ML091030038

CGS-2009-03 - Final Written Exam

ML091030038
Person / Time
Site:	Columbia
Issue date:	03/31/2009
From:	Operations Branch IV
To:	Energy Northwest
References
50-397/09-301
Download: ML091030038 (112)

Text

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 1 EXAM KEY MARCH 2009 Columbia is starting up with the Main Turbine synchronized to the grid with SM-1, SM-2, and SM-3 being powered from the Normal Transformers. The Reactor Operator is preparing to transfer SH-5 and SH-6 to the Normal Transformer when the Startup Transformer loses power.

Which of the following is correct?

A. An immediate Reactor Scram is required; place the MODE switch in SHUTDOWN.

B. ABN-LEVEL is entered due to the unplanned decrease in Reactor water level.

C. ABN-POWER is entered and Reactor power is lowered to LE 3486 MWT.

D. With no operator action, the Reactor will scram on low RPV water level.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295001 AA1.02 Ability to operate and/or monitor the following as they apply to partial or complete loss of forced core flow circulation: RPS (3.3 / 3.3)

REFERENCE:

ABN-RRC-LOSS; ABN-POWER; ABN-LEVEL SOURCE: New LO: 11781 Predict the impacts that a partial or complete loss of the Reactor Recirculation System will have on the following: Reactor Scram; 6733 State the immediate actions associated with ABN-RRC-LOSS.

RATING: H3 ATTACHMENT: None JUSTIFICATION: With the loss startup power to SH-5 and SH-6, all RRC flow is lost (RRC-P-1A powered from SH-5 and RRC-P-1B powered from SH-6). Immediate action for ABN-RRC-LOSS is to initiate a Reactor Scram. A is correct. B is incorrect as RPV level will rise. C is incorrect as power is already LE 3486 MWT. D is incorrect as feed flow is not affected. This distracter would be correct if SM-1, SM-2 and SM-3 were still powered from the Startup Transformer.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 2 EXAM KEY MARCH 2009 If the breaker for the normal AC source to E-IN-1 is opened, which of the following would then be supplying power to US-PP?

A. MC-7A B. MC-7F C. DP-S1-2 D. DP-S2-1 ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295003 AK2.06 Knowledge of the interrelationships between Partial or Complete Loss of AC Power and the following: DC electrical loads (3.4 / 3.5)

REFERENCE:

SD000194 UPS Systems Text Pg 4 and figure 3 SOURCE: New LO: 11826 Identify the effect that a loss or malfunction of the AC Electrical Distribution system will have on the following: DC electrical distribution RATING: L3 ATTACHMENT: None JUSTIFICATION: When normal AC power is lost (MC-7A), the static switch automatically swaps to the DC input which is from battery DP-S2-1. MC-7A is the normal AC input and also the bypass source. MC-7F is the bypass AC source. DP-S1-1 is a Div 1 125VDC battery and supplies IN-2/3 not IN-1.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 3 EXAM KEY MARCH 2009 The plant was operating at 99% power when a LOCA signal was received. While verifying auto actions, the CRO notes neither LPCS-P-1 nor RHR-P-2A started. Additionally, the CRO notes that neither system has valve position indication on P601.

The CRO attempts to start both pumps but neither pump starts with the control switch on P601.

Which of the following is the correct explanation for these conditions?

A loss of.

A. both B1-1 and C1-1 after the LOCA signal.

B. both B1-1 and C1-1 prior to the LOCA signal.

C. both B1-2 and C1-2 after the LOCA signal.

D. both B1-2 and C1-2 before the LOCA signal.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295004 AA2.02 Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of DC power: Extent of partial or complete loss of DC Power (3.5 / 3.9)

REFERENCE:

ABN-ELEC-125VDC Page 12 SOURCE: Bank LO00266 LO: 5262 Given a list of loads that are important to plant safety or vital to plant operation, identify its relationship to 125 VDC Bus. 11842 Describe the effect of a partial or complete loss of DC power on the following: (C) DC bus loads RATING: L3 ATTACHMENT: None JUSTIFICATION: Losing DC after the LOCA signal (and thus after the pumps have started) would not turn the pumps off. LPCS and RHR are Div. 1 systems. B1-1 and C1-1 are Div. 1.

B1-2 and C1-2 are Div 2 and would not affect Div. 1 systems if lost. B is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 4 EXAM KEY MARCH 2009 On day 335 of the current run, with Columbia operating at full power, a Main Turbine trip occurs.

Which of the following describes the basis for the response of the Reactor Recirculation pumps to this event?

The Reactor Recirculation Pumps trip to minimize the effect of the A. increase in reactor power and the increase of reactor water level.

B. decrease in reactor pressure and the increase of reactor water level.

C. increase in reactor power and the increase of reactor pressure.

D. decrease in reactor power and the increase of reactor pressure.

ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295005 AK3.02 Knowledge of the reason for the following responses as they apply to Main Turbine Generator Trip: Recirculation pump downshift/trip (3.4 / 3.5)

REFERENCE:

SD000178 Pg 23 SOURCE: New LO: 11647 Explain the reasons for the following responses as they apply to Main Turbine trip: b. Recirculation pump trip RATING: H2 ATTACHMENT: None JUSTIFICATION: The RRC pump trip on a MT trip (EOC-RPT) is designed to mitigate effects of the increase in reactor power and the increase in reactor pressure - C is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 5 EXAM KEY MARCH 2009 A series of events has occurred resulting in the Control Room Supervisor entering the EOPs.

Which of the following combinations would not require a transition to PPM 5.1.2, RPV Control ATWS, by ensuring that there is sufficient shutdown margin to assure the reactor is shutdown under all conditions?

1. one control rod at position 48

2. one control rod at position 08

3. two control rods at position 04

4. two control rods at position 02

5. all other Control Rods at position 04

6. all other Control Rods at position 02

7. all other Control Rods at position 00 A. 1 and 2 and 7 B. 2 and 3 and 6 C. 2 and 4 and 7 D. 1 and 4 and 5 ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295006 AK1.02 Knowledge of the operational implications of the following as they apply to SCRAM: Shutdown Margin (3.4 / 3.7)

REFERENCE:

OI-15 Page 19 SOURCE: New LO: 7784 Given a list, identify the criteria that must be met to ensure that the existing rod pattern alone can always assure reactor shutdown.

RATING: H2 ATTACHMENT: None JUSTIFICATION: Per OI 15 the reactor is shutdown with one rod at any position and all others at least inserted to position 02. C is the only choice that meets that criteria.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 6 EXAM KEY MARCH 2009 Following a series of events, OPS2 notes that WMA-FN-52B (Cable Spreading Room Recirc Fan) and WMA-FN-53B (Critical Switchgear Rooms Recirc Fan) are both running.

Which of the following explains why these fans are running?

A. Operation of the FRTS power transfer switch at the Remote Shutdown Panel.

B. Operation of the FRTS power transfer switch at the Alternate Remote Shutdown Panel.

C. The auto start of WMA-FN-54B.

D. RPV level dropping to LT -50 inches.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295016 AK2.03 Knowledge of the interrelationships between Control Room abandonment and the following: Control room HVAC (2.9 / 3.1)

REFERENCE:

SD000201 Page 13 SOURCE: New LO: 7736 State the effect when each of the FRTP Switches is placed in Emergency.

RATING: L4 ATTACHMENT: None JUSTIFICATION: Placing the FRTS to emergency at the RSD starts both the 52B and 53B fans. The only fan that gets a start signal from ARSD is the 53A fan. A is correct. ARSD Panel starts WMA-FN-53A (B is incorrect). WMA-FN-54B starts WMA-FN-51B (C is incorrect). WMA-FN-54B gets a start signal from FAZ (D is incorrect).

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 7 EXAM KEY MARCH 2009 CAS-C-1B was operating when a loss of TSW occurred. CAS-C-1B tripped due to high discharge air temperature. The control room directed fire water be aligned to the compressor. The control switch for CAS-C-1B, on P840, is still in the "RUN" position.

Which of the following describes the restart of CAS-C-1B?

A. CAS-C-1B will automatically restart on low control air system pressure regardless of the status of the low cooling water pressure condition.

B. CAS-C-1B will automatically restart as soon as the low cooling water pressure condition clears.

C. After the low cooling water pressure condition clears, CAS-C-1B will restart when the reset pushbutton at the local control cabinet is depressed.

D. After the low cooling water pressure condition clears, CAS-C-1B will restart when the control switch on P840 is placed in "OFF" then back to "RUN".

ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295018 AA2.05 Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of Component Cooling Water: system pressure (2.9 / 2.9)

REFERENCE:

SD000205 Page 13; ARP 4.840.A5 1-5 SOURCE: Bank modified LR00418 LO: 5873 Describe the actions necessary to reset a Control Air Compressor trip when the trip condition has cleared.

RATING: L3 ATTACHMENT: None JUSTIFICATION: To restart a tripped CAS compressor the condition must clear and the reset P/B locally needs to be depressed. C is correct

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 8 EXAM KEY MARCH 2009 During operation at full power, CRO2 responds to a ADS N2 HDR A ISOLATED alarm and refers to Alarm Response Procedure 4.840.A5 8-3. A ADS Header pressure is checked and found to be 155 psig and is trending down slowly.

Which of the following describes the system response to the lowering header pressure and then to header pressure being returned to normal?

A. CIA-V-39A would close; CIA-V-39A would have to be manually opened.

B. CIA-V-39A would close; CIA-V-39A would automatically open.

C. Three minutes after receiving the alarm, CIA-V-39A would close; CIA-V-39A would have to be manually opened.

D. Three minutes after receiving the alarm, CIA-V-39A would close; CIA-V-39A would automatically open.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295019 2.4.11 Partial or complete loss of Inst. Air. Knowledge of Annunciator response procedures (4.0 / 4.2)

REFERENCE:

ARP 4.840.A5 8-3; SD000156 Page 7 SOURCE: New LO: 11755 Describe the function, purpose and design features of the following Containment Instrument Air System components: Solenoid actuated air operated valves: CIA-V-39A and CIA-V-39B RATING: L3 ATTACHMENT: None JUSTIFICATION: The alarm annunciates when pressure has been LT 160 psig for 3 minutes.

Automatic actions include CIA-V-39A going closed. When pressure is returned to normal, CIA-V-39A automatically opens. B is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 9 EXAM KEY MARCH 2009 Columbia has shutdown for a refueling outage after a long run at full power. Refueling activities are underway. A full core offload is approximately half way completed. One RHR loop is providing Shutdown Cooling and the other RHR loop is providing Fuel Pool Cooling Assist. Temperatures in the Reactor Vessel and the Spent Fuel Pool are currently stable.

If RHR-P-2A trips, which of the following is correct?

A. Temperatures remain fairly constant in both the Reactor Vessel and the Spent Fuel Pool.

B. Temperatures in both the Reactor Vessel and the Spent Fuel Pool uniformly increase.

C. Reactor Vessel temperature remains fairly constant while Spent Fuel Pool temperature increases.

D. Reactor Vessel temperature increases while Spent Fuel Pool temperature remains fairly constant.

ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295021 2.1.41 Loss of Shutdown Cooling. Knowledge of the refueling process (2.8 / 3.7)

REFERENCE:

SD000198 Page 6 SOURCE: Bank modified LO: 5774 Describe the flow-path within the appropriate RHR System for each of the following: b. Shutdown Cooling; g. FPC Assist (refuel)

RATING: H3 ATTACHMENT: None JUSTIFICATION: Only B RHR provides Fuel Pool Cooling Assist. A RHR loop is in Shutdown Cooling. A loss of SDC results in rising temperature in the Reactor Vessel.

Temperature in the Spent Fuel Pool remains constant as B RHR is still operating. D is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 10 EXAM KEY MARCH 2009 During refueling, a subcritical check is performed to demonstrate adequate margin to criticality exists thus preventing a possible refueling accident due to inadvertent criticality.

Which of the following describes the relationship between the RPS shorting links and performing a subcritical check?

A. Installing the shorting links prevents an SRM from generating a rod withdraw block to RMCS which then allows a control rod to be withdrawn to perform the subcritical checks.

B. Removing the shorting links allows any SRM to generate a upscale trip reactor scram signal and makes IRM and APRM scram trips non-coincident.

C. Installing the shorting links allows any SRM to generate a upscale trip reactor scram signal if counts become GT 2 x 105 but does nothing to change the IRM or APRM trips.

D. Removing the shorting links allows any SRM to generate a upscale trip reactor scram signal if counts become GT 2 x 105 but does nothing to change the IRM or APRM trips.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295023 AK3.04 Knowledge of the reason for the following responses as they apply to Refueling Accidents: Non-coincident Scram function (3.0 / 3.5)

REFERENCE:

PPM 6.3.3; SD000132 page 26 SOURCE: New LO: 5843 List the scrams and rod blocks generated by the SRM system; 7677 Describe the effect(s) on RPS when the shorting links are removed.

RATING: H2 ATTACHMENT: None JUSTIFICATION: Removal of the shorting links activates the SRM scram trip capability and also makes the IRM and APRM scram trips non-coincident, B is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 11 EXAM KEY MARCH 2009 With Columbia operating at power, a small leak inside containment occurs causing drywell pressure to rise.

A manual scram is inserted prior to the high drywell pressure scram signal. Shortly after the manual scram the automatic high drywell scram signal comes in. All components function as designed.

Which of the following is correct concerning the Standby Gas Treatment systems response to this condition?

A. SGT-FN-1A1 immediately starts based on the high drywell signal.

B. SGT-FN-1B1 immediately starts based on the high drywell signal.

C. SGT-EHC-1A1 energizes based on the high drywell signal and SGT-FN-1A1 starts 10 seconds later.

D. SGT-EHC-1B1 energizes based on the high drywell signal and SGT-FN-1B1 starts 10 seconds later.

ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295024 EA1.20 Ability to operate and/or monitor the following as they apply to High Drywell Pressure: Standby Gas Treatment/FRVS Plant Specific (3.5 / 3.6)

REFERENCE:

SD000144 Page 8 and 10 SOURCE: New LO: 5828 State the SGT system response to a FAZ signal. Include all major valves, heaters, and fans and their associated delay times.

RATING: L2 ATTACHMENT: None JUSTIFICATION: High Drywell Signal energizes the heaters for the lead fans SGT-FN-1A1/1B2. 10 seconds after the heaters energize the fans start. SGT-FN-1A1 and 1B2 are lead fans. SGT-FN-1B1 would only start if SGT-FN-1B2 did not. C is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 12 EXAM KEY MARCH 2009 With Columbia operating in MODE 1 a reactor scram occurs. All rods go full in. After conditions stabilize, CRO1 places the SDV High Level Bypass switch to the bypass position and resets the scram by depressing both scram reset P/Bs on P603. CRO1 notes the following:

• all RPS A/B Logic white indicating lights illuminate

• all Backup scram amber indicating lights de-energize

• the scram discharge volume vent and drain valves do not open Based on the information given, which of the following signals caused the reactor scram?

A. A Drywell pressure rise to 2 psig B. A Reactor power rise to 110 percent C. A Reactor pressure rise to 1130 psig D. A Reactor level drop to -35 inches ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295025 EA1.07 Ability to operate and/or monitor the following as they apply to High Reactor Pressure: ARI/RPT/ATWS: Plant Specific (4.1 / 4.1)

REFERENCE:

SD000161 page 5; SD000142 page 21 and 22 SOURCE: New LO: 5188 - Describe the sequence of events that occur to the SDV vent and drain valves during a scram, scram reset, and valve testing; 5189 State the signals and explain the logic that causes the ATWS-ARI valves to open RATING: H3 ATTACHMENT: None JUSTIFICATION: All choices are scram signals. Only the Reactor pressure of 1130 psig (which is GT 1120 psig signal) operate the ATWS/ARI valves. Depressing only the scram reset P/Bs does not reset ATWS/ARI and without ATWS/ARI the SDV V & D valves will not open. The ATWS/ARI RESET P/B has to be depressed. C is correct

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 13 EXAM KEY MARCH 2009 PPM 5.2.1, "Primary Containment Control" provides direction to enter PPM 5.1.1, RPV Control before Wetwell temperature reaches 110°F.

Which of the following correctly describes the basis for this direction?

A. Directs entry to ensure RPV level and pressure are monitored to determine the cause of the wetwell temperature increase.

B. Assures that adequate core cooling is provided prior to placing the second loop of RHR in suppression pool cooling mode.

C. Assures that the reactor is scrammed and shutdown by control rod insertion before the requirement for boron injection is reached.

D. Directs a Reactor scram to terminate heat addition to the wetwell before the wetwell design temperature is exceeded.

ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295026 EK3.05 Knowledge of the reason for the following responses as they apply to Suppression Pool High Water Temperature: Reactor Scram (3.9 / 4.1)

REFERENCE:

PPM 5.0.10 page 255 SOURCE: Bank - slightly modified - LR00971 LO: 8300 Given a list, identify the statement that describes the reason for entering PPM 5.1.1, "RPV Control", before wetwell temperature reaches 110°F.

RATING: H2 ATTACHMENT: None JUSTIFICATION: Per 5.0.10 a scram is required prior to boron injection. C is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 14 EXAM KEY MARCH 2009 A small steam line rupture has caused drywell temperature to rise to 200°F.

Assuming the actual water level in the RPV were to remain constant, which of the following describes the effect on indicated RPV water level?

Indicated RPV water level would indicate..

A. higher as heating of the reference leg increases the delta-P.

B. lower as heating of the reference leg increases the delta-P.

C. lower as heating of the reference leg decreases the delta-P.

D. higher as heating of the reference leg decreases the delta-P.

ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295028 EK1.01 Knowledge of the operational implications of the following concepts as they apply to High Drywell Temperature: Reactor water level measurement (3.5 / 3.7)

REFERENCE:

5.0.10 Page 62 SOURCE: New LO: 8488 Given a list of RPV water level instrument responses, identify the response that could occur if the RPV saturation temperature curve is exceeded.

