ML081010310

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RO and SRO Dresden Initial Exam - March 2008
ML081010310
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 04/17/2008
From:
Division of Reactor Safety II
To:
Exelon Generation Co
References
50-237/08-301, 50-249/08-301 50-237/08-301, 50-249/08-301
Download: ML081010310 (108)
v • d • e


Text

LIST OF PROVIDED REFERENCES

1. Dresden Emergency Operating Procedure (DEOP) flow charts, with entry conditions blanked out.
2. DOP 1600-02, Torus Water Level Control; Revision 15
3. Dresden Technical Specifications LCO 3.5.1, Emergency Core Cooling Systems (ECCS) and Isolation Condenser (IC) - Operating, with less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Times blanked out; Amendment No. 212/204
4. Dresden Technical Specifications LCO 3.3.1.2, SRM Instrumentation, with less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Times blanked out; Amendment No. 185/180
5. Hot Matrix and Cold Shutdown/Refueling Matrix from EP-AA-1004, Radiological Emergency Plan Annex for Dresden Station; Revision 23
6. Dresden Technical Specifications LCO 3.6.4.3, Standby Gas Treatment System, with less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Times blanked out; Amendment No. 221/212
7. DOA 4400-06, 2/3 Cribhouse Screen Plugging
8. Dresden Technical Specifications Bases 3.3.1.1, RPS Instrumentation

U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: March 10, 2008 Facility/Unit: Dresden U1/U2 Region: I II III Y IV Reactor Type: W CE BW GE Y Start Time: 0800 Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant=s Signature Results Examination Value 75 Points Applicant=s Score Points Applicant=s Grade Percent

U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: March 10, 2008 Facility/Unit: Dresden U1/U2 Reactor Type: W CE BW GE Y Region:

I II III Y IV Start Time: 0800 Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant=s Signature Results RO/SRO-Only/Total Examination Values 75 / 25 / 100 Points Applicant=s Scores

/ / Points Applicant=s Grade

/ / Percent

APPENDIX E POLICIES AND GUIDELINES FOR TAKING NRC EXAMINATIONS Each examinee shall be briefed on the policies and guidelines applicable to the examination category (written, operating, walk-through, and/or simulator test) being administered. The examinees may be briefed individually or as a group. Facility licensees are encouraged to distribute a copy of this appendix to every examinee before the examination begins. All items apply to both initial and requalification examinations, except as noted.

Part A: General Guidelines

1.

[Read Verbatim] Cheating on any part of the examination will result in a denial of your application and/or action against your license.

2.

If you have any questions concerning the administration of any part of the examination, do not hesitate to ask them before starting that part of the test.

3.

SRO applicants will be tested at the level of responsibility of the senior licensed shift position (i.e., shift manager).

4.

You must pass every part of the examination to receive a license or to continue performing license duties. Applicants for an SRO-upgrade license may require remedial training in order to continue their RO duties if the examination reveals deficiencies in the required knowledge and abilities.

5.

The NRC examiner is not allowed to reveal the results of any part of the examination until they have been reviewed and approved by NRC management. Grades provided by the facility licensee are preliminary until approved by the NRC. You will be informed of the official examination results about 30 days after all the examinations are complete.

Part B: Written Examination Guidelines

1.

[Read Verbatim] After you complete the examination, 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.

2.

To pass the examination, you must achieve an overall grade of 80.00 percent or greater, with 70.00 percent or greater on the SRO-only items, if applicable. If you only take the SRO portion of the exam (as a retake or with an upgrade waiver of the RO exam), you must achieve an overall grade of 80.00 percent or better to pass. SRO-upgrade applicants who do take the RO portion of the exam and score below 80.00 percent on that part of the exam can still pass overall, but may require remediation.

Grades will not be rounded up to achieve a passing score. Every question is worth one point.

3.

For an initial examination, the nominal time limit for completing the examination is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the RO exam; 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> for the 25-question, SRO-only exam; and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for the combined RO/SRO exam. Notify the proctor if you need more time.

REACTOR OPERATOR Page 4 of 107

4.

You may bring pens, pencils, and calculators into the examination room; however, programable memories must be erased. Use black dark pencil for this examination to facilitate machine grading.

5.

Print your name in the blank provided on the examination cover sheet and the answer sheet. You may be asked to provide the examiner with some form of positive identification.

6.

Mark your answers on the answer sheet provided, and do not leave any question blank.

Use only the paper provided; you may write anywhere on the provided examination. If you have a machine-gradable form that offers more than four answer choices (e.g., Aa@

through Ae@), be careful to mark the correct column.

7.

If you have any questions concerning the intent or the initial conditions of a question, do not hesitate to ask them before answering the question. Note that questions asked during the examination are taken into consideration during the grading process and when reviewing applicant appeals. Ask questions of the NRC examiner or the designated facility instructor only. A dictionary is available if you need it.

When answering a question, do not make assumptions regarding conditions that are not specified in the question unless they occur as a consequence of other conditions that are stated in the question. For example, you should not assume that any alarm has activated unless the question so states or the alarm is expected to activate as a result of the conditions that are stated in the question. Similarly, you should assume that no operator actions have been taken, unless the stem of the question or the answer choices specifically state otherwise. Finally, answer all questions based on actual plant operation, procedures, and references. If you believe that the answer would be different based on simulator operation or training references, you should answer the question based on the actual plant.

8.

Restroom trips are permitted, but only one applicant at a time will be allowed to leave.

Avoid all contact with anyone outside the examination room to eliminate even the appearance or possibility of cheating.

9.

When you complete the examination, assemble a package that includes the examination cover sheet and the answer sheet, and give it to the NRC examiner or proctor.

Remember to sign the statement on the examination cover sheet indicating that the work is your own and that you have neither given nor received assistance in completing the examination. Leave all other items at your examination table face down. The examination will be retained by the station training department.

10.

After turning in your examination, leave the examination area as defined by the proctor or NRC examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.

11.

Do you have any questions?

REACTOR OPERATOR Page 5 of 107 QUESTION 001 Unit 2 is in Reactor startup. An NSO notes that Recirc loop temperature is 30°F lower than the temperature used by the QNE to predict the critical step/rod/notch?

What affect would this have on the actual critical step/rod/notch?

Actual criticality would.....

be later due to the doppler coefficient.

b.

be sooner due to being over-moderated.

c.

be later due to the moderator temperature coefficient.

d.

be sooner due to the moderator temperature coefficient.

  • ANSWER
d.
  • REFERENCE DGP 1-1 K/A

.2.2.34 Memory Bank

REACTOR OPERATOR Page 6 of 107 QUESTION 002 Unit 2 was operating at near rated power, with TR-86 Out Of Service, when the following occurred:

Time 0 seconds: Drywell pressure increased to +3.8 psig.

Time +15 seconds: annunciator "4 KV BUS 24-1 OVERCURRENT" alarms.

Time +19 seconds: 138kv BT 1-2 CB, 138kv L0904 CB, AND 138kv L1205 CBs open due to an electrical storm.

What is the expected status of the Unit 2 LPCI pumps at time +33 seconds?

a.

NO pumps running.

b.

A & B pumps ONLY running.

c.

C & D pumps ONLY running.

d.

ALL pumps running.

  • ANSWER
b.
  • REFERENCE 12E-2304 DAN 902-8 E-5 K/A 203000K201 High Bank

REACTOR OPERATOR Page 7 of 107 QUESTION 003 Unit 2 is operating at near rated power, with DOS 6600-01 DIESEL GENERATOR SURVEILLANCE TEST, in progress for the Unit 2 Diesel. The NSO is ready to synchronize the Diesel to Bus 24-1.

In accordance with the surveillance, the synchroscope should rotate 1 revolution every

___(1)___ seconds in the ___(2)___ direction.

a.

(1) 30 (2) SLOW

b.

(1) 30 (2) FAST

c.

(1) 60 (2) SLOW

d.

(1) 60 (2) FAST ANSWER

b.

REFERENCE DOS 6600-01 K/A 264000A405 Memory New

REACTOR OPERATOR Page 8 of 107 QUESTION 004 Unit 3 was operating at near rated power when a steam leak occurred inside the Drywell. The following conditions exist:

Drywell pressure is 3.7 psig and increasing.

All control rods fully inserted EXCEPT F-5, which remained at position 24.

Which of the DEOPs below are required to be entered?

1) DEOP 100, RPV CONTROL
2) DEOP 200-1, PRIMARY CONTAINMENT CONTROL
3) DEOP 300-1, SECONDARY CONTAINMENT CONTROL
4) DEOP 400-5, FAILURE TO SCRAM
a.

1 and 2

b.

1 and 3

c.

2 and 3

d.

2 and 4

  • ANSWER
a.
  • REFERENCE DEOP 100 DEOP 200-1 K/A 2.4.1 Memory New REQUIRED

REFERENCES:

DEOP charts, with the entry conditions blanked out.

REACTOR OPERATOR Page 9 of 107 QUESTION 005 Unit 2 was operating at near rated power, when a LOCA occurred. The following conditions exist:

RPV pressure is 200 psig and lowering slowly.

Indicated Wide Range RPV water level is 80 inches and slowly rising.

Drywell pressure is 5.5 psig and rising slowly.

Drywell temperature is 425°F and steady.

Wide Range RPV water level instrumentation is.....accurate AND can be used for trending.

b.

NOT accurate and CAN be used for trending, since WR level is above indicated usable level.

c.

NOT accurate and CANNOT be used for trending, since WR level is below indicated usable level.

d.

NOT accurate and CANNOT be used for trending since D/W temperature above saturation temperature.

ANSWER

d.

REFERENCE DEOP 100 table 'A' EPG B-5-3 K/A 295028K101 High Bank

REACTOR OPERATOR Page 10 of 107 QUESTION 006 Unit 2 was operating at near rated power when a small break LOCA is experienced, with the following set of initial conditions:

Drywell pressure is 1.18 psig.

RPV water level is +30 inches on the Medium Range indicators.

