR                                                            Page 9 STION: 005    (1.00)
While a control rod is being inserted using the EMERGENCY IN contxol switch, rod motion stops. WHICH ONE (1) of the following could have terminated rod insertion?
: a. the automatic sequence timer deenergizes
: b. loss of power to the Rod Position 1'nformation System
: c. a RWM  select block
: d. a RWM  insert block QUESTION: 006    (1.00)
WHICH ONE  (1)  of the following will result in    a  control rod block on input from  IRM B?
: a. Mode switch    is in REFUEL, IRM B  is downscale on range 1.
is in STARTUP, IRM B  indicates  30 on range 3.
: c. Mode  switch is  in STARTUP, IRM B  downscale on range 5.
: d. Mode  switch is  in RUN, IRM B indicates  105 on range 8.
 
B.
REACTOR OPERATOR                                                              Page 10 STION: 007          (1. 00),
                        ~
WHICH ONE (1) of          the following sets of conditions would result in the Unit 2 Automatic
    ~                  ~
Depressurization system 95 second timer starting?
                                    ~    ~
Assume      all  sensors, power supplies, and interlocks are operating properly.
a  ~  RPV  level remains at -125" for 4 minutes and 30 seconds, Drywell pressure peaks at 2.10 psig, >>A>> Core Spray pump discharge pressure    is 190 psig, "C>> Core Spray pump discharge pressure is 195  psig, no other ECCS pumps are running.
: b. RPV  level remains at -125>> for 4 minutes and 30 seconds, Drywell pressure peaks at 2.10 psig, >>A>> Core Spray pump discharge pressure is 175 psig, >>C>> Core Spray pump discharge pressure is 195 psig, no other ECCS pumps are running.
co RPV    level remains at -135>> for 3 minutes and 25 seconds, Drywell pressure peaks at 2.50 psig, >>A>> Core Spray pump discharge pressure is 190 psig, >>B>> Core Spray pump discharge pressure is 195 psig, no other ECCS pumps are running.
: d. RPV level remains at -135>> for 3 minutes and 25 seconds, Drywell pressure peaks at 2.50 psig, >>B>> Core Spray pump discharge pressure is 190 psig, >>D>> Core Spray pump discharge pressure is 175 psig, no other ECCS pumps are running.
QUESTION: 008        (1.00)
A Main Steam        Relief Valve (MSRV) lifts due to high reactor pressure.
(1)  of the following could cause a significant DECREASE in the WHICH ONE MSRV's      lift pressure if it subsequently lifts a    second time?
: a. tailpipe    vacuum breaker    failed CLOSED
: b. tailpipe      vacuum  breaker failed  OPEN
      . c. high drywell pressure
: d. high suppression pool level
 
REACTOR OPERATOR                                                      Page 11 STION: 009    (1.00)
                    ~
Control rod drive mechanism 25-24 has exceeded 350 degrees F, alarm
                ~
TA-85-7, CONTROL ROD DRIVE UNIT TEMP HIGH annunciator (2-XA-55-5A, Window 17) is alarming. WHICH ONE (1) of the following describes the correct response to this hot CRD mechanism'?
: a. Check for scram discharge valve leakage, leave the drive hot.
: b. Check for scram discharge valve leakage, cool the drive by giving  it repeated drive signals.
: c. Check for scram inlet valve leakage, leave the drive hot.
: d. Check for scram inlet valve leakage, cool the drive by giving repeated drive signals.
it QUESTION: 010    (1.00)
WHICH ONE (1) of the following signals from the Post-Treatment Radiation Monitoring System will initiate an AUTOMATIC ISOLATION of the Off gas charge to the main stack (FCV-66-28)?
: a. High-High-High trip in Channel A; Channel B is clear
: b. High trip in Channel A; downscale trip in Channel B
: c. High trip in Channel A; XNOP trip in Channel B.
: d. Downscale    trip in Channel A; INOP trip 'in Channel B.
 
dS.,
REACTOR OPERATOR                                                          Page 12 STXON: 011    (1.00)
During a  LOCA, the SRO  directs you to initiate  drywell sprays. The RHR SYS  I CTMT  VLV SELECT switch is in SELECT and the 2/3 Core coverage OVERRIDE. RHR SYS I keylock  switch  is in                      DW SPRAY INBD VLV (2-FCV  61) cannot be opened.      WHICH ONE (1) of the following interlocks  is preventing valve operation?
: a. RPV level less than -122 inches
: b. RPV  level less than -183 inches
: c. LPCI initiation signal NOT present
: d. Drywell pressure less than 1.96 psig QUESTION: 012      (1.00)
An  earthquake has resulted in a complete loss of off-site power and LOCA on  Unit 2. Drywell pressure has increased to 5 psig on Unit 2.
rgency Diesel Generator "C" has failed to start. All other emergency nt equipment is functioning normally. EXCH ONE (1) of the following ntifies the Core Spray pumps that will respond to the automatic start signal?
: a. 2A, 28
: b. 2A, 2B,  2D
: c. 2A,  2C d  2Ar 2Ct 2D
 
d5.
REACTOR OPERATOR                                                            Page 13 The  Control Room has been evacuated. RHR pump 2C is required for operation in the shutdown cooling mode and the SDC suction valve is OPEN.      RHR pump breaker power has been transferred to the local Emergency position. WHICH ONE (1) of the following will prevent the pump  from starting?
: a. Shutdown Cooling Supply valve, 74-47,    is CLOSED.
: b. RHR Drain pump suction valve, 74-104,  is OPEN.
: c. A  Unit 2 Accident Signal is present.
: d. Undervoltage on Shutdown Board  C.
QUESTION: 014      (1.00)
Condxtzons have been met
      ~  ~
to start the Automatic Depressurization System (ADS) 95 second timers.      WHICH ONE (1) of the following  identifies the initiation signals that will ar?
NOT automatically reset  if conditions
: a. 95 second TIMER and Low Reactor Water Level TIMER
: b. 95 second  TIMER and Low Reactor Water Level signal
: c. High Drywell pressure signal and    Low Reactor Water Level  TIMER
: d. High Drywell pressure signal and    Low Reactor Water Level signal
 
C5.
REACTOR OPERATOR                                                        Page 14 STION: 015  (1.00)
Reactor Recirculation pump "A" is operating at 1310 RPM and is providing 40,000 gpm flow. Reactor Recirculation pump "B" is operating at 1325 RPM. WHICH ONE (1) of the following states the LOWEST flow for Reactor Recirculation pump "B" that would indicate possible jet pump failure7
                                                                    % ~
: a. 44,000  gpm
: b. 44,600  gpm
: c. 46,000  gpm
: d. 46,600  gpm QUESTION: 016    (1.00)
Reactor Recirculation pumps are not operated below 204 speed. WHICH ONE (1)  of the following states the basis for this limit?
: a. Ensures adequate Net Positive Suction Head.
b; Prevents thermal stress in the vessel lower head region.
: c. Prevents unstable fluid coupler operation.
: d. Limits harmonic vibration of the jet pumps.
 
REACTOR OPERATOR                                                        Page 15 I~
STION: 017    (1. 00)
                    ~
The  plant is operating at full power when the "B" Reactor Recirculation
              ~          ~
pump's suction valve drifts to 884 open. WHICH ONE (1) of the following states the expected response?
: a. Pump speed decreases to 284.
: b. Pump speed decreases to 454.
: c. Pump speed decreases to 754.
: d. Pump trips.
QUESTION: 018    (1.00)
While Reactor Recirculation pump "A" is operating at. 804, a failure in pump's  individual M/A station occurs and a signal is sent to the Bailey Positioner calling for a pump speed of zero. WHICH ONE (1) of the following states the expected response of the pump?
: a. Scoop tubes      will lock and speed will remain at 804.
: b. Speed decreases      to 284.
: c. Speed  decreases to 204.
4
: d. Speed  decreases to zero.
 
1 dS.,
REACTOR OPERATOR                                                            Page 16 STION: 019    (1.00)
WHICH ONE  (1)  of the following sets of cavity pressures indicate    a failure of the    &#xb9;2 (outer) Reactor Recirculation pump seals?
            &#xb9;1  CAUITY PRESSURE          &#xb9;2 CAVITY PRESSURE a0          1000  psig                  100  psig
: b.          1000  psig                  1000 psig C~          500  psig                  500 psig
: d.          1000  psig                  500 psig QUESTION: 020    (1.00) l During an accident on Unit 2, power      is lost from the Division II ECCS inverter. WHICH ONE  (1)  of the following HPCI system capabilities is lost'
: a. Flow  control
: b. Automatic  initiation
: c. Automatic isolation
: d. Automatic trip
 
REACTOR OPERATOR                                                                    Page 17
                          \
STION: 021        (1.00)
                        ~
HPCI is    in standby readiness.                        of the following states the
        ~    ~
(1)
HPCI pump      suction status Storage Tank volume        is if Torus level
                                      ~  WHICH ONE 9900 gallons.7 is  +5 inches and  the Condensate a'. Suction is from the CST but can be manually transferred            to the Torus without bypassing interlocks.
: b. Suction      is from the CST and CANNOT be transferred to the Torus without bypassing interlocks.
: c. Suction is from the Torus but can be manually transferred to the CST without bypassing interlocks.
: d. Suction is from the Torus and CANNOT be transferred to the CST without bypassing interlocks.
QUESTION: 022        (1.00) mode      switch is in run and APRM B has failed downscale. No operator ion    is taken.      WHICH ONE (1) of the following correctly describes the ected response        if  the stated IRM failures occur?
: a. IRM B Hi-Hi or ZRM G ZNOP will result in a half scram of RPS Channel A.
: b. IRM      B Hi-Hi or    ZRM G INOP  will result in  a half scram  of  RPS Channel B.
: c. IRM B ZNOP      or  ZRM H  Hi-Hi will result in  a half scram  of  RPS Channel A.
: d. ZRM B ZNOP      or  ZRM H  Hi-Hi will result in  a half scram of  RPS Channel B.
 
0 REACTOR OPERATOR                                                          Page 18 STION: 023    (F 00)
With the plant operating at    100% power, Alarm XA-55-3F, window 31, CORE SPRAY SYS    II SPARGER BREAK, actuates. WHICH ONE (1) of the following identifies the core spray line break location required to actuate the alarm?
a.'nside of the reactor vessel    shroud
: b. inside of the reactor vessel and outside of the shroud
: c. anywhere inside of the reactor vessel
: d. anywhere on the pressurized portion of the injection    line QUESTION: 024      (F 00)
During a LOCA, reactor water level is dropping at a rate of 20 inches per minute. RPV level is currently -132 inches. RPV pressure is 468 psig and Drywell pressure is 2.5 psig. WHICH ONE (1) of the following cribes the expected status of the Unit 2 Core Spray system?
: a. Core Spray system has  NOT  initiated.
: b. Core, Spray pumps have started, injection valve is CLOSED.
: c. Core Spray pumps have started, injection valve is OPEN, but    pump flow is deadheaded against the closed check valve.
: d. Core Spray pumps have started and are I
injecting into the vessel.
 
d.
REACTOR OPERATOR                                                    Page 19 TION: 025  (1.00)
The PSC pumps  trip and cannot be restarted. WHICH ONE (1) of the following conditions is a possible reason for this occurrence?
: a. RPV level is -118 inches.
: b. RHR Room  temperature is 182 degrees F.
: c. 250U RMOV power is lost to Div I.
: d. Suppression pool level is -6.25 inches.
QUESTION: 026    (1 00)
                  ~
During plant startup with reactor power on range 5 of the IRMs, an MSIV closure occurs. WHICH ONE (1) of the following conditions is a possible t
reason for this occurrence?
      'a. Reactor water level is -83 inches.
: b. MSL tunnel temperature is 210 degrees F.
: c. Reactor pressure is 840 psig.
: d. Drywell pressure  is 2.6 psig.
 
0 0
 
d.)
REACTOR OPERATOR                                                            Page 20 STION: 027    (1.00)
During a plant transient, the Main Steam      Isolation Valves isolated  on a valid  Group  I isolation  signal. All control  rods inserted and immediate operator  actions  reguired by procedure have been taken. A decision has been made to unisolate MSL "D" (valves 1-51 and 1-52) to allow use of the main condenser. Given the following plant conditions:
Reactor water level is -5 inches.
Reactor pressure is 700 psig.
Drywell pressure is 3.2 psig.
MSL Area temperature is 185 degrees P.
WHICH ONE    (1) of the following states actions required to reset the Group 1  isolation?
: a. The MSIV switches    for ONLY valves 1-51 and 1-52 must be placed in the  CLOSE position.
: b. A  jumper must be installed  AND the  MSIV switches for  ONLY valves 1-51 and 1-52 must be placed    in the  CLOSE position.
t    c. The MSIV switches for ALL MSIUs must be position.
placed in the
: d. A jumper must be installed AND the MSIV switches must be placed in the CLOSE position.
for CLOSE ALL MSIVs
 
>l REACTOR OPERATOR                                                                            Page 21 STION: 028      (1.~
          ~
exists
                  ~      00)'onditions on Unit
                                            ~
2  that require the initiation of Standby Liquid Control.                                  (1) of the following contains two indications
  ~
WHICH ONE that    SLC  is injectingi
: a. Explosive valve current flow indicator reads 0 milliamps                    AND  the blue SQUIB VALVE CONTINUITY light is illuminated.
: b. Explosive valve current flow indicator reads 4 .milliamps                    AND  the blue SQUIB VALVE CONTINUITY light is illuminated.
: c. Explosive valve current flow indicator reads 0 milliamps                    AND  the blue SQUIB VALVE CONTINUITY light is extinguished.
Explosive valve current flow indicator reads 4 milliamps                  AND  the blue SQUIB VALVE CONTINUITY light is extinguished.
QUESTION: 029        (1 00)
Off-Gas Pretreatment High Radiation alarm for Unit 2 has just ated. WHICH ONE (1) of the following conditions could have caused alarm?
: a. Failure of the on-line Catalytic Recombiner.
: b. Failure of a condensate                    demineralizer resin trap.
: c. Trip of the operating Steam Jet Air Ejector.
: d. Increased steam content of off-gas exhaust flow.
 
0 d.)
REACTOR OPERATOR                                                            Page 22 STION: 03 0    (1 00)
A TIP trace is being run in the automatic mode using TIP Channel A.
While the TIP is at the top of core limit, the reactor scrams on low water level after a loss of electrical power. 120VAC power is lost to the TIP system. RPV level reaches +10 inches minimum. WHICH ONE (1) of the following describes the response of the TIP System following the scram?
: a. The TIP channel    will shift to manual reverse mode withdraw to the in shield    limit and the ball valve will close.
: b. The  TIP channel will shift to manual reverse mode, withdraw to the  in shield limit and the ball valve will fail to close. The Shear valve can be    fired  if isolation  is required.
: c. The TIP channel will remain at it's present position. The Shear valve can be fired    if isolation is required.
: d. The TIP channel will remain at it's present position. The Shear valve will be incapable of firing      if isolation is required.
TION: 031    (1. 00)
Given  that the following conditions exist during refueling on Unit 3:
Bridge is directly over the core Main hoist is loaded to 550 lbs, in the full up position Aux hoist is loaded to 350 lbs, in the full up position Rod 03-17 is at position 02 Mode Switch is in STARTUP WHICH ONE (1) of the following responses would indicate normal interlock functioning on the refuel bridge? (FORWARD means away from the core, REVERSE means    toward the core.)
: a. Bridge    will move in  the forward AND reverse directions.
: b. Bridge    will move in  the forward direction BUT NOT reverse direction.
: c. Bridge    will move in  the reverse direction  BUT NOT  forward direction.
: d. Bridge    will NOT move  in either direction.
 
o B.
REACTOR OPERATOR                                                        Page 23 STION: 032    (1.00)
WHICH ONE    (1) of the following describes the trip logic for the Reactor Building Ventilation Radiation Monitors (Reactor Zone Ventilation Radiation Monitors and Refuel Floor Radiation Monitors)
: a. Two Hi levels in 1 division OR one downscale in 2 divisions
: b. Two Hi levels in 1 division OR two downscales in 1 division
: c. One Hi level in 2 divisions OR one downscale in 2 divisions
: d. One Hi level in 2 divisions OR two downscales in 1 divisions QUESTION: 033    (1.00)
WHICH ONE    (1) of the following describes how the RWCU system is connected  to the RPV in each of the three units?
: a. Suction is from the >>A>> Recirc line on all units, return  is via the >>B>> feed line for Units 1 and 2, and the >>A>> and >>B>>  feed lines for Unit 3.
: b. Suction is from the >>A>> Recirc line on all units, return  is via the >>B>> feed line for Units 1 and 3, and the >>A>> and >>B>>  feed lines for Unit 2.
: c. Suction is from the >>B>> Recirc line on all units, return  is via the >>B>> feed line for Units 1 and 3, and the >>A>> and >>B>>  feed lines for Unit 2.
: d. Suction is from the >>B>> Recirc line on all units, return  is via the >>B>> feed line for Units 1 and 2, and the >>A>> and >>B>>  feed lines for Unit 3.
 
d5.
REACTOR OPERATOR                                                        Page 24 STION: 034    (1.00)
Shutdown Bus 1 was    initially being supplied by Unit Board 2B when Shutdown Board B bus transfer switch (43) transfers to MANUAL. WHICH ONE (1) of the following is a possible reason for this occurrence?
4
: a. Shutdown Board  B Normal Feeder Breaker (1616) Emergency Control Power Transfer Switch has been placed in the Emergency position.
: b. The alternate power supply to Shutdown Bus 1 has sensed a high load differential condition across the 87Uxz breaker.
: c. A phase or ground overcurrent condition has been sensed by the NORMAL shutdown bus power supply.
: d. The residual voltage relay has shut in the close circuit of the alternate power supply to Shutdown Bus 1.
QUESTION: 035    (1.00) cerning the Diesel Generator Mode Switch, WHICH ONE (1) of the lowing modes of operation is used when the diesel generator is in allel with off-site  power?
: a. Test
: b. Single Unit
: c. Units In Parallel
: d. Parallel With System
 
0 0
 
d5.
REACTOR OPERATOR                                                          Page 25 STION: 036    (1 00}
A LOCA has  occurred. Drywell pressure is 3 psig and no off-site power is available. WHICH ONE (1) of the following is the only load allowed to be sequenced onto its associated shutdown board before forty (40) seconds have elapsed'
: a. RHRSW  pumps
: b. A and D  Control Air Compressors
: c. Drywell blowers
: d. RBCCW  pumps QUESTION: 037    (1.00)
WHICH ONE was V
(1) of the following would totally lost' be affected if the +/-24 VDC  system
: a. Neutron Monitoring Instrumentation
: b. Control  Room Annunciators
: c. Diesel Control and Logic power
: d. 480V Shutdown Board Control Power
 
d5.
REACTOR OPERATOR                                                              Page 26 STION: 038    ( 1. 00)
Normal and alternate supply breakers to unit boards 3A and 3B have tripped and the Unit 3 Shutdown Board 43 auto transfer switches have transferred to MANUAI. WHICH ONE (1) of the following describes what has happened?
: a. An automatic shutdown bus      transfer  has taken place.
: b. The associated    4  kV shutdown board has  failed to transfer to the alternate power supply.
: c. The associated backfeed switch has been placed in the        BACKFEED position.
: d. A manual U3 Unit Board high-speed        transfer to the alternate power supply failed.
QUESTION: 039    (1.00) zng  full power    operation on Unit 2, the mechanical spaces exhaust fan ls. WHICH ONE    (1) of the following is a possible consequence of this lure?
: a. Buildup of contaminants      in the Radwaste  building atmosphere
: b. Development of an explosive atmosphere in battery rooms
: c. Main steamline isolation
: d. Unreliable Emergency Range level indication
 
dS.
REACTOR OPERATOR                                                                  Page 27 STION: 040    (1.00)
A  fire  pump has  automatically started.      WHICH ONE  (1)  of the following could have caused the      initiation?
: a. A fog water system was manually started        at the Main turbine oil tanks.
: b. Turbine building area temperatures have steadily risen 40 degrees in the last five minutes.
: c. Main Transformer temperature has increased to 190 degrees F.
: d. Unit 2 HPCI room temperature has increased from 100 to 212 degrees F over the last 30 minutes.
QUESTION: 041      (1.00)
An  RSW  pump has  started to automatically increase level in the RSW storage tank when    a fire pump receives an automatic start signal.          WHICH (1) of the following describes the response of the RSW storage tank lation valves    and  the  RSW  pump?
: a. The  RSW  pump  immediately  trips. The isolation valves    CLOSE but will AUTOMATICALLYreopen      when the  fire pump  stops.
: b. The RSW pump immediately trips. The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire pump stops.
: c. The RSW pump continues running in support of the fire pump. The isolation valves CLOSE but will AUTOMATICALLYreopen when the fire pump stops.
: d. The RSW pump continues running in support of the fire pump. The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire pump stops.
 
d%.
REACTOR OPERATOR                                                          Page 28 STION: 042  (1 ~ 00)
The  plant is being shutdown
            ~
and reactor power is stable at  254 when annunciator "OFFGAS HOLDUP TEMPERATURE HIGH" actuates due to low flow through the SZAE condensers. WHICH ONE (1) of the following could have caused the event'?
: a. In-leakage of noncondensible gases  into the  main condenser.
: b. SPE  Heat Exchanger Balancing valve (FCV 2-190) open.
: c. Condensate demineralizer bypass valve    (FCV 2-130) open.
: d. Only two condensate pumps running.
QUESTION: 043    (1.00)
The Condensate  system is aligned for short cycle cleanup. WHICH ONE (1) of the following describes the flowpath?
: a. Flow returns to the condenser from the outlet of the SJAE condensers.
: b. Flow returns to the condenser from the condensate booster    pump discharge header.
: c. Flow returns to the  CST from the outlet of the  SZAE  condensers.
: d. Flow returns to the  CST from the condensate  booster  pump discharge header.
 
REACTOR OPERATOR                                                                  Page 29 STION: 044        (1." 00)
RHR    loop  1  is in    standby when  electrical power is lost to 480 volt  RMOV board 2D.      WHICH ONE      (1) of the following RHR flowpaths is NOT available?
: a. torus cooling
: b. drywell spray
: c. LPCI injection
: d. pump minimum flow QUESTION: 045        (1.00)
WHICH ONE (1)
Control Room?
of the following RPS      trip signals can be bypassed from the
: a. Scram    Air Header
                      ~
low pressure
: b. Loss of      RPS  power
: c. Hi~
RPV  pressure
: d. Hi  MSL  radiation QUESTION: 046        (1.00)
WHICH ONE      (1)  of the following describes the expected DIRECT response t ne Main Steam        Line radiation monitor reaching it's high trip setpoint?
      . a. Full    scram and full Group 1 Isolation
: b. Full    scram and half Group 1 Isolation
: c. Half    scram and full Group 1 Isolation
: d. Half    scram and half Group 1 Isolation
 
d5.
REACTOR OPERATOR                                                          Page 30 STION: 047  (1.00)
WHICH ONE  (1) of the following states  when  the Rod Block Monitor system initiates  a null  sequence?
: a. reference  APRM  fails upscale b; reference  APRM  is changed to alternate
: c. recirculation flow changes by    10%
: d. reactor power drops below 30%
QUESTION: 048    (1. 00)
Unit 2 is operating at 100% power with FWLC in automatic three element control when the "A" steam flow transmitter fails downscale. WHICH ONE (1) of the following describes the expected control room INDICATIONS after conditions stabilize? (Assume no operator action is taken)
: a. Feed Flow 100%, Steam Flow 75%, Reactor Level 18 inches
: b. Feed Flow  75%, Steam Flow 75%,  Reactor level  18  inches
: c. Feed Flow  100%, Steam Flow 75%,  Reactor Level  33  inches
: d. Feed Flow  75%, Steam Flow 75%,  Reactor Level  33  inches
 
I.
ld
 
dS.
REACTOR OPERATOR                                                              Page 31 I
STION: 049    (1.00)
Unit 2 is operating at 1004 power with the master feedwater level controller is in 3 element when the FWLC system experiences a loss of one of the two feedwater flow inputs.        WHICH ONE (1) of the following describes the expected plant response?        (Assume no operator action is taken)
: a. Reactor level will stabilize      at normal  with.FWLC remaining  in 3 element control.
: b. Reactor level    will stabilize at  normal with  FWLC in single element.
: c. Reactor level    will stabilize  about 15 inches below normal with FWLC  remaining in  3  element control.
: d. Reactor level    will stabilize about  15  inches below normal with FWLC  in single element.
QUESTION: 050      (1.00)
                    ~
H ONE  (1)  of the following conditions will result in
                                  ~
a RFPT trip?
: a. RFPT  "B" suction pressure 95 psig for 25 seconds.
                          ~
: b. Condenser low vacuum 10" Hg.
: c. RFP (pump) low oil pressure 6 psig.
: d. RPV level 52" for 10 seconds.
 
0 0
 
REACTOR OPERATOR                                                        Page 32 STION: 051      (1.00)
Unit  2 has just experienced a small LOCA and Drywell pressure has increased to 3 psig. Reactor pressure is SQQ psig and steady. The increase in Drywell temperature causes reliability concerns for WHICH ONE (1) of the following level instruments'
: a. Emergency Range    indicators,
: b. Normal Range indicators c.. Post Accident indicators
: d. Shutdown Floodup indicators QUESTION: 052      (1.00) t WHICH ONE    (1) of the following describes.how an electrical drawing is verified  as being the current revised copy'P
: a. Refer    to the Controlled Drawing Holders list of drawings that contains only the latest revised drawings.
: b. Refer to the Shift Operations Supervisor/Assistant Shift Operations Shift log book.
: c. Refer to the Lead Unit Operators log book.
: d. Refer to Document Control for assistance.
 
0 REACTOR OPERATOR                                                      Page 33 STION: 053    (1.00)
A surveillance is in progress, with the SOS (initials O.H.) direct'ing the actions of the "UO" (initials S.L.) i.n the plant. The procedure is in the possession of the "UO". WHICH ONE (1) of the following describes the initials that the "UO" is to place on the surveillance step?
a;  OH/SL
: b. SL/OH
: c. OH
: d. SL QUESTION: 054    (1.00)
WHICH ONE  (1) of the following statements DEFINES a radiation area?
: a. An area where an individual can be exposed to dose rates exceeding 5 mrem/hr or receive up to 40 mrem total exposure in any eight (8) hour period.
: b. An area where an individual can be exposed to dose rates exceeding 100 mrem/hr or receive up to 3 REM total exposure in any  five  (5) consecutive days.
: c. An area where an individual can be exposed to dose rates exceeding 5 mrem/hr or receive up to 1QQ mrem in any five (5) consecutive days.
: d. An area where an individual can be exposed to dose rates exceeding 10 mrem/hr or receive up to 8Q mrem in any eight (8) hour period.
 
REACTOR OPERATOR                                                        Page 34 STION: 055    (1 00)
During a Site Area Emergency, the Site Emergency Director is informed
'that the  UO on building rounds did not report to the Control Room and does not respond to the plant paging system. WHICH ONE (1) of the following is the maximum exposure allowed to an individual in order to search for the unaccounted for operator?
: a. BFNP  administrative limits
: b. 10CFR20 non-emergency  limits
: c. 25 REM
: d. 75 REM QUESTION: 056    (1.00)
WHICH ONE  (1) of the following is the maximum length of time a confined space  entry permit is valid without an extension?
: b. 12  hours
: c. 24  hours
: d. 72 hours
 
B.'>
REACTOR OPERATOR                                                                Page 35 STION: 057      (1.00)
WHICH ONE    (1)  of the following is an acceptable way to perform position verification      on a  throttled valve? (assume that the valve is installed in  a system with a local flow indication controlled by the valve, and the valve has a rising stem)
: a. observe the initial valve operator's action in positioning the throttled valve
: b. perform an independent visual check of the valve position by observing the valve stem
: c. independently verify the valve position by a second valve operation
: d. by observing flow indication through the throttled valve's system QUESTION: 058        (1.00) event occurs that,      is required to be logged in the Operating Logs ~
NE  (1) of the following states ALL the Operations Narrative Logs the event would be required to be recorded in according to SSP-12.1, "Conduct of Operations".
: a. SOS
: b. SOS,    ASOS
: c. SOS,    ASOS, UO d  SOS  J  ASOS g  UO ~ STA
 
REACTOR OPERATOR                                                            Page 36 STION: 059    (1.00)
                      ~
A  valve will be
            ~
manipulated at rated power that may influence RPV level.
WHICH ONE    (1)  of  the following forms of verification would ensure the correct valve is manipulated?
: a. Supervisor      Verification
: b. Second Party Verification
: c. Independent Verification
: d. Responsible Manager Verification QUESTION: 060      (1.00)
The  plant is operating at          power  with three (3) hours remaining on a t
80%
24  hour LCO. The Wilson Load  Dispatcher requests the base load to be increased 25    MWE for the remainder of the operating run. WHICH ONE (1) of the following actions should be taken?
: a. Before increasing the electrical load, the request must be approved by EITHER the SOS or the ASOS.
: b. Before increasing the electrical load, the, request must be approved by BOTH the SOS and the ASOS.
: c. Before increasing the electrical load, the request must be approved by any licensed individual.
: d. The request      for a load increase cannot be approved at  this time.
 
REACTOR OPERATOR                                                      Page 37 STION: 061  (1.00)
                    ~
Four licensed UOs attended  a fellow employee's birthday party the last night of their vacation and alcohol was served to all. Below shows when
  ~            ~
each UO stopped drinking alcoholic beverages.
UO  'A':05    am UO 'B':05    am UO 'C':05    am UO 'D':05    am From the four UOs listed above, WHICH ONE (1) of the following states the number available for NRC licensed work the same morning at 7:00 am?
(Assume that all the UOs have blood alcohol levels within SSP 1.6 guidelines).
: a. ONE t
: b. TWO
: c. THREE
: d. FOUR
 
0 REACTOR OPERATOR                                                          Page 38 STION: 062    (1 00)
Six operators enter the RCA. Upon exiting, the following measurements were observed using    the frisker:
Operator 1      200 cpm above background skin contamination.
Operator 2      85 cpm above background skin contamination.
Operator 3      50 cpm above background personal clothing contamination.
Operator 4      150 cpm above background personal clothing contamination.
Operator 5      250 cpm above background personal clothing contamination.
Operator 6      125 cpm above background personal clothing contamination.
WHICH ONE (1) of the following indicates the number of operators that
,are considered contaminated in accordance with procedure SSP 5.1, "Radiation Protection Plan" ?
: a. Four
: b. Three co Two
: d. One QUESTION: 063      (1.00)
Units    1 and 3 are defueld. Unit 2 is at 1004 power. A transient on Unit 2  results in declaring a Site Area Emergency and activation of the accountability siren. WHICH ONE (1) of the following describes the expected response of the Unit 1 and Unit 3 operators?
: a. Remain at their respective units and wait for further direction.
      ~ b. Report to Unit 2 and assist as directed by the SOS.
: c. Unit 1 UOs report to the Unit 2 control room and Unit 3 Uos remain at their station.
: d. Unit 3 Uos report to the Unit 2 control room and Unit 1 Uos remain at their station.
 
C3.
REACTOR OPERATOR                                                      Page 39 TION: 064  ( 1. 00)
WHICH ONE  (1) of the following conditions requires entry into an EOI'?
: a. Reactor Building floor drain sump level at 69 inches.
b,. Drywell temperature at 146 degrees F.
: c. Secondary Containment dp is -0.19 inches H20.
: d. Reactor zone ventilation exhaust radiation level at  68 mR/hr.
QUESTION: 065  (1 00)
During an ATWS with the reactor at high power, EOI-1, step RC/Q-7, directs that recirculation be run back to minimum prior to tripping the Reactor recirculation pumps. WHICH ONE (1) of the following is the basis for this action?
: a. Prevent MSIU closure on high flow.
: b. Promote boron mixing.
: c. Prevent Main Generator reverse power trip.
: d. Prevent Main Turbine high RPU water level trip.
 
CS.
REACTOR OPERATOR                                                      Page 40 STION: 066    (1.00)
Given the  following plant conditions:
Reactor pressure is 930 psig RPV level is +28 inches RCIC is injecting Twenty control rods are at position 48 Reactor power is 9000 cps on the SRMs and decreasing A 90 degree F/hr cooldown is in progress WHICH ONE (1) of the following would require termination of cooldown?
: a. RPV level lowers to +15 inches.
: b. SRM count rate increases to 10000 cps.
: c. Main turbine bypass valves fail closed.
: d. Drywell pressure begins to increase.
ION: 067    (1. 00)
WHICH ONE  (1) of the following responses will be noted on Unit 2 during a complete loss of Unit 2 I&C Bus during reactor operation?
: a. Unit  2  reactor water level increase
: b. Unit  1 Loop A    recirculation pump speed increase
: c. Unit  3 SJAE    flow to offgas system increase
: d. Unit  2  main steam tunnel temperature    increase
 
.REACTOR OPERATOR                                                                  Page 41 STION: 068            (1.00)
During a plant transient on Unit 2, a Group I isolation is caused by high radiation. Five control rods fail to insert. Suppression pool level is 12 feet and pool temperature is 94 degrees F.
WHICH ONE (1) of the following identifies the systems available to help maintain pressure below 1040 psig'?
: a. HPCI, RCIC
: b. RCIC,  RWCU'.
RWCU, MSL        drains
: d. MSL  drains, HPCI QUESTION: 069        (1.00)
During an
      ~
ATWS, EOIs        direct the operator to inhibit ADS automatic wdown when Standby            Liquid Control is injected. WHICH ONE (1) of the lowing states the basis for this requirement'?
          ~
: a. ADS  actuation would impose a severe pressure and temperature transient        on the vessel.
: b. ADS would result in the removal of boron after injected.
it has been
: c. Core damage could result from a large power excursion pressure        ECCS  systems were  to inject.
if  low
: d. ADS/MSRV        system flow  rate is incapable of assuring fuel cooling through steaming above          54 reactor power.
 
d%.
REACTOR OPERATOR                                                        Page 42 STION: 070  (1. 00)
While the reactor is operating at 90% power, reactor pressure is observed decreasing at an approximate rate of 200 psig per minute.
WHICH ONE (1) of the following is the expected immediate operator action'?
: a. Scram the reactor and place the pressure control    unit in manual.
: b. Scram the reactor and close the MSIVs.
: c. Take manual control of the reactor pressure control unit.
: d. Manually transfer to the backup pressure control unit.
QUESTION: 071    (1.00)
A failure of Drywell Control Air has resulted in Drywell control air being supplied by the Plant Control Air header. WHICH ONE (1) of the following is a concern during the malfunction?
        ~
: a. Moisture  in the air
                    ~
may cause  critical valves to fail.
: b. Torus temperature  may increase.
: c. Drywell oxygen level may increase.
: d. Breathing air is unavailable.
 
. REACTOR OPERATOR                                                          Page 43 STION: 072    (1.00)
WHICH ONE  (1) of the following systems is used to inject    Alternate Standby Liquid Control (SLC) boron into the reactor?
: a. Suppression Chamber Head Tank system I
: b. Control Rod Drive system
: c. RHR Standby Coolant system
: d. Condensate and Feedwater system QUESTION: 073    (1.00)
The  reactor has experienced an incomplete scram. WHICH ONE (1) of the following methods of rod insertion requires first resetting the SCRAM?
t      a. De-energization of scram solenoids
: b. Venting of the scram air header
: c. Scraming individual control rods using test switches
: d. Venting the Control Rod Drive over piston volume QUESTION: 074    (1 00)
                    ~
WHICH ONE  (1) of the following constitutes a loss of Secondary containment?
: a. The Reactor Building normal  HVAC is inoperable  and isolated.
: b. Both Reactor Building  ventilation radiation. monitors are  INOP.
: c. The Reactor Building/Suppression Chamber vacuum breaker    is open.
: d. The Standby Gas Treatment system  is inoperable.
 
dS, REACTOR OPERATOR                                                        Page 44 STION: 075  (1.00)
                    ~
EOI-2, Primary Containment Control, requires emergency depressurisation
            ~          ~
if
  ~
suppression pool level cannot be maintained within the safe region of curve 4, "SRV Tail Pipe Level Limit". WHICH ONE (1) of the following identifies the plant changes which both drive the plant toward the UNSAFE portion of the curve and an INCREASED possibility of SRV tail pipe failure?
: a. decreasing suppression pool water level, decreasing reactor pressure
: b. decreasing suppression pool water level, increasing reactor pressure
: c. increasing suppression pool water level, decreasing reactor pressure
: d. increasing suppression pool water level, increasing reactor pressure ION: 076  (1 00)
                  ~
Within two minutes after a loss of Reactor Building Closed Cooling Water, AOI 70-1, "Loss of RBCCW", directs that the reactor be scrammed and both recirculation pumps be tripped. WHICH ONE (1) of the following is the basis for this action?
: a. Loss  of cooling will lead to filter demin inlet temperature increase and auto isolation of RWCU.
: b. Loss of flow to RHR  pump coolers will prevent the RHR system from meeting design  criteria.
: c. Loss of cooling to the Recirculation pump seals will lead to  a primary coolant leak.
: d. Loss of Drywell cooling will lead to an increase in Drywell pressure, actuating safety related equipment.
 
0 REACTOR OPERATOR                                                              Page 45 STION: 077    (1 00)
While the plant is operating at full power, a complete loss of Control Air is experienced. WHICH ONE (1) of the following containment isolation valves is designed to fail open under these circumstances?
: a. Suppression Chamber vacuum      relief valves
: b. Main Steam Isolation Valve
: c. Refuel zone ventilation dampers
: d. RHR process water sampling valve QUESTION: 078    (1.00)
A  pipe shear has resulted in Control Air pressure immediately decreasing t
to  0 psig. WHICH ONE (1) of the following will remain available?
: a. Off Gas
: b. Stator Cooling Water
: c. Reactor Water Cleanup
: d. Raw Service Water supply to      fire systems QUESTION: 079    (1. 00)
WHICH ONE  (1)'f the following plant changes will result in the indication from LI 3-52, Post Accident Range Level instrumentation, becoming more accurate?
: a. Reactor pressure    increases from 900 to    1125. psig.
: b. Drywell temperature increases      from 100 to 212 degrees.
: c. Reactor building temperature increases from        100 to 130 degrees.
: d. Reactor  recirculation  pumps  are manually tripped.
 
d%.
REACTOR OPERATOR                                                        Page 46 TION: 080  (1. 00)
                  ~
The  reactor is shutdown with Recirculation  pumps  off. WHICH ONE (1)  of the following indicates reactor coolant stratification?
            ~
: a. Shutdown Cooling is out of service, RPV pressure is 5 psig, RX VESSEL FLANGE DR LINE temperature is 170 degrees F, and RX VESSEL FN NOZZLE N4B END temperature is 205 degrees F.
: b. Shutdown Cooling is in service, RPV pressure is 5 psig, RX VESSEL BOTTOM HEAD temperature is 215 degrees F, and RX VESSEL FW NOZZLE N4B END temperature  is 260 degrees F.
: c. Shutdown Cooling is out of service, RPV pressure is 0 psig, RX VESSEL FLANGE DR LINE temperature is 130, and feedwater sparger temperature is 170.
: d. Shutdown Cooling is in service, RPV pressure is 0 psig, RX VESSEL BOTTOM HEAD temperature is 140, and feedwater sparger temperature is 195.
 
0 d.)
REACTOR OPERATOR                                                            Page 47 STION: 081    (1.00)
A  Reactor startup is in progress on Unit 2 when the following annunciators actuate. Current readings are also given.
CRD ACCUM CHG WTR HDR                      1480 psig CRD DRIVE WTR FILTER DIFF PRESS  HIGH    50 psid Given the  following plant conditions:
Rx Power  is  5%
Reactor Pressure is 550 psig Charging Water Pressure is 1480 psig ~decreasing slowlyg 1 Accumulator is XNOP due to water level 1 CRD High Temperature alarm WHICH ONE  (1) of the following would be the correct IMMEDIATE action to take in accordance with 2-AOI-85-3, <<CRD System Failure" ?
: a. A Manual Scram  is required under current conditions.
: b. A Manual Scram is required if another Control Rod High t      c.
d.
Temperature alarm is received in conjunction with the LOW SUCTION PRESSURE A Manual Scram received.
A Manual Scram to  1400  psig.
alarm.
is required is required if a second if Charging Accumulator alarm Water Pressure CRD is decreases
 
0 0
 
8.)
REACTOR OPERATOR                                                              Page 48 STION: Q82      (1.QQ)
Unit 2 control room has been abandoned and reactor pressure is decreasing due to a controlled cooldown. Water level is being controlled with the RCIC system at remote shutdown panel 25-32, in accordance with 2-AOI-100-2, "Control Room Abandonment". When reactor pressure decreases to 50 psi, WHICH ONE of the following describes the status of the RCIC system under these circumstances?
: a. tripped and isolated.
: b. tripped but not isolated; can be restarted from Control Room
: c. tripped but not isolated; can NOT be restarted from Control Room
: d. RCIC    is running QUESTION: 083      (1.00)
Unit 2 is operating  \
at 1004  rated power  when  the following indications are received:
          ~
                ~
OG POST TREATMENT RADIATION HI-HI ALARM OG POST TREATMENT RADIATION HI-HI-HI/INOP ALARM OG PRETREATMENT RADIATION HI ALARM OG AVERAGE ANNUAL RELEASE LIMIT EXCEEDED ALARM WHICH ONE  (1)  of the following is the appropriate immediate operator action?
: a. Reduce reactor power      to  604 using recirc flow; manually scram the reactor.
: b. Reduce reactor power to 604 using recirc flow;        insert control rods in reverse order to shutdown the reactor.
: c. Reduce core flow to      60%;  manually scram the reactor.
: d. Reduce core flow      to  60%;  insert control rods in reverse order to shutdown the      reactor.
 
0 REACTOR OPERATOR                                                            Page 49 TION: 0&4    (1.00)
                    ~
During operation at 1004 power, a turbine trip occurs, and subsequently
    ~
a reactor scram signal is generated.        Mater level reaches -15 inches but
                      ~      ~
is recovered by the operator using the feedwater system. Reactor pressure initially reaches 1105 psig, but is controlled normally thereafter by the turbine bypass valves. During response to the transient, the operator notes that neither recirculation pump is running. WHICH ONE    (1)  of the following is the basis for the recirculation  pump  trip?
: a. To prevent damage to the recirculation pump seals when reactor pressure exceeds 1100 psig.
: b. To add negative      reactivity, counteracting the positive reactivity    added due    to the pressure increase which resulted from the turbine      trip.
: c. To promote level swell in the vessel, counteracting the shrink effects caused by the turbine trip.
: d. To protect the recirculation pumps from loss of adequate NPSH caused by the vessel level shrink resulting from the turbine trip.
 
0 B.i REACTOR OPERATOR                                                          Page 50 STION: 085    (1.00)
                    ~
A  loss of  all off-site ~
power has occurred at Unit 2. :You are directed to backfeed the Unit boards from the Diesel generators in order to start
                        ~
a CCW pump andestablish the Main Condenser as a heat sink for cooldown.
WHICH ONE (1) of the following describes the effect of taking the 2 BACKPEED switches on the Unit Boards (Panels 9-23-7 and 9-23-8) to the BACKFEED  position'?
: a. Automatically    trip and lockout the normal and alternate supply breaker, automatically trip the 43 switch to MANUAL, and allow the Unit Board to Shutdown Bus supply breaker to be manually closed.
: b. Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to MANUAL, and allow the alternate supply to Unit Board breaker to be manually closed.
: c. Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to AUTO and allow the alternate supply to Unit Board breaker to be manually closed.
: d. Automatically trip and lockout the alternate supply breaker, automatically trip the 43 switch to AUTO and allow the normal supply to Unit Board breaker to be auto closed.
QUESTION: 086    (1. 00)
Reactor power is 254, main turbine on line, when a small air leak into the condenser starts to reduce vacuum. After performing the subsequent actions of 2-AOI-47<<3, "Loss of Condenser Vacuum", condenser pressure stabilizes at 24" Hg vacuum. WHICH ONE of the following actions is appropriate?
: a. If condenser vacuum later decreases, trip the main turbine before condenser pressure reaches 7" vacuum.
      .b. Trip the main turbine.
: c. Start the mechanical vacuum pump.
: d. Increase SJAE steam inlet pressure to 225 psig.
 
0 d5.
REACTOR OPERATOR                                                            Page 51 I
STION: 087    (1.00)
Control Room instrumentation and annunciation indicates that three turbine stop valves have drifted to 804 open. No rod movement has occurred. You observe that the individual blue lights for each control rod on the full-core display are illuminated. Also, the eight scram solenoid group indicating lights are extinguished. WHICH ONE (1) of the following is a possible cause for the failure to SCRAM'?
: a. Failure of scram pilot valves to open.
: b. Only one RPS bus    is de-energized.
: c. Failure of scram    inlet and outlet valves to  open.
d- Hydraulic lock on the scram discharge volume.
QUESTION: 088    (1.00)
Unit  2 is operating at 25% power when a loss of I&C bus "A" occurs.      RPV evel control is selected to Level "A". Recirc pumps are in individua ua 1 control. WHICH ONE (1) of the following describes the"expected l
nt response and operator actions for this event?,
: a. Feed flow will increase until the turbine    trips  on high level.
A manual SCRAM should be inserted.
: b. Recirc pump B will run back to minimum speed, Recirc pump    A  will experience a scoop tube lockup. Recirc pump A should be manually run back to minimum speed.
: c. Recirc flow will increase    until the Reactor scrams on high  flux.
Both recirc  pumps  should be manually run back to minimum.
: d. Recirc pump A will run back to minimum speed, Recirc pump    B  will experience a scoop tube lockup. Recirc pump B should be, manually run back to minimum speed.
 
~ REACTOR OPERATOR                                                              Page 52 I
TION: 089    (1.00)
Given the  following plant conditions:
RPV level                  +56 inches RPV pressure              1040 psig Drywell press.            2.40 psig Torus level                +1 inch Rx zone vent rad          75 mr/hr Refuel zone vent rad      62 mr/hr WHICH ONE (1) of the following EOI groups should be entered?
: a. EOI-1, "RPV Control" and EOI-2, and EOI-4, Radiation Release Control.
: b. EOI-1, "RPV Control" and EOI-2, "Primary Containment Control".
: c. EOI-2, "Primary Containment Control" and EOI-3, "Secondary Containment Control"..
: d. EOI-3, "Secondary Containment Control" and EOI-4, Radiation Release Control.
QUESTION: 090    (1.00)
Unxt  2 is operating at rated  power when  all  RBCCW  pumps  trip and none can be  restarted. WHICH ONE (1) of the  following describes the IMMEDIATE operator actions appropriate for this situation?
: a. Reduce recirculation flow to minimum,      if  recirc pump seal cavity temperature exceeds 200 degrees F on BOTH pumps, TRIP both recirc pumps and SCRAM the reactor.
: b. If drywell temperature exceeds 145 degrees F, or drywell pressure exceeds 1.66 psig, insert a manual SCRAM, and trip both recirculation pumps.
: c. Run recirculation pumps to 454    speed,  insert,  a manual SCRAM, Trip both recirculation pumps,    and  initiate    a cooldown of 90 degrees F/hour.
: d. IMMEDIATELY TRIP both  recirc pumps and SCRAM      the reactor.
 
0
~ I
 
REACTOR OPERATOR                                                            Page 53 TION: 091    (1.00)
While offloading fuel bundles from the reactor, fuel pool level begins to decrease uncontrollably. WHICH ONE (1) of the following describes a method available from the control room to add water to the fuel pool?
: a. Align fuel pool cooling and cleanup heat exchanger      RBCCW supply to the fuel pool to maintain level.
: b. Start an RHR pump and    inject to the reactor vessel to maintain fuel pool level.
: c. Open emergency makeup supply valve from EECW to the fuel pool to maintain level.
  ~I
: d. Open the CST to Fuel Pool Gravity drain valves.
i QUESTION: 092      (1 00)
WHICH ONE    (1) of the following scram signals is effective  ONLY when  the mode  switch is in RUN?
: a. IRM  hi-hi
: b. Turbine stop valve closure
: c. MSIV closure
: d. EHC low oil pressure QUESTION: 093      (1.00)
Unit  2  is operating at  254 power. WHICH ONE  (1) of the following combinations of events    will NOT result in  a  half reactor scram?
: a. Both  MSIV's in steam lines "A" and "B" isolate
: b. Both  MSIV's in steam lines "A" and "D" isolate
: c. APRM  "E" and "C" trip on hi-hi flux
: d. APRM  "E" and >>A" trip on hi-hi flux 0
 
REACTOR OPERATOR                                                      Page 54 STION: 094  (1. 00)
WHICH ONE  (1) of-the following conditions requires  a manual reactor SCRAM?
: a. RBCCW pump  suction header temperature of 102 degrees F
: b. Pre-treatment radiation HI-HI-Hi
: c. Both recirculation pumps trip with the mode switch in Startup
: d. Off-gas system Hydrogen concentration of 54 QUESTION: 095  (1.00)
WHICH ONE  (1) of the following conditions assures ADEQUATE CORE COOLING?
: a. All rods inserted, RPV level -200, MSRV's cycling on pressure, no injection flow.
: b. RPV level unknown, 6 MSRV's open, reactor pressure is 10 psig.
: c. Reactor power 3%, RPV level -210, one MSRV open, HPCI injecting at maximum flow.
: d. RPV level -230, RHR "B" and "D" injecting at maximum flow, suppression pool level at 15 feet.


1.'echnical Specification 4.3.B.1.a 2~OPL171~006, Obj.14 3~K/Ae 201003G001 (3'/3')201003G001
d5.
..(KA's)ANSWER: 002 (1.00)b.
, REACTOR OPERATOR                                                                              Page 55 1
TION: 096    ( 1. 00)
The Control Room has been abandoned.       All MSRV transfer switches at panel 25-32 have been placed in EMERGENCY. All MSRV control switches at panel 25-32 are in CLOSE. WHICH ONE (1) of the following states the opening capability of the MSRUs?
: a. ONLY manually by placing the panel 25-32 control switches in                        ~
OPEN
: b. ONLY  manually  OR  upon receipt of an ADS initiation signal
: c. ONLY  manually  OR  when their respective pressure relief setpoint is  reached
: d. EITHER manually OR on an ADS initiation signal      OR when                    their respective pressure relief setpoint is reached QUESTION: 097      (1 00) loop I is in shutdown cooling taking suction through Shutdown ing suction valves 74-47 and 74-4&.
I standby lineup. Due to misoperation Loop II of RHR remains in the of ventilation systems, Drywell pressure increases to 2.5 psig. WHICH ONE (1) of the the response of the RHR system?                        following'escribes
: a. Valves 74-47 and 74-48 close, Loop I suppression pool suction valves auto open and BOTH RHR loops inject to the vessel.
: b. Valves 74-47 and 74<<48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves auto open but only Loop II injects.
: c. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and only Loop injects.
II
: d. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and NEITHER Loop injects.


==REFERENCE:==
0 dS.i REACTOR OPERATOR                                                          Page 56 STION: 098    (F ~ 00)
An emergency  exists which requires addition of water to the suppression
                    ~
pool. Your supervisor directs use of Appendix 18 of the Emergency Procedures. Using Appendix 18, WHICH ONE (1) of the following describes the availability of HPCI and RCIC'?
: a. Neither HPCI nor RCIC are available    if they have isolated.
: b. Both HPCI and RCIC are available even    if they have isolated.
: c. HPCI is available unless if isolated.              it has isolated; RCIC is available even
: d. RCIC is available unless if  isolated.
it has isolated; HPCI is available even QUESTION: 099    (1.00)
WHICH ONE  (1) of the following is  the Technical Specification safety it for reactor      pressure?
: a. 1120 psig
: b. 1125 psig
: c. 1250 psig
: d. 1375 psig


OPL171.006, Ob j~130 K/A: 201001K303 (3.1/3.2)201001K303
d%.
..(KA's)ANSWER: 003 (1.00)a~
REACTOR OPERATOR                                                      Page 57 STION: 100    (1 ~ 00)
Unit 3 fuel loading is in progress. WHICH ONE (1) of the following lists the two required communication links between the Unit operator  and the refuel bridge?
: a. PAX phone and radio
: b. PAX  phone and Paging system
: c. Sound Powered phone and radio
: d. Sound Powered phone and Paging system
(**********
END OF EXAMINATION **********)


==REFERENCE:==
0 REACTOR OPERATOR Page 1 ANSWER      K E Y MULTIPLE CHOICE                  b 001: d ar                  024      b 002    b                  025 m
a 003      a                  026      b 004    b                  027      c 005    6                  028      c 006    c                  029    b
'23 007    a                  030    c ooe    a                  031    b 009      a                  032      a d                  033      a 011    cj 034      a 012    c                  035    d 013    b                  036    a 014    c                  037    a 015      c                  038      c 016    c                  039      c 017                        O4O    a 018    c                  041    b 019    a                  042    b 020    a                  043    b 021    a                  044    c O45    a


1.OPL171.029, Obj.1, page 9 2~K/A 201002G008 (3~6/3~4)201002G008
REACTOR OPERATOR Page 2 A N S W E R    K E Y 046      cj                  069      c 047 '                        070      b 048      c                    071      c 049      b                    072      b 050      c                  073      c 051                          074      6 052      d                    075 053      d                    076      6 054      c                    077      a 055 078    b 079      6 057      a or d              080      a 058      c                    081 059      b                    082      6 060                          083      a 061      P'                    084    b 062      a                    OS5    a 063      a                    086    'b O64      a                    087 065      6                    088      b 066      b                    089      c 067      8                    090      c b                    091    b
..(KA's) 0 ,
REACTOR OPERATOR Page 59 WER: 004 (1.00)b.


==REFERENCE:==
B.i REACTOR OPERATOR Page 3 ANSWER      K E Y 092    c 093: b 094  6 095    a 096    c 097    ~J 098    c 099    6 100    c 0
(**********
END OF EXAMINATION **********)


1.'PL171.016 Obj.4, page 19 2.K/A: 223001A302 (3.4/3 4)223001A302
REACTOR OPERATOR                                Page 58 WER    001  (1. 00) a.g b
..(KA's)ANSWER: 005 (1.00)


==REFERENCE:==
==REFERENCE:==
 
: 1.  'echnical Specification          4.3.B.1.a OPL171 ~ 006, Obj. 14
t OPL 171.029, Obj.9, pages 21, 26 K/A: 201002A402 (3~5/3.5)201002A402
                                '/3 ')
..(KA's)ANSWER: 006 (F 00)C~
2 ~
3 ~   K/Ae 201003G001 (3 201003G001        .. (KA's)
ANSWER:     002  (1. 00) b.


==REFERENCE:==
==REFERENCE:==


1.OPL171.020, Obj.5 2~K/A: 215003K401 (F 7/3.7)215003K401
OPL171. 006, Ob K/A: 201001K303 j ~  130 (3. 1/3. 2) 201001K303        .. (KA's)
..(KA's) 8 REACTOR OPERATOR Page 60 WER: 007 (1 00)a~
ANSWER:     003  (1. 00) a~


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.029, Obj. 1, page 9 2~    K/A 201002G008 (3 ~ 6/3 ~ 4) 201002G008        ..(KA's)
0


1.: OPL171.043, Obg.4, page 9 2~K/A: 2 18000K403 (3~8/4~0)2 18 OOOK4 03..(KA's)ANSWER: 008 (1.00)
REACTOR OPERATOR Page 59 WER:     004  (1. 00) b.