RATING: H2 ATTACHMENT: None JUSTIFICATION: As drywell temperature increases, the density of water in the reference leg decreases which would decrease the delta-P between the reference and variable legs given that the variable leg remains the same (actual RPV level). This would cause indicated water level to rise. D is correct

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 15 EXAM KEY MARCH 2009 Due to lowering Suppression Pool water level, PPM 5.2.1, Primary Containment Control, was entered . If Suppression Pool water level can not be maintained GT 192, an Emergency Depressurization is required to be performed.

What is the bases for this direction?

A. Adequate suppression of steam discharged from the RPV cannot be assured below this level.

B. The code allowable stresses on the SRV Tailpipes will not be exceeded during the blowdown.

C. Scrubbing of the steam discharged from the SRVs cannot be assured below this level.

D. Vortexes at the suction of the ECCS pumps begin at this level and can result in air binding of the pumps.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295030 EK3.01 Knowledge of the reason for the following responses as they apply to Low Suppression Pool Water Level: Emergency Depressurization (3.8 / 4.1)

REFERENCE:

PPM 5.0.10 page 262 SOURCE: Bank (LO01703 slightly modified)

LO: 5387 Given a list, identify the statement that describes the reason for emergency depressurizing the RPV if wetwell level and reactor pressure cannot be restored and maintained below the SRVTPLL.

RATING: L3 ATTACHMENT: None JUSTIFICATION: PPM 5.0.10 states that maintaining SP water level GT 192 ensures water level GT downcomer vent openings. If this level was not maintained, steam may not be adequately condensed.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 16 EXAM KEY MARCH 2009 A small-break LOCA has occurred. No high pressure injection sources are available. All low pressure ECCS pumps are running with normal discharge pressures. At 1200 the following plant conditions exist:

Drywell pressure: 3.0 psig and trending up slowly RPV level: -25 inches RPV level is going down at 5 inches per minute Assuming no operator action is taken, at what time will the ADS valves open?

A. 1205 B. 1207 C. 1220 D. 1222 ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295031 EK2.08 Knowledge of the interrelationships between Reactor Low Water Level and the following: Automatic Depressurization System (4.2 / 4.3)

REFERENCE:

SD000186 Page 5 SOURCE: INPO Exam bank #29223 Modified LO: 5071 State the condition that will automatically initiate ADS. Include setpoints and time delays.

RATING: L2 ATTACHMENT: None JUSTIFICATION: ADS initiates 105 seconds after RPV level drops to -129. At the rate of 5/minute it will take 20 minutes to get level to -128. If you add the 105 seconds time delay and the other inch level needs to drop, that is approximately an additional 2 minutes.

1200 + 20 minutes + 2 minutes = 1222 making D correct. C is the time if the time delay is not taken into account. A & B are times using -50 inches vice -129.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 17 EXAM KEY MARCH 2009 A series of events have occurred which has placed Columbia in an ATWS condition. Due to a failure of both SLC pumps to start, the CRS has directed performance of PPM 5.5.8, Alternate Boron Injection. PPM 5.5.8 directs RCIC-V-19 (Minimum Flow Bypass) be closed and breaker MC-S21A/5C opened.

Which of the following describes the reason for the above actions?

A. Prevents draining the Condensate Storage Tanks to the Suppression Pool.

B. Prevent SLC from being pumped to the Condensate Storage Tanks.

C. Allows RCIC to be operated at speeds lower than 2100 rpm without damage to the pump.

D. Prevent SLC from being pumped to the Suppression Pool.

ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295037 EA1.10 Ability to operate and/or monitor the following as they apply to Scram Condition Present and Reactor Power Above APRM Downscale or Unknown: Alternate boron injection methods: Plant Specific (3.7 / 3.9)

REFERENCE:

PPM 5.5.8 SOURCE: Bank Modified LO: 5929 Describe the flowpath used to inject boron solution into the RPV using the RCIC System.

RATING: H2 ATTACHMENT: None JUSTIFICATION: The min flow for the RCIC system goes to the Suppression Pool. Closing the Minimum Flow Valve prevents RCIC from pumping boron into the SP. D is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 18 EXAM KEY MARCH 2009 Columbia is operating at full power. A small fuel pin leak is causing an increase in reactor coolant activity and an off site release.

Which of the following monitors could terminate the release by automatic actuation of plant equipment?

A. Main Steam Line radiation monitors, MS-RIS-610A/B/C/D.

B. Offgas Post-Treatment radiation monitors, OG-RIS-601A/B.

C. Reactor Building Exhaust Plenum radiation monitors, REA-RIS-609A/B/C/D.

D. Reactor Building Stack High Range radiation monitor, PRM-RE-1C.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295038 EK2.02 Knowledge of the interrelationships between High Off-Site Release Rate and the following: Offgas System (3.6 / 3.8)

REFERENCE:

SD000147 Page 15, 18, 19, 20, 34, 35 SOURCE: New LO: 5647 State the automatic actions associated with each of the following gaseous and liquid stream Process Radiation Monitors upon sensing high radiation levels:

a. Offgas Post-Treatment RMS f. Main Steam Line RMS g. Reactor Building Exhaust Plenum RMS RATING: H4 ATTACHMENT: None JUSTIFICATION: MSL PRMs cause an alarm and NS4 actuations. MSIVs do not close (A is incorrect); RB Exhaust Plenum PRMs cause alarm and Z isolations but do nothing to terminate release (C is incorrect); RB Stack PRM cause alarm only (D is incorrect). Only Offgas PRM causes OG-V-60 to close which would isolates/terminates the release.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 19 EXAM KEY MARCH 2009 Which of the following identifies two systems that are not fire protected, and as such, may not be reliable during a fire.

A. RHR-A and RCIC B. RHR-B and RHR-C C. RCIC and HPCS D. HPCS and RHR-B ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 600000 AA2.04 Ability to determine and interpret the following as they apply to Plant Fire On Site: The fires extent of potential operational damage to plant equipment (2.8 / 3.1)

REFERENCE:

ABN-FIRE Page 27 SOURCE: New LO:

RATING: H4 ATTACHMENT: None JUSTIFICATION: Per ABN-Fire Bases, RCIC and HPCS are not fire protected and may not be reliable during a fire. C is correct

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 20 EXAM KEY MARCH 2009 Which of the following identifies the effect of accomplishing injection of Cold Shutdown Boron Weight during an ATWS?

The reactor is shutdown..

A. and will remain shutdown under all conditions.

B. but may return to power if a cooldown is initiated.

C. but may return to power as Xenon depletes during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. with RPV level at its current value but may return to power if RPV level is raised.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295037 EK1.05 Knowledge of the operational implications of the following concepts as they apply to Scram Condition Present And Reactor Power Above APRM Downscale or Unknown; Cold Shutdown Boron Weight (3.4 / 3.6)

REFERENCE:

PPM 5.0.10 SOURCE: Bank (LR00872 slightly modified)

LO: 8180 Define Cold Shutdown Boron Weight RATING: L3 ATTACHMENT: None JUSTIFICATION: CSBW is determined assuming no Xenon, water at most reactive temperature; no voids. A is correct

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 21 EXAM KEY MARCH 2009 Which of the following is the setpoint for the low vacuum trip of the Reactor Feedwater Pumps?

A. 0 in. Hg VAC only when reactor power is LT 30%.

B. 0 in. Hg VAC regardless of reactor power level.

C. 7 in. Hg VAC only when reactor power is LT 30%.

D. 7 in. Hg VAC regardless of reactor power level.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295002 AK2.05 Knowledge of the interrelations between Loss of Main Condenser Vacuum and the following: Feedwater system (2.7 / 2.7)

REFERENCE:

SD000151 page 27 SOURCE: New LO: 5767 Identify the automatic and manual Reactor Feedwater Turbine trips (11 automatic 3 manual)

RATING: L2 ATTACHMENT: None JUSTIFICATION: Per reference the RFW pump trips at 0 in Hg VAC regardless of power level (B is correct and A, C, D are incorrect). The MT low vacuum scram is bypassed at LT 30% power and the BPV closure is at 7 in. Hg VAC.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 22 EXAM KEY MARCH 2009 The plant is operating in MODE 1, when a plant transient occurs. Below are some of the observations made by the Control Room staff:

SGT systems started All MSIVs remained open No Diesel Generators started Control Room Emergency Filtration system started Based on the above plant status, which of the following occurred?

A. Reactor Building Exhaust Plenum radiation level increasing to 14 Mr/hr.

B. Reactor Building Pressure increased to +2 inches H2O.

C. Reactor Water Level dropped to a level of -55 inches.

D. Drywell Pressure increasing to 1.8 psig.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295034 EK2.06 Knowledge of the interrelations between Secondary Containment Ventilation High Radiation and the following: PCIS/NSSS (3.9 / 4.3)

REFERENCE:

ABN-FAZ-QC page 3 & 4 SOURCE: Bank modified - LO00268 LO: 6914 Given plant conditions identify those annunciators and indications that would indicate a F, A or Z Signal Actuation and subsequent entry into ABN-FAZ RATING: H3 ATTACHMENT: None JUSTIFICATION: If RPV level would have dropped to -55, the MSIVs would have closed. If DW/P increased to 1.8 psig, the Diesel Generators would have started. RB/P increase would not have started SGT. High Radiation in Secondary Containment Ventilation starts SGT and Filtration units. A is correct

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 23 EXAM KEY MARCH 2009 With Columbia operating at full power, an Operating Basis Earthquake occurs. The earthquake causes a large LOCA and the plant scrams due to high drywell pressure. Additionally, a number of downcomers shear off above the water level in the suppression pool.

Based on the above, which of the following is correct?

A. Wetwell pressure could now cause the SRV Tail Pipe Level Limit to be exceeded and code allowable stresses on the tail pipe, supports, quenchers, and quencher supports will be exceeded.

B. Wetwell pressure could now cause the Heat Capacity Temperature Limit to be exceeded, causing containment pressure to exceed the Primary Containment Pressure Limit during a reactor emergency depressurization.

C. The high Drywell pressure could now cause operation in the restricted region of the Drywell Spray Initiation Limit, causing a drywell-wetwell interface failure if drywell sprays are initiated.

D. The high Drywell pressure could now cause Wetwell pressure to exceed the Pressure Suppression Pressure and the Primary Containment Pressure Limit due to the pressure suppression function being bypassed.

ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295010 AK1.01 Knowledge of the operational implications of the following concepts as they apply to High Drywell Pressure: Downcomer submergence (3.0 /

3.4)

REFERENCE:

PPM 5.0.10 page 72, 87, 88 and 91 SOURCE: Bank Modified - LO00162 LO: 8339 Given a list, recognize the primary containment functions that the Pressure Suppression Curve is designed to protect.

RATING: H3 ATTACHMENT: None JUSTIFICATION: A is incorrect because SRVTLL is a function of RPV/P not WW/P. B is incorrect as HCTL is a function of WW/T and RPV/P not WW/P. C is incorrect as DSIL is more restrictive at lower DW pressures not higher DW pressures. D is correct per 5.0.10.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 24 EXAM KEY MARCH 2009 Due to a series of events, combustible limits have been reached in the primary containment. EOP 5.2.1, Primary Containment Control, requires an Emergency Depressurization if combustible limits are reached.

Which of the following is the reason for performing an Emergency Depressurization?

An Emergency Depressurization.

A. stops the production of H2 in the reactor.

B. reduces the amount of energy in the containment.

C. places the reactor in the lowest possible energy state.

D. stops the production of O2 in the reactor.

ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 500000 EK3.04 Knowledge of the reasons for the following responses as they apply to High Primary Containment Hydrogen Concentrations: Emergency Depressurization (3.1 / 3.9)

REFERENCE:

PPM 5.0.10 page 293 SOURCE: Bank (LO01226 slightly modified)

LO: 8443 Given a list, identify the statement that describes the reason for emergency depressurizing the RPV if deflagration conditions exist inside primary containment.

RATING: L3 ATTACHMENT: None JUSTIFICATION: PPM 5.0.10 states the reason for the Emergency Depressurization (ED) under these conditions is to place the reactor in the lowest possible energy state. C is correct. A and D are both incorrect because the ED will not stop the production of H2 and O2.

B is incorrect because the ED does not change the amount of energy in the containment but it transfers the energy from one area to another.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 25 EXAM KEY MARCH 2009 Columbia experienced a loss of feed incident and a manual reactor scram was initiated. Due to lowering RPV level RCIC was started. RCIC is maintaining RPV level +13 to + 54.

A High Suppression Pool water level annunciator alarms. Suppression pool level is observed to be +4 inches and going up slow. If Suppression Pool water level continues to rise, which of the following is correct?

When Suppression Pool level reaches +5 inches.

A. no change in the RCIC system valve lineup will occur.

B. the RCIC test bypass valve (RCIC-V-22 ) will receive a close signal.

C. the minimum flow will swap from the Suppression Pool to the CSTs.

D. the RCIC suction lineup will swap from the CSTs to the Suppression Pool.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295029 EA1.04 Ability to operate and/or monitor the following as they apply to High Suppression Pool Water Level: RCIC: Plant Specific (3.4 / 3.5)

REFERENCE:

SD00010 page15, 16, 17 SOURCE: New LO: 5719 Describe the system response for any routine system lineup when the RCIC System initiation logic is satisfied.

RATING: L2 ATTACHMENT: None JUSTIFICATION: There is no response from the RCIC system due to high Suppression Pool water level (just from the HPCS system). A is correct

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 26 EXAM KEY MARCH 2009 During operation at full power, High Pressure Feedwater Heaters 5A and 6A trip due to high water level.

Which of the following is an immediate action performed due to the loss of the feedwater heaters?

A. Insert control rods using the fast shutdown sequence to obtain a rod line LE 105%.

B. Reduce thermal power to LE 3486 MWT.

C. Reduce reactor power with core flow to LE 80 Mlbm/hr.

D. Reduce Main Turbine output to LT 1173 MWe.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 295014 AA1.07 Ability to operate and or monitor the following as they apply to Inadvertent Reactivity Addition: Cold Water Injection (4.0 / 4.1)

REFERENCE:

ABN-POWER page 3 and 9; ABN-FWH-HI LEVEL/TRIP page 2 and 4 SOURCE: New LO: 6747 State the immediate actions (and bases) associated with entry into ABN-POWER RATING: H2 ATTACHMENT: None JUSTIFICATION: Loss of the heaters would cause a feedwater inlet temperature reduction of GT 6°F and would require entry into ABN-POWER and also ABN-FWH-HI LEVEL/TRIP.

Reducing MWT to LT 3486 is a required immediate action of ABN-POWER - B is correct. Per ABN-POWERs subsequent actions, rod line is required to be maintained LT 100% - A is incorrect. Per ABN-POWERs subsequent actions, RRC flow reduction, if required, is to 92 Mlbm/hr - C is incorrect. ABN-FWH-HI LEVEL/TRIP requires turbine output be lowered to 1173 MWe as a subsequent action - D is incorrect.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 27 EXAM KEY MARCH 2009 At 75% reactor power a feed flow to steam flow mismatch develops. RPV level is observed to be slowly rising, steadies after about a 3 level rise, and then returns to its original value.

Which of the following could account for this mismatch and the RPV level perturbation?

A. A Safety Relief Valve opening B. A water level measurement fault that is sensing rising water level C. A steam flow measurement fault that is sensing lowering steam flow D. A feed flow measurement fault that is sensing lowering feed flow ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 205008 AA2.02 Ability to determine and/or interpret the following as they apply to High Reactor Water Level: Steam flow/Feed Flow Mismatch (3.4 / 3.4)

REFERENCE:

SD000157 page 18 and 19 SOURCE: New LO: 5400 Predict the expected response of the feedwater level control system in both Single and Three Element Control, to a failure or malfunction of the following: a.

Loss of a Steam Flow Transmitter b. Loss of Feedwater Flow Transmitter c. Loss of the selected RPV Level Channel d. SRV failing open RATING: H3 ATTACHMENT: None JUSTIFICATION: A is incorrect - sensed steam flow drops causing feedflow to back off causing a level decrease. B is incorrect - causes feedflow to back off and a level decrease. C is incorrect - lower steam flow measurement causes lower feed flow causes level to decrease. D is correct - lower feed flow causes more flow causes level rise.

PLC selects Single element before level changes by more than 3 inches.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 28 EXAM KEY MARCH 2009 Columbia is operating in MODE 1 with RHR-P-2A in Suppression Pool cooling. RHR-V-48A is being closed when a LOCA in containment occurs. The operator stops stroking RHR-V-48A and it is left in a partially opened position. Drywell pressure starts to rise and the CRS directs a reactor scram prior to a high drywell automatic scram. Eight minutes after the automatic scram signal, Drywell pressure is 5 psig.

Which of the following describes the response of the A RHR system to this event?

A. RHR-V- 24A (SP Cooling/Test return) closed. RHR-V-48A (HX bypass) closed. RHR-V-42A (LPCI injection) opened. If RHR-V-48A is opened, it will stay open when the switch is released.

B. RHR-V-24A (SP Cooling/Test return) closed. RHR-V-48A (HX bypass) opened. RHR-V-42A (LPCI injection) remained closed. If RHR-V-48A is closed, it will come back open when the switch is released.

C. RHR-V-24A (SP Cooling/Test return) remained open. RHR-V-48A (HX bypass) opened.

RHR-V-42A (LPCI injection) opened. If RHR-V-48A is closed, it will stay closed when the switch is released.