As Drywell pressure starts to RISE, the Drywell Spray valves are interlocked closed at

___(1)___ psig, but the interlock may be overridden via the use of ___(2)___ keylock switch(es) in each division.

(1) 1.5; (2) a single

b.

(1) 1.5; (2) two

c.

(1) 2; (2) a single

d.

(1) 2; (2) two ANSWER

c.

REFERENCE DAN 902-3 A-13 DOP 1500-03 K/A: 295024K215 MemoryNew

REACTOR OPERATOR Page 11 of 107 QUESTION 007 Unit 2 was operating at near rated power when the following occurred:

TIme 12:00:00 the TR-22 Sudden Pressure Relay device activated.

Time 12:00:01 the Aux Power system "fast transfer" FAILED to occur.

At time 12:00:05, which Condensate/Condensate Booster pumps (if any) would currently have electrical power available?NONE

b.

Only "A" and "B"

c.

Only "C" and "D"

d.

ALL ANSWER

b.

REFERENCE Electrical Print 12E-2370 K/A: 256000K201 High New

REACTOR OPERATOR Page 12 of 107 QUESTION 008 Unit 3 was operating at near rated power when the following 903-7 panel annunciators are received:

C-3, TURB STATOR COOLANT RUNBACK.

C-10, STATOR CLG PANEL TROUBLE.

The Turbine will runback to approximately ___(1)___ stator amps within 2 minutes. If the stator amps do NOT reach this value, the Turbine will trip ___(2)___.

a.

(1) 6350; (2) immediately

b.

(1) 7350; (2) 1 minute later

c.

(1) 8350; (2) 1 minute later

d.

(1) 9350; (2) immediately ANSWER

b.

REFERENCE DAN 902-7 C-3 K/A: 245000K605 Memory Bank

REACTOR OPERATOR Page 13 of 107 QUESTION 009 You are the Unit 2 AUX NSO and an annunciator has been alarming intermittently over several shifts, on the 902-5 panel. Whose concurrence, AT A MINIMUM, is required to stop ANNOUNCING the alarm, per OP-AA-103-102 WATCHSTANDING PRACTICES?The Unit Reactor Operator ONLY.The Unit Supervisor OR Shift Manager.The Unit Reactor Operator AND Shift Manager.The Unit Reactor Operator AND Unit Supervisor.OP-AA-103-102 K/A: 2.4.10 Memory Bank

REACTOR OPERATOR Page 14 of 107 QUESTION 010 Unit 3 is in startup, with rod pulls in progress. The NSO is single notching a Control Rod out from position 12 to position 14, when annunciator 902-5 G-3, RPIS SYS INOP is received.

RMCS.....is uneffected.will return the rod to position 12.will generate a rod select block.will remove the drive signal and a rod drift will occur.DAN 902-5 G-3 K/A: 214000K303 MemoryBank

REACTOR OPERATOR Page 15 of 107 QUESTION 011 Unit 2 was operating at near rated power, when a Reactor scram occurred.On the drawing below, the indication for the breakers in Group 1 is ___(1)___ and the indication for the breakers in Group 2 is ___(2)___.

a.

(1) Correct; (2) Correct

b.

(1) Correct; (2) Incorrect

c.

(1) Incorrect; (2) Correct

d.

(1) Incorrect; (2) Incorrect ANSWER

b.

REFERENCE DOA 6000-01 K/A: 295005A107 High Bank

REACTOR OPERATOR Page 16 of 107 QUESTION 012 The following plant conditions exist after a transient with both units at power:

Unit 2 West Corner Room Sump Level Hi alarm is received.

Unit 3 East Corner Room Sump Level Hi alarm is received.

Unit 2 HPCI Room Floor Drain Sump Level Hi alarm is received.

Area Temperatures and Radiation Levels for all ECCS Rooms on both units are normal.

NLOs are dispatched and provide the following reports:

There is 1 inch of water on the Unit 2 HPCI Room floor - Water level is steady.

The Unit 2 West Corner room floor is covered in water (< 1 inch and level is steady).

Why are the sump pumps operated under these conditions per DEOP 300-1?To maintain equipment operability.To maintain site release rates below 10 CFR 100 limits.To quantify the leakage rate to determine Tech Spec required actions.To ensure environmental conditions are maintained for EQ Instrumentation.

ANSWER

a.

REFERENCE DAN 902-4 C-19 DOA 0040-02 DEOP 300-1 Bases B-8-2 K/A: 295036K304 Memory Bank

REACTOR OPERATOR Page 17 of 107 QUESTION 013 Unit 2 was operating at near rated power when the following sequence of events occurred:

Time = 0 seconds: A spurious Group 1 signal occurs.

Time = 5 seconds: RPV pressure peaks at 1070 psig.

Time = 12 seconds: RPV pressure drops to 1025 psig.

The Reactor scrammed on ___(1)___ and the Isolation Condenser ___(2)___ initiated to control RPV pressure.(1) MSIV closure; (2) automatically(1) MSIV closure; (2) will be manually(1) High RPV pressure; (2) automatically(1) High RPV pressure; (2) will be manuallyElectrical Print 12E-2502A Electrical Print 12E-2506 Electrical Print 12E-2507 Electrical Print 12E-2512 K/A: 207000K402 HighBank

REACTOR OPERATOR Page 18 of 107 QUESTION 014 Given the following:

An extended Refueling and Maintenance Outage is in progress All four of the RPS Shorting Links are removed from the 902-15 and -17 Panels Then SRM 21 spikes to a full scale indication What response is expected from the RPS system under these conditions?No RPS actuation.1/2 scram on RPS channel A ONLY.1/2 scram on RPS channel B ONLY.Full scram.LP DRE212LN001 K/A: 215004A303 MemoryBank

REACTOR OPERATOR Page 19 of 107 QUESTION 015 Unit 2 was operating at near rated power when the output from the Instrument Bus was lost.

If the NSO placed the 2B Electromatic Relief Valve (ERV) control switch to the MANUAL position, the ERV will.....

a.

remain closed.

b.

open and its position could be confirmed by acoustic monitoring ONLY.

c.

open and its position could be confirmed by tailpipe temperature ONLY.

d.

open and its position could be confirmed by BOTH tailpipe temperature AND acoustic monitoring.

ANSWER

b.

REFERENCE DOA 6800-01 K/A: 239002K603 High Bank

REACTOR OPERATOR Page 20 of 107 QUESTION 016 Unit 2 was operating at near rated power with the 'A' SBGT train in PRI and the 'B' SBGT train in STBY, when the following sequence of events occurred:

A steam leak developed in the HPCI room.

Annunciator 902-3 A-3, RX BLDG VENT CH B RAD HI HI was received.

2 minutes later the 'A' SBGT train heater TRIPS.

10 minutes later secondary containment differential pressure would be ___(1)___ because

___(2)___.(1) uneffected; (2) 'A' SBGT would be running and 'B' SBGT would be in standby(1) uneffected; (2) 'B' SBGT would be running and 'A' SBGT would be tripped(1) more negative; (2) 'A' and 'B' SBGT would be running(1) less negative; (2) 'A' and 'B' SBGT would be trippedDAN 902-3 A-3 DAN 923-5 A-6 K/A: 261000K301 High New

REACTOR OPERATOR Page 21 of 107 QUESTION 017 The NSO observes the following 902-5 Panel indication:

Which of the following describes the condition of the FWLC RPV water level instrumentation?

a.

Narrow Range "A" is available Narrow Range "B" is NOT available Medium Range "A" is available Median Level Control is in control

b.

Narrow Range "A" is in control Narrow Range "B" is available Medium Range "A" is available Median Level Control is NOT available

c.

Narrow Range "A" is in control Narrow Range "B" is NOT available Medium Range "A" is NOT available Median Level Control is NOT available

d.

Narrow Range "A" is in control Narrow Range "B" is available Medium Range "A" is NOT available Median Level Control is NOT available ANSWER

d.

REACTOR OPERATOR Page 22 of 107 REFERENCE DOP 0600-06 K/A: 216000A402 High Bank

REACTOR OPERATOR Page 23 of 107 QUESTION 018 Unit 3 was operating at near rated power, when the following occurred:An automatic scram occurred, with an ATWS resulting.

Reactor Power is currently 42%.

Drywell pressure is 1.30 psig and trending up.

RPV water level was terminated and prevented, to -55 inches per DEOP 400-5.

Maximum Torus Cooling has been established.

Then Drywell pressure reaches > 2.0 psig.

What effect does this have on Torus Cooling, if any, AND what must be done to re-establish Max Torus Cooling, if anything?None, because the HX BYPASS VLVs will be interlocked closed; no manipulations are required.None, until RPV pressure drops below 350 psig, at which time the HX BYPASS VLVs will open; the HX BYPASS VLVs are required to be re-closed after they have opened.Cooling will be reduced, because the HX BYPASS VLVs will open and be interlocked open for 30 seconds; the HX BYPASS VLVs are required to be re-closed after interlock has timed out.Cooling will be reduced, because the HX BYPASS VLVs will open and be interlocked open until RPV pressure drops below 350 psig; the HX BYPASS VLVs are required to be re-closed after they have opened.

ANSWER

c.

REFERENCE DOP 1500-02 attach C K/A: 219000A204 High Bank

REACTOR OPERATOR Page 24 of 107 QUESTION 019 Unit 2 was operating at near rated power, with a Torus water temperature of 95°F. If Torus water temperature rises to 110°F, the Safety Parameter Display System (SPDS) indicating bar will....remain yellow and flash.remain green and flash.change from yellow to flashing red.change from green to flashing yellow.DOP 9950-17 K/A: 295026K204 MemoryNew

REACTOR OPERATOR Page 25 of 107 QUESTION 020 Unit 3 was operating at near rated power, when the 3A Recirc pump tripped. The Shift Manager has decided to remain in single loop operation while trouble shooting the cause of the pump trip.

