ML20209H628
| ML20209H628 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/25/1986 |
| From: | Munro J, Rogers T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20209H616 | List: |
| References | |
| 50-269-OL-86-01, 50-269-OL-86-1, NUDOCS 8609150291 | |
| Download: ML20209H628 (59) | |
Text
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p 4Kic UNITED STATES p oq'o NUCLEAR REGULATORY COMMISSION
[" , REGION 11 g j 101 MARIETTA STREET,N.W.
- t ATLANTA, GEORGI A 30323
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ENCLOSURE 1 EXAMINATION REPORT 269/0L-86-01 Facility Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: Oconee Nuclear Station Facility Docket Nos.: 50-260, 50-270 and 50-287 WrittenexaminationswereadmjnisteredattheOconeeNuclearStation.
Chief Examiner: ~,f .o, 7 T V(-
ThomasRogersf Date Signed Approved by: /k N 7 John F. Munro, Ac' ting Section Chief f!dT[l'$
Date Signed Summary:
Examinations on April 21, 1986 Two candidates were administed written re-examinations, both of whom passed.
8609150291 860902 PDR ADOCK 05000269 V PDR
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REPORT DETAILS
- 1. Facility Employees Contacted:
- Paul Stovall, Instructor
- Attended Exit Meeting
- 2. Examiner:
- Thomas Rogers
- Chief Examiner
- 3. Examination Review Meeting At the conclusion of the written examinations, the examiner provided Paul Stovall with a copy of the written examination and answer key for review.
The comments made by the facility technical reviewers are included as Enclosure 3 to this report, and the NRC Resolutions to these coments are listed below. The comments made by the facility Educational Specialist are not addressed, since they provide additional information for exam development only.
I a. SR0 Exam (1) Question 6.06 NRC Resolution: Coment noted; however, no change in the answer key is required.
(2) Question 6.16 NRC Resolution: Coment accepted. The answer key has been changed to require the additional responses for full credit.
(3) Question 7.11 NRC Resolution: Comment accepted in part. The procedure change made choice (a) to be correct in lieu of choice (d). The answer key has been changed accordingly.
(4) Question 7.14 NRC Resolution: Comment accepted. The answer key has been changed accordingly.
(5) Question 7.15 NRC Resolution: Comment accepted. The answer key has been changed accordingly.
, 1 ,,
Enclosure 1 5 (6) Question 7.28 NRC Resolution: Comment accepted. The answer key has been changed to accept a demonstration of knowledge that the seal return will automatically isolate on units 2 and 3. For full credit, however, the unit must be identified.
(7) Question 8.15 NRC Resolution: The examinees were verbally instructed during administration of the examination to provide Duke Power administrative limits.
(8) Question 8.21 NRC Resolution: Comment accepted. The answer key has been changed accordingly.
- 4. Exit Meeting The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
l
r ENCLOSURE 2 U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: OCONEE 1, 2&3 REACTOR TYPE: PWR-B&W177 DATE ADMINISTERED: 06/04/21 EXAMINER: TOM ROGERS APPLICANT: _________________________
INSTRUCTIONS TO APPLICANT:
Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 30 0 25 0
___1__0__ ___1_0 _ ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 30.00 25.00 PLANT SYSTEMS DESIGN, CONTROL, 6.
AND INSTRUMENTATION 30 25 0 PROCEDURES - NORMAL, ABNORMAL,
___1_00______1__0 ___________ ________ 7.
EMERGENCY AND RADIOLOGICAL CONTROL 30 0 25 00 ADMINISTRATIVE PROCEDURES,
___I__0 __ ___.'__ ___________ ________ 8.
CONDITIONS, AND LIMITATIONS 120.00 100.00 TOTALS FINAL GRADE _________________%
All work done on this examination is my own. I have neither S i ven not received aid.
PPLEC5UTI 5~5EUU5TURE~~~~~~~~~~~~~~
r
-5o THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2 QUESTION 5.01 (2.00)
Indicate how the following actions affect the cited rod worth (increase, decrease or no affect).
(a) Inserting a group 5 rod from 100% to 75%.
(b) Withdrawing an APSR from its fully inserted position to its 25%
withdrawn position.
(c) Increasing Tavs.(Any rod)
(d) Increasing the boron concentration. (Any rod).
QUESTION 5.02 ( .50)
A reactor that is prompt critical is also supercritical. TRUE or FALSE?
OUESTION 5.03 ( .50)
Omission of the reactivity associated with Samarium in a shutdown mars in calculation is conservative. TRUE or FALSE?
OUESTION 5.04 ( .50)
The rated power level of 2568 MWt includes the NWt contribution from the Reactor Coolant Pumps to the RCS. TRUE or FALSE?
DUESTION 5.05 (1.00)
What causes self actuated relief valves, such as the MSRVs, to reseat at lower pressures than they lift?
00ESTION 5.06 (1.00)
Explain how water gets in the air receiving tanks.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3 QUESTION 5.07 (1.00)
What two conditions ensure that the shutdown margin is within the limits during power operations?
QUESTION 5.08 (1.00)
Which of the four heat transfer regions in the OTSG has the~(a) highest heat transfer coefficient and (b) the lowest heat transfer coefficient?
GUESTION 5.09 (1.00)
Explain how increasing the OTSG 1evel increases the power level.
QUESTION 5.10 (1.00)
Explain how gas accumulation in the RCS can block reflux boiling.
QUESTION 5.11 (1.00)
What problems can occur due to baron precipitation during a LOCA?
OUESTION 5.12 (1.00)
Why should the primary demineralizers be bypassed prior to an addition of hydrazine to the RCS?.
GUESTION 5.13 (1.00)
Why is there a total gas limit on gases dissolved in the RCS?
GUESTION 5.14 (1.00)
What two isotopes in the fuel provide the largest contribution to the doppler coefficient?
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4 QUESTION 5.15 (1.00)
Explain why ' peak shortening" of the Doppler Coefficient Theory does not cause a decrease in neutron capture.
QUESTION 5.16 (1.00)
How does the average fuel temperature change over core life at 100% power?
Explain why-this change occurs.
QUESTION 5.17 (1.00)
By design, can the Moderator Temperature Coefficient at Oconee be positive?
Explain why or why not.
QUESTION 5.18 (1.00)
Indicate whether the following will dampen, promote, or have no affect on a xenon oscillation.
(a) Doppler coefficient.
(b) Positive moderator temperature coefficient.
QUESTION 5.19 (2.00)
(a) How does xenon worth change over core life?
(b) Give three reasons for the change.
QUESTION 5.20 (1.50)
Define the meaning of the following rod worths when used in reactivity calculations. Include power levels and positions of other rods, as appropriate, in your answer.
(a) Dropped rod worth.
(b) Ejected rod worth.
(c) Stuck rod worth.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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- 3. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 5 GUESTION 5.21 (1.50)
Describe the response of the SUR meter on a 10% stoup withdrawal from a suberitical condition until a new suberitical stable count rate is established. Include an explaination for the response.
QUESTION 5.22 (1.00)
What individual reactivity coefficient provides the highest contribution at EOL to the Power Deficit for each of the following power changes.
(a) 0% to 15% reactor power.
(b) 15% to 100% reactor power. ,
GUESTION 5.23 (1.00)
List four sources of gas that could accumulate in the RCS in the event of a LOCA.
QUESTION 5.24 (1.00)
List the four requirements necessary in order to establish natural circulation.
QUESTION 5.25 (1.00)
When an AC senerator is said to have a leading or lassing power factor, what is the 'leadin3 or lassins' in reference to?
OUESTION 5.26 (1.50)
What is the bases for stopping the reactor coolant pumps during a LOCA?
QUESTION 5.27 (1.00)
What is the change in reactivity associated with a change in Keff from 0.92 to 1.004?
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
- 5. THEORY OF NUCLEAR F0HER FLANT DPERATIGH, FLUIDS, AND PAGE 6 QUESTION 5.28 (1.00)
If reactor power increases from 1000 eps to 5000 eps in 30 seconds, what is the SUR?
(***** END OF CATEGORY 05 *****)
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 7 QUESTION 6.01 (1.00)
The ICS BTU Limit circuit receives its temperature input from
- a. a narrow ranse hot les RTD.
- b. a wide ranse hot let RTD.
- c. a narrow range cold les RTD.
- d. r wide ranse cold les RTD.
QUESTION 6.02 (1.00)
Which of the Engineered Safeguards System digital channels will not recieve an analos trip signal if there is a loss of power to the analos cabinets?
QUESTION 6.03 (1.00)
When can the high pressure injection and low pressure injection signals be blocked during a plant cooldown and depressurization?
OUESTION 6.04 (1.00)
What would be the consequences of a failed high Incore Thermocouple to the core Saturation Marsin Program calculation? Explain your answer.
QUESTION 6.05 (1.00)
Describe the interlock between the Component Cooling Water System and the Control Rod Drive Mechanism.
QUESTION 6.06 (1.00)
If a rod is dropped from a group of 8 rods which were initially withdrawn to 55%, how many assymnetric rod fault lights will come on?
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) l
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 8 QUESTION 6.07 (1.00)
What causes the " dead time" in the operation of a G-M detector? ,
GUESTION 6.08 '(1.00)
(a)What type of detector is used and (b)what type of radiation is monitored at the air ejector off gas?
GUESTION 6.09 (1.00)
During a plant startup to 100% power, when would the IR SUR Rod Withdrawal Inhibits be automatically bypassed? Include signal source and logic.
QUESTION 6.10 (1.00)
Which of the power range channels may be used as inputs to the ICS?
QUESTION 6.11 (1.00)
List two different systems whose pumps may be used to fill the Fuel Transfer Canal.
QUESTION 6.12 (1.00)
If the Main Feed Pump Anticipatory Reactor Trip failed to trip the reactor on a loss of both MFPs, what two other automatic RPS trips would likely trip the reactor?