D. RHR-V-24A (SP Cooling/Test return) remained open. RHR-V-48A (HX bypass) closed.

RHR-V-42A (LPCI injection) remained closed. If RHR-V-48A is opened, it will go closed when the switch is released.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 203000 A3.08 Ability to monitor automatic operation of the RHR/LPCI Injection Mode including System initiation sequence (4.1 / 4.1)

REFERENCE:

SD000198 Page 15, 17, and 19 SOURCE: New LO: 5779 Describe the expected system response, for any routine lineup, when the initiation logic for the LPCI mode of the RHR system is satisfied.

RATING: H3 ATTACHMENT: None JUSTIFICATION: On initiation RHR-V-24A closes, RHR-V-48A opens and will not stay closed for 10 minutes, RHR-V-42A remains closed until 470 psig RPV Pressure. B is correct

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 29 EXAM KEY MARCH 2009 During a plant outage, the Startup Transformer is tagged out of service with supported load centers de-energized. RHR-P-2A and RHR-P-2B are operating in Shutdown Cooling. RPV level is being maintained at

+65 inches.

A loss of which of the following would cause operators to have to monitor RPV metal temperatures every 30 minutes per OSP-RCS-C103 (RPV Hydrostatic In-service Inspection Temperature surveillance)?

A. SM-1 or SM-3 B. SM-1 and SM-3 C. SM-7 or SM-8 D. SM-7 and SM-8 ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 205000 K2.01 Knowledge of the electrical power supplies to the following: Pump Motors (3.1 / 3.1)

REFERENCE:

ABN-RHR-SDC-LOSS page 4 SOURCE: New LO: 6486 With the procedures available, determine the required Cold Shutdown operating configurations for RHR and RPV level.

RATING: H1 ATTACHMENT: Yes - ABN-RHR-SDC-LOSS pages 1, 2, 3 and 4 JUSTIFICATION: Per ABN-RHR-SDC-LOSS, step 4.7, if forced circulation is not being provided by at least one SDC loop with RPV level GT 60, monitoring metal temp. is required.

A loss of SM1 and/or SM-3 will not loose power to RHR pumps as TR-B is still powering SM-7/8. Loosing power to SM-7 or SM-8 would still give one loop in SDC. Loosing both SM-7 AND SM-8 meets the requirements to monitor temperatures. D is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 30 EXAM KEY MARCH 2009 Columbia has experienced a LOCA coincident with a Loss of Offsite Power. The following conditions exist:

RPV/L is -140 inches (for the past 2 minutes)

SM-8 is de-energized due to a lockout on the bus RHR-P-2A is running with a sheared shaft LPCS-P-1 is running normally ADS has NOT been inhibited If LPCS-P-1 trips and will not re-start, which of the following describes the plant response?

The ADS SRVs ......

A. that were open, closed when LPCS discharge pressure became less than 145 psig.

B. that are open, will remain open as long as RHR-P-2A is running.

C. that were open, immediately closed when the LPCS-P-1 breaker opened.

D. have not opened because discharge pressure from both RHR & LPCS pumps is not GT 125 psig.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 209001 K3.02 Knowledge of the effect that a loss or malfunction of the Low Pressure Core Spray System will have on the following: ADS logic (3.8 / 3.9)

REFERENCE:

SD000192 page 16; SD000186 page 7 SOURCE: Bank - Modified LO00170 LO: 8737 Given that ADS has been initiated, state what actions can be taken to shut the ADS valves from the control room.

RATING: H3 ATTACHMENT: None JUSTIFICATION: ADS initiates 105 seconds after -129 with discharge pressure from either pump making D incorrect. B is incorrect because pressure must be GT 125 psig. C is incorrect because the logic works off of pressure and not breaker position. A is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 31 EXAM KEY MARCH 2009 Columbia is in MODE 1 with all systems in their normal, full power lineup. Due to leaking SRVs the Suppression Pool level is rising slowly. The Suppression Pool High Water Level alarm, 4.601.A11 2-3 (SUPP POOL LEVEL HIGH/LOW), annunciates. CRO2 observes Suppression Pool water level to be +0.8 inches.

Which of the following describes the effect of the above, on HPCS-V-1 (Pump suction from CST) and HPCS-V-15 (Pump suction from Suppression Pool); and also describes the procedural guidance to mitigate the consequences of the high Suppression Pool water level?

A. HPCS-V-1 will close and then HPCS-V-15 will open. EOP 5.2.1 will be entered which directs Suppression Pool level be lowered per SOP-FPC-SPC.

B. HPCS-V-15 will close and then HPCS-V-1 will open. EOP 5.2.1 will be entered which directs Suppression Pool level be lowered per SOP-FPC-SPC.

C. HPCS-V-1 will remain open and HPCS-V-15 will remain closed. Suppression Pool level will be lowered per SOP-RHR-SPC.

D. HPCS-V-15 will remain open and HPCS-V-1 will remain closed. Suppression Pool level will be lowered per SOP-RHR-SPC.

ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 209002 A2.12 Ability to predict the impacts of the following on the High Pressure Core Spray System and based on those predictions, use procedures to correct, or mitigate the consequences of those abnormal conditions or operations: High Suppression Pool Water Level (3.3 / 3.5)

REFERENCE:

ARP 4.601.A1 6-6; PPM 5.2.1 Primary Containment Control step L1 SOURCE: New LO: 11721 Describe the physical connection and/or cause-and-effect relationship between the High Pressure Core Spray System and the following: Condensate transfer and storage system .5429 List the automatic initiations and interlocks associated with the following HPCS system components:

CST suction valve (HPCS-V-1) and Suppression Pool Suction valve (HPCS-V-15).

RATING: H2 ATTACHMENT: None JUSTIFICATION: This alarm annunciates at +.73 in the SP. The HPCS suction switchover occurs at

+5.25. EOP entry into PPM 5.2.1 is at +2. No valve actuation will occur at this SP level but SOP-RHR-SPC would be used to lower SP Level.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 32 EXAM KEY MARCH 2009 Towards the end of a refueling outage, you are sent to complete a valve lineup on the Standby Liquid Control system per SOP-SLC-FILL. During the performance of the valve lineup you note that the required position for some of the valves is C+. You check the procedure but it does not indicate the meaning of the C+.

Which of the following describes the meaning of the C+?

The valve is A. torqued closed to the torque value indicated in the comment section.

B. simultaneously checked closed by two operators.

C. Closed and a cap is then required to be installed.

D. located in containment.

ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 211000 2.1.29 SLC System - Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc. (4.1 / 4.0)

REFERENCE:

SOP-SLC-FILL page 13; Glossary page 57 SOURCE: New LO: 9851 Given a valve checklist, determine the required condition of the valve.

RATING: L2 ATTACHMENT: None JUSTIFICATION: Per the glossary a + indicates the valve is closed and capped - C is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 33 EXAM KEY MARCH 2009 Only the A1 trip channel logic for the Reactor Protection System (RPS) trips.

Which of the following is correct?

A. Power to all of the 185 A scram pilot valve solenoids is deenergized causing the scram valves (CRD-V-117s) to open.

B. No power is lost to the scram pilot valve solenoids until both the A1 and A2 channels trip. No scram valves (CRD-V-117 or CRD-V-118) open.

C. Power to only one half of the 185 A RPS scram pilot valve solenoids is deenergized causing the scram valves (CRD-V-117s) to open.

D. Power to only one quarter of the 185 scram pilot valve solenoids is deenergized causing the scram valves (CRD-V-117 and CRD-V-118) to open.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 212000 K5.02 Knowledge of the operational implications of the following concepts as they apply to Reactor Protection System: Specific logic arrangements (3.3 / 3.4)

REFERENCE:

SD000161 Page 4 SOURCE: New LO: 5955 Describe the RPS "one out of two taken twice" trip logic.

RATING: L3 ATTACHMENT: None JUSTIFICATION: Per the reference, a trip of only one of the two trip channels deenergizes the solenoids for all A side scram pilot valve solenoids causing the valves to open.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 34 EXAM KEY MARCH 2009 Columbia is in the process of starting up with reactor power approximately 2%. The following conditions exist:

IRM E indicates 75/125 on Range 8 IRM F indicates 39/40 on Range 7 IRM G indicates 45/125 on Range 8 If the CRO places the Range Switch for IRM G to Range 9, which of the following is correct?

A. There is a 1/2 scram on RPS B and a Rod Block from IRM F. A full Scram is generated when the Range Switch for IRM G is placed on range 9.

B. There is a 1/2 scram on RPS B and a Rod Block from IRM F. Another rod block is generated when the CRO places the Range Switch for IRM G on range 9.

C. There is a 1/2 scram on RPS A. A rod bock is generated when the CRO places the Range Switch for IRM G on range 9.

D. A 1/2 scram and a Rod Block on RPS A is generated from placing the Range Switch for IRM G on range 9.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 215003 A1.05 Ability to predict and/or monitor parameters associated with the Intermediate Range Monitoring System controls including: scram and rod block trip setpoints. (3.9 / 3.9)

REFERENCE:

SD000138 page 17 SOURCE: Bank Modified LO01238 LO: 5459 List the IRM scrams and rod blocks with setpoints and bypass conditions.

RATING: H2 ATTACHMENT: None JUSTIFICATION: An IRM F reading of 39/40 on Range 7 causes a rod block and a 1/2 scram on RPS B.

Ranging IRM G to range 9 causes an addition downscale rod block which is 5/125.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 35 EXAM KEY MARCH 2009 Which of the following is correct concerning the SRM generated control rod withdrawal block that occurs when an SRM detector is not fully inserted and the SRM count rate is LE 100 cps?

This control rod withdrawal block is A. only bypassed when all SRMs have been fully retracted.

B. bypassed when the MODE Switch is in any position other than STARTUP.

C. bypassed if all IRMs are on Range 3 or higher.

D. only bypassed if all IRMs are on Range 8 or higher.

ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 215004 K4.06 Knowledge of Source Range Monitor (SRM) System design feature(s) and/or interlocks which provide for the following: IRM/SRM interlock (3.2 / 3.2)

REFERENCE:

SD000132 page 25 and 26 SOURCE: New LO: 5943 List the scrams and rod blocks generated by the SRM system. Include the setpoint for each and when they are bypassed.

RATING: L3 ATTACHMENT: None JUSTIFICATION: A and D are incorrect because there are other ways to bypass this rod block. B is wrong as the MODE switch should be in RUN. C is correct

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 36 EXAM KEY MARCH 2009 With no equipment out of service, the control room receives an LPRM Downscale alarm on H13-P603. In response the CRO investigates at back panel H13-P608 and notices the downscale light illuminated for an LPRM associated with APRM B. The CRO takes the meter function switch for APRM B to the count position. The meter reads 110%.

Which of the following is correct concerning the indication?

A. APRM B has 23 LPRMs assigned to it. Either one of the assigned LPRMs is not being counted due the downscale indication or a function switch is not in the operate position.

B. There are 22 LPRMs assigned to APRM B. All assigned LPRMs have their function switches in operate. Failed LPRMs can not be determined by this switch position/indication.

C. There are 23 LPRMs assigned to APRM B. This reading indicates that one of the assigned LPRM either failed or the function switch is not in the operate position.

D. APRM B has 22 LPRMs assigned to it. Function switch position nor failed LPRMs can be determined by this switch position/indication.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 215005 K5.06 Knowledge of the operational implications of the following concepts as they apply to Average Power Range Monitor/Local Power Range Monitor System: Assignment of LPRMs to specific APRM Channels (2.5 / 2.6)

REFERENCE:

SD000143 page 9 & 14 SOURCE: New LO: 5095 Describe the physical connections and/or cause-effect relationships between APRM System and the following: LPRMs 7758 Predict the effect(s) that a failure of the following will have on the APRM System: LPRMs RATING: H3 ATTACHMENT: None JUSTIFICATION: Per reference APRM B has 22 LPRMS assigned to it - A and C are incorrect. D is incorrect because the reading is the number of switches in operate. B is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 37 EXAM KEY MARCH 2009 During implementation of PPM 5.1.2, RPV Control ATWS, the CRS is working his way down the level leg.

After he determines that reactor power is GT 5%, there is a block that says RCIC injection will result in Main Turbine trip. If the CRS wants to keep the Main Turbine on line, directions are given to the CRO to prevent the initiation of RCIC.

In response, the CRO should..

A. reference the Quick Card for RCIC and take the control switch for RCIC-V-13 to the close position until the valve closes.

B. reference the Quick Card for RCIC and take the control switch for RCIC-V-1 to the close position until the valve fully closes.

C. arm and depress RCIC while holding the control switch for RCIC-V-13 in the close position. No procedure reference is required per OI-09, Operations Standards and Expectation.

D. take the control switch for RCIC-V-1 to the closed position until the valve fully closes.

No procedure reference is required per OI-09, Operations Standards and Expectation.

ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 217000 A2.01 Ability to predict the impacts of the following on the Reactor Core Isolation Cooling System (RCIC); and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System initiation signal. (3.8 / 3.7)

REFERENCE:

PPM 5.1.2 level leg block L-5; OI-09 Operations Standards and Expectation SOURCE: New LO: 11678 Predict the impact of the following on the Reactor Core Isolation Cooling System: System initiation signal RATING: H2 ATTACHMENT: None JUSTIFICATION: There is no quick card for preventing a RCIC start while in PPM 5.1.2 thus A & B are incorrect. C is viable because this is how HPCS is inhibited when in an ATWS.

To prevent RCIC initiation, RCIC-V-1 is closed - D is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 38 EXAM KEY MARCH 2009 The Control Room has been evacuated and plant operation has been transferred to the Remote Shutdown Room. With all controls transferred to the Remote Shutdown Panel, which of the following is correct concerning operation of the ADS Safety Relief Valves?

Taking the control switches to OPEN will open the ADS SRVs A. if the ADS logic is made up by energizing the SRVs A solenoid.

B. regardless of the ADS logic status by energizing the SRVs A solenoids.

C. if the ADS logic is made up by energizing the SRVs B solenoid.

D. regardless of the ADS logic status by energizing the SRVs B solenoids.

ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 218000 K1.05 Knowledge of the physical connections and/or cause-effect relationships between Automatic Depressurizing System and the following: Remote Shutdown System (3.9 / 3.9)

REFERENCE:

SD000186 figure 4; SD000210 page 8 SOURCE: New LO: 11874 Describe the physical connection and/or cause-and-effect relationship between the Automatic Depressurization System and the following: e. Remote Shutdown System RATING: H2 ATTACHMENT: None JUSTIFICATION: With controls transferred to the RSD, the ADS logic is isolated and operation of the SRVs is via the control switch and the B solenoids - D is correct. A solenoids are utilized on ADS SRVs at the Alternate RSD panel.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 39 EXAM KEY MARCH 2009 Which of the following sets of parameters would cause an automatic isolation of EDR-V-394 and EDR-V-395, Reactor Building Sump Discharge to Radwaste (NS4 Group 3) and an automatic isolation of RHR-V-40 and RHR-V-49, RHR Discharge to Radwaste (NS4 Group 5)?

A. RPV Level of -25 inches B. Drywell Pressure of 2.4 psig C. Main Condenser Vacuum of 0 Hg D. RB Vent Exhaust Rad level of 15 mr/hr ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 223002 A3.02 Ability to monitor automatic operations of the Primary Containment Isolation System/Nuclear Steam Supply Shut-Off including: Valve Closures (3.5 / 3.5)

REFERENCE:

SD000173 Page 7, 8, 9 SOURCE: New LO: 5597 Given the number and name of any of the 7 NS4 isolation groups, list the isolation signals and setpoints (except room and ventilation temps.) for that group.

RATING: H3 ATTACHMENT: None JUSTIFICATION: EDR-V-394/395 (Group 3) isolate on -50, 1.68#, and 13 mr/hr. RHR-V-40/49 (Group 5) isolate on +13, 1.68#. B is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 40 EXAM KEY MARCH 2009 Which of the following describes the vacuum breakers associated with the Safety Relief Valves?

1. One for each SRV tailpipe

2. Two for each SRV tailpipe

3. Located in the Drywell

4. Located in the Wetwell

5. Prevents suction of water into the tailpipe which could cause increased pipe stress and containment loading

6. Prevents suction of water into the tailpipe which could cause acceleration and drag loads on submerged structures A. 2, 3, and 5 B. 1, 4, and 5 C. 1, 3, and 6 D. 2, 4, and 6 ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 239002 K6.05 Knowledge of the effect that a loss or malfunction of the following will have on Relief/Safety Valves: Discharge Line Vacuum Breaker (3.0 / 3.2)

REFERENCE:

SD000128 page 11, 12 and Figure 1 SOURCE: New LO: 11697 Predict the impact on the following with an SRV open: Tail pipe temperature; Reactor pressure; water level power; Turbine load; Suppression pool water temperature; Indicated vs. actual steam flow; Stuck open vacuum breaker; SRV stuck open RATING: H2 ATTACHMENT: None JUSTIFICATION: There are two vacuum breakers per tailpipe, located in the drywell and prevent suction of water to prevent increased pipe stress and containment loading.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 41 EXAM KEY MARCH 2009 With Columbia operating at 100% power, which of the following describes the effect of the reference leg sensing lines of two narrow range level transmitters failing simultaneously?

A. FWLC system shifts to the third narrow range input - no plant transient occurs.

B. FWLC system shifts to single element control - no plant transient occurs.

C. FWLC system shifts to the third narrow range input. The Main Turbine trips causing a Reactor scram.

D. FWLC system shifts to single element control. Both Reactor Recirculation Pumps run back to 30 Hz.

ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 259002 K3.06 Knowledge of the effect that a loss or malfunction of the Reactor Water Level Control System will have on the following: Main Turbine (2.8 / 2.8)

REFERENCE:

SD000157 Pages 6, 7 and 15 SOURCE: New LO: 11699 Predict the plant impact that a loss or malfunction of the Feedwater Level Control System will have on the following: g. Main Turbine RATING: H3 ATTACHMENT: None JUSTIFICATION: A is incorrect as FWLC would select the third NR input but the MT would still trip.