Which of the following Thermal Limits are required to have correction factors implemented within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />?LHGR and MCPR ONLYLHGR and MAPLHGR ONLYMAPLHGR and MCPR ONLYLHGR, MCPR, AND MAPLHGRREFERENCE DGP 3-3 K/A: 295001K103 MemoryBank

REACTOR OPERATOR Page 26 of 107 QUESTION 021 Unit 3 was operating at near rated power, when the following occurred:

05:27:00 Drywell pressure reaches 4 psig.

05:28:00 Torus sprays are initiated.

05:33:10 TR 32 trips AND Unit 3 and 2/3 Emergency Diesel Generators re-energize their associated busses.

Which of the following times is the EARLIEST that rated Torus Spray flow will be re-established?05:33:1505:33:2305:33:3805:34:10REFERENCE\\

UFSAR K/A: 230000A109 HighBank

REACTOR OPERATOR Page 27 of 107 QUESTION 022 Which of the following sets of parameters would require entry into DEOP 200-1?

A Drywell to Torus differential pressure of ___(1)___ and Torus level of ___(2)___.(1) 1.2; (2) -3.4(1) 1.2; (2) -4.4(1) 1.8; (2) -3.4(1) 1.8; (2) -4.4DOP 1600-2 K/A: 295030 2.1.25 HighNew REQUIRED

REFERENCES:

DOP 1600-02.

REACTOR OPERATOR Page 28 of 107 QUESTION 023 Given the following information regarding the Control Room HVAC system:

B AHU is running.

A AHU control switch has a GREEN-TARGET.

The NSO takes the CRM ISOL switch to the "ISOLATE" position, on 923-5 panel.

Which one of the following describes the Control Room Ventilation system response?B AHU continues to run, system dampers line-up for the smoke purge mode.B AHU continues to run, system dampers line-up for the isolation/recirculation mode.B AHU continues to run, A AHU auto starts, system dampers line-up for the isolation/recirculation mode.B AHU is tripped, A AHU and the AFU auto start, and system dampers line-up for the isolation/recirculation mode.DOP 5750-05 DOA 5750-01 DOA 5750-04 K/A: 290003K401 High Bank

REACTOR OPERATOR Page 29 of 107 QUESTION 024 Unit 2 was operating at near rated power when a transient occurred causing an automatic Reactor scram. Which of the following parameters initiated the scram?

a.

RPV pressure

b.

Drywell pressure

c.

RPV water level

d.

Main Condenser vacuum ANSWER

a.

REFERENCE DANs 902-5 D-10, 902-5 C-13, 902-5 D-11, 902-5 B-13, DOA 4400-01 K/A: 295006A204 High New

REACTOR OPERATOR Page 30 of 107 QUESTION 025 Unit 2 is in SHUTDOWN, with both Recirc pumps O.O.S., and the following set of conditions exist:

RPV water temperature is 185°F and trending up.

2A and 2B Shutdown Cooling loops are in operation.

If the SDC system is lost, determine which of the following is the LOWEST RPV water level that would prevent vessel stratification?+30 inches+40 inches+50 inches+60 inchesUFSAR 5.4.1.4 DOP 1000-3 LP DRE223LN004 LP DRE205LN001 K/A: 295021A203 MemoryBank

REACTOR OPERATOR Page 31 of 107 QUESTION 026 An accident has occurred at the station and you have volunteered to perform an evolution to protect valuable property. The dose rate in the area you will be entering is 30 Rem/hr.

What is the MAXIMUM time you can spend in the area performing your task without violating TEDE Radiation Exposure Limits per RP-AA-203 EXPOSURE CONTROL AND AUTHORIZATION?10 minutes.20 minutes.30 minutes.60 minutes.RP-AA-203, EP-AA-113K/A:

2.3.04HighBank

REACTOR OPERATOR Page 32 of 107 QUESTION 027 Unit 2 was operating at near rated power when the annunciator 902-4 E-12, RWCU SYS AFTER NON-REGEN HX TEMP HI, was received.

Which of the following is an all inclusive list of the RWCU valves that would indicate CLOSED?

2-1201-1 RX OUTLET ISOL 2-1201-1A RX OUTLET BYP 2-1201-2 INLET ISOL 2-1201-3 AUX PP SUCT 2-1201-7 RX RETURN

a.

2-1201-1;2-1201-1A; 2-1201-2

b.

2-1201-1; 2-1201-2; 2-1201-3; 2-1201-7

c.

2-1201-1; 2-1201-1A; 2-1201-2; 2-1201-3

d.

2-1201-1; 2-1201-1A; 2-1201-2; 2-1201-3; 2-1201-7 ANSWER

c.

REFERENCE DAN 902-4 E-12 K/A: 204000A305 Memory Bank

REACTOR OPERATOR Page 33 of 107 QUESTION 028 Unit 3 was operating at near rated power when the following occurred:

The Bus 39 feed breaker opened on a fault.

Which of the following ESS indication(s) in the Main Control Room would alert the Operator to this fault?903-8 E-8, ESS UPS ON DC OR ALTERNATE AC, annunciator in alarm ONLY.903-8 E-10, 120/240V AC ESS BUS ON EMERG SPLY, annunciator in alarm ONLY.903-8 E-8, ESS UPS ON DC OR ALTERNATE AC, annunciator in alarm AND a momentary loss of power to the ESS loads.903-8 E-10, 120/240V AC ESS BUS ON EMERG SPLY, annunciator in alarm AND a momentary loss of power to the ESS loads.DAN 903-8 E-8K/A: 262002A301HighBank

REACTOR OPERATOR Page 34 of 107 QUESTION 029 Unit 2 TBCCW system has been lost and cannot be restored.

Which of the following actions are required?Verify Stator Cooling runback occurs, due to high temperatures.Verify the CRD pump oil coolers AUTO transfer to the Service Water system.Announce loss of Service Air on the PA system to warn personnel who may be using U2 Service Air.Reduce Recirc pump speeds to maintain MG Set motor winding temperatures below procedural limits.DOA 4600-01 DOP 3800-01 DAN 923-1 C-5K/A: 295018 2.1.14MemoryNew

REACTOR OPERATOR Page 35 of 107 QUESTION 030 In order to return a Licensee to ACTIVE status from INACTIVE status, the Licensee must.....

a.

obtain special permission from the NRC Regional office for reactivation.

b.

at a minimum, have received a passing grade on a special reactivation exam.

c.

participate in a complete plant tour as part of a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions

d.

complete a minimum of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of shift functions under the direction of an operator or senior operator and in the position to which the individual will be assigned.

ANSWER

c.

REFERENCE OP-AA-105-102 10 CFR 55.53 K/A: 2.1.1 Memory Bank

REACTOR OPERATOR Page 36 of 107 QUESTION 031 Unit 2 was operating at near rated power when Bus 23 de-energized due to an undervoltage condition.

Which one of the following is an automatic response of the AC electrical distribution system?The Bus 26 cross-tie breaker to Bus 25 ONLY will auto close.The Bus 27 cross-tie breaker to Bus 25 ONLY will auto close.Bus 25 will be automatically re-energized when Bus 23 is re-energized.EITHER Bus 26 OR Bus 27 cross-tie breaker to Bus 25 will auto close.DGA-12 LP DRE262LN001K/A: 262001K403HighNew

REACTOR OPERATOR Page 37 of 107 QUESTION 032 Unit 3 is operating at near rated power, when the following occurs:

Main Condenser vacuum begins degrading.

The temperature of the Unit 3 Condensate system will ___(1)___ a manual Scram may be required due to the loss of ___(2)___.(1) increase, and (2) Feedwater Heating(1) increase, and (2) Steam Jet Air Ejectors(1) NOT change, but (2) Feedwater Heating(1) NOT change, but (2) Steam Jet Air EjectorsDOA 3300-02 DOA 4400-01 DGP 3-1K/A: 295002K206 High Bank

REACTOR OPERATOR Page 38 of 107 QUESTION 033 Unit 2 was operating at near rated power, when the following set of conditions occurred:

A Scram occurs on high DW pressure.

A Loss of off-site power (LOOP) occurs.

The 2/3 cribhouse inlet temperature is 93°F and steady.

Given the above conditions, a maximum of ___(1)___ CCSW pumps may be run concurrently, to prevent ___(2)___.(1) 2; (2) overloading the 2/3 EDG(1) 3; (2) overloading the 2/3 EDG(1) 2; (2) choking the DGCWP flow to the 2/3 EDG(1) 3; (2) choking the DGCWP flow to the 2/3 EDG DOP 1500-02 DOP 6600-05 UFSAR 6.3 DGA 12 K/A: 400000 2.1.32 High New

REACTOR OPERATOR Page 39 of 107 QUESTION 034 Unit 2 was operating at near rated conditions, when the following occurred:

Unit 2 experienced a Loss of Off-Site Power (LOOP).

Annunciator 902-8 E-4 2/3 DG OVERLOAD alarmed.

Annunciator 902-8 D-4 2/3 DG GROUND FAULT alarmed.

Annunciator 902-8 E-5 4KV BUS 24-1 OVERCURRENT alarmed.

2/3 DIESEL GENERATOR KILOWATT meter reads 2800 Kilowatts.

What action(s) is/are the NSO required to take?Dispatch an NLO to depress the EMERGENCY STOP pushbutton on the 2/3 DG.Trip ALL loads connected to 2/3 DG, then close breakers one at a time to locate ground fault to prevent damage to the Generator.Trip ALL loads connected to 2/3 DG, then close breakers one at a time to locate ground fault to prevent damage to the load when Off-Site power restored.Trip all UNNECESSARY loads connected to 2/3 DG, then close breakers one at a time to locate ground fault to prevent damage to the load when Off-Site power restored.DAN 902-8 D-4 DAN 902-8 E-4K/A: 295003K304 High Bank

REACTOR OPERATOR Page 40 of 107 QUESTION 035 Unit 3 was operating at near rated conditions, when the following occurred:

A leaking valve has caused water to be sprayed on 'A' SBGT Charcoal Bed.

A fuel handling accident occurred, causing radiation levels at the site boundary to increase.