QUESTION 6.13 (1.00)
Describe all conditions that will cause a Unit 2 Reactor Coolant Pump seal return valve to automatically close.
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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, 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 9 1
, QUESTION 6.14 (2.00) i List all automatic actions that occur from a Switchyard Isolation Signal. !
)
i !
QUESTION 6.15 (1.50)
Explain what the following indications mean from a Vital Inverter Sync Verification Indicator Lamp.
- a. Lamp is blinking.
- b. Lamp is on continuously at half brightness with inverter voltase l normal.
- c. Lamp off with inverter in service.
QUESTION 6.16 (2.00)
~~(a) List the protective trips for the SSF Diesel Generator.
(b) Which of the trips are in effect (not bypassed) in the Emergency Mode?
QUESTION 6.17 ( .50).
After a trip causing MSRV actuation, at what steam pressure should all MSRVs be reseated?
GUESTION 6.18 (1.50)
Explain how the Instrument Air pr. essure is maintained with an air compressor selected for ' BASE *. Setpoints required.
OUESTION 6.19 (1.00)
What conditions are necessary to cause the Emergency Feedwater System to automatically control OTSG level at 240 inches?
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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- 6. PLAdT SYSTEhS DESIGN, CONiROLr AND INSfkUMENTATION PAGE 19 QUESTION 6.20 (1.00)
What does a magenta alarm state indicate on the Safety Parameter Display System?
QUESTION 6.21 (1.00)
Where is the Feedwater Pump Seal Injection Sump Pump water fiormally pumped to?
QUESTION 6.22 (1.50)
List three different examples of when you would use the Rod Control Auxiliary Power Supply.
QUESTION 6.23 (2.00)
List eight Westinghouse Reactor Coolant Pump start interlocks.
QUESTION 6.24 (1.50)
List the normal and all backup cooling water systems that can be used to -
supply cooling water to the HPI pump motor bearings. ,
1 QUESTION 6.25 (1.50)
Name two different LPSW System loads for each of the following locations:
(a) Turbine Building (b) Aux Building -
(c) Reactor Building
{ (***** END OF CATEGORY 06 *****)
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_ . _ - . _ _ _ _ . . _ . - _ . ~ ._ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ .
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11
~~~~R E5i6C55IEAL 55sTR5L'~~~~~~~~~~~~~~~~~~~~~~~
OUESTION 7.01 ( .50)
MD EFWP4 should not take suction from the hotwell without first breaking condenser vacuun. TRUE or FALSE?
QUESTION 7.02 (1.00)
How is CC-8 reopened in recovery from a sustained loss of Instrument Air to the valve?
QUESTION 7.03 (1.50)
During a controlled shutdown due to a SG tube leak, when are you required to trip the reactor and turbine if the tube leak continued to degrade?
GUESTION 7.04 (1.00)
What operator action is required if the turbine is found to not have tripped during verification following a reactor trip?
00ESTION 7.05 (1.00)
How is a SG causins excessive heat transfer identified?
OUESTION 7.06 (1.00)
During a Loss of Heat Transfer, when SG feed cannot be restored and HPI is manually initiated, what should be done if RC-4(PORV Block Valve) was shut and could not be reopened?
QUESTION 7.07 (1.50)
How is ES Channels 1 & 2 actuation verified?
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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ENCLOSURE 2 U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: OCONEE 1r 2&3 REACTOR TYPE: PWR-98W177 DATE ADMINISTERED: 86/04/21 EXAMINER: TOM ROGERS APPLICANT: _________________________
INSTRUCTIONS TO APPLICANT!
Use separate pcPer for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the ensnination starts.
% OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 30 0 00
-- I 0--- I I__
_'5 -------_--_ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS
--30I00-__ -- 25 0 I-0 --------_-_ ________ 6. PLANT SYSTEMS DESIGNr CONTROL.
AND INSTRUMENTATION
--30I 00 --- --25I-0 0
_------ .-______ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 30.00 25.00 ADMINISTRATIVE PROCEDURES,
------ ----------- -------- 8.
120.00 100.00 TOTALS FINAL GRADE _________________%
All work done on this enamination is my own. I have neither given nor received aid.
~~~~~~~~~~~~~~
hPPL5C5bTI5~556UbiURE
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& ' y, o REGION il l 3 -$ 101 M ARIETTA STREET, N.W., SulTE 2900 )
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATIONr FLUIDSr AND PAGE 2 QUESTION 5.01 (2.00)
Indicate how the following actions affect the cited rod worth (increaser decrease or no affect).
(a) Insertins a group 5, rod from 100% to 75%.
(b) Withdrawins an APSR from its fully inserted position to its 25%
withdrawn position.
(c) Increasing Tavs.(Any rod)
(d) Increasing the boron concentration. (Any tod).
QUESTION 5.02 ( .50)
A reactor that is prompt critical is also supercritical. TRUE or FALSE?
GUESTION 5.03 ( .50)
Omission of the. reactivity associated with Samarium in a shutdown margin calculation is' conservative. TRUE or FALSE?
GUESTION 5.04 ( .50)
The rated power level of 2568 MWt includes the MWt-contribution from the Reactor Coolant Pumps to the RCS. TRUE or FALSE?
QUESTION 5.05 (1.0d>
What causes self actuated relief valves, such as the MSRVsr to reseat at lower pressures than they lift?
QUESTION 5.06 (1.00)
Explain how water sets in the air receiving tanks.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDSr AND PAGE ____ ______________________________________
QUESTION 5.07 (1.00)
What two conditions ensure that the shutdown margin is within the limits during power operations?
GUESTION 5.08 (1.00)
Which of the four heat transfer regions in the OTSG has the (a) highest heat transfer coefficient and (b) the lowest heat transfer coefficient?
OUESTION 5.09 (1.00)
Explain how increasing the OTSG level increases the power level.
QUESTION 5.10 (1.00)
Explain how gas accumulation in the RCS can block reflux boiling.
QUESTION 5.11 (1.00)
What problems can occur due to boron precipitation during a LOCA?
QUESTION 5.12 (1.00)
Why should the primary deminerali ors be bypassed prior to an addition of hydrazine to the RCS?.
QUESTION 5.13 (1.00)
Why is there a total gas limit on gases dissolved in the RCS?
l QUESTION 5.14 (1.00)
What two isotopes in the fuel provide the largest contribution to the doppler coefficient?
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4 QUESTION 5.15 (1.00)
Explain why ' peak shortening' of the Doppler Coefficient Theory does not cause a decrease in neutron capture.
QUESTION 5.16 (1.00)
How does the average fuel temperature change over core life at 100% power?
Explain why this change occurs.
QUESTION 5.17 (1.00)
By design, can the Moderator Temperature Coefficient at Oconee be positive?
Explain why or why not.
QUESTION 5.18 (1.00)
Indicate whether the following will dampen, promoter or have no affect on a xenon oscillation.
(a) Doppler coefficient.
(b) Positive moderator temperature coefficient.
QUESTION 5.19 (2.00)
(a) How does xenon worth change over core life?
(b) Give three reasons for the change.
QUESTION 5.20 (1.50)
Define the meaning of the following rod worths when used in reactivity calculations. Include power levels and positions of other rods, as appropriater in your answer.
(a) Dropped rod worth.
(b) Ejected red worth.
(c) Stuck tod worth.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 5 QUESTION 5.21 (1.50)
Describe the response of the SUR meter on a 10% group withdrawal from a suberitical condition until a new suberitical stable count rate is established. Include an explaination for the response.
QUESTION 5.22 (1.00)
What individual reactivity coefficient provides the highest contribution at EOL to the Power Deficit for each of the following power changes.
(a) 0% to 15% reactor power.
(b) 15% to 100% reactor power.
QUESTION 5.23 (1.00)
List four sources of gas that could accumulate in the RCS in the event of a LOCA.
QUESTION 5.24 (1.00)
List the four requirements necessary in order to establish natural circulation.
QUESTION 5.25 (1.00)
When an AC generator is said to have a leading or lagging power factor, what is the ' leading or laggins' in reference to?
OUESTION 5.26 (1.50)
What is the bases for stopping the reactor coolant pumps during a LOCA?
i GUESTION 5.27 (1.00)
What is the change in reactivity associated with a change in Keff from 0.92 to 1.004?
I i (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6 QUESTION 5.28 (1.00)
If reactor power increases from 1000 eps to 5000 cps in 30 seconds, what is the SUR?
(***** END OF CATEGORY 05 *****)
gd K800 UNITED STATES NUCLEAR RE2ULATORY COXMISSION l'
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 7-GUESTION 6.01 (1.00)
The ICS BTU Limit circuit receives its temperature input from
- a. a narrow ranse hot les RTD.
- b. a wide ranse hot let RTD.
- c. a narrow ratise cold les RTD.
- d. a wide ranse cold les RTD.
QUESTION 6.02 (1.00)
Which of the Engineered Safeguards System digital channels will not recieve an analos trip signal if there is a loss of power to the analos cabinets?
OUESTION 6.03 (1.00)
When can the high pressure injection and low pressure injection signals be blocked during a plant cooldown and depressurization?
OUESTION 6.04 (1.00)
What would be the consequences of a failed high Incore Thermocouple to the core Saturation Marsin Program calculation? Explain your answer.
QUESTION 6.05 (1.00)
Describe the interlock between the Component Coclins Water System and the Control Rod Drive Mechanism.
GUESTION 6.06 (1.00)
If a rod in dropped from a group of 8 rods which were initially withdrawn to 55%, how many assymmetric rod fault lights will come on?
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 8 QUESTION 6.07 (1.00)
What causes the ' dead time" in the operation of a G-M detector?
DUESTION 6.08 (1.00)
(a)What type of detector is used and (b)what type of radiation is monitored at the air ejector off sas?
GUESTION 6.09 (1.00)
During a plant startup to 100% power, when would the IR SUR Rod Withdrawal Inhibits be automatically bypassed? Include signal source and logic.