D is incorrect as RRC pump runback occurs as a result of scram to 15 Hz, not 30 Hz. B is incorrect as FWLC does shift to single element control as a result of scram and a MT Trip occurs. C is correct as the reference leg failures would cause dP to go to zero indicating high RPV water level which would cause a MT Trip.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 42 EXAM KEY MARCH 2009 A small leak in containment causes Drywell pressure to rise to 4 psig.

Which of the following describes the operation of SGT-V-1A, the Primary Containment Purge Exhaust Duct Isolation valve, and SGT-V-2A, the Reactor Building Intake Isolation valve?

On the high drywell pressure initiation signal, SGT-V-1A..

A. and SGT-V-2A received closed signals.

B. and SGT-V-2A received open signals.

C. received an open signal and SGT-V-2A received a closed signal.

D. received a closed signal and SGT-V-2A received an open signal.

ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 261000 A4.02 Ability to manually operate and/or monitor in the control room:

Suction Valves (3.1 / 3.1)

REFERENCE:

SD000144 page 6 SOURCE: New LO: 5828 State the SGT system response to a FAZ signal. Include all major valves, heaters, and fans and their associated delay times.

RATING: L3 ATTACHMENT: None JUSTIFICATION: Per reference, on an FAZ signal, SGT-V-1A gets a closed signal and SGT-V-2A gets a open signal. D is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 43 EXAM KEY MARCH 2009 Columbia is operating at power when a ground on electrical bus SM-7 occurs. Investigation reveals that the ground is associated with the breaker for CRD-P-1A.

Which of the following is correct concerning this ground?

CRD-P-1A..

A. could trip due to a ground fault. Refer to ABN-CRD for direction to start CRD-P-1B.

B. will not trip due to a ground fault. Refer to ABN-ELEC-GRID for ground fault isolation directions.

C. could trip due to a ground fault. Refer ABN-ELEC-SM1/SM7 for direction to reset ground fault.

D. will not trip due to a ground fault. Refer to ABN-CRD for direction to start CRD-P-1B and secure CRD-P-1A.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 262001 A2.05 Ability to predict the impacts of the following on the AC Electrical Distribution; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Bus Grounds (2.9 / 3.3)

REFERENCE:

SD000182 page 76; ABN-CRD SOURCE: New LO: 11831 Describe the effects of a ground fault within the AC distribution system.

RATING: H3 ATTACHMENT: None JUSTIFICATION: CRD-P-1A/1B are the only pumps that trip on a ground fault (A and D are incorrect). ABN-ELEC-SM1/SM7 does not give directions for resetting ground fault (C is incorrect). Entry into ABN-CRD is required due to the loss of CRD flow (A is correct).

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 44 EXAM KEY MARCH 2009 A loss of power to which of the following inverters would cause the inboard MSIVs to close?

A. E-IN-1 B. E-IN-2A/2B C. E-IN-3A/3B D. E-IN-5 ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 262002 K1.16 Knowledge of the physical connections and/or cause relationships between Uninterruptible Power Supply (A.C./D.C.) and the following: MSIVs (3.1 /

3.2)

REFERENCE:

SD000194 Page 33 SOURCE: New LO: 7783 Predict the effect a failure of IN-2(3) will have on: MSIVs RATING: L2 ATTACHMENT: None JUSTIFICATION: Per reference, a loss of IN-2 will cause inboard MSIVs to close - B is correct. The outboard MSIVs close on a loss of IN C is incorrect. IN-1 and IN-5 do not supply power to the MSIVs - A and C are incorrect.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 45 EXAM KEY MARCH 2009 Which of the following describes effect on the RCIC system in response to a loss of the 250 VDC electrical bus S2-1?

A. If running, the RCIC turbine will trip on mechanical overspeed, due to the loss of power to the speed sensor.

B. IF running, the RCIC system will continue to operate with normal system flow control still available.

C. The ability to start RCIC from the Control Room is lost and if RCIC is running, RCIC cannot be tripped using the trip pushbutton.

D. If running, RCIC will continue to operate at the current flow and speed. RCIC-FIC-600, RCIC flow indicating controller loses power and speed/flow cannot be adjusted.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 263000 K3.03 Knowledge of the effect that a loss or malfunction of the D.C.

Electrical Distribution will have on the following: Systems with DC components (i.e. valves, motors, solenoids, etc) (3.4 / 3.8)

REFERENCE:

SD000188 page 23 SOURCE: New LO: 7657 Predict the effect(s) a failure of 250VDC bus S2-1 will have on: RCIC system RATING: H3 ATTACHMENT: None JUSTIFICATION: Per reference RCIC will continue to run with normal flow control (B is correct) and (A is incorrect). Normal flow control will still be available (D is incorrect). The manual trip pushbutton is still available (C is incorrect).

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 46 EXAM KEY MARCH 2009 Which of the following describes the effect of going to RAISE on the VOLTAGE REGULATOR control switch for DG-1 in the following conditions?

1. DG-1 is running loaded but IS NOT connected to the grid

2. DG-1 is running loaded and IS connected to the grid A. 1. Voltage remain the same, MVARs increase

2. Voltage increase, MVARs remain the same B. 1. Voltage increase, MVARs increase

2. Voltage remains the same, MVARs increase C. 1. Voltage increase, MVARs remain the same

2. Voltage increase, MVARs increase D. 1. Voltage increase, MVARs remain the same

2. Voltage remains the same, MVARs increase ANSWER: D QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 264000 A4.01 Ability to manually operate and/or monitor in the Control Room:

Adjustment of exciter voltage (3.3 / 3.4)

REFERENCE:

SD000200 Page 22 SOURCE: New LO: 5319 State how DG Megawatts, Megavars, Hertz, Kiloamps and Kilovolts will change when the DG voltage regulator switch is taken to RAISE when: b. DG is loaded but not connected to the grid and c. DG is paralleled to the grid.

RATING: H2 ATTACHMENT: None JUSTIFICATION: Per reference going to raise increases voltage when loaded and not connected to grid and MVARs when loaded and connected to grid. MVARs. D is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 47 EXAM KEY MARCH 2009 With Columbia operating in MODE 1 with all systems operating in a normal lineup and no equipment out of service. The Control Room receives a Control Air Header Pressure Low annunciator.

If CAS pressure continues to drop, which of the following is the next expected response to the drop in air pressure?

A. The Service Air system isolates when SA-PCV-2 closes.

B. The standby CAS compressor(s) start(s).

C. The Control Air Dryer Bypass valve, CAS-PCV-1 opens.

D. The Service Air compressor auto starts.

ANSWER: A QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 300000 K4.02 Knowledge of the Instrument Air design features and/or interlocks which provide for the following: Cross-over to other air systems. (3.0 / 3.0)

REFERENCE:

SD000205 Pages 11, 12,13,14 SOURCE: New LO: 5878 List the expected automatic Control Air system response due to a leak in the Control Air System, for each of the following pressures: a. 100 psig b. 95 psig c. 80 psig d. 75 psig; 5871 Describe the features associated with each position of the Service Air/Control Air Header Crosstie valve SA-PCV-2 (CLOSE, AUTO, OPEN).

RATING: H2 ATTACHMENT: None JUSTIFICATION: The low CAS pressure alarm annunciates at 95 psig. The standby CAS compressor starts at 100 psig so they should have already started B is incorrect; SA-PCV-2 closes at 80 psig, A is correct; CAS-PCV-1 opens at 75 psig, C is incorrect; There are no automatic starts on the Service Air compressor, D is incorrect.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 48 EXAM KEY MARCH 2009 During operation at full power the Control Room receives a RCC HIGH RAD alarm.

Which of the following components should be investigated to determine the source of leakage into the RCC system?

A. Drywell Cooling heat exchangers B. EDR heat exchangers C. RWCU Non-regenerative heat exchangers D. Fuel Pool Cooling heat exchangers ANSWER: C QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 400000 K1.04 Knowledge of the physical connections and/or cause-effect relationships between CCWS and the following: Reactor Coolant System in order to determine source (s) of RCS leakage into CCWS. (2.9 / 3.1)

REFERENCE:

SD000196 Page 15 SOURCE: New LO: 7669 Identify the possible sources of leakage into RCC and how the sources may be identified.

RATING: L2 ATTACHMENT: None JUSTIFICATION: RWCU is the only system that operates at reactor pressure listed - C is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 49 EXAM KEY MARCH 2009 With Columbia operating at power, events occur that include the High Pressure Core Spray pump starting and HPCS-V-4 opening.

Given that the HPCS pump start is from a valid initiation signal, which of the following is correct?

Due to this valid start, entry into.

A. PPM 5.2.1, Primary Containment Control, will always be required.

B. PPM 5.1.1, RPV Control, will always be required.

C. SOP-HPCS-START, will always be required.

D. ABN-POWER will always be required.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 209002 2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions (4.5 / 4.6)

REFERENCE:

SD000174 Page 7; EOP 5.1.1 Entry conditions SOURCE: New LO: 5423 List the signals (including setpoints) which will cause an automatic initiation of the HPCS system; 8017 Given plant conditions, recognize an EOP entry condition(s) and enter the appropriate flow chart.

RATING: H3 ATTACHMENT: None JUSTIFICATION: HPCS initiates on -50: RPV/L and 1.68 psig DW/P. Both of these setpoints requires entry into PPM 5.1.1 (B is correct); PPM 5.2.1 is not entered on low RPV level (A is incorrect); ABN-Power is not entered on a scram but is entered in inadvertent HPCS initiation (D is incorrect); SOP-HPCS-START is superseded by EOP entry condition (C is incorrect).

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 50 EXAM KEY MARCH 2009 With Columbia operating at full power the following alarms and indications are observed at H13-P603:

APRM ACE UPSCL TRIP OR INOP H13-P603.A7 2-5 in alarm ROD OUT BLOCK H13-P603.A7 2-7 in alarm NEUTRON MONITOR SYSTEM TRIP H13-P603.A7 3-3 in alarm 1/2 SCRAM SYSTEM A H13-P603.A7 3-4 in alarm OPRM ENABLED RPS A H13-P603.A7 3-7 in alarm APRM UPSCALE H13-P603.A8 2-6 in alarm FLOW REFERENCE OFF NORMAL H13-P603.A8 3-6 in alarm APRM A, C, AND E: UPSC ALARM lights are illuminated APRM A, C, AND E: UPSC TR OR INOP lights are illuminated Flow Unit A: COMPAR light illuminated Flow Unit C: COMPAR light illuminated Which of the following failures produced the above indications?

A. Flow transmitter RRC-FT-24A, "B" Recirc Loop flow to Flow Unit A failed downscale.

B. Flow transmitter RRC-FT-14C, "A" Recirc Loop flow to Flow Unit C failed downscale.

C. Flow transmitter RRC-FT-24A, "B" Recirc Loop flow to Flow Unit A failed upscale.

D. Flow transmitter RRC-FT-14C, "A" Recirc Loop flow to Flow Unit C failed upscale.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 215005 K6.07 Knowledge of the effect that a loss of the following will have on APRM System: Flow converter/comparator network: Plant Specific (3.2 / 3.3)

REFERENCE:

Columbia Simulator SOURCE: Bank Modified LR00739 LO: 5087 Describe the physical connection and/or cause-and-effect relationship between the APRM Flow Units and: a. APRM Channels b. RBM Channels c. Flow Unit Comparators RATING: H3 ATTACHMENT: None JUSTIFICATION: Flow transmitter failing upscale does not give 1/2 scram (C & D are incorrect); B loop flow transmitter failure would give 1/2 scram on B RPS (A is incorrect).

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 51 EXAM KEY MARCH 2009 With A SGT out of service for maintenance, B SGT is in operation following a LOCA. While raising SGT flow, a HEPA B-1 OUTLET MOIST HIGH alarm is received.

Which of the following describes the possible result of continued SGT operation?

A. Operation of the SGT system with high moisture could reduce the life of the downstream HEPA filters.

B. There is a potential for decreased charcoal filter efficiency which could result in an increase in radioactive iodine being released offsite.

C. There is a potential that SGT B electric strip heaters are not energized. Proper operation of the electric strip heater SGT-ESH-1B should be locally verified.

D. Operation of the SGT system with high moisture could allow particulate matter to pass through the HEPA filter and become entrapped in the charcoal adsorbers resulting in reduced charcoal bed efficiency and increased offsite release rates.

ANSWER: B QUESTION TYPE: RO/SRO Closed Book KA # & KA VALUE: 261000 A1.03 Ability to predict and/or monitor changes in parameters associated with operation of the Standby Gas Treatment System controls including: Off-Site Release Levels (3.2 / 3.8)

REFERENCE:

Alarm Response Procedures 4.811.K2 1-2; 1-3, 3-6, 4-3 SOURCE: New LO: None (LO# 11960 Predict the impact of the following on the Standby Gas Treatment System: d. High train moisture content is being developed)

RATING: H3 ATTACHMENT: None JUSTIFICATION: Reduction of HEPA filter life could be a result of high dP in the prefilter (A is incorrect); Per ARP moisture could result in iodine release (B is correct); If strip heaters are not on a Low Temp alarm would annunciate (C is incorrect); A high HEPA dP could result in particulate matter passing thru filter (D is incorrect)

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 52 EXAM KEY MARCH 2009 RPS Trip System B can be powered from which of the following load centers?

A. Alternate power is fed from MC-6B and normal power is fed from MC-8A B. Alternate power is fed from MC-6A and normal power is fed from MC-8A C. Alternate power is fed from MC-6B and normal power is fed from MC-8B D. Alternate power is fed from MC-6A and normal power is fed from MC-8B ANSWER: A QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 212000 K2.02 Knowledge of the electrical power supplies to the following: Analog Trip System Logic Cabinets (2.7 / 2.9)

REFERENCE:

SD000161 Page 20 SOURCE: New LO: 5950 List the normal and alternate power supplies to the RPS System.

RATING: L3 ATTACHMENT: None JUSTIFICATION: Per reference alternate power is from MC-6B and normal power is from MC-8A

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 53 EXAM KEY MARCH 2009 Columbia is operating in MODE 1. Efforts are underway to transfer IN-1 from the Bypass AC Source that is feeding the Maintenance Bypass Switch to the Normal AC source that is fed from the UPS Inverter.

Concerning the transfer, which of the following is correct?

Power is being transferred from A. MC-7A. The Kirk Key interlocked breakers will be operated and it will be a make-before-break transfer.

B. MC-7F. The Kirk Key interlocked breakers will be operated and it will be a break-before-make transfer.

C. MC-7A. The transfer will be a make-before-break transfer.

D. MC-7F. The transfer will be a make-before-break transfer.

ANSWER: D QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 262002 A4.01 Ability to manually operate or monitor in the control room: Transfer from alternate source to preferred source (2.8 / 3.1)

REFERENCE:

SD000194 Page 3, 4 and 34 SOURCE: Bank modified LO01194 LO: 5896 List the power supplies to each inverter: a. IN-1; 5890 State the function of the IN-1 Kirk Key Interlock.

RATING: H2 ATTACHMENT: None JUSTIFICATION: The Bypass AC power supply to IN1 is from MC-7F not MC-7A (A and C are incorrect). Maintenance Bypass Switch for IN-1 is powered from MC-7F, not MC-7A (A and C are incorrect). The Kirk Key interlocked breakers are operated when transferring IN-1 from its Bypass Source, which is MC-7A and would be a break-before-make transfer (B is incorrect).

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 54 EXAM KEY MARCH 2009 Columbia in operating in MODE 1 with CRD-P-1A running. Events occur that result in an ATWS condition.

The CRS directs performance of PPM 5.5.11. The first action of PPM 5.5.11 is to ensure both CRD pumps are running. CRO1 starts CRD-P-1B and 30 seconds later, the CRD PUMPS ABNORMAL OPERATION alarm annunciates (along with other annunciators).

Which of the following describes the probable cause for the annunciator and the actions necessary to correct the situation?

A. Only CRD-P-1A tripped on low suction pressure. Continue with PPM 5.5.11 which places both suction filters in service and restarts the tripped CRD pump.

B. Only CRD-P-1B tripped on low suction pressure. Continue with PPM 5.5.11 which places both suction filters in service and restarts the tripped CRD pump.

C. Only CRD-P-1B tripped on low suction pressure. Enter ABN-CRD-MAXFLOW and place the second CRD suction filter in service.

D. Both CRD pumps tripped on low suction pressure. Enter ABN-CRD and place the second CRD suction filter in service.

ANSWER: D QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 201001 A2.01 Ability to predict the impacts of the following on the Control Rod Drive Hydraulic System and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Pump Trips (3.2 / 3.3)

REFERENCE:

PPM 5.5.11; 4.603.A7 4-6; ABN-CRD-MAXFLOW SOURCE: New LO: 5190 State the CRD pump trips; 11633 Determine the potential problem associated with operation of both CRD pumps and maximum flow.

RATING: H3 ATTACHMENT: None JUSTIFICATION: Both CRD pumps will trip on low suction (with a 3 second time delay). PPM 5.5.11 does not direct placing both filters in service. Entry conditions are for ABN-CRD and not ABN-CRD -MAXFLOW. D is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 55 EXAM KEY MARCH 2009 Columbia is starting up following a refueling outage. Control Rod sequence A1 is selected and the Reactor Operators have just completed withdrawal of all the control rods in RSCS group 1, RSCS group 2, RSCS group 3, and RSCS group 4.

Which of the following is the control rod density for this condition?