An NSO isolated Reactor Building ventilation and started the 'A' SBGT train.

The release rates at the site boundary will be higher than anticipated for which of the following?

a.

Iodine

b.

Particulates

c.

Transuranics

d.

Noble Gases ANSWER

a.

REFERENCE ILTS027 UFSAR K/A 295038K102 High Bank

REACTOR OPERATOR Page 41 of 107 QUESTION 036 Unit 2 was operating at near rated power, with the 'B' Reactor Building Ventilation Radiation Monitor removed from service, when Bus 29 de-energized on overcurrent.

This will cause.....the SBGT system to auto start.the 2A RPS MG Set to lose power.the ESS Bus ABT to swap to MCC 28-2.the Reactor building crane to be "locked" in its current position.DOA 0500-5 DOP 0500-03 DAN 903-3 G-14K/A: 261000K604 High Bank

REACTOR OPERATOR Page 42 of 107 QUESTION 037 A Chemistry Technician called the Control Room and reported a fire in the Unit 3 trackway.

Which of the following is an IMMEDIATE action to take per DOA 0010-10, FIRE/EXPLOSION, and why?Notify Coal City Fire Protection District to extinguish the fire.Notify Security to respond to the scene to provide support as required.Start the standby Service Water Pump to raise the fire header pressure.Direct Chemistry Technician to remain at the scene to monitor air quality and provide first aid as required.DOA 0010-10 K/A: 600000K304 Memory New

REACTOR OPERATOR Page 43 of 107 QUESTION 038 Given the following set of conditions:

Unit 2 is in Mode 3 with Recirc loop temperatures 310°F and steady.

2A and 2B Shutdown Cooling (SDC) Pumps are running in the COOLING mode with their discharge valves 15% open.

2A and 2B RBCCW pumps are operating on Unit 2.

RPV level is at +30 inches.

If MO 2-3704, RBCCW OUTLET VLV, is INITIALLY timed opened for 16 seconds, the effect would be _______.

a.

an RPV water level increase

b.

a Recirculation loop temperature increase

c.

a Recirculation loop temperature decrease

d.

BOTH RBCCW pumps tripping on low discharge pressure ANSWER

c.

REFERENCE DOP 1000-03 K/A: 205000A103 Memory Bank

REACTOR OPERATOR Page 44 of 107 QUESTION 039 Unit 3 has just scrammed, with the following conditions:

Drywell pressure is 2.8 psig and steady.

The 903-5 panel NSO reports that HPCI is NOT needed for RPV water level control, but MAY be needed at a later time.

Per DOP 2300-04 hardcard attachment 1A, HPCI CONTROL/SHUTDOWN WITH INJECTION SIGNAL PRESENT, what are the proper actions to take on the HPCI flow controller to place HPCI in the configuration specified?

a.

Depress the "M" pushbutton.

Press and hold button "D"until the LED bar is at "0" gpm.

b.

Ensure the "A" pushbutton is depressed.

Press and hold button "D" until the LED bar is at "0" gpm.

c.

Depress the "M" pushbutton.

Move and hold lever "L" in the "C" direction until pointer "P" is at position "0".

d.

Depress button "B" and ensure light "PF" is lit.

Move and hold level "L" in the "C" direction until pointer "P" is at position "0".

ANSWER

c.

REFERENCE DOP 2300-04

REACTOR OPERATOR Page 45 of 107 K/A: 206000A402 Memory Bank

REACTOR OPERATOR Page 46 of 107 QUESTION 040 Both units were operating at near rated power, when the following occurred:

125 VDC POWER FAILURE annunciators alarm on both the 902-8 and 903-8 panels.

NSOs diagnosed a complete loss of the Unit 2 125 Vdc system.

An NLO, in the field, reports a GREEN light above GENERATOR 3 AUX 86B TRIP UNIT 3 control switch is illuminated.

What effect, if any, does this condition have on the Unit 3 Main Generator's protection?No effect.Generator trips as a result of this loss.Half the protection is lost (generator has trip capability).All of the protection is lost (generator does NOT have trip capability).DOA 6900-T1K/A: 263000K302 High New

REACTOR OPERATOR Page 47 of 107 QUESTION 041 Unit 2 is in a startup with power ascension in progress with IRMs indicating 50 on range 4.

Positioning IRM CH 11 RANGE SWITCH from range 4 to 5 will automatically change the scale on IRM-APRM recorder, RR 2-750-10A to ___(1)___ and ___(2)___ will be displayed on the recorder chart trace.(1) 0 - 40 (2) 5.0(1) 0 - 40 (2) 50(1) 0 - 125 (2) 5.0(1) 0 -

125 (2) 50LP DRE215LN003K/A: 215003A301 High Bank

REACTOR OPERATOR Page 48 of 107 QUESTION 042 Unit 2 was operating at near rated power, when a SCRAM occurred. The following parameters are observed:

APRMs are cycling between 8% and 10%.

RPV pressure is 920 psig.

RPV water level is +5 inches.

Drywell pressure is 1.2 psig.

All RPS Channel 'A' and 'B' lights are extinguished.

Which of the statements below demonstrates a proper verbal report from the Unit NSO to the Unit Supervisor per DGP 2-3, REACTOR SCRAM?"Attention for an update, All rods in, Reactor level and pressure and Drywell pressure are trending as expected, End of Update""Attention for an update, Rods did not go in, ARI actuated, it is a hydraulic ATWS, Reactor power is approximately 10%, End of Update""Attention for an update, Rods did not go in, ARI actuated, it is a hydraulic ATWS, Reactor water level is +5 inches, Reactor pressure is 920 psig, Drywell pressure is 1.2 psig, and Reactor power is approximately 10%, End of Update""Attention for an update, Rods did not go in, ARI actuated, it is an electrical ATWS, Reactor water level is +5 inches, Reactor pressure is 920 psig, Drywell pressure is 1.2 psig, and Reactor power is approximately 10%, End of Update"DGP 2-3K/A: 2.1.17 High New

REACTOR OPERATOR Page 49 of 107 QUESTION 043 Unit 2 was operating at near rated power, when the following occurred:

The Reactor scrammed on high Drywell pressure.

Drywell pressure is 7.3 psig and climbing at a rate of 1.0 psig/minute.

10 seconds later, annunciator 923-1 F-1, U2 RBCCW HEAD TANK LVL HI/LO was received.

An NLO reports that the U2 RBCCW head tank level is out of sightglass LOW.

What are the possible consequences of this situation AND what action(s) are required?A potential for the Unit 2 RBCCW pumps to trip exists, due to low suction pressure; isolate RBCCW to the Drywell per DOA 3700-01, LOSS OF THE RBCCW SYSTEM.A potential for the Unit 2 RBCCW pumps to trip exists, due to low suction pressure; open the RBCCW head tank level control bypass valve per DAN 923-1 F-1 U2 RBCCW HEAD TANK LVL HI/LO.A potential of a leakage path from the Primary containment to the Reactor Building via the RBCCW head tank vent exists; isolate RBCCW to the Drywell per DOA 3700-01, LOSS OF THE RBCCW SYSTEM.A potential of a leakage path from the Primary containment to the Reactor Building via the RBCCW head tank vent exists; open the RBCCW head tank level control bypass valve per DAN 923-1 F-1 U2 RBCCW HEAD TANK LVL HI/LO.DAN 923-1 F-1, DOA 3700-01 K/A: 400000A202 High New

REACTOR OPERATOR Page 50 of 107 QUESTION 044 Unit 3 was operating at near rated power when a transient caused Instrument Air pressure to drop rapidly to 0 psig.

If NO Operator actions are taken, which of the following responses will occur?The 3-0302.6A, U3 CRD SYS A FCV, will fail OPEN.The 3-3201A, 3A RFP MIN FLOW VLV, will fail CLOSED.The 3-2301-65, U3 HPCI TURB SV ABOVE SEAT DRAIN VLV, will fail OPEN.The 3-1301-17 and 3-1301-20, U3 ISOL CDSR VENT ISOL VLVs, will fail CLOSED.DOA 4700-01 K/A: 295019K205Memory New

REACTOR OPERATOR Page 51 of 107 QUESTION 045 A transient occurred, which caused the Unit Supervisor to enter several DEOP procedures.

Per OP-DR-103-102-1002, STRATEGIES FOR SUCCESSFUL TRANSIENT MITIGATION, when Drywell pressure approaches or reaches _______ psig, the NSO shall be aware of AND report the parameter.2.0 and 9.0 ONLY1.5 and 2.0 ONLY1.5, 2.0, and 9.0 ONLY1.5, 2.0, 9.0, and 12.0OP-DR-103-102-1002 K/A: 2.4.15 Memory New

REACTOR OPERATOR Page 52 of 107 QUESTION 046 Automatic fire protection for the Unit 3 Emergency Diesel Generator (EDG) room is provided by which of the following system(s)?Halon ONLY.Water ONLY.Cardox ONLY.Cardox AND Halon.DFPS 4183-03 K/A: 286000.K1.09 Memory New

REACTOR OPERATOR Page 53 of 107 QUESTION 047 Secondary Containment Ventilation Radiation levels are rising as indicated by readings on the Fuel Pool Channel Radiation Monitors.

If these radiation monitors continue to rise to their MAXIMUM level, what SBGT system indication would the NSO expect to observe?

a.

Figure A

b.

Figure B

c.

Figure C

d.

Figure D ANSWER

c.

REFERENCE DAN 902-3 C-16 DOP 7500-01 K/A: 295034A102 Memory Bank

REACTOR OPERATOR Page 54 of 107 QUESTION 048 Per DFP 0800-01, MASTER REFUELING PROCEDURE, which of the following is required to verify the Shutdown Margin is adequate prior to start of fuel moves?Shift Manager.Unit Supervisor.Refuel Floor Supervisor.Qualified Nuclear Engineer.DFP 0800-01 K/A: 2.2.26 Memory New

REACTOR OPERATOR Page 55 of 107 QUESTION 049 Both units were operating at near rated power, when the following occurred:

A fire has de-energized Unit 3 DC Turbine Building MCC 3.

