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Exam Rept 50-269/OL-86-01 on 860421.Exam Results:Both Candidates Passed Written Reexams
	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: ML20209H612; ML20209H628; ML20209H647;
References
	50-269-OL-86-01, 50-269-OL-86-1, NUDOCS 8609150291
	Download: ML20209H628 (59)
	v • d • e

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NUCLEAR REGULATORY COMMISSION

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REGION 11 g

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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

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John F. Munro, Ac' ting Section Chief 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

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s.

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 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 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

___1_0

________ 5.

THEORY OF NUCLEAR POWER PLANT

___1__0__

30 0 25 0 OPERATION, FLUIDS, AND THERMODYNAMICS 30.00 25.00 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

___1_00______1__0

________ 7.

PROCEDURES - NORMAL, ABNORMAL, 30 25 0 EMERGENCY AND RADIOLOGICAL CONTROL

___I__0

________ 8.

ADMINISTRATIVE PROCEDURES, 30 0 25 00 CONDITIONS, AND LIMITATIONS 120.00 100.00 TOTALS FINAL GRADE _________________%

All work done on this examination is my own. I have neither i

S ven not received aid.

PPLEC5UT 5~5EUU5TURE~~~~~~~~~~~~~~

I

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) i Omission of the reactivity associated with Samarium in a shutdown mars n 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

- - - - )

r 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

- - - - )

i I

l 9

l

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 *****)

i t

r

\\

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.

wide ranse cold les RTD.

d.

r 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

t 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

- - - - )

i I

i i

l 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 *****)

i

]

i

i 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

- - - - )

i i

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~.

7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11

~~~~ E5i6C55IEAL 55sTR5L'~~~~~~~~~~~~~~~~~~~~~~~

R 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

- - - - )

r 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

-- I 0---

30 0

_'5 00

________ 5.

THEORY OF NUCLEAR POWER PLANT I I__

OPERATION, FLUIDS, AND THERMODYNAMICS

-- I00-__ -- I-0

________ 6.

PLANT SYSTEMS DESIGNr CONTROL.

30 25 0 AND INSTRUMENTATION 30 0 25 0

-- I 0

-- I-0

.-______ 7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 30.00 25.00

8.

ADMINISTRATIVE PROCEDURES, 120.00 100.00 TOTALS FINAL GRADE _________________%

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

hPPL5C5bT 5~556UbiURE

~~~~~~~~~~~~~~

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n 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

- - - - )

l l

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THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDSr AND PAGE-3-

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 *****)

l l

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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 *****)

4 l

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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?

GUESTION 5.27 (1.00) i 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

- - - - )

SA 8 8004 UNITED STATES

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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 Transfer Canal.

l 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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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11

~~~~ 5656L55iEAt C5NTRUE~~~~~~~~~~~~~~~~~~~~~~~~

R 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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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 12

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QUESTION 7.08 (1.00)

During a LOCA with ES actuated, what is the Reactor Coolant Pump trip l

criteria?

i 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 is not available?

j 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

b.

dispatch an operator to the applicable switchgear to open load breakers 3

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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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 13