QUESTION 6.10 (*.00)
Which of the power ranse channels may be used as inputs to the ICS?
OUESTION 6.11 (1.00) 1 List two different systems whose pumps may be used to fill the Fuel l
Transfer Canal.
I GUESTION 6.12 (1.00)
If the Main Feed Pump Anticipatory Reactor Trip failed to trip the reactor on a loss of both MFPs, what two other automatic RPS trips would likely trip the reactor?
t
, OUESTION 6.13 (1.00) 1 Describe all conditions that will cause a Unit 2 Reactor Coolant Pump seal
, return valve to automatically close.
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 9 QUESTION 6.14 (2.00)
List all automatic actions that occur from a Switchyard Isolation Signal.
QUESTION 6.15 (1.50)
Explain what the following indications mean from a Vital Inverter Sync Verification Indicator Lamp.
- a. Lamp is blinkin3+
- b. Lamp is on continuously at half brightness with inverter voltage normal.
- c. Lamp off with inverter in service.
QUESTION 6.16 (2.00)
~~(a) List the protective trips for the SSF Diesel Generator.
(b) Which of the trips are in effect (not bypassed) in the Emergency Mode?
OUESTION 6.17 ( .50)
After a trip causing MSRV actuation, at what steam pressure should all MSRVs be reseated?
OVESTION 6.10 (1.50)
Explain how the Instrument Air pressure is maintained with an air compressor selected for ' BASE *. Setpoints required.
QUESTION 6.19 (1.00)
What conditions are necessary to cause the Emergency Feedwater System to automatically control OTSG 1evel at 240 inches?
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 10 GUESTION 6.20 (1.00)
What does a magenta alarn state indicate on the Safety Parameter Display System?
OUESTION 6.21 (1.00)
Where is the Feedwater Pump Seal Injection Sump Pump water normally pumped to?
QUESTION 6.22 (1.50)
List-three different examples of when you would use the Rod Control Auxiliary Power Supply.
QUESTION 6.23 (2.00)
List eight Westinghcuse Reactor Coolant Pump start interlocks.
QUESTION 6.24 (1.50)
List the normal and all backup cooling water systems that can be used to supply cooling water to the HPI pump motor bearings.
QUESTION 6.25 (1.50)
Name two different LPSW System loads for each of the following locations
- i (a) Turbine Building (b) Au:: Building (c) Reactor Building 1
(***** END OF CATEGORY 06 *****)
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GUESTION 7.01 ( .50)
MD EFWPs should not take suction from the hotwell without first breaking condenser vacuum. TRUE or FALSE?
OUESTION 7.02 (1.00)
How is CC-8 reopened in recovery from a sustained loss of Instrument Air to the valve?
OUESTION 7.03 (1.50)
During a controlled shutdown due to a SG tube leak, when are you required to trip the reactor and turbine if the tube leak continued to degrade?
QUESTION 7.04 (1.00)
What operator action is required if the turbine is found to not have tripped during verification following-a reactor trip?
OUESTION 7.05 (1.00)
How is a SG causin3 excessive heat transfer identified?
QUESTION 7.06 (1.00)
During a Loss of Heat Transfer, when SG feed cannot be restored and HPI is manually initiated, what should be done if RC-4(PORV Block Valve) was shut and could not be reopened?
QUESTION 7.07 (1.50)
How is ES Channels 1 & 2 actuation verified?
(r**** CATEGORY 07 CONTINUED ON NEXT PAGE xxxxx)
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 12 l
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1 i QUESTION 7.08 (1.00)
During a LOCA with ES actuated, what is the Reactor Coolant Pump trip criteria?
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1 QUESTION 7.09 (1.00)
What criteria is used to secure Emergency Boration from the BWST in the ;
j Unanticipated Nuclear Power Production procedure?
GUESTION 7.10 (1.00)
How is feedwater supplied to the SGs during a Blackout if the TD EFWP j is not available?
i 00ESTION 7 11 (1.00)
If a sustained loss of MFB power occurs, followed by ES Channel 1 &2 i actuation, the operator should ______, if a ' LOAD SHED' does not occur.
1 i a. manually secure loads from the main control board i
3
- b. dispatch an operator to the applicable switchgear to open load breakers
- c. reset the ES actuation signal from the main control board .
! d. manually initiate ' LOAD SHED' on ES Channels 1 &2 i
- QUESTION 7.12 (1.50) t
- List three methods to eliminate voids in the Reactor Coolant System.
i GUESTION 7.13 ( .50)
What is the maximum cooldown rate during a natural circulation cooldown?
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(r***x CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 13
~~~~ Rd6EULUU5 EEL U5UTR6L~~~~~~~~~~~~~~~~~~~~~~~~
OUESTION 7.14 (1.00)
When is High Pressure Injection seal flow required to all RC pumps for Units 1,2, and 3? Setpoints required.
QUESTION 7.15 (1.00)
Why is there a minimum level and maximum pressure in the LDST?
OUESTION 7.16 ( .50)
What is the maximum LPI pump run time.without indicated flow?
DUESTION 7.17 ( .50)
What is the bases for the 3000 spm per LPI header while in the recircula-tion mode?
OUESTION 7.10 (1.00)
How is it determined that venting of nitrogen from the Pressurizer is complete when forming a Pressurizer bubble?
QUESTION 7.19 (1.00)
What affect on your body would a 70 Rem acute whole body dose most likely have?
OUESTION 7.20 (1.00)
How do you check the alert setpoint of a Los Ratemeter radiation instro-ment?
M OUESTION 7.21 (1.00)
When is generator operation restricted to the envelope of Figure 7.21?
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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- 7. PROCEDURES - NORMALr ABNORMAL, EMERGENCY AND PAGE 14
- -~~-----------------~~~~
~~~~R 5Di5L55iEAt 55sTR5L QUESTION 7.22 (1.00)
List two meterological conditions that would cause you to postpone a Gaseous Haste Decay Tank release.
QUESTION 7.23 ( .50)
What is the maximum number of Units that can perform a Reactor Building release at one time?
OUESTION 7.24 (1.50)
List the basic steps required to per form a Latch and Alignment of a regulating rod group.
QUESTION 7.25 (1.00)
List four different means to minimize internal radiation exposure.
QUESTION 7.26 (1.00)
List four checks an operator should make prior to using a portable radiation monitoring instrument.
QUESTION 7.27 (1.50)
Describe the Reactor Coolant Pump consecutive starting limits for a pump that has not been run for a day.
QUESTION 7.28 (1.00)
, After a loss of CC and HPI to the Reactor Coolant Pumps, what must
- be done prior to reestablishing Component Cooling and the starting of
- an HPI pump?
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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- 7. PAGE 15
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QUESTION 7 29 (1.00)
When-the body of a controlling procedure refers to another procedurer when can the initial procedure be continued?
00ESTION 7.30 (1,00)
What restrictions are applied to allow use of the Reactor Trip Recovery I procedure for a plant startup once the cause of the trip has been determined and remedied? '
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(***** END OF CATEGORY 07 **?tra)
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 16 GUESTION 8.01 (1.00)
Which of the following is the maximum percentage of scale reading on a pocket dosimeter that is allowable prior to use?
- a. 50%
- b. 60%
- c. 70%
- d. 80%
QUESTION 8.02 (1.00)
Which of the followins is the contamination limit for unconditional release of personal clothing, body surfaces, and hand-held items?
- a. 200 cpm above background
- b. 150 cpm above background
- c. 100 cpm above background
- d. 50 cpm above background QUESTION 8.03 (1.00)
Which of the followins is the maximum allowable background count rate when usins a frisker?
- a. 420 cpm
- b. 400 cpm
- c. 350 cpm
- d. 240 cpm (xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE *****)
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 17 00ESTION 8.04 (1.00)
After initial verification of the working copy of a procedure against the control copy, how often must it be re-verified?
- a. Every 3 days
- b. Every 7 days
- c. Every 14 days
- d. Every 30 days GUESTION 8.05 (1.00)
If the specified surveillance frequency of a piece of equipment is weekly, what is the maximum allowable interval between surveillances?
- a. 8 days
- b. 10 days
- c. 12 days
- d. 14 days GUESTION 0.06 (1.00)
Which of the following is the minimum fire brigade manning requirements?
- a. 7 members, excluding 4 members of minimum operatin3 shift ,
- b. 6 members, excluding 3 members of minimum operating shift
- c. 5 members, excluding 4 members of minimum operating shift
- d. 5 members, excludins 3 members of minimum operating shift
- e. 6 members, excluding 2 members of minimum operating shift
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 18 QUESTION 8.07 (1.00)
To which of the followins locations does the Red Phone in the Control Room connect?
- a. NRC, ReS i on II, Atlanta, GA
- b. NRC, Bethesda, MD
% c. State of SC, Columbia, SC
- d. INPO, Atlanta, CA
- e. NRC, Resident Inspector's Office QUESTION 8.08 (1.50)
Indicate whether the following statements concerning tassins are TRUE or FALSE.
- a. If more than one Supervisor is workins independently on a piece of equipment, then one Supervisor will be assigned responsibilty and the Red Tag will be issued in his name. .(0.5)
- b. In areas where heat seneration and/or moisture may be a possible problem, wire may be used to attach Red Tass to equipment. (0.5)
- c. The stuu is NOT to be removed until after the Red Tag is placed on the equipment. (0.5)
QUESTION 8.09 (1.50)
Indicate whether the followins statements concerning the duties of the SRO in the Control Room are TRUE or FALSE.
- a. May provide relief for Control Room operators. (0.5)
! b. Becomes the reader of EOP should its use be required. (0.5)
- c. May leave the control room if the Unit is below 200 degrees F. (0.5) i
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
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- 8. AbtjINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 19 GUESTION 8.10 (1.00)
FILL IN THE BLANKS When the RCS is in a condition with pressure above _______ psis both CFT's shall be operable with a minimum level of _______ feet, a mini-mum concentration of borated water of _______ ppm boron, and a pres-sure of _______ psi 3+
QUESTION 8.11 (1.00)
(a) What is the maximum time interval that the reactor can be operated at 101.0%?