==REFERENCE:==
==REFERENCE:==
 
: 1.  'PL171.016 Obj.         4, page 19
OPL171.009, Obj.5, page 12 K/A: 239002K605 (3 0/3'}239002K605
: 2. K/A: 223001A302 (3.4/3 4) 223001A302          ..(KA's)
..(KA's)ANSWER: 009 (1.00)a~
ANSWER:     005  (1.00) t


==REFERENCE:==
==REFERENCE:==


1.2-AOI-85-3, Rev 10, p.3 of 5,"Caution" 2..GE SIL 139 3 K/A: 201001A208 (2'/2')
OPL 171.029, Obj.9, pages 21, 26 K/A: 201002A402 (3 5/3 . 5) 201002A402          ..
REACTOR OPERATOR Page 61 WER 010 (1.00)cl 0 REFERENCE 1.'PL171.033, Obj.3, page 14 2.AOI 66-2, page 1 3~K/A: 272000K403 (3.6/3')272000K403
                                  ~
..(KA's)ANSWER: 011 (1.00)d.
(KA's)
ANSWER:     006  (F 00)
C~


==REFERENCE:==
==REFERENCE:==
: 1.      OPL171.020, Obj. 5 2 ~    K/A: 215003K401 (F 7/3.7) 215003K401        ..(KA's)


OPL171.044, Obj.11, page 27 K/A: 226001A403 (3~5/3~4)226001A403
8 REACTOR OPERATOR                                        Page 60 WER:     007  (1 00) a~
..(KA's)ANSWER: 012 (1.00)Co


==REFERENCE:==
==REFERENCE:==


1.OPL171.044, Obj.14, page 29 2.K/A: '03000K601 (3~6/3.7)203000K601
1.:      OPL171.043,     Obg. 4, page   9 2 ~    K/A: 2 18000K403 (3 8/4 0)
..(KA's)
                                ~  ~
REACTOR OPERATOR Page 62 b.WER: 013 (1.QO)
2 18 OOOK4 03      .. (KA's)
ANSWER:       008  (1. 00)


==REFERENCE:==
==REFERENCE:==


1.: OPL171.Q44, Obj.12, page 30 2.K/A: 205000A302 (3~2/3.2)205000A302
OPL171.009, Obj. 5, page 12 K/A: 239002K605 (3 0/3   '}
..(KA's)ANSWER: 014 (1.00)Co REFERENCE OPL171.043, Obj.4, pages 9, 10 K/A 218000K501 (3'/3 8)218000K501
239002K605        ..(KA's)
..(KA's)ANSWER: 015 (1.00)co
ANSWER:       009  (1.00) a~


==REFERENCE:==
==REFERENCE:==
: 1.      2-AOI-85-3, Rev 10, p.      3 of 5, "Caution" GE SIL 139 2..
3        K/A: 201001A208 (2  '/2 ')


1.Technical Specification 4.6.E.1 2.OPL171.007, Obj.32, page 54 3.K/A: 202001G005 (3.4/4')202001G005
REACTOR OPERATOR Page 61 WER      010  (1. 00) cl 0 REFERENCE
..(KA's)
: 1.   'PL171.033, Obj.         3, page 14
REACTOR OPERATOR Page 63 WER 016 (1 00)Co
: 2.      AOI 66-2, page 1 3 ~    K/A: 272000K403 (3.6/3        ')
272000K403          .. (KA's)
ANSWER:        011  (1.00) d.


==REFERENCE:==
==REFERENCE:==


1.: OPL171.Q07, Obj.31, pages 54, 34 2.OI-68, page 6 3~K/A: 202002G010 (3'/3')202002G010
OPL171.044, Obj. 11, page 27 K/A: 226001A403 (3 5/3 4)~  ~
..(KA>s)ANSWER: 017 (1.00)'6~
226001A403          ..(KA's)
ANSWER:       012  (1. 00)
Co


==REFERENCE:==
==REFERENCE:==
: 1.      OPL171.044, Obj.14, page 29
: 2.      K/A: '03000K601 (3 6/3. 7)
                                  ~
203000K601        .. (KA's)


i OPL171.007, Obj.26, page 50, Table 1 K/A: 202001K402 (3'/3')2020Q1K402
REACTOR OPERATOR                       Page 62 WER:   013  (1. QO) b.
..(KA's)ANSWER 018 (1 00)C~REFERENCE 1.OPL171.007, Obj.8, page 21 2~K/A: 202002K305 (3.2/3.3)202002K305
..(KA's)
 
REACTOR OPERATOR Page 64 a.WER: 019 (1.00)


==REFERENCE:==
==REFERENCE:==


1." OPL171.007, Obj.10, page 23 2~K/A: 202001A411 (3~2/3~3)202001A411
1.:  OPL171.Q44, Obj. 12, page 30
..(KA's)ANSWER: 020 (1.00)a~REFERENCE OPL171.042, Obj 6, page 33 K/A: 206000K204 (2~5/2~7)206000K204
: 2. K/A: 205000A302 (3 2/3. 2)
..(KA s)ANSWER: 021 (1.00)REFERENCE 1.OPL171.042, Obj.4, page 8 2.K/A: 206000K419 (F 7/3.8)206000K419
                            ~
..(KA's)
205000A302      .. (KA's)
REACTOR OPERATOR Page 65 WER: 022 (1 00)d.
ANSWER:     014  (1. 00)
Co REFERENCE OPL171.043, Obj. 4, pages 9, 10 K/A 218000K501 (3    '/3 8) 218000K501      .. (KA's)
ANSWER:     015  (1. 00) co


==REFERENCE:==
==REFERENCE:==
: 1. Technical Specification 4.6.E.1 2.
: 3. K/A: 202001G005 (3.4/4  ')
OPL171.007, Obj. 32, page 54 202001G005      ..(KA's)


1.'PL171 022, Ob j~7 2.K/A: 215003K106 (3.9/4.0)215003K106
REACTOR OPERATOR                              Page 63 WER    016  (1 00)
..(KA's)ANSWER: 023 (1 00}
Co


==REFERENCE:==
==REFERENCE:==


OPL171.045, Obj.8, page 14 K/A: 209001K404 (3.0/3~2)209001K404
1.:    OPL171.Q07, Obj. 31, pages 54, 34 OI-68, page 6 2.
..(KA's)ANSWER: 024 (1.00)b.
3  ~  K/A: 202002G010 (3   '/3 ')
202002G010      .. (KA>s)
ANSWER:       017  (1. 00) i
'6 ~


==REFERENCE:==
==REFERENCE:==


1.OPL171.045, Obj.2a, page 20 2.K/A: 209001K408 (3.8/4.0)..(KA's)  
OPL171.007, Obj. 26, page 50, Table 1 K/A: 202001K402 (3  '/3 ')
2020Q1K402      .. (KA's)
ANSWER      018  (1 00)
C~
REFERENCE
: 1.     OPL171.007, Obj. 8, page 21 2~      K/A: 202002K305 (3. 2/3. 3) 202002K305      .. (KA's)


REACTOR OPERATOR Page 66 WER: 025 (1 00)a~
REACTOR OPERATOR                       Page 64 WER:   019  (1.00) a.


==REFERENCE:==
==REFERENCE:==
: 1. " OPL171.007, Obj.10, page 23 2 ~    K/A: 202001A411 (3 2/3 3)
                            ~  ~
202001A411      ..(KA's)
ANSWER:      020  (1. 00) a~
REFERENCE OPL171.042, Obj 6, page 33 K/A: 206000K204 (2 ~ 5/2 ~ 7) 206000K204      .. (KA s)
ANSWER:    021  (1. 00)
REFERENCE
: 1. OPL171.042, Obj. 4, page      8
: 2. K/A: 206000K419 (F 7/3.8) 206000K419      .. (KA's)


1.: OPL171.017, Obj.7, page 14 2.OPL171.045, Obj.2b, page 12 3~K/A: 223002A102 (3'/3')223002A102
REACTOR OPERATOR                    Page 65 WER:   022  (1 00) d.
..(KA's)ANSWER: 026 (1.00)


==REFERENCE:==
==REFERENCE:==
 
: 1. 'PL171    022, Ob  j ~ 7
~~~~~~~OPL171.017, Obj.7, page 13 K/A: 223002K101 (3.8/3~9)223002K101
: 2. K/A: 215003K106 (3.9/4.0) 215003K106        .. (KA's)
..(KA's)ANSWER: 027 (1.00)Co l(
ANSWER:   023    (1 00}
REACTOR OPERATOR Page 67


==REFERENCE:==
==REFERENCE:==


OPL171.009, Obj.14 OPL171.017, Obj.6, page 19 K/A: 239001A212 (4.2/4.3)239001A212
OPL171.045, Obj. 8, page 14 K/A: 209001K404 (3. 0/3 2)~
..(KA's)ANSWER: 028 (1.00)C~
209001K404        ..(KA's)
ANSWER:   024    (1.00) b.


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.045, Obj. 2a, page 20
: 2. K/A: 209001K408 (3.8/4.0)
                      ..(KA's)


1.OPL171.039, Obj.6, page 21 2~K/A: 211000A308 (4.2/4')211000A308
REACTOR OPERATOR                      Page 66 WER:   025  (1 00) a~
..(KA's)ANSWER: 029 (1.00)b.REFERENCE 1~OPL171 030 t Ob j 1 2~K/A: 271000K104 (2~7/2~7)271000K104
..(KA's)ANSWER: 030 (l.00)C~0


REACTOR, OPERATOR Page 68
==REFERENCE:==
: 1.  : OPL171.017, Obj. 7, page 14 2.
3 ~    K/A: 223002A102 (3    '/3 ')
OPL171.045, Obj. 2b, page 12 223002A102      .. (KA's)
ANSWER:    026  (1. 00)


==REFERENCE:==
==REFERENCE:==


t OPL171.023 Objective 2, Rev 2, p.10 of 44 K/A: 215001A208 (F 7/2.9)215001A208
OPL171.017,
..(KA's)ANSWER: 031 (1~00)b.'EFERENCE:
              ~      Obj.~ 7, page 13
1.OPL 171.053, Rev 3, p.13 of 46, Obg.6 2~K/A: 234000K502 (3'/3.7)234000K502
                        ~
..(KA's)ANSWER: 032 (1.00)a~
K/A: 223002K101 (3. 8/3 ~ 9) 223002K101      ..(KA's)
ANSWER:     027  (1.00)
Co
 
l(
REACTOR OPERATOR                  Page 67


==REFERENCE:==
==REFERENCE:==


1.OPL171.033, Rev 4, p.21 of 62 2.K/A: 288000K105 (3'/3')288000K105
OPL171. 009, Obj. 14 OPL171.017, Obj. 6, page 19 K/A: 239001A212 (4.2/4.3) 239001A212      .. (KA's)
..(KA's)ANSWER: 033 (1.00)a~
ANSWER:     028  (1. 00)
REACTOR OPERATOR 8.)Page 69 OPL171.013, Rev 3, p.8 of 33, Objective 2 OPL171.056, Rev 3, p.7 of 23, Objective 1.a K/A: 290002K114 (2'/3.1)290002K114
C~
..(KA's)ANSWER: 034 (1.00)a~


==REFERENCE:==
==REFERENCE:==


1.OPL171.038, Obj.5, page 17 OF 75 2~K/A 262001K401 (3'/3')262001K401
1.
..(KA's)ANSWER: 035 (1 00)6~
2 ~  K/A: 211000A308 (4.2/4  ')
OPL171.039, Obj. 6, page 21 211000A308      .. (KA's)
ANSWER:    029  (1. 00) b.
REFERENCE 1~
2~
OPL171 030 t Ob j  1 K/A: 271000K104 (2 7/2 7)
                            ~  ~
271000K104      .. (KA's)
ANSWER:     030  (l. 00)
C~
0
 
REACTOR, OPERATOR                                  Page 68 t


==REFERENCE:==
==REFERENCE:==


1.OPL171.038, Obj.11, page 52 OF 75 2~K/A 264000G007 (3 6/3~8)264000G007
OPL171.023 Objective 2, Rev 2, p. 10 K/A: 215001A208 (F 7/2.9) of 44 215001A208        .. (KA's)
..(KA s)ANSWER: 036 (1.00) 0' REACTOR OPERATOR Page 70
ANSWER:    031  (1 ~ 00) b.
'EFERENCE:
: 1. OPL 171.053, Rev 3, p. 13 of 46, Obg. 6 2 ~   K/A: 234000K502 (3 '/3.7) 234000K502        .. (KA's)
ANSWER:   032  ( 1. 00) a~


==REFERENCE:==
==REFERENCE:==


~~~~~~~OPL171.038, Obj.12, page 60 K/A 264000K506 (3'/3')264000K506
                              '/3 ') of 62
..(KA's)ANSWER: 037 (1.00)'a~
: 1. OPL171.033, Rev 4, p. 21
: 2. K/A: 288000K105 (3 288000K105        .. (KA's)
ANSWER:    033  (1.00) a~
 
8.)
REACTOR OPERATOR                                    Page 69 OPL171.013, Rev 3, p. 8 of 33, Objective 2 OPL171.056, Rev 3, p. 7 of 23, Objective 1.a K/A: 290002K114 (2 '/3.1) 290002K114        ..(KA's)
ANSWER:   034  (1. 00) a~


==REFERENCE:==
==REFERENCE:==


l.OPL171.037, Obj.9, page 17 of 26 2~K/A 26300QK303 (3 4/3~8)263000K303
1.
..(KA's)ANSWER 038 (1.00)Co REFERENCE 1.OPL171.036, REV 2, Obj.12, page 19 of 37 2~K/A 263000K101 (3'/3.5)263000K101
2~   K/A 262001K401 (3   '/3 ')
..(KA's)ANSWER: 039 (1.00)Ce 0
OPL171.038, Obj. 5, page 17  OF 75 262001K401        .. (KA's)
.REACTOR OPERATOR d%.: Page 71 REFERENCE OPL171.067, Obj.11, 27 K/A: 290001K107 (3~0/3.1)290001K107
ANSWER:    035  (1 00) 6~
..(KA's)ANSWER 040 (1.00)a~


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.038, Obj. 11, page 52  OF 75 2~  K/A 264000G007 (3 6/3 8)  ~
264000G007        .. (KA s)
ANSWER:    036  (1. 00)


1.OPL171.049, Obj.5, page 41 2~K/A: 286000K402 (3.3/3~5)286000K402
0' REACTOR OPERATOR                                    Page 70
..(KA's)ANSWER: 041 (1 00)b.


==REFERENCE:==
==REFERENCE:==
~              ~
OPL171.038,
                              '/3 ')
Obj. 12, page 60
                          ~
                ~          ~
K/A 264000K506 (3 ~      ~
264000K506      .. (KA's)
ANSWER:      037  (1. 00)
'a  ~


1.OPL171.049, Obj.2,5, Page 45 2~K/A: 286000A105 (3 2/3~2)286000A105
==REFERENCE:==
..(KA's)ANSWER: 042 (1.00)b.
: l.     OPL171.037, Obj. 9, page 17    of 26 2  ~    K/A 26300QK303 (3 4/3 8)  ~
263000K303      .. (KA's)
ANSWER      038  (1. 00)
Co REFERENCE
: 1.      OPL171.036, REV 2, Obj. 12, page 19  of 37 2 ~   K/A 263000K101 (3 '/3.5) 263000K101      ..(KA's)
ANSWER:     039  (1. 00)
Ce


REACTOR OPERATOR Page 72
0 d%.:
. REACTOR   OPERATOR                   Page 71 REFERENCE OPL171.067, Obj. 11, 27 K/A: 290001K107 (3 ~ 0/3. 1) 290001K107      ..(KA's)
ANSWER      040  (1. 00) a~


==REFERENCE:==
==REFERENCE:==
 
: 1. OPL171.049, Obj. 5, page 41 2 ~  K/A: 286000K402 (3. 3/3 5) ~
I~~~~~OPL171~011, Obj.4 K/A: 256000K107 (2.9/2')256000K107
286000K402      .. (KA's)
..(KA's)ANSWER: 043 (1.00)b.
ANSWER:       041  (1 00) b.


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.049, Obj. 2,5, Page 45 2 ~  K/A: 286000A105 (3 2/3 2)  ~
286000A105      .. (KA's)
ANSWER:      042  (1. 00) b.


l.OPL171.011, Obj.4 2~K/A: 256000A107 (3.1/3.1)256000A107
REACTOR OPERATOR                         Page 72
..(KA's)ANSWER: 044 (1~00)Ca REFERENCE l.OPL171.044(Obj.9 2~K/A: 203000K202 (2.5/2~7)203000K202
..(KA's)ANSWER: 045 (1.00)a~0 REACTOR OPERATOR Page 73 REFERENCE~~AOI 100-1, page 26 K/A: 212000K412 (3'/4')212000K412
..(KA's)ANSWER: 046 (1.00)REFERENCE 1.OPL171.033, Obj.1 2~K/A: 272000K402 (3.7/F 1)..(KA's)ANSWER: 047 (1.00)b.


==REFERENCE:==
==REFERENCE:==
I Obj.
                                      ')
                            ~
OPL171 ~ 011,          ~  4 K/A: 256000K107          (2.9/2
                                  ~  ~
256000K107          ..(KA's)
ANSWER:    043  (1. 00) b.


1.OPL171.035, Obj.8 2.K/A: 2 150 02K502 (2~4/2~5)215002K502
==REFERENCE:==
..(KA's)ANSWER: 048 (1~00)  
: l. OPL171. 011, Obj . 4 2~    K/A: 256000A107 (3 . 1/3 . 1) 256000A107          .. (KA's)
ANSWER:    044    ( 1 ~ 00)
Ca REFERENCE
: l. OPL171.044( Obj. 9 2 ~  K/A: 203000K202 (2. 5/2 ~ 7) 203000K202          .. (KA's)
ANSWER:   045    (1. 00) a~
0


REACTOR OPERATOR d%.i Page 74
REACTOR OPERATOR Page 73 REFERENCE AOI 100-1, page 26 K/A: 212000K412 (3 ~      '/4 ')~
212000K412          ..(KA's)
ANSWER:    046    (1. 00)
REFERENCE
: 1. OPL171.033, Obj. 1 2~    K/A: 272000K402 (3.7/F 1)
                          .. (KA's)
ANSWER:    047    (1. 00) b.


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.035, Obj.        8
: 2. K/A:  2 150 02K502    (2 ~ 4/2 ~ 5) 215002K502          .. (KA's)
ANSWER:    048    (1 00)
                      ~


~~~~OPL171.012, Rev 4, p.30 of 55~K/A: 216000K312 (3.7/3~8)216000K312 I..(KA's)ANSWER: 049 (1 00)b.REFERENCE 1.OPL171.012, Rev 5, Obj.6, page 24 of 55 2~K/A: 259002K604 (3..1/3~1)259002K604
d%.i REACTOR OPERATOR                                  Page 74
..(KA's)ANSWER: 050 (1.00)C~


==REFERENCE:==
==REFERENCE:==
              ~
OPL171.012,
                ~      Rev 4, p.~ 30 of 55
    ~    K/A: 216000K312 (3. 7/3 ~ 8)
I 216000K312      .. (KA's)
ANSWER:      049  (1 00) b.
REFERENCE
: 1.      OPL171.012, Rev 5, Obj. 6, page 24 of 55 2 ~    K/A: 259002K604 (3.. 1/3 1)~
259002K604        .. (KA's)
ANSWER:      050  (1.00)
C~


1.2-OI-3, Rev 23, Precaution 3.1 2.2-AOI-3-1, Rev 7, 3.1, 3.2 3~K/A: 259001A310 (3.4/3.4)259001A310
==REFERENCE:==
..(KA's)ANSWER: 051 (1.00)  
: 1.     2-OI-3, Rev 23, Precaution 3.1
: 2.     2-AOI-3-1, Rev 7, 3.1, 3.2 3 ~     K/A: 259001A310 (3.4/3.4) 259001A310       .. (KA's)
ANSWER:     051   (1. 00)


REACTOR OPERATOR d.Page 75  
d.
REACTOR OPERATOR                                       Page 75


==REFERENCE:==
==REFERENCE:==


EOZPM Section XZ-B, Operator Cautions, page 4 K/A: 216000K507 (3.6/3.8)216000K507
EOZPM   Section XZ-B, Operator Cautions, page 4 K/A: 216000K507 (3.6/3.8) 216000K507         .. (KA's)
..(KA's)ANSWER: 052 (1.00)d.
ANSWER:   052   (1. 00) d.


==REFERENCE:==
==REFERENCE:==


1~SSP 2~8 g REV 003 g p 9 of 37 2.K/A: 294001A101 (2.9/3')..(KA's)ANSWER: 053 (1.00)d.
of 1~
2.
SSP 2 ~ 8 g REV 003 g K/A: 294001A101 (2.9/3 p  9
                                ') 37
                      .. (KA's)
ANSWER:   053   (1. 00) d.


==REFERENCE:==
==REFERENCE:==


1~SSP-12 F 1, P.81-95 2.KA: 294001A102 (4.2*/4.2*)
1~   SSP-12 F 1, P. 81-95
294001A102
: 2. KA: 294001A102 (4.2*/4.2*)
..(KA's)ANSWER: 054 (1 00)C~
294001A102         .. (KA's)
REACTOR OPERATOR d5.Page 76  
ANSWER:   054   (1 00)
C~
 
d5.
REACTOR OPERATOR Page 76


==REFERENCE:==
==REFERENCE:==


RCI-1, REV 0033, p.19 K/A: 294001K103 (3.3/3')294001K103
RCI-1, REV 0033, p. 19 K/A: 294001K103 (3.3/3     ')
..(KA's)ANSWER: 055 (1.00)d.
294001K103         ..(KA's)
ANSWER:     055   (1. 00) d.


==REFERENCE:==
==REFERENCE:==


1~RCI 2 g REV 0020'6 2.EPIP 15, section 3.1 3~K/A: 294001K103 (3'/3 8)..(KA's)ANSWER: 056 (1 00)b.
1~     RCI 2 g REV 0020'       6
: 2. EPIP 15, section 3.1 3 ~   K/A: 294001K103 (3   '/3   8)
                          ..(KA's)
ANSWER:     056   (1 00) b.


==REFERENCE:==
==REFERENCE:==
: 1. RCI-13, page 5
: 2. K/A: 294001K114 (3    '/3 ')
294001K114        .. (KA's)
ANSWER:      057  (1. 00)
: a. 0~ g 0


1.RCI-13, page 5 2.K/A: 294001K114 (3'/3')294001K114
0 dR.
..(KA's)ANSWER: 057 (1.00)a.0~g 0 0
, REACTOR OPERATOR                                           Page 77
, REACTOR OPERATOR dR.Page 77  


==REFERENCE:==
==REFERENCE:==


SSP 12.6, page 7 OI VOL 13'GOI 300 3g p 7 of 10 K/A: 294001K101 (F 7/3 7)294001K101
SSP 12.6, page 7 OI VOL 13'     GOI 300 3g p     7 of 10 K/A: 294001K101 (F 7/3 7) 294001K101       .. (KA's)
..(KA's)ANSWER: 058 (F 00)Co  
ANSWER:     058   (F 00)
Co


==REFERENCE:==
==REFERENCE:==
 
: 1. SSP-12.1, REV 0008, p. 59     of 95 2 ~   K/A: 294001A106 (3 4/3 6)
1.SSP-12.1, REV 0008, p.59 of 95 2~K/A: 294001A106 (3 4/3 6)..(KA's)ANSWER 059 (1 00)
                        ..(KA's)
ANSWER       059 (1 00)


==REFERENCE:==
==REFERENCE:==


1.SSP-12.6, REV 0001, p.4 of 20 and p.7 of 20 2 K/A: 294001K101 (3.7/3')294001K101
1.
..(KA's)ANSWER: 060 (1.00)  
2 SSP-12.6, REV 0001, p.
K/A: 294001K101 (3.7/3     ') of 4    20 and  p. 7 of 20 294001K101       .. (KA's)
ANSWER:     060 ( 1. 00)


REACTOR OPERATOR Page 78  
REACTOR OPERATOR                       Page 78


==REFERENCE:==
==REFERENCE:==


~~~SSP-12.1, REV 0008, p.34 of 95 K/A: 294001A111 (3.3/4.3)294001A111
SSP-12.1, REV 0008, p. 34 of 95
..(KA's)ANSWER: 061 (1 00)p: q REFERENCE 1.SSP 1.6, REV 002, p.5 of 53 2 K/A: 294001K105 (3'/3')..(KA's)ANSWER: 062 (1.00)a~
              ~                ~
K/A: 294001A111 (3.3/4.3) ~
294001A111       .. (KA's)
ANSWER:   061   (1 00) p: q REFERENCE
: 1.       1.6,                   of
                          '/3 ')
002, p. 5       53 SSP      REV 2   K/A: 294001K105 (3
                      .. (KA's)
ANSWER:   062   (1. 00) a~


==REFERENCE:==
==REFERENCE:==
: 1. SSP 5.1, page 10 2    K/A 294001K103 (3    '/3 ')
294001K103        .. (KA's)
ANSWER:    063  (1. 00) a~


1.SSP 5.1, page 10 2 K/A 294001K103 (3'/3')294001K103
d%.
..(KA's)ANSWER: 063 (1.00)a~
REACTOR OPERATOR                         Page 79 REFERENCE OSZL     100 g P 2 of 3 t 5/24/93 K/A: 294001A106 (2.9/4.7) 294001A106         ..(KA's)
REACTOR OPERATOR d%.Page 79 REFERENCE OSZL 100 g P 2 of 3 t 5/24/93 K/A: 294001A106 (2.9/4.7)294001A106
ANSWER:,   064   (l. 00) a~
..(KA's)ANSWER:, 064 (l.00)a~


==REFERENCE:==
==REFERENCE:==
: 1. OPL171. 204, Ob j 2 ~
2 ~  K/A: 295036G011 (3 8/4 1)    ~
295036G011        ..(KA's)
R:    065  (1.00) 6~


1.OPL171.204, Ob j~2 2~K/A: 295036G011 (3 8/4~1)295036G011
==REFERENCE:==
..(KA's)6~R: 065 (1.00)
 
1 2~
OPL171 ~ 202, Ob3 K/A'95037G007 (3 7/3
                          ~ 13
                                    ')
295037G007        .. (KA's)
ANSWER:     066  (1 00) b.
 
, REACTOR OPERATOR Page 80


==REFERENCE:==
==REFERENCE:==


1 OPL171~202, Ob3~13 2~K/A'95037G007 (3 7/3')295037G007
e          OPL171.205, Obj. 7b K/A: 295015G012 (3.7/4.4) 295015G012        ..(KA's)
..(KA's)ANSWER: 066 (1 00)b.  
ANSWER       067  (1. 00) d.


, REACTOR OPERATOR Page 80
==REFERENCE:==
: 1. OPL171.074, Obj. 1 2~    K/A: 295003A204 (3 4/3 5)
                                ~
295003A204        ..(KA's)
ANSWER:      068  (1.00) b.


==REFERENCE:==
==REFERENCE:==
: 1.      OPL171.202, Obj. 8 2      K/A 295025A105 (3 7/3.7) 295025A105        ..(KA's)
ANSWER:      069  (1. 00)


e OPL171.205, Obj.7b K/A: 295015G012 (3.7/4.4)295015G012
dS.i
..(KA's)ANSWER 067 (1.00)d.
, REACTOR OPERATOR                      Page 81


==REFERENCE:==
==REFERENCE:==


1.OPL171.074, Obj.1 2~K/A: 295003A204 (3~4/3 5)295003A204
OPL171.~ 202, Ob) ~ 14 K/A: 295037G007 (3.~ 5/3.~ 7) 295037G007          .. (KA's)
..(KA's)ANSWER: 068 (1.00)b.
ANSWER:     070    (1 00) b.


==REFERENCE:==
==REFERENCE:==
: 1. AOI 47-2, page 3 2 ~  K/A: 295020G010 (3      '/3.5)
                          .. (KA's)
ANSWER:      071    (1. 00)
C>>


1.OPL171.202, Obj.8 2 K/A 295025A105 (3 7/3.7)295025A105
==REFERENCE:==
..(KA's)ANSWER: 069 (1.00)
, REACTOR OPERATOR dS.i Page 81


==REFERENCE:==
1 2~
OPL171.054, Obg.
K/A: 295019G011 3
(3 '/4 ')
295019G011        .. (KA's)
ANSWER:      072    (1. 00) b.


~~~~OPL171.202, Ob)14 K/A: 295037G007 (3.5/3.7)295037G007
,REA~OR OPERATOR Page 82
..(KA's)ANSWER: 070 (1 00)b.


==REFERENCE:==
==REFERENCE:==


1.AOI 47-2, page 3 2~K/A: 295020G010 (3'/3.5)..(KA's)ANSWER: 071 (1.00)C>>
EOI Appendix 3B K/A: 295037K213 (3   '/4 ')
C 295037K213          .. (KA's)
ANSWER:       073  (1. 00)


==REFERENCE:==
==REFERENCE:==
: 1.      EOI Appendices 1A, 1B, 1C,    1E 2      K/A: 295015K201 (3    '/3  9) 295015K201          .. (KA's)
R:    074  (1. 00)
REFERENCE
: 1.      Tech Spec 3.7.C 2      K/A: 295033K204 (3.9/4.2) 295033K204          .. (KA's)
ANSWER:      075  (1.00) d.


1 OPL171.054, Obg.3 2~K/A: 295019G011 (3'/4')295019G011
,REACTOR OPERATOR                                           Page 83
..(KA's)ANSWER: 072 (1.00)b.
,REA~OR OPERATOR Page 82


==REFERENCE:==
==REFERENCE:==


EOI Appendix 3B K/A: 295037K213 (3'/4')295037K213 C..(KA's)ANSWER: 073 (1.00)
EOI-2, Primary Containment Control bases, page 113 K/A: 295029K301 (3 5/3 9)~
295029K301        ..(KA's)
ANSWER:     076    (1 00)


==REFERENCE:==
==REFERENCE:==
: 1. AOI 70-1, Attachment 1
: 2. K/A: 295018K101 (3.5/3.6) 295018K101        ..(KA's)
ANSWER:      077  (F 00) a0 REFERENCE
: 1. AOI 32-2, page 13-17 2 ~  OPL171 ~ 054,  Obj. 5 3 ~  K/A: 295019K209 (3.3/3.3) 295019K209        ..(KA's)
ANSWER:      078  (1 00)


1.EOI Appendices 1A, 1B, 1C, 1E 2 K/A: 295015K201 (3'/3 9)295015K201
.REACTOR OPERATOR Page 84
..(KA's)R: 074 (1.00)REFERENCE 1.Tech Spec 3.7.C 2 K/A: 295033K204 (3.9/4.2)295033K204
..(KA's)ANSWER: 075 (1.00)d.
,REACTOR OPERATOR Page 83


==REFERENCE:==
==REFERENCE:==


EOI-2, Primary Containment Control bases, page 113 K/A: 295029K301 (3 5/3~9)295029K301
AOI 32-2, page 13-17 OPL171.054, Obj 5 K/A: 295019A202 (3.6/3.7)
..(KA's)ANSWER: 076 (1 00)
        '295019A202        .. (KA's)
ANSWER:       079  (1 00)


==REFERENCE:==
==REFERENCE:==
: 1.      OPL171.003, Obj.13, page 24 2  ~    K/A: 295009A201 (4 2/4 ~ 2)
                                ~
295009A201        .. (KA's)
ANSWER:        080  (1. 00) a~


1.AOI 70-1, Attachment 1 2.K/A: 295018K101 (3.5/3.6)295018K101
==REFERENCE:==
..(KA's)ANSWER: 077 (F 00)a 0 REFERENCE 1.AOI 32-2, page 13-17 2~OPL171~054, Obj.5 3~K/A: 295019K209 (3.3/3.3)295019K209
: 1.     AOI 74-1
..(KA's)ANSWER: 078 (1 00)  
: 2.       OPL171.046, Obj. 13
: 3.      K/A: 295021K102 (3.3/3     ')
295021K102        ..(KA's)
ANSWER:       081  (1.00)


.REACTOR OPERATOR Page 84
. REACTOR OPERATOR                                               Page 85


==REFERENCE:==
==REFERENCE:==


AOI 32-2, page 13-17 OPL171.054, Obj 5 K/A: 295019A202 (3.6/3.7)'295019A202
2-AOI-85-3 Rev 10, p 2 of        5 (immediate actions)
..(KA's)ANSWER: 079 (1 00)
K/A: 295022G010 (3.7/3.5)
                                ~    ~
295022G010        .. (KA's)
ANSWER:       082  (1. 00) d0


==REFERENCE:==
==REFERENCE:==
: 1. 2-AOI-100-2, Note, Rev 2 Page 14        of  55
: 2. OPL171-040 Objective 4 3 ~    K/A: 295016K303 (3    '/3      7) 295016K303        .. (KA's)
WER:    083  (1.00) a~
REFERENCE
: 1. OPL171.074  Objective    2
: 2. 2-AOI-66-2 Rev 8, 4.1 3      K/A: 295017GQ1Q (3.9/3.&)
295017G010        ..(KA's)
ANSWER:        084  (1.00) b.


1.OPL171.003, Obj.13, page 24 2~K/A: 295009A201 (4~2/4~2)295009A201
dS.
..(KA's)ANSWER: 080 (1.00)a~
, REA~OR OPERATOR                                            Page 86


==REFERENCE:==
==REFERENCE:==


1.AOI 74-1 2.OPL171.046, Obj.13 3.K/A: 295021K102 (3.3/3')295021K102
Facility Question Bank 411043 OPL171.007 Objective 12 K/A: 29500SK302 (3.4/3.5) 295005K302        ..(KA's)
..(KA's)ANSWER: 081 (1.00)  
ANSWER:     085  (1 00)
.REACTOR OPERATOR Page 85
  'a ~


==REFERENCE:==
==REFERENCE:==
: 1. OPL  171.036( Rev    2  p. 18 of 37, Objective 12 2  ~  K/A 295003A101      (3. 7/3 8) 295003A101        .. (KA's)
ANSWER:      086    ( 1. 00) b.
REFERENCE-
: 1. 2-AOX-47-3, Rev 6, caution, p.2 of      4 2  ~  K/A: 295002A105 (3.2/3.2) 295002A105        ..(KA's)
ANSWER:      087    (1.00)


~~2-AOI-85-3 Rev 10, p 2 of 5 (immediate actions)K/A: 295022G010 (3.7/3.5)295022G010
0, REACTOR OPERATOR                                      Page 87
..(KA's)ANSWER: 082 (1.00)d 0


==REFERENCE:==
==REFERENCE:==


1.2-AOI-100-2, Note, Rev 2 Page 14 of 55 2.OPL171-040 Objective 4 3~K/A: 295016K303 (3'/3 7)295016K303
OPL  171.005, Rev 4, p. 39~ of 58, Objective 6 K/A 295015K201 (3.8/3 ~ 9) 295015K201        .. (KA's)
..(KA's)WER: 083 (1.00)a~REFERENCE 1.OPL171.074 Objective 2 2.2-AOI-66-2 Rev 8, 4.1 3 K/A: 295017GQ1Q (3.9/3.&)295017G010
ANSWER     088    (1. 00) b.
..(KA's)ANSWER: 084 (1.00)b.  


, REA~OR OPERATOR dS.Page 86
==REFERENCE:==
: l. 1-AOI-57-5A, Rev 10, Cautions, p. 3 of 44
: 2. K/A: 295003G007 (3 2/3 6) 295003G007        ..(KA s)
ANSWER:    089  (1.00)
Ce REFERENCE
: l. EOI  flowcharts
: 2. K/A: 295034G011 (4 2/4 3) 295034G011        .. (KA's)
ANSWER:    090  (F 00)
 
REACTOR OPERATOR                             Page 88


==REFERENCE:==
==REFERENCE:==


Facility Question Bank 411043 OPL171.007 Objective 12 K/A: 29500SK302 (3.4/3.5)295005K302
2-AOX-70-1, Rev 12, p. 2 ~  of 6, 4.1
..(KA's)ANSWER: 085 (1 00)'a~
                                          ~
K/A: 295018G010 (3.4/3.3) ~
295018G010      .. (KA's)
ANSWER:     091  (1 OQ) b.


==REFERENCE:==
==REFERENCE:==


1.OPL 171.036(Rev 2 p.18 of 37, Objective 12 2~K/A 295003A101 (3.7/3 8)295003A101
2-AOI-78-1, Rev 7.
..(KA's)ANSWER: 086 (1.00)b.REFERENCE-1.2-AOX-47-3, Rev 6, caution, p.2 of 4 2~K/A: 295002A105 (3.2/3.2)295002A105
                            '/3 ')
..(KA's)ANSWER: 087 (1.00) 0, REACTOR OPERATOR Page 87
1.
: 2. K/A: 295023GOQ6 (3 295023G006      .. (KA's)
R:   092  (1. 00)
C>>


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.028, Rev 5, Table 2 ~  K/A: 295006K201 (4  '/4 ') 1 295006K201      .. (KA's)
ANSWER      093  (1. 00) b.


~~OPL 171.005, Rev 4, p.39 of 58, Objective 6 K/A 295015K201 (3.8/3 9)295015K201
dR.
..(KA's)ANSWER 088 (1.00)b.
, REA~OR OPERATOR                                                  Page 89


==REFERENCE:==
==REFERENCE:==
              ~ ~
OPL  171.028, Rev 5, p. 16
                  ~                ~  of 39 K/A: 295006A206 (3.5/3.8)  ~
295006A206          ..(KA's)
ANSWER:      094    (1 00)


l.1-AOI-57-5A, Rev 10, Cautions, p.3 of 44 2.K/A: 295003G007 (3 2/3 6)295003G007
==REFERENCE:==
..(KA s)ANSWER: 089 (1.00)Ce REFERENCE l.EOI flowcharts 2.K/A: 295034G011 (4 2/4 3)295034G011
: 1. 2-AOI-100-1, Rev 26, Attachment 5.
..(KA's)ANSWER: 090 (F 00)
: 2. EOI-2, Primary Containment Control, Rv 1, entry conditions 3 ~  K/A: 295028G010 (3    '/3 ')
REACTOR OPERATOR Page 88
                          .. (KA's)
ANSWER:       095  (F 00) a~


==REFERENCE:==
==REFERENCE:==
: l.        flowcharts: EOI-1, C-1, C-2, C-3.
2 EOI K/A: 295031A201 (4    '/4 ')
295031A201        .. (KA's)
ANSWER:      096  ( 1. 00)


~~~2-AOX-70-1, Rev 12, p.2 of 6, 4.1 K/A: 295018G010 (3.4/3.3)295018G010
REACTOR OPERATOR                            Page 90
..(KA's)ANSWER: 091 (1 OQ)b.


==REFERENCE:==
==REFERENCE:==


1.2-AOI-78-1, Rev 7.2.K/A: 295023GOQ6 (3'/3')295023G006
OPL171.074, Ohj. 5 OPL171.009, Obj. 3 K/A 295016A108 (4 ~ 0/4 0) 295016A108        .. (KA's)
..(KA's)C>>R: 092 (1.00)
ANSWER:    097  (1- 00) d REFERENCE-
: 1. OPL171.044, Obj. 19, pages 22, 24, 28 2 ~  K/A: 295021A207 (3.1/3.2)
                      .. (KA's)
ANSWER:     098  ( 1. 00)
C~


==REFERENCE:==
==REFERENCE:==
: 1. EOI, Appendix 18
: 2. OI 74, page 42
: 3. K/A: 295030G012    (3.7/4.4) 295030G012        .. (KA's)
ANSWER:    099  (1 00) d.


1.OPL171.028, Rev 5, Table 1 2~K/A: 295006K201 (4'/4')295006K201
B.
..(KA's)ANSWER 093 (1.00)b.
REA~OR OPERATOR Page 91
 
, REA~OR OPERATOR dR.Page 89


==REFERENCE:==
==REFERENCE:==


~~~~~OPL 171.028, Rev 5, p.16 of 39 K/A: 295006A206 (3.5/3.8)295006A206
Tech Spec 1.2.A
..(KA's)ANSWER: 094 (1 00)
                    ~
K/A: 295025G003      (3.5/4.3)
                              ~    ~
295025G003        .. (KA s)
ANSWER:     100  (1. 00) co REFERENCE
: 1. Facility question 2    K/A 294001A104 (3    '/3 ')
                      .. (KA's)
(**********    END OF EXAMINATION **********)


==REFERENCE:==
U. S. NUCLEAR REGULATORY COMMISSION SITE SPECIFIC EXAMINATION SENIOR OPERATOR LICENSE REGXON  2 CANDXDATEiS NAME.
FACILITY            Browns  Ferry 1, 2, & 3 REACTOR TYPE:
DATE ADMINISTERED    93/09/27 INSTRUCTIONS TO CANDIDATE:
Use  the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires a final grade of at least 804. Examination papers will be picked up four (4) hours after the e    'nation starts.
CANDIDATE~S TEST VALUE        SCORE 100.00                                      TOTALS FINAL GRADE All work  done on received aid.
this examination is  my own. I have  neither given nor Candidate's Signature


1.2-AOI-100-1, Rev 26, Attachment 5.2.EOI-2, Primary Containment Control, Rv 1, entry conditions 3~K/A: 295028G010 (3'/3')..(KA's)ANSWER: 095 (F 00)a~
0 C5.
SENATOR  REACTOR OPERATOR                                            Page 2 A N S W E R    SHEET r
Multiple Choice
          ~        ~
(Circle or X your choice)
If you  change  your answer, write your selection in the blank.
MULTIPLE CHOICE                          023  a    b    c d 001  : a    b    c    d                      024  a    b    c d 002    a    b    c    d                      025  a    b    c d 003    a    b    c    d                    026  a    b    c d 004    a    b    c    d                    027  a  b    c d 005    a    b    c    d                    028  a  b    c d 006    a    b    c    d                    029  a  b    c d 007    a    b    c    d                    030  a  b    c d 008    a    b    c    d                    031  a  b    c d 009    a    b    c    d                    032  a  b    c d a    b    c    d                    033  a  b    c d 011    a    b    c    d                    .034  a  b    c d 012    a    b    c    d                    035  a  b    c d 013    a    b    c    d                    036  a  b    c d 014    a    b    c    d                    037  a  b    c d 015    a    b    c    d                    038  a  b    c d 016    a    b    c    d                    039  a  b    c d 017    a    b    c    d                    040  a  b    c d 018    a    b    c    d                    041  a  b  ..-c d 019    a    b    c    d                    042  a  b    c d 020    a    b    c    d                    043  a  b    c d 021    a    b    c    d                    044  a  b    c d o      a    b    c    d                    045  a   b    c d


==REFERENCE:==
SENX'OR REACTOR OPERATOR                                            Page 3 A N S N E R    SHEET Choice  (Circle or X your choice)                          'ultiple If you  change your answer, write your selection in the blank.
046    a  b    c  d                    069    a  b  c  d 047 " a    b    c  d                    070  a    b  c  d 048    a  b    c  d                    071  a    b  c  d 049    a  b    c  d                    072  a    b  c  d 050    a  b    c  d                    073  a    b  c  d 051'      b    c  d                    074  a    b  c  d 052    a  b    c  d                    075  a    b  c  d 053    a  b    c  d                    076  a  b  c  d 054    a  b    c  d                    077  a  b  c  d oss 057 a
a b
b b
c c
c d
d d
078 079 080 a
a a
b b
b c
c c
d d
d 058    a  b    c  d                    081  a  b  c  d 059    a  b    c  d                    082  a  b  c  d 060    a  b    c  d                    083  a  b  c  d 061    a  b    c  d                    084  a  b  c  d 062    a  b    c  d                    085. a  b  c  d 063    a  b    c  d                    086  a  b  c  d 064    a  b    c  d                    087  a  b  c  d 065    a  b    c  d                    088  a  b  c  d O66    a  b    c  d                    089  a  b  c  d O67    a  b    c  d                    090  a  b  c  d a  b    c  d                    091  a  b  c  d


l.EOI flowcharts:
SENXOR REACTOR OPERATOR                                            Page 4 A N S M E R  S H E E  T 0
EOI-1, C-1, C-2, C-3.2 K/A: 295031A201 (4'/4')295031A201
Multiple Choice  (Circle or X your choice}
..(KA's)ANSWER: 096 (1.00)  
Xf you change your answer, write your selection in the blank.
092    a  b  c  d 093 "  a  b  c  d 094  a    b  c  d 095    a  b  c  d 096  a    b  c  d 097  a. b  c  d 098  a    b  c  d 099  a    b  c  d 100  a    b  c  d
(********** END OF EXAMXNATXON  **********)


REACTOR OPERATOR Page 90
Page 5 NRC RU ES AND GUID    IN S FOR LICENS  EXAMINAT ONS 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 penalties.
: 2. After the examination has been completed, you must sign the statement on the cover sheet indicating 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 exam-ination.
: 3. 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 cheating.
: 4. Use  black ink or dark pencil only to  facilitate legible repro-ducti ons.
: 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
: 6. Fill in the date  on  the cover sheet of the examination    (if necessary).
: 7. Print your name in the upper r.ight-hand corner of the    first page of each section of your answer sheets.
: 8. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
: 9. The  point value for  each question  is indicated in "parentheses after the question.
: 10. Partial credit will  NOT be  given.
ll. If the  intent of a  question is unclear, ask questions of the examiner only.
    '2.
When  you are done and have turned in your examination, leave the examination area as defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.


==REFERENCE:==
SENIOR REACTOR OPERATOR                                                        Page 7 STION: 001      (1. 00)
                      ~
reactor is being restarted near the end of core life following a one
                            'he
                ~      ~
day outage.      Reactor power is at 324. Control rods 34-23 and 58-23 have been isolated at position 00. When rod 42-43 is withdrawn, alarm 2-XA-55-5A-29, CRD ACCUM PRESS LOW LEVEL HIGH, actuates on panel 9-5.
WHICH ONE (1) of the following requirements is in effect under the current plant conditions?
: a. Exercise control rod 42-43 at least one notch at least once each day.
: b. Clear the accumulator trouble alarm on rod 42-43 prior to moving the next control rod.
: c. Control rod 42-43 must be fully inserted and electrically disarmed.
: d. Observe nuclear instrumentation        for response each time rod 42-43 is  movedo Control  Rod 38-23 has been        selected for  a single notch withdrawal from position  02  to position    04. The  following response from the CRD system was  observed:
Insert light illuminates and        goes out.
Withdrawal    light illuminates    and goes out.
Settle light illuminates and        goes out.
The  operator also observes and reports that the selected rod is now at position  06 and is continuing to drift out. A Rod Drift alarm is also present. WHICH ONE (1) of the following has caused the 'conditions?
: a. the automatic sequence timer has failed
: b. stuck open collet fingers
: c. excessive HCU cooling water pressure
: d. leaking scram inlet valve


OPL171.074, Ohj.5 OPL171.009, Obj.3 K/A 295016A108 (4~0/4 0)295016A108
SENIOR REACTOR OPERATOR                                                    Page 8 TION: 003    ( 1. 00)
..(KA's)ANSWER: 097 (1-00)d REFERENCE-1.OPL171.044, Obj.19, pages 22, 24, 28 2~K/A: 295021A207 (3.1/3.2)..(KA's)ANSWER: 098 (1.00)C~
When a    drywell-suppression chamber vacuum breaker valve is exercised through an opening-closing cycle, the position indicating lights in the control  room respond as    follows:
Initial                      Check  ON, Green  ON, Red - OFF Switch to    OPEN            Check  OFF, Green - OFF, Red  ON Switch to    CLOSE  (final)  Check - OFF, Green - ON, Red - OFF WHICH ONE    (1) of the following states the status of the tested valve'
: a. operable      for opening and considered fully closed
: b. operable for opening but considered nonfully closed
: c. inoperable for opening but considered fully closed
: d. inoperable for opening and considered nonfully closed TION: 004    (1. 00) ile a control rod is being inserted using the EMERGENCY IN control switch, rod motion stops. WHICH ONE (1) of the following could have terminated rod insertion?
: a. the automatic sequence timer deenergizes
: b. loss of power to the      Rod Position Information System
: c. a RWM  select block
: d. a  RWM  insert block


==REFERENCE:==
SEN1OR REACTOR OPERATOR                                                  Page 9 TION: 005      (1.00)
A Main Steam    Relief Valve (MSRV) lifts due to high reactor pressure.
of the following could cause a significant DECREASE in the WHICH ONE MSRV's  lift pressure if it subsequently lifts a (1) second time'?
: a. tailpipe    vacuum breaker failed CLOSED
: b. tailpipe    vacuum breaker failed OPEN
      'c. high drywell pressure d- high suppression pool    level QUESTION: 006      (1. 00)
Given the  following plant condition:
The  Unit 2 Division I ECCS ATU Inverter has    been declared inoperable.
      ~
H ONE  (1)  of the following actions is required?
: a. Declare RCIC inoperable.
: b. Declare HPCI inoperable.
: c. Declare Core Spray "2A"    pump inoperable.
: d. Declare Core Spray "28"      pump inoperable.


1.EOI, Appendix 18 2.OI 74, page 42 3.K/A: 295030G012 (3.7/4.4)295030G012
0 0
..(KA's)ANSWER: 099 (1 00)d.


REA~OR OPERATOR B.Page 91
l ~ W SENlOR REACTOR OPERATOR                                                     Page 10 r
TION: 007    (1.00)
During a    LOCA, the SRO  directs  you to initiate drywell sprays. The RHR SYS  I  CTMT VLV SELECT switch  is in SELECT and the 2/3 Core coverage keylock switch is in OVERRIDE. RHR SYS I DW SPRAY INBD VLV (2-FCV  61) cannot be opened.      WHICH ONE (1) of the following interlocks is preventing valve operation?
: a. RPV level less than -122 inches
: b. RPV level less than -183 inches c- LPCI initiation signal NOT present Drywell pressure less than 1.96 psig QUESTION: 008      (1.00)
An  earthquake has resulted in a complete loss of off-site power and LOCA on Unit 2.      Drywell pressure has increased to 5 psig on Unit 2.
rgency Diesel Generator "C" has failed to start. All other emergency t  equipment is functioning normally. WHICH ONE (1) of the following ntifies the Core Spray pumps that will respond to the automatic start signal?
: a. 2A, 2B
: b. 2A, 2B,    2D C. 2Ar 2C
: d. 2A, 2C,    2D


==REFERENCE:==
0 0


~~~Tech Spec 1.2.A K/A: 295025G003 (3.5/4.3)295025G003
SENIOR REACTOR OPERATOR                                                    Page 11 r
..(KA s)ANSWER: 100 (1.00)co REFERENCE 1.Facility question 2 K/A 294001A104 (3'/3')..(KA's)(**********
TION: 009      (1. 00)
END OF EXAMINATION
Conditions have been met to
**********)
      ~  ~
U.S.NUCLEAR REGULATORY COMMISSION SITE SPECIFIC EXAMINATION SENIOR OPERATOR LICENSE REGXON 2 CANDXDATEiS NAME.FACILITY Browns Ferry 1, 2,&3 REACTOR TYPE: DATE ADMINISTERED 93/09/27 INSTRUCTIONS TO CANDIDATE:
start the Automatic Depressurization System (ADS) 95 second      timers. WHICH ONE (1) of the following identifies the ADS clear?
Use the answer sheets provided to document your answers.Staple this cover sheet on top of the answer sheets.Points for each question are indicated in parentheses after the question.The passing grade requires a final grade of at least 804.Examination papers will be picked up four (4)hours after the e'nation starts.TEST VALUE CANDIDATE~S SCORE 100.00 TOTALS FINAL GRADE All work done on this examination is my own.I have neither given nor received aid.Candidate's Signature 0
initiation    signals that will NOT automatically reset if  conditions
SENATOR REACTOR OPERATOR C5.A N S W E R SHEET Page 2 r~~Multiple Choice (Circle or X your choice)If you change your answer, write your selection in the blank.017 018 a b a b c d c d 019 a b c d 020 a b c d 021 o a b c d a b c d MULTIPLE CHOICE 001: a b c d 002 a b c d 003 a b c d 004 a b c d 005 a b c d 006 a b c d 007 a b c d 008 a b c d 009 a b c d a b c d 011 a b c d 012 a b c d 013 a b c d 014 a b c d 015 a b c d 016 a b c d 023 a b 024 a b 025 a b c d c d c d 026 a b c d 027 a b c d 028 a b 029 a b 030 a b 031 a b c d c d c d c d 032 a b c d 033 a b.034 a b 035 a b 036 a b c d c d c d c d 037 a b c d 038 a b 039 a b 040 a b c d c d c d 041 a b..-c d 042 a b c d 043 a b c d 044 a b c d 045 a b c d SENX'OR REACTOR OPERATOR A N S N E R SHEET Page 3'ultiple Choice (Circle or X your choice)If you change your answer, write your selection in the blank.046 a b c 047" a b c 048 a b c 049 a b c 050 a b c d d d d d 051'052 a b c d b c d 053 a b c 054 a b c oss a.b c b c d d d d 057 a b c d 058 a b c d 069 a b c d 070 a b c d 071 a b c d 072 a b c d 073 a b c d 074 a b c d 075 a b c d 076 a b c d 077 a b c d 078 a b c d 079 a b c d 080 a b c d 081 a b c d 059 a b c 060 a b c 061 a b c d d d 082 a b 083 a b 084 a b c d c d c d 062 a b c d 085.a b c d O66 a O67 aa b c b c b c 063 a b c 064 a b c 065 a b c d d d d d d 086 a b 087 a b 088 a b c d c d c d 089 a b c d 090 a b c d 091 a b c d
: a. 95 second TIMER and Low Reactor Water Level TIMER
: b. 95 second TIMER and Low  Reactor Water Level signal
: c. High Drywell pressure signal and Low Reactor Water Level TIMER
: d. High Drywell pressure signal and Low Reactor Water Level signal QUESTION: 010      (1.00)
Reactor Recirculation pump "A" is operating at 1310 RPM and is providing 40,000 gpm flow. Reactor Recirculation pump "B" is operating at 1325 RPM. WHICH ONE (1) of the following states the LOWEST flow for Reactor irculation pump "B" that would indicate possible jet pump failure?
: a. 44,000  gpm
: b. 44,6QQ  gpm
: c. 46,000  gpm
: d. 46,600  gpm


SENXOR REACTOR OPERATOR A N S M E R S H E E T Page 4 0 Multiple Choice (Circle or X your choice}Xf you change your answer, write your selection in the blank.092 a b c d 093" a b c d 094 a b c d 095 a b c d 096 a b c d 097 a.b c d 098 a b c d 099 a b c d 100 a b c d (**********
SEN1OR REACTOR OPERATOR                                                   Page 12 TION: 011  (1.00)
END OF EXAMXNATXON
Reactor Recirculation pumps are not operated below 204 speed.      RiICH  ONE (1)  of the following states the basis for this limit?
**********)
: a. Ensures adequate Net Positive Suction Head.
b.'revents thermal stress in the vessel lower head region.
: c. Prevents unstable fluid coupler operation.
: d. Limits harmonic vibration of the get pumps.
QUESTION: Q12    (1.QQ) awhile Reactor  Recirculation pump "A" is operating at 80%, a failure in pump's  individual M/A station occurs and a signal is sent to the Bailey t
Positioner calling for a pump speed of zero. WHICH ONE (1) of the following states the expected response 'of the pump?
: a. Scoop tubes will lock and speed will remain at 80%.
: b. Speed decreases to 28%.
: c. Speed decreases to 204.
: d. Speed decreases to zero.


NRC RU ES AND GUID IN S FOR LICENS EXAMINAT ONS Page 5 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 penalties.
SENIOR REACTOR OPERATOR                                                            Page 13 STION: 013    (1.00)
2.3.4.5.After the examination has been completed, you must sign the statement on the cover sheet indicating 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 exam-ination.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 cheating.Use black ink or dark pencil only to facilitate legible repro-ducti ons.Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.6.7.8.9.10.ll.'2.Fill in the date on the cover sheet of the examination (if necessary).
During an accident on Unit 2, power
Print your name in the upper r.ight-hand corner of the first page of each section of your answer sheets.Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.The point value for each question is indicated in"parentheses after the question.Partial credit will NOT be given.If the intent of a question is unclear, ask questions of the examiner only.When you are done and have turned in your examination, leave the examination area as defined by the examiner.If you are found in this area while the examination is still in progress, your license may be denied or revoked.  
    ~          ~              ~
is lost
                                              ~
from the Division II ECCS inverter.
  ~
WHICH ONE    (1)  of the following HPCI system capabilities is lost?
: a. Flow control
: b. Automatic    initiation
: c. Automatic isolation
: d. Automatic    trip QUESTION: 014    (1.00)
HPCI is in standby    readiness.                 (1)  of the following states the if Torus level WHICH ONE t
HPCI pump suction    status                    is +5 inches and   the Condensate Storage Tank volume    is  9900 gallons."?
: a. Suction is from the CST but can be manually transferred              to the Torus without bypassing interlocks.
: b. Suction  is  from the   CST  and CANNOT  be  transferred to the Torus without bypassing interlocks.
: c. Suction is from the Torus but can          be manually    transferred to the CST without bypassing interlocks.
: d. Suction  is from the Torus and      CANNOT  be transferred to the   CST without bypassing interlocks.