~~~~ d6EULUU5 EEL U5UTR6L~~~~~~~~~~~~~~~~~~~~~~~~

R 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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PROCEDURES - NORMALr ABNORMAL, EMERGENCY AND PAGE 14

~~~~ 5Di5L55iEAt 55sTR5L

-~~-----------------~~~~

R 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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PROCEDURES - NORMAL, ABNORMAL, EHERGENCY AND 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)

I What restrictions are applied to allow use of the Reactor Trip Recovery procedure for a plant startup once the cause of the trip has been determined and remedied?

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(*****

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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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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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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 on II, Atlanta, GA i

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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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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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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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.

I I

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

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

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KE = mv PE = agh peg + keg +PgVg = PE +KE +P Y22 where V = specific 2

2

~7 volume P = Pressure Q = ic (Tout.Tg,)

Q = UA (T,y,-Tsta)

Q = ilhg.h I p

2 P = P,10(SUR)(t) p. p,,t/T SUR = 26.06 T = (B-p)t 1

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3 1 MW = 3.41 x 10 Btu /hr Density =62.4lbg/ft 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 2

1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 f t-lbm/lbf-sec C

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Enttop>

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F P'"

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0 01604 12061 28.06 1059.9 1088.0 0.0555 2.0393 2.0948 70 0.M31 0.01606 867.9 38.04 1054.3 1092.3 0.0745 1.9902 2.0647 SO 0.5069 0.0160li 6331 48.02 1048.6 1096.6 0.0932 1.9428 2.0%0 90 0.6982 0.01610 468.0 57.99 1042.9 1100.9 0.1115 1.8972 2.0087 100 0.9492 0.01613 350 4 67.97 1037.2 1105.2 0.1295 1.8531 1.9826 110 1.2748 0.01617 265 4 77.94 1031.6 1109.5 0.1417 1.8106 1.9577 120 1.6924 0.01620 203.27 87.92 1025.8 1113.7 0.1645 1.7694 1.9339 130 2.2225 0 01625 157.34 97.90 1020.0 1117.9 0.1816 1.7296 1.9112 140 2.8886 0.01629 123.01 107.89 1014.1 1122.0 0.1984 1.6910 1.8894 150 3.118 0.01634 97.07 117.89 1008.2 1126.1 0.2149 I.6537 1.8685 160 4.741 0.01639 77.29 127.89 1002.3 l 130.2 0.2311 1.6174 1.8485 170 5.992 0.01645 62.06 137.90 996.3 1134.2 0.2472 1.5822 1.8293 180 7.510 0.01651 50.23 147.92 990.2 1138.1 0.2630 1.5480 1.8109 190 9.339 0.01657 40 96 157.95 984.1 1142.0 0.2785 1.5147 1.7932 200 11.526 0.01663 33.64 167.99 977.9 1145.9 0.2938 f.4824 1.7762 210 14.123 0.01670 27.82 178.05 971.6 1149.7 0.3090 1.4508 1.7598 212 14.6 %

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240 24.% 9 0.01692 16.323 208.34 952.2 1160.5 0.3531 1.3609 f.7140 l

250 29 825 0.01700 13.821 216.48 945.5 1164 0 0.3675 1.3323 1.6998 260 35 429 0.01709 Il.763 228.64 9 38.7 1167.3 0.3817 l.3043 l.6860 270 41.858 0.01717 10.061 236.84 931.8 1170.6 0.3958 1.2769 l.6727 280 49.203 0.01726 8.645 249.06 924.7 1173.8 0.4096 1.2501 1.6597 290 57.556 0.01735 7.461 259.31 917.5 1876.8 0.4234 1.2238 I.6472 300 67.013 0.01745 6.466 269.59 910.1 1179.7 0 4369 1.1980 1.6350 310 77.68 0.01755 5.626 279.92 902.6 1882.5 0.4504 1.1727 1.6231 320 89 66 0.01765 4.914 290.28 894.9 1185.2 0.4637 1.1478 1.6115 330 103.06 0.01776 4.307 300.68 887.0 1187.7 0.4769 1.1233 1.6002 340 118 01 0.01787 3.788 311.13 879.0 1190.1 0.4900 1.0992 1.5891 j

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Entropy 9,

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vapor, liquid

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A, A.

A, s,

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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 %

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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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1.9782 93.99 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 1.8625 5.0 162.24 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 1.8292 7.0 176.85 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

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1.5694 160 363.53 0.01815 2.834 -

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$18.23 0.0209 0.5687 509.7 688.9 1198.6 0.7108 0.7045 1.4153 850 525.26 0.0210 0.5327 518.3 678.8 0.7194 0.6891 1.4065 900 531.98 0.0212 0.5006 526.6 668.8 1 5.4 0.7275 0.6744 1.4020 950 538 43 0.0214 0 4717 534 6 659.1 l193.7 0.7355 0.6602 1.3957 1000 544.61 0.0216 0 4456 542.4 649.4 1191.8 0.7430 0.6467 1.3897 l100 5 %.31 0.0220 0 4001 557.4 630 4 1187.7 0.7575 0.6205 1.3780 1200

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p 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)- All rods operableCO.53 3 i all rods withdrawn above insertion limits [0.53 REFERENCE lI ONS, OP-0C-SPS-APC-T47, p.8. ANSWER 5.08 (1.00) 4 (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 h baron concentration CO.5 3 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.

6. TrH Pur *$y t i c d e c o m p o s i t i o n.em kevp N A4e(.

5. RadioJ

s frw 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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f. 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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I 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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i l f 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 77-67.375=9.625 inches cut of avs for 7 rods plus one for the dropped rod. 4 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) y f,,, jf,I4 1 c / J p A b b r" f 0 0.5 points each: 8 (a) 1. Engine overspeed. .M l*W Ib #' jp,,* "2 84}k 2. Generator Diff. Protection. G fety //lgk Cr kcr..tc. Pr.ssue 3. Low-Low Lube Oil Pressure. 7 d'N M' 8" "N O (b).t+t the above. t-3 8 Mrsif Vo her REFERENCE p.13.j g.(o8. ONS, OP-0C-SPS-SSF-DG, 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

..... -. ~

p568 "'Gog'a UNITED STATES NUCLEAR RESULATORY COMMISSION g.

Ao RIGION il ~ f, 7 101 MARIETTA STREET, N.W., SulTE 2900 o, ATLANTA. GEORGIA 30323 +s / l ) i i. i l l i t i l I 4 l i e J

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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.= 4 f i ) 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 35 1 ANSWERe -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS i I REFERENCE ONS, OP-0C-SPS-SY-LPH, p.8. 4 4 i 'e n a J 4 i t ) l t i a I l I i i I I I

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=- e i 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 36 ~~~~ 5656E655Cd[~66 TR5E---------~~------------- R 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 ANSWER 7.05 (1.00) ~ i l 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 ~~~~ A6i6E66fEAE 56sTR6E-----------~~~---------- R 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. 1 REFERENCE t 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 ~~~~ A5i5E55i5AE 555TR5E-~~-~~~~---------------- R 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) eventofHPIEmers. Injection [s] Pprur-To prevent gas from entering HPI pumps in the 'O

I

~ REFERENCE ONS, OP-0C-SPS-SY-HPI.

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1 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 39 ~~~~ A5i5L55iEAL 55RTR5L ~~~~~~~~~~~~~~~~~~~~~~~~ R 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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i 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 40. ~~~~ 5656L5siEEE E6UTRUL~~~~~~~~~~~~~~~~~~~~~~~~ R 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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7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 41 ~~~~ dDi5E55iEAE 55ATRU[~~~~~~~~~~~~~~~~~~~~~~~~ R 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)

U"'

Isolate al f1 and leakoff paths. YYRE $$h tos NoI % l2Grungi p-, DNS, OP/1/A/1103/06, nel. 4.3, p.1.

i f K8809 UNITED STATES ft NUCLEAR RE20LATORY COMISS13N REGION H 3 f, g 3 g 101 MARIETTA 8TREET, N.W., SUITE 2000 4 ATLANTA, GEORGIA 30323 o,s,...../

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 42 ~~~~E5656EUU565E'U6UTRUE~~~~~~~~~~~~~~~~~~~~~~~~ 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

p >2K'009'o,,

g UNITED STATES NUCLEAR RECULATORY COMMISSl2N 8* REosON 11 o 5 \\ 101 MARIETTA STREET, N.W., SulTE 2000 8 ATLANTA, GEORGIA 30323 s / 1 l l

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

p2 E849 UNITED STATES +y ,g NUCLEAR REEULATORY COMMISSION E RE000N il o 2 a 101 MARIETT A STREET. N.W., SUITE 2000 8 ATLANTA.OEORGIA 30323 \\,..... / I l i i I l I i l l k

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 J c

(pga2 atrug[g usseTE3 STATES NUCLEAR RE20LATORY COMMISSION o REGION il f, 5 \\ 101 MAntETT A STREET, N.W., SulTE 2900 ATLANTA, GEORGIA 30323

%...../

L.~......... i

O. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 45 ANSWERS -- OCONEE 1, 2&3 -86/04/21-TOM ROGERS ANSWER 8.11 (1.00) (a) 30 min E0.53. (b) Tech Spec Interpretation 00.53. REFERENCE ONS, TS Interpretations, 1 1. AMSWER 0.12 (1.00)

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) J

p2 28 tog,o,, UNITEo sT.TEs NUCLEAR REIULATORY COMMISSION f, o RE080N H \\ tOf MAmetTTA STREET,N.W., SUITE 3900 2 ATLANTA,0 EOR 04A 30323 ,o L

r 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

gse Ka4 UNITED STATES p d 'o, NUCLEAR REOULATORY COMMISSION [' 'n RE040N il y, 5 \\ 101 MARIETTA STREET, N.W., SulTE 2900 I ATLANTA, GEORGIA 30323 s.,...../ (

T 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

) gseEsto UNITED STATES NUCLEAR RECULATORY CO/.!MISSICN 'i REoloNil 3 \\ 101 MARIETTA STREET, N.W.. SulTE 2900 8 ATLANTA, OEORGIA 30323 o,s, /

f 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 ANSWER 0.27 (1.00) 3 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 ,ew----,_,___ _

T p2 Ef oog'o UNITED STATES NUCLEAR REauLATORY COrMISSitN [' 'n REGION il .f, 3 g 101 MARIETTA STREET, N.W., SulTE 2000 4 ATLANTA, GEORGIA 30323 's,..... $ i i I, i { 1 1 i l l l !}}

ML20209H628: Difference between revisions

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 =Text=
 {{#Wiki_filter:I~
-   \-         .
+\\-
-p 4Kic                              UNITED STATES p         oq'o              NUCLEAR REGULATORY COMMISSION
+p 4Kic UNITED STATES oq'o p
-["              ,                           REGION 11 g               j                   101 MARIETTA STREET,N.W.
+NUCLEAR REGULATORY COMMISSION
-* t                    ATLANTA, GEORGI A 30323
+["
-    \...../
+REGION 11 g
-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.
+j 101 MARIETTA STREET,N.W.
-Chief Examiner:         ~,f     .o,                                7 T V(-
+t ATLANTA, GEORGI A 30323
-ThomasRogersf                                     Date Signed Approved by:                /k N       7 John F. Munro, Ac' ting Section Chief f!dT[l'$
+\\...../
-Date Signed Summary:
+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.:
+-260, 50-270 and 50-287 WrittenexaminationswereadmjnisteredattheOconeeNuclearStation.
+Chief Examiner:
+~,f
+.o, 7 T V(-
+ThomasRogersf Date Signed Approved by:
+/k N 7
+f!dT[l'$
+John F. Munro, Ac' ting Section Chief 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
+8609150291 860902 PDR ADOCK 05000269 V
+PDR
-     . s.      ,
+s.
-REPORT DETAILS
+REPORT DETAILS 1.
-: 1. Facility Employees Contacted:
+Facility Employees Contacted:
 * Paul Stovall, Instructor
-* Attended Exit Meeting
+* Attended Exit Meeting 2.
-: 2. Examiner:
+Examiner:
 * Thomas Rogers
-* Chief Examiner
+* Chief Examiner 3.
-: 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.
+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.
+The comments made by the facility technical reviewers are included as to this report, and the NRC Resolutions to these coments are listed below.
-I               a.                 SR0 Exam (1) Question 6.06 NRC Resolution:  Coment noted; however, no change in the answer key is required.
+The comments made by the facility Educational Specialist are not addressed, since they provide additional information for exam development only.
-(2) Question 6.16 NRC Resolution:   Coment accepted. The answer key has been changed to require the additional responses for full credit.
+I a.
-(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.
+SR0 Exam (1) Question 6.06 NRC Resolution:
-(4) Question 7.14 NRC Resolution:   Comment accepted. The answer key has been changed accordingly.
+Coment noted; however, no change in the answer key is required.
-(5) Question 7.15 NRC Resolution:   Comment accepted. The answer key has been changed accordingly.
+(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     ,,
+5
-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.
+(6) Question 7.28 NRC Resolution:
-(7) Question 8.15 NRC Resolution:   The examinees were verbally instructed during administration of the examination to provide Duke Power administrative limits.
+Comment accepted.
-(8) Question 8.21 NRC Resolution:    Comment accepted. The answer key has been changed accordingly.
+The answer key has been changed to accept a demonstration of knowledge that the seal return will automatically isolate on units 2 and 3.
-: 4. Exit Meeting The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
+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.
+.
+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:                                    _________________________
+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.
+Use separate paper for the answers.
-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.
+Write answers on one side only.
-                                                                 % OF CATEGORY                     % OF    APPLICANT'S         CATEGORY VALUE                  TOTAL             SCORE        VALUE                                                       CATEGORY 30 0                      25 0
+Staple question sheet on top of the answer sheets.
-___1__0__ ___1_0                  _  ___________         ________ 5.                               THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 30.00                     25.00                                                                 PLANT SYSTEMS DESIGN, CONTROL, 6.
+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%.
-AND INSTRUMENTATION 30                        25 0                                                                  PROCEDURES - NORMAL, ABNORMAL,
+Examination papers will be picked up six (6) hours after the examination starts.
-___1_00______1__0                    ___________         ________ 7.
+% OF CATEGORY
-EMERGENCY AND RADIOLOGICAL CONTROL 30 0                      25 00                                                                 ADMINISTRATIVE PROCEDURES,
+% OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY
-___I__0          __       ___.'__    ___________         ________ 8.
+___1_0
-CONDITIONS, AND LIMITATIONS 120.00                    100.00                                                      TOTALS FINAL GRADE _________________%
+________ 5.
-All work done on this examination is my own. I have neither S i ven not received aid.
+THEORY OF NUCLEAR POWER PLANT
-PPLEC5UTI 5~5EUU5TURE~~~~~~~~~~~~~~
+___1__0__
+0 25 0 OPERATION, FLUIDS, AND THERMODYNAMICS 30.00 25.00 6.
+PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
+___1_00______1__0
+________ 7.
+PROCEDURES - NORMAL, ABNORMAL, 30 25 0 EMERGENCY AND RADIOLOGICAL CONTROL
+___I__0
+________ 8.
+ADMINISTRATIVE PROCEDURES, 30 0 25 00 CONDITIONS, AND LIMITATIONS 120.00 100.00 TOTALS FINAL GRADE _________________%
+All work done on this examination is my own. I have neither i
+S ven not received aid.
+PPLEC5UT 5~5EUU5TURE~~~~~~~~~~~~~~
+I
 r
-  -5o     THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND                 PAGE 2 QUESTION              5.01              (2.00)
+-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%.
@@ Line 75: / Line 122: @@
 (c) Increasing Tavs.(Any rod)
 (d) Increasing the boron concentration. (Any rod).
-QUESTION              5.02              ( .50)
+QUESTION 5.02
+(.50)
 A reactor that is prompt critical is also supercritical. TRUE or FALSE?
-OUESTION              5.03              ( .50)
+OUESTION 5.03
-Omission of the reactivity associated with Samarium in a shutdown mars in calculation is conservative. TRUE or FALSE?
+(.50) i Omission of the reactivity associated with Samarium in a shutdown mars n calculation is conservative. TRUE or FALSE?
-OUESTION              5.04              ( .50)
+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)
+DUESTION 5.05 (1.00)
 What causes self actuated relief valves, such as the MSRVs, to reseat at lower pressures than they lift?
-ESTION              5.06              (1.00)
+ESTION 5.06 (1.00)
 Explain how water gets in the air receiving tanks.
-(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
+(***** CATEGORY 05 CONTINUED ON NEXT PAGE
+*****)
-r
+r 5.
-: 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND                 PAGE 3 QUESTION             5.07              (1.00)
+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)