What is the impact (if any) on the Unit 2 HPCI system?HPCI would operate upon an auto start signal, because MO 2-2301-3 TURB STM SUPPLY is unaffected.HPCI would NOT operate upon an auto start signal, because the Aux Oil Pump would be de-energized.HPCI would NOT operate upon an auto start signal, because the Motor Speed Changer would be de-energized.HPCI would NOT operate upon an auto start signal, but could be started by depressing the HPCI AUTO INITIATE pushbutton.DOP 6900-01 DOA 6900-04K/A: 206000K602 High Bank

REACTOR OPERATOR Page 56 of 107 QUESTION 050 Unit 2 was operating at near rated power, when a Reactor Scram occurred.

If RPV pressure is 555 psig and steady, what level correlates to Top of Active Fuel (TAF) on the 902-3 panel Fuel Zone indicators?

a.

-143 inches

b.

-170 inches

c.

-187 inches

d.

-191 inches ANSWER

b.

REFERENCE TSG, attachment L hardcard K/A: 295031A203 Memory Bank

REACTOR OPERATOR Page 57 of 107 QUESTION 051 Unit 2 was operating at near rated power, when U2 125 VDC TURB BLDG MAIN BUS 2A-1 DIST PANEL de-energized.

Which of the following load(s) will have lost Control Power indication in the Control Room?U2 'A' EHC Pump.U2 'B' RBCCW Pump.U2 'A' Circulating Water Pump; U2 'B' Circulating Water Pump.U2 'A' Circulating Water Pump; U2 'C' Circulating Water Pump.DAN 902-8 F-1 DOP 6900-06 DOA 6900-T1K/A: 295004K203 Memory New

REACTOR OPERATOR Page 58 of 107 QUESTION 052 A fire occurred in the Main Control Room, and off-site power IS available.

While performing DSSP 0100-CR, CONTROL ROOM EVACUATION Attachment 'A' on Bus 23-1, the U2 NSO is required to verify the ___(1)___ indicating light is illuminated on the front of the breaker for Cubicle 9, 2-6723-2 MAIN FROM BUS 23 and verify the ___(2)___

indicating light is illuminated on the front of the breaker for Cubicle 14, 2/3-6601, STAND-BY 2/3 DG.(1) RED; (2) RED(1) RED; (2) GREEN(1) GREEN; (2) RED(1) GREEN; (2)

GREENDSSP-0100-CR K/A: 295016A104

REACTOR OPERATOR Page 59 of 107 QUESTION 053 Unit 3 was operating at near rated power when the following occurred:

An Instrument Air pipe ruptured in the Unit 3 Turbine Building.

An NSO reports that the 923-1 Panel IA HDR PRESS gauge is reading 80 psig and dropping at a rate of 5 psig/minute.

What action(s) is/are the Operating Team required to take per DOA 4700-01, INSTRUMENT AIR SYSTEM FAILURE?When IA HDR PRESS lowers to 55 psig, manually Scram the Unit 3 Reactor AND close the in-board (INBD) MSIVs.When IA HDR PRESS lowers to 55 psig, manually Scram the Unit 3 Reactor AND close the out-board (OTBD)

MSIVs.When IA HDR PRESS lowers to 65 psig, manually Scram the Unit 3 Reactor AND close the out-board (OTBD) MSIVs.Immediately close 3-4701-501, U3 SERV AIR TO INST AIR X-TIE MANUAL ISOL VLV to prevent back flow to the Service Air system.DOA 4700-01 K/A: 295019 2.1.2Memory New

REACTOR OPERATOR Page 60 of 107 QUESTION 054 With the Reactor shutdown and fuel loaded in the core, and all control rods normally inserted, per the UFSAR, interlocks are provided which prevent the inadvertent withdrawal of more than

___(1)___ control rod(s) with the mode switch in the ___(2)___ position.(1) one; (2) refuel(1) one; (2) startup(1) two; (2) refuel(1) two; (2) startupUFSAR.4.6.3.4.1K/A:

295023K302 Memory New

REACTOR OPERATOR Page 61 of 107 QUESTION 055 Unit 2 was operating at near rated power, with the 2A SBLC Pump is O.O.S., when a Scram occurred. RPV pressure is 955 psig and steady.

The Unit Supervisor directed SBLC to be injected for an ATWS.

The NSO placed the SBLC INJECTION CONTROL switch to position SYS 2 and 15 seconds later observed the following:

SBLC TANK LVL at 84%.

2B PP DISCH HDR PRESS of 400 psig.

Based on these conditions, the 2B SBLC.....

a.

pump is injecting.

b.

relief valve failed open.

c.

squib valve did NOT fire.

d.

pump accumulator needs charging.

ANSWER

b.

REFERENCE M-33 LP DRE211LN001 K/A: 211000A104 High Bank

REACTOR OPERATOR Page 62 of 107 QUESTION 056 Which of the following symbols is a drawing of a Globe Valve?

a.

Figure A

b.

Figure B

c.

Figure C

d.

Figure D ANSWER

b.

REFERENCE Mechanical Drawing M-11 sht 2 K/A: 2.1.24 Memory New

REACTOR OPERATOR Page 63 of 107 QUESTION 057 Unit 2 was operating at near rated power, when a transient occurred. At time 05:25, the following indications are observed:

Drywell temperature is 150°F and trending up at a rate of 1.0°F/minute.

Drywell pressure is 1.2 psig and trending up at a rate of 0.1 psig/minute.

RPV water level is 20 inches and trending down at a rate of 1 inch/minute.

At time 05:31, which of the following procedures are required to be entered?

1) DAN 902-5 D-11 DRYWELL PRESS HI-HI
2) DEOP 100 RPV CONTROL
3) DEOP 200-1 PRIMARY CONTAINMENT CONTROL
4) DOA 0040-01 SLOW LEAK
a.

1 and 4 ONLY

b.

1, 2, and 4 ONLY

c.

1, 3, and 4 ONLY

d.

1, 2, 3, AND 4 ANSWER

a.

REFERENCE DEOP 100 DEOP 200-1 K/A: 295010 2.4.4 High New

REACTOR OPERATOR Page 64 of 107 QUESTION 058 Unit 2 was operating at near rated power when a scram signal was received. An ATWS occurred, with half the rods NOT fully inserting.

For the Control Rods at position 00, what color will they be displayed in on the Rod Worth Minimizer?CyanGreenYellowMagentaDOP 0400-02K/A: 295015A105

REACTOR OPERATOR Page 65 of 107 QUESTION 059 The Max Safe values for radiation, temperature, and water level in the Reactor Building per DEOP 300-1, SECONDARY CONTAINMENT CONTROL, are based on the maximum value(s).....at which no equipment will fail.expected to be seen during an accident.expected to be seen during normal operations.at which equipment needed for safe shutdown of the plant will not fail.EPG B-8K/A: 295033A202Memory Bank

REACTOR OPERATOR Page 66 of 107 QUESTION 060 Which one of the following choices completes the statement below regarding the conditions required to generate annunciator 902-3 F-8, LPCI SYS B TIMERS NOT HOME?

A LPCI initiation signal is present and.....125 VDC power available to Div 1 initiation logic ONLY.125 VDC power available to Div 2 initiation logic ONLY.125 VDC power available to Div 1 initiation logic AND 4KV power available to Bus 23-1.125 VDC power available to Div 2 initiation logic AND 4KV power available to Bus 24-1.DAN 903-3 E-8 DAN 903-3 H-15K/A: 203000K108Memory New

REACTOR OPERATOR Page 67 of 107 QUESTION 061 Unit 2 was operating at near rated power, when a LOCA occurred. The following conditions exist:

Torus temperature is 109°F and steady.

DW pressure is 10 psig and lowering slowly.

Off site power is available and grid voltage is stable.

Core Spray flow is fluctuating between 2000 gpm to 4000 gpm.

Core Spray discharge pressure is fluctuating between 150 psig and 325 psig.

What is the cause of the Core Spray indications?ECCS suction strainers are plugging.A loss of NPSH caused by Torus temperature.Voltage fluctuations from the Emergency Diesel Generators.Leak in the piping downstream of the PP DISCH VLV MO 2-1402-25A.NRC Bulletin 93-02K/A: 209001K501 High Bank

REACTOR OPERATOR Page 68 of 107 QUESTION 062 Unit 2 was operating at near rated power when the following occurred:

A fire at Bus 29 causes it to become de-energized due to overcurrent.

The ___(1)___ will become de-energized and may manually be re-energized from ___(2)___.

a.

(1) ESS Bus; (2) MCC 28-2

b.

(1) 'A' RPS Bus; (2) MCC 25-2

c.

(1) 'B' RPS Bus; (2) MCC 25-2

d.

(1) Instrument Bus (2) MCC 25-2 ANSWER

b.

REFERENCE DOP 0500-03 K/A: 212000K401 High New

REACTOR OPERATOR Page 69 of 107 QUESTION 063 Unit 3 was operating at near rated power when the following occurred:

Annunciator 903-4 H-17, VALVE LEAK DET SYS TEMP HI is received.

Annunciator 903-4 H-19, ACOUSTIC MONITOR ACTUATED is received.

Drywell pressure is 1.20 psig and steady.

Generator output has lowered by approximately 30 MWe and is steady.

What is/are the FIRST action(s) the NSO is/are required to take?Initiate Torus cooling.Scram the reactor per DGP 2-3.Place the appropriate relief valve control switch to the OFF position.Cycle the appropriate relief valve control switch between OFF then back to AUTO.DOA 0250-01 DAN 902-4 H-19K/A: 218000 2.1.23High Bank

REACTOR OPERATOR Page 70 of 107 QUESTION 064 Unit 2 was operating at near rated power when a transient occurred. At time 04:44 an NSO reports that Instrument Air Header pressure is 91 psig and dropping at a rate of 1 psig/minute.