SENIOR REACTOR OPERATOR Page 7~~~STION: 001 (1.00)'he reactor is being restarted near the end of core life following a one day outage.Reactor power is at 324.Control rods 34-23 and 58-23 have been isolated at position 00.When rod 42-43 is withdrawn, alarm 2-XA-55-5A-29, CRD ACCUM PRESS LOW LEVEL HIGH, actuates on panel 9-5.WHICH ONE (1)of the following requirements is in effect under the current plant conditions?
d5; SENIOR REACTOR OPERATOR                                                     Page 14 STION   015  (1 ~ 00)
a.Exercise control rod 42-43 at least one notch at least once each day.b.Clear the accumulator trouble alarm on rod 42-43 prior to moving the next control rod.c.Control rod 42-43 must be fully inserted and electrically disarmed.d.Observe nuclear instrumentation for response each time rod 42-43 is movedo Control Rod 38-23 has been selected for a single notch withdrawal from position 02 to position 04.The following response from the CRD system was observed: Insert light illuminates and goes out.Withdrawal light illuminates and goes out.Settle light illuminates and goes out.The operator also observes and reports that the selected rod is now at position 06 and is continuing to drift out.A Rod Drift alarm is also present.WHICH ONE (1)of the following has caused the'conditions?
Startup is in progress with reactor pover at 264. While withdraving
a.the automatic sequence timer has failed b.stuck open collet fingers c.excessive HCU cooling water pressure d.leaking scram inlet valve SENIOR REACTOR OPERATOR Page 8 TION: 003 (1.00)When a drywell-suppression chamber vacuum breaker valve is exercised through an opening-closing cycle, the position indicating lights in the control room respond as follows: Initial Check-ON, Green-ON, Red-OFF Switch to OPEN Check-OFF, Green-OFF, Red-ON Switch to CLOSE (final)Check-OFF, Green-ON, Red-OFF WHICH ONE (1)of the following states the status of the tested valve'a.operable for opening and considered fully closed b.operable for opening but considered nonfully closed c.inoperable for opening but considered fully closed d.inoperable for opening and considered nonfully closed TION: 004 (1.00)ile a control rod is being inserted using the EMERGENCY IN control switch, rod motion stops.WHICH ONE (1)of the following could have terminated rod insertion?
                                ~
a.the automatic sequence timer deenergizes b.loss of power to the Rod Position Information System c.a RWM select block d.a RWM insert block SEN1OR REACTOR OPERATOR Page 9 TION: 005 (1.00)A Main Steam Relief Valve (MSRV)lifts due to high reactor pressure.WHICH ONE (1)of the following could cause a significant DECREASE in the MSRV's lift pressure if it subsequently lifts a second time'?a.tailpipe vacuum breaker failed CLOSED b.tailpipe vacuum breaker failed OPEN'c.high drywell pressure d-high suppression pool level QUESTION: 006 (1.00)Given the following plant condition:
control rod 34-23 from notch 24 to notch 48, position indication is lost to all control rods. Upon observing the loss of indication, the operator terminates rod withdrawal and verifies reactor power is stable.
The Unit 2 Division I ECCS ATU Inverter has been declared inoperable.
WHICH ONE (1) of the following is the required action?
~~H ONE (1)of the following actions is required?a.Declare RCIC inoperable.
: a. Declare rod 34-23 inoperable.
b.Declare HPCI inoperable.
: b. Decrease power below, the RNM LPSP using Recirculation flov.
c.Declare Core Spray"2A" pump inoperable.
: c. Be in Cold Shutdown within 24 hours.
d.Declare Core Spray"28" pump inoperable.
: d. Immediately scram the reactor.
0 0 SENlOR REACTOR OPERATOR r l~W Page 10 TION: 007 (1.00)During a LOCA, the SRO directs you to initiate drywell sprays.The RHR SYS I CTMT VLV SELECT switch is in SELECT and the 2/3 Core coverage keylock switch is in OVERRIDE.RHR SYS I DW SPRAY INBD VLV (2-FCV 61)cannot be opened.WHICH ONE (1)of the following interlocks is preventing valve operation?
QUESTION: 016    (1.00)
a.RPV level less than-122 inches b.RPV level less than-183 inches c-LPCI initiation signal NOT present Drywell pressure less than 1.96 psig QUESTION: 008 (1.00)An earthquake has resulted in a complete loss of off-site power and LOCA on Unit 2.Drywell pressure has increased to 5 psig on Unit 2.rgency Diesel Generator"C" has failed to start.All other emergency t equipment is functioning normally.WHICH ONE (1)of the following ntifies the Core Spray pumps that will respond to the automatic start signal?a.2A, 2B b.2A, 2B, 2D C.2Ar 2C d.2A, 2C, 2D 00 SENIOR REACTOR OPERATOR Page 11 r~~TION: 009 (1.00)Conditions have been met to start the Automatic Depressurization System (ADS)95 second timers.WHICH ONE (1)of the following identifies the ADS initiation signals that will NOT automatically reset if conditions clear?a.95 second TIMER and Low Reactor Water Level TIMER b.95 second TIMER and Low Reactor Water Level signal c.High Drywell pressure signal and Low Reactor Water Level TIMER d.High Drywell pressure signal and Low Reactor Water Level signal QUESTION: 010 (1.00)Reactor Recirculation pump"A" is operating at 1310 RPM and is providing 40,000 gpm flow.Reactor Recirculation pump"B" is operating at 1325 RPM.WHICH ONE (1)of the following states the LOWEST flow for Reactor irculation pump"B" that would indicate possible jet pump failure?a.44,000 gpm b.44,6QQ gpm c.46,000 gpm d.46,600 gpm
With the plant operating at        100% pover, Alarm XA-S5-3F, window 31, CORE SPRAY SYS  II SPARGER entifies the core BREAK, actuates. WHICH ONE (1) of the following spray line break location required to actuate the rm7i
: a. inside of the reactor vessel shroud
: b. inside of the reactor vessel and outside of the shroud
: c. anywhere inside of the reactor vessel
: d. anywhere on the pressurized portion of the injection      line


SEN1OR REACTOR OPERATOR Page 12 TION: 011 (1.00)Reactor Recirculation pumps are not operated below 204 speed.RiICH ONE (1)of the following states the basis for this limit?a.Ensures adequate Net Positive Suction Head.b.'revents thermal stress in the vessel lower head region.c.Prevents unstable fluid coupler operation.
d.i SENIOR REACTOR OPERATOR                                               Page 15 STION: 017    (1. 00)
d.Limits harmonic vibration of the get pumps.QUESTION: Q12 (1.QQ)awhile Reactor Recirculation pump"A" is operating at 80%, a failure in pump's individual M/A station occurs and a signal is sent to the Bailey Positioner calling for a pump speed of zero.WHICH ONE (1)of the following states the expected response'of the pump?t a.Scoop tubes will lock and speed will remain at 80%.b.Speed decreases to 28%.c.Speed decreases to 204.d.Speed decreases to zero.  
During a LOCA, reactor water level is dropping at a rate of 20 inches per minute. RPV level is currently -132 inches. RPV pressure is 468 psig and Drywell pressure is 2.5 psig. HHICH ONE (1) of the following describes the expected status of the Unit 2 Core Spray system?
: a. Core Spray system has NOT initiated.
: b. Core Spray pumps have started, injection valve is CLOSED.
: c. Core Spray pumps have started, injection valve is OPEN, but pump flow is deadheaded against the closed check valve.
: d. Core Spray pumps have started and are injecting into the vessel.
QUESTION: 018    (1.00)
The PSC pumps  trip and cannot be restarted. %ICH ONE (1) of the following conditions is a possible reason for this occurrence?
: a. RPV level is -118 inches.
: b. RHR Room  temperature is 182 degrees F.
: c. 250V RMOV power is lost to Div I.
: d. Suppression pool level is -6.25 inches.


SENIOR REACTOR OPERATOR Page 13~~~~~~STION: 013 (1.00)During an accident on Unit 2, power is lost from the Division II ECCS inverter.WHICH ONE (1)of the following HPCI system capabilities is lost?a.Flow control b.Automatic initiation c.Automatic isolation d.Automatic trip QUESTION: 014 (1.00)HPCI is in standby readiness.
0 SENIOR REACTOR OPERATOR                                                       Page 16 STION: 019    (1 00)
WHICH ONE (1)of the following states the HPCI pump suction status if Torus level is+5 inches and the Condensate Storage Tank volume is 9900 gallons."?
During plant startup with reactor power on range 5 of the IRMs, an MSIV closure occurs. WHICH ONE (1) of the following conditions is a possible reason for this occurrence?
t a.Suction is from the CST but can be manually transferred to the Torus without bypassing interlocks.
: a. Reactor water level is -83 inches.
b.Suction is from the CST and CANNOT be transferred to the Torus without bypassing interlocks.
: b. MSL  tunnel temperature is 210 degrees F.
c.Suction is from the Torus but can be manually transferred to the CST without bypassing interlocks.
: c. Reactor pressure is 840 psig.
d.Suction is from the Torus and CANNOT be transferred to the CST without bypassing interlocks.
: d. Drywell pressure is 2.6 psig.
SENIOR REACTOR OPERATOR d5;Page 14~~STION 015 (1 00)Startup is in progress with reactor pover at 264.While withdraving control rod 34-23 from notch 24 to notch 48, position indication is lost to all control rods.Upon observing the loss of indication, the operator terminates rod withdrawal and verifies reactor power is stable.WHICH ONE (1)of the following is the required action?a.Declare rod 34-23 inoperable.
QUESTION    020  (1. 00)
b.Decrease power below, the RNM LPSP using Recirculation flov.c.Be in Cold Shutdown within 24 hours.d.Immediately scram the reactor.QUESTION: 016 (1.00)With the plant operating at 100%pover, Alarm XA-S5-3F, window 31, CORE SPRAY SYS II SPARGER BREAK, actuates.WHICH ONE (1)of the following entifies the core spray line break location required to actuate the rm7i a.inside of the reactor vessel shroud b.inside of the reactor vessel and outside of the shroud c.anywhere inside of the reactor vessel d.anywhere on the pressurized portion of the injection line
During a plant transient, the Main Steam      Isolation Valves isolated    on a valid  Group  I isolation actions signal. All control rods inserted and immediate operator             required by procedure have been taken. A decision has been made to unisolate MSL "D" (valves 1-51 and 1-52) to allow use of e main condenser.      Given the following plant conditions:
Reactor water level is -5 inches.
Reactor pressure is 700 psig.
Drywell pressure is 3.2 psig.
MSL Area temperature is 185 degrees F.
WHICH ONE   (1) of the following states actions required to reset the Group 1  isolation?
: a. The MSIV switches    for ONLY valves 1-51 and 1-52 must be placed in the   CLOSE position.
: b. A  jumper must be installed    AND the MSIV switches  for ONLY valves 1-51 and 1-52 must be placed    in the CLOSE position.
: c. The MSIV switches for ALL MSIVs must be      placed in the CLOSE position.
: d. A  jumper must be installed AND the MSIU switches      for ALL MSIVs must be placed in the CLOSE position.


SENIOR REACTOR OPERATOR d.i Page 15 STION: 017 (1.00)During a LOCA, reactor water level is dropping at a rate of 20 inches per minute.RPV level is currently-132 inches.RPV pressure is 468 psig and Drywell pressure is 2.5 psig.HHICH ONE (1)of the following describes the expected status of the Unit 2 Core Spray system?a.Core Spray system has NOT initiated.
li d.i SEN1OR REACTOR OPERATOR                                                     Page 17 y~
b.Core Spray pumps have started, injection valve is CLOSED.c.Core Spray pumps have started, injection valve is OPEN, but pump flow is deadheaded against the closed check valve.d.Core Spray pumps have started and are injecting into the vessel.QUESTION: 018 (1.00)The PSC pumps trip and cannot be restarted.
STION: 021     (F 00)
%ICH ONE (1)of the following conditions is a possible reason for this occurrence?
After a complete   functional test of the   SLC system the following data is reported:
a.RPV level is-118 inches.b.RHR Room temperature is 182 degrees F.c.250V RMOV power is lost to Div I.d.Suppression pool level is-6.25 inches.
Pump A   Flow Rate                 37 gpm Pump B   Flow Rate                 40 gpm Solution Concentration             9.14 Boron 10 Enrichment                 674 WHICH ONE   (1) of the following states the present status of the Standby Liquid Control System?
0 SENIOR REACTOR OPERATOR Page 16 STION: 019 (1 00)During plant startup with reactor power on range 5 of the IRMs, an MSIV closure occurs.WHICH ONE (1)of the following conditions is a possible reason for this occurrence?
: a. Both subsystems   are operable.
a.Reactor water level is-83 inches.b.MSL tunnel temperature is 210 degrees F.c.Reactor pressure is 840 psig.d.Drywell pressure is 2.6 psig.QUESTION 020 (1.00)During a plant transient, the Main Steam Isolation Valves isolated on a valid Group I isolation signal.All control rods inserted and immediate operator actions required by procedure have been taken.A decision has been made to unisolate MSL"D" (valves 1-51 and 1-52)to allow use of e main condenser.
: b. Only subsystem A   is inoperable.
Given the following plant conditions:
: c. Only subsystem B   is inoperable.
Reactor water level is-5 inches.Reactor pressure is 700 psig.Drywell pressure is 3.2 psig.MSL Area temperature is 185 degrees F.WHICH ONE (1)of the following states actions required to reset the Group 1 isolation?
: d. Both systems are inoperable.
a.The MSIV switches for ONLY valves 1-51 and 1-52 must be placed in the CLOSE position.b.A jumper must be installed AND the MSIV switches for ONLY valves 1-51 and 1-52 must be placed in the CLOSE position.c.The MSIV switches for ALL MSIVs must be placed in the CLOSE position.d.A jumper must be installed AND the MSIU switches for ALL MSIVs must be placed in the CLOSE position.
TION: 022   (1. 00)
li SEN1OR REACTOR OPERATOR d.i Page 17 y~STION: 021 (F 00)After a complete functional test of the SLC system the following data is reported: Pump A Flow Rate Pump B Flow Rate Solution Concentration Boron 10 Enrichment 37 gpm 40 gpm 9.14 674 WHICH ONE (1)of the following states the present status of the Standby Liquid Control System?a.Both subsystems are operable.b.Only subsystem A is inoperable.
Conditions exists on Unit     2 that require the initiation of Standby Liquid Control. WHICH ONE   (1) of the following contains two iridications that SLC is injecting?
c.Only subsystem B is inoperable.
: a. Explosive valve current flow       indicator reads 0 milliamps AND the blue SQUIB VALVE CONTINUITY     light is illuminated.
d.Both systems are inoperable.
: b. Explosive valve current flow indicator reads 4 milliamps       AND the blue SQUIB VALVE CONTINUITY light is illuminated.
TION: 022 (1.00)Conditions exists on Unit 2 that require the initiation of Standby Liquid Control.WHICH ONE (1)of the following contains two iridications that SLC is injecting?
: c. Explosive valve current flow indicator reads 0 milliamps       AND the blue SQUIB VALVE CONTINUITY light is extinguished.
a.Explosive valve current flow indicator reads 0 milliamps AND the blue SQUIB VALVE CONTINUITY light is illuminated.
: d. Explosive valve current flow       indicator reads 4 milliamps AND the blue SQUIB VALVE CONTINUITY     light is extinguished.
b.Explosive valve current flow indicator reads 4 milliamps AND the blue SQUIB VALVE CONTINUITY light is illuminated.
c.Explosive valve current flow indicator reads 0 milliamps AND the blue SQUIB VALVE CONTINUITY light is extinguished.
d.Explosive valve current flow indicator reads 4 milliamps AND the blue SQUIB VALVE CONTINUITY light is extinguished.
0 SENIOR REACTOR OPERATOR d.)Page 18 STION: 023 (1.00)Given that the following conditions exist during refueling on Unit 3: Bridge is directly over the core Main hoist is loaded to 550 lbs, in the full up position Aux hoist is loaded to 350 lbs, in the full up position Rod 03-17 is at position 02 Mode Switch is in STARTUP WHICH ONE (1)of the following responses would indicate normal interlock functioning on the refuel bridge?(FORWARD means away from the core, REVERSE means toward the core.)a.Bridge will move in the forward AND reverse directions.
b.Bridge will move in the forward direction BUT NOT reverse direction.
c.Bridge will move in the reverse direction BUT NOT forward direction.
d.Bridge will NOT move in either direction.
QUESTION: 024 (1.00)Refueling preparations are in progress with the reactor vessel head removed and a partial load of fuel in the vessel.WHICH ONE (1)of the following is a core alteration?
a.Withdrawal of Source Range Monitor b.Removal of an LPRM string c.Conduct of a TIP trace d.Removal of a jet pump nozzle SENIOR REACTOR OPERATOR d.)Page 19~~~~~~~STION: 025 (1.00)WHICH ONE (1)of the following describes the trip logic for the Reactor Building Ventilation Radiation Monitors (Reactor Zone Ventilation Radiation Monitors and Refuel Floor Radiation Monitors)a.Two Hi levels in 1 division OR one downscale in 2 divisions b.Two Hi levels in 1 division OR two downscales in 1 division c.One Hi level in 2 divisions OR one downscale in 2 divisions d.One Hi level in 2 divisions OR two downscales in 1 divisions QUESTION: 026 (F 00)Shutdown Bus 1 was initially being supplied by Unit Board 2B when Shutdown Board B bus transfer switch (43)transfers to MANUAL.WHICH ONE (1)of the following is a possible reason for this occurrence'?
Shutdown Board B Normal Feeder Breaker (1616)Emergency Control Power Transfer Switch has been placed in the Emergency position.The alternate power supply to Shutdown Bus 1 has sensed a high load differential condition across the 87Uxx breaker.c.A phase or ground overcurrent condition has been sensed by the NORMAL shutdown bus power supply.d.The residual voltage relay has shut in the close circuit of the alternate power supply to Shutdown Bus 1.
SENIOR REACTOR OPERATOR Page 20 1 STION 027 (1.00)A LOCA has occurred.Drywell pressure is 3 psig and no off-site power is available.
WHICH ONE (1)of the following is the only load allowed to be sequenced onto its associated shutdown board before forty (40)seconds have elapsed'a.RHRSW pumps b.A and D Control Air Compressors c.Drywell blowers d.RBCC&#xc3;pumps QUESTION: 028 (1.00)Normal and alternate supply breakers to unit boards 3A and 3B have tripped and the Unit 3 Shutdown Board 43 auto transfer switches have transferred to MANUAL.WHICH ONE (1)of the following describes what happened?a.An automatic shutdown bus transfer has taken place.b.The associated 4 kV shutdown board has failed to transfer to the alternate power supply.c.The associated backfeed switch has been placed in the BACKFEED position.d.A manual U3 Unit Board high-speed transfer to the alternate power supply failed.  


SENIOR REACTOR OPERATOR Page 21 STION: 029 (1.00)During full power operation on Unit 2, the mechanical spaces exhaust fan fails.WHICH ONE (1)of the following is a possible consequence of this failure7 a.Buildup of contaminants in the Radwaste building atmosphere.
0 d.)
b.Development of an explosive atmosphere in battery rooms c.Main steamline isolation d.Unreliable Emergency Range level indication QUESTION: 030 (1.00)An RSW pump has started to automatically increase level in the RSW storage tank when a fire pump receives an automatic start signal.WHICH ONE (1)of the following describes the response of the RSW storage tank isolation valves and the RSW pump'?I a.The RSW pump immediately trips.The isolation valves CLOSE but will AUTOMATICALLY reopen when the fire pump stops.b.The RSW pump immediately trips.The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire'pump stops.c.The RSW pump continues running in support of the fire pump.The isolation valves CLOSE but will AUTOMATICALLY reopen when the fire pump stops.d.The RSW pump continues running in support of the fire pump.The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire pump stops.
SENIOR REACTOR OPERATOR                                                   Page 18 STION: 023    (1.00)
SENIOR REACTOR OPERATOR d%.)Page 22 STION: 031 (1~00)The plant is being shutdown and reactor power is stable at 25%when annunciator"OFFGAS HOLDUP TEMPERATURE HIGH" actuates due to low flow through the SZAE condensers.
Given  that the following conditions exist during refueling on Unit 3:
WHICH ONE (1)of the following could have caused the event?a.In-leakage of noncondensible gases into the main condenser.
Bridge is directly over the core Main hoist is loaded to 550 lbs, in the full up position Aux hoist is loaded to 350 lbs, in the full up position Rod 03-17 is at position 02 Mode Switch is in STARTUP WHICH ONE (1) of the following responses would indicate normal interlock functioning on the refuel bridge? (FORWARD means away from the core, REVERSE means    toward the core.)
~b.SPE Heat Exchanger Balancing valve (FCV 2-190}-open.c.Condensate demineralizer bypass valve (FCV 2-130)open.d.Only two condensate pumps running.QUESTION: 032 (1.00)RHR loop 1 is in standby when electrical power is lost to 480 volt RMOV board 2D.WHICH ONE (1}of the following RHR flowpaths is NOT available?
: a. Bridge    will move in  the forward AND reverse directions.
a.torus cooling b.drywell spray c.LPCI injection d.pump minimum flow
: b. Bridge    will move in  the forward direction BUT NOT reverse direction.
: c. Bridge    will move in   the reverse direction  BUT NOT forward direction.
: d. Bridge    will NOT  move  in either direction.
QUESTION: 024    (1.00)
Refueling preparations are in progress with the reactor vessel head removed and a partial load of fuel in the vessel.
WHICH ONE (1) of the following is a core alteration?
: a. Withdrawal of Source Range Monitor
: b. Removal of an    LPRM  string
: c. Conduct of    a TIP  trace
: d. Removal of   a jet  pump   nozzle


SENIOR REACTOR OPERATOR d.i Page 23 r STION: 033 (1 00)WHICH ONE (1)of the following describes the conditions when RHR Unit cross-tie capability must be maintained?
d.)
a.Anytime there is irradiated fuel in the reactor.b.Only when the reactor is NOT in COLD Shutdown.c-Only when the reactor is NOT in HOT Shutdown.d.Only when reactor pressure is greater than 100 psig.QUESTION: 034 (1.00)Unit 2 has just experienced a closure of all MSIVs due to high MSL radiation with a failure of approximately half of the control rods to fully insert.All actions necessary to reduce reactor power were immediately taken.Emergency depressurization was performed and control rods were manually inserted.Reactor power is zero and RPV level is ing controlled at+30 inches.RHR Loop 1 was placed in Shutdown ling ten minutes ago.WHICH ONE (1)of the following can be used to tain a valid, representative sample to detect possible fuel cladding failure?a.RHR (Loop 1)Heat Exchanger"C" sample point b.Jet pump$1 instrument line c.Suppression Pool atmosphere sample line d.Drywell atmosphere sample line
SENIOR REACTOR OPERATOR                                                       Page 19 STION: 025      (1.00)
                      ~
WHICH ONE   (1) of the following describes the trip logic for the Reactor Building Ventilation Radiation Monitors (Reactor Zone Ventilation
    ~  ~        ~      ~      ~  ~
Radiation Monitors and Refuel Floor Radiation Monitors)
: a. Two Hi levels in 1 division OR one downscale in 2 divisions
: b. Two Hi levels in 1 division OR two downscales in 1 division
: c. One  Hi level in    2  divisions OR one downscale  in 2 divisions
: d. One  Hi level in    2  divisions OR two downscales  in 1 divisions QUESTION: 026      (F 00)
Shutdown Bus 1 was       initially  being supplied by Unit Board 2B when Shutdown Board B bus transfer switch (43) transfers to MANUAL. WHICH ONE (1) of the following is a possible reason for this occurrence'?
Shutdown Board B Normal Feeder Breaker (1616) Emergency Control Power Transfer Switch has been placed in the Emergency position.
The  alternate power supply to Shutdown Bus 1 has sensed a high load  differential condition across the 87Uxx breaker.
: c. A phase or ground overcurrent condition has been sensed by the NORMAL    shutdown bus power supply.
: d. The residual voltage relay has shut in the close        circuit of  the alternate power supply to Shutdown Bus 1.


SENIOR REACTOR OPERATOR d.)Page 24 STION: 035 (1.00)WHICH ONE (1)of the following describes the expected DIRECT response to one Main Steam Line radiation monitor reaching it's high trip setpoint'?
SENIOR REACTOR OPERATOR                                                     Page 20 1
a.Full scram and full Group 1 Isolation b.Full scram and half Group 1 Isolation c.Half scram and full Group 1 Isolation d.Half scram and half Group 1 Isolation QUESTION: 036 (1.00)The plant is heating up.Condenser vacuum is 10 inches Hg.RPV water level is being maintained by the Reactor Water Cleanup (RWCU)system.Reject is being directed to the condenser through the Reject to Condenser Valve.RPV level is rising due to the high heatup rate and low reject rate.WHICH ONE (1)of the following is the reason that the ject to Radwaste Valve must not be open at this time'?a.Radwaste system piping would overpressurize.
STION   027    (1. 00)
b.Excess flow would damage the RWCU filter demineralizers.
A LOCA has    occurred. Drywell pressure is 3 psig and no off-site power is available. WHICH ONE (1) of the following is the only load allowed to be sequenced onto its associated shutdown board before forty (40) seconds have elapsed'
\c.RWCU system would isolate on high flow.d.A loss of main condenser vacuum would occur.
: a. RHRSW  pumps
SENIOR REACTOR OPERATOR d%.Page 25 STION: 037 (1 00)Unit 2 is operating at 1004 power with FWLC in automatic three element control when the<<A<<steam flow transmitter fails downscale.
: b. A and D  Control Air Compressors
WHICH ONE (1)of the following describes the expected control room INDICATIONS after conditions stabilize?(Assume no operator action is taken)a.Feed Flow 1004, Steam Flow 754, Reactor Level 18 inches b.Feed Flow 75%, Steam Flow 75%, Reactor level 18 inches c.Feed Flow 1004, Steam Flow 754, Reactor Level 33 inches d.Feed Flow 754, Steam Flow 75%, Reactor Level 33 inches QUESTION: 038 (1.00)Unit 2 is operating at 1004 power with the master feedwater level controller is in 3 element when the FWLC system experiences a loss of one of the two feedwater flow inputs.WHICH ONE (1)of the following describes the expected plant response?(Assume no operator action is en)a.Reactor level will stabilize at normal with FWLC remaining in 3 element control.b.Reactor level will stabilize at normal with FWLC in single element.c.Reactor level will stabilize about 15 inches below normal with FWLC remaining in 3 element control.d.Reactor level will stabilize about 15 inches below normal with FWLC in single element.  
: c. Drywell blowers
: d. RBCC&#xc3; pumps QUESTION: 028    (1.00)
Normal and alternate supply breakers to unit boards 3A and 3B have tripped and the Unit 3 Shutdown Board 43 auto transfer switches have transferred to MANUAL. WHICH ONE (1) of the following describes what happened?
: a. An automatic shutdown bus transfer has taken place.
: b. The associated      4 kV shutdown board has failed to transfer to the alternate power supply.
: c. The associated backfeed switch has been placed in the      BACKFEED position.
: d. A manual U3      Unit Board high-speed transfer to the alternate power supply      failed.


SENIOR REACTOR OPERATOR Page 26 STION: 039 (1 00)WHICH ONE (1)of the following conditions will result in a RFPT trip?a.RFPT"B" suction pressure 95 psig for 25 seconds.b.Condenser low vacuum 10" Hg.c.RFP (pump)low oil pressure 6 psig.d.RPV level 52" for 10 seconds.QUESTION: 040 (1 00)Unit 2 has gust experienced a small LOCA and Drywell pressure has increased to 3 psig.Reactor pressure is 800 psig and steady.The increase in Drywell temperature causes reliability concerns for WHICH ONE (1)of the following level instruments?
SENIOR REACTOR OPERATOR                                                     Page 21 STION: 029    (1.00)
a.Emergency Range indicators b.Normal Range indicators c.Post Accident indicators d.Shutdown Floodup indicators QUESTION: 04 1 (1.00)WHICH ONE (1)of the following describes how an electrical drawing is verified as being the current revised copy?a.Refer to the Controlled Drawing Holders list of drawings that contains only the latest revised drawings.b.Refer to the Shift Operations Supervisor/Assistant Shift Operations Shift log book.c.Refer to the Lead Unit Operators log book.d.Refer to Document Control for assistance.  
During fails.
full power  operation on Unit 2, the mechanical spaces exhaust fan WHICH ONE   (1) of the following is a possible consequence of this failure7
: a. Buildup of contaminants      in the  Radwaste building atmosphere.
: b. Development of an explosive atmosphere in battery rooms
: c. Main steamline isolation
: d. Unreliable Emergency Range level indication QUESTION: 030    (1. 00)
An  RSW pump has started to automatically increase level in the RSW I
storage tank when a fire pump receives an automatic start signal. WHICH ONE (1) of the following describes the response of the RSW storage tank isolation valves and the RSW pump'?
: a. The  RSW  pump  immediately  trips. The isolation valves CLOSE but will AUTOMATICALLYreopen      when  the fire pump stops.
: b. The RSW pump immediately trips. The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire 'pump stops.
: c. The RSW pump continues running in support of the fire pump. The isolation valves CLOSE but will AUTOMATICALLYreopen when the fire pump stops.
: d. The RSW pump continues running in support of the fire pump. The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire pump stops.


SENIOR REACTOR OPERATOR Page 27~~STION 042 (1.00}Given an individual with the following exposure history: (NRC Form 4 is on file)Sex: Age: Lifetime exposure: Current qtr.exp.Male 23 24.80 Rem (Does not include current quarter)250 Mrem WHICH ONE (1)of the following states the individual's current remaining FEDERAL whole body exposure?a.0 Mrem b.750 Mrem c.1000 Mrem QUESTION: 043 (1.00)WHICH ONE (1}of the following situations meets the requirements for operations outside Browns Ferry Technical Specifications?
d%.)
a.The action is necessary to prevent injury to a BROWNS FERRY employee, permission has been obtained from the Plant Manager.b.The action is necessary to prevent injury to a BROWNS FERRY employee, permission has been obtained from the ASOS., c.The action is necessary to prevent damage to the Main Turbine, permission has been obtained from the Shift, SOS.d.The action is necessary to prevent damage to the Main Turbine, permission has been obtained from the Plant Manager.
SENIOR REACTOR OPERATOR                                                     Page 22 STION: 031    (1 ~ 00)
The  plant is being shutdown and reactor power is stable at 25% when annunciator "OFFGAS HOLDUP TEMPERATURE HIGH" actuates due to low flow through the SZAE condensers.         WHICH ONE (1) of the following could have caused the event?
: a. In-leakage of noncondensible gases into the main condenser.        ~
: b. SPE Heat Exchanger Balancing valve (FCV 2-190} -open.
: c. Condensate demineralizer bypass valve        (FCV 2-130) open.
: d. Only two condensate pumps running.
QUESTION: 032    (1. 00)
RHR  loop 1  is in standby when      electrical power is lost to 480 volt RMOV board 2D. WHICH ONE     (1} of the following RHR flowpaths is NOT available?
: a. torus cooling
: b. drywell spray
: c. LPCI injection
: d. pump minimum flow


SENIOR REACTOR OPERATOR Page 28 STION: 044 (1.00)An operator returns from two (2)days off, and works the following shift hours as a control room operator during an outage.Saturday-6 am to 2 pm Sunday-6 am to 2 pm Monday-6 am to 6 pm Tuesday-6 am to 6 pm I'HICH ONE (1)of the following states the maximum number of additional hours the operator can work before 6 pm on Wednesday?
d.i SENIOR REACTOR OPERATOR                                                 Page 23 r
a.4 hours b.8 hours c.12 hours d.16 hours TION: 045 (1.00)During a Site Area Emergency, the Site Emergency Director is informed that the UO on building rounds did not report to the Control Room and does not respond to the plant paging system.WHICH ONE (1)of the following is the maximum exposure allowed to an individual in order to search for the unaccounted for operator?a.BFNP administrative limits b.10CFR20 non-emergency limits c.25 REM d.75 REM
STION: 033    (1 00)
WHICH ONE   (1) of the following describes the conditions when RHR Unit cross-tie capability must be maintained?
: a. Anytime there is irradiated fuel in the reactor.
: b. Only when the reactor is NOT in COLD Shutdown.
c- Only when the reactor is NOT in HOT Shutdown.
: d. Only when reactor pressure is greater than 100 psig.
QUESTION: 034    (1.00)
Unit 2 has just experienced a closure of all MSIVs due to high MSL radiation with a failure of approximately half of the control rods to fully insert. All actions necessary to reduce reactor power were immediately taken. Emergency depressurization was performed and control rods were manually inserted. Reactor power is zero and RPV level is ing controlled at +30 inches. RHR Loop 1 was placed in Shutdown ling ten minutes ago. WHICH ONE (1) of the following can be used to tain a valid, representative sample to detect possible fuel cladding failure?
: a. RHR  (Loop 1) Heat Exchanger "C" sample point
: b. Jet pump    $1  instrument line
: c. Suppression Pool atmosphere sample line
: d. Drywell atmosphere sample line


SENIOR REACTOR OPERATOR Page 29 STION: 046 (1.00)WHICH ONE (1)of the following is the maximum length of time a confined space entry permit is valid without an extension?
d.)
a.4 hours b.12 hours c.24 hours d.72 hours QUESTION: 047 (1.00)WHICH ONE (1)of the following is an acceptable way to perform position verification on a throttled valve?(assume that the valve is installed in a system with a local flow indication controlled by the valve, and the valve has a rising stem)a.observe the initial valve operator's action in positioning the throttled valve b.perform an independent visual check of the valve position by observing the valve stem c.independently verify the valve position by a second valve operation d.by observing flow indication through the throttled valve's system
SENIOR REACTOR OPERATOR                                                   Page 24 STION: 035    (1.00)
WHICH ONE   (1) of the following describes the expected DIRECT response to one Main Steam    Line radiation monitor reaching it's high trip setpoint'?
: a. Full  scram and full Group 1 Isolation
: b. Full  scram and half Group 1 Isolation
: c. Half  scram and full Group 1 Isolation
: d. Half  scram and half Group 1 Isolation QUESTION: 036      (1.00)
The  plant is heating up. Condenser vacuum is 10 inches Hg. RPV water level is being maintained by the Reactor Water Cleanup (RWCU) system.
Reject is being directed to the condenser through the Reject to Condenser Valve. RPV level is rising due to the high heatup rate and low reject rate. WHICH ONE (1) of the following is the reason that the ject to Radwaste Valve must not be open at this time'?
: a. Radwaste system piping would overpressurize.
: b. Excess flow would damage the RWCU filter demineralizers.
                                                              \
: c. RWCU system would isolate on high flow.
: d. A loss of main condenser vacuum would occur.


SENIOR REACTOR OPERATOR Page 30~~~STION: 048 (1.00)A valve will be manipulated at rated power that may influence RPV level.WHICH ONE (1)of the following forms of verification would ensure the correct valve is manipulated?
d%.
a.Supervisor Verification b.Second Party Verification c.Independent Verification d.Responsible Manager Verification QUESTION: 049 (1.00)The UO is required to enter a closed cooling water valve pit (Category I confined space)to perform a valve lineup.WHICH ONE (1)of the following states the requirements for atmospheric monitoring in the area?a.Required at all times.b.Required only if the plant is operating.
SENIOR REACTOR OPERATOR                                                 Page 25 STION: 037    (1 00)
c.Required only if this is the initial entry after shutdown.d.Required only if welding, burning or painting is in progress.
Unit 2 is operating at 1004 power with FWLC in automatic three element control when the <<A<< steam flow transmitter fails downscale. WHICH ONE (1) of the following describes the expected control room INDICATIONS after conditions stabilize? (Assume no operator action is taken)
8 SENIOR REACTOR OPERATOR Page 31 TION: 050 (1.00)An above ground oil storage tank has been discovered leaking.Approximately 25 gallons have been leaked onto the ground surrounding the tank.WHICH set of actions listed below are in the correct order of response?a.Isolate the source of the leak, determine nature and source of spill, coordinate cleanup.b.ce Make the necessary notifications, Isolate the source of the leak, coordinate cleanup.Find the source of the leakage, determine its flowpath, confine the spillage.d.Evacuate the vicinity, determine the nature and source, confine the material.QUESTION: 051 (1 00)plant is operating at 804 power with three (3)hours remaining on a hour LCO.The Wilson Load Dispatcher requests the base load to be increased 25 MWE for the remainder of the operating run.WHICH ONE (1)of the following actions should be taken?a.Before increasing the electrical load, the request must be approved by EITHER the SOS or the ASOS.b.Before increasing the electrical load, the request must be approved by BOTH the SOS and the ASOS.c.Before increasing the electrical load, the request must be approved by any licensed individual.
: a. Feed Flow 1004, Steam Flow 754, Reactor Level 18 inches
d.The request for a load increase cannot be approved at this time.  
: b. Feed Flow 75%, Steam Flow 75%, Reactor level 18 inches
: c. Feed Flow 1004, Steam Flow 754, Reactor Level 33 inches
: d. Feed Flow 754, Steam Flow 75%, Reactor Level 33 inches QUESTION: 038    (1.00)
Unit 2 is operating at 1004 power with the master feedwater level controller is in 3 element when the FWLC system experiences a loss of one of the two feedwater flow inputs. WHICH ONE (1) of the following describes the expected plant response?   (Assume no operator action is en)
: a. Reactor level will stabilize  at normal with FWLC remaining in  3 element control.
: b. Reactor level  will stabilize at normal with FWLC in single element.
: c. Reactor level will stabilize about 15 inches below normal with FWLC remaining in 3 element control.
: d. Reactor level  will stabilize about 15 inches below normal with FWLC in single element.


SENIOR REACTOR OPERATOR d.i Page 32 STION: 052 (1.00)An Alert is declared at the plant.All of the emergency support facilities have been activated and all notifications have been made.The Alert condition no longer exists and you wish to announce that the event is terminated.
SENIOR REACTOR OPERATOR                                                           Page 26 STION: 039        (1 00)
WHICH ONE (1)of the following individuals must approve this?a.Site Emergency Director b.TSC Superintendent c.Site Emergency Preparedness Manager d.NRC Senior Resident, Inspector QUESTION: 053 (1 00)Four licensed UOs attended a fellow employee's birthday party the last night of their vacation and alcohol was served to all.Below shows when h UO stopped drinking alcoholic beverages.
WHICH ONE     (1)   of the following conditions    will result in  a RFPT  trip?
UO'A':05 am UO'B':05 am UO'C':05 am UO'D':05 am From the four, UOs listed above, WHICH ONE (1)of the following states the'number available for NRC licensed work the same morning at 7:00 am?(Assume that all the UOs have blood alcohol levels within SSP 1.6 guidelines)
: a. RFPT    "B" suction pressure 95 psig      for 25 seconds.
.a.ONE b.TWO c.THREE d.FOUR SENIOR REACTOR OPERATOR Page 33 STION: 054 (1.00)WHICH ONE (1)of the following makes this next sentence correct?Fluid or gas systems that operate with temperatures greater than degrees F or pressure greater than psig should be isolated from the work areas by two closed valves in series.a 50/200 100/300 c.150/400 d 200/500 QUESTION: 055 (1.00)WHICH ONE (1)of the following is the Technical Specification Basis for the equilibrium coolant iodine activity limit?l a.To protect plant personnel from increased exposure in the plant during high power operation.
: b. Condenser low vacuum 10" Hg.
b.To reduce exposure to plant personnel during refueling operations.
: c. RFP (pump)       low oil pressure   6 psig.
c.To limit thyroid dose at the exclusion distance following a steam line break.d.To assure the stack gas emissions remain within the Technical Specification limit as calculated on an annual basis.
: d. RPV  level 52" for     10 seconds.
0 4 SENIOR REACTOR OPERATOR d.)Page 34 TION: 056 (1 00)As SOS, you have just declared an ALERT due to weather conditions.
QUESTION: 040        (1 00)
The Emergency Centers are NOT staffed.WHICH ONE of the following should be notified within 5 minutes after the ALERT has been declared?a.Shift Fire Captain b.Operations Duty Specialist c.NRC via Emergency Notification System d.Site Emergency Director{}UESTION:
Unit  2 has gust experienced a small LOCA and Drywell increased to 3 psig. Reactor pressure is 800 psig andpressure      steady.
057 (1.00)Given the following plant conditions:
has The increase in Drywell temperature causes reliability concerns for WHICH ONE (1) of the following level instruments?
A failure to scram has occurred.Reactor power is 24.~~~~~~~~~~A high temperature exists in Secondary Containment due to fire.MSIVs are closed.RCIC is maintaining RPV level.HPCI is inoperable.
: a. Emergency Range indicators
Control rods are being inserted using CRD.WHICH ONE (1)of the following systems should be isolated if discharging into the Secondary?
: b. Normal Range indicators
a.Control Rod Drive b.Reactor Water Cleanup c.Reactor Core Isolation Cooling d.Fire Suppression 0
: c. Post Accident indicators
SENIOR REACTOR OPERATOR d.>Page 35 I TION: 058 (1.00)During an ATWS with the reactor at high power, EOI-1, step RC/Q-l directs that recirculation be run back to minimum prior to tripping the Reactor recirculation pumps.WHICH ONE (1)of the following is the basis for this action?a.Prevent MSIV closure on high flow.b.Promote boron mixing.c.Prevent Main Generator reverse power trip.d.Prevent Main Turbine high RPV water level trip.QUESTION: 059 (1.00)Given the following plant conditions:
: d. Shutdown Floodup indicators QUESTION: 04 1      (1. 00)
Reactor pressure is 930 psig RPU level is+28 inches RCIC is injecting Twenty control rods are at position 48 Reactor power is 9000 cps on the SRMs and decreasing A 90 degree F/hr cooldown is in progress\WHICH ONE (1)of the following would require termination of cooldown?a.RPV level lowers to+15 inches.b.SRM count rate increases to 10000 cps.c.Main turbine bypass valves fail closed.II d.Drywell pressure begins to increase.  
WHICH ONE     (1) of the following describes how an        electrical drawing is verified    as being the current revised copy?
: a. Refer      to the Controlled Drawing Holders list of drawings that contains only the latest revised drawings.
: b. Refer to the Shift Operations Supervisor/Assistant Shift Operations Shift log book.
: c. Refer to the Lead Unit Operators log book.
: d. Refer to Document Control for assistance.


SENIOR REACTOR OPERATOR Page 36 STION: 060 (1.00)WHICH ONE (1)of the following responses.
SENIOR REACTOR OPERATOR                                                         Page 27 STION     042    (1. 00}
will be noted on Unit 2 during a complete loss of Unit 2 ISC Bus during reactor operation?
Given an
a.Unit 2 reactor water level increase b.Unit 1 Loop A recirculation pump speed increase c.Unit 3 SJAE flow to offgas system increase d.Unit 2 main steam tunnel temperature increase QUESTION: 061 (1.00)During a plant transient on Unit 2, a Group I isolation is caused by high radiation.
  ~
Five control rods fail to insert.Suppression pool level is 12 feet and pool temperature is 94 degrees F.WHICH ONE (1)of the following identifies the systems available to help~~'ntain pressure below 1040 psig?a.HPCI, RCIC b.RCIC, RWCU c.RWCU, MSL drains d.MSL drains, HPCI SENIOR REACTOR OPERATOR d.,i Page 37 STION-062 (1.00)The Control Room was evacuated due to a fire 5 minutes ago.All the immediate actions for'~Control Room Abandonment" were performed.
individual with the following exposure history:     (NRC Form 4  is on  file)
Current plant conditions are: The reactor has been verified to be shutdown.RPV level is>+60 inches.RPV pressure is 700 psig and decreasing slowly.The MSIVs are open and cannot be closed.The turbine bypass valves appear to be functioning normally.An operator is stationed to control RPV level and pressure with HPCI as necessary.
        ~
WHICH ONE (1)of the following is the appropriate emergency action level for this situation'?
Sex:                          Male Age:                          23 Lifetime exposure:            24.80 Rem (Does not include current quarter)
a.Unusual Event b.Alert c.Site Area Emergency QUESTION: 063 (1.00)During an ATWS, EOIs direct the operator to inhibit ADS automatic blowdown when Standby Liquid Control is injected.WHICH ONE (1)of the following states the basis for this requirement?
Current qtr. exp.             250 Mrem WHICH ONE (1)       of the following states the individual's current remaining FEDERAL whole      body exposure?
a.ADS actuation would impose a severe pressure and temperature transient on the vessel.b.ADS would result in the removal of boron after it has been injected.c.Core damage could result from a large power.excursion if low pressure ECCS systems were to inject.e d.ADS/MSRV system flow rate is incapable of assuring fuel cooling through steaming above 5%reactor power.  
: a. 0 Mrem
: b. 750  Mrem
: c. 1000  Mrem QUESTION: 043        (1.00)
WHICH ONE     (1} of the following situations meets the requirements for operations outside Browns Ferry Technical Specifications?
: a. The action is necessary to prevent injury to a BROWNS FERRY employee, permission has been obtained from the Plant Manager.
: b. The action    is necessary to prevent injury to a BROWNS  FERRY employee, permission has been obtained from the ASOS.
      ,  c. The action is necessary to prevent damage to the Main Turbine, permission has been obtained from the Shift, SOS.
: d. The action is necessary to prevent damage to the Main Turbine, permission has been obtained from the Plant Manager.


SENIOR REACTOR OPERATOR 8.)Page 38 STION: 064 (1.00)While the reactor is operating at 904 power, reactor pressure is observed decreasing at an approximate rate of 200 psig per minute.WHICH ONE (1)of the following is the expected immediate operator action?a.Scram the reactor and place the pressure control unit in manual.b.Scram the reactor and close the MSIVs.c.Take manual control of the reactor pressure control unit.d.Manually transfer to the backup pressure control unit.QUESTION: 065 (1.00)A failure of Drywell Control Air has resulted in Drywell control air being supplied by the Plant Control Air header.WHICH ONE (1)of the following is a concern during the malfunction?
SENIOR REACTOR OPERATOR                                                         Page 28 STION: 044    (1.00)
a.Moisture in the air may cause critical valves to fail.b.Torus temperature may increase.c.Drywell oxygen level may increase.d.Breathing air is unavailable.
An  operator returns from two (2) days off, and works the following           shift hours as a control room operator during an outage.
0 SENIOR REACTOR OPERATOR d.i Page 39 STION: 066 (1.00)WHICH ONE (1)of the following systems is used to inject Alternate Standby Liquid Control (SLC)boron into the reactor?a.Suppression Chamber Head Tank system b.Control Rod Drive system c.RHR Standby Coolant system d.Condensate
Saturday    - 6 am  to 2 pm Sunday      6 am  to 2 pm Monday      6 am  to 6 pm Tuesday    - 6 am  to 6 pm ONE (1) of the following states the  maximum number of additional I'HICH hours the operator can work before      6 pm on Wednesday?
'and Feedwater system QUESTION: 067 (1.00)The reactor has experienced an incomplete scram.WHICH ONE (1)of the following methods of rod insertion requires first resetting the SCRAM?a.De-energization of scram solenoids b.Venting of the scram air header c.Scraming individual control rods using test switches d.Venting the Control Rod Drive over piston volume QUESTION: 068 (1.00)WHICH ONE (1)of the following constitutes a loss of Secondary Containment?
: a. 4  hours
a.The Reactor Building normal HVAC is inoperable and isolated.b.Both Reactor Building ventilation radiation.
: b. 8  hours
monitors are INOP.c.The Reactor Building/Suppression Chamber vacuum breaker is open.d.The Standby Gas Treatment system is inoperable.
: c. 12  hours
0 SENIOR REACTOR OPERATOR a Page 40~~~STION: 069 (1 00)WHICH ONE (1)of the following describes the basis Xor the Drywell Spray Initiation Limit Curve'I a.To prevent unstable steam condensation in the NSRV tailpipes from exerting excessive cyclic hydraulic loads on the suppression pool structure, b.To ensure that the rate at which the primary containment is depressurized is within the capacity of the reactor building to suppression pool vacuum breakers.c.To prevent chugging in the drywell to suppression pool'owncomers from exerting excessive cyclic hydraulic loads on the suppression pool structure.
: d. 16 hours TION: 045    (1. 00)
d.To ensure adequate noncondensibles remain in the drywell to'revent the suppression pool to drywell vacuum breakers from opening during drywell steam condensation.
During a Site Area Emergency, the Site Emergency Director is informed that the UO on building rounds did not report to the Control Room and does not respond to the plant paging system.       WHICH ONE (1) of the following is the maximum exposure allowed to an individual in order to search  for the   unaccounted  for operator?
TION: 070 (1 00)Drywell pressure has exceeded 30 psig and the Suppression Chamber vent path is unavailable.
: a. BFNP administrative limits
The EOIs direct termination of CAD system use and initiation of venting from the Drywell.WHICH ONE (1)of the following states the basis for'hifting vent paths under these conditions' a.Use of the Containment Air Dilution system at this pressure could cause loss of Containment.
: b. 10CFR20 non-emergency limits
b.The Drywell vent path is designed to withstand greater temperatures and pressures.
: c. 25 REM
c.The Drywell vent path is sized to limit effluent flow rate to ensure releases are within the design basis.d.The Drywell vent path contains supplementary sample lines routed to the Post Accident Sampling system (PASS).
: d. 75  REM


SENIOR REACTOR OPERATOR d.i Page 41~~STION: 071 (1.00)Within two minutes after a loss of Reactor Building Closed Cooling Water, AOI 70-1~"Loss of RBCCW", directs that, the reactor be scrammed and both recirculation pumps be tripped.WHICH ONE (1)of the following is the basis for this action'?a.Loss of cooling will lead to filter demin inlet temperature increase and auto isolation of RWCU.b.Loss of flow to RHR pump coolers will prevent the RHR system from meeting design criteria.c.Loss of cooling to the Recirculation pump seals will lead to a primary coolant leak.d.Loss of Drywell cooling will lead to an increase in Drywell pressure, actuating safety related equipment.
SENIOR REACTOR OPERATOR                                                     Page 29 STION: 046      (1. 00)
{}UESTION:
WHICH ONE   (1) of the following is the maximum length of time    a  confined space  entry permit is valid without an extension?
072 (1 00)reactor has scrammed from 1004 power due to closure of the MSIVs.ening of MSRVs has increased torus temperature to 125 degrees F.Current plant conditions are as follows: All rods in Mode switch in Shutdown Reactor level is+45 inches Reactor pressure is 950 psig Drywell pressure is 1.2 psig WHICH ONE (1)of the following is the required operator action?a.Power operation shall not be resumed until the pool temperature is reduced below 90 degrees F.b.Reactor vessel shall be depressurized to less than 200 psig at normal cooldown rates.c.The reactor shall be in a cold shutdown condition within 24 hours.d.Maintain Primary Containment integrity until pool temperature is reduced below 100 degrees F.
: a. 4  hours
: b. 12  hours
: c. 24  hours
: d. 72 hours QUESTION: 047      ( 1. 00)
WHICH ONE   (1) of the following is an acceptable way to perform position verification    on a  throttled valve? (assume that the valve is installed in  a system with a local flow indication controlled by the valve, and the valve has a rising stem)
: a. observe the initial valve operator's action in positioning the throttled valve
: b. perform an independent visual check of the valve position by observing the valve stem
: c. independently      verify the valve position by a second valve operation
: d. by observing flow indication through the throttled valve's system


SENIOR REACTOR OPERATOR d%.Page 42~~STION: 073 (1.00)EOI-2,"Primary Containment Control," step PC/H-8 requires that Suppression Pool level be verified below 26 feet prior to initiating Suppression Chamber sprays for hydrogen control.WHICH ONE (1)of the following is the basis for this limitV'.Ensure the torus to drywell vacuum breakers are not submerged.
SENIOR REACTOR OPERATOR                                                       Page 30 STION: 048  (1.00)
b.Ensure the torus vent header is not submerged.
                    ~
c.Ensure the torus spray nozzles are not submerged.
A  valve will be manipulated at rated power that may influence RPV level.
d.Ensure the torus downcomer header is not submerged.
            ~            ~
QUESTION: 074 (1.00)While the plant is operating at full power, a complete loss of Control Air is experienced.
WHICH ONE (1) of the following forms of verification would ensure the correct valve is manipulated?
WHICH ONE (1)of the following containment t isolation valves is designed to fail open under these circumstances?
: a. Supervisor Verification
a.Suppression Chamber vacuum relief valves b.Main Steam Isolation Valve c.Refuel zone ventilation dampers d.RHR process water sampling valve SENIOR REACTOR OPERATOR d,i Page 43 STION: 075 (1.00)A pipe shear has resulted in Control Air pressure immediately decreasing to 0 psig.WHICH ONE (1)of the following will remain available' a.Off Gas b'.Stator Cooling Water c.Reactor Water Cleanup d.Raw Service Water supply to fire systems QUESTION: 076 (1.00)The main turbine control valves have failed closed and reactor pressure has increased to the scram setpoint.Approximately one third of the control rods have failed to fully insert, MSIVs remain open and several SRVs are cycling.EOI-1, RPV Control Procedure, step RC/P-6, directs the crew to manually open any cycling SRV until RPV pressure drops to 0 psig.WHICH ONE (1)of the following is the basis for this lower it'?a.Maintain reactor pressure high enough to scram control rods should CRD pumps become unavailable.
: b. Second Party Verification
b.Prevent initiation of a low reactor pressure scram signal while attempting to drive rods.c.Limit the amount of energy sent to the suppression pool through the MSRVs.d.Preclude the possibility of a Group 1 isolation on low Main Steam Line pressure.  
: c. Independent Verification
: d. Responsible Manager      Verification QUESTION: 049    (1. 00)
The UO  is required to enter a closed cooling water valve pit (Category confined space) to perform a valve lineup. WHICH ONE (1) of the I
following states the requirements for atmospheric monitoring in the area?
: a. Required at      all times.
: b. Required only      if  the plant is operating.
: c. Required only      if  this is the initial entry after shutdown.
: d. Required only      if  welding, burning or painting is in progress.


SENIOR REACTOR OPERATOR 8.}Page 44 r~~k STION: 077 (1.00)WHICH ONE (1)of the following plant changes vill result in the indication from LI 3-52, Post Accident Range Level instrumentation, becoming more accurate?a.Reactor pressure increases from 900 to 1125 psig.b.Dryvell temperature increases from 100 to 212 degrees.c.Reactor building temperature increases from 10Q to 13Q degrees.d.Reactor recirculation pumps are manually tripped.QUESTION: 078 (1.00)The reactor is shutdown with Recirculation pumps off.WHICH ONE (1)of the following indicates reactor coolant stratification?
8 SENIOR REACTOR OPERATOR                                                   Page 31 TION: 050    (1.00)
a.Shutdown Cooling is out of service, RPV pressure is 5 psig, RX , VESSEL FLANGE DR LINE temperature is 170 degrees F, and RX VESSEL FW NOZZLE N4B END temperature is 205 degrees F.b.Shutdown Cooling is in service, RPV pressure is 5 psig, RX VESSEL BOTTOM HEAD temperature is 215 degrees F, and RX VESSEL FW NOZZLE N4B END temperature is 260 degrees F.c.Shutdovn Cooling is out of service, RPV pressure is 0 psig, RX VESSEL FLANGE DR LINE temperature is 130, and feedwater sparger temperature is 170.d.Shutdown Cooling is in service, RPV pressure is 0 psig, RX VESSEL BOTTOM HEAD temperature is 140, and feedwater sparger temperature is 195.  
An above ground oil storage tank has been discovered leaking.
Approximately 25 gallons have been leaked onto the ground surrounding the tank. WHICH set of actions listed below are in the correct order of response?
: a. Isolate the source of the leak, determine nature    and source of spill,  coordinate cleanup.
: b. Make the necessary notifications, Isolate the source of the leak, coordinate cleanup.
ce Find the source of the leakage, determine its flowpath, confine the spillage.
: d. Evacuate the vicinity, determine the nature and source, confine the material.
QUESTION: 051    (1 00) plant is operating at    804 power with three (3) hours remaining on a hour LCO. The Wilson Load Dispatcher requests the base load to be increased 25  MWE for the remainder of the operating run. WHICH ONE (1) of the following actions should be taken?
: a. Before increasing the electrical load, the request must be approved by EITHER the SOS or the ASOS.
: b. Before increasing the electrical load, the request must be approved by    BOTH the SOS and the ASOS.
: c. Before increasing the electrical load, the request must be approved by any licensed individual.
: d. The request for a load increase cannot be approved at this time.