A. 25 percent B. 40 percent C. 50 percent D. 100 percent ANSWER: C QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 201004 K5.03 Knowledge of the operational implications of the following concepts as the apply to Rod Sequence Control System: Group notch control limits and rod density (3.3 / 3.5)

REFERENCE:

SD000160 Page 13 and 14 SOURCE: New LO: 5806 Explain the following terms: d. Control Rod density; e. Control Rod sequence RATING: H2 ATTACHMENT: None JUSTIFICATION: Completion of the 1st 4 (out of 10) RSCS rod groups places 50% of the rods in the full out position. This is 50% rod density. C is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 56 EXAM KEY MARCH 2009 Reactor Recirculation Pump 1A (RRC-P-1A) is being started.

If only one ASD channel is in operation, which of the following is correct?

A. RRC pump speed is limited to a maximum of 30 Hz.

B. RRC Pump speed is limited to a maximum of 51 Hz.

C. When the RAISE P/B is depressed, the rate of pump speed increase is always limited to 0.2 Hz/sec.

D. The ONE ASD CHANNEL FAILURE limiter light is illuminated until the second ASD channel is started.

ANSWER: B QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 202002 K4.07 Knowledge of the Recirculation Flow Control System design features and/or interlocks which provide for the following: Minimum and maximum pump speed setpoint (2.9 / 2.9)

REFERENCE:

SD000184 Pages 4 & 10 SOURCE: New LO: 9682 Given an initial operating condition, describe the response of the RRFC system to the removal or trip of a single ASD channel.

RATING: H2 ATTACHMENT: None JUSTIFICATION: Per reference, with one ASD channel - frequency is limited to 51 Hz (B is correct).

30 Hz is a runback speed (A is incorrect); Speed increase is limited for just the first 1.5 seconds at 0.2 Hz/sec (C is incorrect); This light is illuminated when a runback condition exists and only one channel is powered (D is incorrect).

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 57 EXAM KEY MARCH 2009 Columbia was operating at full power when a series of events occurred that resulted in an ATWS . The CRS has entered level/power control. The following plant parameters now exist:

RPV Level is -120 inches on uncompensated fuel zone meter MS-LI 610 RPV Level is -150 inches on wide range level instrument MS-LIS-36A Mode Switch is in Shutdown Reactor Power is 6 %

Drywell pressure is 4 psig Drywell Temperature is 285 °F Wetwell Temperature is 112 °F RPV Pressure is 380 psig Which of the following is correct?

RPV level ..

A. should be reported as -100 inches.

B. should be reported as -120 inches.

C. should be reported as -150 inches.

D. cannot be determined due to operation within the SAT curve.

ANSWER: A QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 216000 A3.01 Ability to monitor automatic operation of the Nuclear Boiler Instrumentation including: Relationship between meter/recorder readings and actual parameter valves: Plant Specific (3.4 / 3.4)

REFERENCE:

Operator Aid #94-089 SOURCE: New LO: 5582 List theand nominal ranges for each of the five ranges of reactor water level instruments: bowie Range; 11774 Describe the operational implications of the following concepts as they apply to the NBI: Vessel level measurement RATING: H4 ATTACHMENT: Yes - EOP 5.2.1 SAT Curve, Operator Aid #94-089 JUSTIFICATION: Parameters given indicate level/power conditions exist. Based on pressure no level correction is needed but because of level power conditions you add +20 inches to indicated (B is correct)

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 58 EXAM KEY MARCH 2009 Which of the following is designed to prevent the differential pressure across the primary containment boundary from exceeding the design limit?

A. Reactor Building to Drywell vacuum breakers.

B. Standby Gas Treatment (SGT) system.

C. Reactor Building to Wetwell vacuum breakers.

D. Wetwell to Drywell vacuum breakers.

ANSWER: C QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 223001 K4.06 Knowledge of the Primary Containment System and Auxiliaries design feature(s) and/or interlocks which provide for the following: Maintains proper containment/secondary containment to drywell differential pressure (3.1 / 3.3)

REFERENCE:

SD000127 Page 4 SOURCE: Bank modified LO00472 LO: 5636 Describe the function, purpose and design features of the following Primary Containment System components: h Reactor building to wetwell vacuum breakers RATING: L2 ATTACHMENT: None JUSTIFICATION: Per reference the RB to WW vacuum breakers are designed to prevent dP from exceeding design limit (C is correct)

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 59 EXAM KEY MARCH 2009 With Columbia operating at 80 percent power following a refueling outage, a CIA leak causes the MSIVs to close. An automatic reactor scram occurred and Safety Relief Valves are observed to be cycling.

Which of the following correctly describes the correct actions to take?

A. The MSIV control switches should be placed in CLOSED. SRVs are cycled to control RPV pressure at 800 psig to 1000 psig. No EOP entry conditions exist.

B. Take manual control of cycling SRVs and maintain RPV pressure 800 psig to 1000 psig.

Report EOP entry into PPM 5.1.1.

C. Report EOP entry into PPM 5.1.1 and PPM 5.2.1. Wait until CRS directs pressure control band to open SRVs.

D. Manually cycle SRVs as needed to maintain Bypass Valves full open. Report EOP entry into PPM 5.1.1.

ANSWER: B QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 239001 A2.10 Ability to predict the impacts of the following on the Main And Reheat Steam System and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Closure of one or more MSIVs at power (3.8 / 3.9)

REFERENCE:

OI-15; SD000128 page 5; EOP 5.1.1 SOURCE: New LO: 8017 Given plant conditions, recognize an EOP entry condition(s) and enter the appropriate flow chart.

RATING: H2 ATTACHMENT: None JUSTIFICATION: SRVs start to cycle at 1091 psig. EOP entry into PPM 5.1.1 is at 1060 psig (A is incorrect). No EOP entry into 5.2.1 is given (C is incorrect); Bypass valves are isolated due to MSIV closure (D is incorrect).

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 60 EXAM KEY MARCH 2009 With the reactor scrammed and MSIVs closed, SRVs are being cycled to control RPV pressure. CRO3 reports EOP entries into PPM 5.2.1 on high Suppression Pool temperature and high Wetwell level. In response, the CRS enters EOP PPM 5.2.1.

Which of the following is correct?

A. Either RHR A or RHR B should be started as both allow reduction of suppression pool temperature. PPM 5.2.1 then requires HPCS be started to lower Wetwell level per PPM 5.5.23.

B. Either RHR A or RHR B should be started as both allow reduction of suppression pool temperature and letdown of Wetwell to RadWaste.

C. RHR A should be started to allow reduction of suppression pool temperature and letdown of Wetwell to RadWaste.

D. RHR B should be started to allow reduction of suppression pool temperature and letdown of Wetwell to RadWaste.

ANSWER: D QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 268000 K1.09 Knowledge of the physical connections and/or cause-effect relationship between Radwaste and the following: ECCS Systems (2.6 / 2.8)

REFERENCE:

SD000198 Figure 1; EOP 5.2.1 WW Level leg SOURCE: New LO: 11801 Describe the function, purpose and design features of the following Residual Heat Removal System components: RHR-V-40/49, RHR discharge to RadWaste RATING: H3 ATTACHMENT: None JUSTIFICATION: Only RHR-B can both cool the SP and letdown to RadWaste (B and C are incorrect, D is correct); PPM 5.5.23 actually raises SP level (A is incorrect)

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 61 EXAM KEY MARCH 2009 Columbia is starting up. One Condensate pump is currently running in short cycle cleanup. COND-FC-11, the Condensate Pump Min Flow Controller, is in AUTO and in the CASCADE position.

Which of the following describes Condensate System min flow when a second and third Condensate pump is started?

Condensate System min flow..

A. does not change until COND-LCV-11 is re-positioned manually using the controller tapeset.

B. will increase by 5,600 gpm when the second condensate pump is started and 800 gpm when the third condensate pump is started for a total of 12,000 gpm.

C. will increase by 5,600 gpm when the second condensate pump is started and 5,600 gpm when the third condensate pump is started for a total of 16,800 gpm.

D. does not change until COND-LCV-11 is re-positioned manually by depressing the OPEN pushbutton on the controller.

ANSWER: B QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 256000 A1.01 Ability to predict and/or monitor changes in parameters associated with operating the Reactor Condensate System controls including: System Flow (2.9 / 2.9)

REFERENCE:

SD000134 Page 15 SOURCE: New LO: 5167 Explain the operation of the Condensate Pump minimum flow controller when in the CASCADE mode of automatic control.

RATING: H2 ATTACHMENT: None JUSTIFICATION: COND-FC-11 opens (in Auto and Cascade) to allow 5600 gpm per pump breaker closed up to a maximum of 12000 gpm. (5600+5600+800=12000 gpm B is correct)

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 62 EXAM KEY MARCH 2009 Columbia is starting up with Reactor Feed pump 1B being started. The TURBINE EMERG TRIP/RESET selector switch is placed in the RESET position. A few seconds later the HP stop valve (MS-V-172B) IN TEST light goes out and only the red open position light is illuminated. Ten seconds later the CRO looks back down and notices that the IN TEST light is still illuminated for the LP stop valve (BS-V-60B) but neither the green nor the red position indicating lights are illuminated.

Which of the following explains this indication?

A. This is a normal indication. BS-V-60B is in the process of stroking open.

B. Control power for BS-V-60B has been lost. BS-V-60B will not open.

C. The IN TEST light for BS-V-60B will extinguish when the TURBINE EMERG TRIP/RESET selector switch is released.

D. The trip oil header has not pressurized yet. BS-V-60B will start to open when the header pressurizes and the IN TEST light extinguishes.

ANSWER: A QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 259001 A3.09 Ability to monitor operation of the Reactor Feedwater System including: Lights and Alarms (3.0 / 3.0)

REFERENCE:

SD000151 Page 17, Simulator SOURCE: New LO: 5753 Describe the functions of the RFP Turbine Emerg Trip/Reset switch in each of its positions (TRIP, NORM, and RESET).

RATING: L3 ATTACHMENT: None JUSTIFICATION: Per reference and simulator the indications in the stem is how the system functions.

A is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 63 EXAM KEY MARCH 2009 Columbia is in the process of a reactor shutdown. With reactor power being reduced from 35% to 30%

power, CRO1 receives a Below/LPAP Rod Worth Minimizer (RWM) alarm.

Which of the following signals causes this Rod Worth Minimizer alarm?

A. The total steam flow from all four main steam line flow instruments.

B. The average Reactor power from all APRM instruments.

C. Reactor power as calculated by PPCRS.

D. Main Turbine first stage pressure.

ANSWER: A QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 201006 K1.04 Knowledge of the physical connections and/or cause-effect relationships between Rod Worth Minimizer and the following: Steam flow/Reactor power (3.1 / 3.2)

REFERENCE:

SD000154 Page 5 and 16 SOURCE: Bank LX00601 Modified slightly LO: 5916 Describe the physical connection and/or cause-and-effect relationship between RMW and: a. FWLC RATING: L2 ATTACHMENT: None JUSTIFICATION: Per reference the steam flow inputs are summed to determine 32% power and give the alarm (A is correct).

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 64 EXAM KEY MARCH 2009 Columbia is operating in MODE 1 at 60 % power with ROA-FN-1A and REA-FN-1A maintaining Reactor Building dP. ROA-FN-1B and REA-FN-1B are in standby. A lockout on bus SM-1 occurs and TR-B re-energizes SM-7.

Which of the following correctly describes the plant response to this event?

A. ROA-FN-1A and REA-FN-1A stop on the loss of power to SM-7 but will automatically restart when power to SM-7 is restored. Reactor Building dp decreases slightly but is restored to -0.6 WG.

B. After a 10 second time delay, ROA-FN-1B and REA-FN-1B auto start on low dp across the other fan. Reactor Building dp decreases but is restored to -0.6 WG.

C. ROA-FN-1A and REA-FN-1A stop on the loss of power to SM-7. ROA-FN-1B and REA-FN-1B do not auto start. Reactor Building dp decreases to approximately 0 WG.

D. After a 25 second time delay, ROA-FN-1B and REA-FN-1B auto start on low dp across the other fan. Reactor Building dp drops to approximately 0 WG but is restored to -0.6 WG.

ANSWER: C QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 288000 K3.05 Knowledge of the effect that a loss or malfunction of the Plant Ventillation System will have on the following: Reactor Building pressure (3.1 /

3.3)

REFERENCE:

SD000183 Page 16 and 17 SOURCE: New LO: 5680 List the signals that will result in an automatic start and an automatic trip of ROA-FN-1A and 1B; 5681 List the signals that will result in an automatic start and an automatic trip of REA-FN-1A and 1B.

RATING: L3 ATTACHMENT: None JUSTIFICATION: The standby fans will auto start on low dp if opposite fan has not tripped (is running). ROA-FN-1A and REA-FN-1A are NOT running therefore the standby fans will NOT start (A and D are incorrect). The tripped fans do not restart (A is incorrect). There is a 10 second time delay for the auto start and the time delay is 25 seconds if TR-B re-energizes SM-7.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 65 EXAM KEY MARCH 2009 A series of events has resulted in a high drywell pressure reactor scram. Drywell pressure is currently 14 psig and down slow due to the initiation of wetwell sprays on RHR-P-2B and drywell sprays on RHR-P-2A.

If a malfunction causes RHR-V-4A (RHR-P-2A Suppression Pool suction valve) to go closed, which of the following is correct?

RHR-P-2A will trip..

A. as soon as RHR-V-4A is not fully opened. RHR-V-16A and RHR-V-17A should then be manually closed.

B. when RHR-V-4A is fully closed. RHR-V-16A and RHR-V-17A will automatically go closed.

C. as soon as RHR-V-4A is not fully opened. RHR-V-16A and RHR-V-17A will automatically go closed.

D. when RHR-V-4A is fully closed. RHR-V-16A and RHR-V-17A should then be manually closed.

ANSWER: A QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 226001 K6.13 Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI Containment Spray System Mode: Suction Flow Path (3.2 / 3.2)

REFERENCE:

SD000198 Page 10, 12, 14, 15; ARP for BISI for RHR-N-4A not full open 4.601.A4 SOURCE: New LO: 5781 List the interlocks and trips associated with the following RHR System components: a. RHR Pumps; e. RHR-V-16A/B and RHR-V-17A/B RATING: L3 ATTACHMENT: None JUSTIFICATION: RHR-V-4A going closed immediately trips RHR-P-2A. The spray valves have to be manually closed. A is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 66 EXAM KEY MARCH 2009 Due to a series of events CRO1 is directed to initiates SLC. Two minutes after SLC initiation, the GDS valve status screen is checked, and the border for GROUP 7 is yellow.

Which of the following is correct based on the above?

A. Both RWCU-V-1 and RWCU-V-4 closed. GROUP 7 isolations are complete.

B. RWCU-V-1 closed and RWCU-V-4 remained open. GROUP 7 isolations are complete.

C. RWCU-V-1 and RWCU-V-4 remained open. GROUP 7 isolations are not complete.

D. RWCU-V-1 remained open and RWCU-V-4 closed. GROUP 7 isolations are not complete.

ANSWER: C QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.1.19 Ability to use plant computer to evaluate system or component status (3.9 / 3.8)

REFERENCE:

SD000173 page 7; None for GDS - Simulator was used.

SOURCE: New LO: 5925 Describe the expected response to placing the SLC SYSTEM A or B keylock switch in the OPERATE position. None for GDS.

RATING: L3 ATTACHMENT: None JUSTIFICATION: Initiation of SLC results in the closure of RWCU-V-4. The position of RWCU-V-1 does not change with SLC initiation and RPV/L did not reach -50 so RWCU-V-1 does not close. (B is incorrect). GDS having a yellow background indicates a valve in the group has not isolated (A and D are incorrect). C is correct as RWCU-V-4 should have closed but did not and isolations are not complete.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 67 EXAM KEY MARCH 2009 Which of the following thermal limits is a Safety Limit that attempts to prevent fuel failure by assuring that bulk nucleate boiling heat transfer is maintained for all expected operational transients?

A. APLHGR B. MFLPD C. LHGR D. MCPR ANSWER: D QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits (3.2 / 4.2)

REFERENCE:

Tech Spec Bases page B 2.1.1-3; SD000131 Pages 22 and 34 SOURCE: Bank - Modified slightly LX00264 LO: 6924 State Columbia's safety limits, applicability, action statements and bases. 5390 Determine the Safety Limits and LCOs directly associated with Fuel.

RATING: L2 ATTACHMENT: None JUSTIFICATION: Per bases MCPR attempts to prevent fuel failure by assuring that bulk nucleate boiling heat transfer is maintained for all expected operational transients (D is correct). LHGR is the actual rate of heat generation per unit length of a specified fuel rod (C is incorrect); MFLPD is the actual linear heat generation rate (LHGR) divided by the technical specification limit for LHGR (B is incorrect); APLHGR limits the peak cladding temperature will not exceed 2200°F after a design loss of coolant accident (A is incorrect).

COMMENTS: Keep this question - This K/A has an RO value of 3.2692 and Columbia has a specific learning objective for this.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 68 EXAM KEY MARCH 2009 When PPM 5.4.1, Radioactivity Release Control, is entered it directs that Radwaste and Turbine Building HVAC be restarted if not running.

Which of the following describes the reason for restarting Radwaste and Turbine Building HVAC?

A. Without Radwaste and Turbine Building HVAC running, the Area Radiation Monitors will not give accurate indication of local radiation levels.

B. Operation of Radwaste and Turbine Building HVAC preserves personal accessibility and provides for an elevated monitored release path.

C. Operation of Radwaste and Turbine Building HVAC prevents the Control Room from becoming uninhabitable due to high radiation levels.

D. With Radwaste and Turbine Building HVAC running, the air balance is maintained and there is less leakage from the Reactor Building.

ANSWER: B QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.3.11 Ability to control radiation releases (3.8 / 4.3)

REFERENCE:

PPM 5.0.10 Page 318 SOURCE: Bank Modified LO00213 LO: 8477 Identify the statement that describes the purpose of restarting turbine building and RadWaste building HVAC during attempts to control offsite radioactivity release rates above the Alert Level.