+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)
+GUESTION 5.09 (1.00)
 Explain how increasing the OTSG 1evel increases the power level.
-QUESTION             5.10              (1.00)
+QUESTION 5.10 (1.00)
 Explain how gas accumulation in the RCS can block reflux boiling.
-QUESTION             5.11              (1.00)
+QUESTION 5.11 (1.00)
 What problems can occur due to baron precipitation during a LOCA?
-OUESTION             5.12              (1.00)
+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)
+GUESTION 5.13 (1.00)
 Why is there a total gas limit on gases dissolved in the RCS?
-GUESTION             5.14              (1.00)
+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 *****)
+(*****
+CATEGORY 05 CONTINUED ON NEXT PAGE
+*****)
 i I
 l 9
 l
-: 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND                 PAGE 4 QUESTION             5.15              (1.00)
+.
+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)
+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)
+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)
+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)
+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)
+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.
@@ Line 132: / Line 188: @@
 r
-                                                                                      \
+\\
-: 3. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND                 PAGE 5 GUESTION              5.21              (1.50)
+.
+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)
+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.                                                 ,
+(b) 15% to 100% reactor power.
-GUESTION              5.23              (1.00)
+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)
+QUESTION 5.24 (1.00)
 List the four requirements necessary in order to establish natural circulation.
-QUESTION              5.25              (1.00)
+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)
+OUESTION 5.26 (1.50)
 What is the bases for stopping the reactor coolant pumps during a LOCA?
-QUESTION              5.27              (1.00)
+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 *****)
+(***** CATEGORY 05 CONTINUED ON NEXT PAGE
-: 5. THEORY OF NUCLEAR F0HER FLANT DPERATIGH, FLUIDS, AND             PAGE 6 QUESTION             5.28         (1.00)
+*****)
+.
+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 *****)
+(***** END OF CATEGORY 05
-: 6.       PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION                       PAGE 7 QUESTION               6.01                     (1.00)
+*****)
+.
+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.
+c.
-: d. r    wide ranse cold les RTD.
+a narrow range cold les RTD.
-QUESTION               6.02                     (1.00)
+wide ranse cold les RTD.
+d.
+r 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)
+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)
+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)
+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)
+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
+(***** CATEGORY 06 CONTINUED ON NEXT PAGE
+*****)
+l
-t
+t 6.
-: 6.        PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION                                  PAGE      8 QUESTION                 6.07                        (1.00)
+PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 8
-What causes the " dead time" in the operation of a G-M detector?                                       ,
+QUESTION 6.07 (1.00)
-GUESTION                 6.08                       '(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)
+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)
+QUESTION 6.10 (1.00)
 Which of the power range channels may be used as inputs to the ICS?
-QUESTION                 6.11                        (1.00)
+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)
+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)
+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 *****)
+(***** CATEGORY 06 CONTINUED ON NEXT PAGE
+*****)
 i I
-l
+i i
-I i
+l 6.
-i                                                                                                                                                        l
+PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 9
- ,   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.
-,    QUESTION                 6.14                           (2.00) i    List all automatic actions that occur from a Switchyard Isolation Signal.                                                                           !
+)
-                                                                                                                                                           )
+i QUESTION 6.15 (1.50)
-i                                                                                                                                                         !
-QUESTION                 6.15                           (1.50)
 Explain what the following indications mean from a Vital Inverter Sync Verification Indicator Lamp.
-: a.          Lamp is blinking.
+a.
-: b.           Lamp is on continuously at half brightness with inverter voltase l                  normal.
+Lamp is blinking.
-: c.          Lamp off with inverter in service.
+b.
-QUESTION                 6.16                           (2.00)
+Lamp is on continuously at half brightness with inverter voltase l
-    ~~(a) List the protective trips for the SSF Diesel Generator.
+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).
+QUESTION 6.17
+(
+.50).
 After a trip causing MSRV actuation, at what steam pressure should all MSRVs be reseated?
-GUESTION                 6.18                           (1.50)
+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)
+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 *****)
@@ Line 215: / Line 292: @@
 i
-i
+i 6.
-: 6. PLAdT SYSTEhS DESIGN, CONiROLr AND INSfkUMENTATION                                                         PAGE           19 QUESTION           6.20                (1.00)
+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)
+QUESTION 6.21 (1.00)
 Where is the Feedwater Pump Seal Injection Sump Pump water fiormally pumped to?
-QUESTION           6.22                (1.50)
+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)
+QUESTION 6.23 (2.00)
 List eight Westinghouse Reactor Coolant Pump start interlocks.
-QUESTION           6.24                (1.50)
+QUESTION 6.24 (1.50)
-List the normal and all backup cooling water systems that can be used to                                                         -
+List the normal and all backup cooling water systems that can be used to supply cooling water to the HPI pump motor bearings.
-supply cooling water to the HPI pump motor bearings.                                                                             ,
+QUESTION 6.25 (1.50)
-QUESTION           6.25                (1.50)
 Name two different LPSW System loads for each of the following locations:
-(a) Turbine Building (b) Aux Building                                                                                                                 -
+(a) Turbine Building (b) Aux Building (c) Reactor Building
-(c) Reactor Building
+{
-{                                         (***** END OF CATEGORY 06 *****)
+(*****
+END OF CATEGORY 06
+*****)
 i i
 f i
 e
-_ .                      _                  -              . _ _ _ _      . . _ . - _ . ~ ._ _   _ _ . _ _ _ _ _ _    _ _ _ _ _ .
+~.
-: 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                            PAGE 11
-   ~~~~R E5i6C55IEAL 55sTR5L'~~~~~~~~~~~~~~~~~~~~~~~
+.
-OUESTION              7.01         ( .50)
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11
+~~~~ E5i6C55IEAL 55sTR5L'~~~~~~~~~~~~~~~~~~~~~~~
+R 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)
+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)
+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)
+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?
-ESTION              7.05         (1.00)
+ESTION 7.05 (1.00)
 How is a SG causins excessive heat transfer identified?
-OUESTION              7.06         (1.00)
+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)
+QUESTION 7.07 (1.50)
 How is ES Channels 1 & 2 actuation verified?
-(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
+(***** CATEGORY 07 CONTINUED ON NEXT PAGE
+*****)
-r                                                            , .
+r ENCLOSURE 2 U.
-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:                                _________________________
+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.
+Use separate pcPer for the answers.
-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.
+Write answers on one side only.
-                                                               % OF CATEGORY                  % OF        APPLICANT'S      CATEGORY VALUE               TOTAL               SCORE       VALUE                                                  CATEGORY 30 0                          00
+Staple question sheet on top of the answer sheets.
-  -- I 0---                 I I__
+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%.
-_'5           -------_--_      ________ 5.                      THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS
+Examination papers will be picked up six (6) hours after the ensnination starts.
-  --30I00-__ --             25 0 I-0    --------_-_      ________ 6.                      PLANT SYSTEMS DESIGNr CONTROL.
+% OF CATEGORY
-AND INSTRUMENTATION
+% OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY
-  --30I 00      ---       --25I-0  0
+-- I 0---
-                                        ----_------      .-______ 7.                      PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 30.00                  25.00                                                         ADMINISTRATIVE PROCEDURES,
+0
-  -------- ------                       -----------      -------- 8.
+_'5 00
-.00                  100.00                                                TOTALS FINAL GRADE _________________%
+________ 5.
+THEORY OF NUCLEAR POWER PLANT I I__
+OPERATION, FLUIDS, AND THERMODYNAMICS
+-- I00-__ -- I-0
+________ 6.
+PLANT SYSTEMS DESIGNr CONTROL.
+25 0 AND INSTRUMENTATION 30 0 25 0
+-- I 0
+-- I-0
+.-______ 7.
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 30.00 25.00
+-------- 8.
+ADMINISTRATIVE PROCEDURES, 120.00 100.00 TOTALS FINAL GRADE _________________%
 All work done on this enamination is my own. I have neither given nor received aid.
-                                                                                                                                 ~~~~~~~~~~~~~~
+hPPL5C5bT 5~556UbiURE
-hPPL5C5bTI5~556UbiURE
+~~~~~~~~~~~~~~
+I
-s                       UNITED CTATES
+[s >3 "%g s
-[s >3 "%gog,   NUCLEAR REGULATORY COMMISSION
+UNITED CTATES o
-  &       ' y,  o                  REGION il               l 3            -$   101 M ARIETTA STREET, N.W., SulTE 2900 )
+NUCLEAR REGULATORY COMMISSION g,
-* 8 o                       ATLANTA, GEORGIA 30323 s.,
+' y, o
-               /                                           ,
+REGION il l
-l l
+101 M ARIETTA STREET, N.W., SulTE 2900
-k
+)
+ATLANTA, GEORGIA 30323 o
+s.,
+/
+l k
-n
+n 5.
-: 5. THEORY OF NUCLEAR POWER PLANT OPERATIONr FLUIDSr AND                 PAGE 2 QUESTION              5.01               (2.00)
+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%.
@@ Line 288: / Line 392: @@
 (c) Increasing Tavs.(Any rod)
 (d) Increasing the boron concentration. (Any tod).
-QUESTION              5.02               ( .50)
+QUESTION 5.02
+(.50)
 A reactor that is prompt critical is also supercritical. TRUE or FALSE?
-GUESTION              5.03               ( .50)
+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)
+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>
+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)
+QUESTION 5.06 (1.00)
 Explain how water sets in the air receiving tanks.
-(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
+(***** CATEGORY 05 CONTINUED ON NEXT PAGE
+*****)
 l l
 A
-g4 E800                       UNITED STATES
+g4 E800 UNITED STATES
-                   #p          -'
+#p NUCLEAR REGULATORY COMMISSION
-NUCLEAR REGULATORY COMMISSION
+[
-[      f,        'g                  REGION il 5                 g     101 MARIETTA STREET, N.W., SulTE 2000
+'g REGION il f,
-* 8           ATLANTA, GEORGIA 30323
+g
-                  \...../                                                                                                             e 4
+MARIETTA STREET, N.W., SulTE 2000 8
+ATLANTA, GEORGIA 30323
+\\...../
+e 4
 J
 i 5
@@ Line 313: / Line 424: @@
 a
-r
+r 5.
-: 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDSr AND                 PAGE      ____                          ______________________________________
+THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDSr AND PAGE-3-
-QUESTION             5.07               (1.00)
+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)
+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)
+OUESTION 5.09 (1.00)
 Explain how increasing the OTSG level increases the power level.
-QUESTION             5.10               (1.00)
+QUESTION 5.10 (1.00)
 Explain how gas accumulation in the RCS can block reflux boiling.
-QUESTION             5.11               (1.00)
+QUESTION 5.11 (1.00)
 What problems can occur due to boron precipitation during a LOCA?
-QUESTION             5.12               (1.00)
+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)
+QUESTION 5.13 (1.00)
 Why is there a total gas limit on gases dissolved in the RCS?
-l QUESTION             5.14               (1.00)
+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 *****)
 l l
-I.                                                                                       )
+I.
+)
-UNITED STATES g,fsP K8Cg'{e                          p,                     NUCLEAR REIULATORY COMMISSION 2      y,                                o                                    REGION il 5                                    ..                          101 MARIETTA STREET, N.W., SulTE 2900 l
+g,fsP K8Cg'{e UNITED STATES NUCLEAR REIULATORY COMMISSION p,
-  *
+o
-* ATLANTA, GEORGtA 30323 F
+REGION il y,
+101 MARIETTA STREET, N.W., SulTE 2900 l
+ATLANTA, GEORGtA 30323 F
-r
+r 5.
-: 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND                 PAGE 4 QUESTION             5.15              (1.00)
+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)
+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)
+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)
+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)
+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)
+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.
@@ Line 365: / Line 480: @@
 i
-                                                                                                                                                 .. y g>S 814                 UNITED STATES 9
+.. y g>S 814 UNITED STATES 9
-(   f, g
+(
-NUCLEAR REOULATORY COMMISSION REGION il 5             g   101 MARIETTA STREET, N.W., SulTE 2000
+NUCLEAR REOULATORY COMMISSION REGION il g
-* 4         ATLANTA, GEORGIA 30323 o,
+f, 5
-s,...../
+g 101 MARIETTA STREET, N.W., SulTE 2000 4
+ATLANTA, GEORGIA 30323 o,s,...../
 I
 r.
-: 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND                 PAGE 5 QUESTION              5.21             (1.50)
+.
+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)
+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)
+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)
+QUESTION 5.24 (1.00)
 List the four requirements necessary in order to establish natural circulation.
-QUESTION              5.25             (1.00)
+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)
+OUESTION 5.26 (1.50)
 What is the bases for stopping the reactor coolant pumps during a LOCA?
-i GUESTION              5.27             (1.00)
+GUESTION 5.27 (1.00) i What is the change in reactivity associated with a change in Keff from 0.92 to 1.004?
-What is the change in reactivity associated with a change in Keff from 0.92 to 1.004?
+I i
-I i                               (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
+(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
+sd 400 UNITED STATES g=
+,9'o$
+NUCLEAR REGULATORY COMMISSION f,
+g REGION il 5
+g 101 MARIETTA STREET, N.W., SulTE 2900 ATLANTA, GEORGIA 30323
+'+,.....$
+E i '
+t 1
+1
+t a
+l
+l e
+i
-sd 400                                              UNITED STATES
+.
-                       #          ,9'o$
+THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6
-NUCLEAR REGULATORY COMMISSION g=
+QUESTION 5.28 (1.00)
-                  .            f,     g                                             REGION il 5                   g                                101 MARIETTA STREET, N.W., SulTE 2900
-                  *
-* ATLANTA, GEORGIA 30323
-                        '+, .....$                                                                                                               l E
-i' t
-4
-t
-a 4
-l l
-e i
-: 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     *****)
+(***** END OF CATEGORY 05 *****)
-gd K800                                     UNITED STATES NUCLEAR RE2ULATORY COXMISSION l'
+gd K800 UNITED STATES NUCLEAR RE2ULATORY COXMISSION l'
+'(
-                                   '(g 2
+REoioN u 0
-REoioN u 101 MARIETTA STREET. N.W., SulTE 2000 o                                           ATLANTA, GEORGIA 30323 s,
+g 101 MARIETTA STREET. N.W., SulTE 2000 2
-                                /
+ATLANTA, GEORGIA 30323 os,