SENIOR REACTOR OPERATOR Page 45 STION: 079 (1 00)A Reactor startup is in progress on Unit 2 when the following annunciators actuate.Current readings are also given.CRD ACCUM CHG WTR HDR 1480 psig CRD DRIVE WTR FILTER DIFF PRESS HIGH 50 psid Given the following plant conditions:
d.i SENIOR REACTOR OPERATOR                                                 Page 32 STION: 052    (1.00)
Rx Power is 5%Reactor Pressure is 550 psig Charging Water Pressure is 1480 psig (decreasing slowly)1 Accumulator is INOP due to water level 1 CRD High Temperature alarm WHICH ONE (1)of the following would be the correct IMMEDIATE action to take in accordance with 2-AOI-85-3,"CRD System Failure"'?
An  Alert is   declared at the plant. All of the emergency support facilities  have been activated and all notifications have been made.
a.A Manual Scram is required under current conditions.
The Alert condition no longer exists and you wish to announce that the event is terminated. WHICH ONE (1) of the following individuals must approve  this?
b.A Manual Scram is required if another Control Rod High Temperature alarm is received in congunction with the LOW CRD SUCTION PRESSURE alarm.c.A Manual Scram is required if a second Accumulator alarm is received.d.A Manual Scram is required if Charging Water Pressure decreases to 1400 psig.
: a. Site Emergency Director
: b. TSC  Superintendent
: c. Site Emergency Preparedness Manager
: d. NRC Senior Resident, Inspector QUESTION: 053      (1 00)
Four licensed UOs attended a fellow employee's birthday party the last night of their vacation and alcohol was served to all. Below shows when h UO stopped drinking alcoholic beverages.
UO  'A':05    am UO  'B':05    am UO  'C':05    am UO  'D':05    am From the four, UOs listed above, WHICH ONE (1) of the following states the'number available for NRC licensed work the same morning at 7:00 am?
(Assume that all the UOs have blood alcohol levels within SSP 1.6 guidelines)  .
: a. ONE
: b. TWO
: c. THREE
: d. FOUR


SENIOR REACTOR OPERATOR d.~Page 46 STION: 080 (F 00)Unit 2 control room has been abandoned and reactor pressure is decreasing due to a controlled cooldown.Water level is being controlled with the RCIC system at remote shutdown panel 25-32, in accordance with 2-AOI-100-2,"Control Room Abandonment".
SENIOR REACTOR OPERATOR                                                   Page 33 STION: 054    (1.00)
When reactor pressure decreases to 50 psi, WHICH ONE of the following describes the status of the RCIC system under these circumstances?
WHICH ONE   (1) of the following makes this next sentence correct? Fluid or gas systems that operate with temperatures greater than degrees F or pressure greater than                psig should be isolated from the work areas by two closed valves in series.
a.tripped and isolated.b.tripped but not isolated;can be restarted from Control Room c.tripped but not isolated;can NOT be restarted from Control Room d.RCIC is running QUESTION: 081 (1~00)Suppression pool temperature is 145 degrees F, Conditions have NOT been met for automatic transfer of HPCI suction.WHICH ONE (1)of the lowing describes the reason that the HPCI suppression pool water el suction transfer logic interlock is defeated and HPCI is operated th a suction from the CST?a.The suppression pool provides insufficient NPSH to the HPCI pump and cavitation may occur at rated flow.b.The HPCI shaft pump seals are not designed to operate at temperatures in excess of 140 degrees F and may fail.c.The HPCI lube oil will exceed allowable temperatures and the HPCI function could be lost due to damaged bearings.d.The HPCI turbine exhaust pressure is likely to exceed the trip setpoint at elevated suppression pool temperatures.
a  50/200 100/300
SENIOR REACTOR OPERATOR d.i Page 47~O STION: 082 (1.00)Unit 2 is operating at 100%rated power when the following indications are received: OG POST TREATMENT RADIATION HI-HI ALARM OG POST TREATMENT RADIATION HI-HI-HI/INOP ALARM OG PRETREATMENT RADIATION HI ALARM OG AVERAGE ANNUAL RELEASE LIMIT EXCEEDED ALARM WHICH ONE (1)of the following is the appropriate immediate operator action'?a.Reduce reactor power to 604 using recirc flow;manually scram the reactor.b.Reduce reactor power to 60%using recirc flow;insert control rods in reverse order to shutdown the reactor.c.Reduce core flow to 604;manually scram the reactor.d.Reduce core flow to 604;insert control rods in reverse order to shutdown the reactor.
: c. 150/400 d 200/500 l
SENIOR REACTOR OPERATOR Page 48~I STION: 083 (1.00)During operation at 1004 power, a turbine trip occurs, and subsequently a reactor scram signal is generated.
QUESTION: 055      (1.00)
Water level reaches-15 inches but is recovered by the operator using the feedwater system.Reactor pressure initially reaches 1105 psig, but is controlled normally thereafter by the turbine bypass valves.During response to the transient, the operator notes that neither recirculation pump is running.WHICH ONE (1)of the following is the basis for the recirculation pump trip7\a.To prevent damage to the recirculation pump seals when reactor pressure exceeds 1100 psig.b.To add negative reactivity, counteracting the positive reactivity added due to the pressure increase'hich resulted from the turbine trip.c.To promote level swell in the vessel, counteracting the shrink effects caused by the turbine trip.d.To protect the recirculation pumps from loss of adequate NPSH caused by the vessel level shrink resulting from the turbine trip.0
WHICH ONE   (1) of the following is the Technical Specification Basis for the equilibrium coolant iodine activity limit?
: a. To protect plant personnel from increased exposure in the plant during high power operation.
: b. To reduce exposure to plant personnel during refueling operations.
: c. To   limit thyroid  dose at the exclusion distance following  a steam  line break.
: d. To assure the stack gas emissions remain within the Technical Specification limit as calculated on an annual basis.


SENIOR REACTOR OPERATOR d.i Page 49 STION: 084 (1 00}A loss of all off-site power has occurred at, Unit 2.You are directed to backfeed the Unit boards from the Diesel generators in order to start a CCW pump and establish the Main Condenser as a heat sink for cooldown.WHICH ONE (1)of the following describes the effect of taking the 2 BACKFEED switches on the Unit Boards (Panels 9-23-7 and 9-23-8)to the BACKFEED position'?
0 4
a.Automatically trip and lockout the normal and alternate supply breaker, automatically trip the 43 switch to MANUAL, and allow the Unit Board to Shutdown Bus supply breaker to be manually closed.b.Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to MANUAL, and allow the alternate supply to Unit Board breaker to be manually closed.c.Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to AUTO and allow the alternate supply to Unit Board breaker to be manually closed.d.Automatically trip and lockout the alternate supply breaker, automatically trip the 43 switch to AUTO and allow the normal supply to Unit Board breaker to be auto closed.QUESTION: 085 (1.00)Control Room instrumentation and annunciation indicates that three turbine stop valves have drifted to 804 open.No rod movement has occurred.You observe that the individual blue lights for each control rod on the full-core display are illuminated.
Also, the eight scram solenoid group indicating lights are extinguished.
WHICH ONE (1}of the following is a possible cause for the failure to SCRAM?a.Failure of scram pilot valves to open.b.Only one RPS bus is de-energized.
c.Failure of scram inlet and outlet valves to open.d.Hydraulic lock on the scram discharge volume.


SENIOR REACTOR OPERATOR dS.i Page 50 STION'86 (1.00)Unit 2 is operating at 254 power when a loss of I&C bus"A" occurs.RPV level control is selected to Level"A".Recirc pumps are in individual manual control.WHICH ONE (1)of the following describes the expected plant response and operator actions for this event?a.Feed flow will increase until the turbine trips on high level.A manual SCRAM should be inserted.b.Recirc pump B will run back to minimum speed, Recirc pump A will experience a scoop tube lockup.Recirc pump A should be manually run back to minimum speed.c.Recirc flow will increase until the Reactor scrams on high flux.Both recirc pumps should be manually run back to minimum.d.Recirc pump A will run back to minimum speed, Recirc pump B will experience a scoop tube lockup.Recirc pump B should be manually run back to minimum speed.STION: 087 (1.00)ven the following plant conditions:
d.)
RPV level RPV pressure Drywell press.Torus level Rx zone vent rad Refuel zone vent rad+56 inches 1040 psig 2.40 psig+1 inch 75 mr/hr 62 mr/hr WHICH ONE (1)of the following EOI groups should be entered'?a.EOI-1,"RPV Control" and EOI-2, and EOI-4, Radiation Release Control.~b.EOI-1,"RPV Control" and EOI-2,"Primary Containment Control".c.EOI-2,"Primary Containment Control" and EOI-3,"Secondary Containment Control"..
SENIOR REACTOR OPERATOR                                                   Page 34 TION: 056    (1 00)
d.EOI-3,"Secondary Containment Control" and EOI-4, Radiation Release Control.
As SOS, you have    just declared an ALERT due to weather conditions. The Emergency Centers are NOT    staffed. WHICH ONE of the following should be notified within 5 minutes after the ALERT has been declared?
SENIOR REACTOR OPERATOR B.i Page 51~~STION: 088 (1.00)While operating at 754 power, a plant transient causes a trip of one Reactor Recirculation pump.Given the following plant conditions:
: a. Shift Fire Captain
Reactor power is 484 Core flow is 334 APRM A reading increases 44 and stabilizes Using the attached POWER/FLOW map, WHICH ONE (1)of the following states the appropriate operator action?a.Restart the idle recirculation pump to restore core flow to greater than 45%of rated.b.Increase recirculation flow on the operating pump to restore core flow to greater than 45%of rated.c.Insert control rods to reduce reactor power to less than 454.d.Scram the reactor.TION: 089 (1.00)Unit 2 is operating at rated power when all RBCCW pumps trip and none can be restarted.
: b. Operations Duty Specialist
WHICH ONE (1)of the following describes the IMMEDIATE operator actions appropriate for this situation'?
: c. NRC via Emergency Notification System
a.Reduce recirculation flow to minimum, if recirc pump seal cavity temperature exceeds 200 degrees F on BOTH pumps, TRIP both recirc pumps and SCRAM the reactor.b.If drywell temperature exceeds 145 degrees F, or drywell pressure exceeds 1.66 psig, insert a manual SCRAM, and trip both recirculation pumps.c.Run recirculation pumps to 45%speed, insert a manual SCRAM, Trip both recirculation pumps, and initiate a cooldown of 90 degrees F/hour.d.IMMEDIATELY TRIP both recirc pumps and SCRAM the reactor.
: d. Site Emergency Director
SENIOR REACTOR OPERATOR Page 52 STION: 090 (1.00)While offloading fuel bundles from the reactor, fuel pool level begins to decrease uncontrollably.
{}UESTION: 057    (1.00)
WHICH ONE (1)of the following describes a method available from the control room to add water to the fuel pool?a.Al'ign fuel pool cooling and cleanup heat exchanger RBCCW supply to the fuel pool to maintain level.b.Start an RHR pump and inject to the reactor vessel to maintain fuel pool level.c.Open emergency makeup supply valve from EECW to the fuel pool to maintain level.d.Open the CST to Fuel Pool Gravity drain valves.QUESTION: 091 (1.00)WHICH ONE (1)of the following scram signals is effective ONLY when the mode switch is in RUN?b.Turbine stop valve closure c.MSIU closure d.EHC low oil pressure QUESTION: 092 (1.00)Unit 2 is operating at 25%power.WHICH ONE (1)of the following combinations of events will NOT result in a half reactor scram?a.Both MSIU's in steam lines"A" and"B" isolate b.Both MSIU's in steam lines"A" and"D" isolate c.APRM"E" and"C" trip on hi-hi flux d.APRM"E" and"A" trip on hi-hi flux SENIOR REACTOR OPERATOR d%., Page 53 STION: 093 (1~00)WHICH ONE (1)of the following conditions requires a manual reactor SCRAM?a.RBCCW pump suction header temperature of 102 degrees F b.Pre-treatment radiation HI-HI-Hi c.Both recirculation pumps trip with the mode switch in Startup d.Off-gas system Hydrogen concentration of 5%QUESTION: 094 (1.00)WHICH ONE (1)of the following conditions assures ADEQUATE CORE COOLING?a.All rods inserted, RPV level-200, MSRV's cycling on pressure, no injection flow.b.RPV level unknown, 6 MSRV's open, reactor pressure is 10 psig.c.Reactor power 34, RPV level-210, one MSRV open, HPCI injecting at maximum flow.d.RPV level-230, RHR"B" and"D" injecting at maximum flow, suppression pool level at 15 feet.
Given the following plant conditions:
SENIOR REACTOR OPERATOR Page 54 STION: 095 (1.00)The Control Room has been abandoned.
A failure to scram has occurred.
All MSRV transfer switches at panel 25-32 have been placed in EMERGENCY.
Reactor power is 24.
All MSRV control switches at panel 25-32 are in CLOSE.WHICH ONE (1)of the following states the opening capability of the MSRVs'?a;ONLY manually by placing the panel 25-32 control switches in.OPEN b.ONLY manually OR upon receipt of an ADS initiation signal c.ONLY manually OR when their respective pressure relief setpoint is reached d.EITHER manually OR on an ADS initiation signal OR when their respective pressure relief setpoint is reached QUESTION: 096 (1-00)loop I is in shutdown cooling taking suction through Shutdown ling suction valves 74-47 and 74-48.Loop II of RHR remains in the CI standby lineup.Due to misoperation of ventilation systems, Drywell pressure increases to 2.5 psig.WHICH ONE (1)of the following describes the response of the RHR system'P a.Valves 74-47 and 74-48 close, Loop I suppression pool suction valves auto open and BOTH RHR loops inject to the vessel.b.Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves auto open but only Loop II injects.c.Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and only Loop II injects.d.Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and NEITHER Loop injects.
A high temperature exists in Secondary Containment
0 SENIOR REACTOR OPERATOR Page 55 TION: 097 (1 00)An emergency exists which requires addition of water to the suppression pool.Your supervisor directs use of Appendix 18 of the Emergency Procedures.
                                ~
Using Appendix 18, WHICH ONE (1)of the following describes the availability of HPCI and RCIC?a.Neither HPCI nor RCIC are available if they have isolated.b.Both HPCI and RCIC are available even if they have isolated., c.HPCI is available unless it has isolated;RCIC is available even if isolated.d.RCIC is available unless it has isolated;HPCI is available even if isolated.QUESTION: 098 (1.00)A severe earthquake has occurred, causing a LOCA and complete loss of-site power.The Diesel generators are carrying plant loads as igned.Plant conditions are as follows: RPV level RPV pressure Drywell press.Torus level Rx zone vent rad Refuel zone vent rad Spent fuel pool level Off-site release rate Radiation levels+15 inches, steady 50 psig, decreasing 2.40 psig, increasing slowly-2 inches, decreasing slowly 75 mr/hr 62 mr/hr dropping rapidly, fuel uncovered 100 Ci/sec gaseous at stack 25 mr/hr at site boundary WHICH ONE (1)'of the following is the appropriate EPIP classification?
due to fire.
a.Unusual Event b.Alert c.Site Area Emergency d.General Emergency
MSIVs are closed.
RCIC is maintaining RPV
                  ~    ~
level.
HPCI is inoperable.
                ~
Control rods are being inserted using CRD.
                                            ~
WHICH ONE (1) of the following systems should be isolated into the Secondary?
if discharging
: a. Control Rod Drive
: b. Reactor Water Cleanup
: c. Reactor Core Isolation Cooling
: d. Fire Suppression


SENIOR REACTOR OPERATOR d.)Page 56 STION: 099 (1.00)n An emergency has been declared and all emergency response centers have been staffed.WHICH ONE (1)of the following duties of the Site Emergency Director can be delegated?
0 d.>
a.Determination of emergency event classification b.Issuance of off-site Protective Action Recommendation c.Approval to exceed 10 CFR 20 radiation exposure limits d.Ordering evacuation of the plant a.Reducing RPV pressure ensures a slower, more stable reflood to limit thermal shock to the reactor core.QUESTION: 100 (1 00)Reactor level cannot be determined.
SENIOR REACTOR OPERATOR                                               Page 35 I
Prior to entering RPV Flooding, the EOIs direct that Emergency Depressurization must be performed.
TION: 058    (1. 00)
WHICH ONE (1)of the following is the bases for requiring RPV depressurization t prior to entering RPV Flooding?b.Opening the ADS valves ensures the minimum number of MSRVs required to support RPV flooding will be open.c.Reducing RPV pressure ensures dynamic loading on the MSRVs is minimized as RPV water level reaches MSRVs and is discharged.
During an ATWS with the reactor at high power, EOI-1, step RC/Q-l directs that recirculation be run back to minimum prior to tripping the Reactor recirculation pumps. WHICH ONE (1) of the following is the basis for this action?
d.Emergency procedures assume that high pressure injection sources may be unavailable due to failed high RPV level instrumentation.
: a. Prevent MSIV closure on high flow.
(+*********
: b. Promote boron mixing.
END OF EXAMINATION
: c. Prevent Main Generator reverse power trip.
**********)
: d. Prevent Main Turbine high RPV water level trip.
QUESTION: 059    (1.00)
Given the  following plant conditions:
Reactor pressure is 930 psig RPU level is +28 inches RCIC is injecting Twenty control rods are at position 48 Reactor power is 9000 cps on the SRMs and decreasing A 90 degree F/hr cooldown is in progress
                                                          \
WHICH ONE (1) of the following would require termination of cooldown?
: a. RPV level lowers to +15 inches.
: b. SRM count rate increases to 10000 cps.
: c. Main turbine bypass valves fail closed.
II
: d. Drywell pressure begins to increase.


SENIOR REACTOR OPERATOR ANSWER KEY Page.1 MULTIPLE CHOICE 001: P hor4 002 b 003 b 004 d 005 a 006 a 007 d 008 c 009 c~~011 c 012 c 013 a 014 a 015 a 016 b 017 b 018 a 019 b 020 c 021 bc 023 b 024 b 025 a 026 a 027 a 028 c 029 c 030 b 031 b 032 c 033 b 034 c 035 d 036 d 037 c 038 b 039 c 040 041 d 042 c 043 b 044 c 045 d SENXOR REACTOR OPERATOR d%.A N S W E R K E Y Page 2 046 b 047" a orb 048 b 049 a 050 c 051 1 052 a 053 W Ch 054 0 058 6 059 b 060 6 061 b 062 c orb 063 c 064 b 065 c 066 b 067 cd 069 b 070 a 071 072 b 073 c 074 a 075 b 076 c 077 078 a 079 080 6 081 c 082 a 083 b 084 a 085 6 086 b 087 c 088 b 089 c 090 b 091 c  
SENIOR REACTOR OPERATOR                                                 Page 36 STION: 060    (1.00)
WHICH ONE  (1)  of the following responses. will be noted on Unit 2 during a complete  loss of Unit 2 ISC Bus during reactor operation?
: a. Unit 2 reactor water level increase
: b. Unit 1 Loop A recirculation pump speed increase
: c. Unit 3 SJAE flow to offgas system increase
: d. Unit 2 main steam tunnel temperature increase QUESTION: 061    (1.00)
During a plant transient on Unit 2, a Group I isolation is caused by high radiation. Five control rods fail to insert. Suppression pool level is 12 feet and pool temperature is 94 degrees F.
WHICH ONE (1) of the following identifies the systems available to help
  'ntain pressure below 1040 psig?
  ~
: a. HPCI, RCIC
: b. RCIC, RWCU
: c. RWCU, MSL  drains
: d. MSL  drains, HPCI


SENIOR REACTOR OPERATOR d.)A N S W E R K E Y Page 3 092 b 093'094 a 095 c 096 097 c 098 c 099 b 100 c (**********
d.,i SENIOR REACTOR OPERATOR                                                     Page 37 STION- 062    (1.00)
END OF EXAMINATION
The  Control Room was evacuated due to a fire 5 minutes ago. All the immediate actions    for '~Control Room Abandonment" were performed.
******+***)
Current plant conditions are:
SENIOR REACTOR OPERATOR Page 57 WER 001 (1.00)a.oc b  
The  reactor has been verified to be shutdown.
RPV  level is > +60 inches.
RPV  pressure is 700 psig and decreasing slowly.
The MSIVs are open and cannot be closed.
The turbine bypass valves appear to be functioning normally.
An operator is stationed to control RPV level and pressure with HPCI as  necessary.
WHICH ONE    (1) of the following is the appropriate  emergency  action level for this situation'?
: a. Unusual Event
: b. Alert
: c. Site Area Emergency QUESTION: 063    (1.00)
During an ATWS, EOIs direct the operator      to inhibit ADS automatic blowdown when Standby Liquid Control is      injected. WHICH ONE (1) of the following states the basis for this requirement?
: a. ADS actuation would impose a severe pressure and temperature transient on the vessel.
: b. ADS would result in the removal of boron after injected.
it has been
: c. Core damage could result from a large power. excursion pressure ECCS systems were to inject.
if low e
: d. ADS/MSRV system flow rate is incapable of assuring fuel cooling through steaming above 5% reactor power.


==REFERENCE:==
8.)
SENIOR REACTOR OPERATOR                                                  Page 38 STION: 064  (1.00)
While the reactor is operating at 904 power, reactor pressure is observed decreasing at an approximate rate of 200 psig per minute.
WHICH ONE (1) of the following is the expected immediate operator action?
: a. Scram the reactor and place the pressure control    unit in manual.
: b. Scram the reactor and close the MSIVs.
: c. Take manual control of the reactor pressure control unit.
: d. Manually transfer to the backup pressure control unit.
QUESTION: 065    (1.00)
A failure of Drywell Control Air has resulted in Drywell control air being supplied by the Plant Control Air header. WHICH ONE (1) of the following is a concern during the malfunction?
: a. Moisture  in the air  may cause  critical valves to fail.
: b. Torus temperature  may  increase.
: c. Drywell oxygen level may increase.
: d. Breathing air is unavailable.


1.'echnical Speci.fication 4.3.B.3..a 2~OPL171.006, Ob)14 3~K/A: 201003G001 (3 6/3 7)201003G001
0 d.i SENIOR REACTOR OPERATOR                                                  Page 39 STION: 066    (1.00)
..(KA's)ANSWER: QQ2 (1.00)b.REFERENCE-OPL171.006, Obj.13'/A 201001K303 (3~1/3~2)201001K303
WHICH ONE  (1) of the following systems is used to inject    Alternate Standby Liquid Control (SLC) boron into the reactor?
..(KA's)ANSWER: 003 (1.00)b.  
: a. Suppression Chamber Head Tank system
: b. Control Rod Drive system
: c. RHR Standby Coolant system
: d. Condensate 'and Feedwater system QUESTION: 067    (1.00)
The reactor has experienced an incomplete scram. WHICH ONE (1) of the following methods of rod insertion requires first resetting the SCRAM?
: a. De-energization of scram solenoids
: b. Venting of the scram air header
: c. Scraming individual control rods using test switches
: d. Venting the Control Rod Drive over piston volume QUESTION: 068    (1.00)
WHICH ONE  (1) of the following constitutes  a loss of Secondary Containment?
: a. The Reactor Building normal  HVAC is inoperable  and isolated.
: b. Both Reactor Building  ventilation radiation. monitors are  INOP.
: c. The Reactor Building/Suppression  Chamber vacuum  breaker  is open.
: d. The Standby Gas Treatment system  is inoperable.


SENIOR REACTOR OPERATOR d%.i Page 58
0 a
SENIOR REACTOR OPERATOR                                                                     Page 40 STION: 069      (1 ~ 00)
WHICH ONE      (1) of the following describes the basis Xor the Drywell Spray Initiation Limit Curve'
      ~            ~
I
: a. To prevent unstable steam condensation in the NSRV tailpipes from exerting excessive cyclic hydraulic loads on the suppression pool structure,
: b. To ensure that the rate at which the primary containment is depressurized is within the capacity of the reactor building to suppression pool vacuum breakers.
: c. To prevent chugging in the drywell to suppression pool from exerting excessive cyclic hydraulic loads on the
                                                                        'owncomers suppression pool structure.
: d. To ensure adequate noncondensibles remain in the drywell to the suppression pool to drywell vacuum breakers from        'revent opening during drywell steam condensation.
TION: 070      (1 00)
Drywell pressure has exceeded 30 psig and the Suppression Chamber vent path is unavailable. The EOIs direct termination of CAD system use and initiation of venting from the Drywell. WHICH ONE (1) of the following states the basis for'hifting vent paths under these conditions'
: a. Use  of the Containment Air Dilution system at    this pressure could cause loss of Containment.
: b. The Drywell vent path is designed to withstand greater temperatures and pressures.
: c. The Drywell vent path is sized to limit effluent flow rate to ensure releases are within the design basis.
: d. The Drywell vent path contains supplementary sample      lines routed to the Post Accident Sampling system (PASS).


==REFERENCE:==
d.i SENIOR REACTOR OPERATOR                                                          Page 41 STION: 071      (1.00)
                      ~
Within two minutes after a loss of Reactor Building Closed Cooling
                  ~
Water, AOI 70-1~ "Loss of RBCCW", directs that, the reactor be scrammed and both recirculation pumps be tripped. WHICH ONE (1) of the following is the basis for this action'?
: a. Loss    of cooling will lead to filter demin    inlet temperature increase and auto isolation of RWCU.
: b. Loss of flow to RHR      pump  coolers will prevent  the RHR  system from meeting design      criteria.
: c. Loss of cooling to the Recirculation pump seals will lead to          a primary coolant leak.
: d. Loss of Drywell cooling will lead to an increase in Drywell pressure, actuating safety related equipment.
{}UESTION: 072      (1 00) reactor has scrammed from 1004 power due to closure of the MSIVs.
ening of MSRVs has increased torus temperature to 125 degrees F.
Current plant conditions are as follows:
All rods in Mode  switch in Shutdown Reactor level is +45 inches Reactor pressure is 950 psig Drywell pressure is 1.2 psig WHICH ONE    (1)    of the following is the required operator action?
: a. Power      operation shall not be resumed until the pool temperature is reduced below 90 degrees F.
: b. Reactor vessel shall be depressurized        to less than  200  psig at normal cooldown rates.
: c. The reactor shall be in        a  cold shutdown condition within  24 hours.
: d. Maintain Primary Containment        integrity until pool temperature is reduced below 100 degrees F.


Tech Spec 3.7.A.4 and bases OPL171.016 Obj.4, 18, page 19 K/A: 223001G006 (3'/4 0)'223001G006
d%.
..(KA's)ANSWER: 004 (1.00)d.
SENIOR REACTOR OPERATOR                                                Page 42 STION: 073    (1.00)
                    ~
EOI-2, "Primary Containment Control," step PC/H-8 requires that
            ~
Suppression Pool level be verified below 26 feet prior to initiating Suppression Chamber sprays for hydrogen control. WHICH ONE (1) of the following is the basis for this    limitV'.
Ensure the torus to drywell vacuum breakers are not submerged.
: b. Ensure the torus vent header is not submerged.
: c. Ensure the torus spray nozzles are not submerged.
: d. Ensure the torus downcomer header is not submerged.
QUESTION: 074    (1.00) t While the plant is operating at full power, a complete loss of Control Air is experienced. WHICH ONE (1) of the following containment isolation valves is designed to fail open under these circumstances?
: a. Suppression Chamber vacuum          relief valves
: b. Main Steam    Isolation Valve
: c. Refuel zone ventilation dampers
: d. RHR  process water sampling valve


==REFERENCE:==
d,i SENIOR REACTOR OPERATOR                                                    Page 43 STION: 075      (1. 00)
A  pipe shear has resulted in Control Air pressure immediately decreasing to  0 psig. WHICH ONE (1) of the following will remain available'
: a. Off Gas b'. Stator Cooling Water
: c. Reactor Water Cleanup
: d. Raw  Service Water supply to  fire systems QUESTION: 076      (1.00)
The main    turbine control valves have failed closed and reactor pressure has increased    to the scram setpoint. Approximately one third of the control rods have failed to fully insert, MSIVs remain open and several SRVs are cycling.        EOI-1, RPV Control Procedure, step RC/P-6, directs the crew to manually open any cycling SRV until RPV pressure drops to 0 psig.      WHICH ONE (1) of the following is the basis for this lower it'?
: a. Maintain reactor pressure high enough      to scram control rods should CRD pumps become unavailable.
: b. Prevent    initiation of a low reactor pressure scram signal while attempting to drive rods.
: c. Limit the amount of energy sent to the suppression pool through the MSRVs.
: d. Preclude the possibility of a Group 1 isolation on low Main Steam Line pressure.


1.OPL 171.029, Obj.9, pages 21, 26 2.K/A 201002A402 (3~5/3~5)..(KA's)ANSWER: 005 (1.00)a~
8.}
SENIOR REACTOR OPERATOR                                                      Page 44 r
k STION: 077    (1.00)
WHICH ONE    (1) of the following plant changes vill result in the indication from LI 3-52, Post Accident Range Level instrumentation,
  ~ ~
becoming more accurate?
: a. Reactor pressure increases  from 900  to  1125 psig.
: b. Dryvell temperature increases  from 100  to  212 degrees.
: c. Reactor building temperature increases from 10Q to      13Q degrees.
: d. Reactor recirculation pumps are manually tripped.
QUESTION: 078      (1.00)
The  reactor is shutdown with Recirculation    pumps  off. WHICH ONE  (1)  of the following indicates reactor coolant stratification?
: a. Shutdown Cooling is out of service, RPV pressure is 5 psig, RX
          , VESSEL FLANGE DR LINE temperature is 170 degrees F, and RX VESSEL FW NOZZLE N4B END temperature is 205 degrees F.
: b. Shutdown Cooling is in service, RPV pressure is 5 psig, RX VESSEL BOTTOM HEAD temperature is 215 degrees F, and RX VESSEL FW NOZZLE N4B END temperature is 260 degrees F.
: c. Shutdovn Cooling is out of service, RPV pressure is 0 psig, RX VESSEL FLANGE DR LINE temperature is 130, and feedwater sparger temperature is 170.
: d. Shutdown Cooling is in service, RPV pressure is 0 psig, RX VESSEL BOTTOM HEAD temperature is 140, and feedwater sparger temperature is 195.


==REFERENCE:==
SENIOR REACTOR OPERATOR                                                      Page 45 STION: 079    (1 00)
A  Reactor startup is in progress on Unit 2 when the following annunciators actuate. Current readings are also given.
CRD ACCUM CHG WTR HDR                      1480 psig CRD DRIVE WTR FILTER DIFF PRESS    HIGH    50 psid Given the  following plant conditions:
Rx Power  is  5%
Reactor Pressure is 550 psig Charging Water Pressure is 1480 psig (decreasing slowly) 1 Accumulator is INOP due to water level 1 CRD High Temperature alarm WHICH ONE  (1) of the following would be the correct IMMEDIATE action to take in accordance with 2-AOI-85-3, "CRD System Failure"'?
: a. A Manual Scram is required under current conditions.
: b. A Manual Scram  is required if another Control Rod High Temperature alarm  is received in congunction with the LOW    CRD SUCTION PRESSURE  alarm.
: c. A Manual Scram received.
is required  if a second  Accumulator alarm  is
: d. A Manual Scram to  1400  psig.
is required  if Charging  Water Pressure  decreases


1.OPL171.009, Obj.5, page 12 2~K/A: 239002K605 (3.0/3.2)239002K605
d.~
..(KA's)ANSWER: 006 (1.00)
SENIOR REACTOR OPERATOR                                                    Page 46 STION: 080    (F 00)
SENIOR REACTOR OPERATOR d.Page 59
Unit 2 control room has been abandoned and reactor pressure is decreasing due to a controlled cooldown. Water level is being controlled with the RCIC system at remote shutdown panel 25-32, in accordance with 2-AOI-100-2, "Control Room Abandonment". When reactor pressure decreases to 50 psi, WHICH ONE of the following describes the status of the RCIC system under these circumstances?
: a. tripped and isolated.
: b. tripped but not isolated; can be restarted from Control Room
: c. tripped but not isolated; can NOT be restarted from Control Room
: d. RCIC  is running QUESTION: 081    (1 ~ 00)
Suppression pool temperature    is 145 degrees F, Conditions have NOT been met  for automatic transfer of HPCI suction. WHICH ONE (1) of the lowing describes the reason that the HPCI suppression pool water el suction transfer logic interlock is defeated and HPCI is operated th  a suction from the    CST?
: a. The suppression pool provides insufficient    NPSH  to the HPCI pump and cavitation may occur at rated flow.
: b. The HPCI shaft pump seals are not designed to operate at temperatures in excess of 140 degrees F and may fail.
: c. The  HPCI  lube oil will exceed allowable temperatures and the HPCI  function could be lost due to damaged bearings.
: d. The HPCI turbine exhaust pressure is likely to exceed the trip setpoint at elevated suppression pool temperatures.


==REFERENCE:==
d.i SENIOR REACTOR OPERATOR                                                  Page 47
                    ~O STION: 082  (1.00)
Unit 2 is operating at  100%  rated power when the following indications are received:
OG POST TREATMENT RADIATION HI-HI ALARM OG POST TREATMENT RADIATION HI-HI-HI/INOP ALARM OG PRETREATMENT RADIATION HI ALARM OG AVERAGE ANNUAL RELEASE LIMIT EXCEEDED ALARM WHICH ONE  (1) of the following is the appropriate immediate operator action'?
: a. Reduce reactor power to 604 using  recirc flow; manually scram the reactor.
: b. Reduce reactor power to 60% using recirc flow; insert control rods in reverse order to shutdown the reactor.
: c. Reduce core flow to 604; manually scram the reactor.
: d. Reduce core flow to 604; insert control rods in reverse order to shutdown the reactor.


'~~~~~OI-71, Precaution 3.23 OPL171.037, Obj.11 3~K/A: 263000G005 (3'/3')263000G005
SENIOR REACTOR OPERATOR                                                    Page 48
..(KA's)ANSWER 007 (1.0,0)
                      ~ I STION: 083    (1.00)
During operation at 1004 power, a turbine trip occurs, and subsequently a  reactor scram signal is generated. Water level reaches -15 inches but is recovered by the operator using the feedwater system. Reactor pressure initially reaches 1105 psig, but is controlled normally thereafter by the turbine bypass valves. During response to the transient, the operator notes that neither recirculation pump is running. WHICH ONE (1) of the following is the basis for the recirculation  pump    trip7        \
: a. To prevent damage to the recirculation pump seals when reactor pressure exceeds 1100 psig.
: b. To add negative      reactivity, counteracting the positive reactivity      added due  to the pressure increase'hich resulted from the turbine      trip.
: c. To promote      level swell in the vessel, counteracting the shrink effects caused by the turbine trip.
: d. To protect the recirculation pumps from loss of adequate NPSH caused by the vessel level shrink resulting from the turbine trip.
0


==REFERENCE:==
d.i SENIOR REACTOR OPERATOR                                                Page 49 STION: 084    (1 00}
A loss of all off-site power has occurred at, Unit 2. You are directed to backfeed the Unit boards from the Diesel generators in order to start a CCW pump and establish the Main Condenser as a heat sink for cooldown.
WHICH ONE (1) of the following describes the effect of taking the 2 BACKFEED switches on the Unit Boards (Panels 9-23-7 and 9-23-8) to the BACKFEED  position'?
: a. Automatically trip and lockout the normal and alternate supply breaker, automatically trip the 43 switch to MANUAL, and allow the Unit Board to Shutdown Bus supply breaker to be manually closed.
: b. Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to MANUAL, and allow the alternate supply to Unit Board breaker to be manually closed.
: c. Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to AUTO and allow the alternate supply to Unit Board breaker to be manually closed.
: d. Automatically trip and lockout the alternate supply breaker, automatically trip the 43 switch to AUTO and allow the normal supply to Unit Board breaker to be auto closed.
QUESTION: 085    (1.00)
Control Room instrumentation and annunciation indicates that three turbine stop valves have drifted to 804 open. No rod movement has occurred. You observe that the individual blue lights for each control rod on the full-core display are illuminated. Also, the eight scram solenoid group indicating lights are extinguished. WHICH ONE (1} of the following is a possible cause for the failure to SCRAM?
: a. Failure of scram pilot valves to open.
: b. Only one  RPS bus is de-energized.
: c. Failure of scram  inlet and outlet valves to open.
: d. Hydraulic lock on the scram discharge volume.


1.OPL171.044, Obj.11, page 27 2 K/A: 226001A403 (3.5/3.4)226001A403
dS.i SENIOR REACTOR OPERATOR                                                  Page 50 STION'86 (1. 00)
..(KA's)ANSWER: 008 (1.00)co
Unit 2 is operating at 254 power when a loss of I&C bus "A" occurs. RPV level control is selected to Level "A". Recirc pumps are in individual manual control. WHICH ONE (1) of the following describes the expected plant response and operator actions for this event?
: a. Feed flow will increase until the turbine trips on high level.
A manual SCRAM should be inserted.
: b. Recirc pump B will run back to minimum speed, Recirc pump A will experience a scoop tube lockup. Recirc pump A should be manually run back to minimum speed.
: c. Recirc flow will increase until the Reactor scrams on high flux.
Both  recirc  pumps  should be manually run back to minimum.
: d. Recirc pump A will run back to minimum speed, Recirc pump    B will experience a scoop tube lockup. Recirc pump B should be manually run back to minimum speed.
STION: 087    (1.00) ven the  following plant conditions:
RPV level                    +56 inches RPV pressure                1040 psig Drywell press.               2.40 psig Torus level                  +1 inch Rx zone  vent rad          75 mr/hr Refuel zone vent rad        62 mr/hr WHICH ONE  (1)  of the following EOI groups should  be entered'?
: a. EOI-1, "RPV Control" and EOI-2, and EOI-4, Radiation Release Control.
    ~ b. EOI-1,  "RPV  Control" and EOI-2, "Primary Containment Control".
: c. EOI-2, "Primary Containment Control" and EOI-3, "Secondary Containment    Control"..
: d. EOI-3, "Secondary Containment Control" and EOI-4, Radiation Release Control.


==REFERENCE:==
B.i SENIOR REACTOR OPERATOR                                                    Page 51 STION: 088    (1.00)
                    ~
While operating at 754 power, a plant transient causes a trip of one
                ~
Reactor Recirculation pump. Given the following plant conditions:
Reactor power    is 484 Core  flow is  334 APRM A  reading increases 44 and stabilizes Using the attached POWER/FLOW map, WHICH ONE (1) of the following states the appropriate operator action?
: a. Restart the idle recirculation pump to restore core flow to greater than 45% of rated.
: b. Increase recirculation flow on the operating pump to restore core flow to greater than 45% of rated.
: c. Insert control rods to reduce reactor power to less than 454.
: d. Scram the reactor.
TION: 089    (1.00)
Unit  2 is operating at rated    power when all  RBCCW  pumps trip and none can be  restarted. WHICH ONE (1) of the following describes the IMMEDIATE operator actions appropriate for this situation'?
: a. Reduce recirculation flow to minimum,    if  recirc pump seal cavity temperature exceeds 200 degrees F on BOTH pumps, TRIP both recirc pumps and SCRAM the reactor.
: b. If drywell temperature exceeds 145 degrees F, or drywell pressure exceeds 1.66 psig, insert a manual SCRAM, and trip both recirculation pumps.
: c. Run recirculation pumps to 45% speed, insert a manual SCRAM, Trip both recirculation pumps, and initiate a cooldown of 90 degrees F/hour.
: d. IMMEDIATELY TRIP both    recirc pumps and SCRAM  the reactor.


1.OPL171.044, Ob j.14, page 29 2~K/A: 203000K601 (3.6/3.7)203000K601
SENIOR REACTOR OPERATOR                                                      Page 52 STION: 090      (1.00)
..(KA's)ANSWER: 009 (1.00)  
While offloading fuel bundles from the reactor, fuel pool level begins to decrease uncontrollably. WHICH ONE (1) of the following describes a method available from the control room to add water to the fuel pool?
: a. Al'ign fuel pool cooling and cleanup heat exchanger        RBCCW supply to the fuel pool to maintain level.
: b. Start an RHR pump and inject to the reactor vessel to maintain fuel pool level.
: c. Open emergency makeup supply valve from EECW to the fuel pool to maintain level.
: d. Open the CST to Fuel Pool Gravity drain valves.
QUESTION: 091    (1.00)
WHICH ONE  (1) of the following  scram  signals is effective  ONLY when  the mode switch is in    RUN?
: b. Turbine stop valve closure
: c. MSIU closure
: d. EHC  low  oil pressure QUESTION: 092    (1.00)
Unit 2  is operating at    25%  power. WHICH ONE  (1) of the following combinations of events    will NOT result in  a  half reactor scram?
: a. Both    MSIU's in steam lines "A" and "B" isolate
: b. Both    MSIU's in steam lines "A" and "D" isolate
: c. APRM  "E" and "C" trip on hi-hi flux
: d. APRM  "E" and "A" trip on hi-hi flux


SENZOR REACTOR OPERATOR Page 60
d%.,
SENIOR REACTOR OPERATOR                                                 Page 53 STION: 093    (1 ~ 00)
WHICH ONE  (1) of the following conditions requires    a manual reactor SCRAM?
: a. RBCCW  pump    suction header temperature of 102 degrees F
: b. Pre-treatment radiation HI-HI-Hi
: c. Both recirculation pumps trip with the mode switch in Startup
: d. Off-gas system Hydrogen concentration of 5%
QUESTION: 094  (1.00)
WHICH ONE  (1) of the following conditions assures ADEQUATE CORE COOLING?
: a. All rods inserted, RPV level -200, MSRV's cycling on pressure, no injection flow.
: b. RPV level unknown, 6 MSRV's open, reactor pressure is 10 psig.
: c. Reactor power 34, RPV level -210, one MSRV open, HPCI injecting at maximum flow.
: d. RPV level -230, RHR "B" and "D" injecting at maximum flow, suppression pool level at 15 feet.


==REFERENCE:==
SENIOR REACTOR OPERATOR                                                Page 54 STION: 095    (1. 00)
The Control Room has been abandoned. All MSRV transfer switches at panel 25-32 have been placed in EMERGENCY. All MSRV control switches at panel 25-32 are in CLOSE. WHICH ONE (1) of the following states the opening capability of the MSRVs'?
a; ONLY manually by placing the panel 25-32 control switches in.
OPEN
: b. ONLY manually  OR upon receipt of an ADS initiation signal
: c. ONLY manually  OR when their respective pressure relief setpoint is reached
: d. EITHER manually OR on an ADS initiation signal  OR when their respective pressure relief setpoint is reached QUESTION: 096    (1-00) loop I is in shutdown cooling taking suction through Shutdown ling suction valves 74-47 and 74-48. Loop II of RHR remains in the CI standby lineup. Due to misoperation of ventilation systems, Drywell pressure increases to 2.5 psig. WHICH ONE (1) of the following describes the response of the RHR system'P
: a. Valves 74-47 and 74-48 close, Loop I suppression pool suction valves auto open and BOTH RHR loops inject to the vessel.
: b. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop suppression pool suction valves auto open but only Loop injects.
III
: c. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and only Loop injects.
II
: d. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and NEITHER Loop injects.


~~~~OPL171.043, Obj.4, pages 9, 10 K/A: 218000K501 (3.8/3.8)218000K501
0 SENIOR REACTOR OPERATOR                                                  Page 55 TION: 097    (1 00)
..(KA's)ANSWER 010 (1.00)ci
An emergency  exists which requires addition of water to the suppression pool. Your supervisor directs use of Appendix 18 of the Emergency Procedures. Using Appendix 18, WHICH ONE (1) of the following describes the availability of HPCI and RCIC?
: a. Neither HPCI nor RCIC are available    if they have isolated.
: b. Both HPCI and RCIC are available even    if they have isolated.,
: c. HPCI is available unless if isolated.             it has isolated; RCIC is available even
: d. RCIC is available if isolated.       unless it has isolated;  HPCI is available  even QUESTION: 098    (1.00)
A severe earthquake has occurred, causing a LOCA and complete loss of
    -site power. The Diesel generators are carrying plant loads as igned. Plant conditions are as follows:
RPV  level                      +15 inches, steady RPV  pressure                    50 psig, decreasing Drywell press.                    2.40 psig, increasing slowly Torus level                      -2 inches, decreasing slowly Rx zone vent rad                  75 mr/hr Refuel zone vent rad              62 mr/hr Spent fuel pool level            dropping rapidly, fuel uncovered Off-site release rate            100 Ci/sec gaseous at stack Radiation levels                  25 mr/hr at site boundary WHICH ONE  (1)'of the following is the appropriate EPIP classification?
: a. Unusual Event
: b. Alert
: c. Site Area Emergency
: d. General Emergency


==REFERENCE:==
d.)
SENIOR REACTOR OPERATOR                                                    Page 56 STION: 099  (1.00) n An emergency has been declared and    all  emergency response  centers have been staffed. WHICH ONE (1) of the    following duties of the Site Emergency Director can be delegated?
: a. Determination  of  emergency event  classification
: b. Issuance of  off-site Protective Action    Recommendation
: c. Approval to exceed 10 CFR 20 radiation exposure      limits
: d. Ordering evacuation of the plant QUESTION: 100  (1 00)
Reactor level cannot be determined. Prior to entering RPV Flooding, the t
EOIs direct that Emergency Depressurization must be performed. WHICH ONE (1) of the following is the bases for requiring RPV depressurization prior to entering RPV Flooding?
: a. Reducing RPV pressure ensures a slower, more stable reflood to limit thermal shock to the reactor core.
: b. Opening the ADS valves ensures the minimum number of MSRVs required to support RPV flooding will be open.
: c. Reducing RPV pressure ensures dynamic loading on the MSRVs is minimized as RPV water level reaches MSRVs and is discharged.
: d. Emergency procedures assume that high pressure injection sources may be unavailable due to failed high RPV level instrumentation.
(+*********  END OF EXAMINATION  **********)


1.Technical Specification 4.6.E.1 2.OPL171.007, Obj.32, page 54 3~K/A: 2020016005 (3'/4')202001G005
SENIOR REACTOR OPERATOR Page. 1 ANSWER    KEY MULTIPLE CHOICE            023    b 001: P    hor4                  024    b 002    b                      025    a 003    b                      026    a 004    d                      027    a 005      a                      028    c 006      a                      029    c 007     d                      030    b 008    c                      031    b 009    c                      032    c
..(KA's)ANSWER: 011 (1 00)ci
~011
        ~
c 033 034 b
c 012    c                      035    d 013      a                      036    d 014    a                      037    c 015    a                      038    b 016    b                      039    c 017    b                      040 018    a                      041    d 019    b                      042    c 020    c                      043    b 021    b                      044    c c                      045    d


==REFERENCE:==
d%.
SENXOR REACTOR OPERATOR Page 2 A N S W E R    K E Y 046    b                                069    b 047 " a orb                              070    a 048    b                                071 049    a                                072    b 050    c                                073    c 051    1                                074    a 052    a                                075    b 053    W Ch                              076    c 054                                      077 0
078    a 079 080    6 058    6                                081    c 059    b                                082    a 060    6                                083    b 061    b                                084    a 062    c  orb                          085    6 063    c                                086    b 064    b                                087    c 065    c                                088    b 066    b                                089    c 067    c                                090    b d                                091    c


1.OPL171.007, Obj.31, pages 54, 34 2.OZ-68, page 6 3~K/A: 202002G010 (3.3/3.3)2020026010
d.)
..(KA's)ANSWER: 012 (1.00)  
SENIOR REACTOR OPERATOR                                    Page 3 A N S W E R  K E Y 092  b 093 '
094  a 095  c 096 097  c 098  c 099  b 100  c
(**********END OF EXAMINATION ******+***)


SENIOR REACTOR OPERATOR Page 61
SENIOR REACTOR OPERATOR                     Page 57 WER    001  (1.00) a.oc b


==REFERENCE:==
==REFERENCE:==
: 1.  'echnical    Speci.fication 4.3.B.3..a 2~    OPL171.006, Ob)      14 3~    K/A: 201003G001 (3 6/3 7) 201003G001        .. (KA's)
ANSWER:    QQ2  (1. 00) b.
REFERENCE-OPL171.006, Obj.
201001K303 (3 ~ 1/3 2) 13'/A
                                  ~
201001K303        .. (KA's)
ANSWER:    003    (1. 00) b.


~~~OPL171.007, Obj.8, page 21~K/A 202002K305 (3'/3')202002K305
d%.i SENIOR REACTOR OPERATOR                  Page 58
~.(KA s)ANSWER: 013 (1.00)a~


==REFERENCE:==
==REFERENCE:==


1.OPL171.042, Obj 6, page 33 2.K/A: 206000K204 (2.5/2.7)..(KA's)ANSWER: 014 (1.00)a~
Tech Spec 3.7.A.4 and bases OPL171.016 Obj. 4, 18, page 19 K/A: 223001G006 (3    '/4      0)
    '223001G006        .. (KA's)
ANSWER:     004  (1. 00) d.


==REFERENCE:==
==REFERENCE:==
: 1. OPL  171.029, Obj.9, pages 21, 26
: 2. K/A 201002A402 (3 5/3 5)
                              ~      ~
                        .. (KA's)
ANSWER:    005    (1. 00) a~


1.OPL171.042, Obj.4, page 8 2~K/A: 206000K419 (3.7/3~8)206000K419
==REFERENCE:==
..(KA s)ANSWER: 015 (1.00)a~
: 1. OPL171.009, Obj. 5, page 12 2 ~   K/A: 239002K605 (3. 0/3. 2) 239002K605        .. (KA's)
0 SENIOR REACTOR OPERATOR Page 62
ANSWER:     006    (1.00)
 
d.
SENIOR REACTOR OPERATOR Page 59


==REFERENCE:==
==REFERENCE:==


4~Tech Spec 3.3.A.2.f OPL171.024, Obj.7 AOI 85-4 K/A: 214000G011 (3.1/4')214000G011
OI-71, Precaution 3.23    ~
..(KA's)ANSWER: 016 (1.00)b.
OPL171.037, Obj. 11
                                    '/3 ')
                                ~
                                  ~
3 ~    K/A: 263000G005 (3       ~    ~
263000G005          .. (KA's)
ANSWER         007    ( 1. 0,0)


==REFERENCE:==
==REFERENCE:==
: 1.      OPL171.044, Obj. 11, page 27 2      K/A: 226001A403 (3. 5/3. 4) 226001A403          .. (KA's)
ANSWER:        008    (1. 00) co


1.OPL171.045, Obj.8, page 14 2 K/A: 209001K404 (3 0/3')209001K404
==REFERENCE:==
..(KA's)ANSWER: 017 (1.00)b.
: 1.     OPL171. 044, Ob j . 14, page 29 2 ~    K/A: 203000K601 (3.6/3.7) 203000K601          .. (KA's)
ANSWER:       009  (1.00)
 
SENZOR REACTOR OPERATOR                  Page 60


==REFERENCE:==
==REFERENCE:==


1.OPL171.045, Obj.2a, page 20 2-K/A: 209001K408 (3.8/4~0)209001K408
OPL171.043, Obj.~ 4, pages 9, 10
..(KA's)ANSWER: 018 (1.00)
                ~
SENIOR REACTOR OPERATOR d.)Page 63 OPL171.017, Obj.7, page 14 OPL171.045, Obj.2b, page 12 K/A: 223002A102 (3~7/3~7)''223 002A102..(KA's)ANSWER: 019 (1.00)b.REFERENCE 1.OPL171.Q17, Obj.7, page 13 2 K/A: 223002K101 (3.8/3 9)..(KA's)ANSWER: 020 (1.QQ)Co
    ~   K/A: 218000K501 (3. 8/3.~ 8) 218000K501      ..(KA's)
ANSWER       010  (1.00) ci


==REFERENCE:==
==REFERENCE:==
: 1. Technical Specification 4.6.E.1 2.
3 ~    K/A: 2020016005    (3 '/4 ')
OPL171.007, Obj. 32, page 54 202001G005      ..(KA's)
ANSWER:      011  (1 00) ci


1 OPL171~009s Ob3~14 2.OPL171.017, Obj.6, page 19 3~K/A: 239001A212 (4.2/4.3)239001A212
==REFERENCE:==
..(KA's)ANSWER: 021 (1.00)  
: 1. OPL171.007, Obj. 31, pages 54, 34
: 2. OZ-68, page 6 3 ~   K/A: 202002G010    (3.3/3.3) 2020026010      .. (KA's)
ANSWER:     012  (1. 00)


SENIOR REACTOR OPERATOR d.)Page 64
SENIOR REACTOR OPERATOR               Page 61


==REFERENCE:==
==REFERENCE:==


Tech Spec 4.4.A.2.b OPL171.039, Obg.10 K/A: 211000G005 (3.6/4')'211000G005
    ~
..(KA's)ANSWER: 022 (1.00)co REFERENCE 1.OPL171.039, Obg.6, page 21 2 K/A: 211000A308 (4 2/4.2)..(KA's)ANSWER: 023 (1.00)b.
OPL171.007,
                ~
K/A 202002K305 (3   '/3 ')
Obj.~ 8, page 21
                                  ~
202002K305      ~ .(KA s)
ANSWER:     013  (1.00) a~


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.042, Obj 6, page 33
: 2. K/A: 206000K204 (2.5/2.7)
                      .. (KA's)
ANSWER:    014  (1.00) a~


1.OPL 171.053, Rev 3, p.13 of 46, Obj.6 2~K/A: 234000K502 (F 1/3.7)234000K502
==REFERENCE:==
..(KA's)ANSWER: 024 (1.00)b.
: 1. OPL171.042, Obj. 4, page 8 2 ~   K/A: 206000K419 (3. 7/3 ~ 8) 206000K419      .. (KA s)
ANSWER:     015  (1. 00) a~


SENIOR REACTOR OPERATOR d.)Page 65
0 SENIOR REACTOR OPERATOR             Page 62


==REFERENCE:==
==REFERENCE:==


~~~T.S.1.0, item S, p.1.0-7 K/A: 234000G011 (2.8/3 9*)234000G011
Tech Spec 3.3.A.2.f OPL171.024, Obj.7 4 ~
..(KA's)ANSWER: 025 (1 00)a~
AOI 85-4 K/A: 214000G011 (3.1/4  ')
214000G011      .. (KA's)
ANSWER:     016  (1.00) b.


==REFERENCE:==
==REFERENCE:==


1.OPL171.033, Rev 4, p.21 of 62 2~K/A: 288000K105 (3 3/3')..(KA's)ANSWER: 026 (1 00)a~
1.
2                              ')
OPL171.045, Obj. 8, page 14 K/A: 209001K404 (3 0/3 209001K404      .. (KA's)
ANSWER:     017  (1. 00) b.


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.045, Obj. 2a, page 20 2-    K/A: 209001K408 (3. 8/4 0)
                                ~
209001K408      ..(KA's)
ANSWER:    018  (1.00)


1.OPL171.038, Obj.5, page 17 OF 75 2.K/A 262001K401 (3.0/3.4)262001K401
d.)
..(KA's)ANSWER: 027 (1.00)a~
SENIOR REACTOR OPERATOR                Page 63 OPL171.017, Obj. 7, page 14 OPL171.045, Obj. 2b, page 12 K/A: 223002A102 (3 ~ 7/3 ~ 7)
d.SENXOR REACTOR OPERATOR Page 66
    ''223 002A102        .. (KA's)
ANSWER:      019    (1. 00) b.
REFERENCE
: 1.     OPL171.Q17, Obj. 7, page 13 2       K/A: 223002K101 (3.8/3 9)
                          .. (KA's)
ANSWER:       020    (1. QQ)
Co


==REFERENCE:==
==REFERENCE:==


~~~~~~OPL171.038, Obj.12, page 60 K/A 264000K506 (3 4/3 5)264000K506
1      OPL171 ~ 009s  Ob3 ~ 14
..(KA's)ANSWER: 028 (1 00)Co
: 2.      OPL171.017, Obj. 6, page 19 3 ~    K/A: 239001A212 (4.2/4.3) 239001A212        .. (KA's)
ANSWER:       021    (1. 00)
 
d.)
SENIOR REACTOR OPERATOR                          Page 64


==REFERENCE:==
==REFERENCE:==


1.OPL171.036, REV 2, Obj.12, page 19 of 37 2~K/A 263000K101 (3'/3.5)..(KA~s)ANSWER: 029 (1.00)Ce
Tech Spec 4.4.A.2.b OPL171.039, Obg. 10 K/A: 211000G005 (3.6/4      ')
    '211000G005        .. (KA's)
ANSWER:      022  ( 1. 00) co REFERENCE
: 1. OPL171.039, Obg. 6, page 21 2     K/A: 211000A308 (4 2/4.2)
                        .. (KA's)
ANSWER:     023  (1. 00) b.