(b) Where is this limit stated?
QUESTION 8.12 (1.00)
There are two Safety Limit Curves for each Unit. What are the axes on EACH of these curves?
QUESTION 8.13 (1.00)
According to the Technical Specifications, what temperature indications are used to determine RCS cooldown rates? Also indicate under what conditions each is used.
QUESTION 8.14 (1.50)
Technical Specification 3.1.6.8 states that when the reactor is above 2%
power, two reactor coolant leak detection systems of different operating principles shall be operable. List three different' leak detection princi-ples that meets this requirement.
(**xx* CATEGORY 08 CONTINUED ON NEXT PAGE **xxx)
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 20 QUESTION 8.15 (1.00)
What are the maximum allowable non-emergency whole body dose equivalents for an employee with a completed NRC4 for the followin3 time periods?
- a. In any calendar quarter (0.5)
- b. In any calendar year (0.5)
QUESTION 8.16 (1.00)
What are the TWO relocation areas for plant personnel should the plant site be evacuated?
00ESTION 8.17 ( .50)
If a contaminated, injured person needs immediate medical attention, to where should he/she be transported?
DUESTION 8.18 (1.50)
List FIVE locations / teams / centers that the Control Room may communicate with using the Emergency Radio System. Note: Redundant locations / teams /
center only count as one, i.e., Fire Team #1 and Fire Team 42.
QUESTION 8.19 (1.00)
- a. When in a Limiting Condition for Operations (LCO) that requires a plant shutdown, what is the maximum time that an evaluation to determine whether the LCO can be met can last before starting shutdown? (0.5)
- b. For a unit shutdown required by an LCO, what is the minimum shutdown rate? (0.5)
GUESTION 8.20 (1.50)
What TWO requirements are necessary to deviate from the sequence of sequentially numbered steps in an operating procedure?
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONSr AND LIMITATIONS PAGE 21 GUESTION 8.21 (1.00)
List the conditions that determine the reactor is in Hot Shutdown.
QUESTION 8.22 (1.00)
What transient / accident is considered in the bases for determining the mar.imum secondary system activity?
OUESTION 8.23 (1.00)
What is the bases of the Reactor Building Hydrogen Purge System's operability requirements?
QUESTION 8.24 (1.50)
What is the Technical Specification minimum operating shift requirements with all units operating at full power?
DUESTION 8.25 (1.00)
When a system, subsytem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power' source is inoperabler it may be consid-ered operable for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided two conditions are met. List these TWO conditions.
QUESTION 8.26 (1.50)
For operation above 80% power, give the minimum incore instrumentation for axial imbalance measurements.
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QUESTION 8.27 (1.00)
What actions, according to Technical Specifications, must be taken in the event that a sprinkler system in a safety related area is declared inoperable?
(***** END OF CATEGORY 08 *****)
(************* END OF EXAMINATION ***************)
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. ENCLOSURE 4.10 4
GUIDELINES FOR GENERATOR OPERATION AT REDUCED LOAD
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EQUATION SHEET Where og a m2 .
( dens i ty)g ( vel oci ty) g ( a rea ) g = ( den s i ty )2 ( vel oc i ty )2 ( a re a )2 KE = mv 2 PE = agh peg + keg +PgVg = PE2+KE 2+P Y22 where V = specific
~7 volume P = Pressure Q = icp(Tout.Tg,) Q = UA (T,y,-Tsta) Q = ilhg.h2 I P = P,10(SUR)(t) p . p,,t/T SUR = 26.06 T = (B-p)t 1 P del ta K = (K,gg-1)/K,gg CRg (1-K,ggg) = CR 2 II-Keff2) CR = S/(1.K,gy)
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ll-Keff2I Keff
! decay constant = In (2) = 0.693 A = A ,e-(decay constant)s(t) t t 1/2 1/2 Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 1010 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 ft3 = 7.48 gallons I hp = 2.54 x 10 3 Btu /hr Density =62.4lbg/ft 3 1 MW = 3.41 x 106 Btu /hr Density = 1 pm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbe Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 f t-lbm/lbf-sec 2 C
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Specific volume 1emp, AI*
Set Sai Sat
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E f *) f 0.00 1075.8 0.0000 2.1877 2.1877 32 0 0s854 001602 '3306 10.75.8 3.02 1074.1 1077.1 0.0061 2.1709 2.1770 35 0.09995 0.01602 2947 8 03 1071.3 1079.3 0.0162 2.1435 2.1597 40 0 12170 0 01602 2444 0.01602 20 % 4 13.06 1068 4 1081.5 0.0262 2.1167 2.1429 45 0.14752 0.17bil 0.01603 1703.2 18.07 1065.6 1083.7 0.0%I 2.0903 2.1264 50 12061 28.06 1059.9 1088.0 0.0555 2.0393 2.0948 60 0.2%) 0 01604 0.01606 867.9 38.04 1054.3 1092.3 0.0745 1.9902 2.0647 70 0.M31 0.0160li 6331 48.02 1048.6 1096.6 0.0932 1.9428 2.0%0 SO 0.5069 0.01610 468.0 57.99 1042.9 1100.9 0.1115 1.8972 2.0087 90 0.6982 350 4 67.97 1037.2 1105.2 0.1295 1.8531 1.9826 100 0.9492 0.01613 265 4 77.94 1031.6 1109.5 0.1417 1.8106 1.9577 110 1.2748 0.01617 203.27 87.92 1025.8 1113.7 0.1645 1.7694 1.9339 120 1.6924 0.01620 0 01625 157.34 97.90 1020.0 1117.9 0.1816 1.7296 1.9112 130 2.2225 107.89 1014.1 1122.0 0.1984 1.6910 1.8894 140 2.8886 0.01629 123.01 0.01634 97.07 117.89 1008.2 1126.1 0.2149 I.6537 1.8685 150 3.118 77.29 127.89 1002.3 l 130.2 0.2311 1.6174 1.8485 160 4.741 0.01639 0.01645 62.06 137.90 996.3 1134.2 0.2472 1.5822 1.8293 170 5.992 0.01651 50.23 147.92 990.2 1138.1 0.2630 1.5480 1.8109 180 7.510 0.01657 40 96 157.95 984.1 1142.0 0.2785 1.5147 1.7932 190 9.339 0.01663 33.64 167.99 977.9 1145.9 0.2938 f.4824 1.7762 200 11.526 27.82 178.05 971.6 1149.7 0.3090 1.4508 1.7598 210 14.123 0.01670 26.80 180.07 970.3 1850 4 0.3120 1.4446 1.7566 212 14.6 % 0.01672 0.01677 23.15 188.13 965.2 1153.4 0.3239 1.4201 1.7440 220 17.186 19.382 196.23 958.8 1157.0 0.3387 1.3901 1.7288 230 20.780 0.01684 0.01692 16.323 208.34 952.2 1160.5 0.3531 1.3609 f.7140 1 240 24.% 9 l
13.821 216.48 945.5 1164 0 0.3675 1.3323 1.6998 250 29 825 0.01700 0.01709 Il.763 228.64 9 38.7 1167.3 0.3817 l.3043 l.6860 260 35 429 10.061 236.84 931.8 1170.6 0.3958 1.2769 l.6727 270 41.858 0.01717 8.645 249.06 924.7 1173.8 0.4096 1.2501 1.6597 280 49.203 0.01726 7.461 259.31 917.5 1876.8 0.4234 1.2238 I.6472 290 57.556 0.01735 6.466 269.59 910.1 1179.7 0 4369 1.1980 1.6350 300 67.013 0.01745 5.626 279.92 902.6 1882.5 0.4504 1.1727 1.6231 310 77.68 0.01755 4.914 290.28 894.9 1185.2 0.4637 1.1478 1.6115 320 89 66 0.01765 4.307 300.68 887.0 1187.7 0.4769 1.1233 1.6002 330 103.06 0.01776 311.13 879.0 1190.1 0.4900 1.0992 1.5891 340 118 01 0.01787 3.788 j