-: 6.       PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION                      PAGE 7-GUESTION              6.01                      (1.00)
+/
+.
+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.
@@ Line 419: / Line 543: @@
 : c. a narrow ratise cold les RTD.
 : d. a wide ranse cold les RTD.
-QUESTION              6.02                      (1.00)
+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)
+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)
+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)
+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)
+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 *****)
+(***** CATEGORY 06 CONTINUED ON NEXT PAGE
+*****)
-SA 8 8004                  UNITED STATES
+SA 8 8004 UNITED STATES
-                       'o   NUCLEAR RESULATORY COMMISSION
+:./st
-:./st f,
+'o NUCLEAR RESULATORY COMMISSION 4
-g                REGION il 7                      g   101 MAAlETTA STREET, N.W., SulTE 2000
+g REGION il f,
-* 2 o                               ATLANTA, GEORGIA 30323 s...../
+g
+MAAlETTA STREET, N.W., SulTE 2000 2
+ATLANTA, GEORGIA 30323 os...../
 I e
-                                                                           =
+=
 f
 i 1
@@ Line 446: / Line 573: @@
 f l
-: 6.            PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION                                                                                               PAGE        8 QUESTION                 6.07                            (1.00)
+.
+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)
+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)
+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)
+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
+OUESTION 6.11 (1.00) 1 List two different systems whose pumps may be used to fill the Fuel Transfer Canal.
-Transfer Canal.
+l I
-I GUESTION                 6.12                            (1.00)
+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
+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.
-,                    OUESTION                 6.13                            (1.00) 1 Describe all conditions that will cause a Unit 2 Reactor Coolant Pump seal
+(***** CATEGORY 06 CONTINUED ON NEXT PAGE
-,                      return valve to automatically close.
+*****)
-(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
 i
-    - - - . -%.-i,a-        --*-y.,,..--y-     - .-e.,,-- ---,---.%,y9
+-%.-i,a-
-                                                                    ,  p ,,,q,y    .,,---p.-,w,y,,,v_
+--*-y.,,..--y-
-                                                                                         -y           ,, y, y y-,gy,,-,,y .y.-, y-yy.y .r.-wy-9, qu - y ,y.,.f. ,.-e ,-,s,-,,.,ym,9      ww-y,.   -.,w-. y.y
+-.-e.,,--
+---,---.%,y9
+,,,q,y
+.,,---p.-,w,y,,,v_
+y, y
+y-,gy,,-,,y
+.y.-,
+y-yy.y
+.r.-wy-9, qu y
+,y.,.f.
+,.-e
+,-,s,-,,.,ym,9 ww-y,.
+-.,w-.
+y.y p
+-y
+skS E8h GlTED STATES
++j g%,
+p NUCLEAR RE2ULATORY COMMISSION REG 10N il g
+.f, g
+g 101 MARIETTA STREET, N.W., SulTE 2000 2
+ATLANTA, GEORCIA 30323 o
+%...../
-p skS E8h                                                                GlTED STATES
+.
-   +j         g%,                                                 NUCLEAR RE2ULATORY COMMISSION g                                                                REG 10N il g         .f,
+PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 9
-.-              g                                                   101 MARIETTA STREET, N.W., SulTE 2000
+QUESTION 6.14 (2.00)
-* 2 o                                                                        ATLANTA, GEORCIA 30323
-   %...../
-: 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)
+QUESTION 6.15 (1.50)
 Explain what the following indications mean from a Vital Inverter Sync Verification Indicator Lamp.
-: a. Lamp is blinkin3+
+a.
+Lamp is blinkin3+
 : b. Lamp is on continuously at half brightness with inverter voltage normal.
-: c. Lamp off with inverter in service.
+c.
-QUESTION               6.16                     (2.00)
+Lamp off with inverter in service.
-  ~~(a) List the protective trips for the SSF Diesel Generator.
+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)
+OUESTION 6.17
+(.50)
 After a trip causing MSRV actuation, at what steam pressure should all MSRVs be reseated?
-OVESTION              6.10                      (1.50)
+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)
+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 *****)
@@ Line 492: / Line 644: @@
 I 1
-p>2 H49                           UNITED STATES fj             %,  NUCLEAR REQULATCRY CO%MISSICN 3                 o                       REGION 11 5                 $   101 MARIETTA STREET, N.W., SulTE 2000 ATLANTA, GEORGIA 30323 o,              [
+p>2 H49 UNITED STATES fj NUCLEAR REQULATCRY CO%MISSICN 3
-: 6.       PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION                      PAGE 10 GUESTION               6.20                     (1.00)
+o REGION 11 5
+MARIETTA STREET, N.W., SulTE 2000 o,
+[
+ATLANTA, GEORGIA 30323
+.
+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)
+OUESTION 6.21 (1.00)
 Where is the Feedwater Pump Seal Injection Sump Pump water normally pumped to?
-QUESTION               6.22                     (1.50)
+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)
+QUESTION 6.23 (2.00)
 List eight Westinghcuse Reactor Coolant Pump start interlocks.
-QUESTION               6.24                     (1.50)
+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)
+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 *****)
+(*****
+END OF CATEGORY 06
+*****)
-g                                                                UNITED STATES
+#p >S Kit g
-                      #p >S Kit                                       NUCLEAR RE2ULATORY COMMISSION 4
+UNITED STATES NUCLEAR RE2ULATORY COMMISSION 4
-    .f,                o                                             REGION il 3                         a                         101 MARIETTA STREET, N.W., SulTE 2000
+o
-* 2                                     ATLANTA, GEORGIA 30323 l                    \...../
+REGION il
+.f, 3
+a 101 MARIETTA STREET, N.W., SulTE 2000 2
+ATLANTA, GEORGIA 30323 l
+\\...../
 i s
 s i
@@ Line 524: / Line 688: @@
 i, 4
 i 1d
-: 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                           PAGE 11
-~~~~R 5656L55iEAt C5NTRUE~~~~~~~~~~~~~~~~~~~~~~~~
+.
-GUESTION             7.01        ( .50)
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11
+~~~~ 5656L55iEAt C5NTRUE~~~~~~~~~~~~~~~~~~~~~~~~
+R 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)
+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)
+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)
+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)
+OUESTION 7.05 (1.00)
 How is a SG causin3 excessive heat transfer identified?
-QUESTION             7.06        (1.00)
+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)
+QUESTION 7.07 (1.50)
 How is ES Channels 1 & 2 actuation verified?
 (r**** CATEGORY 07 CONTINUED ON NEXT PAGE xxxxx)
-"4  4 UNITE 3 STATES 4f. 's      %, NUCLEAR RE2ULATORY COMMISSION E       f,     o                REGION il 5              3   101 MARIETTA STREET,N.W SulTE 2900
+"4 UNITE 3 STATES 4f. 's NUCLEAR RE2ULATORY COMMISSION 4#
-* e o                       ATLANTA, GEORGIA 30323 s.,
+E o
-             /
+REGION il f,
+3
+MARIETTA STREET,N.W SulTE 2900 e
+ATLANTA, GEORGIA 30323 o
+s.,
+/
 p.
-' 1
+1
-                                                                                         )
+)
-l 1
+I
-l I
+i l
-i
+.
-: 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                           PAGE 12 l
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 12
-   --- RA5i6E65iERE               E6RiR5E------------------------
+--- RA5i6E65iERE E6RiR5E------------------------
-i  QUESTION              7.08        (1.00)
+i
-During a LOCA with ES actuated, what is the Reactor Coolant Pump trip criteria?
+QUESTION 7.08 (1.00)
-l i
+During a LOCA with ES actuated, what is the Reactor Coolant Pump trip l
-  QUESTION              7.09        (1.00)
+criteria?
-What criteria is used to secure Emergency Boration from the BWST in the              ;
+i 1
-j   Unanticipated Nuclear Power Production procedure?
+QUESTION 7.09 (1.00)
-GUESTION              7.10        (1.00)
+What criteria is used to secure Emergency Boration from the BWST in the j
-How is feedwater supplied to the SGs during a Blackout if the TD EFWP j    is not available?
+Unanticipated Nuclear Power Production procedure?
-i  00ESTION              7 11        (1.00)
+GUESTION 7.10 (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.
+How is feedwater supplied to the SGs during a Blackout if the TD EFWP is not available?
-i    a. manually secure loads from the main control board i
+j i
+ESTION 7 11 (1.00)
-: b. dispatch an operator to the applicable switchgear to open load breakers
+If a sustained loss of MFB power occurs, followed by ES Channel 1 &2 i
-;   c. reset the ES actuation signal from the main control board                       .
+actuation, the operator should ______, if a ' LOAD SHED' does not occur.
-!   d. manually initiate ' LOAD SHED' on ES Channels 1 &2 i
+i
-:  QUESTION              7.12        (1.50) t
+a.
-;   List three methods to eliminate voids in the Reactor Coolant System.
+manually secure loads from the main control board i
-i GUESTION              7.13        ( .50)
+b.
+dispatch an operator to the applicable switchgear to open load breakers 3
+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?
-i                                                                                      '
+i l
-l l
+l (r***x CATEGORY 07 CONTINUED ON NEXT PAGE *****)
-(r***x CATEGORY 07 CONTINUED ON NEXT PAGE *****)
 i 1
 l l
 h
 i i
-?                                                                                      !
+?
-j                                                                                      i 1
+j i
+4
+,#
+UNITED STATES
+#c NUCLEAR RE20LATO.'aY CO' ''ISSitN l
+['
+REGION 11 g
+f, 5
+g 101 MARIETTA STREET, N.W., SulTE 2000 4
+ATLANTA, GEORGIA 30323
+~s.,. /
-                   #   944,#                             UNITED STATES
+.
-                  #         #c   NUCLEAR RE20LATO.'aY CO'                l ''ISSitN
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 13
-['      f,     g                            REGION 11 5              g   101 MARIETTA STREET, N.W., SulTE 2000
+~~~~ d6EULUU5 EEL U5UTR6L~~~~~~~~~~~~~~~~~~~~~~~~
-* 4                     ATLANTA, GEORGIA 30323
+R OUESTION 7.14 (1.00)
-                ~s.,....  . /
-: 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)
+QUESTION 7.15 (1.00)
 Why is there a minimum level and maximum pressure in the LDST?
-OUESTION                7.16        ( .50)
+OUESTION 7.16
+(.50)
 What is the maximum LPI pump run time.without indicated flow?
-DUESTION                7.17        ( .50)
+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)
+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)
+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)
+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)
+M OUESTION 7.21 (1.00)
 When is generator operation restricted to the envelope of Figure 7.21?
-(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
+(*****
+CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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-L
+l 1
+L
+pS U10 UNITED STATES 9,o,,
+p NUCLEAR RE2ULATORY COMMISSl!N
++
+REGION il 2
+y, g
+s
+MARIETTA STREET, N.W., SulTE 2000 a
+ATLANTA, OEORGIA 30323 o,s,
+/
-pS U10                                                  UNITED STATES p
+.
-                                +
+PROCEDURES - NORMALr ABNORMAL, EMERGENCY AND PAGE 14
-                               ,,         9,o,, NUCLEAR RE2ULATORY COMMISSl!N 2       y,     g                                                 REGION il 3              s                                   101 MARIETTA STREET, N.W., SulTE 2000
+~~~~ 5Di5L55iEAt 55sTR5L
-* a                                          ATLANTA, OEORGIA 30323 o,
+-~~-----------------~~~~
-s,
+R QUESTION 7.22 (1.00)
-                                           /
-: 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)
+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)
+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)
+QUESTION 7.25 (1.00)
 List four different means to minimize internal radiation exposure.
-QUESTION             7.26        (1.00)
+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)
+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)
+QUESTION 7.28 (1.00)
-,  After a loss of CC and HPI to the Reactor Coolant Pumps, what must
+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?
-;  be done prior to reestablishing Component Cooling and the starting of
-;  an HPI pump?
 (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
 l
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+.-~
-d E84g                                                             UNITED STATES
+.m.
-[(j o,,
+._.m_..
-o NUCLEAR REGULATORY COZMISSION REGION il 5                     g                                101 MARIETTA STREET N.W SUITE 2900 8                                             ATLANTA, GEORGIA 30323
+__ -_.._ -. _.. ~.. _ -
-                          \, . . . . . /                                                                                                                                            .
+d E84 UNITED STATES
- 'i i
+[(j g
+o,,
+NUCLEAR REGULATORY COZMISSION o
+REGION il 5
+g 101 MARIETTA STREET N.W SUITE 2900 8
+ATLANTA, GEORGIA 30323
+\\,..... /
+'i i
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+I
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+j i
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+\\
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+I f
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+e%m---.
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+=-w.wa w, sw w -_... r e e so -e
-                                                                                                                                                                             . -.. -   . . . . .~. .-      -    . - .
+.....~..-
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-                                                                                                                                 \
+\\
-PROCEDURES - NORMAL, ABNORMAL, EHERGENCY AND
+.
-: 7.                                                                                                                                                                                     PAGE   15
+PROCEDURES - NORMAL, ABNORMAL, EHERGENCY AND PAGE 15
-               ~~~ EA5i5E55iEAE E5NTs5E----~~~~~~~~-----~~~-~~~                                                                                                                                                       >
+~~~ EA5i5E55iEAE E5NTs5E----~~~~~~~~-----~~~-~~~
-QUESTION                              7 29                                       (1.00)
+QUESTION 7 29 (1.00)
 When-the body of a controlling procedure refers to another procedurer when can the initial procedure be continued?
-ESTION                              7.30                                       (1,00)
+ESTION 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?                                                                                     '
+I What restrictions are applied to allow use of the Reactor Trip Recovery procedure for a plant startup once the cause of the trip has been determined and remedied?
 t s
-                                                                                                                                \                    .g ?
+\\
-(*****                    END OF CATEGORY 07 **?tra)
+?
+.g
+(*****
+END OF CATEGORY 07 **?tra)
 A k
 9
+.m
 (
-s                                                                                 UNITED STATES
+#jn ta#g s
-                 #jn ta#g #,                     *9s           NUCLEAR RESULATCRY COMMISSION o*
+UNITED STATES NUCLEAR RESULATCRY COMMISSION
-               .                                      o                                                               REGION il 3                                       g                101 MARIETTA STREET, N,W., SulTE 2900
+*9 o*
-* 4                                     ATLANTA,31ORGIA 30323
+s o
-                \,
+REGION il 3
-                                             /
+g 101 MARIETTA STREET, N,W., SulTE 2900 4
+ATLANTA,31ORGIA 30323
+\\,
+/
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+l
-l i
+\\
-I
+i I
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-: 8.         ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS                        PAGE 16 GUESTION                        8.01                             (1.00)
+.
+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%
+a.
-: b.         60%
+%
-: c.         70%
+b.
-: d.         80%
+%
-QUESTION                        8.02                             (1.00)
+c.
+%
+d.
+%
+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
+a.
-: b.         150 cpm above background
+cpm above background b.
-: c.         100 cpm above background
+cpm above background c.
-: d.            50 cpm above background QUESTION                        8.03                             (1.00)
+cpm above background d.
+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
+a.
-: b.          400 cpm
+cpm b.
-: c.          350 cpm
+cpm c.
-: d.          240 cpm (xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE *****)
+cpm d.
+cpm (xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE
+*****)