==REFERENCE:==
==REFERENCE:==
: 1. OPL  171.053, Rev 3, p. 13 of 46, Obj. 6 2 ~    K/A: 234000K502 (F 1/3.7) 234000K502        .. (KA's)
ANSWER:      024  (1.00) b.


1.OPL171.067, Obj.11, 27 2~K/A: 290001K107 (3~0/3~1)290001K107
d.)
..(KA's)ANSWER: 030 (1.00)b.
SENIOR REACTOR OPERATOR                       Page 65
SENXOR REACTOR OPERATOR Page 67


==REFERENCE:==
==REFERENCE:==


~~~~OPL171.049, Obj.2,5, Page 45 K/A: 286000A105 (3.2/3.2)286000A105
T.S. 1.0, item S, p. 1.0-7
..(KA's)ANSWER: 031 (1.00)'.
              ~              ~
K/A: 234000G011 (2.8/3 9*)
                            ~
234000G011      .. (KA's)
ANSWER:     025  (1 00) a~


==REFERENCE:==
==REFERENCE:==


1.OPL171.011, Obj~4 2 K/A: 256000K107 (2~9/2 9)..(KA's)ANSWER: 032 (1.00)Co REFERENCE 1.OPL171.044, Obj.9 2~K/A: 203000K202 (2.5/2.7)203000K202
1.
..(KA's)ANSWER: 033 (1~00)b.
2 ~
SENIOR REACTOR OPERATOR d%.i Page 68
OPL171.033, Rev 4, p. 21 K/A: 288000K105 (3 3/3    ') of 62
                      ..(KA's)
ANSWER:   026  (1 00) a~


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.038, Obj. 5, page 17      OF 75
: 2. K/A 262001K401 (3.0/3.4) 262001K401      ..(KA's)
ANSWER:    027  (1. 00) a~


Tech Spec 3.5.B.11 OPL171~044, Obj 20 K/A 203000G005 (3'/4 4)'203000G005
d.
..(KA's)ANSWER: 034 (1.00)c~
SENXOR REACTOR OPERATOR                          Page 66


==REFERENCE:==
==REFERENCE:==
~
OPL171.038,
              ~    Obj.~ 12, page 60
                        ~
K/A 264000K506 (3 ~ 4/3 ~ 5) 264000K506      .. (KA's)
ANSWER:    028  (1 00)
Co


1.OPL171.016, Obj.13, page 47 2~K/A 272000A201 (3.7/F 1)..(KA's)ANSWER: 035 (F 00)8~
==REFERENCE:==
: 1. OPL171.036, REV 2, Obj. 12, page 19 of 37 2 ~   K/A 263000K101 (3 '/3.5)
                      ..(KA~s)
ANSWER:     029  (1.00)
Ce


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.067, Obj. 11, 27 2 ~  K/A: 290001K107 (3 0/3 1)
                              ~    ~
290001K107      ..  (KA's)
ANSWER:    030  (1. 00) b.


1.OPL171.033, Obj.1 2.K/A: 272000K402 (3.7/4.1)272000K402
SENXOR REACTOR OPERATOR                     Page 67
..(KA's)ANSWER: 036 (1.00)
SENIOR REACTOR OPERATOR d%.)Page 69


==REFERENCE:==
==REFERENCE:==
              ~
OPL171.049,
              ~      Obj.~    2,5, Page 45 K/A: 286000A105        (3.2/3.2)
                                    ~
286000A105        ..(KA's)
ANSWER:    031  (1. 00)


~~~~OPL171.013, Obj.11 K/A: 204000K106 (2'/2 8)204000K106
==REFERENCE:==
..(KA's)ANSWER: 037 (1.00)Ce
: 1. OPL171. 011, Obj ~ 4 2    K/A: 256000K107 (2 ~ 9/2 9)
                      .. (KA's)
ANSWER:    032  (1. 00)
Co REFERENCE
: 1. OPL171.044, Obj. 9 2 ~  K/A: 203000K202 (2. 5/2. 7) 203000K202        ..(KA's)
ANSWER:   033  (1 ~ 00) b.
 
d%.i SENIOR REACTOR OPERATOR Page 68


==REFERENCE:==
==REFERENCE:==


1.OPL171.012, Rev 4, p.30 of 55 2~K/A: 216QOOK312 (3 7/F 8)..(KA's)ANSWER: 038 (1.00)b.
Tech Spec 3.5.B.11 OPL171 044, Obj 20
                                    '/4
                    ~
K/A 203000G005 (3             4)
        '203000G005          .. (KA's)
ANSWER:         034    (1. 00) c  ~


==REFERENCE:==
==REFERENCE:==
: 1.      OPL171.016, Obj. 13, page 47 2 ~      K/A 272000A201 (3.7/F 1)
                              .. (KA's)
ANSWER:          035    (F 00) 8~


2~OPL171.012, Rev 5, Obj.6, page 24 of 55 K/A: 259002K6Q4 (3'/3 1)259002K604
==REFERENCE:==
..(KA's)ANSWER: 039 (1.00)Co SENIOR REACTOR OPERATOR Page 70 2-0I-3, Rev 23, Precaution 3.1 2-AOI-3-1, Rev 7, 3.1, 3.2 K/A: 259001A310 (3.4/3.4)'259001A310
: 1.      OPL171.033, Obj. 1
..(KA's)ANSWER:.040 (1.00)
: 2.       K/A: 272000K402 (3.7/4. 1) 272000K402          ..(KA's)
ANSWER:         036    (1. 00)
 
d%.)
SENIOR REACTOR OPERATOR                          Page 69


==REFERENCE:==
==REFERENCE:==


1.EOIPM Section II-B, Operator Cautions, page 4 2 K/A 216000K507 (3.6/3.8)216000K507
OPL171.013, Obj.~ 11
..(KA's)ANSWER: 041 (1.00)d.
    ~
                ~
K/A: 204000K106 (2  '/2
                            ~      8) 204000K106      ..(KA's)
ANSWER:     037  (1. 00)
Ce


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.012, Rev 4, p. 30 of 55 2~    K/A: 216QOOK312 (3 7/F 8)
                      .. (KA's)
ANSWER:    038  (1.00) b.


1~SSP 2.8, REV 003s p.9 of 37 2.K/A: 294001A101 (2.9/3~4)294001A101
==REFERENCE:==
..(KA's)ANSWER: 042 (1.00)
SENIOR REACTOR OPERATOR Page 71


==REFERENCE:==
OPL171.012, Rev 5, Obj. 6, page 24 of 55 2 ~    K/A: 259002K6Q4 (3  '/3    1) 259002K604      .. (KA's)
ANSWER:    039  (1. 00)
Co


~~~RCI-2, VOL-1, p.3 K/A: 294001K103 (3 3/3.8)294001K103
SENIOR REACTOR OPERATOR                                  Page 70 2-0I-3,  Rev 23, Precaution 3.1 2-AOI-3-1, Rev 7, 3.1, 3.2 K/A: 259001A310 (3.4/3.4)
..(KA's)ANSWER: 043 (1.00)b.
    '259001A310        .. (KA's)
ANSWER:   . 040  (1. 00)


==REFERENCE:==
==REFERENCE:==
 
: 1. EOIPM  Section  II-B, Operator Cautions, page 4 2     K/A 216000K507      (3.6/3.8) 216000K507        .. (KA's)
1.SSP-12.1, REV.0008, p.77 of 95 2~K/A 294001A109 (3'/4')..(KA's)ANSWER: 044 (1 00)C~
ANSWER:     041  (1. 00) d.


==REFERENCE:==
==REFERENCE:==


1.SSP-1.7, REV 0001, p.3 of 5 2 KA: 294001A109 (3 3/4.2)294001A109
1~  SSP 2.8, REV 003s p. 9 of 37
..(KA s)'NSWER: 045 (1.00)  
: 2. K/A: 294001A101 (2. 9/3 4) ~
294001A101        ..(KA's)
ANSWER:     042  (1. 00)


SENIOR REACTOR OPERATOR Page 72
SENIOR REACTOR OPERATOR                       Page 71


==REFERENCE:==
==REFERENCE:==


RCI-2, REV 0020, p.6 EPIP 15, section 3.1 K/A: 294001K103 (3'/3')'294001K103
RCI-2, VOL-1, p.3 ~
..(KA's)ANSWER 046 (1.00)b.
K/A: 294001K103 (3 ~ 3/3.8) ~
294001K103       .. (KA's)
ANSWER:    043  (1.00) b.


==REFERENCE:==
==REFERENCE:==
 
: 1. SSP-12.1, REV. 0008, p. 77      of 2 ~   K/A 294001A109 (3   '/4 ')         95
1.RCI-13, page 5 2~K/A: 294001K114 (3.2/3.4)..(KA s)ANSWER 047 (1.00)a.or 3
                        .. (KA's)
ANSWER:    044  (1 00)
C~


==REFERENCE:==
==REFERENCE:==
: 1. SSP-1.7,  REV  0001, p. 3  of 5 2    KA: 294001A109    (3  3/4.2) 294001A109      .. (KA s)
'NSWER:      045  (1. 00)


1.SSP 12.6, page 7 2.OI VOL-13, O-GOI-300-3, p.7 of 10 3~K/A: 294001K101 (3'/3')294001K101
SENIOR REACTOR OPERATOR                   Page 72
..(KA's)ANSWER 048 (1.00) 0 0 SENIOR REACTOR OPERATOR d5.Page 73


==REFERENCE:==
==REFERENCE:==


~~SSP-12.6, REV 0001, p.4 of 20 and p.7 of 20 K/A: 294001K101 (3.7/3 7)4 294001K101
RCI-2, REV 0020, p. 6 EPIP 15, section 3.1 K/A: 294001K103 (3   '/3 ')
..(KA's)ANSWER 049 (1 00)a~REFERENCE 1.Safety and Health Manual, p.VII-74 and 75 2 K/A: 294001K114 (3.2/3.4)294001K114
    '294001K103      .. (KA's)
..(KA's)ANSWER: 050 (1.00)C~
ANSWER     046  (1. 00) b.


==REFERENCE:==
==REFERENCE:==
: 1. RCI-13, page 5 2 ~    K/A: 294001K114 (3.2/3.4)
                      ..(KA s)
ANSWER      047  (1.00)
: a. or 3


1.Safety and Health Manual, p.VII-135 2~K/A: 294001A110 (3'/4')294001A110
==REFERENCE:==
..(KA's)ANSWER: 051 (1 00)d.
: 1. SSP 12.6, page 7 OI VOL-13, O-GOI-300-3, p. 7 of 2.
SENIOR REACTOR OPERATOR d.i Page 74
3 ~   K/A: 294001K101 (3   '/3 ')     10 294001K101        .. (KA's)
ANSWER     048  (1. 00)


==REFERENCE:==
0 0


~~~SSP-12.1, REV'0008, p.34 of 95 K/A: 294001A111 (3.3/4 3)294001A111
d5.
..(KA's)ANSWER: 052 (1.00)a e REFERENCE 1.EPZP 16, page 1 2~K/A: 294001A116 (2'/4')..(KA's)ANSWER: 053 (F 00)OL
SENIOR REACTOR OPERATOR                                Page 73


==REFERENCE:==
==REFERENCE:==


1.SSP 1.6, REV 002, p.5 of 53 2~K/A 294001K105 (3~2/3~7)294001K105
SSP-12.6,
..(KA's)ANSWER: 054 (1.00)
              ~  REV 0001, p. 4 of 20 and p.
SENIOR REACTOR OPERATOR 8.)Page 75
                                ~             7 of 20 K/A: 294001K101 (3.7/3 7) 4 294001K101        .. (KA's)
ANSWER      049  (1 00) a~
REFERENCE
: 1. Safety and Health Manual, p. VII-74 and  75 2    K/A: 294001K114 (3.2/3.4) 294001K114        ..(KA's)
ANSWER:     050  (1.00)
C~


==REFERENCE:==
==REFERENCE:==


~~~~SSP<<12.3, REV 0008, p.19 of 105 K/A: 294001K109 (3'/3')294001K109
Safety and Health Manual, p. VII-135 1.
..(KA s)ANSWER: 055 (1.00)C~
2 ~  K/A: 294001A110 (3   '/4 ')
294001A110        ..(KA's)
ANSWER:     051  (1 00) d.
 
d.i SENIOR REACTOR OPERATOR                  Page 74


==REFERENCE:==
==REFERENCE:==


1.T.S.3.6.B Basis 2~K/A: 294001A114 (2'/3')294001A114
SSP-12.1, REV '0008, p. 34 of 95
..(KA's)ANSWER: 056 (1.00)b.
                ~                ~
K/A: 294001A111 (3.3/4 ~ 3) 294001A111      .. (KA's)
ANSWER:      052  (1. 00) ae REFERENCE 1.
2 ~
EPZP  16, page 1 K/A: 294001A116 (2   '/4 ')
                      .. (KA's)
ANSWER:     053  (F 00)
OL


==REFERENCE:==
==REFERENCE:==
: 1. SSP 1.6, REV 002, p. 5 of 53 2 ~  K/A 294001K105 (3 2/3 7)
                            ~    ~
294001K105        ..(KA's)
ANSWER:      054  (1. 00)


1.BNF-EPIP-3, p.2 2~K/A: 294001A116 (2'/4')294001A116
8.)
..(KA's)ANSWER: '057 (1.00)b.
SENIOR REACTOR OPERATOR                     Page 75
SENIOR REACTOR OPERATOR d%.Page 76


==REFERENCE:==
==REFERENCE:==


l OPL171 204, Obj~5 K/A: 295036G012 (3.5/3.9)295036G012
of
..(KA's)ANSWER: 058 (1~00)d.
  ~
SSP<<12.3,
              ~   REV K/A: 294001K109 (3     '/3 ')
0008, p. 19
                                ~
                                  ~
105 294001K109        .. (KA s)
ANSWER:     055  (1. 00)
C~


==REFERENCE:==
==REFERENCE:==


1.OPL171.202, Obj.13 2~K/A: 295037G007 (3 7/3')..(KA's)ANSWER: 059 (1.00)b.
T.S.3.6.B Basis 1.
2 ~   K/A: 294001A114 (2    '/3 ')
294001A114        .. (KA's)
ANSWER:     056  (1. 00) b.


==REFERENCE:==
==REFERENCE:==


1.OPL171.205, Obj.7b 2.K/A: 295015G012 (3.7/4.4)295015G012
1.
..(KA's)ANSWER: 060 (F 00)d.  
2~
BNF-EPIP-3, p. 2 K/A: 294001A116 (2    '/4 ')
294001A116        ..(KA's)
ANSWER:   '057  ( 1. 00) b.


SENIOR REACTOR OPERATOR B,)Page 77 REFERENCE':
d%.
t OPL171.074, Obj.1 K/A: 295003A204 (3.4/3.5)295003A204
l SENIOR REACTOR OPERATOR Page 76
..(KA's)ANSWER: 061 (1~00)b.


==REFERENCE:==
==REFERENCE:==


1.OPL171.202, Obj.8 2.K/A: 295025A105 (3.7/3.7)295025A105
OPL171 204, Obj     ~  5 K/A: 295036G012        (3. 5/3. 9) 295036G012          ..(KA's)
..(KA's)ANSWER: 062 (1.00)c.or b
ANSWER:       058  (1 ~ 00) d.


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.202, Obj. 13 2  ~    K/A: 295037G007 (3 7/3          ')
                            ..(KA's)
ANSWER:        059  (1. 00) b.


1.EPIP-1,"Emergency Classification Flowchart 2~K/A: 2950166002 (2 9/4')295016G002
==REFERENCE:==
..(KA's)ANSWER: 063 (1~00)
: 1. OPL171.205, Obj. 7b
SENIOR REACTOR OPERATOR Page 78
: 2.      K/A: 295015G012 (3. 7/4. 4) 295015G012          .. (KA's)
ANSWER:       060  (F 00) d.
 
B,)
SENIOR REACTOR OPERATOR                           Page 77 t
REFERENCE':
OPL171.074, Obj. 1 K/A: 295003A204 (3.4/3.5) 295003A204        ..(KA's)
ANSWER:    061  (1 ~ 00) b.


==REFERENCE:==
==REFERENCE:==
 
: 1. OPL171.202, Obj.      8
t OPL171~202 t Ob)~14 K/A: 295037G007 (3.5/3.7)295037G007
: 2. K/A: 295025A105      (3.7/3.7) 295025A105        ..(KA's)
..(KA's)ANSWER: 064 (1.00)b.
ANSWER:     062  (1. 00)
: c. or b


==REFERENCE:==
==REFERENCE:==


1.AOI 47-2, page 3 2~K/A 295020G010 (3'/3')295020G010
EPIP-1, "Emergency Classification Flowchart 1.
..(KA's)ANSWER: 065 (1.00)C~REFERENCE 1.OPL17 1~054, Ob)3 2.K/A: 295019G011 (3'/4.1)295019G011 (KA')ANSWER:,.066 (l.00)b.
2 ~   K/A: 2950166002 (2 9/4      ')
295016G002        .. (KA's)
ANSWER:     063  (1 ~ 00)


SENIOR REACTOR OPERATOR dS.i Page 79
SENIOR REACTOR OPERATOR                 Page 78 t


==REFERENCE:==
==REFERENCE:==


EOI Appendix 3B K/A: 295037K213 (3.4/4.1)295037K213
OPL171 ~ 202 t Ob)
..(KA's)ANSWER: 067 (1.00)c
K/A: 295037G007
                          ~  14 (3. 5/3. 7) 295037G007        ..(KA's)
ANSWER:     064    (1. 00) b.


==REFERENCE:==
==REFERENCE:==


1.EOI Appendices 1A, 1B, 1C, 1E 2~K/A 295015K201 (3.8/3')J II 295015K201
AOI 47-2, page 3 1.
..(KA's)WER: 068 (1~00)
2 ~   K/A 295020G010 (3       '/3 ')
295020G010        .. (KA's)
ANSWER:     065    (1.00)
C~
REFERENCE
: 1. OPL17 1 ~ 054, Ob)    3
: 2. K/A: 295019G011 (3 '/4.1) 295019G011            (KA')
ANSWER:,. 066      (l. 00) b.
 
dS.i SENIOR REACTOR OPERATOR                  Page 79


==REFERENCE:==
==REFERENCE:==


1.Tech Spec 3.7.C 2.K/A: 295033K204 (3.9/4.2)295033K204
EOI Appendix 3B K/A: 295037K213 (3.4/4.1) 295037K213          ..(KA's)
..(KA's)ANSWER: 069 (1~00)b.
ANSWER:         067 ( 1. 00) c
SENIOR REACTOR OPERATOR d%..Page 80


==REFERENCE:==
==REFERENCE:==


Primary Containment Control bases manual, page 47 K/A: 295024K304 (3.7/4.1)295024K304
1.
..(KA's)ANSWER: 070 (1.00)a 0
2 ~
EOI Appendices 1A, 1B, 1C, 1E K/A 295015K201 (3.8/3 II J
                                      ')
295015K201          ..(KA's)
WER:       068 (1~  00)


==REFERENCE:==
==REFERENCE:==
: 1. Tech Spec 3.7.C
: 2. K/A: 295033K204      (3.9/4.2) 295033K204          .. (KA's)
ANSWER:        069 (1 00)
                      ~
b.


1.OPL171.032, Obj.11, page 26 2~K/A: 295017G007 (3.2/3~6)295017G007
d%..
..(KA's)ANSWER: 07 1 (1.00)d.
SENIOR REACTOR OPERATOR                                  Page 80


==REFERENCE:==
==REFERENCE:==


1.AOX 70-1, Attachment 1 2~K/A: 295018K101 (3.5/3')295018K101
Primary Containment Control bases manual, page 47 K/A: 295024K304 (3.7/4.1) 295024K304        .. (KA's)
..(KA's)ANSWER 072 (1.00)
ANSWER:      070  (1. 00) a0
SENIOR REACTOR OPERATOR B:)Page 81 REFERENCE Technical Specification 3.7.A.l.d 295013G008 (3 5/4.4)'295013G008
 
..(KA's)ANSWER 073 (1.00)c~
==REFERENCE:==
: 1. OPL171.032, Obj. 11, page 26 2~    K/A: 295017G007      (3. 2/3 6)
                                      ~
295017G007        ..(KA's)
ANSWER:      07 1  ( 1. 00) d.


==REFERENCE:==
==REFERENCE:==


1.EOI-2, Primary Containment Control bases, page 145 2 K/A: 295029K201 (3 0/3')295029K201
70-1, Attachment 1 1.
..(KA s), ANSWER: 074 (1-00)a~
2 ~
AOX K/A: 295018K101 (3.5/3       ')
295018K101        .. (KA's)
ANSWER       072  (1. 00)
 
B:)
SENIOR REACTOR OPERATOR                                    Page 81 REFERENCE Technical Specification 3.7.A.l.d 295013G008 (3 5/4.4)
        '295013G008        .. (KA's)
ANSWER        073  (1. 00) c ~


==REFERENCE:==
==REFERENCE:==
: 1. EOI-2, Primary Containment Control bases, 2      K/A: 295029K201 (3 0/3    ')              page 145 295029K201        .. (KA s)
, ANSWER:      074  (1- 00) a~


1.AOI 32-2, page 13-17 2.OPL171.054, Obj.5 3~K/A: 295019K209 (3.3/3.3)295019K209
==REFERENCE:==
..(KA's)ANSWER: 075 (1.00)  
: 1. AOI 32-2, page 13-17
: 2. OPL171.054, Obj. 5 3 ~   K/A: 295019K209 (3.3/3.3) 295019K209       ..(KA's)
ANSWER:       075   (1. 00)


SENIOR REACTOR OPERATOR Page 82 AOI 32-2, page 13-17 OPL171.054, Obj~5 K/A: 295019A202 (3.6/3 7)295019A202
SENIOR REACTOR OPERATOR                 Page 82 AOI 32-2, page 13-17 OPL171.054, Obj ~ 5 K/A: 295019A202 (3.6/3 7) 295019A202       .. (KA's)
..(KA's)ANSWER 076 (1.00)Co  
ANSWER     076 (1. 00)
Co


==REFERENCE:==
==REFERENCE:==


1.EOI-1, RPV Control Bases, page 33 2~K/A: 295007K304 (4'/4')295007K304
EOI-1, RPV Control Bases, page 33 1.
..(KA s)ANSWER: 077 (1.00)
2 ~   K/A: 295007K304 (4   '/4 ')
295007K304       .. (KA s)
ANSWER:   077   (1.00)


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.003, Obj.13, page 24 2 ~                          f K/A: 295009A201 (4 ~ 2 4 2) 295009A201      .. (KA's)
ANSWER:    078  (1. 00)


1.OPL171.003, Obj.13, page 24 2~K/A: 295009A201 (4~2 f 4 2)295009A201
0 d.i SENIOR REACTOR OPERATOR                                     Page 83
..(KA's)ANSWER: 078 (1.00) 0 SENIOR REACTOR OPERATOR d.i Page 83  


==REFERENCE:==
==REFERENCE:==


AOI 74-1 OPL171.046, Obj.13 K/A: 295021K102 (3~3/3~4)'295021K102
AOI 74-1 OPL171.046, Obj. 13 K/A: 295021K102 (3 ~ 3/3 ~ 4)
..(KA's)ANSWER: 079 (1 00)d.
    '295021K102       .. (KA's)
ANSWER:       079 (1 00) d.


==REFERENCE:==
==REFERENCE:==
: 1. 2-AOI-85-3 Rev 10, p 2 of    5 (immediate actions) 2~    K/A: 295022G010 (F 7/3.5) 295022G010        .. (KA's)
REFERENCE 2-AOI-100-2, Note, Rev 2 Page 14    of  55
: 2. OPL171-040 Objective 4 3 ~    K/A: 295016K303 (3.5/3.7) 295016K303        .. (KA's)
ANSWER:        081 (1 00)
                    ~


1.2-AOI-85-3 Rev 10, p 2 of 5 (immediate actions)2~K/A: 295022G010 (F 7/3.5)295022G010
d.i SENIOR REACTOR OPERATOR                 Page 84
..(KA's)REFERENCE'.2-AOI-100-2, Note, Rev 2 Page 14 of 55 2.OPL171-040 Objective 4 3~K/A: 295016K303 (3.5/3.7)295016K303
..(KA's)ANSWER: 081 (1~00)
SENIOR REACTOR OPERATOR d.i Page 84  


==REFERENCE:==
==REFERENCE:==


~~~~Facility Question Bank 410526~K/A: 295026G007 (3'/3.8)295026G007
Facility
..(KA's)ANSWER: 082 (1~00)a~
              ~
Question Bank 410526
                          ~
  ~   K/A: 295026G007         '/3.8)
(3 ~    ~
295026G007         .. (KA's)
ANSWER:     082   (1 ~ 00) a~


==REFERENCE:==
==REFERENCE:==
: 1. OPL171.074  Objective      2 2-AOI-66-2 Rev 8, 4.1 2.
3 ~  K/A: 295017G010 (3      '/3 ')
                        .. (KA's)
ANSWER:    083  (1.00) b.


1.OPL171.074 Objective 2 2.2-AOI-66-2 Rev 8, 4.1 3~K/A: 295017G010 (3'/3')..(KA's)ANSWER: 083 (1.00)b.
==REFERENCE:==
: 1. Facility  Question Bank 411043 OPL171.007 Objective 12 2.
3 ~   K/A: 295005K302 (3       '/3 ')
295005K302        .. (KA's)
ANSWER:     084  (1. 00)
 
d.i SENIOR REACTOR OPERATOR                                  Page 85 t


==REFERENCE:==
==REFERENCE:==


1.Facility Question Bank 411043 2.OPL171.007 Objective 12 3~K/A: 295005K302 (3'/3')295005K302
                              '/3 ') of 37, OPL 171.036, Rev 2 p. 18 K/A 295003A101 (3 Objective  12 I
..(KA's)ANSWER: 084 (1.00)  
295003A101        .. (KA's)
ANSWER:     085  (1. 00)


SENIOR REACTOR OPERATOR d.i Page 85
==REFERENCE:==
: 1.      OPL 171.005, Rev 4, p. 39    of 58, Objective  6 2 ~    K/A: 295015K201 (3 8/3 9)
                            ~    ~
295015K201        ..(KA's)
ANSWER:      086  (1. 00) b.


==REFERENCE:==
==REFERENCE:==


t OPL 171.036, Rev 2 p.18 of 37, Objective 12 K/A 295003A101 (3'/3')295003A101 I..(KA's)ANSWER: 085 (1.00)
1-AOI-57-5A, Rev 10, Cautions, p.     of
                            '/3 ')
: 1.    ,                                      3    44 2 ~    K/A: 295003G007 (3 295003G007        ..(KA's)
ANSWER      087  (1. 00)
Co
 
d.)
SENIOR REACTOR OPERATOR                              Page 86 REFERENCE flowcharts EOI K/A: 295034G011 (4.2/4    ')
295034G011        .. (KA's)
ANSWER:    088  (1. 00) b.
 
==REFERENCE:==
: 1. 2-AOI-68-1, Rev 15,    Cauter.on, p. 3 of 11 2.
2 ~
OPL171.074, Obj. 22
      .K/A 295001A201    (3 5/3 ')
                      .. (KA's)
ANSWER:     089  (1 00)
Co


==REFERENCE:==
==REFERENCE:==
: 1. 2-AOI-70-1, Rev 12, p. 2 of 6, 4.1
: 2. K/A: 295018G010 (3.4/3.3) 295018G010        .. (KA s)
ANSWER:    090  (l. 00) b.


1.OPL 171.005, Rev 4, p.39 of 58, Objective 6 2~K/A: 295015K201 (3~8/3~9)295015K201
0 B.i SENIOR REACTOR OPERATOR                Page 87
..(KA's)ANSWER: 086 (1.00)b.


==REFERENCE:==
==REFERENCE:==


1., 1-AOI-57-5A, Rev 10, Cautions, p.3 of 44 2~K/A: 295003G007 (3'/3')295003G007
2-AOX-78-1, Rev 7.
..(KA's)ANSWER 087 (1.00)Co d.)SENIOR REACTOR OPERATOR Page 86 REFERENCE EOI flowcharts K/A: 295034G011 (4.2/4')295034G011
K/A: 2950236006 (3 4/3 6) 295023G006        ..(KA's)
..(KA's)ANSWER: 088 (1.00)b.
ANSWER:    091  (1. 00)
Co REFERENCE OPL171.028, Rev 5, Table 1 1.
2 ~  K/A: 295006K201 (4   '/4 ')
295006K201        .. (KA's)
ANSWER:   092  ( 1. 00) b.


==REFERENCE:==
==REFERENCE:==
: 1. OPL 171.028, Rev 5, p. 16 of 39
: 2. K/A: 295006A206 (3 '/3.8) 295006A206        ..(KA's)
ANSWER:    093  (1 00)


1.2-AOI-68-1, Rev 15, Cauter.on, p.3 of 11 2.OPL171.074, Obj.22 2~.K/A 295001A201 (3 5/3')..(KA's)ANSWER: 089 (1 00)Co
d.)
SENIOR REACTOR OPERATOR                                            Page 88 REFERENCE 2-AOI-100-1, Rev 26, Attachment 5.
EOI-2, Primary Containment Control, Rv 1, entry conditions K/A 295028G010 (3.9/3.6)
      '2950286010        .. (KA's)
ANSWER:       094  (1 00)
  'a ~


==REFERENCE:==
==REFERENCE:==
: 1.      EOI flowcharts: EOI-1, C-1, C-2, C-3.
2~      K/A: 295031A201 (4.6/4.6) 295031A201        ..(KA's)
ANSWER        095  ( 1. 00) ce


1.2-AOI-70-1, Rev 12, p.2 of 6, 4.1 2.K/A: 295018G010 (3.4/3.3)295018G010
==REFERENCE:==
..(KA s)ANSWER: 090 (l.00)b.
: 1.     OPL171.074, Obj. 5 2~      OPL171 009t Obj. 3
0 SENIOR REACTOR OPERATOR B.i Page 87
                ~
2~      K/A'95016A108 (4.0/4.0) 295016A108        ..(KA's)
ANSWER:       096  (1 00)
 
0 SENIOR REACTOR OPERATOR                             Page 89


==REFERENCE:==
==REFERENCE:==


2-AOX-78-1, Rev 7.K/A: 2950236006 (3 4/3 6)295023G006
I OPL171.044,
..(KA's)ANSWER: 091 (1.00)Co REFERENCE 1.OPL171.028, Rev 5, Table 1 2~K/A: 295006K201 (4'/4')295006K201
              ~
..(KA's)ANSWER: 092 (1.00)b.
K/A: 295021A207 (3 ~  '/3 ')
Obg.~ 19, pages 22, 24, 28
                                ~
295021A207        .. (KA's)
ANSWER:     097  (1.00)
Co
 
==REFERENCE:==
: 1. EOI, Appendix 18
: 2. OI 74, page 42
: 3. K/A: 295030G012 (3.7/4.4) 295030G012        .. (KA's)
ANSWER:     098  { 1. 00)
Co


==REFERENCE:==
==REFERENCE:==


1.OPL 171.028, Rev 5, p.16 of 39 2.K/A: 295006A206 (3'/3.8)295006A206
EPIP-1, Rev 13, Attachment 1, p. 1    of 1.
..(KA's)ANSWER: 093 (1 00)  
2 ~  K/A: 295023A202 (3   '/3 ')             12 295023A202        .. (KA's)
ANSWER:     099  (1. 00) b.


SENIOR REACTOR OPERATOR d.)Page 88 REFERENCE 2-AOI-100-1, Rev 26, Attachment 5.EOI-2, Primary Containment Control, Rv 1, entry conditions K/A 295028G010 (3.9/3.6)'2950286010
d5.
..(KA's)ANSWER: 094 (1 00)'a~
SENIOR REACTOR OPERATOR                                         Page 90 t


==REFERENCE:==
==REFERENCE:==


1.EOI flowcharts:
NP-REP, page 13, K/A: 294001A116 3.1.2 (2.9/4.7) 294001A116      .. (KA's)
EOI-1, C-1, C-2, C-3.2~K/A: 295031A201 (4.6/4.6)295031A201
ANSWER:    100  (1. 00)
..(KA's)ANSWER 095 (1.00)ce
Co


==REFERENCE:==
==REFERENCE:==


1.OPL171.074, Obj.5 2~OPL171~009t Obj.3 2~K/A'95016A108 (4.0/4.0)295016A108
EOI-1, RPV Control Bases, page 27.
..(KA's)ANSWER: 096 (1 00) 0 SENIOR REACTOR OPERATOR Page 89
1.
2~   K/A: 2950286004 (2.7/3    ')
295028G004      ..(KA's)
(**********  END OF EXAMINATION *****+****)