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- F Sai Sai Sat Sai Sai Sat liquid vapor, liquid Esar tapor liquid Esar ,,po,
- r *, *, A, A. A, s, s, s, 350 134.63 0.01799 3.342 321.63 870 7 1192.3 0.5029 1.0754 1.5783 360 153 04 0 01811 2 957 332.18 852.2 1194 4 0.5158 1.0519 1.5677 370 173.37 0 01823 2.625 342.79 853 5 1196.3 0.5286 1.0287 1.5573 380 195.77 0 01836 2 335 353 45 844 6 1898.1 0.5413 1.0059 1.5471 390 220.37 0 01850 2.0836 364.17 8354 1199.6 0.5539 0.9832 1.5371 400 247.31 0 01864 1.8633 374 97 826 0 1201.0 0.5664 0.9608 1.5272 410 276.75 0 01878 1.6700 385 83 816.3 1202.1 0.5788 0.9386 I.5174 420 308.83 0 01894 1.5000 396 77 806.3 1203.1 0.5912 0.9166 1.5078 430 343.72 0.01910 1.3499 407.79 796 0 1203 8 0.6035 0.8947 1.4982 440 381.59 0.01926 1.2171 418.90 785 4 1204.3 0.6158 0.8730 1.4887 450 422.6 0.0194 1.0993 4301 774.5 1204.6 0.6280 0.8513 1.4793 460 466.9 0 01 % 0.9944 441.4 763.2 1204 6 0.6402 0.8298 1.4700 470 514.7 0 0198 0.9009 452 8 bl.5 1204.3 0.6523 0.8083 1.4606 480 566.1 0.0200 0 8172 464 4 739 4 1203.7 0.6645 0 7868 l.4513 490 621.4 0.0202 0.7423 476 0 726 8 1202It 0 6766 0 7653 1.4419 500 680.8 0 0204 0.6749 487.8 713 9 1201.7 0.6887 0 7438 1.4325 520 812.4 0 0209 0.5594 511.9 686 4 l 195.2 0.7130 0.7006 1.4136 540 962.5 0 0215 0 4649 536 6 656.6 l 193.2 0.7374 0.6568 1.3942 56Q 1133.1 0.0221 0.3868 562.2 624.2 1886 4 0 7621 0.6121 1.3742 ,
580 1325.8 0 0228 0 3217 588.9 588 4 I177.3 0.7872 0.5659 1.3532 600 1542.9 0 0236 0.2668 610.0 548.5 1165.5 0.8131 0.5176 1.3307 620 1786 6 0.0247 0.2201 646.7 503 6 1150.3 0 8398 0 4664 1.3062 640 2059.7 0 0260 0.1798 678.6 452.0 1I30.5 0.8679 0 4110 1.2789 660 2365 4 0 0278 0.1442 714.2 390.2 1104.4 0.8987 0.3485 1.2472 l 680 27081 0 0305 0.1115 757.3 309.9 1067.2 0.9351 0.2719 1.2071
! 700 3093.7 0 0369 0.0761 823.3 172.1 995.4 0.9905 0.1484 1.1389 l
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,,po, 3,q , g r o e, e, A, h, h, s, s, s, 1.0 101.74 0.01614 333.6 1036.3 1106.0. 0.1326 1.84 % 1.9782 2.0 126.06 0.0162) 173.73 93.99. 69.70 1022.2 t i l6.2 0.1749 1.7451 1.9200 3.0 141.46 0.01630 l18 71 109.37 1013.2 1122.6 0.2008 1.6855 1.8863 40 152.97 0016k 90.63 120 86 10064 1127.3 0.2198 I.6427 5.0 1.8625 162.24 0.01640 73.52 130.13 1001.0 1131.1 0.2347 2.6094 1.8441 60 170D6 0 01645 61.98 137.96 996.2 l134.2 0.2472 I.5820 7.0 1.8292 176.85 0 01649 53.64 144.76 992.1 1836.9 0.2581 1.5586 l.8167 8.0 182.86 0.01653 47.34 150.79 988.5 1139.3 0.2674 1.5383 1.0057 9.0 188.28 0.01656 42 40 1%.22 985.2 1I41.4 0.2759 1.52C3 l.7962 10 193.21 0 01659 38 42 161.17 982.1 1143.3 0.2835 1.5041 1.7876 14.696 212.00 0.01672 26.80 180.07 970.3 l150 4 0.3120 1.4446 1.7566 15 213.03 0.01672 26.29 181.11 969.7 1150.8 0.3135 1.4415 1.7549 20 227.% 0.01683 20 089 1 %.16 960.1 l 156.3 0.33 % 1.3%2 1.7319 25 240.07 0.01692 16.303 208 42 952.I 1160.6 0.3533 1.3606 1.7139 30 250.33 0.01701 13.746 218.82 945.3 1864.1 0.3680 1.3313 1.6993 35 259.28 0.01706 11.89b 227.91 939.2 II67.1 0.3807 1.3063 1.6870 40 267.25 0.01715 10 498 236.03 933.7 l169.7 0.3919 1.2844 1.6763 45 274.44 0.01721 9.40I 243.36 928.6 1872.0 0 4019 1.2650 1.6669 50 281.01 0.01727 8.515 250.09 924.0 1I74.1 0.4110 1.2474 1.6584 55 287.07 0.01732 7.787 256.30 919.6 I I75.9 0.4193 1.2316 I.65(N 60 292.71 0.01738 7.175 262.09 915.5 1177.6 0.4270 1.2168 1.6438 65 297.97 0.01743 6.655 267.50 911.6 1179.1 0.4342 I.2032 1.6374 70 302.92 0.01748 6.206 272.61 907.9 1I80.6 0 4409 1.1906 1.6315 75 307.L) 0.0175.1 5 816 277.43 904 5 1I81.9 0 4472 1.1787 1.6259 80 312.03 0.01757 5 472 282.02 901.1 1183.1 0 4531 1.1676 1.6207 s 85 316.25 0.0176I 5.168 286.39 897.8 l 184.2 0.4587 1.t$71 1.6158 90 320.27 0.01766 4.8% 290.56 894.7 1I85.3 0 4641 1.1471 1.6112 l 95 324.12 0.01770 4 652 294.56
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3,726 312.44 877.9 1190 4 0.4916 1.0962 1.5876 120 341.25 0.01789 872.9 1191.1 0 4995 l.0817 1.5812 130 347.32 0 01796 3 455 318.81 868.2 1193 0 0.5069 1.0682 1.5751 140 353.02 0 01802 3.220 324.82 863.6 1194.1 0.5136 1.05 % 1.5694 150 356 42 0 01809 3 015 330.51 2.834 - 335.93 859.2 18951 0.5204 1.0436 f.5640 160 363.53 0.01815 341.09 854 9 1896 0 0.5266 1.0324 1.5590 170 % 8 41 0.01822 2.675 0,01827 850 B II96 9 0.5325 f.0217 1.5542 180 373.06 2'532 346.03 350 79 846.8 1897.6 0.5381 1.0116 l.5497 190 377.51 0.01833 2 404 355.36 843.0 1898 4 0.5435 1.0018 1.5453 200 381.79 0.01839 2.28b 376 00 825.1 1201.1 0.5675 0.9588 I.5263 250 400.95 0.01865 1.8438 393.84 8^h9 1202.8 0.5879 0.9225 1.5104 300 417.33 0.01890 1.5433 409.69 794.2 1203.9 0.6056 0.8910 1.4966 350 431.72 0.01913 1.3260 1.1613 424 0 780.5 1204.5 0 6214 0.8630 1.4844 400 444.59 0.0193 437.2 767.4 1204.6 0.6356 0.8378 1.4734 450 4 % .28 0.0195 1.0320 0.9276 449.4 755.0 1204 4 0.6487 0.8147 I.4634 500 467.01 0 0197 4608 743.1 1203.9 0.6608 0.7934 1.4542 550 476.94 0 0199 0 8424 471.6 731.6 1203 2 0.6720 0.7734 1.4454 600 486.21 0.0201 0 7698 481.8 720.5 Yi 2.3 0.6826 0.7548 1.4374 650 494.90 0.0203 0.7083 491.5 709.7 1201.2 0.6925 0.7371 1.4296 700 503.10 0.0205 0.6554 500.8 699.2 1200.0 0.7019 0.7204 1.4223 750 510.86 0.0207 0.6092 509.7 688.9 1198.6 0.7108 0.7045 1.4153 000 $18.23 0.0209 0.5687 518.3 678.8 0.7194 0.6891 1.4065 850 525.26 0.0210 0.5327 900 531.98 0.0212 0.5006 526.6 668.8 1 5.4 0.7275 0.6744 1.4020 0 4717 534 6 659.1 l193.7 0.7355 0.6602 1.3957 950 538 43 0.0214 0 4456 542.4 649.4 1191.8 0.7430 0.6467 1.3897 1000 544.61 0.0216 0 4001 557.4 630 4 1187.7 0.7575 0.6205 1.3780 l100 5 %.31 0.0220 0.0223 0.M19 571.7 61i.7 ,]J.83.4 0.7711 0.5956 1.3667 1200 % 7.22 0.3293 585 4 593.2 0 7840 0 5719 1.3559 1300 577.46 0 0227 0 0231 0.3012 $98.7 574.7 173 4 0 7963 0.5491 1.34 54
- 1400 587.10 1500 5 % .23 0.0235 0 2765 611.6 E 0.8082 0.5269 1.3351 1.2849 0.0257 0.1878 671.7 463 4 1135.1 0.8619 0.4230 2000 635 82 0.1307 730.6 360.5 1091.1 0.9126 0.3197 1.2322 2500 668.13 0.0287 802.5 217.8 1020.3 0.9731 0.1885 1.1615 3000 695.M 0.0346 0 0858 0.0503 0.0503 902.7 0 902.7 1.0580 0 1.0580 320e.2 705.40 i .