At time 04:59, what automatic action(s) will have occurred?IA dryers 2A, and 2B bypasses opened.IA dryers 2A, and 2B bypasses opened then AUTOMATICALLY re-closed when header pressure was restored.AO 2-4701-500, U2 SERV AIR TO INST AIR AUTO X-TIE VLV, opened.AO 2-4701-500, U2 SERV AIR TO INST AIR AUTO X-TIE VLV, opened then AUTOMATICALLY re-closed when header pressure was restored.DOA 4700-01K/A: 300000K402

REACTOR OPERATOR Page 71 of 107 QUESTION 065 Regarding the Recirc MG Sets, with the Scoop Tube fully ___(1)___, ___(2)___ oil is present in the fluid coupler, resulting in ___(3)___ Recirc pump speed.(1) in; (2) less; (3) increasing(1) in; (2) more; (3) decreasing(1) out; (2) less; (3) decreasing(1) out; (2) more; (3) increasing ANSWER

d.

REFERENCE LP DRE 202LN001 K/A: 202002K501 High New

REACTOR OPERATOR Page 72 of 107 QUESTION 066 The Maximum Recycle Concentrators purify water by ___(1)___ and send that PURIFIED effluent to the ___(2)___.

a.

(1) distillation and/or an evaporation process; (2) Waste Transfer Tanks

b.

(1) distillation and/or an evaporation process; (2) Concentrator Condensers

c.

(1) filtration and/or a reverse osmosis process; (2) Waste Transfer Tanks

d.

(1) filtration and/or a reverse osmosis process; (2) Concentrator Condensers ANSWER

b.

REFERENCE LP DRE269LN001 K/A: 268000 2.1.28 Memory New

REACTOR OPERATOR Page 73 of 107 QUESTION 067 With the unit operating at near rated power, which of the following is a Technical Specification ENTRY CONDITION?Torus water level of 14 ft 8.5 inches.Drywell average air temperature of 145°F.Reactor Steam Dome pressure of 1010 psig.Reactor Coolant System unidentified leakage of 4 gpm.Tech Spec 3.4.10K/A: 295025 2.1.33 Memory New

REACTOR OPERATOR Page 74 of 107 QUESTION 068 Unit 2 was operating at near rated power when the following occurred:

An unsuccessful Reactor scram was initiated.

While executing the DEOPs, the Unit Supervisor directs injection of SBLC for an ATWS condition.

Given the drawing below, what action (if any) is the NSO required to take, to ensure injection of SBLC with an ATWS condition present?

a.

None, the SBLC system is injecting.

b.

Reposition the SBLC INJECTION CONTROL keyswitch to the SYS 2 position.

c.

Reposition the SBLC INJECTION CONTROL keyswitch to the SYS 1 & 2 position.

d.

Reposition the SBLC INJECTION CONTROL keyswitch to the SYS 2 & 1 position.

ANSWER

b.

REFERENCE DOP 1100-02

REACTOR OPERATOR Page 75 of 107 K/A: 295037A104 High New

REACTOR OPERATOR Page 76 of 107 QUESTION 069 What is the bases for operating Turbine Building Ventilation when an Off-Site release rate is above the ALERT level of GSEP?To discharge radioactivity through an elevated, release point.To maintain building pressure greater than environmental pressure.To prevent a Reactor scram due to high temperatures in the X-area.To contain, dilute and hold up fission products that leak from primary containment after a DBA.DEOP bases section 9-4K/A:

295017K102 Memory Bank

REACTOR OPERATOR Page 77 of 107 QUESTION 070 Unit 2 was operating at near rated power when Bus 28 experienced an overcurrent condition.

Which of the following will be de-energized?APRM channels 1, 2, and 3APRM channels 4, 5, and 6IRM channels 11, 12, 13, 14IRM channels 15, 16, 17, 18DOP 0500-03K/A: 215005K202 High New

REACTOR OPERATOR Page 78 of 107 QUESTION 071 A Unit 2 Drywell entry is required to be made.

Which of the following statements are correct, with regards to dose concerns, for the personnel making the Drywell entry?Reactor is shutdown.Reactor power is 34% OR lower.If in operation, the HPCI system MUST be secured.If in operation, the RWCU system MUST be secured.DOP 1600-22K/A: 2.3.10Memory New

REACTOR OPERATOR Page 79 of 107 QUESTION 072 Unit 2 was operating at near rated power, with the 2B CRD pump is O.O.S., when the following occurred:

The 2A CRD pump breaker was inadvertently tripped by a worker in the area.

Several seconds later a transient occurred, which caused the ANNUN DC PWR FAILURE alarm windows to be the only annunciators illuminated on the 902-3 through 902-8 panels.

To restore remote starting capability of the 2A CRD Pump, an NLO should be directed to transfer ___(1)___ control power from ___(2)___ to ___(3)___.(1) Bus 23; (2) 2A-1 Dist Panel; (3) 2B-1 Dist Panel(1) Bus 23; (2) 2B-1 Dist Panel; (3) 2A-1 Dist Panel(1) Bus 23-1; (2) 2A-1 Dist Panel; (3) U2 Rx Bldg Dist Panel(1) Bus 23-1; (2) U2 Rx Bldg Dist Panel; (3) 2A-1 Dist PanelDOA 6900-02 DOP 0300-E1 DOP 6900-06 DOP 6900-07K/A: 262001K502 High Bank

REACTOR OPERATOR Page 80 of 107 QUESTION 073 With Unit 3 operating at rated conditions, which of the following signals will cause the Unit 3 FWLC system to transfer from 3-Element to 1-Element control, AND what action should the operator take?3A Feed Flow instrument fails to Bad Quality; manually control the FRVs3A Steam Flow instrument fails to Bad Quality; depress the 1-ELEM pushbutton"A" NR level instrument fails to Bad Quality;depress the 1-ELEM pushbutton"A" NR level instrument fails to Bad Quality; manually control the FRVsDOP 0600-06 DAN 902-5 G-8K/A: 259002A201 High Bank

REACTOR OPERATOR Page 81 of 107 QUESTION 074 Unit 2 was operating at near rated power, when the feed breaker to Bus 29 de-energized on overcurrent.

Which PCIS alarm(s) would occur due to this condition?GROUP 3 ONLYGROUP 1 AND GROUP 2 ONLYGROUP 2 AND GROUP 3 ONLYGROUP 1, GROUP 2 AND GROUP 3DAN 902-4 H-20 DAN 902-5 B-13K/A: 223002K120 High New

REACTOR OPERATOR Page 82 of 107 QUESTION 075 Unit 2 was operating at near rated power when the following occurred:

TR-86 Sudden Pressure Relay activated.

A reactor Scram occurred.

Which statement below is a consequence, 30 seconds after the above transients occurred?2A Recirc MG Set will be de-energized.2A RBCCW pump will be de-energized.2B RBCCW pump will be de-energized.The ESS Bus ABT will transfer to MCC 28-2.DOP 0201-E1 AC Dist DrawingK/A: 202001K202 High New

SENIOR REACTOR OPERATOR Page 83 of 107 QUESTION 076 Unit 2 was operating at near rated power when the following occurred:

Feedwater was isolated due to a leak.

RPV water level was -40 inches and dropping at a rate of 1 inch/minute.

RPV pressure is 880 psig and steady.

HPCI injection was ordered for RPV water level control.

An NSO reported that the HPCI Auxiliary Oil pump will NOT start.

As the Unit Supervisor, which one of the following describes the NEXT appropriate action(s) to mitigate the RPV water level condition?Direct initiation of the SBLC system.Anticipate RPV blowdown and direct opening ALL bypass valves.Wait until level reaches -164 inches and then blowdown the RPV.Immediately direct manual startup of the HPCI emergency oil pump (EOP).DEOP 100K/A: 206000A215High Bank REQUIRED

REFERENCES:

DEOP charts, with the entry conditions blanked out.

SENIOR REACTOR OPERATOR Page 84 of 107 QUESTION 077 Unit 2 was operating at near rated power, with 2A LPCI pump taken O.O.S. at 0100 on March 1, 2008, and the following conditions exist:

2A Core Spray pump is running per DOS 1400-05, CORE SPRAY SYSTEM PUMP OPERABILITY AND QUARTERLY IST TEST WITH TORUS AVAILABLE.

System Discharge pressure is 235 psig.

System flow is 4400 gpm with MO 2-1402-4A, FLOW TEST VLV full open.

What is the impact to the Core Spray system and what actions are required?

a.

2A Core Spray subsystem is INOP; 7 day LCO to restore EITHER LPCI OR Core Spray subsystem to operability

b.

2A Core Spray subsystem is INOP; immediately enter LCO 3.0.3 for shutdown

c.

2A Core Spray subsystem is OPERABLE; restore LPCI subsystem to operability by 0100 on March 8, 2008

d.

2A Core Spray subsystem is OPERABLE; restore 2A LPCI pump to operability by 0100 on March 31, 2008 ANSWER

b.

REFERENCE T.S. 3.5.1 DOS 1400-05 K/A: 209001A206 High Bank REQUIRED

REFERENCES:

Tech Spec 3.5.1 with less than one hour times blanked out.

SENIOR REACTOR OPERATOR Page 85 of 107 QUESTION 078 Unit 2 is in Refuel and spent fuel movements within the Reactor Pressure Vessel are in progress.

Which of the following describes the MINIMUM RPV water level that would meet the requirements to perform this evolution, per Tech Specs, AND the bases for this?19 feet above top of irradiated fuel assemblies; to limit Iodine release during a fuel handling accident.19 feet above top of irradiated fuel assemblies; to limit Iodine release during a loss of fuel pool cooling.23 feet above top of RPV flange; to limit Iodine release during a fuel handling accident.23 feet above top of RPV flange; to limit Iodine release during a loss of fuel pool cooling.T.S. and Bases 3.9.6 DOA 1900-01K/A: 2.1.33 Memory Bank

SENIOR REACTOR OPERATOR Page 86 of 107 QUESTION 079 Unit 2 was in startup at ~10% power, when the following occurred:

A transient has occurred inside the Drywell.