==REFERENCE:==
                      '55NESSEE VAILZYAUXKORXTY        '"-'-""
I QQOlTRC'~~:
BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE El'Il'-1 EMERGENCY PLAN  CLASSIFICATION LOGIC RKSIQN 13 PREPARED BY  T. W  CORNELIUS                      PHONE:    2038 RESPONSIBLE ORGANIZATION:    EMERGENCY PREPAREDNESS APPROVED BY:  T W. CORNELIUS                        DATE:    07/01/92 EFFECTIVE DATE:  OZ/09/92 VALIDATIONDATE: NOT REQUIRED QUALITY-RELATED


~~~~I OPL171.044, Obg.19, pages 22, 24, 28 K/A: 295021A207 (3'/3')295021A207
REVISION LOG Procedure Number:    EPIP-1 i Revision Number: 13
..(KA's)ANSWER: 097 (1.00)Co
. Pages. Affected:  15 Pagination Pages:    NONE Description of Change:
Change phone 0 from 236-1500 to 273-8500.


==REFERENCE:==
EMERGENCY  CLASSIFICATION LOGIC 1.0  PURPOSE 1.1    To provide guidance to the Shift Operations    Supervisor  (SOS)  or Site Emergency Director (SED) on what constitute's    an emergency classification.
      '1.2  To ensure that the emergency classification is consistent      with that used by the local and state governments and the NRC.
1.3  To  provide a cross reference between this procedure and the ONP-REP, Appendix A,    for use by the SOS or SED for additional information in
            'classifying events.
2.0  SCOPE 2.1  This procedure applies to those events, that in the professional judgment of the SOS or the SED constitutes an emergency.        The SOS and the SED are the only individuals authorized to make the emergency class determination.
2.2  The events  listed in the attachments to this procedure cannot possibly incorporate    all events which can occur. Therefore,    all classifications should    be judged  against the general guidance  listed below:
2.2.1  Notification of  Unusual Event Unusual events are  in process or have occurred which indicate a  potential degradation of the level of safety of the plant.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
2.2.2 Alert Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure  levels.
0300p


1.EOI, Appendix 18 2.OI 74, page 42 3.K/A: 295030G012 (3.7/4.4)295030G012
i Page 2 REV 00 ZS              BFN-EPIP-1 2.0  (Continued) 2.2'.3  Site. Area Emergency Events are  in  process or have occurred which involve actual rotection of the ublic. Any releases are not, expected to exceed EPA Protective Action Guideline exposure levels except near  site boundary-2.2e4  General 'Emergency Events are  in process or have occurred vhich invoive actual or imminent'suhstantial core de radation or meltin vith pbtential for loss of -containment inte rit . Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
..(KA's)ANSWER: 098{1.00)Co
3 0  INSTRUCTION 3.1  Review Attachment    1  'to determine  if an event should be classified as an emergency.
Note:   (1)  If an emergency action level for a higher classification was exceeded,    but the present situation indicates a lower classification, the fact that the higher classification occurred shall be reported to the NRC and the CECC (if staffed), but should not be declared. (2) If an emergency action level was met but the emergency has been totally resolved, the emergency class that was appropriate shall be declared and terminated at the same time.
s 3.1.1  Attachment  1  captures events  in four br'oad categories:
Fission Product Barrier Degradation (F)
System Malfunction (S)
Radiation Levels Abnormal/Radiological Effluents (R)
Hazards and Other Conditions Affecting Plant Safety (H) 3.1.2  Each actual condition in a category is given an alphanumeric designator (FU1 = Fission Product Barrier Degradation (F) resulting in Notification of Unusual Event (U) 01).
3.1.3  The  only significance of the alphanumeric designator is a cross-reference to ONP-REP, Appendix A, which provides additional information for the SOS/SED in classifying the event.
0300p


==REFERENCE:==
3.0  (Continued) 3.2  If the event is determined to be one of the four emergency classification, the SOS assumes the responsibilities of SED.
3.2.1    Implement one of the following procedures as applicable:
EPZP-2  - Notification of Unusual Event EPIP-3  - Alert EPIP-4  - Site Area Emergency EPPP-5  General  Emergency 3.2N2  Continue to review the emergency conditions in Attachment  1 to escalate, de-escalate or terminate the emergency as appropriate.
3.3  If the event is determined not to be one of the four emergency classifications, continue to monitor plant conditions.
4.0  ATTACHMENTS Attachment 1, Emergency Classification Flowchart [NER/C    NRC in 89-072]
0300p


1.EPIP-1, Rev 13, Attachment 1, p.1 of 12 2~K/A: 295023A202 (3'/3')295023A202
azv                P>s                          Page 4 BFN-EPIP-1 Index to Emer enc                          Classification Flow Chart DESCRIPTION                                                                                                    PAGE G I. Fission Product Barrier                    De      radation 4
..(KA's)ANSWER: 099 (1.00)b.  
A. Fuel Damage .                                                                                                          1 B. Primary System Leakage                                                                                                  1 C. Primary Coolant Break or Loss of Inventory                                                                  ~  ~      2 D.      Primary Containment Integrity .                                                                  ~      ~  ~  ~      2 E. Loss of Fission -Product Barriers                                                                            ~   ~      2 II. S  stem Malfunction A. Tech Spec LCO ~                                                                                            0  4      3 B. RPS/Core        ~    ~    ~ ~ ~      ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~      ~  ~  s      3 C. Thermal Power ~ ~ ~ ~ ~                            ~    ~    ~    ~    ~        ~    ~    ~    ~      ~  ~  0      3 D. Shutdown ~ ~ ~ ~ ~ ~ ~ ~                            ~    ~    ~    ~    ~    o    ~    ~    ~    ~      ~  ~  ~      2 E. Turbine and Condenser .                                                                                    ~  ~      3 F. AC Power        ~    A    . A A o . .              o    A    A    . .      A    .    ~                    ~  ~      4 G    DC Power        ~ ~ ~ ~ ~ ~              ~    ~    ~    ~    ~    ~    ~    o    ~    ~    ~    ~      ~              4 H.      Instrumentation, Controls, and Communications                                                                          5 III. Radiation Levels Abnormal/Radiolo ical/Effluents A. Radiological Effluents (Liquid)                                   . . . . . . . . . .                                  6 B.
C. Area Radiation                .. '............ ~...
Radiological Effluents (Gaseous)                                       . . . . . . . . .                              7 8
IV. Hazards and Other Conditions Affectin Plant Safet A. Security Threat .                                      ~    ~    ~    ~    ~    ~    ~    ~    ~      ~              9 B. Missiles or Aircraft                                    ~    ~    ~    ~    ~    ~    ~    ~    ~      ~              9 C. Injuries      ~    ~    ~  ~  ~  ~    ~    ~        ~    ~    ~    ~    ~    ~    ~    ~    ~      ~              10 D. Uncontrolled Toxic                Gases                ~    ~    ~    ~    ~    ~    ~    ~    ~      ~              10 E. Control Room                                            ~    ~    ~                                                  10 ll
                                                                                      ~    ~    ~    ~    ~    ~      ~
F. Earthquake                                              ~    ~    ~    ~    ~    ~    ~    ~    ~      ~
G. Flood ~ ~ ~          ~    ~  ~  .        ~    ~    ~  ~    ~    ~    ~  ~    ~  ~                                11 ll
                                                                                                          ~  ~      ~
H. Tornado . .          ~                                  ~    ~    ~    ~    ~    ~    ~    ~    ~
I. High Winds                                              ~    ~    ~    ~    ~    ~    ~    ~    ~
                                                                                                                      ~
                                                                                                                      ~              11 J. Low  Reservoir .                                      ~    ~    ~    ~    ~    ~    ~,  ~    ~      ~              12 K~    ~
Fire
                ~
                        ~ ~  ~    ~    ~  ~  ~  ~    ~    ~    o    ~    ~    ~    ~    ~    ~    ~    ~    ~      ~              12 Lo    Explosion      ~    ~    ~  ~  ~  ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~      ~              12 M. Flammable Gas            or Vapors .                   ~    ~    ~    ~    ~    ~    ~    ~    ~    ~              12.
No    Other    ~ ~  ~    ~    ~  ~  ~  ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~    ~              12 0130p


SENIOR REACTOR OPERATOR d5.Page 90
~ I
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==REFERENCE:==
                        ~ '
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t NP-REP, page 13, 3.1.2 K/A: 294001A116 (2.9/4.7)294001A116
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..(KA's)ANSWER: 100 (1.00)Co
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==REFERENCE:==
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1.EOI-1, RPV Control Bases, page 27.2~K/A: 2950286004 (2.7/3')295028G004
ra a    ~'               ~
..(KA's)(**********
                                                    )
END OF EXAMINATION
I  I I  ~ ~ ~    I I  ~                ~
*****+****)
                                                  '   I
'55NESSEE VAILZY AUXKORXTY'"-&#x17d;-"" I QQOlTRC'~~:
                  ~ ~
BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE El'Il'-1 EMERGENCY PLAN CLASSIFICATION LOGIC RKSIQN 13 PREPARED BY T.W CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION:
                                  ~      ~                      ~  ~
EMERGENCY PREPAREDNESS APPROVED BY: T W.CORNELIUS DATE: 07/01/92 EFFECTIVE DATE: OZ/09/92 VALIDATION DATE: NOT REQUIRED QUALITY-RELATED Procedure Number: EPIP-1 i.Pages.Affected: 15 Pagination Pages: NONE Description of Change: REVISION LOG Revision Number: 13.Change phone 0 from 236-1500 to 273-8500.  
a lal la  a                  a l all      l  a        a . aa  l all


EMERGENCY CLASSIFICATION LOGIC 1.0 PURPOSE 1.1 To provide guidance to the Shift Operations Supervisor (SOS)or Site Emergency Director (SED)on what constitute's an emergency classification.
lNOTE: The Np-REP, Appendix A, EHERGENCY CLASSIFICATION FLOWCHART REV 00        ys contains information or detail, related to emergency classifications or emergency action levels.
'1.2 To ensure that the emergency classification is consistent with that used by the local and state governments and the NRC.1.3 To provide a cross reference between this procedure and the ONP-REP, Appendix A, for use by the SOS or SED for additional information in'classifying events.2.0 SCOPE 2.1 This procedure applies to those events, that in the professional judgment of the SOS or the SED constitutes an emergency.
Page lO BF N-EP IP- I ATTACHHENT (Page 6 l
The SOS and the SED are the only individuals authorized to make the emergency class determination.
of l2)
2.2 The events listed in the attachments to this procedure cannot possibly incorporate all events which can occur.Therefore, all classifications should be judged against the general guidance listed below: 2.2.1 Notification of Unusual Event Unusual events are in process or have occurred which indicate a potential degradation of the level of safety of the plant.No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.2.2.2 Alert Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.0300p i
RADIOLOGKAL        QQ LIQUID  RELEASE EXCEEDING      gQ  LIQUID RELEASE EXCEEDING EFFLUENTS            TECH SPECS  3.8.A.l, 3             lo TINES TECH SPECS LIQUID                OR  5.                             3.8.A.l., 3, OR 5 j5P LIQUID RELEASE  THAT CANNOT BE TERHINATED l879o
2.0 (Continued)
REV 00 ZS Page 2 BFN-EPIP-1 2.2'.3 Site.Area Emergency Events are in process or have occurred which involve actual rotection of the ublic.Any releases are not, expected to exceed EPA Protective Action Guideline exposure levels except near site boundary-2.2e4 General'Emergency Events are in process or have occurred vhich invoive actual or imminent'suhstantial core de radation or meltin vith pbtential for loss of-containment inte rit.Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.3 0 INSTRUCTION 3.1 Review Attachment 1'to determine if an event should be classified as an emergency.
Note: (1)If an emergency action level for a higher classification was exceeded, but the present situation indicates a lower classification, the fact that the higher classification occurred shall be reported to the NRC and the CECC (if staffed), but should not be declared.(2)If an emergency action level was met but the emergency has been totally resolved, the emergency class that was appropriate shall be declared and terminated at the same time.s 3.1.1 Attachment 1 captures events in four br'oad categories:
Fission Product Barrier Degradation (F)System Malfunction (S)Radiation Levels Abnormal/Radiological Effluents (R)Hazards and Other Conditions Affecting Plant Safety (H)3.1.2 Each actual condition in a category is given an alphanumeric designator (FU1=Fission Product Barrier Degradation (F)resulting in Notification of Unusual Event (U)01).3.1.3 The only significance of the alphanumeric designator is a cross-reference to ONP-REP, Appendix A, which provides additional information for the SOS/SED in classifying the event.0300p 3.0 (Continued) 3.2 If the event is determined to be one of the four emergency classification, the SOS assumes the responsibilities of SED.3.2.1 Implement one of the following procedures as applicable:
EPZP-2-Notification of Unusual Event EPIP-3-Alert EPIP-4-Site Area Emergency EPPP-5-General Emergency 3.2N2 Continue to review the emergency conditions in Attachment 1 to escalate, de-escalate or terminate the emergency as appropriate.
3.3 If the event is determined not to be one of the four emergency classifications, continue to monitor plant conditions.


==4.0 ATTACHMENTS==
I''
Attachment 1, Emergency Classification Flowchart[NER/C NRC in 89-072]0300p azv P>s Page 4 BFN-EPIP-1 Index to Emer enc Classification Flow Chart DESCRIPTION PAGE G I.Fission Product Barrier De radation 4 A.Fuel Damage.B.Primary System Leakage C.Primary Coolant Break or Loss of Inventory D.Primary Containment Integrity.E.Loss of Fission-Product Barriers~~1 1~~2~~2~~2 II.S stem Malfunction A.B.C.D.E.F.G H.Tech Spec LCO~RPS/Core~~~~~~~~~~~~~~~~~~~Thermal Power~~~~~~~~~~~~~~~Shutdown~~~~~~~~~~~~~o~~~~~Turbine and Condenser.AC Power~A.A A o..o A A..A.~DC Power~~~~~~~~~~~~~o~~~~~Instrumentation, Controls, and Communications 0 4 3~s 3~0 3~~2~~3~~4 4 5 III.Radiation Levels Abnormal/Radiolo ical/Effluents A.Radiological Effluents (Liquid)..........6 B.Radiological Effluents (Gaseous).........7 C.Area Radiation..'............
I '
~...8 IV.Hazards and Other Conditions Affectin Plant Safet A.Security Threat.B.Missiles or Aircraft C.Injuries~~~~~~~~D.Uncontrolled Toxic Gases E.Control Room F.Earthquake G.Flood~~~~~~.~~~H.Tornado..~I.High Winds J.Low Reservoir.K~~~Fire~~~~~~~~~~o Lo Explosion~~~~~~~~~M.Flammable Gas or Vapors.No Other~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~9 9 10 10 10 ll 11 ll 11 12 12 12 12.12 0130p
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~I~~
ge 12 BF N-EPIP-1 REV 00.18                      ATTACHMENT (Page 8  of 1
12)
EMERGENCY  CLASSIFICATION FLONCMART NOTE:  The NP-REP, Appendix A, contains inforeation or detail, related to emergency classifications or emergency action levels.
AREA RADIATION
                                                          ~   RADIATION UNEXPECTEDLY ABNORMAL INCREASE BY 1 R/MR (ALARM/RAOCON CONFIRMATION jhow AIRBORNE RADIATION UNEXPECTEDLY INCREASES BY 100 MPC FOR A CONTROLLED AREA.  (CAH ALARM/RADCON CONFIRMATION)
(1)  MPC = MPC FOR A CONTROLI.EO AREA.
'I879o


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TITLE: REACTOR RECIRCULATION SYSTEH REV 0033 UNIT 2.2-OI-68 ILNSTRATION 1 (Page 1 of 3)OTENTIAL POiK INCREASE AMARElKSS INSTASILITY OR POIKR INSTABILIT'20 Ilo O IOO 90 80 t-70 z D 60~50 40 30.~~2o lo d HATURAL CIRCLLATI LIHE~r r~\~d0 1 I l.IHE~ROD 70.ROD I LIHE A~~~APRM ROD SLOCK R E I 0 H-(y~r R E G I 0 H iSX CORE, I FLOll I l IOC CORE l I KOM I I OOX I~~I ROD LIIK', r~~F~~r~r~r l rd r~~I C PUMP CONSTANT SPEED LINE MASTER MANUAL FLt&#xc3;CONTldL RAHGE 20 PldSI SPEED L~~HIKdl ItOlKR..:...LIN&!~MINIldkl EXPECTED~~FL(N COHTROL LIHE"'r rr~~~I I RECIRC PLOP@&i LIMO LINE~I r~I dlET PNS'PSH LIMIT LIHE~~OD~~~r r~r r lo 20 30 40 50 60 70 80 90 IOO IIO PERCENT RATED CORE FLOH 330(227)Page 49 of 57 2-OI-68 P" dh}}

Latest revision as of 16:20, 3 February 2020

Forwards Comments on Written Part of Operator Licensing Exams Administered During Wk of 930927
ML18037A584
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/07/1993
From: Zeringue O
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18037A566 List:
References
NUDOCS 9312130396
Download: ML18037A584 (341)
v • d • e


Text

ENCLOSURE 3 Tennessee Valley Authority. Post Office Box 2000, Decatur. Alabama 35609.2000 O. J. "Ike Zeringue Vice President, Browns Ferry Nuclear Plant OCT 07 19%

Mr. Stewart D. Ebneter Regional Administrator ATTH: Branch Chief, Operator Licensing U.S. Huclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323

Dear Sir:

In the Matter of Docket Hos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWHS FERRY NUCLEAR PLANT (BFH) REACTOR OPERATOR (RO) AHD SEHIOR REACTOR OPERATOR (SRO) LICENSING EXAMIHATIOH COMMENTS In accordance with the requirements of the HUREG 1021, "Operator Licensing Examiner Standard," Section ES-402, TVA is providing the enclosed comments on the written part of the Operator Licensing Examinations. The examinations were administered at BFN during the week of September 27, 1993.

A copy of the enclosed examination comments was given to the lead examiner on September 30, 1993.

9312130396 931D28 pre roach osoooa59 V PDR

Mr. Stewart D. Ebneter Page 2 cc~ ov ~>>

If you have any questions, please telephone Terry Dexter at (205) ?29-3470.

Sincerely, O. J. Zeringue Enclosure cc (Enclosure):

Mr. Robert M. Gallo Chief, Operator Licensing Branch, DLPQ U.S. Nuclear Regulatory Commission MS OWFN 10D-22 Washington, D.C. 20555 Mr. M. E. Ernstes Chief, Operator Licensing Section 2 U.S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, HW Atlanta, Georgia 30323 Mr. R. V. Crlenjak, Project Chief U.S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, HW Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 HRC Resident Inspector Browns Ferry Huclear Plant Route 12 Box 637 Athens, Alabama 35611

EHCLOSURE Tennessee Valley Authority (TVA)

Browns Ferry Huclear Plant (BFH) s 0 e ato e s a o

0 HLT 9208 written examination post examination comments RO question 01; SRO question 01 Question: The reactor is being restarted near the end of core life following a one day outage. Reactor power is at 32%. Control rods 34-23 and 58-23 have been isolated at position 00. When rod 42-43 is withdrawn, alarm 2-XA-55-5A-29, CRD ACCUM PRESS LOW LEVEL HIGH, actuates on panel 9-5. WHICH ONE (1) of the following requirements is in effect under current plant con ditionsV

a. Exercise control rod 42-43 at least one notch at least once each day.
b. Clear the accumulator trouble alarm on rod 42-43 prior to moving to the next control rod.
c. Control rod 42-43 must be fully inserted and electrically disarmed.
d. Observe nuclear instrumentation for response each time rod 42-43 is moved.

Answer key answer: D Comment: For any event that can directly affect reactivity, it is considered to be of a critical nature and strict procedural compliance along with conservative actions must be followed. This caution is prevalent throughout BFNP procedures such as:

SSP 12.17 Reactivity Management, page 9 2-0I-85 Control Rod Drive system Precaution and Limitations 3.1.13, page 8, 10, 11 [ INPO SOER 84-002 ]

2-GOI 100-1A Unit Startup From Cold Conditions section 3.12 page 12 [INPO SOER 89-006, SOER 88-002]

2-Gol 100-1B Unit Startup From Cold Shutdown to Hot Standby section 3.11 page 12; [INPO SOER 89-006, SOER 88-002]

2-GOI 100-1C Unit Startup from Hot Standby page 9 section 3.10.

[INPO SOER 89-006, SOER 88-002]

During the situation described in the stem of this question, rod 42-43 is potentially inoperable if the accumulator alarm is valid. This would make answer B also correct since during a reactor startup, it would be assumed that the next control rod movement would be a rod withdrawal, it would not be conservative action to continue rod withdrawal with an potentially inoperable rod that is not fully inserted. Additionally, the alarm response procedure directs dispatching of personnel to determine if the alarm is valid and directs the use of 2-Ol-85 to clear the alarm. This would be the expected course of action should this event occur in the plant. Answer D is correct because this requirement is in place per Technical Specifications whether the rod is being inserted or withdrawn.

I Proposed resolution: Accept either B or D as a correct answer

HLT 9208 written examination post examination comments RO question ¹57; SRO question ¹47 Question: WHICH ONE (1) of the following is an acceptable way to perform position verification on a throttled valve? (assume that the valve is installed in a system with local indication controlled by the valve, and the valve has a rising stem)

a. observe the initial valve operator's action in positioning the throttled valve
b. perform an independent visual check of the valve position by observing the valve stem
c. independently verify the valve position by a second valve operation
d. by observing flow indication through the throttled valve's system Answer key answer: A Comment: SSP 12.6 (Verification program) page 7, states that throttled valves are normally verified using second party verification. However, section 3.3.3 (also on page 7) states that alternate verification methods may be used at the D is also correct.

thief discretion of shift supervisory personnel. One of these alternate verification techniques is the use of process parameters. Since the question stem asks for lygp Proposed resolution: Accept either A or D as the correct answer

HLT 920B written examination post examination comments RO question 061; SRO question 053 Question: Four licensed UOs attended a fellow employee's birthday party the last night of their vacation and alcohol was served to all. Below shows when each UO stopped drinking alcoholic beverages.

UO A1:05 am UO B2:05 am UO C 3:05 am UO D 4:05 am From the four UOs listed above, WHICH ONE (1) of the following states the number available for NRC licensed work the same morning at 7:00 am?

(Assume that all the UOs have blood alcohol levels within SSP 1.6 guidelines)

a. ONE
b. TWO
c. THREE
d. FOUR Answer key answer: B Comment: SSP 1.6 (Fitness for duty) states on page 6, section 3.1.4 that a person covered by the scope of the procedure shall abstain from the consumption of alcohol for at least 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> preceding any scheduled work.

Therefore, to be available for work at 7:00 am, an individual would have to stop drinking prior to 2:00 am. Since only UO A had stopped drinking prior to 2:00 am, he or she would be the only one available to work at 7:00 am. Answer B is not correct.

Proposed resolution: Accept A as the correct answer

HLT 9208 written examination post examination comments SRO question ¹62 Question: The control room was evacuated due to a fire 5 minutes ago. Atl the immediate actions for "Control Room Abandonment" were performed. Current plant conditions are:

The reactor has been verified to be shutdown.

RPV level is >+60 inches.

RPY pressure is 700 psig and decreasing slowly.

The MSIVs are open and cannot be closed, The turbine bypass valves appear to functioning normally.

An operator is stationed to control RPY level and pressure with HPCI as necessary WHICH ONE (1) of the following is the appropriate emergency action level for this situation?

a. Unusual Event
b. Alert
c. Site Area Emergency
d. General Emergency Answer key answer: C Comment: The stem of the question states that the control room was evacuated due to a fire, but does not state the location of the fire. Due to the proximity of some offices to the control room, it is conceivable that a fire in those offices could result in enough smoke in the control room to warrant evacuation without an actual fire in the control room. With this limited information, it is merely a judgment call by the SOS as to whether the fire is in i I (alert) or actually ff i vi I r (site area emergency). Additionally some of the information given in the stem is confusing: (1) HPCI is being used to control level and pressure, but in 2-AOI-100-2, step 4.2.10, HPCI would be disabled (2) The MSIVs are stuck open, reactor pressure is dropping, but the bypass valves are functioning normally. There is no available indication of bypass valve position at the backup control panel. The pressure decrease could be considered to be normal (depending on recent power history) with reactor water level at+60 and normal auxiliary steam loads in service and without supporting indications (radiation or temperature alarms, or reports from the plant) the slow pressure decrease would not necessarily be indicative of a leak during the first 5 minutes of the event. With no data on radiation levels in the plant or coolant activity levels, reference to the general descriptions of the emergency classifications on pages 1 and 2 of EPIP-1 could lead to alert as the appropriate classification.

Proposed resolution: Accept either B or C as the correct answer

HLT 9208 written examination post examination comments RO question ¹97; SRO question ¹96 Question: RHR loop I is in shutdown cooling taking suction through Shutdown Cooling suction valves 74<7 and 74-48. Loop II of RHR remains in the LPCI standby lineup. Due to misoperation of ventilation systems, drywell pressure increases to 2.5 psig. WHICH ONE (1) of the following describes the response of the RHR system?

a. Valves 74-47 and 74-48 close, Loop I suppression pool suction valves auto and BOTH RHR loops inject to the vessel.
b. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, suppression pool suction valves auto open but only Loop II injects.
c. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression suction valves remain closed and only Loop II injects.
d. Valves 74-47 and 74-48 close, Loop I RHR pump trip, Loop I suppression pool suction valves remain closed and NEITHER Loop injects.

Answer key answer: C Comment: 2-0I-74 page 69 of 202, and Lesson Plan OPL171.044 page 24 states the actions that occur on a group 2 isolation when the RHR system is operating in the shutdown cooling mode. On the isolation signal, both of the Loop I and II inboard injection valves would receive a close signaI and would not automatically reopen until the group 2 isolation signal was reset on panel 9-

3. Therefore, neither loop of RHR would inject without some form of operator manual action. Since this action was not listed in the stem of the question, answer C could not be correct.

Proposed resolution: Accept D as the correct answer

0 0

ENCLOSURE 4 RESOLUTION OF FACILITY COMMENTS ON WRITTEN EXAM

1. SRO Question 1 (RO Question 1)

Facility comment accepted.

2. SRO Question 47 (RO Question 57)

Facility comment accepted.

3. SRO Question 53 (RO Question 61)

Facility comment accepted.

4. SRO Question 62 (No RO question)

Facility comment accepted.

5. SRO Question 96 (RO Question 97)

Facility comment accepted.

U. S. NUCLEAR REGULATORY 'OMMISSION Afas 4~

SITE SPECIFIC EXAMINATION REACTOR OPERATOR LICENSE REGION 2 CANDIDATE~S NAME:

FACILITY: Browns Ferry 1, 2, & 3 REACTOR TYPE: BWR-GE4 DATE ADMINISTERED: 93/09/27 INSTRUCTIONS TO CANDIDATE:

Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires a final grade of at least 804. Examination papers will be picked up four (4) hours after the

'nation starts.

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CANDIDATE'S TEST VALUE SCORE 100.00 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

REACTOR OPERATOR Page 2 ANSWER SHEET I

Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

MULTIPLE CHOICE 023 a b c d 001 a b c d Q24 a b c d 002 a b c d 025 a b c ~ d 003 a h c d 026 a b c d 004 a b c d 027 a b c d QQ5 a b c d 028 a h c d 006 a h c d 029 a b c d 007 a b c d 030 a b c d 008 a b c d 031 a b c d a b c d 032 a b c d 0 a a

b b

c c

d d

033 034 a

a b

h c

c d

d 012 a h c d 035 a b c d 013 a b c d 036 a b c d 014 a b c d 037 a b c d 015 a b c d 038 a b c d 016 a b c d 039 a b c d 017 h c d 040 a b c d 018 a b c d 041 a b,. c d 019 b c d 042 a h c d 020 b c d 043 a b c d 021 a b c d 044 a h c d a b c d 045 a b c d

REACTOR OPERATOR Page 3 AN'SWER SHEET Multiple Choice

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(Circle or X your choice)

Zf you change your answer, write your selection in the blank.

046 a b c d 069 a b c, d 047 b c d 070 a b c d 048 a b c d 071 a b c d 049 a b c d 072 a b c d 050 a b c d 073 a b c d 051 a b c d 074 a b c d 052 a b c d 075 a b c d 053 a b c d 076 a b c d 054 a b c d 077 a b c d a b c d 078 a b c d a b c d 079 a b c d a b c d 080 a b c d 058 a b c d Q81 a b c d 059 a b c d 082 a b c d 060 a b c d Q83 a b c d 061 a b c d 084 a b c d 062 a b c d 085 a b c d 063 a b c d 086 a b c d I

064 a b c d 087 a b . c d 065 a b c d 088 a b c -d 066 a b c d 089 a b c d 067 a b c d 090 a b c d a b c d 091 a b c d

d,i REACTOR OPERATOR Page 4 A N S N E R S H E E T Multiple Choice

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(Circle or X your choice)

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If you change your answer, write your selection in the blank.

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092 a b c d 093 b c d 094 a b c d 095 a b c d 096 a b c d 097 a b c d 098 a b c d 099 a b c d 100 a b c d 0

(********** END OF EXAMINATION **********)

0 Page 5 RC RULES AND GUIDE IN S FOR L CENSE EXAMINATIONS 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 penalties.
2. After the examination has been completed, you must sign the ~

statement on the cover sheet indicating 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 exam-ination.

3. 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, cheating.
4. Use black ink or dark pencil only to facilitate legible repro-ductions.
5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
6. Fill in the date on the cover sheet of the examination (if necessary).
7. Print your name in the upper right-hand corner of the first page of each section of your answer sheets.
8. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
9. The point value for each question is indicated in parentheses after the question.
10. Partial credit will NOT be given.

ll. If the intent of a question is unclear, ask questions of the examiner only.

12. When you are done and have turned in your examination, leave the examination area as defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.

Page 6 Blank Page

C%.

REACTOR OPERATOR Page 7 TION: 001 (1. 00)

The reactor is being restarted near the end of core life following a one day outage. Reactor power is at 324. Control rods 34-23 and 58-23 have been isolated at position 00. When rod 42-43 is withdrawn, alarm 2-XA-55-5A-29, CRD ACCUM PRESS LOW LEVEL HIGH, actuates on panel 9-5.

WHICH ONE (1) of the following requirements is in effect under the current plant conditions?

a. Exercise control rod 42-43 at least one notch at least once each day.
b. Clear the accumulator trouble alarm on rod 42-43 prior to moving the next control rod.
c. Control rod 42-43 must be fully inserted and electrically disarmed.
d. Observe nuclear instrumentation for response each time rod 42-43 is moved.

ION: 002 (1. QO)

Control Rod 38-23 has been selected for a single notch withdrawal from position 02 to position Q4. The following response from the CRD system was observed:

Insert light illuminates and goes out.

Withdrawal light illuminates and goes out.

Settle light illuminates and goes out.

The operator also observes and reports that the selected rod is now at position 06 and is continuing to drift out. A Rod Drift alarm is also present. WHICH ONE (1) of the following has caused the conditions?

a. the automatic sequence timer has failed
b. stuck open .,collet fingers
c. excessive HCU cooling water pressure
d. leaking scram inlet valve

0 REACTOR OPERATOR Page 8 STION: 003 (1.00)

WHICH ONE (1) of the following states the condition identified by an illuminated blue scram light for each control rod on the Full Core Display?

a. Both inlet and outlet scram valves for that rod are open.
b. Both inlet and outlet scram valves for that rod are closed.
c. Both scram pilot air valves for that rod are energized.
d. Both scram pilot air valves for that. rod are deenergized.

QUESTION: 004 (1.00)

Following performance of a torus-drywell vacuum breaker operability surveillance instruction, the vacuum breaker has the following indications:

Check light - OFF Green light ON Red light - OFF

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WHICH ONE (1) of the following states the position of the vacuum breaker'?

a. fully closed
b. cracked open (less than 3 degrees open)
c. partially open (between 3 degrees and 80 degrees open)
d. fully open (greater than 80 degrees open)

REACTOR OPERATOR Page 9 STION: 005 (1.00)

While a control rod is being inserted using the EMERGENCY IN contxol switch, rod motion stops. WHICH ONE (1) of the following could have terminated rod insertion?

a. the automatic sequence timer deenergizes
b. loss of power to the Rod Position 1'nformation System
c. a RWM select block
d. a RWM insert block QUESTION: 006 (1.00)

WHICH ONE (1) of the following will result in a control rod block on input from IRM B?

a. Mode switch is in REFUEL, IRM B is downscale on range 1.

is in STARTUP, IRM B indicates 30 on range 3.

c. Mode switch is in STARTUP, IRM B downscale on range 5.
d. Mode switch is in RUN, IRM B indicates 105 on range 8.

B.

REACTOR OPERATOR Page 10 STION: 007 (1. 00),

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WHICH ONE (1) of the following sets of conditions would result in the Unit 2 Automatic

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Depressurization system 95 second timer starting?

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Assume all sensors, power supplies, and interlocks are operating properly.

a ~ RPV level remains at -125" for 4 minutes and 30 seconds, Drywell pressure peaks at 2.10 psig, >>A>> Core Spray pump discharge pressure is 190 psig, "C>> Core Spray pump discharge pressure is 195 psig, no other ECCS pumps are running.

b. RPV level remains at -125>> for 4 minutes and 30 seconds, Drywell pressure peaks at 2.10 psig, >>A>> Core Spray pump discharge pressure is 175 psig, >>C>> Core Spray pump discharge pressure is 195 psig, no other ECCS pumps are running.

co RPV level remains at -135>> for 3 minutes and 25 seconds, Drywell pressure peaks at 2.50 psig, >>A>> Core Spray pump discharge pressure is 190 psig, >>B>> Core Spray pump discharge pressure is 195 psig, no other ECCS pumps are running.

d. RPV level remains at -135>> for 3 minutes and 25 seconds, Drywell pressure peaks at 2.50 psig, >>B>> Core Spray pump discharge pressure is 190 psig, >>D>> Core Spray pump discharge pressure is 175 psig, no other ECCS pumps are running.

QUESTION: 008 (1.00)

A Main Steam Relief Valve (MSRV) lifts due to high reactor pressure.

(1) of the following could cause a significant DECREASE in the WHICH ONE MSRV's lift pressure if it subsequently lifts a second time?

a. tailpipe vacuum breaker failed CLOSED
b. tailpipe vacuum breaker failed OPEN

. c. high drywell pressure

d. high suppression pool level

REACTOR OPERATOR Page 11 STION: 009 (1.00)

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Control rod drive mechanism 25-24 has exceeded 350 degrees F, alarm

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TA-85-7, CONTROL ROD DRIVE UNIT TEMP HIGH annunciator (2-XA-55-5A, Window 17) is alarming. WHICH ONE (1) of the following describes the correct response to this hot CRD mechanism'?

a. Check for scram discharge valve leakage, leave the drive hot.
b. Check for scram discharge valve leakage, cool the drive by giving it repeated drive signals.
c. Check for scram inlet valve leakage, leave the drive hot.
d. Check for scram inlet valve leakage, cool the drive by giving repeated drive signals.

it QUESTION: 010 (1.00)

WHICH ONE (1) of the following signals from the Post-Treatment Radiation Monitoring System will initiate an AUTOMATIC ISOLATION of the Off gas charge to the main stack (FCV-66-28)?

a. High-High-High trip in Channel A; Channel B is clear
b. High trip in Channel A; downscale trip in Channel B
c. High trip in Channel A; XNOP trip in Channel B.
d. Downscale trip in Channel A; INOP trip 'in Channel B.

dS.,

REACTOR OPERATOR Page 12 STXON: 011 (1.00)

During a LOCA, the SRO directs you to initiate drywell sprays. The RHR SYS I CTMT VLV SELECT switch is in SELECT and the 2/3 Core coverage OVERRIDE. RHR SYS I keylock switch is in DW SPRAY INBD VLV (2-FCV 61) cannot be opened. WHICH ONE (1) of the following interlocks is preventing valve operation?

a. RPV level less than -122 inches
b. RPV level less than -183 inches
c. LPCI initiation signal NOT present
d. Drywell pressure less than 1.96 psig QUESTION: 012 (1.00)

An earthquake has resulted in a complete loss of off-site power and LOCA on Unit 2. Drywell pressure has increased to 5 psig on Unit 2.

rgency Diesel Generator "C" has failed to start. All other emergency nt equipment is functioning normally. EXCH ONE (1) of the following ntifies the Core Spray pumps that will respond to the automatic start signal?

a. 2A, 28
b. 2A, 2B, 2D
c. 2A, 2C d 2Ar 2Ct 2D

d5.

REACTOR OPERATOR Page 13 The Control Room has been evacuated. RHR pump 2C is required for operation in the shutdown cooling mode and the SDC suction valve is OPEN. RHR pump breaker power has been transferred to the local Emergency position. WHICH ONE (1) of the following will prevent the pump from starting?

a. Shutdown Cooling Supply valve, 74-47, is CLOSED.
b. RHR Drain pump suction valve,74-104, is OPEN.
c. A Unit 2 Accident Signal is present.
d. Undervoltage on Shutdown Board C.

QUESTION: 014 (1.00)

Condxtzons have been met

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to start the Automatic Depressurization System (ADS) 95 second timers. WHICH ONE (1) of the following identifies the initiation signals that will ar?

NOT automatically reset if conditions

a. 95 second TIMER and Low Reactor Water Level TIMER
b. 95 second TIMER and Low Reactor Water Level signal
c. High Drywell pressure signal and Low Reactor Water Level TIMER
d. High Drywell pressure signal and Low Reactor Water Level signal

C5.

REACTOR OPERATOR Page 14 STION: 015 (1.00)

Reactor Recirculation pump "A" is operating at 1310 RPM and is providing 40,000 gpm flow. Reactor Recirculation pump "B" is operating at 1325 RPM. WHICH ONE (1) of the following states the LOWEST flow for Reactor Recirculation pump "B" that would indicate possible jet pump failure7

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a. 44,000 gpm
b. 44,600 gpm
c. 46,000 gpm
d. 46,600 gpm QUESTION: 016 (1.00)

Reactor Recirculation pumps are not operated below 204 speed. WHICH ONE (1) of the following states the basis for this limit?

a. Ensures adequate Net Positive Suction Head.

b; Prevents thermal stress in the vessel lower head region.

c. Prevents unstable fluid coupler operation.
d. Limits harmonic vibration of the jet pumps.

REACTOR OPERATOR Page 15 I~

STION: 017 (1. 00)

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The plant is operating at full power when the "B" Reactor Recirculation

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pump's suction valve drifts to 884 open. WHICH ONE (1) of the following states the expected response?

a. Pump speed decreases to 284.
b. Pump speed decreases to 454.
c. Pump speed decreases to 754.
d. Pump trips.

QUESTION: 018 (1.00)

While Reactor Recirculation pump "A" is operating at. 804, a failure in pump's individual M/A station occurs and a signal is sent to the Bailey Positioner calling for a pump speed of zero. WHICH ONE (1) of the following states the expected response of the pump?

a. Scoop tubes will lock and speed will remain at 804.
b. Speed decreases to 284.
c. Speed decreases to 204.

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d. Speed decreases to zero.

1 dS.,

REACTOR OPERATOR Page 16 STION: 019 (1.00)

WHICH ONE (1) of the following sets of cavity pressures indicate a failure of the ¹2 (outer) Reactor Recirculation pump seals?

¹1 CAUITY PRESSURE ¹2 CAVITY PRESSURE a0 1000 psig 100 psig

b. 1000 psig 1000 psig C~ 500 psig 500 psig
d. 1000 psig 500 psig QUESTION: 020 (1.00) l During an accident on Unit 2, power is lost from the Division II ECCS inverter. WHICH ONE (1) of the following HPCI system capabilities is lost'
a. Flow control
b. Automatic initiation
c. Automatic isolation
d. Automatic trip

REACTOR OPERATOR Page 17

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STION: 021 (1.00)

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HPCI is in standby readiness. of the following states the

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(1)

HPCI pump suction status Storage Tank volume is if Torus level

~ WHICH ONE 9900 gallons.7 is +5 inches and the Condensate a'. Suction is from the CST but can be manually transferred to the Torus without bypassing interlocks.

b. Suction is from the CST and CANNOT be transferred to the Torus without bypassing interlocks.
c. Suction is from the Torus but can be manually transferred to the CST without bypassing interlocks.
d. Suction is from the Torus and CANNOT be transferred to the CST without bypassing interlocks.

QUESTION: 022 (1.00) mode switch is in run and APRM B has failed downscale. No operator ion is taken. WHICH ONE (1) of the following correctly describes the ected response if the stated IRM failures occur?

a. IRM B Hi-Hi or ZRM G ZNOP will result in a half scram of RPS Channel A.
b. IRM B Hi-Hi or ZRM G INOP will result in a half scram of RPS Channel B.
c. IRM B ZNOP or ZRM H Hi-Hi will result in a half scram of RPS Channel A.
d. ZRM B ZNOP or ZRM H Hi-Hi will result in a half scram of RPS Channel B.

0 REACTOR OPERATOR Page 18 STION: 023 (F 00)

With the plant operating at 100% power, Alarm XA-55-3F, window 31, CORE SPRAY SYS II SPARGER BREAK, actuates. WHICH ONE (1) of the following identifies the core spray line break location required to actuate the alarm?

a.'nside of the reactor vessel shroud

b. inside of the reactor vessel and outside of the shroud
c. anywhere inside of the reactor vessel
d. anywhere on the pressurized portion of the injection line QUESTION: 024 (F 00)

During a LOCA, reactor water level is dropping at a rate of 20 inches per minute. RPV level is currently -132 inches. RPV pressure is 468 psig and Drywell pressure is 2.5 psig. WHICH ONE (1) of the following cribes the expected status of the Unit 2 Core Spray system?

a. Core Spray system has NOT initiated.
b. Core, Spray pumps have started, injection valve is CLOSED.
c. Core Spray pumps have started, injection valve is OPEN, but pump flow is deadheaded against the closed check valve.
d. Core Spray pumps have started and are I

injecting into the vessel.

d.

REACTOR OPERATOR Page 19 TION: 025 (1.00)

The PSC pumps trip and cannot be restarted. WHICH ONE (1) of the following conditions is a possible reason for this occurrence?

a. RPV level is -118 inches.
b. RHR Room temperature is 182 degrees F.
c. 250U RMOV power is lost to Div I.
d. Suppression pool level is -6.25 inches.

QUESTION: 026 (1 00)

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During plant startup with reactor power on range 5 of the IRMs, an MSIV closure occurs. WHICH ONE (1) of the following conditions is a possible t

reason for this occurrence?

'a. Reactor water level is -83 inches.

b. MSL tunnel temperature is 210 degrees F.
c. Reactor pressure is 840 psig.
d. Drywell pressure is 2.6 psig.

0 0

d.)

REACTOR OPERATOR Page 20 STION: 027 (1.00)

During a plant transient, the Main Steam Isolation Valves isolated on a valid Group I isolation signal. All control rods inserted and immediate operator actions reguired by procedure have been taken. A decision has been made to unisolate MSL "D" (valves 1-51 and 1-52) to allow use of the main condenser. Given the following plant conditions:

Reactor water level is -5 inches.

Reactor pressure is 700 psig.

Drywell pressure is 3.2 psig.

MSL Area temperature is 185 degrees P.

WHICH ONE (1) of the following states actions required to reset the Group 1 isolation?

a. The MSIV switches for ONLY valves 1-51 and 1-52 must be placed in the CLOSE position.
b. A jumper must be installed AND the MSIV switches for ONLY valves 1-51 and 1-52 must be placed in the CLOSE position.

t c. The MSIV switches for ALL MSIUs must be position.

placed in the

d. A jumper must be installed AND the MSIV switches must be placed in the CLOSE position.

for CLOSE ALL MSIVs

>l REACTOR OPERATOR Page 21 STION: 028 (1.~

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exists

~ 00)'onditions on Unit

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2 that require the initiation of Standby Liquid Control. (1) of the following contains two indications

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WHICH ONE that SLC is injectingi

a. Explosive valve current flow indicator reads 0 milliamps AND the blue SQUIB VALVE CONTINUITY light is illuminated.
b. Explosive valve current flow indicator reads 4 .milliamps AND the blue SQUIB VALVE CONTINUITY light is illuminated.
c. Explosive valve current flow indicator reads 0 milliamps AND the blue SQUIB VALVE CONTINUITY light is extinguished.

Explosive valve current flow indicator reads 4 milliamps AND the blue SQUIB VALVE CONTINUITY light is extinguished.

QUESTION: 029 (1 00)

Off-Gas Pretreatment High Radiation alarm for Unit 2 has just ated. WHICH ONE (1) of the following conditions could have caused alarm?

a. Failure of the on-line Catalytic Recombiner.
b. Failure of a condensate demineralizer resin trap.
c. Trip of the operating Steam Jet Air Ejector.
d. Increased steam content of off-gas exhaust flow.

0 d.)

REACTOR OPERATOR Page 22 STION: 03 0 (1 00)

A TIP trace is being run in the automatic mode using TIP Channel A.

While the TIP is at the top of core limit, the reactor scrams on low water level after a loss of electrical power. 120VAC power is lost to the TIP system. RPV level reaches +10 inches minimum. WHICH ONE (1) of the following describes the response of the TIP System following the scram?

a. The TIP channel will shift to manual reverse mode withdraw to the in shield limit and the ball valve will close.
b. The TIP channel will shift to manual reverse mode, withdraw to the in shield limit and the ball valve will fail to close. The Shear valve can be fired if isolation is required.
c. The TIP channel will remain at it's present position. The Shear valve can be fired if isolation is required.
d. The TIP channel will remain at it's present position. The Shear valve will be incapable of firing if isolation is required.

TION: 031 (1. 00)

Given that the following conditions exist during refueling on Unit 3:

Bridge is directly over the core Main hoist is loaded to 550 lbs, in the full up position Aux hoist is loaded to 350 lbs, in the full up position Rod 03-17 is at position 02 Mode Switch is in STARTUP WHICH ONE (1) of the following responses would indicate normal interlock functioning on the refuel bridge? (FORWARD means away from the core, REVERSE means toward the core.)

a. Bridge will move in the forward AND reverse directions.
b. Bridge will move in the forward direction BUT NOT reverse direction.
c. Bridge will move in the reverse direction BUT NOT forward direction.
d. Bridge will NOT move in either direction.

o B.

REACTOR OPERATOR Page 23 STION: 032 (1.00)

WHICH ONE (1) of the following describes the trip logic for the Reactor Building Ventilation Radiation Monitors (Reactor Zone Ventilation Radiation Monitors and Refuel Floor Radiation Monitors)

a. Two Hi levels in 1 division OR one downscale in 2 divisions
b. Two Hi levels in 1 division OR two downscales in 1 division
c. One Hi level in 2 divisions OR one downscale in 2 divisions
d. One Hi level in 2 divisions OR two downscales in 1 divisions QUESTION: 033 (1.00)

WHICH ONE (1) of the following describes how the RWCU system is connected to the RPV in each of the three units?

a. Suction is from the >>A>> Recirc line on all units, return is via the >>B>> feed line for Units 1 and 2, and the >>A>> and >>B>> feed lines for Unit 3.
b. Suction is from the >>A>> Recirc line on all units, return is via the >>B>> feed line for Units 1 and 3, and the >>A>> and >>B>> feed lines for Unit 2.
c. Suction is from the >>B>> Recirc line on all units, return is via the >>B>> feed line for Units 1 and 3, and the >>A>> and >>B>> feed lines for Unit 2.
d. Suction is from the >>B>> Recirc line on all units, return is via the >>B>> feed line for Units 1 and 2, and the >>A>> and >>B>> feed lines for Unit 3.

d5.

REACTOR OPERATOR Page 24 STION: 034 (1.00)

Shutdown Bus 1 was initially being supplied by Unit Board 2B when Shutdown Board B bus transfer switch (43) transfers to MANUAL. WHICH ONE (1) of the following is a possible reason for this occurrence?

4

a. Shutdown Board B Normal Feeder Breaker (1616) Emergency Control Power Transfer Switch has been placed in the Emergency position.
b. The alternate power supply to Shutdown Bus 1 has sensed a high load differential condition across the 87Uxz breaker.
c. A phase or ground overcurrent condition has been sensed by the NORMAL shutdown bus power supply.
d. The residual voltage relay has shut in the close circuit of the alternate power supply to Shutdown Bus 1.

QUESTION: 035 (1.00) cerning the Diesel Generator Mode Switch, WHICH ONE (1) of the lowing modes of operation is used when the diesel generator is in allel with off-site power?

a. Test
b. Single Unit
c. Units In Parallel
d. Parallel With System

0 0

d5.

REACTOR OPERATOR Page 25 STION: 036 (1 00}

A LOCA has occurred. Drywell pressure is 3 psig and no off-site power is available. WHICH ONE (1) of the following is the only load allowed to be sequenced onto its associated shutdown board before forty (40) seconds have elapsed'

a. RHRSW pumps
b. A and D Control Air Compressors
c. Drywell blowers
d. RBCCW pumps QUESTION: 037 (1.00)

WHICH ONE was V

(1) of the following would totally lost' be affected if the +/-24 VDC system

a. Neutron Monitoring Instrumentation
b. Control Room Annunciators
c. Diesel Control and Logic power
d. 480V Shutdown Board Control Power

d5.

REACTOR OPERATOR Page 26 STION: 038 ( 1. 00)

Normal and alternate supply breakers to unit boards 3A and 3B have tripped and the Unit 3 Shutdown Board 43 auto transfer switches have transferred to MANUAI. WHICH ONE (1) of the following describes what has happened?

a. An automatic shutdown bus transfer has taken place.
b. The associated 4 kV shutdown board has failed to transfer to the alternate power supply.
c. The associated backfeed switch has been placed in the BACKFEED position.
d. A manual U3 Unit Board high-speed transfer to the alternate power supply failed.

QUESTION: 039 (1.00) zng full power operation on Unit 2, the mechanical spaces exhaust fan ls. WHICH ONE (1) of the following is a possible consequence of this lure?

a. Buildup of contaminants in the Radwaste building atmosphere
b. Development of an explosive atmosphere in battery rooms
c. Main steamline isolation
d. Unreliable Emergency Range level indication

dS.

REACTOR OPERATOR Page 27 STION: 040 (1.00)

A fire pump has automatically started. WHICH ONE (1) of the following could have caused the initiation?

a. A fog water system was manually started at the Main turbine oil tanks.
b. Turbine building area temperatures have steadily risen 40 degrees in the last five minutes.
c. Main Transformer temperature has increased to 190 degrees F.
d. Unit 2 HPCI room temperature has increased from 100 to 212 degrees F over the last 30 minutes.

QUESTION: 041 (1.00)

An RSW pump has started to automatically increase level in the RSW storage tank when a fire pump receives an automatic start signal. WHICH (1) of the following describes the response of the RSW storage tank lation valves and the RSW pump?

a. The RSW pump immediately trips. The isolation valves CLOSE but will AUTOMATICALLYreopen when the fire pump stops.
b. The RSW pump immediately trips. The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire pump stops.
c. The RSW pump continues running in support of the fire pump. The isolation valves CLOSE but will AUTOMATICALLYreopen when the fire pump stops.
d. The RSW pump continues running in support of the fire pump. The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire pump stops.

d%.

REACTOR OPERATOR Page 28 STION: 042 (1 ~ 00)

The plant is being shutdown

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and reactor power is stable at 254 when annunciator "OFFGAS HOLDUP TEMPERATURE HIGH" actuates due to low flow through the SZAE condensers. WHICH ONE (1) of the following could have caused the event'?

a. In-leakage of noncondensible gases into the main condenser.
b. SPE Heat Exchanger Balancing valve (FCV 2-190) open.
c. Condensate demineralizer bypass valve (FCV 2-130) open.
d. Only two condensate pumps running.

QUESTION: 043 (1.00)

The Condensate system is aligned for short cycle cleanup. WHICH ONE (1) of the following describes the flowpath?

a. Flow returns to the condenser from the outlet of the SJAE condensers.
b. Flow returns to the condenser from the condensate booster pump discharge header.
c. Flow returns to the CST from the outlet of the SZAE condensers.
d. Flow returns to the CST from the condensate booster pump discharge header.

REACTOR OPERATOR Page 29 STION: 044 (1." 00)

RHR loop 1 is in standby when electrical power is lost to 480 volt RMOV board 2D. WHICH ONE (1) of the following RHR flowpaths is NOT available?

a. torus cooling
b. drywell spray
c. LPCI injection
d. pump minimum flow QUESTION: 045 (1.00)

WHICH ONE (1)

Control Room?

of the following RPS trip signals can be bypassed from the

a. Scram Air Header

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low pressure

b. Loss of RPS power
c. Hi~

RPV pressure

d. Hi MSL radiation QUESTION: 046 (1.00)

WHICH ONE (1) of the following describes the expected DIRECT response t ne Main Steam Line radiation monitor reaching it's high trip setpoint?

. a. Full scram and full Group 1 Isolation

b. Full scram and half Group 1 Isolation
c. Half scram and full Group 1 Isolation
d. Half scram and half Group 1 Isolation

d5.

REACTOR OPERATOR Page 30 STION: 047 (1.00)

WHICH ONE (1) of the following states when the Rod Block Monitor system initiates a null sequence?

a. reference APRM fails upscale b; reference APRM is changed to alternate
c. recirculation flow changes by 10%
d. reactor power drops below 30%

QUESTION: 048 (1. 00)

Unit 2 is operating at 100% power with FWLC in automatic three element control when the "A" steam flow transmitter fails downscale. WHICH ONE (1) of the following describes the expected control room INDICATIONS after conditions stabilize? (Assume no operator action is taken)

a. Feed Flow 100%, Steam Flow 75%, Reactor Level 18 inches
b. Feed Flow 75%, Steam Flow 75%, Reactor level 18 inches
c. Feed Flow 100%, Steam Flow 75%, Reactor Level 33 inches
d. Feed Flow 75%, Steam Flow 75%, Reactor Level 33 inches

I.

ld

dS.

REACTOR OPERATOR Page 31 I

STION: 049 (1.00)

Unit 2 is operating at 1004 power with the master feedwater level controller is in 3 element when the FWLC system experiences a loss of one of the two feedwater flow inputs. WHICH ONE (1) of the following describes the expected plant response? (Assume no operator action is taken)

a. Reactor level will stabilize at normal with.FWLC remaining in 3 element control.
b. Reactor level will stabilize at normal with FWLC in single element.
c. Reactor level will stabilize about 15 inches below normal with FWLC remaining in 3 element control.
d. Reactor level will stabilize about 15 inches below normal with FWLC in single element.

QUESTION: 050 (1.00)

~

H ONE (1) of the following conditions will result in

~

a RFPT trip?

a. RFPT "B" suction pressure 95 psig for 25 seconds.

~

b. Condenser low vacuum 10" Hg.
c. RFP (pump) low oil pressure 6 psig.
d. RPV level 52" for 10 seconds.

0 0

REACTOR OPERATOR Page 32 STION: 051 (1.00)

Unit 2 has just experienced a small LOCA and Drywell pressure has increased to 3 psig. Reactor pressure is SQQ psig and steady. The increase in Drywell temperature causes reliability concerns for WHICH ONE (1) of the following level instruments'

a. Emergency Range indicators,
b. Normal Range indicators c.. Post Accident indicators
d. Shutdown Floodup indicators QUESTION: 052 (1.00) t WHICH ONE (1) of the following describes.how an electrical drawing is verified as being the current revised copy'P
a. Refer to the Controlled Drawing Holders list of drawings that contains only the latest revised drawings.
b. Refer to the Shift Operations Supervisor/Assistant Shift Operations Shift log book.
c. Refer to the Lead Unit Operators log book.
d. Refer to Document Control for assistance.

0 REACTOR OPERATOR Page 33 STION: 053 (1.00)

A surveillance is in progress, with the SOS (initials O.H.) direct'ing the actions of the "UO" (initials S.L.) i.n the plant. The procedure is in the possession of the "UO". WHICH ONE (1) of the following describes the initials that the "UO" is to place on the surveillance step?

a; OH/SL

b. SL/OH
c. OH
d. SL QUESTION: 054 (1.00)

WHICH ONE (1) of the following statements DEFINES a radiation area?

a. An area where an individual can be exposed to dose rates exceeding 5 mrem/hr or receive up to 40 mrem total exposure in any eight (8) hour period.