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,, . 392.6 452.3 512 0 571.6 631.2 6908 750 4 809.9 869.5 929.1 988.7 1807.8 I A... ... l150 4 l195.8 1241.7 1288 3 1335.7 13838 1432.8 14s2 7 1533.5 1585.2 1637.7 1745.7 (101.14) s... . . . 2.0512 2.1153 2.1720 2.2233 ' 2.2702 2.3137 2.3542 2.292.1 2 42:3 2.4625 2 4952 2.5566
,, . 78.16 90.25 102.26 114 22 126 16 138 10 150 03 161.95 17387 185.79 197.71 221.6 5 A... 1148.8 1995.0 1241.2 1288.0 1335 4 1383.6 1432.7 14s2.6 ,1533 4 1585.1 1637.7 1745.7 (162.24) s. . 1.8718 1.9370 1.9942 2 04 % 2 0927 2.1%l 2.1767 2.214h 2.2509 2.2851 2.3178 2.3792 v.. 38.85 45.00 51.04 57.05 63.03 69 01 74 9s 30 95 146.9 2 92.88 ~ 98.84
- 10.77 10 A. 1846 6 l193.9 1240 6 1287.5 1335.l 1383 4 1432.5 14s2 4 1533.2 15s5 0 1637.6 1745.6 (193.21) s. 1.7927 1.8595 I.9172 1. % 89 2.0160 2.05 % 2.1002 2.13M t 2 1744 2.2068 2.2413 2.3028
- v. 30.53 34 68 36.78 42.86 46 94 51.00 $5.07 59.13 63.19 67.25 75.37 14A96 A. . . 1192.8 1239.9 1287.1 13348 1383.2 1432.3 1482.3 1533.1 1554.5 1637.5 1745.5 (2121101 s . . l.8160 1.8743 I.9261 1.9734 2.0170 2.0576 2.0958 2.1319 2.1662 2.1989 2 2603
- v. 22.36 25 43 28 46 31.47 34 47 37.46 40 45 43 44 46 42 49.41 55.37
- A.. . . l 191.6 1239.2 1286 6 1334 4 1382.9 1432.1 1482.1 1533 0 15s4 7 1637.4 1745.4 (227.%) s. .. l.7s08 1.8396 ' l.8918 1.9392 1.9829 2.0235 2.0615 2.0978 2.1321 2.1648 2.2263
,. 11.040 12.628 14 168 15.688 17.19s 18 702 20.20 21.70 23.20 24 69 27.68 40 A. l 186.8 1236.5 1284.8 1333.1 13bl.9 1431.3 1481.4 1532.4 1584 3 1637.0 1745.1 (367.25) 3. . 1.6994 1.7608 1.8140 1.8619 1.9058 1.9467 1.9850 2.0212 2.0555 2.0s83 2.1498
- r. . 7.259 8.357 9 403 10.427 11.441 12 449 13.452 14 454 15.453 16 451 18.446 60 A. . 1181.6 1233.6 1283.0 1331.8 1380.9 1430.5 1480.8 1531.9 15nn 1636 6 1744.8 (292.71) s. . . .. l.6492 1.7135 I.7678 1.8162 1.8605 I.9015 1.9400 1.9762 2.olub 2.0434 2.1049
- v. . 6.220 7.020 7.797 8.562 9.322 10.077 10.830 ti.5M2 12.332 13.830 to A. 1230.7 1281.1 1330.5 1379.9 1429.7 1480.1 1531.3 15N3 4 1636.2 1744.5 (312.03) s. .. . .. . l.6791 1.7346 1.7836 1.8281 1.8694 l.9079 1.9442 1.97M7 2.0115 2.0731 y... .. . .. 4.937 5.549 6.218 6.835 7.446 8.052 8.656 9.259 9.860 11.060 100 A. . . . 1227.6 1279.1 1329.1 1378.9 1428.9 1479.5 1530.8 1582.9 1635.7 1744.2 (327.81) s . .. . . l.6518 1.7085 1.7581 1.0029 1.8443 1.8829 1.9193 I.9538 1.9867 2.0454
- e. . 4.081 44M 5.165 5.683 5.195 6.702 7.207 7.710 8.212 9.214 130 A. .. . . . 1224.4 1277.2 1327.7 1377.8 1428.1 1478.8 1530.2 1582.4 1635.3 1743.9 0 41.2 % s . .{.. ..{... .( 1A287 LAC 49 1.1310 ; l.1822 1.8237 2.8625 l.8990 1.9335 1.9664 2.0281
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- v. 3.008 3 443 3 849 4.244 4.631 160 A. 1217 6 12731 1325.0 5.015 5.3% 5.775 6.152 6.906 1375.7 1426 4 1477.5 (M3.53) s. . 1.590b l.6519 1.7033 1.7491 1529.1 1581.4 1634.5 1743.2 1.7911 1.8301 1.8667 1.9014 1.9344
- v. 1.9962 2.649 3 044 3.4 l l 3.764 4.Il0 180 A. 4.452 4.792 5.129 5.466 6.136 1214.0 1275.0 1323.5 1374.7 1425.6 j (373.06) s 1476.8 1528.6 1581.0 1634.1 1742.9 1.5745 1.6373 1.6894 1.7355
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$. THEDRY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 22 AN5WERS -- OCONEE 1, 283 -86/04/21-TOM ROGERS ANSWER 5.01 (2.00)
(s) Increase (b) Increase (c) Increase (d) Decrease 0 0.5 points each. REFERENCE ONS, OP-0C-SPS-RT-IP, pp. 21-22. ANSWER 5.02 ( .50) TRUE. REFERENCE NET, Vol. 3, NUS, G-15. DNS, OP-0C-SPS-RT-RK. ANSWER 5.03 ( .50) TRUE REFERENCE ONS: OP-0C-SPS-RT-RBC, p.9. ANSWER 5.04 ( .50) FALSE
- REFERENCE ONS, OP-0C-SPS-THF-CTH, p.7.
{ t
- ANSWER 5.05 (1.00) l After lifting off its seat, the steam pressure has more surface area j to work against (which increases the force against the valve springs).
I I l l
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 23
! ANSWERS -- OCONEE 1, 283 -86/04/21-TOM ROGERS REFERENCE ONS, OP_0C-SPS-SY-MS, p.15. ANSWER 5.06 (1.00) i
- As air enter the reciever, it expands the air in a larger volume causing the air to cool, which causes condensation of moisture in the air.
REFERENCE ONS, OP-0C-SPS-SY-IA, p.13. l ANSWER 5.07 (1.00)- 3 All rods operableCO.53 i all rods withdrawn above insertion limits [0.53 REFERENCE ONS, OP-0C-SPS-APC-T47, p.8. lI 4 ANSWER 5.08 (1.00) (a) The nucleate boiling region [0.5]. (b) The superheat region [0.5].
! REFERENCE
- ONS, OP-0C-SPS-CM-SGr pp. 12-14.
j ANSWER 5.09 (1.00) It increases the heat transfer area A [0.5] in the heat transfer rate equation 0=UA delta T CO.5]. REFERENCE ONS, OP-0C-SPS-CM-SG. i 4 4 I l j i i t l
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50 THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 24 ANSWERS -- OCONEE 1, 2R3 -86/04/21-TOM ROGERS ANSWER 5.10 (1.00) It accumulates in the OTSG tubes (top of hot legs) [0.53 retarding or stop-ping heat transfer to the secondary plant not allowing the RCS coolant to condense [0.53. REFERENCE ONS, OP-DC-SPS-PTR-AM-2. p.12. ANSWER 5.11 (1.00) Heat transfer from clad to coolant can be reduced due to boron collecting on the cladding E0.53 and flow blockage can occur from boron collecting on other core structures E0.53 both of which cause higher fuel and cladding temperatures. REFERENCE ONS, GP-0C-SPS-PTR-AM-1. ANSWER 5.12 (1.00) Hydrazine exchange in the demin. (ammonia form) could cause a Cl release. REFERENCE ONS, OP-0C-SPS-CH-PC, p.10. ANSWER 5.13 (1.00) Prevent gases from coming out of solution which may damage CRDs on a trip or RCP impeller due to cavitation. REFERENCE ONS, OP-DC-SPS-CH-PC, p.13. ANSWER 5.14 (1.00) U238 E0.53 Pu240 CO.53 b
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4 , 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 25 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS REFERENCE ONS, OP-0C-SPS-RT-RC, p.8. ANSWER 5.15 (1.00) The peak shortening reflects the probability of neutron capture in the microscopic crossection but the probability of capture within the fuel is a function of the macroscopic crossection E0.53. The shortening of the peak does not cause the capture probabilty in the fuel to fall below the saturation value of the Oconee fuel CO.53. REFERENCE ONS, OP-0C-SPS-RT-RC, p.9. ANSWER 5.16 (1.00) Decreases E0.53. Pellet swell and clad creep decreases the gap which promotes heat transfer E0.53. j REFERENCE ONS, OP-0C-SPS-RT-RC, p.26. ANSWER 5.17 (1.00) Yes CO.53, at BOL it can be positive due to a hi 3 h baron concentration CO.5 l 3. i REFERENCE ONS, OP-0C-SPS-RT-RC, p.26, i i ANSWER 5.18 (1.00) (a) dampen (b) promote 0 0 5 points each. i REFERENCE ONS, OP-0C-SPS-RT-FPPr. p.16. t
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i i 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 26 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 5.19 (2.00) (a) Becomes more nesative.EO.53. l (b) Pu-239 increases, which has a hisher fission yield than U-235 for Xe. Thermal flux increases over core life.EO.53 Baron decreases. [0.53 REFERENCE ONS, OP-0C-SPS-RT-FPP, p.18. ANSWER 5.20 (1.50) , (a) Worth of a fully inserted rod 0 100% power with all other rods , fully withdrawn. E0.53. I (b) Worth of rod ejected from the core 0 0% power with safety rods fully withdrawn and res rods fully inserted.CO.53 (c) Worth of rod that remains out of the core when all other rods fully insert from 100% power.CO.53 REFERENCE ONS, OP-0C-SPS-RT-IP, p.72. ANSWER 5.21 (1.50) Increases immediately until the rods stop E0.253 due to prompt jump E0.253. Decreases E0.25] then increases E0.253 due to the delayed neutrons E0.253. Then decreases to zero at the SCR E0.253. REFERENCE , DNS, OP-0C-SPS-RT-SM, pp. 20-21. ANSWER 5.22 (1.00) (a) MTC E0.53 (b) Doppler E0.53 REFERENCE ONS, OP-0C-SPS-RT-RC, p.20. f i
. _ . - - _ . . _ _ _ _ . . - - . .. _. - - - . _ . . _ , , . _ = . . _ - - . . , _ , _ , - - . .
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 27 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS AMSWER 5.23 (1.00)
Any 4 0 c.25 points each:
- 1. Dissolved gases in the RCS.
- 2. Fission gases from clad failure.
- 3. Impurities in the BWST.
- 4. Nitrogen in the CFTs.
- 5. RadioJ
- 6. TrH Pur *$y
- st i frw c d e c o m p o s i t i o n .em kevp N A4e(.
REFERENCE ONSr OP-0C-SPS-PTR-AM-2, p.14. ANSWER 5.24 (1.00) 0 0.25 points each
- 1. Heat sink
- 2. Heat source
- 3. Coupling
- 4. Thermal centers of OTSG > Core.