-__ . _ = - _ _ _ - - _ -      . - _ _ _ _ _ . _                . _ . . _ . . _ _ . . _ . _ _ . _ _ _ .. . _ _ _ . .                    m   . . . . ____ _ .         ,
+__. _ = - _ _ _ - - _ -
-f E849#g                                        U%ITED STATES
+m f E849 U%ITED STATES
-  ~
+~
-NUCLEAR RESULATORY COMMISSION se *                     *4
+#g NUCLEAR RESULATORY COMMISSION se *
-                              .?                          o                                   REGION 11 5                            a          101 MARIETTA STREET, N.W., SulTE 2000
+*4
-* e o                                              ATLANTA, GEORGIA 30323
+.?
-                                %...../
+o REGION 11 5
+a 101 MARIETTA STREET, N.W., SulTE 2000 e
+ATLANTA, GEORGIA 30323 o
+%...../
 J J
 l 4
@@ Line 733: / Line 956: @@
 i f
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-i I
+I i
 (-
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 {
-_ ~ ~ _ _ _ _ _ _ _ _ _ . . _ . - . . . _ . . _ _                        . . . _ _ . . . _ _ . . . _ _ . . _ _ .                        -   _ . . - - - _ _ _ . _ - . _ - _ . - - - - - - .
+~ ~
-: 8.       ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS                  PAGE 17 00ESTION               8.04                     (1.00)
+.
+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
+a.
-: b.       Every           7 days
+Every 3 days b.
-: c.       Every 14 days
+Every 7 days c.
-: d.       Every 30 days GUESTION               8.05                     (1.00)
+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
+a.
-: b.        10 days
+days b.
-: c.        12 days
+days c.
-: d.        14 days GUESTION               0.06                     (1.00)
+days d.
+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             ,
+a.
-: b.       6 members, excluding 3 members of minimum operating shift
+members, excluding 4 members of minimum operatin3 shift b.
-: c.       5 members, excluding 4 members of minimum operating shift
+members, excluding 3 members of minimum operating shift c.
-: d.       5 members, excludins 3 members of minimum operating shift
+members, excluding 4 members of minimum operating shift d.
-: e.       6 members, excluding 2 members of minimum operating shift
+members, excludins 3 members of minimum operating shift e.
+members, excluding 2 members of minimum operating shift
 (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
 i
-ghs mi%                                                             UNITED STATES
+ghs mi%
-                        +f                %,                                NUCLEAR REGULATORY COMMISSION f,           g                                                       REGION il 5                         3                             101 MARIETTA STREET.N.W. 5UITE 2000
+UNITED STATES
-* 2 o,                                                                    ATLANTA, GEORGIA 30323 s-
++f NUCLEAR REGULATORY COMMISSION f,
-                                        /
+g REGION il 5
+101 MARIETTA STREET.N.W. 5UITE 2000 2
+ATLANTA, GEORGIA 30323 o,s-
+/
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-    --,.g.- ,_ . - ,-     ,,n.-m,.    -
+--,.g.-
-                                        -,.--r-   - - . , . , ~ . . . , - , ,   .,-----.,,,,,--ym,           ,      ,-- m . _ n-          .,en n ,n e m m _
+,,n.-m,.
-: 8.           ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS                            PAGE   18 QUESTION                         8.07                      (1.00)
+-,.--r-
+., ~..., -,,
+.,-----.,,,,,--ym,
+,-- m. _ n-
+.,en n,n e m m _
+.
+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
+a.
-: b.           NRC, Bethesda, MD
+: NRC, ReS on II, Atlanta, GA i
-%    c.           State of SC, Columbia, SC
+b.
-: d.           INPO, Atlanta, CA
+NRC, Bethesda, MD c.
-: e.           NRC, Resident Inspector's Office QUESTION                         8.08                      (1.50)
+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)
+a.
-: 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)
+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.
-: c.           The stuu is NOT to be removed until after the Red Tag is placed on the equipment.                                                                  (0.5)
+.(0.5) b.
-QUESTION                        8.09                       (1.50)
+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)
+a.
-!    b.           Becomes the reader of EOP should its use be required.                              (0.5)
+May provide relief for Control Room operators.
-: c.           May leave the control room if the Unit is below 200 degrees F.                     (0.5) i
+(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 *****)
 l l
 l L
-s   04                      UNITED STATES
+,d,p *8 880 s
-     ,d,p *8 880
+UNITED STATES
-               ,o,,    NUCLEAR REQULATORY COMMISSION
+,o,,
-    **           o
+NUCLEAR REQULATORY COMMISSION o
-* MEGION 11 5             s      101 MARIETTA STREET, N.W., SulTE 2900
+MEGION 11 5
-* 2             ATLANTA, GEORGIA 30323
+s 101 MARIETTA STREET, N.W., SulTE 2900 2
-     \,
+ATLANTA, GEORGIA 30323
-               /
+\\,
-I l                             ~
+/
+I l
+~
 2
-: 8.        AbtjINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS                              PAGE 19 GUESTION                 8.10                        (1.00)
+.
+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)
+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)
+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)
+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)
+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)
+(**xx*
+CATEGORY 08 CONTINUED ON NEXT PAGE **xxx)
 ?
-E                                                                                                        a
+E a
-ks troog                                                       UNITED STATES
+ks troog UNITED STATES
 ((
-*
+o,,
-     +          o,,
+NUCLEAR REGULATORY COMMISSION
-o NUCLEAR REGULATORY COMMISSION REGIONil 101 MARIETTA STREET, N.W., SUITE 2000 o              #                                        ATLANTA, GEORGIA 30323 s.,...../
++
+o REGIONil 5
+MARIETTA STREET, N.W., SUITE 2000 ATLANTA, GEORGIA 30323 os.,...../
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-: 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS                                PAGE   20 QUESTION          8.15                     (1.00)
+.
+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)
+a.
-: b. In any calendar year                                                                    (0.5)
+In any calendar quarter (0.5) b.
-QUESTION          8.16                     (1.00)
+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?
-ESTION          8.17                     ( .50)
+ESTION 8.17
+(.50)
 If a contaminated, injured person needs immediate medical attention, to where should he/she be transported?
-DUESTION          8.18                     (1.50)
+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 /
+List FIVE locations / teams / centers that the Control Room may communicate with using the Emergency Radio System.
-center only count as one, i.e., Fire Team #1 and Fire Team 42.
+Note: Redundant locations / teams /
-QUESTION          8.19                      (1.00)
+center only count as one, i.e.,
-: 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)
+Fire Team #1 and Fire Team 42.
-: b. For a unit shutdown required by an LCO, what is the minimum shutdown rate?                                                                          (0.5)
+QUESTION 8.19 (1.00) a.
-GUESTION          8.20                     (1.50)
+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 *****)
+(***** CATEGORY 08 CONTINUED ON NEXT PAGE
+*****)
-g      .                                                UNITED STATES
+#p >nascoq#g g
-                           #p >nascoq#g NUCLEAR REGULATORY COMMISSION
+UNITED STATES NUCLEAR REGULATORY COMMISSION
-[     p       g                                                     REGION 11 5             g                               101 MARIETTA STREET, N.W.. SulTE 2900
+[
-* a                                     ATLANTA, GEORGIA 30323
+REGION 11 p
-                           \...../
+g 5
+g 101 MARIETTA STREET, N.W.. SulTE 2900 a
+ATLANTA, GEORGIA 30323
+\\...../
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-: 8.        ADMINISTRATIVE PROCEDURES, CONDITIONSr AND LIMITATIONS                                           PAGE         21 GUESTION                 8.21                        (1.00)
+.
+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)
+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)
+OUESTION 8.23 (1.00)
 What is the bases of the Reactor Building Hydrogen Purge System's operability requirements?
-QUESTION                 8.24                        (1.50)
+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)
+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.
+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.
-QUESTION                 8.26                        (1.50)
+List these TWO conditions.
+QUESTION 8.26 (1.50)
 For operation above 80% power, give the minimum incore instrumentation for axial imbalance measurements.
 I I
-QUESTION                 8.27                        (1.00)
+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 ***************)
+END OF CATEGORY 08
+*****)
+(************* END OF EXAMINATION
+***************)
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-                  UNITED STATES
+# "'%q%,
-                                         +j      # "'%q%,      NUCLEAR REQULATORY COMMISSION
+UNITED STATES
-                                     .                       o                 REGION il 5
++j NUCLEAR REQULATORY COMMISSION o
-                                    *                      .$    101 MARiETT A STREET, N.W., SulTE 2000 ATLANTA, GEORGIA 30323 o,                    [
+REGION il 5
-                                              ' e , , , e **
+MARiETT A STREET, N.W., SulTE 2000 o,
+[
+ATLANTA, GEORGIA 30323
+' e,,, e **
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@@ Line 878: / Line 1,154: @@
 l
-l~              **
+l~
-Checked Control Copy                                                                                                                         ,
+Checked Control Copy Page 1 of 1 i
-Page 1 of 1 i
+Date/ Time OP/1/A/1106/01 ENCLOSURE 4.10 GUIDELINES FOR GENERATOR OPERATION AT REDUCED LOAD 4
-Date/ Time                                                                                                                                        ,
+.._. =,
-OP/1/A/1106/01
+___ -... _., -
-                  .                                                                                                                                   ENCLOSURE 4.10 4
+r u
-GUIDELINES FOR GENERATOR OPERATION AT REDUCED LOAD
+.__ _,_
-                                                                                                                                                                                                                         .._ . = ,
+z.
-r u                                                                                                                              _ ,.            -
-___ -. . . _ . , -                                   ..                                                                          _ _ _ _ _ ,    . _ _ .
-: z.             4.__ _,_                            __
-                                                                                                                                                                                                                                                                                           ---p.
-                                                                                                                                                                                                                                                                                                           .==. ,,
 m.
-                                                                                                                                                                                                                                                                          ~.                                                             .,
+---p.
-                            --                                                                                                                                                                                                                                                        ~
+.==.,,
-40u                                                                                                                                                                                                        .
+~.
-c                                                                                                                                                                    ,/
-s                                                                -
+~
-                                                                                                                                   #
+40u 30c
-i                                                   ._                                                                                                                              ._.                                                       ,__.            ,
+,/
-s-t 10u                  -
+s 200 i
-                                                                                                                                                           -/                                                                                             -
+s-10u
-m                                            .. .                             --                        1                                                                                                                       .
+-/
-as
+t m
-                                  <;              C                                                                                                                                                                                                                                          -
+as C
-I                                                                                                                                                          .                                                                                                                                                      _ _.
+I
 d.
-lou                                                                                                                                                                                                  __            _.. .                                 __g                                _-
+lou
-                                                       .... - ... n                                     .             .
+__g
-                                                                                                                                     .. x                                                                                                                                                                                                  *
+.... -... n
-                                                                                                                                                                                          ..t.                                                  h.=
+.. x 3Qg..
-Qg..                                                                                     -
+..t.
-                                                                                                                                                                                                                          +_.__
+h.=
++ _. _ _
 t-
-                                              ,og _
+,og _
-_-=                                                                .
+_ - =
-                                                                                                                                                                                                           - - = _ ..._   ...
+- - = _...
-c      ._ _.
+c 5 00",-_ ------
-00",-_ ------
+.t-_
-                                                                                                                                                                                                                                                                                               .t-_
+_ _.. _ _.. _ _ + _ _
-__..__..__+__         .
-                                                                                                                                                                                                                                                                                        .. e __..                                   .-
+.. e __..
-                                                                                                                                                                                                                                                               .._..._.t_.._........_..._.....
+_...._..._.t_.._........_..._....... _
-                                                                                                                                                                                                                                                                  ..._._t._......