b. An area where an individual can be exposed to dose rates exceeding 100 mrem/hr or receive up to 3 REM total exposure in any five (5) consecutive days.
c. An area where an individual can be exposed to dose rates exceeding 5 mrem/hr or receive up to 1QQ mrem in any five (5) consecutive days.
d. An area where an individual can be exposed to dose rates exceeding 10 mrem/hr or receive up to 8Q mrem in any eight (8) hour period.

REACTOR OPERATOR Page 34 STION: 055 (1 00)

During a Site Area Emergency, the Site Emergency Director is informed

'that the UO on building rounds did not report to the Control Room and does not respond to the plant paging system. WHICH ONE (1) of the following is the maximum exposure allowed to an individual in order to search for the unaccounted for operator?

a. BFNP administrative limits
b. 10CFR20 non-emergency limits
c. 25 REM
d. 75 REM QUESTION: 056 (1.00)

WHICH ONE (1) of the following is the maximum length of time a confined space entry permit is valid without an extension?

b. 12 hours
c. 24 hours
d. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

B.'>

REACTOR OPERATOR Page 35 STION: 057 (1.00)

WHICH ONE (1) of the following is an acceptable way to perform position verification on a throttled valve? (assume that the valve is installed in a system with a local flow indication controlled by the valve, and the valve has a rising stem)

a. observe the initial valve operator's action in positioning the throttled valve
b. perform an independent visual check of the valve position by observing the valve stem
c. independently verify the valve position by a second valve operation
d. by observing flow indication through the throttled valve's system QUESTION: 058 (1.00) event occurs that, is required to be logged in the Operating Logs ~

NE (1) of the following states ALL the Operations Narrative Logs the event would be required to be recorded in according to SSP-12.1, "Conduct of Operations".

a. SOS
b. SOS, ASOS
c. SOS, ASOS, UO d SOS J ASOS g UO ~ STA

REACTOR OPERATOR Page 36 STION: 059 (1.00)

~

A valve will be

~

manipulated at rated power that may influence RPV level.

WHICH ONE (1) of the following forms of verification would ensure the correct valve is manipulated?

a. Supervisor Verification
b. Second Party Verification
c. Independent Verification
d. Responsible Manager Verification QUESTION: 060 (1.00)

The plant is operating at power with three (3) hours remaining on a t

80%

24 hour LCO. The Wilson Load Dispatcher requests the base load to be increased 25 MWE for the remainder of the operating run. WHICH ONE (1) of the following actions should be taken?

a. Before increasing the electrical load, the request must be approved by EITHER the SOS or the ASOS.
b. Before increasing the electrical load, the, request must be approved by BOTH the SOS and the ASOS.
c. Before increasing the electrical load, the request must be approved by any licensed individual.
d. The request for a load increase cannot be approved at this time.

REACTOR OPERATOR Page 37 STION: 061 (1.00)

~

Four licensed UOs attended a fellow employee's birthday party the last night of their vacation and alcohol was served to all. Below shows when

~ ~

each UO stopped drinking alcoholic beverages.

UO 'A':05 am UO 'B':05 am UO 'C':05 am UO 'D':05 am From the four UOs listed above, WHICH ONE (1) of the following states the number available for NRC licensed work the same morning at 7:00 am?

(Assume that all the UOs have blood alcohol levels within SSP 1.6 guidelines).

a. ONE t
b. TWO
c. THREE
d. FOUR

0 REACTOR OPERATOR Page 38 STION: 062 (1 00)

Six operators enter the RCA. Upon exiting, the following measurements were observed using the frisker:

Operator 1 200 cpm above background skin contamination.

Operator 2 85 cpm above background skin contamination.

Operator 3 50 cpm above background personal clothing contamination.

Operator 4 150 cpm above background personal clothing contamination.

Operator 5 250 cpm above background personal clothing contamination.

Operator 6 125 cpm above background personal clothing contamination.

WHICH ONE (1) of the following indicates the number of operators that

,are considered contaminated in accordance with procedure SSP 5.1, "Radiation Protection Plan" ?

a. Four
b. Three co Two
d. One QUESTION: 063 (1.00)

Units 1 and 3 are defueld. Unit 2 is at 1004 power. A transient on Unit 2 results in declaring a Site Area Emergency and activation of the accountability siren. WHICH ONE (1) of the following describes the expected response of the Unit 1 and Unit 3 operators?

a. Remain at their respective units and wait for further direction.

~ b. Report to Unit 2 and assist as directed by the SOS.

c. Unit 1 UOs report to the Unit 2 control room and Unit 3 Uos remain at their station.
d. Unit 3 Uos report to the Unit 2 control room and Unit 1 Uos remain at their station.

C3.

REACTOR OPERATOR Page 39 TION: 064 ( 1. 00)

WHICH ONE (1) of the following conditions requires entry into an EOI'?

a. Reactor Building floor drain sump level at 69 inches.

b,. Drywell temperature at 146 degrees F.

c. Secondary Containment dp is -0.19 inches H20.
d. Reactor zone ventilation exhaust radiation level at 68 mR/hr.

QUESTION: 065 (1 00)

During an ATWS with the reactor at high power, EOI-1, step RC/Q-7, directs that recirculation be run back to minimum prior to tripping the Reactor recirculation pumps. WHICH ONE (1) of the following is the basis for this action?

a. Prevent MSIU closure on high flow.
b. Promote boron mixing.
c. Prevent Main Generator reverse power trip.
d. Prevent Main Turbine high RPU water level trip.

CS.

REACTOR OPERATOR Page 40 STION: 066 (1.00)

Given the following plant conditions:

Reactor pressure is 930 psig RPV level is +28 inches RCIC is injecting Twenty control rods are at position 48 Reactor power is 9000 cps on the SRMs and decreasing A 90 degree F/hr cooldown is in progress WHICH ONE (1) of the following would require termination of cooldown?

a. RPV level lowers to +15 inches.
b. SRM count rate increases to 10000 cps.
c. Main turbine bypass valves fail closed.
d. Drywell pressure begins to increase.

ION: 067 (1. 00)

WHICH ONE (1) of the following responses will be noted on Unit 2 during a complete loss of Unit 2 I&C Bus during reactor operation?

a. Unit 2 reactor water level increase
b. Unit 1 Loop A recirculation pump speed increase
c. Unit 3 SJAE flow to offgas system increase
d. Unit 2 main steam tunnel temperature increase

.REACTOR OPERATOR Page 41 STION: 068 (1.00)

During a plant transient on Unit 2, a Group I isolation is caused by high radiation. Five control rods fail to insert. Suppression pool level is 12 feet and pool temperature is 94 degrees F.

WHICH ONE (1) of the following identifies the systems available to help maintain pressure below 1040 psig'?

a. HPCI, RCIC
b. RCIC, RWCU'.

RWCU, MSL drains

d. MSL drains, HPCI QUESTION: 069 (1.00)

During an

~

ATWS, EOIs direct the operator to inhibit ADS automatic wdown when Standby Liquid Control is injected. WHICH ONE (1) of the lowing states the basis for this requirement'?

~

a. ADS actuation would impose a severe pressure and temperature transient on the vessel.
b. ADS would result in the removal of boron after injected.

it has been

c. Core damage could result from a large power excursion pressure ECCS systems were to inject.

if low

d. ADS/MSRV system flow rate is incapable of assuring fuel cooling through steaming above 54 reactor power.

d%.

REACTOR OPERATOR Page 42 STION: 070 (1. 00)

While the reactor is operating at 90% power, reactor pressure is observed decreasing at an approximate rate of 200 psig per minute.

WHICH ONE (1) of the following is the expected immediate operator action'?

a. Scram the reactor and place the pressure control unit in manual.
b. Scram the reactor and close the MSIVs.
c. Take manual control of the reactor pressure control unit.
d. Manually transfer to the backup pressure control unit.

QUESTION: 071 (1.00)

A failure of Drywell Control Air has resulted in Drywell control air being supplied by the Plant Control Air header. WHICH ONE (1) of the following is a concern during the malfunction?

~

a. Moisture in the air

~

may cause critical valves to fail.

b. Torus temperature may increase.
c. Drywell oxygen level may increase.
d. Breathing air is unavailable.

. REACTOR OPERATOR Page 43 STION: 072 (1.00)

WHICH ONE (1) of the following systems is used to inject Alternate Standby Liquid Control (SLC) boron into the reactor?

a. Suppression Chamber Head Tank system I
b. Control Rod Drive system
c. RHR Standby Coolant system
d. Condensate and Feedwater system QUESTION: 073 (1.00)

The reactor has experienced an incomplete scram. WHICH ONE (1) of the following methods of rod insertion requires first resetting the SCRAM?

t a. De-energization of scram solenoids

b. Venting of the scram air header
c. Scraming individual control rods using test switches
d. Venting the Control Rod Drive over piston volume QUESTION: 074 (1 00)

~

WHICH ONE (1) of the following constitutes a loss of Secondary containment?

a. The Reactor Building normal HVAC is inoperable and isolated.
b. Both Reactor Building ventilation radiation. monitors are INOP.
c. The Reactor Building/Suppression Chamber vacuum breaker is open.
d. The Standby Gas Treatment system is inoperable.

dS, REACTOR OPERATOR Page 44 STION: 075 (1.00)

~

EOI-2, Primary Containment Control, requires emergency depressurisation

~ ~

if

~

suppression pool level cannot be maintained within the safe region of curve 4, "SRV Tail Pipe Level Limit". WHICH ONE (1) of the following identifies the plant changes which both drive the plant toward the UNSAFE portion of the curve and an INCREASED possibility of SRV tail pipe failure?

a. decreasing suppression pool water level, decreasing reactor pressure
b. decreasing suppression pool water level, increasing reactor pressure
c. increasing suppression pool water level, decreasing reactor pressure
d. increasing suppression pool water level, increasing reactor pressure ION: 076 (1 00)

~

Within two minutes after a loss of Reactor Building Closed Cooling Water, AOI 70-1, "Loss of RBCCW", directs that the reactor be scrammed and both recirculation pumps be tripped. WHICH ONE (1) of the following is the basis for this action?

a. Loss of cooling will lead to filter demin inlet temperature increase and auto isolation of RWCU.
b. Loss of flow to RHR pump coolers will prevent the RHR system from meeting design criteria.
c. Loss of cooling to the Recirculation pump seals will lead to a primary coolant leak.
d. Loss of Drywell cooling will lead to an increase in Drywell pressure, actuating safety related equipment.

0 REACTOR OPERATOR Page 45 STION: 077 (1 00)

While the plant is operating at full power, a complete loss of Control Air is experienced. WHICH ONE (1) of the following containment isolation valves is designed to fail open under these circumstances?

a. Suppression Chamber vacuum relief valves
b. Main Steam Isolation Valve
c. Refuel zone ventilation dampers
d. RHR process water sampling valve QUESTION: 078 (1.00)

A pipe shear has resulted in Control Air pressure immediately decreasing t

to 0 psig. WHICH ONE (1) of the following will remain available?

a. Off Gas
b. Stator Cooling Water
c. Reactor Water Cleanup
d. Raw Service Water supply to fire systems QUESTION: 079 (1. 00)

WHICH ONE (1)'f the following plant changes will result in the indication from LI 3-52, Post Accident Range Level instrumentation, becoming more accurate?

a. Reactor pressure increases from 900 to 1125. psig.
b. Drywell temperature increases from 100 to 212 degrees.
c. Reactor building temperature increases from 100 to 130 degrees.
d. Reactor recirculation pumps are manually tripped.

d%.

REACTOR OPERATOR Page 46 TION: 080 (1. 00)

~

The reactor is shutdown with Recirculation pumps off. WHICH ONE (1) of the following indicates reactor coolant stratification?

~

a. Shutdown Cooling is out of service, RPV pressure is 5 psig, RX VESSEL FLANGE DR LINE temperature is 170 degrees F, and RX VESSEL FN NOZZLE N4B END temperature is 205 degrees F.
b. Shutdown Cooling is in service, RPV pressure is 5 psig, RX VESSEL BOTTOM HEAD temperature is 215 degrees F, and RX VESSEL FW NOZZLE N4B END temperature is 260 degrees F.
c. Shutdown Cooling is out of service, RPV pressure is 0 psig, RX VESSEL FLANGE DR LINE temperature is 130, and feedwater sparger temperature is 170.
d. Shutdown Cooling is in service, RPV pressure is 0 psig, RX VESSEL BOTTOM HEAD temperature is 140, and feedwater sparger temperature is 195.

0 d.)

REACTOR OPERATOR Page 47 STION: 081 (1.00)

A Reactor startup is in progress on Unit 2 when the following annunciators actuate. Current readings are also given.

CRD ACCUM CHG WTR HDR 1480 psig CRD DRIVE WTR FILTER DIFF PRESS HIGH 50 psid Given the following plant conditions:

Rx Power is 5%

Reactor Pressure is 550 psig Charging Water Pressure is 1480 psig ~decreasing slowlyg 1 Accumulator is XNOP due to water level 1 CRD High Temperature alarm WHICH ONE (1) of the following would be the correct IMMEDIATE action to take in accordance with 2-AOI-85-3, <<CRD System Failure" ?

a. A Manual Scram is required under current conditions.
b. A Manual Scram is required if another Control Rod High t c.

d.

Temperature alarm is received in conjunction with the LOW SUCTION PRESSURE A Manual Scram received.

A Manual Scram to 1400 psig.

alarm.

is required is required if a second if Charging Accumulator alarm Water Pressure CRD is decreases

0 0

8.)

REACTOR OPERATOR Page 48 STION: Q82 (1.QQ)

Unit 2 control room has been abandoned and reactor pressure is decreasing due to a controlled cooldown. Water level is being controlled with the RCIC system at remote shutdown panel 25-32, in accordance with 2-AOI-100-2, "Control Room Abandonment". When reactor pressure decreases to 50 psi, WHICH ONE of the following describes the status of the RCIC system under these circumstances?

a. tripped and isolated.
b. tripped but not isolated; can be restarted from Control Room
c. tripped but not isolated; can NOT be restarted from Control Room
d. RCIC is running QUESTION: 083 (1.00)

Unit 2 is operating \

at 1004 rated power when the following indications are received:

~

~

OG POST TREATMENT RADIATION HI-HI ALARM OG POST TREATMENT RADIATION HI-HI-HI/INOP ALARM OG PRETREATMENT RADIATION HI ALARM OG AVERAGE ANNUAL RELEASE LIMIT EXCEEDED ALARM WHICH ONE (1) of the following is the appropriate immediate operator action?

a. Reduce reactor power to 604 using recirc flow; manually scram the reactor.
b. Reduce reactor power to 604 using recirc flow; insert control rods in reverse order to shutdown the reactor.
c. Reduce core flow to 60%; manually scram the reactor.
d. Reduce core flow to 60%; insert control rods in reverse order to shutdown the reactor.

0 REACTOR OPERATOR Page 49 TION: 0&4 (1.00)

~

During operation at 1004 power, a turbine trip occurs, and subsequently

~

a reactor scram signal is generated. Mater level reaches -15 inches but

~ ~

is recovered by the operator using the feedwater system. Reactor pressure initially reaches 1105 psig, but is controlled normally thereafter by the turbine bypass valves. During response to the transient, the operator notes that neither recirculation pump is running. WHICH ONE (1) of the following is the basis for the recirculation pump trip?

a. To prevent damage to the recirculation pump seals when reactor pressure exceeds 1100 psig.
b. To add negative reactivity, counteracting the positive reactivity added due to the pressure increase which resulted from the turbine trip.
c. To promote level swell in the vessel, counteracting the shrink effects caused by the turbine trip.
d. To protect the recirculation pumps from loss of adequate NPSH caused by the vessel level shrink resulting from the turbine trip.

0 B.i REACTOR OPERATOR Page 50 STION: 085 (1.00)

~

A loss of all off-site ~

power has occurred at Unit 2. :You are directed to backfeed the Unit boards from the Diesel generators in order to start

~

a CCW pump andestablish the Main Condenser as a heat sink for cooldown.

WHICH ONE (1) of the following describes the effect of taking the 2 BACKPEED switches on the Unit Boards (Panels 9-23-7 and 9-23-8) to the BACKFEED position'?

a. Automatically trip and lockout the normal and alternate supply breaker, automatically trip the 43 switch to MANUAL, and allow the Unit Board to Shutdown Bus supply breaker to be manually closed.
b. Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to MANUAL, and allow the alternate supply to Unit Board breaker to be manually closed.
c. Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to AUTO and allow the alternate supply to Unit Board breaker to be manually closed.
d. Automatically trip and lockout the alternate supply breaker, automatically trip the 43 switch to AUTO and allow the normal supply to Unit Board breaker to be auto closed.

QUESTION: 086 (1. 00)

Reactor power is 254, main turbine on line, when a small air leak into the condenser starts to reduce vacuum. After performing the subsequent actions of 2-AOI-47<<3, "Loss of Condenser Vacuum", condenser pressure stabilizes at 24" Hg vacuum. WHICH ONE of the following actions is appropriate?

a. If condenser vacuum later decreases, trip the main turbine before condenser pressure reaches 7" vacuum.

.b. Trip the main turbine.

c. Start the mechanical vacuum pump.
d. Increase SJAE steam inlet pressure to 225 psig.

0 d5.

REACTOR OPERATOR Page 51 I

STION: 087 (1.00)

Control Room instrumentation and annunciation indicates that three turbine stop valves have drifted to 804 open. No rod movement has occurred. You observe that the individual blue lights for each control rod on the full-core display are illuminated. Also, the eight scram solenoid group indicating lights are extinguished. WHICH ONE (1) of the following is a possible cause for the failure to SCRAM'?

a. Failure of scram pilot valves to open.
b. Only one RPS bus is de-energized.
c. Failure of scram inlet and outlet valves to open.

d- Hydraulic lock on the scram discharge volume.

QUESTION: 088 (1.00)

Unit 2 is operating at 25% power when a loss of I&C bus "A" occurs. RPV evel control is selected to Level "A". Recirc pumps are in individua ua 1 control. WHICH ONE (1) of the following describes the"expected l

nt response and operator actions for this event?,

a. Feed flow will increase until the turbine trips on high level.

A manual SCRAM should be inserted.

b. Recirc pump B will run back to minimum speed, Recirc pump A will experience a scoop tube lockup. Recirc pump A should be manually run back to minimum speed.
c. Recirc flow will increase until the Reactor scrams on high flux.

Both recirc pumps should be manually run back to minimum.

d. Recirc pump A will run back to minimum speed, Recirc pump B will experience a scoop tube lockup. Recirc pump B should be, manually run back to minimum speed.

~ REACTOR OPERATOR Page 52 I

TION: 089 (1.00)

Given the following plant conditions:

RPV level +56 inches RPV pressure 1040 psig Drywell press. 2.40 psig Torus level +1 inch Rx zone vent rad 75 mr/hr Refuel zone vent rad 62 mr/hr WHICH ONE (1) of the following EOI groups should be entered?

a. EOI-1, "RPV Control" and EOI-2, and EOI-4, Radiation Release Control.
b. EOI-1, "RPV Control" and EOI-2, "Primary Containment Control".
c. EOI-2, "Primary Containment Control" and EOI-3, "Secondary Containment Control"..
d. EOI-3, "Secondary Containment Control" and EOI-4, Radiation Release Control.

QUESTION: 090 (1.00)

Unxt 2 is operating at rated power when all RBCCW pumps trip and none can be restarted. WHICH ONE (1) of the following describes the IMMEDIATE operator actions appropriate for this situation?

a. Reduce recirculation flow to minimum, if recirc pump seal cavity temperature exceeds 200 degrees F on BOTH pumps, TRIP both recirc pumps and SCRAM the reactor.
b. If drywell temperature exceeds 145 degrees F, or drywell pressure exceeds 1.66 psig, insert a manual SCRAM, and trip both recirculation pumps.
c. Run recirculation pumps to 454 speed, insert, a manual SCRAM, Trip both recirculation pumps, and initiate a cooldown of 90 degrees F/hour.
d. IMMEDIATELY TRIP both recirc pumps and SCRAM the reactor.

0

~ I

REACTOR OPERATOR Page 53 TION: 091 (1.00)

While offloading fuel bundles from the reactor, fuel pool level begins to decrease uncontrollably. WHICH ONE (1) of the following describes a method available from the control room to add water to the fuel pool?

a. Align fuel pool cooling and cleanup heat exchanger RBCCW supply to the fuel pool to maintain level.
b. Start an RHR pump and inject to the reactor vessel to maintain fuel pool level.
c. Open emergency makeup supply valve from EECW to the fuel pool to maintain level.

~I

d. Open the CST to Fuel Pool Gravity drain valves.

i QUESTION: 092 (1 00)

WHICH ONE (1) of the following scram signals is effective ONLY when the mode switch is in RUN?

a. IRM hi-hi
b. Turbine stop valve closure
c. MSIV closure
d. EHC low oil pressure QUESTION: 093 (1.00)

Unit 2 is operating at 254 power. WHICH ONE (1) of the following combinations of events will NOT result in a half reactor scram?

a. Both MSIV's in steam lines "A" and "B" isolate
b. Both MSIV's in steam lines "A" and "D" isolate
c. APRM "E" and "C" trip on hi-hi flux
d. APRM "E" and >>A" trip on hi-hi flux 0

REACTOR OPERATOR Page 54 STION: 094 (1. 00)

WHICH ONE (1) of-the following conditions requires a manual reactor SCRAM?

a. RBCCW pump suction header temperature of 102 degrees F
b. Pre-treatment radiation HI-HI-Hi
c. Both recirculation pumps trip with the mode switch in Startup
d. Off-gas system Hydrogen concentration of 54 QUESTION: 095 (1.00)

WHICH ONE (1) of the following conditions assures ADEQUATE CORE COOLING?

a. All rods inserted, RPV level -200, MSRV's cycling on pressure, no injection flow.
b. RPV level unknown, 6 MSRV's open, reactor pressure is 10 psig.
c. Reactor power 3%, RPV level -210, one MSRV open, HPCI injecting at maximum flow.
d. RPV level -230, RHR "B" and "D" injecting at maximum flow, suppression pool level at 15 feet.

d5.

, REACTOR OPERATOR Page 55 1

TION: 096 ( 1. 00)

The Control Room has been abandoned. All MSRV transfer switches at panel 25-32 have been placed in EMERGENCY. All MSRV control switches at panel 25-32 are in CLOSE. WHICH ONE (1) of the following states the opening capability of the MSRUs?

a. ONLY manually by placing the panel 25-32 control switches in ~

OPEN

b. ONLY manually OR upon receipt of an ADS initiation signal
c. ONLY manually OR when their respective pressure relief setpoint is reached
d. EITHER manually OR on an ADS initiation signal OR when their respective pressure relief setpoint is reached QUESTION: 097 (1 00) loop I is in shutdown cooling taking suction through Shutdown ing suction valves 74-47 and 74-4&.

I standby lineup. Due to misoperation Loop II of RHR remains in the of ventilation systems, Drywell pressure increases to 2.5 psig. WHICH ONE (1) of the the response of the RHR system? following'escribes

a. Valves 74-47 and 74-48 close, Loop I suppression pool suction valves auto open and BOTH RHR loops inject to the vessel.
b. Valves 74-47 and 74<<48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves auto open but only Loop II injects.
c. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and only Loop injects.

II

d. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and NEITHER Loop injects.

0 dS.i REACTOR OPERATOR Page 56 STION: 098 (F ~ 00)

An emergency exists which requires addition of water to the suppression

~

pool. Your supervisor directs use of Appendix 18 of the Emergency Procedures. Using Appendix 18, WHICH ONE (1) of the following describes the availability of HPCI and RCIC'?

a. Neither HPCI nor RCIC are available if they have isolated.
b. Both HPCI and RCIC are available even if they have isolated.
c. HPCI is available unless if isolated. it has isolated; RCIC is available even
d. RCIC is available unless if isolated.

it has isolated; HPCI is available even QUESTION: 099 (1.00)

WHICH ONE (1) of the following is the Technical Specification safety it for reactor pressure?

a. 1120 psig
b. 1125 psig
c. 1250 psig
d. 1375 psig

d%.

REACTOR OPERATOR Page 57 STION: 100 (1 ~ 00)

Unit 3 fuel loading is in progress. WHICH ONE (1) of the following lists the two required communication links between the Unit operator and the refuel bridge?

a. PAX phone and radio
b. PAX phone and Paging system
c. Sound Powered phone and radio
d. Sound Powered phone and Paging system

(**********

END OF EXAMINATION **********)

0 REACTOR OPERATOR Page 1 ANSWER K E Y MULTIPLE CHOICE b 001: d ar 024 b 002 b 025 m

a 003 a 026 b 004 b 027 c 005 6 028 c 006 c 029 b

'23 007 a 030 c ooe a 031 b 009 a 032 a d 033 a 011 cj 034 a 012 c 035 d 013 b 036 a 014 c 037 a 015 c 038 c 016 c 039 c 017 O4O a 018 c 041 b 019 a 042 b 020 a 043 b 021 a 044 c O45 a

REACTOR OPERATOR Page 2 A N S W E R K E Y 046 cj 069 c 047 ' 070 b 048 c 071 c 049 b 072 b 050 c 073 c 051 074 6 052 d 075 053 d 076 6 054 c 077 a 055 078 b 079 6 057 a or d 080 a 058 c 081 059 b 082 6 060 083 a 061 P' 084 b 062 a OS5 a 063 a 086 'b O64 a 087 065 6 088 b 066 b 089 c 067 8 090 c b 091 b

B.i REACTOR OPERATOR Page 3 ANSWER K E Y 092 c 093: b 094 6 095 a 096 c 097 ~J 098 c 099 6 100 c 0

(**********

END OF EXAMINATION **********)

REACTOR OPERATOR Page 58 WER 001 (1. 00) a.g b

REFERENCE:

1. 'echnical Specification 4.3.B.1.a OPL171 ~ 006, Obj. 14

'/3 ')

2 ~

3 ~ K/Ae 201003G001 (3 201003G001 .. (KA's)

ANSWER: 002 (1. 00) b.

REFERENCE:

OPL171. 006, Ob K/A: 201001K303 j ~ 130 (3. 1/3. 2) 201001K303 .. (KA's)

ANSWER: 003 (1. 00) a~

REFERENCE:

1. OPL171.029, Obj. 1, page 9 2~ K/A 201002G008 (3 ~ 6/3 ~ 4) 201002G008 ..(KA's)

0

REACTOR OPERATOR Page 59 WER: 004 (1. 00) b.

REFERENCE:

1. 'PL171.016 Obj. 4, page 19
2. K/A: 223001A302 (3.4/3 4) 223001A302 ..(KA's)

ANSWER: 005 (1.00) t

REFERENCE:

OPL 171.029, Obj.9, pages 21, 26 K/A: 201002A402 (3 5/3 . 5) 201002A402 ..

~

(KA's)

ANSWER: 006 (F 00)

C~

REFERENCE:

1. OPL171.020, Obj. 5 2 ~ K/A: 215003K401 (F 7/3.7) 215003K401 ..(KA's)

8 REACTOR OPERATOR Page 60 WER: 007 (1 00) a~

REFERENCE:

1.: OPL171.043, Obg. 4, page 9 2 ~ K/A: 2 18000K403 (3 8/4 0)

~ ~

2 18 OOOK4 03 .. (KA's)

ANSWER: 008 (1. 00)

REFERENCE:

OPL171.009, Obj. 5, page 12 K/A: 239002K605 (3 0/3 '}

239002K605 ..(KA's)

ANSWER: 009 (1.00) a~

REFERENCE:

1. 2-AOI-85-3, Rev 10, p. 3 of 5, "Caution" GE SIL 139 2..

3 K/A: 201001A208 (2 '/2 ')

REACTOR OPERATOR Page 61 WER 010 (1. 00) cl 0 REFERENCE

1. 'PL171.033, Obj. 3, page 14
2. AOI 66-2, page 1 3 ~ K/A: 272000K403 (3.6/3 ')

272000K403 .. (KA's)

ANSWER: 011 (1.00) d.

REFERENCE:

OPL171.044, Obj. 11, page 27 K/A: 226001A403 (3 5/3 4)~ ~

226001A403 ..(KA's)

ANSWER: 012 (1. 00)

Co

REFERENCE:

1. OPL171.044, Obj.14, page 29
2. K/A: '03000K601 (3 6/3. 7)

~

203000K601 .. (KA's)

REACTOR OPERATOR Page 62 WER: 013 (1. QO) b.

REFERENCE:

1.: OPL171.Q44, Obj. 12, page 30

2. K/A: 205000A302 (3 2/3. 2)

~

205000A302 .. (KA's)

ANSWER: 014 (1. 00)

Co REFERENCE OPL171.043, Obj. 4, pages 9, 10 K/A 218000K501 (3 '/3 8) 218000K501 .. (KA's)

ANSWER: 015 (1. 00) co

REFERENCE:

1. Technical Specification 4.6.E.1 2.
3. K/A: 202001G005 (3.4/4 ')

OPL171.007, Obj. 32, page 54 202001G005 ..(KA's)

REACTOR OPERATOR Page 63 WER 016 (1 00)

Co

REFERENCE:

1.: OPL171.Q07, Obj. 31, pages 54, 34 OI-68, page 6 2.

3 ~ K/A: 202002G010 (3 '/3 ')

202002G010 .. (KA>s)

ANSWER: 017 (1. 00) i

'6 ~

REFERENCE:

OPL171.007, Obj. 26, page 50, Table 1 K/A: 202001K402 (3 '/3 ')

2020Q1K402 .. (KA's)

ANSWER 018 (1 00)

C~

REFERENCE

1. OPL171.007, Obj. 8, page 21 2~ K/A: 202002K305 (3. 2/3. 3) 202002K305 .. (KA's)

REACTOR OPERATOR Page 64 WER: 019 (1.00) a.

REFERENCE:

1. " OPL171.007, Obj.10, page 23 2 ~ K/A: 202001A411 (3 2/3 3)

~ ~

202001A411 ..(KA's)

ANSWER: 020 (1. 00) a~

REFERENCE OPL171.042, Obj 6, page 33 K/A: 206000K204 (2 ~ 5/2 ~ 7) 206000K204 .. (KA s)

ANSWER: 021 (1. 00)

REFERENCE

1. OPL171.042, Obj. 4, page 8
2. K/A: 206000K419 (F 7/3.8) 206000K419 .. (KA's)

REACTOR OPERATOR Page 65 WER: 022 (1 00) d.

REFERENCE:

1. 'PL171 022, Ob j ~ 7
2. K/A: 215003K106 (3.9/4.0) 215003K106 .. (KA's)

ANSWER: 023 (1 00}

REFERENCE:

OPL171.045, Obj. 8, page 14 K/A: 209001K404 (3. 0/3 2)~

209001K404 ..(KA's)

ANSWER: 024 (1.00) b.

REFERENCE:

1. OPL171.045, Obj. 2a, page 20
2. K/A: 209001K408 (3.8/4.0)

..(KA's)

REACTOR OPERATOR Page 66 WER: 025 (1 00) a~

REFERENCE:

1.  : OPL171.017, Obj. 7, page 14 2.

3 ~ K/A: 223002A102 (3 '/3 ')

OPL171.045, Obj. 2b, page 12 223002A102 .. (KA's)

ANSWER: 026 (1. 00)

REFERENCE:

OPL171.017,

~ Obj.~ 7, page 13

~

K/A: 223002K101 (3. 8/3 ~ 9) 223002K101 ..(KA's)

ANSWER: 027 (1.00)

Co

l(

REACTOR OPERATOR Page 67

REFERENCE:

OPL171. 009, Obj. 14 OPL171.017, Obj. 6, page 19 K/A: 239001A212 (4.2/4.3) 239001A212 .. (KA's)

ANSWER: 028 (1. 00)

C~

REFERENCE:

1.

2 ~ K/A: 211000A308 (4.2/4 ')

OPL171.039, Obj. 6, page 21 211000A308 .. (KA's)

ANSWER: 029 (1. 00) b.

REFERENCE 1~

2~

OPL171 030 t Ob j 1 K/A: 271000K104 (2 7/2 7)

~ ~

271000K104 .. (KA's)

ANSWER: 030 (l. 00)

C~

0

REACTOR, OPERATOR Page 68 t

REFERENCE:

OPL171.023 Objective 2, Rev 2, p. 10 K/A: 215001A208 (F 7/2.9) of 44 215001A208 .. (KA's)

ANSWER: 031 (1 ~ 00) b.

'EFERENCE:

1. OPL 171.053, Rev 3, p. 13 of 46, Obg. 6 2 ~ K/A: 234000K502 (3 '/3.7) 234000K502 .. (KA's)

ANSWER: 032 ( 1. 00) a~

REFERENCE:

'/3 ') of 62

1. OPL171.033, Rev 4, p. 21
2. K/A: 288000K105 (3 288000K105 .. (KA's)

ANSWER: 033 (1.00) a~

8.)

REACTOR OPERATOR Page 69 OPL171.013, Rev 3, p. 8 of 33, Objective 2 OPL171.056, Rev 3, p. 7 of 23, Objective 1.a K/A: 290002K114 (2 '/3.1) 290002K114 ..(KA's)

ANSWER: 034 (1. 00) a~

REFERENCE:

1.

2~ K/A 262001K401 (3 '/3 ')

OPL171.038, Obj. 5, page 17 OF 75 262001K401 .. (KA's)

ANSWER: 035 (1 00) 6~

REFERENCE:

1. OPL171.038, Obj. 11, page 52 OF 75 2~ K/A 264000G007 (3 6/3 8) ~

264000G007 .. (KA s)

ANSWER: 036 (1. 00)

0' REACTOR OPERATOR Page 70

REFERENCE:

~ ~

OPL171.038,

'/3 ')

Obj. 12, page 60

~

~ ~

K/A 264000K506 (3 ~ ~

264000K506 .. (KA's)

ANSWER: 037 (1. 00)

'a ~

REFERENCE:

l. OPL171.037, Obj. 9, page 17 of 26 2 ~ K/A 26300QK303 (3 4/3 8) ~

263000K303 .. (KA's)

ANSWER 038 (1. 00)

Co REFERENCE

1. OPL171.036, REV 2, Obj. 12, page 19 of 37 2 ~ K/A 263000K101 (3 '/3.5) 263000K101 ..(KA's)

ANSWER: 039 (1. 00)

Ce

0 d%.:

. REACTOR OPERATOR Page 71 REFERENCE OPL171.067, Obj. 11, 27 K/A: 290001K107 (3 ~ 0/3. 1) 290001K107 ..(KA's)

ANSWER 040 (1. 00) a~

REFERENCE:

1. OPL171.049, Obj. 5, page 41 2 ~ K/A: 286000K402 (3. 3/3 5) ~

286000K402 .. (KA's)

ANSWER: 041 (1 00) b.

REFERENCE:

1. OPL171.049, Obj. 2,5, Page 45 2 ~ K/A: 286000A105 (3 2/3 2) ~

286000A105 .. (KA's)

ANSWER: 042 (1. 00) b.

REACTOR OPERATOR Page 72

REFERENCE:

I Obj.

')

~

OPL171 ~ 011, ~ 4 K/A: 256000K107 (2.9/2

~ ~

256000K107 ..(KA's)

ANSWER: 043 (1. 00) b.

REFERENCE:

l. OPL171. 011, Obj . 4 2~ K/A: 256000A107 (3 . 1/3 . 1) 256000A107 .. (KA's)

ANSWER: 044 ( 1 ~ 00)

Ca REFERENCE

l. OPL171.044( Obj. 9 2 ~ K/A: 203000K202 (2. 5/2 ~ 7) 203000K202 .. (KA's)

ANSWER: 045 (1. 00) a~

0

REACTOR OPERATOR Page 73 REFERENCE AOI 100-1, page 26 K/A: 212000K412 (3 ~ '/4 ')~

212000K412 ..(KA's)

ANSWER: 046 (1. 00)

REFERENCE

1. OPL171.033, Obj. 1 2~ K/A: 272000K402 (3.7/F 1)

.. (KA's)

ANSWER: 047 (1. 00) b.

REFERENCE:

1. OPL171.035, Obj. 8
2. K/A: 2 150 02K502 (2 ~ 4/2 ~ 5) 215002K502 .. (KA's)

ANSWER: 048 (1 00)

~

d%.i REACTOR OPERATOR Page 74

REFERENCE:

~

OPL171.012,

~ Rev 4, p.~ 30 of 55

~ K/A: 216000K312 (3. 7/3 ~ 8)

I 216000K312 .. (KA's)

ANSWER: 049 (1 00) b.

REFERENCE

1. OPL171.012, Rev 5, Obj. 6, page 24 of 55 2 ~ K/A: 259002K604 (3.. 1/3 1)~

259002K604 .. (KA's)

ANSWER: 050 (1.00)

C~

REFERENCE:

1. 2-OI-3, Rev 23, Precaution 3.1
2. 2-AOI-3-1, Rev 7, 3.1, 3.2 3 ~ K/A: 259001A310 (3.4/3.4) 259001A310 .. (KA's)

ANSWER: 051 (1. 00)

d.

REACTOR OPERATOR Page 75

REFERENCE:

EOZPM Section XZ-B, Operator Cautions, page 4 K/A: 216000K507 (3.6/3.8) 216000K507 .. (KA's)

ANSWER: 052 (1. 00) d.

REFERENCE:

of 1~

2.

SSP 2 ~ 8 g REV 003 g K/A: 294001A101 (2.9/3 p 9

') 37

.. (KA's)

ANSWER: 053 (1. 00) d.

REFERENCE:

1~ SSP-12 F 1, P. 81-95

2. KA: 294001A102 (4.2*/4.2*)

294001A102 .. (KA's)

ANSWER: 054 (1 00)

C~

d5.

REACTOR OPERATOR Page 76

REFERENCE:

RCI-1, REV 0033, p. 19 K/A: 294001K103 (3.3/3 ')

294001K103 ..(KA's)

ANSWER: 055 (1. 00) d.

REFERENCE:

1~ RCI 2 g REV 0020' 6

2. EPIP 15, section 3.1 3 ~ K/A: 294001K103 (3 '/3 8)

..(KA's)

ANSWER: 056 (1 00) b.

REFERENCE:

1. RCI-13, page 5
2. K/A: 294001K114 (3 '/3 ')

294001K114 .. (KA's)

ANSWER: 057 (1. 00)

a. 0~ g 0

0 dR.

, REACTOR OPERATOR Page 77

REFERENCE:

SSP 12.6, page 7 OI VOL 13' GOI 300 3g p 7 of 10 K/A: 294001K101 (F 7/3 7) 294001K101 .. (KA's)

ANSWER: 058 (F 00)

Co

REFERENCE:

1. SSP-12.1, REV 0008, p. 59 of 95 2 ~ K/A: 294001A106 (3 4/3 6)

..(KA's)

ANSWER 059 (1 00)

REFERENCE:

1.

2 SSP-12.6, REV 0001, p.

K/A: 294001K101 (3.7/3 ') of 4 20 and p. 7 of 20 294001K101 .. (KA's)

ANSWER: 060 ( 1. 00)

REACTOR OPERATOR Page 78

REFERENCE:

SSP-12.1, REV 0008, p. 34 of 95

~ ~

K/A: 294001A111 (3.3/4.3) ~

294001A111 .. (KA's)

ANSWER: 061 (1 00) p: q REFERENCE

1. 1.6, of

'/3 ')

002, p. 5 53 SSP REV 2 K/A: 294001K105 (3

.. (KA's)

ANSWER: 062 (1. 00) a~

REFERENCE:

1. SSP 5.1, page 10 2 K/A 294001K103 (3 '/3 ')

294001K103 .. (KA's)

ANSWER: 063 (1. 00) a~

d%.

REACTOR OPERATOR Page 79 REFERENCE OSZL 100 g P 2 of 3 t 5/24/93 K/A: 294001A106 (2.9/4.7) 294001A106 ..(KA's)

ANSWER:, 064 (l. 00) a~

REFERENCE:

1. OPL171. 204, Ob j 2 ~

2 ~ K/A: 295036G011 (3 8/4 1) ~

295036G011 ..(KA's)

R: 065 (1.00) 6~

REFERENCE:

1 2~

OPL171 ~ 202, Ob3 K/A'95037G007 (3 7/3

~ 13

')

295037G007 .. (KA's)

ANSWER: 066 (1 00) b.

, REACTOR OPERATOR Page 80

REFERENCE:

e OPL171.205, Obj. 7b K/A: 295015G012 (3.7/4.4) 295015G012 ..(KA's)

ANSWER 067 (1. 00) d.

REFERENCE:

1. OPL171.074, Obj. 1 2~ K/A: 295003A204 (3 4/3 5)

~

295003A204 ..(KA's)

ANSWER: 068 (1.00) b.

REFERENCE:

1. OPL171.202, Obj. 8 2 K/A 295025A105 (3 7/3.7) 295025A105 ..(KA's)

ANSWER: 069 (1. 00)

dS.i

, REACTOR OPERATOR Page 81

REFERENCE:

OPL171.~ 202, Ob) ~ 14 K/A: 295037G007 (3.~ 5/3.~ 7) 295037G007 .. (KA's)

ANSWER: 070 (1 00) b.

REFERENCE:

1. AOI 47-2, page 3 2 ~ K/A: 295020G010 (3 '/3.5)

.. (KA's)

ANSWER: 071 (1. 00)

C>>

REFERENCE:

1 2~

OPL171.054, Obg.

K/A: 295019G011 3

(3 '/4 ')

295019G011 .. (KA's)

ANSWER: 072 (1. 00) b.

,REA~OR OPERATOR Page 82

REFERENCE:

EOI Appendix 3B K/A: 295037K213 (3 '/4 ')

C 295037K213 .. (KA's)

ANSWER: 073 (1. 00)

REFERENCE:

1. EOI Appendices 1A, 1B, 1C, 1E 2 K/A: 295015K201 (3 '/3 9) 295015K201 .. (KA's)

R: 074 (1. 00)

REFERENCE

1. Tech Spec 3.7.C 2 K/A: 295033K204 (3.9/4.2) 295033K204 .. (KA's)

ANSWER: 075 (1.00) d.

,REACTOR OPERATOR Page 83

REFERENCE:

EOI-2, Primary Containment Control bases, page 113 K/A: 295029K301 (3 5/3 9)~

295029K301 ..(KA's)

ANSWER: 076 (1 00)

REFERENCE:

1. AOI 70-1, Attachment 1
2. K/A: 295018K101 (3.5/3.6) 295018K101 ..(KA's)

ANSWER: 077 (F 00) a0 REFERENCE

1. AOI 32-2, page 13-17 2 ~ OPL171 ~ 054, Obj. 5 3 ~ K/A: 295019K209 (3.3/3.3) 295019K209 ..(KA's)

ANSWER: 078 (1 00)

.REACTOR OPERATOR Page 84

REFERENCE:

AOI 32-2, page 13-17 OPL171.054, Obj 5 K/A: 295019A202 (3.6/3.7)

'295019A202 .. (KA's)

ANSWER: 079 (1 00)

REFERENCE:

1. OPL171.003, Obj.13, page 24 2 ~ K/A: 295009A201 (4 2/4 ~ 2)

~

295009A201 .. (KA's)

ANSWER: 080 (1. 00) a~

REFERENCE:

1. AOI 74-1
2. OPL171.046, Obj. 13
3. K/A: 295021K102 (3.3/3 ')

295021K102 ..(KA's)

ANSWER: 081 (1.00)

. REACTOR OPERATOR Page 85

REFERENCE:

2-AOI-85-3 Rev 10, p 2 of 5 (immediate actions)

K/A: 295022G010 (3.7/3.5)

~ ~

295022G010 .. (KA's)

ANSWER: 082 (1. 00) d0

REFERENCE:

1. 2-AOI-100-2, Note, Rev 2 Page 14 of 55
2. OPL171-040 Objective 4 3 ~ K/A: 295016K303 (3 '/3 7) 295016K303 .. (KA's)

WER: 083 (1.00) a~

REFERENCE

1. OPL171.074 Objective 2
2. 2-AOI-66-2 Rev 8, 4.1 3 K/A: 295017GQ1Q (3.9/3.&)

295017G010 ..(KA's)

ANSWER: 084 (1.00) b.

dS.

, REA~OR OPERATOR Page 86

REFERENCE:

Facility Question Bank 411043 OPL171.007 Objective 12 K/A: 29500SK302 (3.4/3.5) 295005K302 ..(KA's)

ANSWER: 085 (1 00)

'a ~

REFERENCE:

1. OPL 171.036( Rev 2 p. 18 of 37, Objective 12 2 ~ K/A 295003A101 (3. 7/3 8) 295003A101 .. (KA's)

ANSWER: 086 ( 1. 00) b.

REFERENCE-

1. 2-AOX-47-3, Rev 6, caution, p.2 of 4 2 ~ K/A: 295002A105 (3.2/3.2) 295002A105 ..(KA's)

ANSWER: 087 (1.00)

0, REACTOR OPERATOR Page 87

REFERENCE:

OPL 171.005, Rev 4, p. 39~ of 58, Objective 6 K/A 295015K201 (3.8/3 ~ 9) 295015K201 .. (KA's)

ANSWER 088 (1. 00) b.

REFERENCE:

l. 1-AOI-57-5A, Rev 10, Cautions, p. 3 of 44
2. K/A: 295003G007 (3 2/3 6) 295003G007 ..(KA s)

ANSWER: 089 (1.00)

Ce REFERENCE

l. EOI flowcharts
2. K/A: 295034G011 (4 2/4 3) 295034G011 .. (KA's)

ANSWER: 090 (F 00)

REACTOR OPERATOR Page 88

REFERENCE:

2-AOX-70-1, Rev 12, p. 2 ~ of 6, 4.1

~

K/A: 295018G010 (3.4/3.3) ~

295018G010 .. (KA's)

ANSWER: 091 (1 OQ) b.

REFERENCE:

2-AOI-78-1, Rev 7.

'/3 ')

1.

2. K/A: 295023GOQ6 (3 295023G006 .. (KA's)

R: 092 (1. 00)

C>>

REFERENCE:

1. OPL171.028, Rev 5, Table 2 ~ K/A: 295006K201 (4 '/4 ') 1 295006K201 .. (KA's)

ANSWER 093 (1. 00) b.

dR.

, REA~OR OPERATOR Page 89

REFERENCE:

~ ~

OPL 171.028, Rev 5, p. 16

~ ~ of 39 K/A: 295006A206 (3.5/3.8) ~

295006A206 ..(KA's)

ANSWER: 094 (1 00)

REFERENCE:

1. 2-AOI-100-1, Rev 26, Attachment 5.
2. EOI-2, Primary Containment Control, Rv 1, entry conditions 3 ~ K/A: 295028G010 (3 '/3 ')

.. (KA's)

ANSWER: 095 (F 00) a~

REFERENCE:

l. flowcharts: EOI-1, C-1, C-2, C-3.

2 EOI K/A: 295031A201 (4 '/4 ')

295031A201 .. (KA's)

ANSWER: 096 ( 1. 00)

REACTOR OPERATOR Page 90

REFERENCE:

OPL171.074, Ohj. 5 OPL171.009, Obj. 3 K/A 295016A108 (4 ~ 0/4 0) 295016A108 .. (KA's)

ANSWER: 097 (1- 00) d REFERENCE-

1. OPL171.044, Obj. 19, pages 22, 24, 28 2 ~ K/A: 295021A207 (3.1/3.2)

.. (KA's)

ANSWER: 098 ( 1. 00)

C~

REFERENCE:

1. EOI, Appendix 18
2. OI 74, page 42
3. K/A: 295030G012 (3.7/4.4) 295030G012 .. (KA's)

ANSWER: 099 (1 00) d.

B.

REA~OR OPERATOR Page 91

REFERENCE:

Tech Spec 1.2.A

~

K/A: 295025G003 (3.5/4.3)

~ ~

295025G003 .. (KA s)

ANSWER: 100 (1. 00) co REFERENCE

1. Facility question 2 K/A 294001A104 (3 '/3 ')

.. (KA's)

(********** END OF EXAMINATION **********)

U. S. NUCLEAR REGULATORY COMMISSION SITE SPECIFIC EXAMINATION SENIOR OPERATOR LICENSE REGXON 2 CANDXDATEiS NAME.

FACILITY Browns Ferry 1, 2, & 3 REACTOR TYPE:

DATE ADMINISTERED 93/09/27 INSTRUCTIONS TO CANDIDATE:

Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires a final grade of at least 804. Examination papers will be picked up four (4) hours after the e 'nation starts.

CANDIDATE~S TEST VALUE SCORE 100.00 TOTALS FINAL GRADE All work done on received aid.

this examination is my own. I have neither given nor Candidate's Signature

0 C5.

SENATOR REACTOR OPERATOR Page 2 A N S W E R SHEET r

Multiple Choice

~ ~

(Circle or X your choice)

If you change your answer, write your selection in the blank.

MULTIPLE CHOICE 023 a b c d 001  : a b c d 024 a b c d 002 a b c d 025 a b c d 003 a b c d 026 a b c d 004 a b c d 027 a b c d 005 a b c d 028 a b c d 006 a b c d 029 a b c d 007 a b c d 030 a b c d 008 a b c d 031 a b c d 009 a b c d 032 a b c d a b c d 033 a b c d 011 a b c d .034 a b c d 012 a b c d 035 a b c d 013 a b c d 036 a b c d 014 a b c d 037 a b c d 015 a b c d 038 a b c d 016 a b c d 039 a b c d 017 a b c d 040 a b c d 018 a b c d 041 a b ..-c d 019 a b c d 042 a b c d 020 a b c d 043 a b c d 021 a b c d 044 a b c d o a b c d 045 a b c d

SENX'OR REACTOR OPERATOR Page 3 A N S N E R SHEET Choice (Circle or X your choice) 'ultiple If you change your answer, write your selection in the blank.

046 a b c d 069 a b c d 047 " a b c d 070 a b c d 048 a b c d 071 a b c d 049 a b c d 072 a b c d 050 a b c d 073 a b c d 051' b c d 074 a b c d 052 a b c d 075 a b c d 053 a b c d 076 a b c d 054 a b c d 077 a b c d oss 057 a

a b

b b

c c

c d

d d

078 079 080 a

a a

b b

b c

c c

d d

d 058 a b c d 081 a b c d 059 a b c d 082 a b c d 060 a b c d 083 a b c d 061 a b c d 084 a b c d 062 a b c d 085. a b c d 063 a b c d 086 a b c d 064 a b c d 087 a b c d 065 a b c d 088 a b c d O66 a b c d 089 a b c d O67 a b c d 090 a b c d a b c d 091 a b c d

SENXOR REACTOR OPERATOR Page 4 A N S M E R S H E E T 0

Multiple Choice (Circle or X your choice}

Xf you change your answer, write your selection in the blank.

092 a b c d 093 " a b c d 094 a b c d 095 a b c d 096 a b c d 097 a. b c d 098 a b c d 099 a b c d 100 a b c d

(********** END OF EXAMXNATXON **********)

Page 5 NRC RU ES AND GUID IN S FOR LICENS EXAMINAT ONS 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 penalties.

2. After the examination has been completed, you must sign the statement on the cover sheet indicating 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 exam-ination.
3. 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 cheating.
4. Use black ink or dark pencil only to facilitate legible repro-ducti ons.
5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
6. Fill in the date on the cover sheet of the examination (if necessary).
7. Print your name in the upper r.ight-hand corner of the first page of each section of your answer sheets.
8. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
9. The point value for each question is indicated in "parentheses after the question.
10. Partial credit will NOT be given.

ll. If the intent of a question is unclear, ask questions of the examiner only.

'2.

When you are done and have turned in your examination, leave the examination area as defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.

SENIOR REACTOR OPERATOR Page 7 STION: 001 (1. 00)

~

reactor is being restarted near the end of core life following a one

'he

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day outage. Reactor power is at 324. Control rods 34-23 and 58-23 have been isolated at position 00. When rod 42-43 is withdrawn, alarm 2-XA-55-5A-29, CRD ACCUM PRESS LOW LEVEL HIGH, actuates on panel 9-5.

WHICH ONE (1) of the following requirements is in effect under the current plant conditions?

a. Exercise control rod 42-43 at least one notch at least once each day.
b. Clear the accumulator trouble alarm on rod 42-43 prior to moving the next control rod.
c. Control rod 42-43 must be fully inserted and electrically disarmed.
d. Observe nuclear instrumentation for response each time rod 42-43 is movedo Control Rod 38-23 has been selected for a single notch withdrawal from position 02 to position 04. The following response from the CRD system was observed:

Insert light illuminates and goes out.

Withdrawal light illuminates and goes out.

Settle light illuminates and goes out.

The operator also observes and reports that the selected rod is now at position 06 and is continuing to drift out. A Rod Drift alarm is also present. WHICH ONE (1) of the following has caused the 'conditions?

a. the automatic sequence timer has failed
b. stuck open collet fingers
c. excessive HCU cooling water pressure
d. leaking scram inlet valve

SENIOR REACTOR OPERATOR Page 8 TION: 003 ( 1. 00)

When a drywell-suppression chamber vacuum breaker valve is exercised through an opening-closing cycle, the position indicating lights in the control room respond as follows:

Initial Check ON, Green ON, Red - OFF Switch to OPEN Check OFF, Green - OFF, Red ON Switch to CLOSE (final) Check - OFF, Green - ON, Red - OFF WHICH ONE (1) of the following states the status of the tested valve'

a. operable for opening and considered fully closed
b. operable for opening but considered nonfully closed
c. inoperable for opening but considered fully closed
d. inoperable for opening and considered nonfully closed TION: 004 (1. 00) ile a control rod is being inserted using the EMERGENCY IN control switch, rod motion stops. WHICH ONE (1) of the following could have terminated rod insertion?
a. the automatic sequence timer deenergizes
b. loss of power to the Rod Position Information System
c. a RWM select block
d. a RWM insert block

SEN1OR REACTOR OPERATOR Page 9 TION: 005 (1.00)

A Main Steam Relief Valve (MSRV) lifts due to high reactor pressure.

of the following could cause a significant DECREASE in the WHICH ONE MSRV's lift pressure if it subsequently lifts a (1) second time'?

a. tailpipe vacuum breaker failed CLOSED
b. tailpipe vacuum breaker failed OPEN

'c. high drywell pressure d- high suppression pool level QUESTION: 006 (1. 00)

Given the following plant condition:

The Unit 2 Division I ECCS ATU Inverter has been declared inoperable.

~

H ONE (1) of the following actions is required?

a. Declare RCIC inoperable.
b. Declare HPCI inoperable.
c. Declare Core Spray "2A" pump inoperable.
d. Declare Core Spray "28" pump inoperable.

0 0

l ~ W SENlOR REACTOR OPERATOR Page 10 r

TION: 007 (1.00)

During a LOCA, the SRO directs you to initiate drywell sprays. The RHR SYS I CTMT VLV SELECT switch is in SELECT and the 2/3 Core coverage keylock switch is in OVERRIDE. RHR SYS I DW SPRAY INBD VLV (2-FCV 61) cannot be opened. WHICH ONE (1) of the following interlocks is preventing valve operation?

a. RPV level less than -122 inches
b. RPV level less than -183 inches c- LPCI initiation signal NOT present Drywell pressure less than 1.96 psig QUESTION: 008 (1.00)

An earthquake has resulted in a complete loss of off-site power and LOCA on Unit 2. Drywell pressure has increased to 5 psig on Unit 2.

rgency Diesel Generator "C" has failed to start. All other emergency t equipment is functioning normally. WHICH ONE (1) of the following ntifies the Core Spray pumps that will respond to the automatic start signal?

a. 2A, 2B
b. 2A, 2B, 2D C. 2Ar 2C
d. 2A, 2C, 2D

0 0

SENIOR REACTOR OPERATOR Page 11 r

TION: 009 (1. 00)

Conditions have been met to

~ ~

start the Automatic Depressurization System (ADS) 95 second timers. WHICH ONE (1) of the following identifies the ADS clear?

initiation signals that will NOT automatically reset if conditions

a. 95 second TIMER and Low Reactor Water Level TIMER
b. 95 second TIMER and Low Reactor Water Level signal
c. High Drywell pressure signal and Low Reactor Water Level TIMER
d. High Drywell pressure signal and Low Reactor Water Level signal QUESTION: 010 (1.00)

Reactor Recirculation pump "A" is operating at 1310 RPM and is providing 40,000 gpm flow. Reactor Recirculation pump "B" is operating at 1325 RPM. WHICH ONE (1) of the following states the LOWEST flow for Reactor irculation pump "B" that would indicate possible jet pump failure?

a. 44,000 gpm
b. 44,6QQ gpm
c. 46,000 gpm
d. 46,600 gpm

SEN1OR REACTOR OPERATOR Page 12 TION: 011 (1.00)

Reactor Recirculation pumps are not operated below 204 speed. RiICH ONE (1) of the following states the basis for this limit?

a. Ensures adequate Net Positive Suction Head.

b.'revents thermal stress in the vessel lower head region.

c. Prevents unstable fluid coupler operation.
d. Limits harmonic vibration of the get pumps.

QUESTION: Q12 (1.QQ) awhile Reactor Recirculation pump "A" is operating at 80%, a failure in pump's individual M/A station occurs and a signal is sent to the Bailey t

Positioner calling for a pump speed of zero. WHICH ONE (1) of the following states the expected response 'of the pump?

a. Scoop tubes will lock and speed will remain at 80%.
b. Speed decreases to 28%.
c. Speed decreases to 204.
d. Speed decreases to zero.

SENIOR REACTOR OPERATOR Page 13 STION: 013 (1.00)

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During an accident on Unit 2, power

~ ~ ~

is lost

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from the Division II ECCS inverter.

~

WHICH ONE (1) of the following HPCI system capabilities is lost?

a. Flow control
b. Automatic initiation
c. Automatic isolation
d. Automatic trip QUESTION: 014 (1.00)

HPCI is in standby readiness. (1) of the following states the if Torus level WHICH ONE t

HPCI pump suction status is +5 inches and the Condensate Storage Tank volume is 9900 gallons."?

a. Suction is from the CST but can be manually transferred to the Torus without bypassing interlocks.
b. Suction is from the CST and CANNOT be transferred to the Torus without bypassing interlocks.
c. Suction is from the Torus but can be manually transferred to the CST without bypassing interlocks.
d. Suction is from the Torus and CANNOT be transferred to the CST without bypassing interlocks.

d5; SENIOR REACTOR OPERATOR Page 14 STION 015 (1 ~ 00)

Startup is in progress with reactor pover at 264. While withdraving

~

control rod 34-23 from notch 24 to notch 48, position indication is lost to all control rods. Upon observing the loss of indication, the operator terminates rod withdrawal and verifies reactor power is stable.

WHICH ONE (1) of the following is the required action?

a. Declare rod 34-23 inoperable.
b. Decrease power below, the RNM LPSP using Recirculation flov.
c. Be in Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d. Immediately scram the reactor.

QUESTION: 016 (1.00)

With the plant operating at 100% pover, Alarm XA-S5-3F, window 31, CORE SPRAY SYS II SPARGER entifies the core BREAK, actuates. WHICH ONE (1) of the following spray line break location required to actuate the rm7i

a. inside of the reactor vessel shroud
b. inside of the reactor vessel and outside of the shroud
c. anywhere inside of the reactor vessel
d. anywhere on the pressurized portion of the injection line

d.i SENIOR REACTOR OPERATOR Page 15 STION: 017 (1. 00)

During a LOCA, reactor water level is dropping at a rate of 20 inches per minute. RPV level is currently -132 inches. RPV pressure is 468 psig and Drywell pressure is 2.5 psig. HHICH ONE (1) of the following describes the expected status of the Unit 2 Core Spray system?

a. Core Spray system has NOT initiated.
b. Core Spray pumps have started, injection valve is CLOSED.
c. Core Spray pumps have started, injection valve is OPEN, but pump flow is deadheaded against the closed check valve.
d. Core Spray pumps have started and are injecting into the vessel.

QUESTION: 018 (1.00)

The PSC pumps trip and cannot be restarted. %ICH ONE (1) of the following conditions is a possible reason for this occurrence?

a. RPV level is -118 inches.
b. RHR Room temperature is 182 degrees F.
c. 250V RMOV power is lost to Div I.
d. Suppression pool level is -6.25 inches.

0 SENIOR REACTOR OPERATOR Page 16 STION: 019 (1 00)

During plant startup with reactor power on range 5 of the IRMs, an MSIV closure occurs. WHICH ONE (1) of the following conditions is a possible reason for this occurrence?

a. Reactor water level is -83 inches.
b. MSL tunnel temperature is 210 degrees F.
c. Reactor pressure is 840 psig.
d. Drywell pressure is 2.6 psig.

QUESTION 020 (1. 00)

During a plant transient, the Main Steam Isolation Valves isolated on a valid Group I isolation actions signal. All control rods inserted and immediate operator required by procedure have been taken. A decision has been made to unisolate MSL "D" (valves 1-51 and 1-52) to allow use of e main condenser. Given the following plant conditions:

Reactor water level is -5 inches.

Reactor pressure is 700 psig.

Drywell pressure is 3.2 psig.

MSL Area temperature is 185 degrees F.

WHICH ONE (1) of the following states actions required to reset the Group 1 isolation?

a. The MSIV switches for ONLY valves 1-51 and 1-52 must be placed in the CLOSE position.
b. A jumper must be installed AND the MSIV switches for ONLY valves 1-51 and 1-52 must be placed in the CLOSE position.
c. The MSIV switches for ALL MSIVs must be placed in the CLOSE position.
d. A jumper must be installed AND the MSIU switches for ALL MSIVs must be placed in the CLOSE position.

li d.i SEN1OR REACTOR OPERATOR Page 17 y~

STION: 021 (F 00)

After a complete functional test of the SLC system the following data is reported:

Pump A Flow Rate 37 gpm Pump B Flow Rate 40 gpm Solution Concentration 9.14 Boron 10 Enrichment 674 WHICH ONE (1) of the following states the present status of the Standby Liquid Control System?

a. Both subsystems are operable.
b. Only subsystem A is inoperable.
c. Only subsystem B is inoperable.
d. Both systems are inoperable.

TION: 022 (1. 00)

Conditions exists on Unit 2 that require the initiation of Standby Liquid Control. WHICH ONE (1) of the following contains two iridications that SLC is injecting?

a. Explosive valve current flow indicator reads 0 milliamps AND the blue SQUIB VALVE CONTINUITY light is illuminated.
b. Explosive valve current flow indicator reads 4 milliamps AND the blue SQUIB VALVE CONTINUITY light is illuminated.
c. Explosive valve current flow indicator reads 0 milliamps AND the blue SQUIB VALVE CONTINUITY light is extinguished.
d. Explosive valve current flow indicator reads 4 milliamps AND the blue SQUIB VALVE CONTINUITY light is extinguished.

0 d.)

SENIOR REACTOR OPERATOR Page 18 STION: 023 (1.00)

Given that the following conditions exist during refueling on Unit 3:

Bridge is directly over the core Main hoist is loaded to 550 lbs, in the full up position Aux hoist is loaded to 350 lbs, in the full up position Rod 03-17 is at position 02 Mode Switch is in STARTUP WHICH ONE (1) of the following responses would indicate normal interlock functioning on the refuel bridge? (FORWARD means away from the core, REVERSE means toward the core.)

a. Bridge will move in the forward AND reverse directions.
b. Bridge will move in the forward direction BUT NOT reverse direction.
c. Bridge will move in the reverse direction BUT NOT forward direction.
d. Bridge will NOT move in either direction.

QUESTION: 024 (1.00)

Refueling preparations are in progress with the reactor vessel head removed and a partial load of fuel in the vessel.

WHICH ONE (1) of the following is a core alteration?

a. Withdrawal of Source Range Monitor
b. Removal of an LPRM string
c. Conduct of a TIP trace
d. Removal of a jet pump nozzle

d.)

SENIOR REACTOR OPERATOR Page 19 STION: 025 (1.00)

~

WHICH ONE (1) of the following describes the trip logic for the Reactor Building Ventilation Radiation Monitors (Reactor Zone Ventilation

~ ~ ~ ~ ~ ~

Radiation Monitors and Refuel Floor Radiation Monitors)

a. Two Hi levels in 1 division OR one downscale in 2 divisions
b. Two Hi levels in 1 division OR two downscales in 1 division
c. One Hi level in 2 divisions OR one downscale in 2 divisions
d. One Hi level in 2 divisions OR two downscales in 1 divisions QUESTION: 026 (F 00)

Shutdown Bus 1 was initially being supplied by Unit Board 2B when Shutdown Board B bus transfer switch (43) transfers to MANUAL. WHICH ONE (1) of the following is a possible reason for this occurrence'?

Shutdown Board B Normal Feeder Breaker (1616) Emergency Control Power Transfer Switch has been placed in the Emergency position.

The alternate power supply to Shutdown Bus 1 has sensed a high load differential condition across the 87Uxx breaker.

c. A phase or ground overcurrent condition has been sensed by the NORMAL shutdown bus power supply.
d. The residual voltage relay has shut in the close circuit of the alternate power supply to Shutdown Bus 1.

SENIOR REACTOR OPERATOR Page 20 1

STION 027 (1. 00)

A LOCA has occurred. Drywell pressure is 3 psig and no off-site power is available. WHICH ONE (1) of the following is the only load allowed to be sequenced onto its associated shutdown board before forty (40) seconds have elapsed'

a. RHRSW pumps
b. A and D Control Air Compressors
c. Drywell blowers
d. RBCCÃ pumps QUESTION: 028 (1.00)

Normal and alternate supply breakers to unit boards 3A and 3B have tripped and the Unit 3 Shutdown Board 43 auto transfer switches have transferred to MANUAL. WHICH ONE (1) of the following describes what happened?

a. An automatic shutdown bus transfer has taken place.
b. The associated 4 kV shutdown board has failed to transfer to the alternate power supply.
c. The associated backfeed switch has been placed in the BACKFEED position.
d. A manual U3 Unit Board high-speed transfer to the alternate power supply failed.

SENIOR REACTOR OPERATOR Page 21 STION: 029 (1.00)

During fails.

full power operation on Unit 2, the mechanical spaces exhaust fan WHICH ONE (1) of the following is a possible consequence of this failure7

a. Buildup of contaminants in the Radwaste building atmosphere.
b. Development of an explosive atmosphere in battery rooms
c. Main steamline isolation
d. Unreliable Emergency Range level indication QUESTION: 030 (1. 00)

An RSW pump has started to automatically increase level in the RSW I

storage tank when a fire pump receives an automatic start signal. WHICH ONE (1) of the following describes the response of the RSW storage tank isolation valves and the RSW pump'?

a. The RSW pump immediately trips. The isolation valves CLOSE but will AUTOMATICALLYreopen when the fire pump stops.
b. The RSW pump immediately trips. The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire 'pump stops.
c. The RSW pump continues running in support of the fire pump. The isolation valves CLOSE but will AUTOMATICALLYreopen when the fire pump stops.
d. The RSW pump continues running in support of the fire pump. The isolation valves CLOSE and the tank must be MANUALLY realigned when the fire pump stops.

d%.)

SENIOR REACTOR OPERATOR Page 22 STION: 031 (1 ~ 00)

The plant is being shutdown and reactor power is stable at 25% when annunciator "OFFGAS HOLDUP TEMPERATURE HIGH" actuates due to low flow through the SZAE condensers. WHICH ONE (1) of the following could have caused the event?

a. In-leakage of noncondensible gases into the main condenser. ~
b. SPE Heat Exchanger Balancing valve (FCV 2-190} -open.
c. Condensate demineralizer bypass valve (FCV 2-130) open.
d. Only two condensate pumps running.

QUESTION: 032 (1. 00)

RHR loop 1 is in standby when electrical power is lost to 480 volt RMOV board 2D. WHICH ONE (1} of the following RHR flowpaths is NOT available?

a. torus cooling
b. drywell spray
c. LPCI injection
d. pump minimum flow

d.i SENIOR REACTOR OPERATOR Page 23 r

STION: 033 (1 00)

WHICH ONE (1) of the following describes the conditions when RHR Unit cross-tie capability must be maintained?

a. Anytime there is irradiated fuel in the reactor.
b. Only when the reactor is NOT in COLD Shutdown.

c- Only when the reactor is NOT in HOT Shutdown.

d. Only when reactor pressure is greater than 100 psig.

QUESTION: 034 (1.00)