RATING: L2 ATTACHMENT: None JUSTIFICATION: Per PPM 5.0.10 B is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 69 EXAM KEY MARCH 2009 PPM 3.1.10, Operating Data Logs, requires a timed entry for the Time of reactor criticality during startup and also Pertinent plant data at criticality (e.g. reactor coolant temperature, period, neutron level, control rod number and position).

During a plant startup CRO1 is taking the data at criticality and notes the following:

T = 0:00:00 SRM C indicates 1200 counts per second T = 0:02:10 SRM C indicates 2400 counts per second Which of the following should be logged in the CRO log as the period for this criticality?

A. 90 seconds B. 146 seconds C. 187 seconds D. 302 seconds ANSWER: C QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports (3.6 / 3.8)

REFERENCE:

PPM 3.1.10 Page 8 SOURCE: New LO: 6167 With the Admin procedures available, determine the item that must be entered into the control room log.

RATING: L2 ATTACHMENT: None JUSTIFICATION: Stem gives counts doubled in 130 seconds. Period is 130 x 1.44 = a period of 187 seconds (C is correct). 130/1.44 = 90 A is incorrect; 210 x 1.44 = 302 D is incorrect; 210/1.44 = 146 B is incorrect

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 70 EXAM KEY MARCH 2009 Which of the following level instruments is identified as post-accident instrumentation?

A. MS-LI-604, the Wide Range level indicator on H13-P603, which has a orange placard with black letters that read PAM.

B. MS-LR-623A, the Wide Range level indicator on H13-P601, which has a red placard with white letters that read PAM.

C. MS-LI-605, the Shutdown Flooding level indicator on H13-P602, which has a black placard with white letters that read PAM.

D. MS-LI-612, the Compensated Fuel Zone level indicator on H13-P601, which has a white placard with black letters that read PAM.

ANSWER: B QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.4.3 Ability to identify post-accident instrumentation (3.7 / 3.9)

REFERENCE:

SD000173 Page 14, Simulator SOURCE: New LO: 11264 Ability to identify post-accident instrumentation.

RATING: L2 ATTACHMENT: None JUSTIFICATION: Only MS-LR-623A is a PAM instrument per reference and control board marking of a red placard with white lettering.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 71 EXAM KEY MARCH 2009 With Columbia starting up following a refueling outage and reactor power at 35%, Condensate Pumps COND-P-1A, COND-P-1B and COND-P-1C are running. Condensate Booster Pumps (CBP) COND-P-2A and COND-P-2B are running. A lockout on breaker N1-2 occurs and all systems operate as designed.

Which of the following describes a required immediate action that should be performed for this event?

A. Reduce RRC flow to 60 Mlbm/hr.

B. If HPCS DG is running, trip the HPCS DG.

C. There are no required immediate actions that should be performed for this event.

D. Reduce power with flow to ensure a CBP Suction Pressure Low alarm does not annunciate.

ANSWER: C QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls (4.6 / 4.4)

REFERENCE:

ABN-ELEC-SM2/SM4 SOURCE: New LO: 10343 Given that a loss of power to SM-2, SM-4 or MC-4A has occurred, determine the immediate actions (and bases) required. [ABN-ELEC-SM2/SM4]

RATING: H3 ATTACHMENT: None JUSTIFICATION: A lockout on breaker N1-2 causes a loss of power to SM-2, SM-4 will be energized by the HPCS DG. With power at 35%, RRC Flow is already LT 60 mlbm/hr (A is incorrect); Tripping the HPCS DG is only required if HPCS-P-2 is not operating and stem says all systems operate as designed (B is incorrect); Reducing power to ensure low pressure alarm doesnt annunciate is a subsequent action (D is incorrect). C is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 72 EXAM KEY MARCH 2009 While hanging or removing a tag out, which of the following has been determined to be the lowest cumulative exposure that will allow the CRS/Shift Manager to consider waiving the performance of independent or simultaneous verification.

A. 1 mrem B. 5 mrem C. 25 mrem D. 50 mrem ANSWER: B QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions (3.2 / 3.7)

REFERENCE:

PPM 1.3.1 Conduct of Operations page 41; PPM 1.3.64 Plant Clearance Order Page 27 SOURCE: New LO: 6264 State who has the authority to waive Independent Verification when significant radiation exposures are likely to occur as a result of performing an Independent Verification and state how this is performed.

RATING: L3 ATTACHMENT: None JUSTIFICATION: Per PPM 1.3.1 and PPM 1.3.64, a cumulative exposure of 5 mrem allows waiving verification by CRS/SM.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 73 EXAM KEY MARCH 2009 Columbia has entered PPM 5.1.4, RPV Flooding, due to a series of events that has caused a loss of all RPV water level instruments.

Which of the following does PPM 5.1.4 identify as indications that the RPV has been flooded to the elevation of the Main Steam Lines and Flooding conditions exist?

1. Increasing RPV pressure

2. Decreasing RPV pressure

3. WW level increases from suction sources aligned to the WW

4. WW level decreases from suction sources aligned to the WW

5. WW level steadies if suction sources are from inside containment

6. WW level steadies if suction sources are from outside containment

7. Audible 2-phase flow from an unisolated main steam line A. 1, 5, and 7 B. 2, 3, and 5 C. 1, 4, and 6 D. 2, 4, and 7 ANSWER: A QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control (4.0 / 4.6)

REFERENCE:

PPM 5.0.10 Page 205 table 12 of PPM 5.1.4 SOURCE: Bank Modified Stem slightly LO001290 LO: 11021 Given a list, identify the indications of Flooded Main Steam Lines.

RATING: H3 ATTACHMENT: None JUSTIFICATION: Per Table 12 of PPM 5.1.4, choices 1, 5 and 7 are correct. A is answer.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 74 EXAM KEY MARCH 2009 Which statement best describes Minimum Steam Cooling Pressure?

Minimum Steam Cooling Pressure is the lowest RPV pressure at which..

A. steam flow through the Minimum Number of SRVs Required for Emergency Depressurization is sufficient to remove all decay heat from the core.

B. steam flow through open SRVs is sufficient to preclude any clad temperature from exceeding 2200 deg F with RPV level at or below TAF.

C. the covered portion of the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1800 deg F.

D. steam flow through open SRVs is sufficient to preclude any clad temperature from exceeding 1500 deg F even with RPV level below TAF.

ANSWER: D QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.4.17 Knowledge of EOP terms and definitions (3.9 / 4.3)

REFERENCE:

PPM 5.0.10 SOURCE: Bank Modified LO01416 LO: 8040 Given a standard EOP term or phrase and a list of possible definitions, identify the definition that states the meaning of the term or phrase.

RATING: L3 ATTACHMENT: None JUSTIFICATION: Per PPM 5.0.10 D is correct.

COLUMBIA GENERATING STATION WRITTEN EXAMINATION QUESTION # 75 EXAM KEY MARCH 2009 With Columbia operating in MODE 1, the Control Room receives annunciator 4.602.A13 1-2 REACTOR BLDG FLOOR SUMP R4 LEVEL HI-HI. The alarm response procedure requires local investigation of sump level.

To investigate the cause of this alarm, CRO3 should dispatch.

A. OPS 2 to the RHR-C pump room.

B. OPS 3 to the RHR-A pump room.

C. OPS 2 to the RHR-B pump room.

D. OPS 3 to the LPCS pump room.

ANSWER: A QUESTION TYPE: RO/SRO Closed KA # & KA VALUE: 2.1.8 Ability to coordinate personnel activities outside the control room (3.4 / 4.1)

REFERENCE:

SD000139 figure 2A; PPM 1.3.1 Conduct of Operations Page 54 SOURCE: New LO: None RATING: L2 ATTACHMENT: None JUSTIFICATION: OPS 2 is the Reactor Building watch stander and R-4 sump is in the RHR-C pump room - A is correct

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 1 EXAM KEY MARCH 2009 Columbia is operating at full power in Mode 1. A Main Turbine trip causes a reactor scram. The lights in the Control Room go out and approximately 5 seconds later some of the lights come back on.

Which of the following describes the probable electrical plant lineup and what procedures would the Control Room Supervisor enter after receiving the scram report from CRO1?

A. TR-B is powering SM-7 and SM-8. Enter PPM 3.3.1 Reactor Scram, and ABN-ELEC-GRID.

B. DG-1 is powering SM-7 and DG-2 is powering SM-8. Enter PPM 3.3.1 Reactor Scram; PPM 5.1.1 RPV Control, and ABN-ELEC-GRID.

C. TR-B is powering SM-7 and SM-8. Enter PPM 5.1.1 RPV Control, and ABN-ELEC-GRID.

D. DG-1 is powering SM-7 and DG-2 is powering SM-8. Enter PPM 5.1.1 RPV Control, and ABN-ELEC-GRID.

ANSWER: C QUESTION TYPE: SRO Closed KA # & KA VALUE: 295003 AA2.05 Ability to determine and/or interpret the following as they apply to Partial or Complete loss of A.C. Power: Whether a partial or complete loss of A.C.

power has occurred. (3.9 / 4.2) 55.43.5

REFERENCE:

SD000182 pages 55, 60, 61; PPM 5.1.1; SD000200 page 41; ABN-ELEC-GRID page 2 SOURCE: New LO: 5050 Describe the cause-and-effect relationship for: a. N" and "S" breakers on each bus; b. breakers DG1-7, B-7, B-8 and DG2-8.

RATING: H2 ATTACHMENT: None JUSTIFICATION: TR-S should have immediately closed in but did not which is indicated by the lights going out. TR-B closes in on SM-7/8 5.5 seconds after UV on SM7/8 and when it does, some of the lights come back on (All dont come on because CR lights on MC-7E and 8E are load shed). It takes at least 10 seconds for DG-1/2 to come up to

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION speed and then close in (B and D are incorrect); PPM 3.3.1 is not entered by the CRS (A is incorrect). PPM 5.1.1 will always be entered due to low RPV Level (A is incorrect) and ABN-ELEC-GRID is entered due to the unanticipated loss of TR-S.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 2 EXAM KEY MARCH 2009 Columbia was operating in MODE 1 when events occurred that require the control room crew to evacuate the Main Control Room. All immediate actions were completed prior to leaving. The following plant conditions now exist:

Reactor Power is 4 percent and steady One SRV is cycling RPV level is -10 inches and up slow Drywell pressure is 1.3 psig and up slow Suppression Pool temperature is 85° and up slow Which of the following procedures should the crew perform?

A. PPM 5.1.1, RPV Control B. PPM 5.1.2 , RPV Control ATWS C. PPM 5.2.1, Primary Containment Control D. ABN-CR-EVAC ANSWER: D QUESTION TYPE: SRO Closed KA # & KA VALUE: 295016 2.4.16 Control Room Abandonment. Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines (3.5 / 4.4) 55.43.5

REFERENCE:

ABN-CR-EVAC Page 7 SOURCE: Bank modified LO01620 LO: 6105 State which procedures have priority/precedence over all other operating procedures when an emergency exists.

RATING: H2 ATTACHMENT: None JUSTIFICATION: EOP 5.1.1 could be entered on SRV cycling and RPV level; EOP 5.1.2 could be entered from 5.1.1 on failure to scram; There is no current entry into PPM 5.2.1; Per ABN-CR-EVAC note, the ABN supersedes EOPs and PPM 3.3.1 (D is correct)

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 3 EXAM KEY MARCH 2009 Columbia is in MODE 5 with the fuel shuffle on going and the Drywell open for outage maintenance activities. A fuel bundle free falls from the fuel grapple and lands on the reactor flange. In response, the Reactor Building Ventillation isolates and both Standby Gas Treatment systems auto start.

Which of the following is correct for these conditions?

A. Enter PPM 5.4.1, Radioactivity Release Control.

B. Enter PPM 5.3.1, Secondary Containment Control.

C. Enter ABN-RAD RELEASE.

D. Enter ABN-RAD-HIGH.

ANSWER: B QUESTION TYPE: SRO Closed KA # & KA VALUE: 295023 AA2.01 Ability to determine and/or interpret the following as they apply to Refueling Accidents: Area radiation levels (3.6 / 4.0) 55.43.4 and 5

REFERENCE:

PPM 5.3.1 entry condition SOURCE: New LO: 8017 Given plant conditions, recognize an EOP entry condition(s) and enter the appropriate flow chart.

RATING: H2 ATTACHMENT: None JUSTIFICATION: RB Ventillation isolating and SGT starting is indication a Z signal exists which is entry condition into EOP 5.3.1; EOP 5.4.1 is entered on offsite release (A is incorrect); Entry conditions do not exist for either of the ABNs (C & D incorrect)

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 4 EXAM KEY MARCH 2009 A series of events has resulted in the following plant conditions:

MSIVs are closed Suppression Pool Temperature is 111°F APRM Downscale Lights are not illuminated RPV Level is -140 and is steady 2 SRVs are being cycled to maintain RPV Pressure Based on the current plant status, what EOP should the CRS be in and what should be the next level band directed?

A. PPM 5.2.1 and PPM 5.1.2; -140 to -80 B. PPM 5.3.1 and PPM 5.1.1; -155 to -65 C. PPM 5.3.1 and PPM 5.1.2; -161 to -65 D. PPM 5.2.1 and PPM 5.1.2; -183 to -161 ANSWER: D QUESTION TYPE: SRO Closed KA # & KA VALUE: 295037 EA2.02 Ability to determine and/or interpret the following as they apply to Scram Condition Present and Reactor Power above APRM Downscale or Unknown:

Reactor water level (4.1 / 4.2) 55.43.5

REFERENCE:

PPM 5.0.10 pages 149, 150, 151. PPM 5.1.2 flow chart level leg SOURCE: New LO: 8108 Given a list, identify the statement that describes the reasons for maintaining the specified RPV water level for the following conditions: 3. Level/Power Conditions exist RATING: H2 ATTACHMENT: None JUSTIFICATION: Parameters given indicate that Level/Power conditions exist. EOP 5.2.1 and 5.1.2 are entered by the CRS. No entry into PPM 5.3.1 is indicated in the stem. RPV level is lowered to -161 and no less than -183 (D is correct). -140 to -80 is the normal level band for ATWS (A is incorrect). -155 to -65 is current level to highest LL

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION allowed in an ATWS (B is incorrect) -161 is lower end of band without level/power conditions and -65 is highest level in ATWS (C is incorrect).

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 5 EXAM KEY MARCH 2009 Columbia is in MODE 5 during a refueling outage with fuel shuffle underway. SM-8 is currently de-energized for maintenance. Forty five minutes ago, RHR-P-2A developed low discharge pressure and was secured.

Based on the above information which of the following is correct?

A. Within the next hour verify an alternate method of decay heat removal is available.

B. Immediately suspend loading irradiated fuel into the RPV.

C. Within the next 15 minutes verify reactor coolant circulation by an alternate method.

D. Within the next 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 15 minutes initiate actions to suspend OPDRVs.

ANSWER: C QUESTION TYPE: SRO Closed KA # & KA VALUE: 295021 2.1.40 Loss of Shutdown Cooling - Knowledge of refueling administrative requirements (2.8 / 3.9) 55.43.2

REFERENCE:

TS 3.9.8 pages 1 and 2; 3.5.2 pages 1 and 2 SOURCE: New LO: 9670 Given appropriate conditions, indications and copies of Technical Specifications, determine when an entry condition is met and interpret required Technical Specification actions from an analysis of plant conditions.

RATING: L3 ATTACHMENT: Yes - TS pages 3.9.8-1 and 3.9.8-2; 3.5.2-1 and 3.5.2-2 JUSTIFICATION: Question implies no RHR loop is in SDC sending you to Tech Spec 3.9.8. A is incorrect as this would be 1 hr 45 min. after condition A is met and is required within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. B is incorrect as it gives you a total of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as per action A.1 - you would have an additional 15 minutes before having to do this; C is correct because the 1 hr time clock is over in 15 minutes. D is incorrect as Tech Spec 3.5.2 is NOT applicable due to refueling being underway (Spec is not applicable as water is GT 22 ft above flange in stem) but would be required after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per action B.1

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 6 EXAM KEY MARCH 2009 Columbia experienced a LOCA. When the Reactor was manually scrammed, all rods did not go in. Reactor power is 2% and steady, Drywell Pressure is 12 psig and trending up slow and Suppression Pool temperature is 85°F and steady. The Shift Manager declares a Site Area Emergency.

Which of the following prompts the Shift Manager to declare a Site Area Emergency and what actions should the CRS direct?

A. Suppression Pool Level indicates 19 ft. 1 inch. Direct HPCS initiation per PPM 5.5.23.

B. Wetwell Pressure indicates 12 psig. Direct Drywell sprays be initiated per PPM 5.2.1.

C. RPV/L indicates -181. Enter PPM 5.1.5 and direct an Emergency Depressurization.

D. An ATWS exists. Enter PPM 5.1.2 and direct PPM 5.5.10 and PPM 5.5.11 to insert rods.

ANSWER: B POST EXAM COMMENT - The answer key was changed to accept A or B for this question. Both sets of conditions require declaring an SAE.

QUESTION TYPE: SRO Closed KA # & KA VALUE: 295024 AA2.04 Ability to determine and/or interpret the following as they apply to High Drywell Pressure: Suppression chamber pressure (3.9 / 3.9) 55.43.5

REFERENCE:

PPM 13.1.1 block 3.1.S.1; PPM 5.2.1 SOURCE: New LO: 6131 With the procedures available for reference and plant conditions such that an emergency classification be declared, correctly classify the event.