Drywell pressure is 4.5 psig and rising at a rate of 2 psig/minute.

DEOP 200-1, PRIMARY CONTAINMENT CONTROL, was entered and no actions have been directed.

Three (3) minutes later, the Unit 2 Drywell Coolers are ___(1)___ AND the SRO will be procedurally required to direct the crew to initiate ___(2)___ sprays FIRST.

a.

(1) tripped (2) Torus

b.

(1) tripped (2) Drywell

c.

(1) NOT tripped (2) Torus

d.

(1) NOT tripped (2) Drywell ANSWER

a.

REFERENCE DAN 923-5 E-1 DEOP 200-01 K/A: 223001A207 High Bank

SENIOR REACTOR OPERATOR Page 87 of 107 QUESTION 080 Unit 3 was operating at near rated power when a scram occurred. The following conditions exist:

Drywell pressure is 2.3 psig.

RPV pressure is 500 psig.

RPV water level is -160 inches.

ALL injection sources become unavailable and are not expected to be restored for 15 minutes.

What action(s) is/are the SRO required to take?

DEOP 100, RPV CONTROL DEOP 400-2, EMERGENCY DEPRESSURIZATION DEOP 400-3, STEAM COOLING DEOP 500-3, ALTERNATE WATER INJECTION SYSTEMS

a.

Enter DEOP 400-2

b.

Exit ALL DEOPs and enter the SAMGs

c.

Exit DEOP 100 AND enter DEOP 400-3

d.

Exit DEOP 100 AND DEOP 500-3 then enter DEOP 400-3 ANSWER

c.

REFERENCE DEOP 100 K/A: 2.4.6 High Bank REQUIRED

REFERENCES:

DEOP Charts, with the entry conditions blanked out.

SENIOR REACTOR OPERATOR Page 88 of 107 QUESTION 081 Unit 3 was operating at near rated power when the following indications are observed:

Indicated core flow increased.

Core thermal power decreased.

Main Generator power decreased.

Core plate differential pressure decreased.

What has occurred and what action is the Unit Supervisor required to direct?jet pump failure; lockup scoop tubejet pump failure; secure affected recirc pumprecirc pump run up; lockup scoop tuberecirc pump run up; isolate affected recirc pumpDOA 0201-01K/A: 295001 2.4.49High Bank

SENIOR REACTOR OPERATOR Page 89 of 107 QUESTION 082 Which one of the following would qualify as a "Temporary Configuration Change" to be controlled by CC-AA-112, "Temporary Configuration Changes"?A plug installed in a floor drain.A portable air monitor permanently installed in the RWCU Demin room.An electrical lead is lifted in accordance with a surveillance procedure.A Service Air hose is being used for maintenance on a Condensate pump.CC-AA-112K/A:

2.2.11Memory New

SENIOR REACTOR OPERATOR Page 90 of 107 QUESTION 083 Unit 2 was operating at near rated power, when the NSO reported the following:

2A off gas system flow on the 902-7 panel has risen from 135 to 170 cfm and remains steady.

A short time later the following alarms were received:

902-54 C-7, OFF GAS FLOW HI/LO.

902-7 D-13, OFF GAS FILTER DP HI.

Then the Aux NSO reported the following:

Panel 902-54 INLET FLOW TO 2/3 CHIMNEY OFF GAS AFTER FILTER meter indication has risen from 20 to 55 cfm and is now steady.

Recombiner temperature remains relatively unchanged.

There has been an ___(1)___ AND the Unit Supervisor is required to direct entering ___(2)___.

a.

(1) Off Gas explosion in the holdup volume (2) DOA 0010-10 FIRE/EXPLOSION

b.

(1) increase in condenser air in-leakage (2) DOA 3300-02 LOSS OF CONDENSER VACUUM

c.

(1) Off Gas system fire in the 2A air ejector after condenser (2) DOP 5400-14 EXTINGUISHING AN OFF GAS FIRE

d.

(1) increase in Hydrogen Addition system oxygen injection flow (2) DOP 3390-01 HYDROGEN ADDITION SYSTEM OPERATION ANSWER

b.

REFERENCE DOA 3300-02 DAN 902-7 D-13 DAN 902-54 C-7 K/A: 295002A204 High Bank

SENIOR REACTOR OPERATOR Page 91 of 107 QUESTION 084 Unit 2 is in STARTUP, with IRMs on range 1, with control rods being withdrawn. SRM 22 failed upscale and SRM 24 failed downscale.

Which of the following describes the required action?Restore SRM Channel 22 OR 24 to operable status within 4 hrs.Restore inoperable channel(s) to OPERABLE status within 7 days.Suspend control rod withdrawals until SRM 22 OR 24 has been restored to operable status.Restore the Upscale Rod Block function of SRM Channel 22 OR 24 to operable status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.ITS 3.3.1.2K/A: 215004 2.1.12 High BankREQUIRED

REFERENCES:

I.T.S. 3.3.1.2 with less than one hour times blanked out.

SENIOR REACTOR OPERATOR Page 92 of 107 QUESTION 085 Unit 2 was operating at near rated conditions with the 902-36 back-panel recorder TIRS 2-1640-200A, TORUS TEMP MON DIV I Out Of Service (O.O.S.) due to a failed power supply. The following conditions exist:

RPV pressure is 1000 psig.

HPCI testing per DOS 2300-03 "HIGH PRESSURE COOLANT INJECTION SYSTEM OPERABILITY AND QUARTERLY IST VERIFICATION TEST" is in progress.

TIRS 2-1640-200B currently indicates the following:

Point 1 165°F Point 2 90°F Point 3 110°F Point 4 150°F Point 5 140°F Point 6 160°F Point 7 125°F Point 8 130°F What action(s) is/are required based on the current readings?

a.

Start all available Torus cooling ONLY.

b.

Start all available Torus cooling and scram ONLY.

c.

Secure HPCI testing and start all available Torus cooling ONLY.

d.

Secure HPCI testing, start all available Torus cooling, AND scram.

ANSWER

d.

REFERENCE DEOP 200-1 K/A: 295013A201 High Bank REQUIRED

REFERENCES:

DEOP charts, with the entry conditions blanked out.

SENIOR REACTOR OPERATOR Page 93 of 107 QUESTION 086 Given the following set of conditions on Unit 2:

Primary containment is open.

RPV Water level is 90 inches.

RPV Water temperature is 190°F.

The MODE switch is in SHUTDOWN.

Reactor Vessel head bolts are tensioned.

An event occurred that caused RPV Water temperature to rise to and stabilize at 220°F.

Which of the following describes the current plant MODE and which procedure is required to be entered?

a.

Mode 3, enter DEOP 300-1, Secondary Containment Control

b.

Mode 4, enter DEOP 300-1, Secondary Containment Control

c.

Mode 3, enter DOA 1000-01, Residual Heat Removal Alternatives

d.

Mode 4, enter DOA 1000-01, Residual Heat Removal Alternatives ANSWER

c.

REFERENCE DOA 1000-01 Tech Spec Bases 1.1 K/A: 2.1.22 High Bank

SENIOR REACTOR OPERATOR Page 94 of 107 QUESTION 087 Unit 2 is in SHUTDOWN with the following conditions:

2A and 2B Recirc Pumps are in operation at minimum speed.

2A and 2B Shutdown Cooling (SDC) loops are controlling cool down rate.

RPV water temperature is currently 305°F.

Then annunciator 902-4 H-8, 2B RECIRC LOOP WATER TEMP HI is received.

The NSO reports that the 2B Recirc Loop temperature indicates full upscale on the Recirc Loop Temperature recorder.

SDC flow will ___(1)___ and the Unit Supervisor directs ___(2)___.

a.

(1) be lost ;

(2) securing Both recirc pumps

b.

(1) be lost; (2) increasing RWCU flow to maximize heat removal rate

c.

(1) still be established; (2) securing Both recirc pumps

d.

(1) still be established; (2) increasing RWCU flow to maximize heat removal rate ANSWER

b.

REFERENCE DAN 902-4 H-8 DOA 1000-01 K/A: 295021A202 High New

SENIOR REACTOR OPERATOR Page 95 of 107 QUESTION 088 Given the following set of conditions:

Torus water level is 16.5 feet and steady.

Torus water temperature is 180°F and steady.

Which of the following is the HIGHEST RPV pressure that will not exceed a limit? a.

225 psig

b.

325 psig

c.

425 psig

d.

525 psig ANSWER

b.

REFERENCE DEOP 200-1 curve M K/A: 295026A203 High New REQUIRED

REFERENCES:

DEOP charts, with the entry conditions blanked out.

SENIOR REACTOR OPERATOR Page 96 of 107 QUESTION 089 Which of the following provide the bases for DEOP actions to maintain Torus water level above

-4.5 inches, in Modes 1, 2, and 3?

Ensures a sufficient amount of water.....with the Minimum CST Volume, Long-Term Cooling is available for the Design Basis Accident.would be available to adequately condense the steam from the relief valve quenchers ONLY.with the Minimum CST Volume, in the event of a LOCA to permit recirculation cooling flow to the core.would be available to adequately condense the steam from the relief valve quenchers, downcomer lines, OR HPCI turbine exhaust line.Bases 3.6.2.2K/A:

295030 2.2.25Memory Bank

SENIOR REACTOR OPERATOR Page 97 of 107 QUESTION 090 Unit 2 has just completed DOS 1100-04 STANDBY LIQUID CONTROL SYSTEM QUARTERLY/COMPREHENSIVE PUMP TEST FOR THE INSERVICE TESTING (IST)

PROGRAM.

As the Unit Supervisor reviewing the results, you discover that the 'A' pump results are in the ALERT range.