+..._._t._......
-.. .._ .._
+....._.
-                                                                                                                                                                             . .. .... . ......... . . ..._..t.
+: t....._..t.
-: t. .
+200 300 400 500 600 700 800 900 MECA*4ATT.'s FI 60 R.E 7,1.1
-                  200              300             400             500                600                 700                         800                  900 MECA*4ATT.'s
-!                                                                                                                  FI 60 R.E                   7,1.1
-EQUATION SHEET Where og a m2                                        .
+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
+( 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 2
-                 ~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)
+KE = mv PE = agh peg + keg +PgVg = PE +KE +P Y22 where V = specific 2
-M = (1-K,ggg)                                               SDM = (1.K,ff) x 100%
-ll-Keff2I                                                           Keff
+~7 volume P = Pressure Q = ic (Tout.Tg,)
-!         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
+Q = UA (T,y,-Tsta)
+Q = ilhg.h I p
+P = P,10(SUR)(t) p. p,,t/T SUR = 26.06 T = (B-p)t 1
+P CR (1-K,ggg) = CR II-Keff2)
+CR = S/(1.K,gy) del ta K = (K,gg-1)/K,gg g
+M = (1-K,ggg)
+SDM = (1.K,ff) x 100%
+ll-Keff2I Keff A = A,e-(decay constant)s(t)
+In (2) 0.693 decay constant
+=
+=
+t t
+/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 3
+ft3 = 7.48 gallons I hp = 2.54 x 10 Btu /hr 6
+1 MW = 3.41 x 10 Btu /hr Density =62.4lbg/ft 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 2
+Atm = 14.7 psia = 29.9 in Hg g = 32.174 f t-lbm/lbf-sec C
 m i
-l                                                                                                                     J
+l J
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-T ABLE D-lb                                                      -
+T ABLE D-lb Properties of Dr3 Saturated Steam nontinuets Tempersture Specific volume E.nthalp>
-Properties of Dr3 Saturated Steam nontinuets Tempersture E.nthalp>                      Enttop>
+Enttop>
-Specific volume 1emp,    AI*
+AI*
-Set        Sai                Sat
+: 1emp,
-                    *F     P'"''         Sat         Set         Sat -   E*ap                           Evap psia       liquid       vapor      liquHl               vapor     liquid              ,,p ,,
+*F P'"''
-                                                      'a           O        O n        N o       sj        og        i s
+Sat Set Sat -
-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
+Set Sai Sat E*ap Evap psia liquid vapor liquHl vapor liquid
-.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
+,,p,,
+O O
+N o
+i E
+f
+*)
+'a f
+n o
+sj g
+s 32 0 0s854 001602
+'3306 0.00 1075.8 10.75.8 0.0000 2.1877 2.1877 35 0.09995 0.01602 2947 3.02 1074.1 1077.1 0.0061 2.1709 2.1770 40 0 12170 0 01602 2444 8 03 1071.3 1079.3 0.0162 2.1435 2.1597 45 0.14752 0.01602 20 % 4 13.06 1068 4 1081.5 0.0262 2.1167 2.1429 50 0.17bil 0.01603 1703.2 18.07 1065.6 1083.7 0.0%I 2.0903 2.1264 60 0.2%)
+01604 12061 28.06 1059.9 1088.0 0.0555 2.0393 2.0948 70 0.M31 0.01606 867.9 38.04 1054.3 1092.3 0.0745 1.9902 2.0647 SO 0.5069 0.0160li 6331 48.02 1048.6 1096.6 0.0932 1.9428 2.0%0 90 0.6982 0.01610 468.0 57.99 1042.9 1100.9 0.1115 1.8972 2.0087 100 0.9492 0.01613 350 4 67.97 1037.2 1105.2 0.1295 1.8531 1.9826 110 1.2748 0.01617 265 4 77.94 1031.6 1109.5 0.1417 1.8106 1.9577 120 1.6924 0.01620 203.27 87.92 1025.8 1113.7 0.1645 1.7694 1.9339 130 2.2225 0 01625 157.34 97.90 1020.0 1117.9 0.1816 1.7296 1.9112 140 2.8886 0.01629 123.01 107.89 1014.1 1122.0 0.1984 1.6910 1.8894 150 3.118 0.01634 97.07 117.89 1008.2 1126.1 0.2149 I.6537 1.8685 160 4.741 0.01639 77.29 127.89 1002.3 l 130.2 0.2311 1.6174 1.8485 170 5.992 0.01645 62.06 137.90 996.3 1134.2 0.2472 1.5822 1.8293 180 7.510 0.01651 50.23 147.92 990.2 1138.1 0.2630 1.5480 1.8109 190 9.339 0.01657 40 96 157.95 984.1 1142.0 0.2785 1.5147 1.7932 200 11.526 0.01663 33.64 167.99 977.9 1145.9 0.2938 f.4824 1.7762 210 14.123 0.01670 27.82 178.05 971.6 1149.7 0.3090 1.4508 1.7598 212 14.6 %
+.01672 26.80 180.07 970.3 1850 4 0.3120 1.4446 1.7566 220 17.186 0.01677 23.15 188.13 965.2 1153.4 0.3239 1.4201 1.7440 230 20.780 0.01684 19.382 196.23 958.8 1157.0 0.3387 1.3901 1.7288 1
+24.% 9 0.01692 16.323 208.34 952.2 1160.5 0.3531 1.3609 f.7140 l
+29 825 0.01700 13.821 216.48 945.5 1164 0 0.3675 1.3323 1.6998 260 35 429 0.01709 Il.763 228.64 9 38.7 1167.3 0.3817 l.3043 l.6860 270 41.858 0.01717 10.061 236.84 931.8 1170.6 0.3958 1.2769 l.6727 280 49.203 0.01726 8.645 249.06 924.7 1173.8 0.4096 1.2501 1.6597 290 57.556 0.01735 7.461 259.31 917.5 1876.8 0.4234 1.2238 I.6472 300 67.013 0.01745 6.466 269.59 910.1 1179.7 0 4369 1.1980 1.6350 310 77.68 0.01755 5.626 279.92 902.6 1882.5 0.4504 1.1727 1.6231 320 89 66 0.01765 4.914 290.28 894.9 1185.2 0.4637 1.1478 1.6115 330 103.06 0.01776 4.307 300.68 887.0 1187.7 0.4769 1.1233 1.6002 340 118 01 0.01787 3.788 311.13 879.0 1190.1 0.4900 1.0992 1.5891 j
 l l
 l l
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+l
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+TABLE D.lb Properties of Dr3 Saturated Steam frontinueds Temperaturc Specific solume 8pthalp?
-TABLE D.lb Properties of Dr3 Saturated Steam frontinueds Temperaturc 9,       Specific solume              8pthalp?                   Entropy 7emp.      '
+Entropy 9,
-            *F              Sai          Sai      Sat               Sai        Sai            Sat liquid       vapor,  liquid    Esar     tapor     liquid  Esar    ,,po,
+emp.
-             #      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                 ,
+*F Sai Sai Sat Sai Sai Sat Esar tapor liquid Esar liquid
-  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
+: vapor, liquid
-!          700   3093.7  0 0369       0.0761   823.3      172.1    995.4   0.9905   0.1484  1.1389 l
+,,po, r
-4 3206.2  0 0503       0 0503   902.7        0      902.7    1.0580    0     1.0580 l
+A, A.
+A, s,
+s, s,
+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 %
+.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
+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
+4 3206.2 0 0503 0 0503 902.7 0
+.7 1.0580 0
+.0580 l
 i t_
 b
@@ Line 967: / Line 1,274: @@
 L*
 T A BLE D.la' Propenses of Dr3 Satur. net! Steam +
-Pressure A b.                IP'C'r.c  volume             E nthalp3                          E ntrop3 pren . 7mp.
+Pressure A b.
-p.,,                 $at        $4        Sat                   Sat 9        hque       wpor      liqud     gtar                    ist Esop         ist
+IP'C'r.c volume E nthalp3 E ntrop3 7mp.
-                                                                                   ,,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$71     1.6158 90    320.27 0.01766         4.8%   290.56      894.7     1I85.3     0 4641      1.1471     1.6112 l                    95    324.12 0.01770         4 652  294.56
+pren.
-'                                                                    891.7     l186.2 0 4692          1.1376     1.6066 100 327.81 0.01774            4.432  298.40      888.8     l 187.2 0 4740         1.1286     1.6026 110 334 77 0.01782            4.049  305.66      883.2     1888.9 0 4832          1.1117     1.5946 o
+$at
+$4 Sat Sat ist ist p.,,
+hque wpor liqud gtar
+,,po, 3,q, g Esop r
+o e,
+e, A,
+h, h,
+s, s,
+s, 1.0 101.74 0.01614 333.6 2.0 126.06 0.0162) 173.73. 69.70 1036.3 1106.0. 0.1326 1.84 %
+.9782 93.99 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 1.8625 5.0 162.24 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 1.8292 7.0 176.85 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.%
+.01683 20 089 1 %.16 960.1 l 156.3 0.33 %
+.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
+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%
+.56 894.7 1I85.3 0 4641 1.1471 1.6112 l
+324.12 0.01770 4 652 294.56 891.7 l186.2 0 4692 1.1376 1.6066 100 327.81 0.01774 4.432 298.40 888.8 l 187.2 0 4740 1.1286 1.6026 110 334 77 0.01782 4.049 305.66 883.2 1888.9 0 4832 1.1117 1.5946 o
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+~
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 Tall.E D-la Properties of Dr3 Saturated Sicam trontmurds
-                                                         . Pressure ntbah                      Ennop.s
+. Pressure
-                                      $p    oc    ume Ath     7emp.
+$p oc ume ntbah Ennop.s Ath 7emp.
-press .                                                       Sai       $si                 Sat
+.F Sai ist Sat Sai
-                  .*      .F         Sai        ist        Sat                                 Esap     up,,
+$si Sat press.
-liquid     sapor     lieud    I''P    wapor     lieud p          8           ',         ',         b      4        4,        Jf        Ja        J.
+Esap I''P liquid sapor lieud wapor lieud up,,
-,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
+p 8
-* 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                                                                               .
+b 4
+, J
+J J.
+f a
+341.25 0.01789 3,726 312.44 877.9 1190 4 0.4916 1.0962 1.5876 130 347.32 0 01796 3 455 318.81 872.9 1191.1 0 4995 l.0817 1.5812 140 353.02 0 01802 3.220 324.82 868.2 1193 0 0.5069 1.0682 1.5751 150 356 42 0 01809 3 015 330.51 863.6 1194.1 0.5136 1.05 %
+.5694 160 363.53 0.01815 2.834 -
+.93 859.2 18951 0.5204 1.0436 f.5640 170
+% 8 41 0.01822 2.675 341.09 854 9 1896 0 0.5266 1.0324 1.5590 180 373.06 0,01827 2'532 346.03 850 B II96 9 0.5325 f.0217 1.5542 190 377.51 0.01833 2 404 350 79 846.8 1897.6 0.5381 1.0116 l.5497 200 381.79 0.01839 2.28b 355.36 843.0 1898 4 0.5435 1.0018 1.5453 250 400.95 0.01865 1.8438 376 00 825.1 1201.1 0.5675 0.9588 I.5263 300 417.33 0.01890 1.5433 393.84 8^h9 1202.8 0.5879 0.9225 1.5104 350 431.72 0.01913 1.3260 409.69 794.2 1203.9 0.6056 0.8910 1.4966 400 444.59 0.0193 1.1613 424 0 780.5 1204.5 0 6214 0.8630 1.4844 450 4 %.28 0.0195 1.0320 437.2 767.4 1204.6 0.6356 0.8378 1.4734 500 467.01 0 0197 0.9276 449.4 755.0 1204 4 0.6487 0.8147 I.4634 550 476.94 0 0199 0 8424 4608 743.1 1203.9 0.6608 0.7934 1.4542 600 486.21 0.0201 0 7698 471.6 731.6 1203 2 0.6720 0.7734 1.4454 650 494.90 0.0203 0.7083 481.8 720.5 Yi 2.3 0.6826 0.7548 1.4374 700 503.10 0.0205 0.6554 491.5 709.7 1201.2 0.6925 0.7371 1.4296 750 510.86 0.0207 0.6092 500.8 699.2 1200.0 0.7019 0.7204 1.4223 000
+$18.23 0.0209 0.5687 509.7 688.9 1198.6 0.7108 0.7045 1.4153 850 525.26 0.0210 0.5327 518.3 678.8 0.7194 0.6891 1.4065 900 531.98 0.0212 0.5006 526.6 668.8 1 5.4 0.7275 0.6744 1.4020 950 538 43 0.0214 0 4717 534 6 659.1 l193.7 0.7355 0.6602 1.3957 1000 544.61 0.0216 0 4456 542.4 649.4 1191.8 0.7430 0.6467 1.3897 l100 5 %.31 0.0220 0 4001 557.4 630 4 1187.7 0.7575 0.6205 1.3780 1200
+% 7.22 0.0223 0.M19 571.7 61i.7
+,]J.83.4 0.7711 0.5956 1.3667 1300 577.46 0 0227 0.3293 585 4 593.2 0 7840 0 5719 1.3559 1400 587.10 0 0231 0.3012
+$98.7 574.7 173 4 0 7963 0.5491 1.34 54 1500 5 %.23 0.0235 0 2765 611.6 E 0.8082 0.5269 1.3351 2000 635 82 0.0257 0.1878 671.7 463 4 1135.1 0.8619 0.4230 1.2849 2500 668.13 0.0287 0.1307 730.6 360.5 1091.1 0.9126 0.3197 1.2322 3000 695.M 0.0346 0 0858 802.5 217.8 1020.3 0.9731 0.1885 1.1615 320e.2 705.40 0.0503 0.0503 902.7 0
+.7 1.0580 0
+.0580 i
 c a
-               .                                                                            Propertmf Superhealed Steam' Ahs press.                                                                                                7 mpetasers.4 18as a p .4 i                           3o0             m                aoD          300         eau         too         300       mo         1000        1800      im        3a00
+Propertmf Superhealed Steam' Ahs press.
-                        ,,       .                   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
+mpetasers.4 18as a p.4 i 3o0 m
-                        ,,     .                     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
+aoD 300 eau too 300 mo 1000 1800 im 3a00 392.6 452.3 512 0 571.6 631.2 6908 750 4 809.9 869.5 929.1 988.7 1807.8 I
-                                                                                                                                                                                         - 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
+A...
-: 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
+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...
-: v.                                         22.36            25 43        28 46        31.47       34 47       37.46     40 45      43 44       46 42     49.41     55.37
+.0512 2.1153 2.1720 2.2233 '
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+~lf s
-                                                                                                                                                                                  / l/%.
+L's.'
-s ru''. V w''~s / ;m/
+f t/1 J.,
-    '"in'a'"v                                                                                                                                                              '**'.
+' f 'i.'t i /
-w                                                                                                          n 't v' 'v i '/                         /.v.,                                   ~'
+Al /T / J ' l */ r* T!
-W/i /1/ / t /%.fi                    >         N_ / t/ N'! I i 1W                                            /       2%/s /                    / * '/ *           /    350*7 W1 f f]4/ / K                                  / f%Z i /h.</                                        NL/                 / / 7%^- *:r V ''                             M *F "'
+' l 1 f_
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+t e v
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+'is 11 E I (1.I iN / if f f ECD'e ~f /
-                                                                                                               /%:
+( N/ a Q's,imer$se ens e SsC s - 7" M
-V fhL/ f 6 / NT 1v                e rst s ,
+* tr 7 ' *f 1*[Y'97
-                                                                                                                                                                                  ,/            w
+,'.'1 i LTI.' f* fi I/ i 'if (*
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+."Q4
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+'A 1 A!VM V fMu* *!
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+If4TI (I I '. W k
+* L/ / l/k*%,' I.'
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+'"in'a'"v s ru''. V w''~s / ;m/
+'t v' 'v '/
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+N_ / t/ N'! I i 1W
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+NL/
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+l W F, M f /h; 11
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+NT
+} y g. -
+s
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+'-w f rx i ryu f g [LE AA }
+nsi 1v e rst s,
+.g,f a f fw ff,x
+, f,7 m.
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+Ni V
-                                                                                        % l/           W/of ,g//                                                                                                                                   *
+'w sf Vis'M1 l/ W/of,g//
-                                                                       ){n /l lf,?
+(W JJ
-                                                              '6                                                           // M                              J Y              Lii>                           -3W
+/ MJ
-                                               -Y                      <                                         l'U V                     /         b f                  .' ih V                       =    ' * * .
+/e/h k
-u y,                    pa,,                        ,L;              ,
+IX
-                                                                                                                                                                                   , , . , , , x, ,_ .;                            y
+!V F f,?
-    ,                                 jY                                                            /VM/                 / / K                        A                   '.                ti.' r f .%                            g il fy                                                   -* f./s i) ]<f                                     f JM -                          %                                            * " S*E
+// M J Y Lii>
-                             ,                 J                .
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+'6 ){n /l l%
-                               /V /        \_f   FV                               V                / 'i/ 2 /N                               i ILN
-                                           /V J')%.f                               "a s '/ h)                                   / h                  '
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-                                  /)                                                                                                                        .'i                                             e EOOO    L V n% / :L/ /1                                      // %V /t) '4 / I M*                                                                               i               o y
+/
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+b