RATING: H3 ATTACHMENT: Yes - PPM 13.1.1 blocks for 2.2.S.1; 3.1.S.1; 2.1.S.1; 3.2.U.1 JUSTIFICATION: The SAE is declared due to 3.1.S.1 - Drywell pressure response not consistent with LOCA conditions as WW and DW pressures are almost equal. Normal dP is 5 psig.

A is incorrect as a UE would be declared. C is incorrect as RPV/L would need to be

-183 for SAE. D is incorrect as all the conditions for 2.2.S.1 are not met.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 7 EXAM KEY MARCH 2009 Columbia is operating at 80% power. A malfunction in the DEH system causes the governor valves to start to slowly go closed.

Which of the following explains the plant response to the failure and what procedure would be entered first to mitigate the transient?

A. Reactor power will rise. ABN-PRESSURE will be entered.

B. Reactor power will drop. ABN-PRESSURE will be entered.

C. Reactor power will rise. ABN-POWER will be entered.

D. Reactor power will drop. ABN-POWER will be entered.

ANSWER: A QUESTION TYPE: SRO Closed KA # & KA VALUE: 295025 EA2.02 Ability to determine and/or interpret the following as they apply to High Reactor Pressure: Reactor power (4.2 / 4.2) 55.43.6

REFERENCE:

ABN-PRESSURE page 2 and 12; ABN-POWER page 2 SOURCE: New LO: 11666 Explain the cause-effect relationships between the DEH Control System and the following: Reactor power RATING: H3 ATTACHMENT: None JUSTIFICATION: Closing of the GVs causes RPV/P to rise (B and D are incorrect) ABN-PRESSURE is the procedure utilized to mitigate the rise in RPV Pressure caused by GVs closing.

ABN power is also entered but ABN pressure mitigates the failure.(C is incorrect).

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 8 EXAM KEY MARCH 2009 Columbia is shutdown in a refueling outage with a complete core offload in progress. There are two evolutions in progress, that if not coordinated, could drain the reactor vessel. The outside air temperature is 110°F. OPS2 contacts the Control Room and reports that the general area temperature on the 471 elevation of the Reactor Building West side (area around SH-10 breaker) has been 105°F for the last 75 minutes. The high temperature is partially due to maintenance on the ventilation system in that area of the plant.

Which of the following is correct?

A. Immediately initiate actions to suspend operations that have a potential of draining the reactor vessel.

B. Initiate actions to restore the areas temperature to within limits of Condition C within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

C. Any required action may be delayed for up to four hours because the temperature increase was partially due to maintenance activities.

D. Immediately suspend movement of irradiated fuel in the Secondary Containment.

ANSWER: A QUESTION TYPE: SRO Closed KA # & KA VALUE: 295032 EA2.02 Ability to determine and/or interpret the following as they apply to High Secondary Containment Area Temperature; Equipment operability (3.3 / 3.5) 55.43.2

REFERENCE:

LCS 1.7.1; TS 3.4.6.3 SOURCE: Bank LO01643 LO: 9540 Given appropriate conditions, indications, and copies of Technical Specifications, determine when an entry condition is met and interpret the required Tech Spec actions from an analysis of plant conditions.

RATING: H4 ATTACHMENT: Yes - LCS 1.7.1; TS 3.6.4.3 JUSTIFICATION: The temperature is GT the Max (104°F) for that area per LCS Table 1.7.1-1.

Because of that you go further into LCS and determine the affected equipment. SGT Div 1 and Div 2 are affected equipment (Table 1.7.1-2). High temp for 75 minutes causes both trains of SGT to be inoperable per . TS 3.6.4.3 requires OPDRVs be

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION suspended (A is correct). The delay of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> does not apply (C is incorrect).

Suspending movement of irradiated fuel was a requirement prior to source term revision (D is incorrect). B is incorrect because requirement is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, not 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 9 EXAM KEY MARCH 2009 Following a Loss of Coolant Accident and subsequent reactor scram, Drywell pressure reached 13 psig.

Additionally, Drywell and Wetwell hydrogen concentrations have increased to 6.2 percent and Drywell and Wetwell oxygen concentrations have increased to 3.6 percent.

The Incident Advisor then informs you that the following plant conditions now exist:

Drywell pressure is now 17 psig Hydrogen in the Drywell has been reduced to 5.8 percent and Oxygen in the Drywell is now 4.8 percent Hydrogen in the Wetwell is still 6.2 percent and Oxygen in the Wetwell is now 5.2 percent ODCM RFO Limits of TABLE 27 will not be exceeded Which of the following actions is correct for this situation?

A. Enter PPM 5.1.3 and perform an Emergency Depressurization.

B. Spray the Wetwell and Drywell. Disregard adequate core cooling if necessary.

C. Stop operation of the Drywell recirculation fans.

D. Perform PPM 5.5.21. Disregard offsite release rates limits if necessary.

ANSWER: A QUESTION TYPE: SRO Closed KA # & KA VALUE: 500000 EA2.04 Ability to determine and/or interpret the following as they apply to High Primary Containment Hydrogen Concentrations: Combustible limits for Wetwell (3.3 / 3.3) 55.43.5

REFERENCE:

PPM 5.2.1 SOURCE: New LO: 11150 Given plant conditions and EOP flowcharts, evaluate plant conditions and determine the appropriate actions according to EOP 5.2.1 RATING: H2 ATTACHMENT: Yes - PPM 5.2.1 Diagram 19 - Combustible limits JUSTIFICATION: ED is required per leg U due to combustible limit reached in WW (A is correct).

5.5.21 can be performed but release rates limits are not disregarded because combustible levels do not exist in DW (D is incorrect). DW recirc fans are stopped if DW combustible levels are exceeded (C is incorrect). Only WW sprays can be initiated with adequate core cooling disregarded (B is incorrect).

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 10 EXAM KEY MARCH 2009 Columbia is starting up following a maintenance outage. Main Generator output is 760 MWe. Problems with screen fouling in the Circ Water basin has caused a delay in the startup. Backpressure is currently 5.5 Hg and going up (getting worse) at the rate of 1 hg per hour.

Based on the above, which of the following is correct?

A. Entry into ABN-GENERATOR and ABN-BACKPRESSURE is required. Columbia can remain on line for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> but then a manual Reactor scram and Main Turbine trip will be required within the following half hour.

B. Entry into ABN-GENERATOR and ABN- BACKPRESSURE is required. An immediate Reactor scram and Main Turbine trip is required due to exceeding backpressure limits.

C. Entry into ABN-BACKPRESSURE is required. Within the next hour, a required manual Reactor scram will be inserted and then the Main Turbine will be tripped.

D. Entry into ABN-GENERATOR is required. The Main Turbine will automatically trip on high backpressure at 8 Hg. which will then cause an automatic Reactor scram.

ANSWER: C QUESTION TYPE: SRO Closed KA # & KA VALUE: 295002 2.4.49 Loss of Main Condenser Vacuum. Ability to perform without reference to procedures those actions that require immediate operation of system components and controls (4.6 / 4.4) 55.43.5

REFERENCE:

ABN-BACKPRESSURE SOURCE: New LO: 6785 Describe the immediate actions (and bases) required for a Loss of Main Condenser Vacuum and the desired effect these actions will have.

RATING: H2 ATTACHMENT: Yes - Attachment 7.1 of ABN-BACKPRESSURE JUSTIFICATION: Per ABN-BACKPRESSURE, if backpressure gets within 1 of trip setpoint a scram and MT trip is required. No entry into ABN-GENERATOR is required. The parameters and trends given will put operation within the 1 limit within the next hour (C is correct and B is incorrect). A is incorrect as it does not take into account the procedure requirement to scram/trip within 1 of limit. D is incorrect as it is limit for output at GT 840 MWe.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 11 EXAM KEY MARCH 2009 During operation in MODE 1, LPCS-P-2 trips. Direction is given to start LPCS-P-1 and RHR-P-2A. Before RHR-P-2A can be started, the RHR A PUMP DISCH PRESS HIGH/LOW alarm annunciates and the control power fuses are pulled to prevent a pump start. A short time later a LOCA and a Loss of Offsite Power occur. The following plant conditions now exist:

DG-2 inoperable HPCS-P-1 tripped LPCS-P-1 injecting at 6800 gpm Reactor pressure 150 psig down slow Reactor level -50 inches down slow Drywell pressure 16 psig up slow Wetwell pressure 11 psig up slow SP temperature 108 degrees F and up slow Given the above, which of the following is the correct?

A. Enter PPM 5.1.1 and PPM 5.2.1. Leave the control power fuses removed and do not use RHR-P-2A.

B. Enter PPM 5.2.1. Fill and vent A RHR system, reinstall the control power fuses and then spray the Wetwell and place the remainder of available flow into Suppression Pool cooling.

C. Enter PPM 5.1.1 and PPM 5.2.1. Reinstall the control power fuses and commence injection into the RPV.

D. Enter PPM 5.1.1. Reinstall the control power fuses and spray the Wetwell and then spray the Drywell.

ANSWER: C QUESTION TYPE: SRO closed KA # & KA VALUE: 203000 A2.17 Ability to (a) predict the impacts of the following on RHR/LPCI Injection Mode and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Keep fill system failure (3.3 / 3.5) 55.43.5

REFERENCE:

ARP 4.601.A4 drop 3-1; PPM 5.0.10; PPM 5.2.1 SOURCE: New LO: 11144 Given plant conditions and EOP flowcharts, evaluate plant conditions and

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION determine the appropriate actions according to EOP 5.1.1.; 11150 Given plant conditions and EOP flowcharts, evaluate plant conditions and determine the appropriate actions according to EOP 5.2.1.

RATING: H3 ATTACHMENT: None JUSTIFICATION: Entry conditions are given for PPM 5.1.1 and PPM 5.2.1. RHR-P-2A can be restarted for EOP related activities (A and B are incorrect). Fill and Vent is required per ABN-RHR-DEPRESS but EOPs override ABNs (B is incorrect). Correct use for RHR A after fuses are installed is to inject. (C is correct). Spraying the DW is not permitted until WW/P is GT 12 psig, not Drywell pressure. (D is incorrect).

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 12 EXAM KEY MARCH 2009 Columbia is in MODE 5 with all control rods fully inserted. A fuel bundle is in transit between the spent fuel pool and the reactor cavity. SRM-A and SRM-C are both out of service with maintenance troubleshooting underway to repair the instrument drawer.

During troubleshooting activities, the I&C Technician inadvertently moves the Mode Switch for SRM-B out of the OPERATE position.

Which of the following is correct?

A. Only one SRM channel is required to be operable for this Mode of operation. The fuel shuffle may continue per the approved NCTL.

B. Return at least one SRM to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The fuel shuffle may not continue, place the fuel bundle in a temporary location that is designated on the NCTL.

C. Immediately suspend control rod withdrawals. The fuel shuffle can continue if the operable SRM is in the quadrant where the bundle will be placed.

D. Immediately suspend core alterations except for control rod insertions. Place the fuel bundle back in its original location and orientation.

ANSWER: D QUESTION TYPE: SRO Closed KA # & KA VALUE: 215004 2.2.36 SRM System - Ability to analyze the affect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations (3.1 / 4.2) 55.43.2; 55.43.7

REFERENCE:

TS 3.3.1.2; PPM 6.3.2 page 15.

SOURCE: New LO: 10294 Given appropriate conditions, indications and copies of Technical Specifications, interpret required Technical Specification actions from an analysis of plant conditions.

RATING: H2 ATTACHMENT: Yes - TS 3.3.1.2 page 6 JUSTIFICATION: From stem the plant is in MODE 5. Table 3.3.1.2-1 requires 2 SRMs in Mode 5 (A is incorrect). B and C are incorrect as these are Mode 2 requirement. Additionally, the fuel bundle should be placed in original location per NCTL (D is correct).

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION COMMENTS: Could rewrite to have a full offload in progress and only SRM is where fuel is. This would make note b applicable and change answer to A.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 13 EXAM KEY MARCH 2009 The following plant conditions exist:

A loss of offsite power has occurred and DG-2 is the only source of power available RHR B system is tagged out for maintenance and RHR-P-2C has a shaft shear Efforts are being made to return RHR B to service but no source of RPV injection is currently available RPV level is -170 inches and trending down slow RPV pressure is being maintained 800 psig to 1000 psig and one SRV is currently opened A malfunction of both CIA programmers renders the continuous SRV pneumatic supply unavailable.

Based on the above, which of the following is correct?

A. Enter PPM 5.1.1 and PPM 5.6.1. When RPV level decreases to -183 inches enter PPM 5.1.3, as Emergency Depressurization of the RPV would be required.

B. Enter PPM 5.1.1 and PPM 5.1.3 as Emergency Depressurization of the RPV is now required.

C. Enter PPM 5.1.1. When RPV level reaches -201 inches enter PPM 5.1.3, as Emergency Depressurization of the RPV would be required.

D. Enter PPM 5.1.1 and ABN-CIA. Place control switches for all SRVs to the AUTO position.

ANSWER: B QUESTION TYPE: SRO Closed KA # & KA VALUE: 239002 2.4.6 Relief/Safety Valves. Knowledge of EOP mitigation strategies (3.7 / 4.7) 55.43.5

REFERENCE:

PPM 5.1.1 SOURCE: New LO: 8057 Given a list, identify the conditions that exist when continuous SRV nitrogen supply is unavailable.

RATING: H3 ATTACHMENT: None JUSTIFICATION: Entry into PPM 5.1.1 is required. PPM 5.1.3 would be entered when ED is required.

Entry into PPM 5.6.1 is not required as DG-2 is available. With Steam Cooling required take override in pressure leg and enter leg N. Leg N override states that if

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION one or more SRVs are used and SRV pneumatic supply becomes unavailable then ED is required (B is correct). A would be correct if block L-13 is answered incorrectly. C would be correct if Leg N were not entered. D could be an action taken to maximize the remaining CIA pressure.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 14 EXAM KEY MARCH 2009 Columbia is operating at 88% power with no equipment out of service. Due to a valving error coincident with a planned surveillance, the High Pressure Core Spray system receives an initiation signal.

Concerning the initiation of the HPCS System, which of the following is correct?

A. Reactor power would increase. ABN-POWER would be entered and CRO2 would check two Drywell pressure and two RPV level indicators and if no initiation parameter is met, would then secure HPCS-P-1 and close HPCS-V-4.

B. Reactor power would decrease. ABN-POWER would be entered and CRO2 would check two Drywell pressure and two RPV level indicators and if no initiation parameter is met, would then secure HPCS-P-1 and close HPCS-V-4.

C. There would be an increase in RPV level. ABN-LEVEL would be entered. CRO2 would check two RPV level indicators and when RPV Level is observed to be in normal operating band, CRO2 would then secure HPCS-P-1 and close HPCS-V-4.

D. There would be a decrease in Reactor power. ABN-POWER would be entered and CRO2 would check a Drywell pressure and a RPV level indicator and if no initiation parameter is met, CRO2 would then secure HPCS-P-1 and close HPCS-V-4.

ANSWER: B QUESTION TYPE: SRO Closed KA # & KA VALUE: 209002 A2.01 Ability to (a) predict the impacts of the following on High Pressure Core Spray System and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

System initiation (3.8 / 3.8) 55.43.5; 55.43.6

REFERENCE:

ABN-POWER pages 2, 4, 12; SD000174 pages 12 & 13 SOURCE: New LO: 11723 Describe the operational implications of the following concepts as they apply to the High Pressure Core Spray System: d. Inadvertent HPCS initiation RATING: H3 ATTACHMENT: None JUSTIFICATION: Inadvertent HPCS injection has been shown to cause a power drop and NOT a power increase. ABN-POWER is entered due to the HPCS initiation and directs

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION securing pump/valve closure on invalid signal. The bases and PPM 1.3.1 require 2 indicators be checked (2 Pressure/2 levels) B is correct. There is no entry into ABN-LEVEL given although level would go up (C is incorrect).

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 15 EXAM KEY MARCH 2009 Columbia is operating at full power with SGT-FN-1B1 running for containment venting per SOP-CN-CONT-VENT. A trip of both Reactor Feedwater Pumps occurs. All systems respond as designed.

Which of the following describes the Standby Gas Treatments response and which procedures are entered to mitigate the effects of the event?

A. SGT-FN-1B1 trips SGT-FN-1B2 auto starts SGT-V-1B (containment purge exhaust) was opened and now closes SGT-V-2B (Reactor Building intake) remains open, providing pressure control for the Reactor Building PPM 5.1.1, RPV Control, and ABN-FAZ are entered.

B. SGT-FN-1B1 trips SGT-V-1B (containment purge exhaust) was opened and now closes SGT-V-2B (Reactor Building intake) remains closed RB HVAC maintains pressure control for the Reactor Building PPM 5.1.1, RPV Control, PPM 5.3.1, Secondary Containment Control, and ABN-FAZ are entered.

C. SGT-FN-1B1 remains running SGT-FN-1B2 auto starts SGT-V-1B (containment purge exhaust) was opened and now closes SGT-V-2B (Reactor Building intake) was closed and now opens, providing pressure control for the Reactor Building PPM 5.1.1, RPV Control, is entered.

D. SGT-FN-1B1 remains running SGT-V-1B (containment purge exhaust) was opened and now closes SGT-V-2B (Reactor Building intake) was closed and now opens, providing pressure control for the Reactor Building PPM 5.1.1, RPV Control, and ABN-FAZ are entered.

ANSWER: A QUESTION TYPE: SRO Closed KA # & KA VALUE: 261000 A2.10 Ability to (a) predict the impacts of the following on Standby Gas Treatment System and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Low reactor water level (3.1 / 3.2) 55.43.4, 55.43.5

REFERENCE:

SD000144 Pages 7, 8, and 10 PPM 5.1.1 Entry Conditions; ABN-FAZ page 2; SOP-

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION SGT-START Pages 6 and 7 SOURCE: New LO: 5828 State the SGT system response to a FAZ signal. Include all major valves, heaters, and fans and their associated time delays. 8017 Given plant conditions, recognize an EOP entry condition(s) and enter the appropriate flow chart.