Which of the following, if any, is the required action per the above DOS?Required action range is NOT exceeded and no further action required.Notify the In-Service Testing (IST) coordinator.Initiate an Issue Report (IR) to check the calibration of the appropriate gauges/inspect the pump.Declare ONE subsystem inoperable and ensure the requirements of Tech Spec 3.1.7, STANDBY LIQUID CONTROL SYSTEM, are met.DOS 1100-04K/A: 211000 2.2.12Memory New

SENIOR REACTOR OPERATOR Page 98 of 107 QUESTION 091 Unit 2 was operating at near rated conditions, when an ATWS occurred, with the following conditions:

Reactor power is 15%.

RPV water level is 20 inches and slowly decreasing.

Torus temperature is 90°F and steady.

What is the next RPV water level action required AND which containment isolations will initiate as a result?

a.

Terminate and Prevent RPV injection until water level drops to -40 inches; group 2 AND 3 isolations ONLY

b.

Terminate and Prevent RPV injection until water level drops to -40 inches; group 1, 2, AND 3 isolations ONLY

c.

Hold RPV water level between -164 and 48 inches; group 2 AND 3 isolations ONLY

d.

Hold RPV water level between -164 and 48 inches; group 1, 2, AND 3 isolations ONLY ANSWER

a.

REFERENCE DEOP 400-5 DOA 600-1 DAN 902-5 E-5 DAN 902-5 D-4 DAN 902-5 D-5 OP-DR-103-102-1002 K/A: 295037A207 High Bank REQUIRED

REFERENCES:

DEOP Charts with the entry conditions blanked out.

SENIOR REACTOR OPERATOR Page 99 of 107 QUESTION 092 Unit 2 was operating at near rated power, with the following conditions:

The Unit 2A 125 Vdc Battery Charger is supplying the Unit 2 125 Vdc system.

The Unit 2/3 250 Vdc Battery Charger is supplying the Unit 2 250 Vdc system.

Then a fire caused Bus 28 to de-energize.

What effect will this have AND what actions can be taken to mitigate the transient?

a.

The Unit 2 125 Vdc batteries ONLY will begin to discharge; place the Unit 2 125 Vdc Battery Charger in service.

b.

The Unit 2 250 Vdc batteries ONLY will begin to discharge; place the Unit 2 250 Vdc Battery Charger in service.

c.

The Unit 2 125 AND 250 Vdc batteries will begin to discharge; place the Unit 2 125 AND Unit 2 250 Vdc Battery Chargers in service.

d.

The Unit 2 125 AND 250 Vdc batteries will begin to discharge; place the Unit 2 125 Alternate Battery AND Unit 2 250 Vdc Battery Charger in service.

ANSWER

a.

REFERENCE DOA 6900-04 DOA 6900-T1 K/A: 295004A204 High New

SENIOR REACTOR OPERATOR Page 100 of 107 QUESTION 093 Both units were operating at near rated power, when the following occurred:

A fire started in the 2/3 Cribhouse.

No Visible Damage to structures or Safety System equipment is reported.

The Fire Brigade has been fighting the fire for 16 minutes.

Shift Supervision is required to.....declare an Unusual Event for a plant fire; activate the TSCdeclare an Unusual Event for a plant fire; ensure a fire location announcement is made over the plant PA systemdeclare an Alert for a plant fire; activate the TSCdeclare an Alert for a plant fire; ensure a fire location announcement is made over the plant PA systemEP-AA-1004 DOA 0010-10K/A: 600000 2.4.25 High New REQUIRED

REFERENCES:

EP charts.

SENIOR REACTOR OPERATOR Page 101 of 107 QUESTION 094 Both units are operating at near rated power with the following conditions:

Fuel handlers are inspecting new fuel on the Refuel Floor.

The 2/3A SBGT train is in day 2 of a seven day OOS for planned maintenance.

The 2/3B SBGT train is in PRI position.

What required action is initiated IF the planned maintenance on the 2/3A SBGT train lasted past the planned 7 day duration? a.

Place the 2/3B SBGT train in operation.

b.

Restore the 2/3A SBGT train to OPERABLE status.

c.

Immediately suspend movement of new fuel assemblies.

d.

Place both units in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

ANSWER

d.

REFERENCE Tech Spec Section 3.6.4.3 K/A: 2.2.23 High Bank REQUIRED

REFERENCES:

TS 3.6.4.3 pages 1, 2, & 3, with less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> times removed.

SENIOR REACTOR OPERATOR Page 102 of 107 QUESTION 095 Unit 2 and 3 are operating at near rated power with DOS 6600-01, DIESEL GENERATOR SURVEILLANCE TEST in progress on the Unit 2 EDG, when MCC 29-2 experiences an overcurrent condition.

What is a consequence of the overcurrent on MCC 29-2, AND what actions are required to be taken?The U2 EDG Cooling Water pump will be de-energized; reduce load on the EDGThe U2 EDG Cooling Water pump will be de-energized; declare the U2 EDG inoperableThe U2 EDG Air Start Compressor 'A' will be de-energized; verify pressure in Air Receiver 'A' is > 120 psigThe U2 EDG Air Start Compressor 'B' will be de-energized; verify pressure in Air Receiver 'B' is > 120 psigDAN 902-7 G-8 T.S. 3.8.1K/A: 264000A209

SENIOR REACTOR OPERATOR Page 103 of 107 QUESTION 096 A transient has occurred that requires venting Primary Containment.

Primary Containment water level is 45 feet and steady.

Venting is secured to minimize radiation release when Torus Bottom pressure is below _______

psig.20406065DEOP 500-04K/A: 2.3.11High New

SENIOR REACTOR OPERATOR Page 104 of 107 QUESTION 097 Unit 2 was operating at near rated conditions when the annunciator 902-7 B-15, SCREEN WASH CONTROL PANEL TROUBLE was received. An NLO reported the following:

A large buildup of fish on the inlet side of the traveling screens.

There is a 14 inch level difference across the traveling screens.

15 minutes later the following occurred:

An NSO reported Main Condenser vacuum trending down at a rate of 0.5 inches Hg per minute.

An NLO reported the level difference is getting worse as more fish are accumulating on the traveling screens.

Which of the following action(s) is/are required to be performed, AND what is the bases for these action(s)?

a.

Depress the manual scram pushbuttons; Maintain Condenser vacuum and maintain Service Water system available

b.

Depress the manual scram pushbuttons; Protect the Condenser from over pressure and maintain heat sink available

c.

Insert Cram rods, dial down the master Recirc flow controller and leave only one Circulating Water pump running; Maintain Condenser vacuum and maintain Service Water system available

d.

Insert Cram rods, dial down the master Recirc flow controller and leave only one Circulating Water pump running; Protect the Condenser from over pressure and maintain heat sink available ANSWER

b.

REFERENCE DOA 4400-06 TS Bases 3.3.1.1 K/A: 2.4.49 High Bank REQUIRED

REFERENCES:

SENIOR REACTOR OPERATOR Page 105 of 107 QUESTION 098 Given the following Unit 2 parameters:

Steam Dome Pressure is 750 psig.

Core flow is 8% with only ONE Recirc pump operating.

The Reactor Core Safety Limit is ___(1)___ which ___(2)___.

a.

(1) MCPR > 1.12; (2) ensures that fuel cladding integrity is maintained

b.

(1) MCPR > 1.12; (2) protects the Reactor Coolant System against overpressurization

c.

(1) Thermal Power < 25%;

(2) ensures that fuel cladding integrity is maintained

d.

(1) Thermal Power < 25%;

(2) protects the Reactor Coolant System against overpressurization ANSWER

c.

REFERENCE I.T.S. Safety Limits 2.0 and bases K/A: 202001 2.2.22 Memory New

SENIOR REACTOR OPERATOR Page 106 of 107 QUESTION 099 Unit 3 was operating at near rated power, when a HPCI steam line ruptured. Attempts to isolate the leak have been unsuccessful.

The following parameters are reported:

Clean Up Pump & Ht X Area is 175°F.

HPCI pump room temperature is 200°F Clean Up Demin Room temperature is 187°F HPCI Cubicle radiation level is 2750 mr/hr.

West LPCI Pump radiation level is 2600 mr/hr.

West CRD module radiation level is 1750 mr/hr.

Which of the following choices lists ALL the DEOP procedures that the Unit Supervisor is currently required to enter?

DEOP 100, RPV CONTROL DEOP 200-1, PRIMARY CONTAINMENT CONTROL DEOP 300-1, SECONDARY CONTAINMENT CONTROL DEOP 400-2, EMERGENCY DEPRESSURIZATION

a.

DEOP 300-1 ONLY

b.

DEOP 100 AND DEOP 300-1

c.

DEOP 100, DEOP 300-1, AND DEOP 400-2

d.

DEOP 100, DEOP 200-1, DEOP 300-1, AND DEOP 400-2 ANSWER

c.

REFERENCE DEOP 300-1 K/A: 295033 2.3.10 High New REQUIRED

REFERENCES:

DEOP charts, with the entry conditions blanked out.

SENIOR REACTOR OPERATOR Page 107 of 107 QUESTION 100 Unit 3 was operating at near rated power, with the B EHC pressure regulator out of service, when the A EHC pressure regulator setpoint failed high.

The following parameters are reported:

IRMs are reading 50 on range 6 and decreasing.

RPV pressure is 1065 psig and trending up at 1 psig/minute.

RPV water level dropped to -12 inches and trending up at 1 inch/minute.

The Unit Supervisor is required to enter the DEOPs based on ___(1)___ and direct ___(2)___.

a.

(1) RPV pressure ONLY; (2) controlling RPV pressure between 800 to 1060 psig.

b.

(1) RPV pressure AND water level; (2) controlling RPV pressure between 800 to 1060 psig and RPV water level between 8 and 48 inches.

c.

(1) RPV pressure AND failure to scram; (2) controlling RPV pressure between 800 to 1060 psig and RPV water level between -164 and 48 inches.

d.

(1) failure to scram ONLY; (2) controlling RPV pressure between 800 to 1060 psig and RPV water level between -164 and 48 inches.

ANSWER

b.

REFERENCE DEOP 100 K/A: 241000 2.1.7 High New

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