Unit 2 has just experienced a closure of all MSIVs due to high MSL radiation with a failure of approximately half of the control rods to fully insert. All actions necessary to reduce reactor power were immediately taken. Emergency depressurization was performed and control rods were manually inserted. Reactor power is zero and RPV level is ing controlled at +30 inches. RHR Loop 1 was placed in Shutdown ling ten minutes ago. WHICH ONE (1) of the following can be used to tain a valid, representative sample to detect possible fuel cladding failure?

a. RHR (Loop 1) Heat Exchanger "C" sample point
b. Jet pump $1 instrument line
c. Suppression Pool atmosphere sample line
d. Drywell atmosphere sample line

d.)

SENIOR REACTOR OPERATOR Page 24 STION: 035 (1.00)

WHICH ONE (1) of the following describes the expected DIRECT response to one Main Steam Line radiation monitor reaching it's high trip setpoint'?

a. Full scram and full Group 1 Isolation
b. Full scram and half Group 1 Isolation
c. Half scram and full Group 1 Isolation
d. Half scram and half Group 1 Isolation QUESTION: 036 (1.00)

The plant is heating up. Condenser vacuum is 10 inches Hg. RPV water level is being maintained by the Reactor Water Cleanup (RWCU) system.

Reject is being directed to the condenser through the Reject to Condenser Valve. RPV level is rising due to the high heatup rate and low reject rate. WHICH ONE (1) of the following is the reason that the ject to Radwaste Valve must not be open at this time'?

a. Radwaste system piping would overpressurize.
b. Excess flow would damage the RWCU filter demineralizers.

\

c. RWCU system would isolate on high flow.
d. A loss of main condenser vacuum would occur.

d%.

SENIOR REACTOR OPERATOR Page 25 STION: 037 (1 00)

Unit 2 is operating at 1004 power with FWLC in automatic three element control when the <<A<< steam flow transmitter fails downscale. WHICH ONE (1) of the following describes the expected control room INDICATIONS after conditions stabilize? (Assume no operator action is taken)

a. Feed Flow 1004, Steam Flow 754, Reactor Level 18 inches
b. Feed Flow 75%, Steam Flow 75%, Reactor level 18 inches
c. Feed Flow 1004, Steam Flow 754, Reactor Level 33 inches
d. Feed Flow 754, Steam Flow 75%, Reactor Level 33 inches QUESTION: 038 (1.00)

Unit 2 is operating at 1004 power with the master feedwater level controller is in 3 element when the FWLC system experiences a loss of one of the two feedwater flow inputs. WHICH ONE (1) of the following describes the expected plant response? (Assume no operator action is en)

a. Reactor level will stabilize at normal with FWLC remaining in 3 element control.
b. Reactor level will stabilize at normal with FWLC in single element.
c. Reactor level will stabilize about 15 inches below normal with FWLC remaining in 3 element control.
d. Reactor level will stabilize about 15 inches below normal with FWLC in single element.

SENIOR REACTOR OPERATOR Page 26 STION: 039 (1 00)

WHICH ONE (1) of the following conditions will result in a RFPT trip?

a. RFPT "B" suction pressure 95 psig for 25 seconds.
b. Condenser low vacuum 10" Hg.
c. RFP (pump) low oil pressure 6 psig.
d. RPV level 52" for 10 seconds.

QUESTION: 040 (1 00)

Unit 2 has gust experienced a small LOCA and Drywell increased to 3 psig. Reactor pressure is 800 psig andpressure steady.

has The increase in Drywell temperature causes reliability concerns for WHICH ONE (1) of the following level instruments?

a. Emergency Range indicators
b. Normal Range indicators
c. Post Accident indicators
d. Shutdown Floodup indicators QUESTION: 04 1 (1. 00)

WHICH ONE (1) of the following describes how an electrical drawing is verified as being the current revised copy?

a. Refer to the Controlled Drawing Holders list of drawings that contains only the latest revised drawings.
b. Refer to the Shift Operations Supervisor/Assistant Shift Operations Shift log book.
c. Refer to the Lead Unit Operators log book.
d. Refer to Document Control for assistance.

SENIOR REACTOR OPERATOR Page 27 STION 042 (1. 00}

Given an

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individual with the following exposure history: (NRC Form 4 is on file)

~

Sex: Male Age: 23 Lifetime exposure: 24.80 Rem (Does not include current quarter)

Current qtr. exp. 250 Mrem WHICH ONE (1) of the following states the individual's current remaining FEDERAL whole body exposure?

a. 0 Mrem
b. 750 Mrem
c. 1000 Mrem QUESTION: 043 (1.00)

WHICH ONE (1} of the following situations meets the requirements for operations outside Browns Ferry Technical Specifications?

a. The action is necessary to prevent injury to a BROWNS FERRY employee, permission has been obtained from the Plant Manager.
b. The action is necessary to prevent injury to a BROWNS FERRY employee, permission has been obtained from the ASOS.

, c. The action is necessary to prevent damage to the Main Turbine, permission has been obtained from the Shift, SOS.

d. The action is necessary to prevent damage to the Main Turbine, permission has been obtained from the Plant Manager.

SENIOR REACTOR OPERATOR Page 28 STION: 044 (1.00)

An operator returns from two (2) days off, and works the following shift hours as a control room operator during an outage.

Saturday - 6 am to 2 pm Sunday 6 am to 2 pm Monday 6 am to 6 pm Tuesday - 6 am to 6 pm ONE (1) of the following states the maximum number of additional I'HICH hours the operator can work before 6 pm on Wednesday?

a. 4 hours
b. 8 hours
c. 12 hours
d. 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> TION: 045 (1. 00)

During a Site Area Emergency, the Site Emergency Director is informed that the UO on building rounds did not report to the Control Room and does not respond to the plant paging system. WHICH ONE (1) of the following is the maximum exposure allowed to an individual in order to search for the unaccounted for operator?

a. BFNP administrative limits
b. 10CFR20 non-emergency limits
c. 25 REM
d. 75 REM

SENIOR REACTOR OPERATOR Page 29 STION: 046 (1. 00)

WHICH ONE (1) of the following is the maximum length of time a confined space entry permit is valid without an extension?

a. 4 hours
b. 12 hours
c. 24 hours
d. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> QUESTION: 047 ( 1. 00)

WHICH ONE (1) of the following is an acceptable way to perform position verification on a throttled valve? (assume that the valve is installed in a system with a local flow indication controlled by the valve, and the valve has a rising stem)

a. observe the initial valve operator's action in positioning the throttled valve
b. perform an independent visual check of the valve position by observing the valve stem
c. independently verify the valve position by a second valve operation
d. by observing flow indication through the throttled valve's system

SENIOR REACTOR OPERATOR Page 30 STION: 048 (1.00)

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A valve will be manipulated at rated power that may influence RPV level.

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WHICH ONE (1) of the following forms of verification would ensure the correct valve is manipulated?

a. Supervisor Verification
b. Second Party Verification
c. Independent Verification
d. Responsible Manager Verification QUESTION: 049 (1. 00)

The UO is required to enter a closed cooling water valve pit (Category confined space) to perform a valve lineup. WHICH ONE (1) of the I

following states the requirements for atmospheric monitoring in the area?

a. Required at all times.
b. Required only if the plant is operating.
c. Required only if this is the initial entry after shutdown.
d. Required only if welding, burning or painting is in progress.

8 SENIOR REACTOR OPERATOR Page 31 TION: 050 (1.00)

An above ground oil storage tank has been discovered leaking.

Approximately 25 gallons have been leaked onto the ground surrounding the tank. WHICH set of actions listed below are in the correct order of response?

a. Isolate the source of the leak, determine nature and source of spill, coordinate cleanup.
b. Make the necessary notifications, Isolate the source of the leak, coordinate cleanup.

ce Find the source of the leakage, determine its flowpath, confine the spillage.

d. Evacuate the vicinity, determine the nature and source, confine the material.

QUESTION: 051 (1 00) plant is operating at 804 power with three (3) hours remaining on a hour LCO. The Wilson Load Dispatcher requests the base load to be increased 25 MWE for the remainder of the operating run. WHICH ONE (1) of the following actions should be taken?

a. Before increasing the electrical load, the request must be approved by EITHER the SOS or the ASOS.
b. Before increasing the electrical load, the request must be approved by BOTH the SOS and the ASOS.
c. Before increasing the electrical load, the request must be approved by any licensed individual.
d. The request for a load increase cannot be approved at this time.

d.i SENIOR REACTOR OPERATOR Page 32 STION: 052 (1.00)

An Alert is declared at the plant. All of the emergency support facilities have been activated and all notifications have been made.

The Alert condition no longer exists and you wish to announce that the event is terminated. WHICH ONE (1) of the following individuals must approve this?

a. Site Emergency Director
b. TSC Superintendent
c. Site Emergency Preparedness Manager
d. NRC Senior Resident, Inspector QUESTION: 053 (1 00)

Four licensed UOs attended a fellow employee's birthday party the last night of their vacation and alcohol was served to all. Below shows when h UO stopped drinking alcoholic beverages.

UO 'A':05 am UO 'B':05 am UO 'C':05 am UO 'D':05 am From the four, UOs listed above, WHICH ONE (1) of the following states the'number available for NRC licensed work the same morning at 7:00 am?

(Assume that all the UOs have blood alcohol levels within SSP 1.6 guidelines) .

a. ONE
b. TWO
c. THREE
d. FOUR

SENIOR REACTOR OPERATOR Page 33 STION: 054 (1.00)

WHICH ONE (1) of the following makes this next sentence correct? Fluid or gas systems that operate with temperatures greater than degrees F or pressure greater than psig should be isolated from the work areas by two closed valves in series.

a 50/200 100/300

c. 150/400 d 200/500 l

QUESTION: 055 (1.00)

WHICH ONE (1) of the following is the Technical Specification Basis for the equilibrium coolant iodine activity limit?

a. To protect plant personnel from increased exposure in the plant during high power operation.
b. To reduce exposure to plant personnel during refueling operations.
c. To limit thyroid dose at the exclusion distance following a steam line break.
d. To assure the stack gas emissions remain within the Technical Specification limit as calculated on an annual basis.

0 4

d.)

SENIOR REACTOR OPERATOR Page 34 TION: 056 (1 00)

As SOS, you have just declared an ALERT due to weather conditions. The Emergency Centers are NOT staffed. WHICH ONE of the following should be notified within 5 minutes after the ALERT has been declared?

a. Shift Fire Captain
b. Operations Duty Specialist
c. NRC via Emergency Notification System
d. Site Emergency Director

{}UESTION: 057 (1.00)

Given the following plant conditions:

A failure to scram has occurred.

Reactor power is 24.

A high temperature exists in Secondary Containment

~

due to fire.

MSIVs are closed.

RCIC is maintaining RPV

~ ~

level.

HPCI is inoperable.

~

Control rods are being inserted using CRD.

~

WHICH ONE (1) of the following systems should be isolated into the Secondary?

if discharging

a. Control Rod Drive
b. Reactor Water Cleanup
c. Reactor Core Isolation Cooling
d. Fire Suppression

0 d.>

SENIOR REACTOR OPERATOR Page 35 I

TION: 058 (1. 00)

During an ATWS with the reactor at high power, EOI-1, step RC/Q-l directs that recirculation be run back to minimum prior to tripping the Reactor recirculation pumps. WHICH ONE (1) of the following is the basis for this action?

a. Prevent MSIV closure on high flow.
b. Promote boron mixing.
c. Prevent Main Generator reverse power trip.
d. Prevent Main Turbine high RPV water level trip.

QUESTION: 059 (1.00)

Given the following plant conditions:

Reactor pressure is 930 psig RPU level is +28 inches RCIC is injecting Twenty control rods are at position 48 Reactor power is 9000 cps on the SRMs and decreasing A 90 degree F/hr cooldown is in progress

\

WHICH ONE (1) of the following would require termination of cooldown?

a. RPV level lowers to +15 inches.
b. SRM count rate increases to 10000 cps.
c. Main turbine bypass valves fail closed.

II

d. Drywell pressure begins to increase.

SENIOR REACTOR OPERATOR Page 36 STION: 060 (1.00)

WHICH ONE (1) of the following responses. will be noted on Unit 2 during a complete loss of Unit 2 ISC Bus during reactor operation?

a. Unit 2 reactor water level increase
b. Unit 1 Loop A recirculation pump speed increase
c. Unit 3 SJAE flow to offgas system increase
d. Unit 2 main steam tunnel temperature increase QUESTION: 061 (1.00)

During a plant transient on Unit 2, a Group I isolation is caused by high radiation. Five control rods fail to insert. Suppression pool level is 12 feet and pool temperature is 94 degrees F.

WHICH ONE (1) of the following identifies the systems available to help

'ntain pressure below 1040 psig?

~

a. HPCI, RCIC
b. RCIC, RWCU
c. RWCU, MSL drains
d. MSL drains, HPCI

d.,i SENIOR REACTOR OPERATOR Page 37 STION- 062 (1.00)

The Control Room was evacuated due to a fire 5 minutes ago. All the immediate actions for '~Control Room Abandonment" were performed.

Current plant conditions are:

The reactor has been verified to be shutdown.

RPV level is > +60 inches.

RPV pressure is 700 psig and decreasing slowly.

The MSIVs are open and cannot be closed.

The turbine bypass valves appear to be functioning normally.

An operator is stationed to control RPV level and pressure with HPCI as necessary.

WHICH ONE (1) of the following is the appropriate emergency action level for this situation'?

a. Unusual Event
b. Alert
c. Site Area Emergency QUESTION: 063 (1.00)

During an ATWS, EOIs direct the operator to inhibit ADS automatic blowdown when Standby Liquid Control is injected. WHICH ONE (1) of the following states the basis for this requirement?

a. ADS actuation would impose a severe pressure and temperature transient on the vessel.
b. ADS would result in the removal of boron after injected.

it has been

c. Core damage could result from a large power. excursion pressure ECCS systems were to inject.

if low e

d. ADS/MSRV system flow rate is incapable of assuring fuel cooling through steaming above 5% reactor power.

8.)

SENIOR REACTOR OPERATOR Page 38 STION: 064 (1.00)

While the reactor is operating at 904 power, reactor pressure is observed decreasing at an approximate rate of 200 psig per minute.

WHICH ONE (1) of the following is the expected immediate operator action?

a. Scram the reactor and place the pressure control unit in manual.
b. Scram the reactor and close the MSIVs.
c. Take manual control of the reactor pressure control unit.
d. Manually transfer to the backup pressure control unit.

QUESTION: 065 (1.00)

A failure of Drywell Control Air has resulted in Drywell control air being supplied by the Plant Control Air header. WHICH ONE (1) of the following is a concern during the malfunction?

a. Moisture in the air may cause critical valves to fail.
b. Torus temperature may increase.
c. Drywell oxygen level may increase.
d. Breathing air is unavailable.

0 d.i SENIOR REACTOR OPERATOR Page 39 STION: 066 (1.00)

WHICH ONE (1) of the following systems is used to inject Alternate Standby Liquid Control (SLC) boron into the reactor?

a. Suppression Chamber Head Tank system
b. Control Rod Drive system
c. RHR Standby Coolant system
d. Condensate 'and Feedwater system QUESTION: 067 (1.00)

The reactor has experienced an incomplete scram. WHICH ONE (1) of the following methods of rod insertion requires first resetting the SCRAM?

a. De-energization of scram solenoids
b. Venting of the scram air header
c. Scraming individual control rods using test switches
d. Venting the Control Rod Drive over piston volume QUESTION: 068 (1.00)

WHICH ONE (1) of the following constitutes a loss of Secondary Containment?

a. The Reactor Building normal HVAC is inoperable and isolated.
b. Both Reactor Building ventilation radiation. monitors are INOP.
c. The Reactor Building/Suppression Chamber vacuum breaker is open.
d. The Standby Gas Treatment system is inoperable.

0 a

SENIOR REACTOR OPERATOR Page 40 STION: 069 (1 ~ 00)

WHICH ONE (1) of the following describes the basis Xor the Drywell Spray Initiation Limit Curve'

~ ~

I

a. To prevent unstable steam condensation in the NSRV tailpipes from exerting excessive cyclic hydraulic loads on the suppression pool structure,
b. To ensure that the rate at which the primary containment is depressurized is within the capacity of the reactor building to suppression pool vacuum breakers.
c. To prevent chugging in the drywell to suppression pool from exerting excessive cyclic hydraulic loads on the

'owncomers suppression pool structure.

d. To ensure adequate noncondensibles remain in the drywell to the suppression pool to drywell vacuum breakers from 'revent opening during drywell steam condensation.

TION: 070 (1 00)

Drywell pressure has exceeded 30 psig and the Suppression Chamber vent path is unavailable. The EOIs direct termination of CAD system use and initiation of venting from the Drywell. WHICH ONE (1) of the following states the basis for'hifting vent paths under these conditions'

a. Use of the Containment Air Dilution system at this pressure could cause loss of Containment.
b. The Drywell vent path is designed to withstand greater temperatures and pressures.
c. The Drywell vent path is sized to limit effluent flow rate to ensure releases are within the design basis.
d. The Drywell vent path contains supplementary sample lines routed to the Post Accident Sampling system (PASS).

d.i SENIOR REACTOR OPERATOR Page 41 STION: 071 (1.00)

~

Within two minutes after a loss of Reactor Building Closed Cooling

~

Water, AOI 70-1~ "Loss of RBCCW", directs that, the reactor be scrammed and both recirculation pumps be tripped. WHICH ONE (1) of the following is the basis for this action'?

a. Loss of cooling will lead to filter demin inlet temperature increase and auto isolation of RWCU.
b. Loss of flow to RHR pump coolers will prevent the RHR system from meeting design criteria.
c. Loss of cooling to the Recirculation pump seals will lead to a primary coolant leak.
d. Loss of Drywell cooling will lead to an increase in Drywell pressure, actuating safety related equipment.

{}UESTION: 072 (1 00) reactor has scrammed from 1004 power due to closure of the MSIVs.

ening of MSRVs has increased torus temperature to 125 degrees F.

Current plant conditions are as follows:

All rods in Mode switch in Shutdown Reactor level is +45 inches Reactor pressure is 950 psig Drywell pressure is 1.2 psig WHICH ONE (1) of the following is the required operator action?

a. Power operation shall not be resumed until the pool temperature is reduced below 90 degrees F.
b. Reactor vessel shall be depressurized to less than 200 psig at normal cooldown rates.
c. The reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d. Maintain Primary Containment integrity until pool temperature is reduced below 100 degrees F.

d%.

SENIOR REACTOR OPERATOR Page 42 STION: 073 (1.00)

~

EOI-2, "Primary Containment Control," step PC/H-8 requires that

~

Suppression Pool level be verified below 26 feet prior to initiating Suppression Chamber sprays for hydrogen control. WHICH ONE (1) of the following is the basis for this limitV'.

Ensure the torus to drywell vacuum breakers are not submerged.

b. Ensure the torus vent header is not submerged.
c. Ensure the torus spray nozzles are not submerged.
d. Ensure the torus downcomer header is not submerged.

QUESTION: 074 (1.00) t While the plant is operating at full power, a complete loss of Control Air is experienced. WHICH ONE (1) of the following containment isolation valves is designed to fail open under these circumstances?

a. Suppression Chamber vacuum relief valves
b. Main Steam Isolation Valve
c. Refuel zone ventilation dampers
d. RHR process water sampling valve

d,i SENIOR REACTOR OPERATOR Page 43 STION: 075 (1. 00)

A pipe shear has resulted in Control Air pressure immediately decreasing to 0 psig. WHICH ONE (1) of the following will remain available'

a. Off Gas b'. Stator Cooling Water
c. Reactor Water Cleanup
d. Raw Service Water supply to fire systems QUESTION: 076 (1.00)

The main turbine control valves have failed closed and reactor pressure has increased to the scram setpoint. Approximately one third of the control rods have failed to fully insert, MSIVs remain open and several SRVs are cycling. EOI-1, RPV Control Procedure, step RC/P-6, directs the crew to manually open any cycling SRV until RPV pressure drops to 0 psig. WHICH ONE (1) of the following is the basis for this lower it'?

a. Maintain reactor pressure high enough to scram control rods should CRD pumps become unavailable.
b. Prevent initiation of a low reactor pressure scram signal while attempting to drive rods.
c. Limit the amount of energy sent to the suppression pool through the MSRVs.
d. Preclude the possibility of a Group 1 isolation on low Main Steam Line pressure.

8.}

SENIOR REACTOR OPERATOR Page 44 r

k STION: 077 (1.00)

WHICH ONE (1) of the following plant changes vill result in the indication from LI 3-52, Post Accident Range Level instrumentation,

~ ~

becoming more accurate?

a. Reactor pressure increases from 900 to 1125 psig.
b. Dryvell temperature increases from 100 to 212 degrees.
c. Reactor building temperature increases from 10Q to 13Q degrees.
d. Reactor recirculation pumps are manually tripped.

QUESTION: 078 (1.00)

The reactor is shutdown with Recirculation pumps off. WHICH ONE (1) of the following indicates reactor coolant stratification?

a. Shutdown Cooling is out of service, RPV pressure is 5 psig, RX

, VESSEL FLANGE DR LINE temperature is 170 degrees F, and RX VESSEL FW NOZZLE N4B END temperature is 205 degrees F.

b. Shutdown Cooling is in service, RPV pressure is 5 psig, RX VESSEL BOTTOM HEAD temperature is 215 degrees F, and RX VESSEL FW NOZZLE N4B END temperature is 260 degrees F.
c. Shutdovn Cooling is out of service, RPV pressure is 0 psig, RX VESSEL FLANGE DR LINE temperature is 130, and feedwater sparger temperature is 170.
d. Shutdown Cooling is in service, RPV pressure is 0 psig, RX VESSEL BOTTOM HEAD temperature is 140, and feedwater sparger temperature is 195.

SENIOR REACTOR OPERATOR Page 45 STION: 079 (1 00)

A Reactor startup is in progress on Unit 2 when the following annunciators actuate. Current readings are also given.

CRD ACCUM CHG WTR HDR 1480 psig CRD DRIVE WTR FILTER DIFF PRESS HIGH 50 psid Given the following plant conditions:

Rx Power is 5%

Reactor Pressure is 550 psig Charging Water Pressure is 1480 psig (decreasing slowly) 1 Accumulator is INOP due to water level 1 CRD High Temperature alarm WHICH ONE (1) of the following would be the correct IMMEDIATE action to take in accordance with 2-AOI-85-3, "CRD System Failure"'?

a. A Manual Scram is required under current conditions.
b. A Manual Scram is required if another Control Rod High Temperature alarm is received in congunction with the LOW CRD SUCTION PRESSURE alarm.
c. A Manual Scram received.

is required if a second Accumulator alarm is

d. A Manual Scram to 1400 psig.

is required if Charging Water Pressure decreases

d.~

SENIOR REACTOR OPERATOR Page 46 STION: 080 (F 00)

Unit 2 control room has been abandoned and reactor pressure is decreasing due to a controlled cooldown. Water level is being controlled with the RCIC system at remote shutdown panel 25-32, in accordance with 2-AOI-100-2, "Control Room Abandonment". When reactor pressure decreases to 50 psi, WHICH ONE of the following describes the status of the RCIC system under these circumstances?

a. tripped and isolated.
b. tripped but not isolated; can be restarted from Control Room
c. tripped but not isolated; can NOT be restarted from Control Room
d. RCIC is running QUESTION: 081 (1 ~ 00)

Suppression pool temperature is 145 degrees F, Conditions have NOT been met for automatic transfer of HPCI suction. WHICH ONE (1) of the lowing describes the reason that the HPCI suppression pool water el suction transfer logic interlock is defeated and HPCI is operated th a suction from the CST?

a. The suppression pool provides insufficient NPSH to the HPCI pump and cavitation may occur at rated flow.
b. The HPCI shaft pump seals are not designed to operate at temperatures in excess of 140 degrees F and may fail.
c. The HPCI lube oil will exceed allowable temperatures and the HPCI function could be lost due to damaged bearings.
d. The HPCI turbine exhaust pressure is likely to exceed the trip setpoint at elevated suppression pool temperatures.

d.i SENIOR REACTOR OPERATOR Page 47

~O STION: 082 (1.00)

Unit 2 is operating at 100% rated power when the following indications are received:

OG POST TREATMENT RADIATION HI-HI ALARM OG POST TREATMENT RADIATION HI-HI-HI/INOP ALARM OG PRETREATMENT RADIATION HI ALARM OG AVERAGE ANNUAL RELEASE LIMIT EXCEEDED ALARM WHICH ONE (1) of the following is the appropriate immediate operator action'?

a. Reduce reactor power to 604 using recirc flow; manually scram the reactor.
b. Reduce reactor power to 60% using recirc flow; insert control rods in reverse order to shutdown the reactor.
c. Reduce core flow to 604; manually scram the reactor.
d. Reduce core flow to 604; insert control rods in reverse order to shutdown the reactor.

SENIOR REACTOR OPERATOR Page 48

~ I STION: 083 (1.00)

During operation at 1004 power, a turbine trip occurs, and subsequently a reactor scram signal is generated. Water level reaches -15 inches but is recovered by the operator using the feedwater system. Reactor pressure initially reaches 1105 psig, but is controlled normally thereafter by the turbine bypass valves. During response to the transient, the operator notes that neither recirculation pump is running. WHICH ONE (1) of the following is the basis for the recirculation pump trip7 \

a. To prevent damage to the recirculation pump seals when reactor pressure exceeds 1100 psig.
b. To add negative reactivity, counteracting the positive reactivity added due to the pressure increase'hich resulted from the turbine trip.
c. To promote level swell in the vessel, counteracting the shrink effects caused by the turbine trip.
d. To protect the recirculation pumps from loss of adequate NPSH caused by the vessel level shrink resulting from the turbine trip.

0

d.i SENIOR REACTOR OPERATOR Page 49 STION: 084 (1 00}

A loss of all off-site power has occurred at, Unit 2. You are directed to backfeed the Unit boards from the Diesel generators in order to start a CCW pump and establish the Main Condenser as a heat sink for cooldown.

WHICH ONE (1) of the following describes the effect of taking the 2 BACKFEED switches on the Unit Boards (Panels 9-23-7 and 9-23-8) to the BACKFEED position'?

a. Automatically trip and lockout the normal and alternate supply breaker, automatically trip the 43 switch to MANUAL, and allow the Unit Board to Shutdown Bus supply breaker to be manually closed.
b. Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to MANUAL, and allow the alternate supply to Unit Board breaker to be manually closed.
c. Automatically trip and lockout the normal supply breaker, automatically trip the 43 switch to AUTO and allow the alternate supply to Unit Board breaker to be manually closed.
d. Automatically trip and lockout the alternate supply breaker, automatically trip the 43 switch to AUTO and allow the normal supply to Unit Board breaker to be auto closed.

QUESTION: 085 (1.00)

Control Room instrumentation and annunciation indicates that three turbine stop valves have drifted to 804 open. No rod movement has occurred. You observe that the individual blue lights for each control rod on the full-core display are illuminated. Also, the eight scram solenoid group indicating lights are extinguished. WHICH ONE (1} of the following is a possible cause for the failure to SCRAM?

a. Failure of scram pilot valves to open.
b. Only one RPS bus is de-energized.
c. Failure of scram inlet and outlet valves to open.
d. Hydraulic lock on the scram discharge volume.

dS.i SENIOR REACTOR OPERATOR Page 50 STION'86 (1. 00)

Unit 2 is operating at 254 power when a loss of I&C bus "A" occurs. RPV level control is selected to Level "A". Recirc pumps are in individual manual control. WHICH ONE (1) of the following describes the expected plant response and operator actions for this event?

a. Feed flow will increase until the turbine trips on high level.

A manual SCRAM should be inserted.

b. Recirc pump B will run back to minimum speed, Recirc pump A will experience a scoop tube lockup. Recirc pump A should be manually run back to minimum speed.
c. Recirc flow will increase until the Reactor scrams on high flux.

Both recirc pumps should be manually run back to minimum.

d. Recirc pump A will run back to minimum speed, Recirc pump B will experience a scoop tube lockup. Recirc pump B should be manually run back to minimum speed.

STION: 087 (1.00) ven the following plant conditions:

RPV level +56 inches RPV pressure 1040 psig Drywell press. 2.40 psig Torus level +1 inch Rx zone vent rad 75 mr/hr Refuel zone vent rad 62 mr/hr WHICH ONE (1) of the following EOI groups should be entered'?

a. EOI-1, "RPV Control" and EOI-2, and EOI-4, Radiation Release Control.

~ b. EOI-1, "RPV Control" and EOI-2, "Primary Containment Control".

c. EOI-2, "Primary Containment Control" and EOI-3, "Secondary Containment Control"..
d. EOI-3, "Secondary Containment Control" and EOI-4, Radiation Release Control.

B.i SENIOR REACTOR OPERATOR Page 51 STION: 088 (1.00)

~

While operating at 754 power, a plant transient causes a trip of one

~

Reactor Recirculation pump. Given the following plant conditions:

Reactor power is 484 Core flow is 334 APRM A reading increases 44 and stabilizes Using the attached POWER/FLOW map, WHICH ONE (1) of the following states the appropriate operator action?

a. Restart the idle recirculation pump to restore core flow to greater than 45% of rated.
b. Increase recirculation flow on the operating pump to restore core flow to greater than 45% of rated.
c. Insert control rods to reduce reactor power to less than 454.
d. Scram the reactor.

TION: 089 (1.00)

Unit 2 is operating at rated power when all RBCCW pumps trip and none can be restarted. WHICH ONE (1) of the following describes the IMMEDIATE operator actions appropriate for this situation'?

a. Reduce recirculation flow to minimum, if recirc pump seal cavity temperature exceeds 200 degrees F on BOTH pumps, TRIP both recirc pumps and SCRAM the reactor.
b. If drywell temperature exceeds 145 degrees F, or drywell pressure exceeds 1.66 psig, insert a manual SCRAM, and trip both recirculation pumps.
c. Run recirculation pumps to 45% speed, insert a manual SCRAM, Trip both recirculation pumps, and initiate a cooldown of 90 degrees F/hour.
d. IMMEDIATELY TRIP both recirc pumps and SCRAM the reactor.

SENIOR REACTOR OPERATOR Page 52 STION: 090 (1.00)

While offloading fuel bundles from the reactor, fuel pool level begins to decrease uncontrollably. WHICH ONE (1) of the following describes a method available from the control room to add water to the fuel pool?

a. Al'ign fuel pool cooling and cleanup heat exchanger RBCCW supply to the fuel pool to maintain level.
b. Start an RHR pump and inject to the reactor vessel to maintain fuel pool level.
c. Open emergency makeup supply valve from EECW to the fuel pool to maintain level.
d. Open the CST to Fuel Pool Gravity drain valves.

QUESTION: 091 (1.00)

WHICH ONE (1) of the following scram signals is effective ONLY when the mode switch is in RUN?

b. Turbine stop valve closure
c. MSIU closure
d. EHC low oil pressure QUESTION: 092 (1.00)

Unit 2 is operating at 25% power. WHICH ONE (1) of the following combinations of events will NOT result in a half reactor scram?

a. Both MSIU's in steam lines "A" and "B" isolate
b. Both MSIU's in steam lines "A" and "D" isolate
c. APRM "E" and "C" trip on hi-hi flux
d. APRM "E" and "A" trip on hi-hi flux

d%.,

SENIOR REACTOR OPERATOR Page 53 STION: 093 (1 ~ 00)

WHICH ONE (1) of the following conditions requires a manual reactor SCRAM?

a. RBCCW pump suction header temperature of 102 degrees F
b. Pre-treatment radiation HI-HI-Hi
c. Both recirculation pumps trip with the mode switch in Startup
d. Off-gas system Hydrogen concentration of 5%

QUESTION: 094 (1.00)

WHICH ONE (1) of the following conditions assures ADEQUATE CORE COOLING?

a. All rods inserted, RPV level -200, MSRV's cycling on pressure, no injection flow.
b. RPV level unknown, 6 MSRV's open, reactor pressure is 10 psig.
c. Reactor power 34, RPV level -210, one MSRV open, HPCI injecting at maximum flow.
d. RPV level -230, RHR "B" and "D" injecting at maximum flow, suppression pool level at 15 feet.

SENIOR REACTOR OPERATOR Page 54 STION: 095 (1. 00)

The Control Room has been abandoned. All MSRV transfer switches at panel 25-32 have been placed in EMERGENCY. All MSRV control switches at panel 25-32 are in CLOSE. WHICH ONE (1) of the following states the opening capability of the MSRVs'?

a; ONLY manually by placing the panel 25-32 control switches in.

OPEN

b. ONLY manually OR upon receipt of an ADS initiation signal
c. ONLY manually OR when their respective pressure relief setpoint is reached
d. EITHER manually OR on an ADS initiation signal OR when their respective pressure relief setpoint is reached QUESTION: 096 (1-00) loop I is in shutdown cooling taking suction through Shutdown ling suction valves 74-47 and 74-48. Loop II of RHR remains in the CI standby lineup. Due to misoperation of ventilation systems, Drywell pressure increases to 2.5 psig. WHICH ONE (1) of the following describes the response of the RHR system'P
a. Valves 74-47 and 74-48 close, Loop I suppression pool suction valves auto open and BOTH RHR loops inject to the vessel.
b. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop suppression pool suction valves auto open but only Loop injects.

III

c. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and only Loop injects.

II

d. Valves 74-47 and 74-48 close, Loop I RHR pumps trip, Loop I suppression pool suction valves remain closed and NEITHER Loop injects.

0 SENIOR REACTOR OPERATOR Page 55 TION: 097 (1 00)

An emergency exists which requires addition of water to the suppression pool. Your supervisor directs use of Appendix 18 of the Emergency Procedures. Using Appendix 18, WHICH ONE (1) of the following describes the availability of HPCI and RCIC?

a. Neither HPCI nor RCIC are available if they have isolated.
b. Both HPCI and RCIC are available even if they have isolated.,
c. HPCI is available unless if isolated. it has isolated; RCIC is available even
d. RCIC is available if isolated. unless it has isolated; HPCI is available even QUESTION: 098 (1.00)

A severe earthquake has occurred, causing a LOCA and complete loss of

-site power. The Diesel generators are carrying plant loads as igned. Plant conditions are as follows:

RPV level +15 inches, steady RPV pressure 50 psig, decreasing Drywell press. 2.40 psig, increasing slowly Torus level -2 inches, decreasing slowly Rx zone vent rad 75 mr/hr Refuel zone vent rad 62 mr/hr Spent fuel pool level dropping rapidly, fuel uncovered Off-site release rate 100 Ci/sec gaseous at stack Radiation levels 25 mr/hr at site boundary WHICH ONE (1)'of the following is the appropriate EPIP classification?

a. Unusual Event
b. Alert
c. Site Area Emergency
d. General Emergency

d.)

SENIOR REACTOR OPERATOR Page 56 STION: 099 (1.00) n An emergency has been declared and all emergency response centers have been staffed. WHICH ONE (1) of the following duties of the Site Emergency Director can be delegated?

a. Determination of emergency event classification
b. Issuance of off-site Protective Action Recommendation
c. Approval to exceed 10 CFR 20 radiation exposure limits
d. Ordering evacuation of the plant QUESTION: 100 (1 00)

Reactor level cannot be determined. Prior to entering RPV Flooding, the t

EOIs direct that Emergency Depressurization must be performed. WHICH ONE (1) of the following is the bases for requiring RPV depressurization prior to entering RPV Flooding?

a. Reducing RPV pressure ensures a slower, more stable reflood to limit thermal shock to the reactor core.
b. Opening the ADS valves ensures the minimum number of MSRVs required to support RPV flooding will be open.
c. Reducing RPV pressure ensures dynamic loading on the MSRVs is minimized as RPV water level reaches MSRVs and is discharged.
d. Emergency procedures assume that high pressure injection sources may be unavailable due to failed high RPV level instrumentation.

(+********* END OF EXAMINATION **********)

SENIOR REACTOR OPERATOR Page. 1 ANSWER KEY MULTIPLE CHOICE 023 b 001: P hor4 024 b 002 b 025 a 003 b 026 a 004 d 027 a 005 a 028 c 006 a 029 c 007 d 030 b 008 c 031 b 009 c 032 c

~011

~

c 033 034 b

c 012 c 035 d 013 a 036 d 014 a 037 c 015 a 038 b 016 b 039 c 017 b 040 018 a 041 d 019 b 042 c 020 c 043 b 021 b 044 c c 045 d

d%.

SENXOR REACTOR OPERATOR Page 2 A N S W E R K E Y 046 b 069 b 047 " a orb 070 a 048 b 071 049 a 072 b 050 c 073 c 051 1 074 a 052 a 075 b 053 W Ch 076 c 054 077 0

078 a 079 080 6 058 6 081 c 059 b 082 a 060 6 083 b 061 b 084 a 062 c orb 085 6 063 c 086 b 064 b 087 c 065 c 088 b 066 b 089 c 067 c 090 b d 091 c

d.)

SENIOR REACTOR OPERATOR Page 3 A N S W E R K E Y 092 b 093 '

094 a 095 c 096 097 c 098 c 099 b 100 c

(**********END OF EXAMINATION ******+***)

SENIOR REACTOR OPERATOR Page 57 WER 001 (1.00) a.oc b

REFERENCE:

1. 'echnical Speci.fication 4.3.B.3..a 2~ OPL171.006, Ob) 14 3~ K/A: 201003G001 (3 6/3 7) 201003G001 .. (KA's)

ANSWER: QQ2 (1. 00) b.

REFERENCE-OPL171.006, Obj.

201001K303 (3 ~ 1/3 2) 13'/A

~

201001K303 .. (KA's)

ANSWER: 003 (1. 00) b.

d%.i SENIOR REACTOR OPERATOR Page 58

REFERENCE:

Tech Spec 3.7.A.4 and bases OPL171.016 Obj. 4, 18, page 19 K/A: 223001G006 (3 '/4 0)

'223001G006 .. (KA's)

ANSWER: 004 (1. 00) d.

REFERENCE:

1. OPL 171.029, Obj.9, pages 21, 26
2. K/A 201002A402 (3 5/3 5)

~ ~

.. (KA's)

ANSWER: 005 (1. 00) a~

REFERENCE:

1. OPL171.009, Obj. 5, page 12 2 ~ K/A: 239002K605 (3. 0/3. 2) 239002K605 .. (KA's)

ANSWER: 006 (1.00)

d.

SENIOR REACTOR OPERATOR Page 59

REFERENCE:

OI-71, Precaution 3.23 ~

OPL171.037, Obj. 11

'/3 ')

~

~

3 ~ K/A: 263000G005 (3 ~ ~

263000G005 .. (KA's)

ANSWER 007 ( 1. 0,0)

REFERENCE:

1. OPL171.044, Obj. 11, page 27 2 K/A: 226001A403 (3. 5/3. 4) 226001A403 .. (KA's)

ANSWER: 008 (1. 00) co

REFERENCE:

1. OPL171. 044, Ob j . 14, page 29 2 ~ K/A: 203000K601 (3.6/3.7) 203000K601 .. (KA's)

ANSWER: 009 (1.00)

SENZOR REACTOR OPERATOR Page 60

REFERENCE:

OPL171.043, Obj.~ 4, pages 9, 10

~

~ K/A: 218000K501 (3. 8/3.~ 8) 218000K501 ..(KA's)

ANSWER 010 (1.00) ci

REFERENCE:

1. Technical Specification 4.6.E.1 2.

3 ~ K/A: 2020016005 (3 '/4 ')

OPL171.007, Obj. 32, page 54 202001G005 ..(KA's)

ANSWER: 011 (1 00) ci

REFERENCE:

1. OPL171.007, Obj. 31, pages 54, 34
2. OZ-68, page 6 3 ~ K/A: 202002G010 (3.3/3.3) 2020026010 .. (KA's)

ANSWER: 012 (1. 00)

SENIOR REACTOR OPERATOR Page 61

REFERENCE:

~

OPL171.007,

~

K/A 202002K305 (3 '/3 ')

Obj.~ 8, page 21

~

202002K305 ~ .(KA s)

ANSWER: 013 (1.00) a~

REFERENCE:

1. OPL171.042, Obj 6, page 33
2. K/A: 206000K204 (2.5/2.7)

.. (KA's)

ANSWER: 014 (1.00) a~

REFERENCE:

1. OPL171.042, Obj. 4, page 8 2 ~ K/A: 206000K419 (3. 7/3 ~ 8) 206000K419 .. (KA s)

ANSWER: 015 (1. 00) a~

0 SENIOR REACTOR OPERATOR Page 62

REFERENCE:

Tech Spec 3.3.A.2.f OPL171.024, Obj.7 4 ~

AOI 85-4 K/A: 214000G011 (3.1/4 ')

214000G011 .. (KA's)

ANSWER: 016 (1.00) b.

REFERENCE:

1.

2 ')

OPL171.045, Obj. 8, page 14 K/A: 209001K404 (3 0/3 209001K404 .. (KA's)

ANSWER: 017 (1. 00) b.

REFERENCE:

1. OPL171.045, Obj. 2a, page 20 2- K/A: 209001K408 (3. 8/4 0)

~

209001K408 ..(KA's)

ANSWER: 018 (1.00)

d.)

SENIOR REACTOR OPERATOR Page 63 OPL171.017, Obj. 7, page 14 OPL171.045, Obj. 2b, page 12 K/A: 223002A102 (3 ~ 7/3 ~ 7)

223 002A102 .. (KA's)

ANSWER: 019 (1. 00) b.

REFERENCE

1. OPL171.Q17, Obj. 7, page 13 2 K/A: 223002K101 (3.8/3 9)

.. (KA's)

ANSWER: 020 (1. QQ)

Co

REFERENCE:

1 OPL171 ~ 009s Ob3 ~ 14

2. OPL171.017, Obj. 6, page 19 3 ~ K/A: 239001A212 (4.2/4.3) 239001A212 .. (KA's)

ANSWER: 021 (1. 00)

d.)

SENIOR REACTOR OPERATOR Page 64

REFERENCE:

Tech Spec 4.4.A.2.b OPL171.039, Obg. 10 K/A: 211000G005 (3.6/4 ')

'211000G005 .. (KA's)

ANSWER: 022 ( 1. 00) co REFERENCE

1. OPL171.039, Obg. 6, page 21 2 K/A: 211000A308 (4 2/4.2)

.. (KA's)

ANSWER: 023 (1. 00) b.

REFERENCE:

1. OPL 171.053, Rev 3, p. 13 of 46, Obj. 6 2 ~ K/A: 234000K502 (F 1/3.7) 234000K502 .. (KA's)

ANSWER: 024 (1.00) b.

d.)

SENIOR REACTOR OPERATOR Page 65

REFERENCE:

T.S. 1.0, item S, p. 1.0-7

~ ~

K/A: 234000G011 (2.8/3 9*)

~

234000G011 .. (KA's)

ANSWER: 025 (1 00) a~

REFERENCE:

1.

2 ~

OPL171.033, Rev 4, p. 21 K/A: 288000K105 (3 3/3 ') of 62

..(KA's)

ANSWER: 026 (1 00) a~

REFERENCE:

1. OPL171.038, Obj. 5, page 17 OF 75
2. K/A 262001K401 (3.0/3.4) 262001K401 ..(KA's)

ANSWER: 027 (1. 00) a~

d.

SENXOR REACTOR OPERATOR Page 66

REFERENCE:

~

OPL171.038,

~ Obj.~ 12, page 60

~

K/A 264000K506 (3 ~ 4/3 ~ 5) 264000K506 .. (KA's)

ANSWER: 028 (1 00)

Co

REFERENCE:

1. OPL171.036, REV 2, Obj. 12, page 19 of 37 2 ~ K/A 263000K101 (3 '/3.5)

..(KA~s)

ANSWER: 029 (1.00)

Ce

REFERENCE:

1. OPL171.067, Obj. 11, 27 2 ~ K/A: 290001K107 (3 0/3 1)

~ ~

290001K107 .. (KA's)

ANSWER: 030 (1. 00) b.

SENXOR REACTOR OPERATOR Page 67

REFERENCE:

~

OPL171.049,

~ Obj.~ 2,5, Page 45 K/A: 286000A105 (3.2/3.2)

~

286000A105 ..(KA's)

ANSWER: 031 (1. 00)

REFERENCE:

1. OPL171. 011, Obj ~ 4 2 K/A: 256000K107 (2 ~ 9/2 9)

.. (KA's)

ANSWER: 032 (1. 00)

Co REFERENCE

1. OPL171.044, Obj. 9 2 ~ K/A: 203000K202 (2. 5/2. 7) 203000K202 ..(KA's)

ANSWER: 033 (1 ~ 00) b.

d%.i SENIOR REACTOR OPERATOR Page 68

REFERENCE:

Tech Spec 3.5.B.11 OPL171 044, Obj 20

'/4

~

K/A 203000G005 (3 4)

'203000G005 .. (KA's)

ANSWER: 034 (1. 00) c ~

REFERENCE:

1. OPL171.016, Obj. 13, page 47 2 ~ K/A 272000A201 (3.7/F 1)

.. (KA's)

ANSWER: 035 (F 00) 8~

REFERENCE:

1. OPL171.033, Obj. 1
2. K/A: 272000K402 (3.7/4. 1) 272000K402 ..(KA's)

ANSWER: 036 (1. 00)

d%.)

SENIOR REACTOR OPERATOR Page 69

REFERENCE:

OPL171.013, Obj.~ 11

~

~

K/A: 204000K106 (2 '/2

~ 8) 204000K106 ..(KA's)

ANSWER: 037 (1. 00)

Ce

REFERENCE:

1. OPL171.012, Rev 4, p. 30 of 55 2~ K/A: 216QOOK312 (3 7/F 8)

.. (KA's)

ANSWER: 038 (1.00) b.

REFERENCE:

OPL171.012, Rev 5, Obj. 6, page 24 of 55 2 ~ K/A: 259002K6Q4 (3 '/3 1) 259002K604 .. (KA's)

ANSWER: 039 (1. 00)

Co

SENIOR REACTOR OPERATOR Page 70 2-0I-3, Rev 23, Precaution 3.1 2-AOI-3-1, Rev 7, 3.1, 3.2 K/A: 259001A310 (3.4/3.4)

'259001A310 .. (KA's)

ANSWER: . 040 (1. 00)

REFERENCE:

1. EOIPM Section II-B, Operator Cautions, page 4 2 K/A 216000K507 (3.6/3.8) 216000K507 .. (KA's)

ANSWER: 041 (1. 00) d.

REFERENCE:

1~ SSP 2.8, REV 003s p. 9 of 37

2. K/A: 294001A101 (2. 9/3 4) ~

294001A101 ..(KA's)

ANSWER: 042 (1. 00)

SENIOR REACTOR OPERATOR Page 71

REFERENCE:

RCI-2, VOL-1, p.3 ~

K/A: 294001K103 (3 ~ 3/3.8) ~

294001K103 .. (KA's)

ANSWER: 043 (1.00) b.

REFERENCE:

1. SSP-12.1, REV. 0008, p. 77 of 2 ~ K/A 294001A109 (3 '/4 ') 95

.. (KA's)

ANSWER: 044 (1 00)

C~

REFERENCE:

1. SSP-1.7, REV 0001, p. 3 of 5 2 KA: 294001A109 (3 3/4.2) 294001A109 .. (KA s)

'NSWER: 045 (1. 00)

SENIOR REACTOR OPERATOR Page 72

REFERENCE:

RCI-2, REV 0020, p. 6 EPIP 15, section 3.1 K/A: 294001K103 (3 '/3 ')

'294001K103 .. (KA's)

ANSWER 046 (1. 00) b.

REFERENCE:

1. RCI-13, page 5 2 ~ K/A: 294001K114 (3.2/3.4)

..(KA s)

ANSWER 047 (1.00)

a. or 3

REFERENCE:

1. SSP 12.6, page 7 OI VOL-13, O-GOI-300-3, p. 7 of 2.

3 ~ K/A: 294001K101 (3 '/3 ') 10 294001K101 .. (KA's)

ANSWER 048 (1. 00)

0 0

d5.

SENIOR REACTOR OPERATOR Page 73

REFERENCE:

SSP-12.6,

~ REV 0001, p. 4 of 20 and p.

~ 7 of 20 K/A: 294001K101 (3.7/3 7) 4 294001K101 .. (KA's)

ANSWER 049 (1 00) a~

REFERENCE

1. Safety and Health Manual, p. VII-74 and 75 2 K/A: 294001K114 (3.2/3.4) 294001K114 ..(KA's)

ANSWER: 050 (1.00)

C~

REFERENCE:

Safety and Health Manual, p. VII-135 1.

2 ~ K/A: 294001A110 (3 '/4 ')

294001A110 ..(KA's)

ANSWER: 051 (1 00) d.

d.i SENIOR REACTOR OPERATOR Page 74

REFERENCE:

SSP-12.1, REV '0008, p. 34 of 95

~ ~

K/A: 294001A111 (3.3/4 ~ 3) 294001A111 .. (KA's)

ANSWER: 052 (1. 00) ae REFERENCE 1.

2 ~

EPZP 16, page 1 K/A: 294001A116 (2 '/4 ')

.. (KA's)

ANSWER: 053 (F 00)

OL

REFERENCE:

1. SSP 1.6, REV 002, p. 5 of 53 2 ~ K/A 294001K105 (3 2/3 7)

~ ~

294001K105 ..(KA's)

ANSWER: 054 (1. 00)

8.)

SENIOR REACTOR OPERATOR Page 75

REFERENCE:

of

~

SSP<<12.3,

~ REV K/A: 294001K109 (3 '/3 ')

0008, p. 19

~

~

105 294001K109 .. (KA s)

ANSWER: 055 (1. 00)

C~

REFERENCE:

T.S.3.6.B Basis 1.

2 ~ K/A: 294001A114 (2 '/3 ')

294001A114 .. (KA's)

ANSWER: 056 (1. 00) b.

REFERENCE:

1.

2~

BNF-EPIP-3, p. 2 K/A: 294001A116 (2 '/4 ')

294001A116 ..(KA's)

ANSWER: '057 ( 1. 00) b.

d%.

l SENIOR REACTOR OPERATOR Page 76

REFERENCE:

OPL171 204, Obj ~ 5 K/A: 295036G012 (3. 5/3. 9) 295036G012 ..(KA's)

ANSWER: 058 (1 ~ 00) d.

REFERENCE:

1. OPL171.202, Obj. 13 2 ~ K/A: 295037G007 (3 7/3 ')

..(KA's)

ANSWER: 059 (1. 00) b.

REFERENCE:

1. OPL171.205, Obj. 7b
2. K/A: 295015G012 (3. 7/4. 4) 295015G012 .. (KA's)

ANSWER: 060 (F 00) d.

B,)

SENIOR REACTOR OPERATOR Page 77 t

REFERENCE':

OPL171.074, Obj. 1 K/A: 295003A204 (3.4/3.5) 295003A204 ..(KA's)

ANSWER: 061 (1 ~ 00) b.

REFERENCE:

1. OPL171.202, Obj. 8
2. K/A: 295025A105 (3.7/3.7) 295025A105 ..(KA's)

ANSWER: 062 (1. 00)

c. or b

REFERENCE:

EPIP-1, "Emergency Classification Flowchart 1.

2 ~ K/A: 2950166002 (2 9/4 ')

295016G002 .. (KA's)

ANSWER: 063 (1 ~ 00)

SENIOR REACTOR OPERATOR Page 78 t

REFERENCE:

OPL171 ~ 202 t Ob)

K/A: 295037G007

~ 14 (3. 5/3. 7) 295037G007 ..(KA's)

ANSWER: 064 (1. 00) b.

REFERENCE:

AOI 47-2, page 3 1.

2 ~ K/A 295020G010 (3 '/3 ')

295020G010 .. (KA's)

ANSWER: 065 (1.00)

C~

REFERENCE

1. OPL17 1 ~ 054, Ob) 3
2. K/A: 295019G011 (3 '/4.1) 295019G011 (KA')

ANSWER:,. 066 (l. 00) b.

dS.i SENIOR REACTOR OPERATOR Page 79

REFERENCE:

EOI Appendix 3B K/A: 295037K213 (3.4/4.1) 295037K213 ..(KA's)

ANSWER: 067 ( 1. 00) c

REFERENCE:

1.

2 ~

EOI Appendices 1A, 1B, 1C, 1E K/A 295015K201 (3.8/3 II J

')

295015K201 ..(KA's)

WER: 068 (1~ 00)

REFERENCE:

1. Tech Spec 3.7.C
2. K/A: 295033K204 (3.9/4.2) 295033K204 .. (KA's)

ANSWER: 069 (1 00)

~

b.

d%..

SENIOR REACTOR OPERATOR Page 80

REFERENCE:

Primary Containment Control bases manual, page 47 K/A: 295024K304 (3.7/4.1) 295024K304 .. (KA's)

ANSWER: 070 (1. 00) a0

REFERENCE:

1. OPL171.032, Obj. 11, page 26 2~ K/A: 295017G007 (3. 2/3 6)

~

295017G007 ..(KA's)

ANSWER: 07 1 ( 1. 00) d.

REFERENCE:

70-1, Attachment 1 1.

2 ~

AOX K/A: 295018K101 (3.5/3 ')

295018K101 .. (KA's)

ANSWER 072 (1. 00)

B:)

SENIOR REACTOR OPERATOR Page 81 REFERENCE Technical Specification 3.7.A.l.d 295013G008 (3 5/4.4)

'295013G008 .. (KA's)

ANSWER 073 (1. 00) c ~

REFERENCE:

1. EOI-2, Primary Containment Control bases, 2 K/A: 295029K201 (3 0/3 ') page 145 295029K201 .. (KA s)

, ANSWER: 074 (1- 00) a~

REFERENCE:

1. AOI 32-2, page 13-17
2. OPL171.054, Obj. 5 3 ~ K/A: 295019K209 (3.3/3.3) 295019K209 ..(KA's)

ANSWER: 075 (1. 00)

SENIOR REACTOR OPERATOR Page 82 AOI 32-2, page 13-17 OPL171.054, Obj ~ 5 K/A: 295019A202 (3.6/3 7) 295019A202 .. (KA's)

ANSWER 076 (1. 00)

Co

REFERENCE:

EOI-1, RPV Control Bases, page 33 1.

2 ~ K/A: 295007K304 (4 '/4 ')

295007K304 .. (KA s)

ANSWER: 077 (1.00)

REFERENCE:

1. OPL171.003, Obj.13, page 24 2 ~ f K/A: 295009A201 (4 ~ 2 4 2) 295009A201 .. (KA's)

ANSWER: 078 (1. 00)

0 d.i SENIOR REACTOR OPERATOR Page 83

REFERENCE:

AOI 74-1 OPL171.046, Obj. 13 K/A: 295021K102 (3 ~ 3/3 ~ 4)

'295021K102 .. (KA's)

ANSWER: 079 (1 00) d.

REFERENCE:

1. 2-AOI-85-3 Rev 10, p 2 of 5 (immediate actions) 2~ K/A: 295022G010 (F 7/3.5) 295022G010 .. (KA's)

REFERENCE 2-AOI-100-2, Note, Rev 2 Page 14 of 55

2. OPL171-040 Objective 4 3 ~ K/A: 295016K303 (3.5/3.7) 295016K303 .. (KA's)

ANSWER: 081 (1 00)

~

d.i SENIOR REACTOR OPERATOR Page 84

REFERENCE:

Facility

~

Question Bank 410526

~

~ K/A: 295026G007 '/3.8)

(3 ~ ~

295026G007 .. (KA's)

ANSWER: 082 (1 ~ 00) a~

REFERENCE:

1. OPL171.074 Objective 2 2-AOI-66-2 Rev 8, 4.1 2.

3 ~ K/A: 295017G010 (3 '/3 ')

.. (KA's)

ANSWER: 083 (1.00) b.

REFERENCE:

1. Facility Question Bank 411043 OPL171.007 Objective 12 2.

3 ~ K/A: 295005K302 (3 '/3 ')

295005K302 .. (KA's)

ANSWER: 084 (1. 00)

d.i SENIOR REACTOR OPERATOR Page 85 t

REFERENCE:

'/3 ') of 37, OPL 171.036, Rev 2 p. 18 K/A 295003A101 (3 Objective 12 I

295003A101 .. (KA's)

ANSWER: 085 (1. 00)

REFERENCE:

1. OPL 171.005, Rev 4, p. 39 of 58, Objective 6 2 ~ K/A: 295015K201 (3 8/3 9)

~ ~

295015K201 ..(KA's)

ANSWER: 086 (1. 00) b.

REFERENCE:

1-AOI-57-5A, Rev 10, Cautions, p. of

'/3 ')

1. , 3 44 2 ~ K/A: 295003G007 (3 295003G007 ..(KA's)

ANSWER 087 (1. 00)

Co

d.)

SENIOR REACTOR OPERATOR Page 86 REFERENCE flowcharts EOI K/A: 295034G011 (4.2/4 ')

295034G011 .. (KA's)

ANSWER: 088 (1. 00) b.

REFERENCE:

1. 2-AOI-68-1, Rev 15, Cauter.on, p. 3 of 11 2.

2 ~

OPL171.074, Obj. 22

.K/A 295001A201 (3 5/3 ')

.. (KA's)

ANSWER: 089 (1 00)

Co

REFERENCE:

1. 2-AOI-70-1, Rev 12, p. 2 of 6, 4.1
2. K/A: 295018G010 (3.4/3.3) 295018G010 .. (KA s)

ANSWER: 090 (l. 00) b.

0 B.i SENIOR REACTOR OPERATOR Page 87

REFERENCE:

2-AOX-78-1, Rev 7.

K/A: 2950236006 (3 4/3 6) 295023G006 ..(KA's)

ANSWER: 091 (1. 00)

Co REFERENCE OPL171.028, Rev 5, Table 1 1.

2 ~ K/A: 295006K201 (4 '/4 ')

295006K201 .. (KA's)

ANSWER: 092 ( 1. 00) b.

REFERENCE:

1. OPL 171.028, Rev 5, p. 16 of 39
2. K/A: 295006A206 (3 '/3.8) 295006A206 ..(KA's)

ANSWER: 093 (1 00)

d.)

SENIOR REACTOR OPERATOR Page 88 REFERENCE 2-AOI-100-1, Rev 26, Attachment 5.

EOI-2, Primary Containment Control, Rv 1, entry conditions K/A 295028G010 (3.9/3.6)

'2950286010 .. (KA's)

ANSWER: 094 (1 00)

'a ~

REFERENCE:

1. EOI flowcharts: EOI-1, C-1, C-2, C-3.

2~ K/A: 295031A201 (4.6/4.6) 295031A201 ..(KA's)

ANSWER 095 ( 1. 00) ce

REFERENCE:

1. OPL171.074, Obj. 5 2~ OPL171 009t Obj. 3

~

2~ K/A'95016A108 (4.0/4.0) 295016A108 ..(KA's)

ANSWER: 096 (1 00)

0 SENIOR REACTOR OPERATOR Page 89

REFERENCE:

I OPL171.044,

~

K/A: 295021A207 (3 ~ '/3 ')

Obg.~ 19, pages 22, 24, 28

~

295021A207 .. (KA's)

ANSWER: 097 (1.00)

Co

REFERENCE:

1. EOI, Appendix 18
2. OI 74, page 42
3. K/A: 295030G012 (3.7/4.4) 295030G012 .. (KA's)

ANSWER: 098 { 1. 00)

Co

REFERENCE:

EPIP-1, Rev 13, Attachment 1, p. 1 of 1.

2 ~ K/A: 295023A202 (3 '/3 ') 12 295023A202 .. (KA's)

ANSWER: 099 (1. 00) b.

d5.

SENIOR REACTOR OPERATOR Page 90 t

REFERENCE:

NP-REP, page 13, K/A: 294001A116 3.1.2 (2.9/4.7) 294001A116 .. (KA's)

ANSWER: 100 (1. 00)

Co

REFERENCE:

EOI-1, RPV Control Bases, page 27.

1.

2~ K/A: 2950286004 (2.7/3 ')

295028G004 ..(KA's)

(********** END OF EXAMINATION *****+****)

'55NESSEE VAILZYAUXKORXTY '"-'-""

I QQOlTRC'~~:

BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE El'Il'-1 EMERGENCY PLAN CLASSIFICATION LOGIC RKSIQN 13 PREPARED BY T. W CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: T W. CORNELIUS DATE: 07/01/92 EFFECTIVE DATE: OZ/09/92 VALIDATIONDATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-1 i Revision Number: 13

. Pages. Affected: 15 Pagination Pages: NONE Description of Change:

Change phone 0 from 236-1500 to 273-8500.

EMERGENCY CLASSIFICATION LOGIC 1.0 PURPOSE 1.1 To provide guidance to the Shift Operations Supervisor (SOS) or Site Emergency Director (SED) on what constitute's an emergency classification.

'1.2 To ensure that the emergency classification is consistent with that used by the local and state governments and the NRC.

1.3 To provide a cross reference between this procedure and the ONP-REP, Appendix A, for use by the SOS or SED for additional information in

'classifying events.

2.0 SCOPE 2.1 This procedure applies to those events, that in the professional judgment of the SOS or the SED constitutes an emergency. The SOS and the SED are the only individuals authorized to make the emergency class determination.

2.2 The events listed in the attachments to this procedure cannot possibly incorporate all events which can occur. Therefore, all classifications should be judged against the general guidance listed below:

2.2.1 Notification of Unusual Event Unusual events are in process or have occurred which indicate a potential degradation of the level of safety of the plant.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

2.2.2 Alert Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

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i Page 2 REV 00 ZS BFN-EPIP-1 2.0 (Continued) 2.2'.3 Site. Area Emergency Events are in process or have occurred which involve actual rotection of the ublic. Any releases are not, expected to exceed EPA Protective Action Guideline exposure levels except near site boundary-2.2e4 General 'Emergency Events are in process or have occurred vhich invoive actual or imminent'suhstantial core de radation or meltin vith pbtential for loss of -containment inte rit . Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

3 0 INSTRUCTION 3.1 Review Attachment 1 'to determine if an event should be classified as an emergency.

Note: (1) If an emergency action level for a higher classification was exceeded, but the present situation indicates a lower classification, the fact that the higher classification occurred shall be reported to the NRC and the CECC (if staffed), but should not be declared. (2) If an emergency action level was met but the emergency has been totally resolved, the emergency class that was appropriate shall be declared and terminated at the same time.

s 3.1.1 Attachment 1 captures events in four br'oad categories:

Fission Product Barrier Degradation (F)

System Malfunction (S)

Radiation Levels Abnormal/Radiological Effluents (R)

Hazards and Other Conditions Affecting Plant Safety (H) 3.1.2 Each actual condition in a category is given an alphanumeric designator (FU1 = Fission Product Barrier Degradation (F) resulting in Notification of Unusual Event (U) 01).

3.1.3 The only significance of the alphanumeric designator is a cross-reference to ONP-REP, Appendix A, which provides additional information for the SOS/SED in classifying the event.

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3.0 (Continued) 3.2 If the event is determined to be one of the four emergency classification, the SOS assumes the responsibilities of SED.

3.2.1 Implement one of the following procedures as applicable:

EPZP-2 - Notification of Unusual Event EPIP-3 - Alert EPIP-4 - Site Area Emergency EPPP-5 General Emergency 3.2N2 Continue to review the emergency conditions in Attachment 1 to escalate, de-escalate or terminate the emergency as appropriate.

3.3 If the event is determined not to be one of the four emergency classifications, continue to monitor plant conditions.

4.0 ATTACHMENTS Attachment 1, Emergency Classification Flowchart [NER/C NRC in 89-072]

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azv P>s Page 4 BFN-EPIP-1 Index to Emer enc Classification Flow Chart DESCRIPTION PAGE G I. Fission Product Barrier De radation 4

A. Fuel Damage . 1 B. Primary System Leakage 1 C. Primary Coolant Break or Loss of Inventory ~ ~ 2 D. Primary Containment Integrity . ~ ~ ~ ~ 2 E. Loss of Fission -Product Barriers ~ ~ 2 II. S stem Malfunction A. Tech Spec LCO ~ 0 4 3 B. RPS/Core ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s 3 C. Thermal Power ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 3 D. Shutdown ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ 2 E. Turbine and Condenser . ~ ~ 3 F. AC Power ~ A . A A o . . o A A . . A . ~ ~ ~ 4 G DC Power ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 4 H. Instrumentation, Controls, and Communications 5 III. Radiation Levels Abnormal/Radiolo ical/Effluents A. Radiological Effluents (Liquid) . . . . . . . . . . 6 B.

C. Area Radiation .. '............ ~...

Radiological Effluents (Gaseous) . . . . . . . . . 7 8

IV. Hazards and Other Conditions Affectin Plant Safet A. Security Threat . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 B. Missiles or Aircraft ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 C. Injuries ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 D. Uncontrolled Toxic Gases ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 E. Control Room ~ ~ ~ 10 ll

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F. Earthquake ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

G. Flood ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 11 ll

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No Other ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 12 0130p

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Page lO BF N-EP IP- I ATTACHHENT (Page 6 l

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RADIOLOGKAL QQ LIQUID RELEASE EXCEEDING gQ LIQUID RELEASE EXCEEDING EFFLUENTS TECH SPECS 3.8.A.l, 3 lo TINES TECH SPECS LIQUID OR 5. 3.8.A.l., 3, OR 5 j5P LIQUID RELEASE THAT CANNOT BE TERHINATED l879o

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EMERGENCY CLASSIFICATION FLONCMART NOTE: The NP-REP, Appendix A, contains inforeation or detail, related to emergency classifications or emergency action levels.

AREA RADIATION

~ RADIATION UNEXPECTEDLY ABNORMAL INCREASE BY 1 R/MR (ALARM/RAOCON CONFIRMATION jhow AIRBORNE RADIATION UNEXPECTEDLY INCREASES BY 100 MPC FOR A CONTROLLED AREA. (CAH ALARM/RADCON CONFIRMATION)

(1) MPC = MPC FOR A CONTROLI.EO AREA.

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EHERGENCY CLASSIFICATION FLOMCHART NQTE: The Hp&Ep, Appendix A, contains information or detail. related to emergency classifications or emergency action levels.

INURIES (1) ~ INURED AND COHTAHIHATED INDIVIDUA1. TRANSPORTED TO OFFSITE HOSPITAL UNCONTROLLED TOXIC GASES (2) gQ TOXIC GASES NEAR Qg QNSITE gg HAY IHPAIR STATIQN

~ TOXIC GASES WITHIN PROTECTED AREA AFFECTING

~ TOXIC GASES MITHIH VITAL AREAS AFFECTING OPERABILITY (SQS JUDGHENT) SAFE OPERATIQH OPERATIONS gfQ HOT IN COLD SHUTDQW CONTROL ROQH

~ EVACUATION OR ANTICIPATED EVACUATIOH OF THE CONTROL 855 EVACUATION FRQH THE CONTROL ROON AHQ CONTROL ROON FRON BACKUP CONTROL PANEL' ESTABLISHED MITHIH 15 HINUTES (1) Refer to EPIP-10 for any medical emergency.

(2) Refer to spill prevention control and countermeasures plan and implement as required.

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