-M L.i j.0sA     l F.                                        .
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+,L f
-                               ./AI/          )      I IX      <                                                                                                                       L' W
+,,.,,, x,,_.;
-                                      'Y'        #~h # ^ '' *#                                                 ' ''
+y ih V u y, pa,,
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+ti.' r f.%
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+//
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+y M L.i j.0 F. VY / M V, W J MJ j' fe % /t)
+A. M sA l e
+Y /t /.//t h
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+//,
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+Ye C
+~T L'
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+I IX N
+.
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-                                   >   /r      */! A / f X/Vt / */ / %)?dY4fI-ffQ%/ 6 tJ
+/
-* E t), J \ // >HJ l}                                      h.I l' M g.,G                                                               9
+Yt' A' t/f M ffQ%/
-                                  .r s _*, I A/A3'                          / IM,                    tfXi                   k L'N                        ,       .*                                                                h pgg itA W-                  T4 VI 2LY                      JK              I      't D: h Vb '+ ' '~'
+tJ
-.3               1.4                   1.5                    1.6                      1.7                        1.s Entropy k
+/r
+*/! A / f X/Vt / */ / %)?dY4fI-9 h
+E t), J \\ // >HJ l}
+h.I l' M g.,G
+.r s _*, I A/A3'
+/ IM, tfXi k L'N pgg itA W-T4 VI 2LY JK I
+'t D: h Vb '+ ' '~'
+.3 1.4 1.5 1.6 1.7 1.s Entropy k
-p
+p THEDRY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 22 AN5WERS -- OCONEE 1, 283
-    $. THEDRY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND                                 PAGE 22 AN5WERS -- OCONEE 1,                  283                           -86/04/21-TOM ROGERS ANSWER                5.01             (2.00)
+-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)
+ANSWER 5.02
+(.50)
 TRUE.
-REFERENCE NET, Vol. 3,            NUS, G-15.
+REFERENCE NET, Vol. 3, NUS, G-15.
 DNS, OP-0C-SPS-RT-RK.
-ANSWER                5.03             ( .50)
+ANSWER 5.03
-TRUE REFERENCE ONS: OP-0C-SPS-RT-RBC,                    p.9.
+(.50)
-ANSWER                5.04             ( .50)
+TRUE REFERENCE ONS: OP-0C-SPS-RT-RBC, p.9.
-FALSE
+ANSWER 5.04
-;      REFERENCE ONS, OP-0C-SPS-THF-CTH,                      p.7.
+(.50)
+FALSE REFERENCE
 {
-t
+ONS, OP-0C-SPS-THF-CTH, p.7.
-;   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).
+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
-SA# K800                      UNITED STATES
+SA# K800 UNITED STATES 9'o NUCLEAR REGULATORY COMMISSION
-     #             9'o   NUCLEAR REGULATORY COMMISSION
-   ==                4 3         f,         o                 REG 40N il 5                    g   101 MARIEiTA STREET, N.W., SUITE 2900 os                            ATLANTA, GEORGIA 30323 g!
+==
-. . . . . ,O' I
+3
+o REG 40N il f,
+g
+MARIEiTA STREET, N.W., SUITE 2900 g!
+ATLANTA, GEORGIA 30323 os 9.....,O' I
 I
 h i
@@ Line 1,189: / Line 1,717: @@
 I 1
 i I
-: 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
+THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 23 ANSWERS -- OCONEE 1, 283
-;           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.
+-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)-
+l ANSWER 5.07 (1.00)-
-All rods operableCO.53 i           all rods withdrawn above insertion limits [0.53 REFERENCE ONS, OP-0C-SPS-APC-T47, p.8.
+All rods operableCO.53 3
-lI 4
+i all rods withdrawn above insertion limits [0.53 REFERENCE lI ONS, OP-0C-SPS-APC-T47, p.8.
-ANSWER                     5.08         (1.00)
+ANSWER 5.08 (1.00) 4 (a) The nucleate boiling region [0.5].
-(a) The nucleate boiling region [0.5].
 (b) The superheat region [0.5].
- !          REFERENCE
+REFERENCE ONS, OP-0C-SPS-CM-SGr pp. 12-14.
-:          ONS, OP-0C-SPS-CM-SGr pp. 12-14.
+j ANSWER 5.09 (1.00)
-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.
@@ Line 1,212: / Line 1,739: @@
-                                ># 880                                                                            UNITED STATES
+># 880 UNITED STATES
-                   ?.'                                       .
+?.'
-NUCLEAR REGULATORY COMMISSION                                                                                     !
+NUCLEAR REGULATORY COMMISSION 2
-                      f,                           o                                                REGION il 5                                                    g                   101 MARIETTA STREET N.W SUITE 2900
+o REGION il f,
-               *
+g
-* ATLANTA, GEORGIA 30323 j
+MARIETTA STREET N.W SUITE 2900 ATLANTA, GEORGIA 30323 j
-                                                                                                                                'e
+'e
-                                                                                                                                                                                                       ?
+,% j
-                                                                                                                                   ,% j          .,
+?
-                                                                                                                                                    -.e d:'
+d:'
-                                                                                                                                                           .r    a ..
+-.e
+.r a..
 It' I
-e                                                    ''
+e k
-k c_v
+c_
-                                                                                                                                                                              , ) . _ ''I ( '
+v
-i                                                                                                                                                                                  'M         .. ,
+, ). _ '' ( '
-l                                                                                                                                                                      e                       .. >
+I i
-i
+'M l
-i
+e 1
-l I
+i 1
-I l
+i l
-t l
+I I
-l i
+l t
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 l l
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+i F
-     -...L,_=,   _- . . . _ . . . . . . . _ . . _ _ . . _ _ . - . - _ _ - . _ _ , . . _ _ . , . . . - - _ _ .                       __ _ _ . . _ . . . - .              ... ._ _... _ . _
+l
+l r
+-...L,_=,
-   THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND                                       PAGE 24 ANSWERS -- OCONEE 1,            2R3                            -86/04/21-TOM ROGERS ANSWER               5.10        (1.00)
+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)
+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)
+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)
+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.
+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)
+ANSWER 5.14 (1.00)
 U238 E0.53 Pu240 CO.53 b
-    ..- . - . _ . - .               .   . . _ . .   -   ..    . ..          _ - . _-    . . . . . = _ , . . . . . - . .
+= _,
-T i                        >S 880%                                 UNITED STATES                                              ;
+T i
-}                     +f          Io,,              NUCLEAR REGULATORY COMMISSION
+>S 880%
-                  !                   e                              REGONn I                   $               101 MARIETTA STREET, N.W., SulTE 2000 ATLANTA, GEORGIA 30323 o.
+UNITED STATES
-                       ''' . . . . . *#,u!
+}
-i                                                                                 -
++f Io,,
+NUCLEAR REGULATORY COMMISSION REGONn e
+I 101 MARIETTA STREET, N.W., SulTE 2000
+'''..... *#,u!
+ATLANTA, GEORGIA 30323 o.
 i i
-f l
+i f
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-i I
+l i
-f e
+I f
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-i f
+I i
+f 1
+5.
-,   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.
+THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 25 ANSWERS -- OCONEE 1, 2&3
-ANSWER                5.15           (1.00)
+-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.
+REFERENCE ONS, OP-0C-SPS-RT-RC, p.9.
-ANSWER                5.16           (1.00)
+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.
+j REFERENCE ONS, OP-0C-SPS-RT-RC, p.26.
-ANSWER                5.17           (1.00)
+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
+Yes CO.53, at BOL it can be positive due to a hi h baron concentration CO.5 3
-.
+l 3.
-i      REFERENCE ONS, OP-0C-SPS-RT-RC, p.26, i
+i REFERENCE ONS, OP-0C-SPS-RT-RC, p.26, i
-i ANSWER                5.18           (1.00)
+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.
+i REFERENCE ONS, OP-0C-SPS-RT-FPPr. p.16.
 t
-i 5 E800                                                   UNITED STATES 9
+i 5 E800 UNITED STATES
-                          .#jk
+.#jk 9
-                                                  #o t
+#o NUCLEAR REGULATORY COMMISSION t
-NUCLEAR REGULATORY COMMISSION                                                                                        ,
+p'
-i 2               p'              g                                          REGION il 3                             . g                             101 MARIETTA STREET, N.W., SUITE 2000
+g REGION il i
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-                          %...../
+. g 101 MARIETTA STREET, N.W., SUITE 2000 a
+ATLANTA, GEORGIA 30323
+%...../
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-       ----mm---,,-,-r---                     s    ,-em   w- eww,- +-- n e n- r- e--                    .---r--wn,,--wma----,.v      >m<--,+, -r,m--a. .e a-s.    -- - - - - -     - - --r-+-,-, ---e
+----mm---,,-,-r---
+s
+,-em w-eww,-
++-- n e n-r- e--
+.---r--wn,,--wma----,.v
+>m<--,+,
+-r,m--a.
+.e a-s.
+- - --r-+-,-,
+---e
-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)
+i i
+.
+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.
+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)                                                                                                                                ,
+ANSWER 5.20 (1.50)
-(a) Worth of a fully inserted rod 0 100% power with all other rods
+(a) Worth of a fully inserted rod 0 100% power with all other rods fully withdrawn. E0.53.
-,             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.
-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)
-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
+REFERENCE DNS, OP-0C-SPS-RT-SM, pp. 20-21.
-,     DNS, OP-0C-SPS-RT-SM, pp. 20-21.
+ANSWER 5.22 (1.00)
-ANSWER                     5.22                 (1.00)
 (a) MTC E0.53 (b) Doppler E0.53 REFERENCE ONS, OP-0C-SPS-RT-RC, p.20.
 f i
-                                    . _ .   - - _ .   . _ _ _ _ .      . - - . .. _. - - - . _ . . _ ,           , . _ = . . _ - - . . , _ , _ , - - . .
+,. _ =.. _ - -.., _, _, - -..
+n Rico UNITED STATES a
+/
+%'o NUCLEAR REGULATORY COMMISSION
+[
+REGIONil 5
+Y 101 MARIETTA 87REET.N.W SutTE 2tGO 4
+ATLANTA, GEORGIA 30323 5
+n I
+I i
-naRico                 UNITED STATES
+.
-      /             NUCLEAR REGULATORY COMMISSION
+THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 27 ANSWERS -- OCONEE 1, 2&3
-[           %'o                REGIONil 5             Y   101 MARIETTA 87REET.N.W SutTE 2tGO 4         ATLANTA, GEORGIA 30323
+-86/04/21-TOM ROGERS AMSWER 5.23 (1.00)
-      %         n5 I
-I                                                        i
-: 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.
+Dissolved gases in the RCS.
-: 3. Impurities in the BWST.
+.
-: 4. Nitrogen in the CFTs.
+Fission gases from clad failure.
+.
+Impurities in the BWST.
+.
+Nitrogen in the CFTs.
+: 6. TrH Pur *$y t i c d e c o m p o s i t i o n.em kevp N A4e(.
 : 5. RadioJ
-: 6. TrH Pur *$y
+* s frw REFERENCE ONSr OP-0C-SPS-PTR-AM-2, p.14.
-* st i frw c d e c o m p o s i t i o n .em kevp N A4e(.
+ANSWER 5.24 (1.00) 0 0.25 points each 1.
-REFERENCE ONSr OP-0C-SPS-PTR-AM-2, p.14.
+Heat sink 2.
-ANSWER                  5.24                   (1.00) 0 0.25 points each
+Heat source 3.
-: 1. Heat sink
+Coupling 4.
-: 2. Heat source
+Thermal centers of OTSG > Core.
-: 3. Coupling
-: 4. Thermal centers of OTSG > Core.
 REFERENCE ONS, OP-0C-SPS-PTR-AM-1, p.42.
-ANSWER                  5.25                    (1.00)
+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)
+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.
-g>D K8Cg                  UNITED STATES 4          [og  NUCLEA". RESULATORY COMMISSION
+g>D K8Cg UNITED STATES
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+[o NUCLEA". RESULATORY COMMISSION 4
-o                REGION il 5               $   101 MARIETTA STREET N.W., SUITE 2900
+g
-* e o                        ATLANTA, GEORGIA 30323 s...../
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-I i                                            . ..          _ -. --- - - - .. .-
+I i
 f.
-: 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.
+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
+ANSWER 5.28 (1.00) 1.4 DPH i
-REFERENCE MNS OP-MC-SPS-RT-RK,                          p.7.
+REFERENCE MNS OP-MC-SPS-RT-RK, p.7.
 HBR RXTH-HO-1, 43,p.3.
 l
-b
+b ffsgs3 K8C (o
-         %                  UNITED STATES ffsgs3 K8C(o  NUCLEAR RECULATORY COMMISSION
+NUCLEAR RECULATORY COMMISSION UNITED STATES o
-&     f,     o                 REGION tl 3            g   101 MARIETTA ST REET, N.W., SUITE 2900 o
+REGION tl f,
-* ATL ANTA, GEO9GIA 30323
+g
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+MARIETTA ST REET, N.W., SUITE 2900 ATL ANTA, GEO9GIA 30323 o
+%...../
+/
-I l
+I 6.
-: 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.
+PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 29 ANSWERS -- OCONEE 1, 2&3
-ANSWER                   6.02                        (1.00)
+-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.
+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)
+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)
+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.
+REFERENCE OP-0C-SPS-CM-CRD, p.7.
-yg>8 "80 0                  UNITED STATES 9(og, NUCLEAR REGULATOhY COMMISSION r
+y >8 "80 g
+UNITED STATES
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+(o NUCLEAR REGULATOhY COMMISSION g,
-REGION il 101 MARIETTA STREET, N.W., SulTE 2900    '
+REGION il g
-o*              '8          ATLANTA, GEORGIA 30373 t
+f, I
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+a 101 MARIETTA STREET, N.W., SulTE 2900 r
+'8 ATLANTA, GEORGIA 30373 o*
+t l
+l
-i                                                                                             l l
+i l
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+f 6.
-: 6.       PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION                      PAGE 30 ANSWERS -- OCONEE 1r 2&3                                  -86/04/21-TOM ROGERS i
+PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 30 ANSWERS -- OCONEE 1r 2&3
-ANSWER                 6.06                     (1.00) 8.
+-86/04/21-TOM ROGERS i
-(55%(7/8)=48.125%, 55%(1.4/1%)=77 inches, 48.125(1.4/1%)=67.375 inchese 4
+ANSWER 6.06 (1.00) 8.
--67.375=9.625 inches cut of avs for 7 rods plus one for the dropped rod.
+(55%(7/8)=48.125%, 55%(1.4/1%)=77 inches, 48.125(1.4/1%)=67.375 inchese 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)
+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)
+ANSWER 6.08 (1.00)
-(a) Scinillation (NaI) E.53 (b) Gamma E.53 REFERENCE l        ONSr DP-0C-SPS-IC-PRM I
+(a) Scinillation (NaI) E.53 (b) Gamma E.53 REFERENCE l
-ANSWER                6.09                      (1.00)
+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.
+REFERENCE l
-ANSWER                6.10                      (1.00) l        NI-5 or NI-9.
+ONS, OP-0C-SPS-IC-NI, p.18.
-i        REFERENCE l        ONS, OP-0C-SPS-SY-LPI,                               p.8.
+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
@@ Line 1,415: / Line 1,989: @@
 (
-                                  >2 K8cg                                                               UNITED STATES
+>2 K8cg UNITED STATES
-                       /.                               'o.
+/.
-NUCLEAR RECULATORY COMMISSION 3                  .f,                   o                                             REGION il j                  $                                          g                               101 MARIETTA STREET, N.W., SulTE 2000
+'o.
-* a                                      ATLANTA, GEORGIA 30323 o.
+NUCLEAR RECULATORY COMMISSION 3
-                                 $ggg4 l
+o REGION il
+.f, j
+g 101 MARIETTA STREET, N.W., SulTE 2000 a
+o.
+ATLANTA, GEORGIA 30323
+$ggg4 l
 l i
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@@ Line 1,427: / Line 2,006: @@
 i 1
 i J
-: 6.        PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION                       PAGE 31 ANSWERS -- OCONEE 1,                                2&3    -86/04/21-TOM ROGERS ANSWER                   6.11                        (1.00)
+.
+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)
+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)
+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.