REFERENCE ONS, OP-0C-SPS-PTR-AM-1, p.42. ANSWER 5.25 (1.00) Whether current leads or lags voltage. REFERENCE Applied Fnsineering Principles, Westinghouse Corp., p.1-12. ANSWER 5.26 (1.50) RCP will pump coolant from the RCS through the break E0.5]. If the RCPs were then lost, phase separation could occur in the RCS possibly uncovering the core CO.5], which would cause severe rise in fuel / clad temoerature CO.5 J.
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 28 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 5.27 (1.00) a p=(k2-k1)/k2ki=(1.004-0.92)/1.004(.92)=0.91.
REFERENCE NET, Mod. 3, NUS Corp. p.6.1. DNS, OP-0C-SPS-RT-RK. ANSWER 5.28 (1.00) 1.4 DPH i REFERENCE MNS OP-MC-SPS-RT-RK, p.7. HBR RXTH-HO-1, 43,p.3. 1 l
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 29 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 6.01 (1.00) a REFERENCE OP_0C-SPS-IC-RCI, p.12.
ANSWER 6.02 (1.00) Channels 7 and 8 (RB Spray-10 psis). REFERENCE ONS OP-0C-SPS-IC-ES, p.7. ANSWER 6.03 (1.00) 0.5 each HPI- RCS<1750 psis LPI-RCS<900 psis REFERENCE ONS, OP-0C-SPS-IC-ES, p.7, ANSWER 6.04 (1.00) Nothin3.E.53If any of (the 19) exceed the ave temp by more than 50F, it will not be used in the calculation.E.5]. REFERENCE ONS, OP-0C-SPS-IC-RCI ANSWER 6.05 (1.00) Must have at least 138 spm total CC stator cooling flow to energize stator. REFERENCE OP-0C-SPS-CM-CRD, p.7. 2
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 30 ANSWERS -- OCONEE 1r 2&3 -86/04/21-TOM ROGERS i
ANSWER 6.06 (1.00) 8. (55%(7/8)=48.125%, 55%(1.4/1%)=77 inches, 48.125(1.4/1%)=67.375 inchese 4 77-67.375=9.625 inches cut of avs for 7 rods plus one for the dropped rod. Set point is 9 inches out of avs.) REFERENCE ONS, OP-0C-SPS-IC-CRI, pp. 23-25. ANSHER 6.07 (1.00) The shielding of electron avalance;by the + ions moving toward the negative (outer) electrode. REFERENCE ONS, OP-0C-SPS-IC-PRM, p.15. ? ANSWER 6.08 (1.00) (a) Scinillation (NaI) E.53 (b) Gamma E.53 REFERENCE l ONSr DP-0C-SPS-IC-PRM I ANSWER 6.09 (1.00) When either NI-5 or NI-6 and NI-7 or HI-8 are above 10% power. ! REFERENCE l ONS, OP-0C-SPS-IC-NI, p.18. ANSWER 6.10 (1.00) l NI-5 or NI-9. i REFERENCE l ONS, OP-0C-SPS-SY-LPI, p.8. i l l l r l t (
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 31 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 6.11 (1.00)
LPI [.5] SFPCS E.5] REFERENCE ONS, OP-0C-SPS-SY-LPI, p.8. ANSWER 6.12 (1.00) High RCS pressure C.5] High Th E.5] REFERENCE ONS, OP-0C-SPS-IC-RPS, p.14. ANSWER 6.13 (1.00)
- 1. Loss of seal injection when RCP is off.E.5]
- 2. Loss of seel injection with loss of CCW flow.C.5]
REFERENCE ONS, OP-0C-SPS-SY-HPI. p.3. ANSWER 6.14 (2.00) 0 0.5 points each
- 1. 230 kv yellow bus isolates.
- 2. Path established from one Keowee Hydro Unit to each SU xfmr.
- 3. Aligns other Keowee Unit to underground feeder to supply CT-4.
- 4. Starts both Keowee Hydro Units.
REFERENCE ONS, OP-0C-SPS-EL-EPD, pp.24-25. 1 i i k
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 32 ANSWERS -- OCONEE le 2&3 -86/04/21-TOM ROGERS ANSWER 6.15 (1.50) 0 0.5 points each:
- a. Two sources are out of phase.
- b. AC line volatse is low.
- c. Two sources are in phase.
REFERENCE ONS, OP-0C-SPS-EL-VPS, p.13. ANSWER 6.16 (2.00) 0 0.5 points each: y f ,,8 , jf,I4 1 c / J p A b b r" f (a) 1. Engine overspeed.
.M l*W Ib #'
jp,,*
- 2. Generator Diff. Protection. .
- 3. Low-Low Lube Oil Pressure. "2 84}k //lgk Cr kcr..tc. Pr.ssue G fety (b).t+t the above. 7 d'N M' 8" "N O t- 3 8 Mrsif Vo her REFERENCE ONS, OP-0C-SPS-SSF-DG, p.13.j g.(o8.
ANSWER 6.17 ( .50) 1010 psis. REFERENCE ONS, OP-0C-SPS-SY-MS, p.15. ANSWER 6.18 (1.50) 0 0.5 points each:
- 1. Compressor run continuously.
- 2. At 95 psi decreasing, unloader valves close.
- 3. At 100 psi increasing, unloader valves open.
REFERENCE ONSr OP-0C-SPS-SY-IAr p.14. (
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6o PLANT SYSTEMS DESIGNr CONTROL, AND INSTRUMENTATION PAGE 33 ANSWERS -- OCONEE le 283 -86/04/21-TOM ROGERS ANSWER 6.19 (1.00) MFWPT tripped with a loss of 4 RCPs. REFERENCE ONS, OP-0C-SPS-SY-EFr p.33. ANSWER 6.20 (1.00) The safety function is indeterminate due to an invalid input. REFERENCE ONSs OP-0C-SPS-IC-SPDS, p.10. ANSWER 6.21 (1.00) CST REFERENCE ONS, OP-0C-SPS-SY-F0W, p.21. ANSWER 6.22 (1.50) 0 0.5 points each:
- 1. Pull out Safety Rods.
- 2. Operate Res Rods for a group with a failed power supply.
- 3. To recover a dropped rod.
REFERENCE OP-0C-SPS-IC-CRT, p.14. < u
- - - - - , - . . . . . . . . . - . ~ _ , - - . .- - . -- .
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 34 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 6.23 (2.00)
Any 8 0 .25 points each:
- 1. Upper oil pot level not low.
- 2. Lower oil pot level not low.
- 3. Seal injection flow at least 22 spm.
- 4. CC flow st least 575 spm.
- 5. ti seal dp at least 275 psid.
- 6. Reactor power less than-50%.
- 7. Oil lift pump pressure at least 600 psis.
- 8. Oil lift pump running.
- 9. Tc greater than 430F.
REFERENCE ONS, OP-0C-SPS-CH-CPS, p.21. ANSWER 6.24 (1.50) Normal-LP Service Water. BU-HP Service Water. BU-Aux Service Water. 0 0.5 points each. REFERENCE ONS, OP-0C-SPS-SY-HPI, p.24. ANSWER 6.25 (1.50) 0 0.25 points per load, any 2 from each. (a) Main turbine oil coolers, I A camp aft coolers, MSR pumps, MDEFW pump motors, TDEFP cooling Jacket, Chilled water cond., seal water to main vac pumps and or priming pumps, air conditioner cond on aiterex, flush water for RIA 33 & 34. (b) LPI coolers, CC coolers, HPI motor bearings, aux building ventilation coolers. (c) RB cooling units, RCP motor and oil coolers, aux fan coolers, fire hose stations.
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ANSWERe -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS i I REFERENCE ONS, OP-0C-SPS-SY-LPH, p.8. 4 4 i
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e i 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 36 ;
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ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS t - ANSWER 7.01 ( .50)
- TRUE ;
5 REFERENCE i DNS, OP-0C-SPS-SY-EF, p.67. i I ANSWER 7.02 (1.00) 1-Get pin from SS key locker, insert pin locally to engage shaft to handwheel i and open it. , , t
- REFERENCE ONS, OP-0C-SPS-SY-CC, p.16.
i . I i ANSWER 7.03 (1.50) i l When PZR level cannot bo maintained above 220' E0.5] with letdown isolated ! I E0.53 and full HPI flow E0.5]. 1 l REFERENCE i ONS, EP/1/A/1800/01, SEC. 504, i i
- ANSWER ?.04 (1.00) i Trip both EHC pumps.
t j REFERENCE l j ONS, EP/1/A/1800/01, p.4. I ; i i I ANSWER 7.05
~
l (1.00) i l By lower and/or decce sino steam pressure E0.5] or high SG 1evel E0.5]. l l REFERENCE i ONS, EP/1/A/1800/01, p.33. l ) ! l ] i i 1 7 I 4 4 r i I 5
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 37
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g i ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS i !f 1 ANSWER 7.06 (1.00) l Open all RCS high point vents. (SG & RV head vents) I REFERENCE i ONS, EP, p.22. i ANSWER 7.07 (1.50) ) 0 0.5 points each: 2
- 1. All blue ES RZ module ' AUTO' lights on.
- 2. All white ES RZ " POSITION' lights on.
- 3. ES HP Injection Channels A,B,C Trip alarms on.
i REFERENCE i DNS, EP, p.62. i i ANSWER 7.00 (1.00) ,1 j Any subcooling margin =0F. t 1 REFERENCE
! ONS, EP, p.62.
l , ANSWER 7.09 (1.00) Doth IR <E-6 amps and decreasins. REFERENCE ! ONS, EP, p.69. ! ANSWER 7.10 (1,00) l SSF Aux Service Water ' Ump. l REFERENCE l ONS, AP/1/A/1700/11, p.18. i i i ! O 4 i i l i 1
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 38
~~~~R A5i5E55i5AE 555TR5E-~~-~~~~----------------
ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS
ANSWER 7.11 (1.00)
$b REFERENCE AP/1/A/1700/11. p.5.
ANSWER 7.12 (1.50) Any 3 0 0.5 points each
- 1. Repressurizing RCS with heaters.
- 2. Venting RCS high points to RB.