RATING: H2 ATTACHMENT: None JUSTIFICATION: A trip of both RFW pumps causes a -50 isolation (an A signal). PPM 5.1.1 and ABN-FAZ are entered. There would be no entry into PPM 5.3.1 (C is incorrect). Fan 1B1 trips and fan 1B2 auto starts (B and D are incorrect). SGT-V-2B remains open.

RB HVAC trips.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 16 EXAM KEY MARCH 2009 Columbia has just entered MODE 2 following a refueling outage. Per OSP-CRD-C701, the Control Rod Coupling Integrity surveillance, the first affected control rod that requires a coupling check, rod 18-51, is being withdrawn. During the coupling check, the ROD OVERTRAVEL annunciator (4.603.A7 1-8), is received.

Which of the following is correct concerning this alarm?

A. This alarm signifies that the control rod is stuck at position 48. Tech Spec 3.1.3 Action Statement A is entered. If another control rod is determined to be stuck Action Statement B is entered which requires Columbia to be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

B. This alarm signifies the control rod is not coupled. Entry into ABN-ROD is made which gives direction to insert the control rod to position 00 to accomplish recoupling. The control rod is then withdrawn to position 48 to verify coupling. This attempt is only allowed once.

C. This alarm signifies the control rod is not coupled. Tech Spec 3.1.3 Action Statement C is entered. The alarm response procedure will provide direction to attempt to recouple the control rod. This attempt is only allowed once.

D. This alarm signifies the control rod is not coupled. Entry into ABN-ROD is made which gives direction to insert the control rod fully within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and to disarmed the control rod within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ANSWER: C QUESTION TYPE: SRO Closed KA # & KA VALUE: 201003 A2.02 Ability to (a) predict the impacts of the following on the Control Rod And Drive Mechanism and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Uncoupled rod (3.7 / 3.8) 55.43.5; 55.43.2

REFERENCE:

4.603.A7 1-8, ABN-ROD entry conditions; TS 3.1.3 SOURCE: New LO: 10363 Given plant annunciation and indications, evaluate conditions for entry into ABN-ROD. 5219 Referencing Technical Specifications associated with the Control Rod Drive Mechanism and a set of plant conditions, determine as applicable the LCO, the action statement, and the appropriate bases.

RATING: H3

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION ATTACHMENT: Yes - Tech Spec 3.1.3 Pages 1, 2 and 3 JUSTIFICATION: If the annunciator is expected, which it is not, this is the action the CRO would take (A is incorrect). ABN-ROD does not have an entry for uncoupled rod (B is incorrect). ARP allows one attempt to recouple and then if not recoupled the TS 3.1.3 action C is entered, not ABN-ROD (D is incorrect). C is correct per the ARP.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 17 EXAM KEY MARCH 2009 A control rod withdrawal for start up is underway with power below the RSCS Low Power Setpoint (LPSP).

Control rod 30-19 is being withdrawn from position 00 to position 12. At position 10, CRO1 notes an XX indication and the DATA FAULT light illuminated.

Which of the following is correct?

The reed switch at position.....

A. 08 failed to open. Refer to ABN-RMCS and if unable to enter a substitute position, drive 30-19 full in and declare it inoperable per Tech Spec 3.1.3, Control Rod Operability.

B. 10 failed to close. Refer to ABN-RPIS. If unable to enter a substitute position, drive 30-19 full in, and declare it inoperable per Tech Spec 3.1.3, Control Rod Operability.

C. 08 failed to open. Refer to ABN-RPIS to insert a substitute value in RSCS and RWM.

D. 10 failed to close. Refer to ABN-RMCS to insert a substitute value in RSCS and RWM.

ANSWER: C QUESTION TYPE: SRO Closed KA # & KA VALUE: 214000 A2.01 Ability to (a) predict the impacts of the following on the Rod Position Information System and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Failed reed switches (3.1 / 3.3) 55.43.5; 55.43.2

REFERENCE:

SD000148 page 9 ABN-RPIS pages 2, 6, and 7 SOURCE: Bank Modified LO00194 LO: 7781 List the available rod position indications available on Panel P603 and PPCRS computer. 6708 Given plant annunciation and indications' evaluate conditions for entry into ABN-RPIS.

RATING: H2 ATTACHMENT: None JUSTIFICATION: XX indicates reed switch 08 failed to open and 2 positions are being sent (08 and

10) (B and D are incorrect). You would drive rod full in and declare the rod inoperable per TS if unable to insert a substitute position but not per ABN-RMCS (per ABN-RPIS) (A is incorrect). C is correct per ABN-RPIS.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 18 EXAM KEY MARCH 2009 The plant is operating at 100% power. B RHR was declared inoperable yesterday at 0800 because of a ground on RHR-P-2Bs motor. During an A RHR Operability test, RHR-V-4A, Suppression Pool suction valve, was closed, tripped on electrical overload mid-stroke, and was subsequently declared inoperable at 1200 today. Then at 1800 today, B RHR was declared operable.

Based on the above information, Columbia must be in MODE 3 no later than A. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 2000 today.

B. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 0200 tomorrow.

C. 7 days plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 0800 yesterday.

D. 7 days plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 1200 today.

ANSWER: D POST EXAM COMMENT - The answer key for this question was incorrect and the correct answer was changed from D to C.

QUESTION TYPE: SRO Closed KA # & KA VALUE: 226001 A2.11 Ability to (a) predict the impacts of the following on the RHR/LPCI:

Containment Spray Mode and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Motor operated valve failures (3.0 / 3.0) 55.43.2

REFERENCE:

TS 3.6.1.5-1; TS 3.6.1.3-1 & -2; TS 3.5.1-1, -2 & -3; TS 3.6.2.3-1 SOURCE: NEW LO: 5783 Referencing Columbias Technical Specifications associated with the RHR System and a set of plant conditions, determine as applicable the LSSS, the LCO, the action statement, and the bases.

RATING: H3 ATTACHMENT: Yes - TS 1.3-1 and 1.3-2. TS 3.6.1.5-1; TS 3.6.1.3-1 & -2 TS 3.5.1-1, -2 and -3; TS 3.6.2.3-1 JUSTIFICATION: At 0800 yesterday a 7 day clock started. At 1200 today the 7 day clock became a 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock (2 spray systems OOS). At 1800 the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock stopped and again became a 7 day clock but clock is started from first RHR system failure (B RHR ground) and not A RHR (RHR-V-4A failure). A is incorrect as it is for 2 trains OOS from 1200 today; B is incorrect as it is todays time (1800) plus 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. C is incorrect as it is 7 days from the first RHR failure and does not take into account that the completion times may be extended per TS section 1.3. D is correct.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 19 EXAM KEY MARCH 2009 During operation at 60% power, SM-7 is being powered from the Backup Transformer.

Due to a failure of the S-3 breaker to close, the S-3 breaker is declared inoperable.

Which of the following Technical Specifications, if any, should be entered?

A. No Tech Spec LCO is applicable B. Enter Tech Spec LCO 3.8.1A C. Enter Tech Spec LCO 3.8.1C D. Enter Tech Spec LCO 3.8.7A ANSWER: B QUESTION TYPE: SRO Closed KA # & KA VALUE: 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits (3.2 / 4.2) 55.43.2

REFERENCE:

TS 3.8.1, TS 3.8.7 and bases page 3.8.1-4 SOURCE: New LO: 6925 Identify the basis for and Technical Specification LCO RATING: H2 ATTACHMENT: TS 3.8.1 and TS 3.8.7 JUSTIFICATION: Per TS 3.8.1 bases, TR-S must be able to supply power to SM-4 and either SM-7 or SM-8. The question implies that the Startup Transformer can not be closed in on SM-8 (due to MOC switch problems on S-3 breaker) or SM-7 (TR-B is supplying SM-7 and there is no auto transfer from TR-B to TR-S). (B is correct).

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 20 EXAM KEY MARCH 2009 During the fuel shuffle in a refueling outage, as the Refueling Floor Supervisor, you observe a fuel bundle that doesnt seem to have the correct orientation. You review the NCTL and note the fuel bundles orientation is 180 degrees different from what the NCTL requires.

Which of the following is correct concerning this situation?

A. This is not considered to be a fuel loading error nor is it considered to be a reactivity event. The Refuel Floor Supervisor has the authority to correctly orientate the fuel bundle and will document the move on the NCTL.

B. This is considered to be a fuel loading error. The Refuel Floor Supervisor will correctly orientate the fuel bundle and document the move on the NCTL.

C. This is not considered to be a fuel loading error. This is considered to be a reactivity event which should be brought to managements attention.

D. This is considered to be a fuel loading error. The Reactivity Manager and the Shift Manager will determine how to resolve the error and must give permission to recommence the fuel shuffle.

ANSWER: C POST EXAM COMMENT - The answer key was changed to accept either answer C or D for this question.

QUESTION TYPE: SRO Closed KA # & KA VALUE: 2.1.42 Knowledge of new and spent fuel movement procedures (2.5 / 3.4) 55.43.7

REFERENCE:

PPM 6.3.2 Precaution and Limitation 5.25 page 15 SOURCE: New LO: 8816 Given copies of plant procedures locate and demonstrate an understanding of the procedural "prerequisites, precautions and limitations" (Refueling).

RATING: L3 ATTACHMENT: None JUSTIFICATION: Per PPM 6.3.2, the SM and Reactivity Manager are notified and will resolve error and give permission to recommence core alts (C is correct). The RFO does not have authority to resolve error alone (A is incorrect). Neither the CRS nor the Reactivity Manager alone gives permission to restart core alts (B and D are incorrect).

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 21 EXAM KEY MARCH 2009 Which of the following identifies the correct 10 CFR 20 occupational limit, the allowable dose limit increase, and approval for the task indicated?

A. Adult workers are limited to 5 rem TEDE with an increase to 25 Rem TEDE for life-saving activities when an Emergency Exposure Request is approved by the Emergency Director.

B. Declared pregnant woman is limited to 50 mrem TEDE with an increase to 10 Rem TEDE for protection of valuable property without the initiation of an Emergency Exposure Request.

C. Adult workers are limited to 5 rem TEDE with an increase to 25 Rem TEDE for life-saving activities when an Emergency Exposure Request is approved by the Radiological Emergency Manager.

D. An employed minor is limited to 0.1 rem TEDE with an increase to 25 rem TEDE for protection of valuable property when an Emergency Exposure Request is approved by the Emergency Director.

ANSWER: A QUESTION TYPE: SRO Closed KA # & KA VALUE: 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions (3.2 / 3.7) 55.43.4

REFERENCE:

PPM 13.2.1 Pages 4, 8, 9, 16 SOURCE: New LO: 11257 Knowledge of 10 CFR: 20 and related facility radiation control requirements.

RATING: L2 ATTACHMENT: None JUSTIFICATION: 10CFR20 limit is 5 rem with increase to 25 for lifesaving activities. ED approval is required - A is correct. B incorrect as a Emergency Exposure request IS required. C is incorrect as ED is required approval not the REM. D is incorrect as minor is limited to 1/10th of adult worker so it should be .5 not .1 rem.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 22 EXAM KEY MARCH 2009 Which of the following is correct concerning automatic Protective Action Recommendation (PARs) and a Site Area Emergency declaration?

A. Automatic PARs include evacuation of the Exclusion Area.

B. Automatic PARs include evacuation of the Columbia River.

C. Automatic PARs include sheltering all sections for a two mile radius and evacuation of affected sector 2-10 miles downwind.

D. There are no automatic Protective Action Recommendations associated with a Site Area Emergency declaration.

ANSWER: B QUESTION TYPE: SRO Closed KA # & KA VALUE: 2.4.44 Knowledge of emergency plan protective action recommendations (2.4 / 4.4) 55.43.5

REFERENCE:

Classification Notification Form #24075 Block 5c SOURCE: New LO: 8893 Identify the required PARs for each Emergency Classification.

RATING: L3 ATTACHMENT: None JUSTIFICATION: Per CNF, automatic PARs at SAE require Columbia River evacuation and not Exclusion area (B is correct and A and D are incorrect). Sheltering is required at a GE not a SAE (C is incorrect).

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 23 EXAM KEY MARCH 2009 BPA has contacted Columbia and requested a reduction in power to 85% for economic dispatch. During the downpower, a loss of the annunciators associated with H13-P601, H13-P602 and H13-P603 occurs. H13-P603.A7-1.1 ANNUNCIATOR 125 VDC LOSS is illuminated.

Which of the following is correct?

A. The required Reactor scram is made promptly and a continuous walk down of all plant parameters on H13-P601, P602 and P603 must be started. All operations not essential to safe plant operations and surveillance testing must be stopped. An Unusual Event is declared immediately.

B. The required controlled plant shutdown may commence immediately. A continuous walk down of H13-P601, P602 and P603 of scram parameters shall be performed during the plant shutdown. An Unusual Event is declared after 15 minutes if annunciation is not restored.

C. The plant downpower is stopped. An Unusual Event is not declared as annunciation on Bd. C is still active. Continuously monitor non-annunciated plant and scram parameters on H13-P601, P602 and P603.

D. The plant downpower is stopped. An Unusual Event is declared after 15 minutes if annunciation is not restored. Continuously monitor non-annunciated plant and scram parameters on H13-P601, P602 and P603.

ANSWER: D QUESTION TYPE: SRO Closed KA # & KA VALUE: 2.4.32 Knowledge of operator response to loss of all annunciators (3.6 / 4.0) 55.43.5

REFERENCE:

ABN-ANNUN Page 2 and 3; 4.P603.A7-1.1; PPM 13.1.1A page 122 (7.3.U.1 bases); OI-15 page 25 SOURCE: New LO: 9972 Describe the actions required to be performed promptly for a Loss of Control Room Annunciators and discuss the desired effect these actions will have.

RATING: L2 ATTACHMENT: Yes - 13.1.1 Att. 5.1 - box for 7.3.U.1 (UE associated with loss of annunciation)

JUSTIFICATION: There is no required scram or shutdown (A and B are incorrect); Even though the

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION UE (7.3.U.1) also includes Bd C, having the annunciators still active on that panel does not preclude the UE declaration. The Bases for this classification states a judgment call should be made by the ED with about 75% being the threshold.

Additionally, the ARP for P603.A7-1.1 ANNUNCIATOR 125 VDC LOSS requires PPM 13.1.1 be referenced for classification. An Unusual Event is required but 15 minutes is waited (A and C are incorrect). D is correct.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 24 EXAM KEY MARCH 2009 Columbia operating in MODE 1. Three hours ago SGT-FN-1A1 was tagged out for motor replacement. As the CRS, you receive a call from the Shift Support Supervisor, who informs you that the electricians have removed the power leads from SGT-FN-1B1 instead of from SGT-FN-1A1.

Which of the following Technical Specification actions, if any, is required?

A. Enter LCO 3.0.3 and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> take actions to be in MODE 2 within the next 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and MODE 4 within the next 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.

B. Return SGT-FN-1B1 to operable status within 7 days or be in MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

C. Run SGT-FN-1B2 to verify B SGT operability. SGT A is required to be operable in 7 days or be in MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

D. Both the A and the B SGT systems are still considered operable. No Tech Specs actions are applicable.

ANSWER: B QUESTION TYPE: SRO Closed KA # & KA VALUE: 2.2.36 Ability to analyze the effect of maintenance activities, such ass degraded power sources, on the status of limiting conditions for operations. (3.1 / 4.2) 55.43.2

REFERENCE:

TS 3.6.4.3-1 and -2 and bases pages 3.6.4.3-2 and -3 SOURCE: New LO: 9670 Given appropriate conditions, indications and copies of Technical Specifications, determine when an entry condition is met and interpret required Technical Specification actions from an analysis of plant conditions. (Containment)

RATING: H3 ATTACHMENT: Yes - TS 3.6.4.3-1 and -2 JUSTIFICATION: Reliance for SGT operability with one primary fan (SGT-FN-1B2) and one backup fan (SGT-FN-1A2) is not allowed per bases therefore one train has to be declared inoperable - B is correct and D is incorrect. A is incorrect as both SGT trains need to be inop for Condition D to apply. C is the time for one SGT and not restored within the 7 day timeframe of Condition A.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 25 EXAM KEY MARCH 2009 The plant was operating at 90% power with HPCS out of service for a motor replacement when a loss of both SM-1 & SM-2 occurred coincident with a failure of RCIC to start. Assume no operator actions are taken for this transient.

Which of the following is correct for these conditions?

A. PPM 1.10.1 requires an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report due to a reactor scram.

B. PPM 1.10.1 requires an 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report due to the RCIC failure.

C. GIH-9.1.3 requires that the CEO be notified in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

D. GIH-9.1.3 requires that the CEO be notified in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ANSWER: C QUESTION TYPE: SRO Closed KA # & KA VALUE: 2.1.14 Knowledge of criteria or condition that require plant-wide announcements, such as pump starts, reactor trips, mode change, etc. (3.1 / 3.1) 55.43.5

REFERENCE:

PPM 1.10.1 rev. 29, page 10 GIH-9.1.3 rev. 0 SOURCE: Bank - 2005 NRC Exam LO: 6086 State what information should be announced to the plant staff. 6011 With the Admin procedures available and given a specific event, determine the NRC notification requirements ands the reportability time limits.

RATING: H3 ATTACHMENT: Yes - PPM 1.10.1 Page 10 GIH 9.1.3 JUSTIFICATION: A is incorrect because the scram requires a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report. B is incorrect because it would require an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification. D is incorrect because GIH 9.1.3 requires a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notification of the CEO on an emergency classification of UE or greater. C is correct.