- 3. Running RCP.
- 4. Waiting for ambient cooling to condense voids.
REFERENCE ONS, EP, p.140. ANSWER 7.13 ( .50)
<50F/HR.
REFERENCE ONS, EPr p.140.
~~ ANSWER 7.14 (1.00)
Unit 1- RC pressure >100 psis or RC temp >190F E.53. Units 283-RC pressure $100 psis or RC temp >200F.E6]. REFERENCE ONSr OP-0C-SPS-SY-HPI, p.39.
~~' ANSWER 7.15 (1.00)
Pprur-To prevent gas from entering HPI pumps in the eventofHPIEmers. Injection [s] REFERENCE
~
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ONS, OP-0C-SPS-SY-HPI.
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 39
- ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R A5i5L55iEAL 55RTR5L ANSWERS -- OCONEE 1, 283 -86/04/21-TOM ROGERS 1
i , ANSWER 7.16 ( .50)
-30 min.
REFERENCE ONS, OP-0C-SPS-SY-LPIr i ANSWER 7.17 ( .50) NPSH REFERENCE ONSr OP-0C-SPS-SY-LPIr p.15. ANSWER 7.18 (1.00) 1 When Quench Tank pressure stops increasing during PZR venting. REFERENCE ONS, OP-0C-SPS-CM-PZR, p.22. ANSWER 7.19 (1.00) j Blood changes [0.53 Sickness-(nausear vomiting, fatique)[0.53 REFERENCE ONS, OP-0C-SPS-RAD-RPT, p.22. j ANSWER 7.20 (1.00) Chek the meter deflection with the alert light depressed. ! REFERENCE j ONS, OP-0C-SPS-IC-PRMr p.16. I I i t
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 40.
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ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 7.21 (1.00) When load reductions >100mw from loads 600 mw or greater until cold Sas temperatures stabilize. REFERENCE ONS, OP/1/A/1106/01, Encl. 4.10. ANSWER 7.22 (1.00) Temperature inversion CO.53 and low wind speed E0.5] REFERENCE OP/1/A/1104/10, Encl. 4.6, p.1. ANSWER 7.23 ( .50) 3. REFERENCE ONS, OP/1/A/1104 ANSWER 7.24 (1.50)
- 1. Select group control and group to be aligned.
- 2. Select SED OVERRIDE.
- 3. Select J0G.
- 4. Press Latch Switch and drive in for 15 sec.
- 5. Compare absolute and relative positions.
- 6. Select desired CRD and use PI RESET RAISE / LOWER for adjustment.
G 0.25 points each. REFERENCE ONS, OP/0/A/1105/09, Encl. 4.3.
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ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 7.25 (1.00) Any 4 0 0.25 points eacht:
- 1. Anti Cs
- 2. Respirators
- 3. MPC hours
- 4. Do not take anything by mouth in contaminated area
- 5. Keep hands or any contaminated item away from face REFERENCE ONG, OP-0C-CPG-RAD-RPT, p.27.
ANSWER 7.26 (1.00) G 0.25 points each
- 1. Visually inspect instrument for damage.
- 2. Verify it is in cal.
- 3. Battery check.
- 4. Source check.
REFERENCE ONS, OP-0C-SPS-RAD-RPT ANSWER 7.27 (1.50) 3 attempted starts within a 2 hour periodE0.53 with 30 minute idle periods between attempts CO.53. A fourth attempt may then be made after a 1 hour idle periodt0.5]. REFERENCE ONS, OP/1/A/1103/06, Sec 2.3.
~~' ANSWER 7.28 (1.00)
Isolate al f1 and leakoff paths. *U"' , YYRE DNS, OP/1/A/1103/06,
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 42
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ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 7.29 (1.00) When the refered to procedure is complete and reviewed and signed as complete by the Unit Supervisor. REFERENCE ONS, OP/1/A/1102/04, p.3. ANSWER 7.30 (1.00) Startup must beSin within 8 hours of the tripCO.5] A plant cooldown was not initiatedCO.5] REFERENCE ONS, OP/1/A/1102/02, p.1. t l i l
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- 8. ADMINISTRATIVE PROCEDURES, CONDITION 3, AND LIMITATIONS PAGE 43 ANSWERS -- OCONEE 1, 2&3 -06/04/21-TOM ROGERS ANSWER B.01 (1.00) b REFERENCE ONS, Directive 3.3.1 (TS), p. 2 ANSWER 8.02 (1.00) b REFERENCE ONS, Directive 3.3.2 (TS), p. 3 ANSWER 8.03 (1.00) d REFERENCE ONS, Directive 3.3.2 (TS), Enclosure 4 1 ANSWER 0.04 (1.00) c REFERENCE ONS, OMP 1-9, p. 3 ANSWER 8.05 (1.00) b REFERENCE ONS, TS, p. 4.0-1 ANSWER 0.06 (1.00) d 3
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- 0. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 44 ANSWERS -- OCONEE 1, 283 -86/04/21-TOM ROGERS REFERENCE ONS, TS, p. 6.1-6a ANSWER 8.07 (1.00) b REFERENCE ONS, Emergency Plan ANSWER 0.00 (1.50)
- a. FALSE (0.5)
- b. FALSE (0 5)
- c. TRUE (0.5)
REFERENCE ONS, Directive 3.1.1 (OP), pp. 2 & 3 ANSWER 0.09 (1.50)
- a. FALSE (0,5)
- b. TRUE (0.5)
- c. TRUE (0.5)
REFERENCE ONS, OMP 2-1, Enclosure 4.2 ANSWER 0.10 (1.00)
- 1. 800 (0.25)
- 2. 13 (+/- .44) (1040 +/- 30 cubic feet) (0 25)
- 3. 1035 (0 25)
- 4. 600 (+/- 25) (0.25)
REFERENCE ONS, TS, p. 3.3-2 I I c J
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- 1. Outlet temperature E0 253 and outlet pressure to.253.
- 2. Thermal power 00.253 and reactor power imbalance EO.253.
REFERENCE ONS, TS, pp. 2.1-1, 2.1-4, a 2.1-7. ANSWER 8 13 (1 00)
- 1. Cold leg temperature CO.253 when RCP is on or NC cooldown CO.253.
- 2. LPI cooler outlet temperature to.25] on LPI cooldown 00.253.
REFERENCE ONS, TS, p.3.1-5b. ANSWER 0.14 (1.50) 0 0.5 points eacht
- 1. Activity.
- 2. Sump level.
- 3. Inventory.
REFERENCE ONS, TS, p. 3.1-14 & 16. ANSWER 0.15 (1.00)
- a. 2500 MREM (0.5)
- b. 4500 MREM (0.5)
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 46 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS REFERENCE ONS, Directive 3.3 1 (TS), p. 2 ANSWER 8.16 (1.00)
- 1. Daniel High School (Central, SC) (0.5)
- 2. Keowee Elementary School (Seneca, SC) (0.5)
REFERENCE ONS, .. Emergency Plan, p. H-4 ANSWER 8.17 ( .50) Oconee Memorial Hospital (0.5) REFERENCE ONS, Emergency Plan, p. L-1 ANSWER 0.18 (1.50) (Any FIVE at 0.3 points each)
- 1. Technical Support Center
- 2. Field Monitoring Team (Leader, A - F)
- 3. Crisis Management Team (Training Center)
- 4. Pickens County (LEC, Courthouse, C.D. Office)
- 5. Oconee County (LEC)
- 6. State of SC (Clemson National Guard Armory)
REFERENCE ONS, Emergency Plan, pp. F-2 & 6 ANSWER 0 19 (1.00)
- a. 1 Hour (0.5)
- b. 10%/hr (0.5)
REFERENCE ONS, OMP 1-4, p. 1 i 5 1 i
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- 8. ADMINISTRATIVE PF.0CEDURES, CONDITIONS, AND LIMITATIONS PAGE 47 ANSWERS -- OCONEE in 2&3 -86/04/21-TOM ROGERS ANSWER 8.20 (1.50)
- 1. (Verbal) approval of two operators (0.3), one of whom is a supervisor (0.3) who holds an SRO license (0.3). (0.9)
- 2. Change documentta on working copy (0.3) and initia11ed by SRO (0.3). (0.6)
REFERENCE ONS, OMP 1-9, p. 9 ANSWER 0.21 (1.00)
- 1. Suberitical by 1% delta K/K (0.5)
- 2. Tava at or -less than 525 degrees F (0.5)
C. tu G' REFERENCE / ONS, TS, p. 1-1 ANSWER 8.22 (1.00) Loss of Load REFERENCE ONS, TS, p. 3.13-1 ANSWER 0 23 (1.00) Limit hydrogen concentration (in Reactor Building) following a LOCA to 4%. REFERENCE ONS, TS, p. 3.16-1
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS -PAGE 48 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 8.24 (1.50)
- 1. 1 SS(SRO) (0.3)
- 2. 2 SRO (0.3)
- 3. 1 STA(SRO) (0.3)
- 4. 5 R0 (0.3)
- 5. 5 NEO (0.3)
REFERENCE ONS, TS, p. 6.1-6 ANSWER 8.25 (1.00)
- 1. Its curresponding normal or emergency source is operable, and (0.5)
- 2. All its redundant components are operable. (0.5)
REFERENCE Sorry, TS 3.0-1 ONS. TS, p 1-2 ANSWER 0.26 (1.50) ri t least three detectors (0.25) in each of at least three strings (0.25) shall lie in the same axial plane (0 25), with one plane in each axial core half (0.25). The axial planes in each core half shall be symettri-cal about the core mid-plane (0.25). The detector strings shall not have radial symetry(0.25). (1.5) REFERENCE ONS, TS, p. 3.5-33 3 ANSWER 0.27 (1.00) A continous fire watch (0.4) with backup fire suppression equipment (0.3) in the area within one hour (0.3). (1.0) [ PEFERENCE ONS, TS, p. 3 17-2 i f i l ? l
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