+Loss of seel injection with loss of CCW flow.C.5]
-ANSWER                   6.14                        (2.00) 0 0.5 points each
+REFERENCE ONS, OP-0C-SPS-SY-HPI.
-: 1. 230 kv yellow bus isolates.
+p.3.
+ANSWER 6.14 (2.00) 0 0.5 points each 1.
+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.
+Aligns other Keowee Unit to underground feeder to supply CT-4.
+.
+Starts both Keowee Hydro Units.
 REFERENCE ONS, OP-0C-SPS-EL-EPD, pp.24-25.
 i
 i k
-pS 880                                                          UNITED STATES
+pS 880 UNITED STATES
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+%,'o NUCLEAR RE*uuLATORY COMMISSION g4 P
-!                 5                                                  101 MARIETTA STREET, N.W., SUITE 2000
+O o
-* I o                                                                  ATLANTA, GEORGIA 30323
+REGION il 5
-                    +s
+MARIETTA STREET, N.W., SUITE 2000 I
-                                      /
+o ATLANTA, GEORGIA 30323
++s
+/
 t i
 t i
 f 4
-    * - - - = --w     ,y--ve-.      .,     - ~ , , - -<-.~.-w__,,,    , , - - , _ _ ,         ,         _.--,--...,_--,,.,....,-.--_,_,--.,._-,..,.-,--..-._,,e,,-.-         ..---- +-
+* - - - = --w
-: 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:
+,y--ve-.
-: a.      Two sources are out of phase.
+- ~,, -
-: b.      AC line volatse is low.
+-<-.~.-w__,,,
-: c.      Two sources are in phase.
+_.--,--...,_--,,.,....,-.--_,_,--.,._-,..,.-,--..-._,,e,,-.-
+..---- +-
+.
+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.
+ANSWER 6.16 (2.00) y f,,, jf,I4 1 c / J p A b b r" f 0 0.5 points each:
-                                                                                    .M l*W I''b #'
+(a) 1.
+Engine overspeed.
+.M l*W I''b #'
 jp,,*
-: 2. Generator Diff. Protection.                            .
+"2 84}k 2.
-: 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.
+Generator Diff. Protection.
-ANSWER                       6.17                      ( .50) 1010 psis.
+G fety
+//lgk Cr kcr..tc.
+Pr.ssue 3.
+Low-Low Lube Oil Pressure.
+d'N M' 8" "N O
+(b).t+t the above.
+t-3 8 Mrsif Vo her REFERENCE p.13.j g.(o8.
+ONS, OP-0C-SPS-SSF-DG, 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:
+ANSWER 6.18 (1.50) 0 0.5 points each:
-: 1. Compressor run continuously.
+.
-: 2. At 95 psi decreasing, unloader valves close.
+Compressor run continuously.
-: 3. At 100 psi increasing, unloader valves open.
+.
+At 95 psi decreasing, unloader valves close.
+.
+At 100 psi increasing, unloader valves open.
 REFERENCE ONSr OP-0C-SPS-SY-IAr p.14.
 (
-      >S "%g#               UNITED STATES ff o
+>S "%g#
-NUCLEAR RECULATORY COMMISSION REGION il
+UNITED STATES ff NUCLEAR RECULATORY COMMISSION o
-! $           g   101 MARIETTA STREET. N.W., SulTE 2000 i                       ATLANTA, GEORGIA 30323
+REGION il g
-;  \...../
+MARIETTA STREET. N.W., SulTE 2000 i
+ATLANTA, GEORGIA 30323
+\\...../
 l
 i d
-o         PLANT SYSTEMS DESIGNr CONTROL, AND INSTRUMENTATION                      PAGE 33 ANSWERS -- OCONEE le 283                                   -86/04/21-TOM ROGERS ANSWER                       6.19                      (1.00)
+o 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)
+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)
+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:
+ANSWER 6.22 (1.50) 0 0.5 points each:
-: 1. Pull out Safety Rods.
+.
+Pull out Safety Rods.
 : 2. Operate Res Rods for a group with a failed power supply.
-: 3. To recover a dropped rod.
+.
+To recover a dropped rod.
 REFERENCE OP-0C-SPS-IC-CRT, p.14.
-<                                                                                            u
+u
-   - - - -  -      ,       - .    . . .   . . . . . - . ~    _ , - - . .- - . -- .
+..... -. ~
-UNITED STATES
+#p568 "'Gog'a UNITED STATES NUCLEAR RESULATORY COMMISSION g.
-              #p568 "'Gog'a    NUCLEAR RESULATORY COMMISSION
+Ao RIGION il
-: g.          A
+~
-           ~       f,   o                              RIGION il 7             $       101 MARIETTA STREET, N.W., SulTE 2900
+f, 7
-$           o,                          ATLANTA. GEORGIA 30323 l
+MARIETTA STREET, N.W., SulTE 2900 o,
-              +s
+ATLANTA. GEORGIA 30323
-                       /
++s
+/
+l
 )
 i i.
@@ Line 1,517: / Line 2,136: @@
 i e
 J
-: 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.
+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:
+.
+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.
+Seal injection flow at least 22 spm.
-: 5. ti seal dp at least 275 psid.
+.
+CC flow st least 575 spm.
+.
+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.
+.
+Tc greater than 430F.
 REFERENCE ONS, OP-0C-SPS-CH-CPS, p.21.
-ANSWER                   6.24                        (1.50)
+ANSWER 6.24 (1.50)
 Normal-LP Service Water.
 BU-HP Service Water.
@@ Line 1,535: / Line 2,162: @@
 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.
+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.
-tma Kr309                 UNITED STATES
+tm Kr30 UNITED STATES a
-          #p          #
-NUCLEAR RECULATORY CCMMISSION 3
+#p
-s'               *\                 REGION il f,      g
+*\\
-  -                     t   101 MARIETTA STREET, N.W., SUITE 2000
+NUCLEAR RECULATORY CCMMISSION s'
-* 2         ATLANTA, GEORGIA 30323 6
+f,
-          '+9.....
+g REGION il t
-i
+MARIETTA STREET, N.W., SUITE 2000 2
+ATLANTA, GEORGIA 30323
+'+9.....
+i
-                                                   ._         .-       .              .-           .=                                         .. . _. .
+.=
 f
 i
-   )
+)
-  ;     6.        PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION                                                                                         PAGE         35 1
+.
-ANSWERe -- OCONEE 1,                                 2&3                                               -86/04/21-TOM ROGERS i
+PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 35 1
-I         REFERENCE ONS, OP-0C-SPS-SY-LPH, p.8.
+ANSWERe -- OCONEE 1, 2&3
+-86/04/21-TOM ROGERS i
+I REFERENCE ONS, OP-0C-SPS-SY-LPH, p.8.
 4
 i
- 'e n
+'e n
 a J
 i
 t
- )
+)
 l t
 i a
@@ Line 1,570: / Line 2,202: @@
 I I
-UNITED STATES
+(( >S Kirg*[q,,
-         >S Kirg*[q,,
+UNITED STATES NUCLEAR RESULATORY COZZISSl!N f,
-((
+g REGION il 5
-f,    g g
+g
-NUCLEAR RESULATORY COZZISSl!N REGION il
+' 101 MARIETTA STREET, N.W., SulTE 2900 8
-                       ' 101 MARIETTA STREET, N.W., SulTE 2900
+ATLANTA, GEORGIA 30323
-      ,         8              ATLANTA, GEORGIA 30323 s.,...../
+,s.,...../
-                                                                                                                            ,^
+.,^
-s %*    s
+s %*
-                                                               - _ _ _ . _ _ _ . _ . _ _ . _ . _ _ _ . . _ _ _ _ _ _ . _        _1
+s
+_1
-            .             -              ..                ..   .-      .  =-       - --                 . .              .--.. .- - . - . - .                       . .      .  . ..
+=-
-e i                     7.                  PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                                                                                 PAGE   36      ;
+e i
-                      ~~~~R5656E655Cd[~66 TR5E---------~~-------------
+.
-ANSWERS -- OCONEE 1,                     2&3                             -86/04/21-TOM ROGERS t                                                                                                                                                                                     -
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 36
-ANSWER                               7.01     ( .50)
+~~~~ 5656E655Cd[~66 TR5E---------~~-------------
-;                           TRUE                                                                                                                                                      ;
+R ANSWERS -- OCONEE 1, 2&3
-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.                                                                                                                                               ,
+-86/04/21-TOM ROGERS t
-,                                                                                                                                                                                     t
+ANSWER 7.01
-;                           REFERENCE ONS, OP-0C-SPS-SY-CC, p.16.
+(.50)
-i                                                                                                                                                                                    .
+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].
+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
-ANSWER                               7.03     (1.50) i l                          When PZR level cannot bo maintained above 220' E0.5] with letdown isolated                                                                                !
+I ANSWER 7.05 (1.00)
-I                           E0.53 and full HPI flow E0.5].
+~
-l                           REFERENCE i                          ONS, EP/1/A/1800/01, SEC. 504, i
+i l
-i
+i l
-:                     ANSWER                               ?.04     (1.00) i                          Trip both EHC pumps.
+By lower and/or decce sino steam pressure E0.5] or high SG 1evel E0.5].
-t j                          REFERENCE                                                                                                                                                   l j                          ONS, EP/1/A/1800/01,                      p.4.
+l l
-I                                                                                                                                                                                      ;
+REFERENCE i
-i i
+ONS, EP/1/A/1800/01, p.33.
-I ANSWER                               7.05
+l
-                                                                                                                                                                                      ~
+)
-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
 ]
@@ Line 1,609: / Line 2,258: @@
 7
 I 4
-                                                                                                                                                                                     r i
+r
-I                                                                                                                                                                                      5
+i I
-p ta4                                            UNITED STATES 1      y4 .'              o o
+p ta4 UNITED STATES y.'
-NUCLEAR RE20LATORY COMMISSIUN
+o
-       .       y,                                             REG 40N il
+NUCLEAR RE20LATORY COMMISSIUN 1
-,      2                    $                 101 MARIETTA STREET,N.W 50lTE 2900
+o REG 40N il y,
- ;
+101 MARIETTA STREET,N.W 50lTE 2900 t
-* t                           ATLANTA, GEORGIA 30323 i
+ATLANTA, GEORGIA 30323 9....8 4
-9....8 i
+i i
 i i
 I
@@ Line 1,627: / Line 2,277: @@
 k l
-   ~.      . - _ -          ._ -      _-   . - -. _ -  _. _ . . .   -            -     - -. . __ -    -.
+~.
-;     7.       PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                                  PAGE     37
+.
-      ~~~~RA6i6E66fEAE 56sTR6E-----------~~~----------
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 37
-g i      ANSWERS -- OCONEE 1,                        2&3            -86/04/21-TOM ROGERS i
+~~~~ A6i6E66fEAE 56sTR6E-----------~~~----------
-!f 1     ANSWER                     7.06           (1.00) l     Open all RCS high point vents. (SG & RV head vents)
+R g
-I REFERENCE i      ONS, EP, p.22.
+i ANSWERS -- OCONEE 1, 2&3
-i ANSWER                     7.07           (1.50)
+-86/04/21-TOM ROGERS i
-)      0 0.5 points each:
+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)
+)
+0.5 points each:
 : 1. All blue ES RZ module ' AUTO' lights on.
-:     2. All white ES RZ " POSITION' 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.
+ES HP Injection Channels A,B,C Trip alarms on.
-i i     ANSWER                     7.00           (1.00)
+i REFERENCE i
-,1 j      Any subcooling margin =0F.
+DNS, EP, p.62.
-t 1      REFERENCE
+i i
- !     ONS, EP, p.62.
+ANSWER 7.00 (1.00)
-l
+,1 j
-,     ANSWER                     7.09           (1.00)
+Any subcooling margin =0F.
+REFERENCE t
+ONS, EP, p.62.
+l ANSWER 7.09 (1.00)
 Doth IR <E-6 amps and decreasins.
-REFERENCE
+REFERENCE ONS, EP, p.69.
-!      ONS, EP, p.69.
+ANSWER 7.10 (1,00) l SSF Aux Service Water ' Ump.
-!     ANSWER                     7.10           (1,00) l      SSF Aux Service Water ' Ump.
+l REFERENCE l
-l      REFERENCE l      ONS, AP/1/A/1700/11, p.18.
+ONS, AP/1/A/1700/11, p.18.
 i i
-i
+i O
-!        O 4
+i
-i i
+i l
-l i
+i 1
-88 %                                                                                     UNITED STATES
+88 %
-                     ,/.        y, 9
+UNITED STATES
-g NUCLEAR RECULATORY COMMISSION REGION il 5                                     3                              101 MARIETTA STREET, N.W., SUITE 2000
+,/.
-* 2                                                 ATLANTA, GEORGIA 30323
+NUCLEAR RECULATORY COMMISSION REGION il g
-                     \...../
+y, 5
+101 MARIETTA STREET, N.W., SUITE 2000 2
+ATLANTA, GEORGIA 30323
+\\...../
 i 1
 (
@@ Line 1,669: / Line 2,330: @@
 I 1
 i 4
- \
+\\
 i
 i t
@@ Line 1,680: / Line 2,341: @@
 s t
 i i
-"Wm1+' an.--->        -- e w -we g
+"Wm1+'
-* my,yh->*-wm+-g-                              y  q* ye q wFw p Cp.WW.                                yNM9M'"m'g,       - - "
+an.--->
-: 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                            PAGE   38
+-- e w -we g
-       ~~~~R A5i5E55i5AE            555TR5E-~~-~~~~----------------
+* my,yh->*-wm+-g-y q* ye q wFw p Cp.WW.
-ANSWERS -- OCONEE             1,  2&3         -86/04/21-TOM ROGERS
+yNM9M'"m'g,
- '' ANSWER                   7.11        (1.00)
-       $b REFERENCE AP/1/A/1700/11. p.5.
+.
-ANSWER                7.12        (1.50)
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 38
-Any 3 0 0.5 points each
+~~~~ A5i5E55i5AE 555TR5E-~~-~~~~----------------
-: 1. Repressurizing RCS with heaters.
+R ANSWERS -- OCONEE 1,
-: 2. Venting RCS high points to RB.
+&3
-: 3. Running RCP.
+-86/04/21-TOM ROGERS
-: 4. Waiting for ambient cooling to condense voids.
+'' ANSWER 7.11 (1.00)
+$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.
+.
+Venting RCS high points to RB.
+.
+Running RCP.
+.
+Waiting for ambient cooling to condense voids.
 REFERENCE ONS, EP, p.140.
-ANSWER                7.13        ( .50)
+ANSWER 7.13
-        <50F/HR.
+(.50)
+<50F/HR.
 REFERENCE ONS, EPr p.140.
-    ~~ ANSWER                7.14        (1.00)
+~~ ANSWER 7.14 (1.00)
-Unit 1- RC pressure >100 psis or RC temp >190F E.53.
+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)
+~~' ANSWER 7.15 (1.00) eventofHPIEmers. Injection [s]
-Pprur-To prevent gas from entering HPI pumps in the               eventofHPIEmers. Injection [s]
+Pprur-To prevent gas from entering HPI pumps in the
-REFERENCE
+'O
-                                  ~
+*I
-                                                 'O   *I             #"   '
+~
-ONS, OP-0C-SPS-SY-HPI.
+REFERENCE ONS, OP-0C-SPS-SY-HPI.
-Ho%                   UNITED STATES
+Ho%
-     +f          Io,,  NUCLEAR RECULATORY COMMISSION 7
+UNITED STATES
-f,       g                REGION il
++f Io,,
-  -                  g   101 MARIETTA STREET, N.W SUITE 2900 o.,               8         ATLANTA, GEORGIA 30323 l
+NUCLEAR RECULATORY COMMISSION g
-                                                                                       \
+REGION il 7
-t l
+f, g
-l                                                                                      1 l
+MARIETTA STREET, N.W SUITE 2900 8
+o.,
+ATLANTA, GEORGIA 30323
+\\
+l t
+l 1
 l
 l l
@@ Line 1,725: / Line 2,403: @@
 l
+7.
-: 7.         PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                                                                                                        PAGE 39
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 39
-                                                     -                                 ~~~~~~~~~~~~~~~~~~~~~~~~
+~~~~ A5i5L55iEAL 55RTR5L
-                ~~~~R A5i5L55iEAL 55RTR5L ANSWERS -- OCONEE 1, 283                                                                       -86/04/21-TOM ROGERS 1
+~~~~~~~~~~~~~~~~~~~~~~~~
-i                                                                                                                                                                                          ,
+R ANSWERS -- OCONEE 1, 283
-ANSWER                       7.16                          ( .50)
+-86/04/21-TOM ROGERS 1
-                 -30 min.
+i ANSWER 7.16
-REFERENCE ONS, OP-0C-SPS-SY-LPIr i               ANSWER                       7.17                          ( .50)
+(.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.
+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.
+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)
+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.
+REFERENCE j
+ONS, OP-0C-SPS-IC-PRMr p.16.
 I I
 i t
-                                                       --,. ---,-...~.,.--,,,-_ ,, _ ,                            - - . , - - -      . - , - . . . - - . - . - , , _ ~ . , , .      - - - -
+--,. ---,-...~.,.--,,,-_,, _,
+. -, -... - -. -. -,, _ ~.,,.
-UNITED STATES I   /t>3 E8 Coq'g                                     NUCLEAR REEULATORY COMMISSION E      E    'g                                                     REGION 11 101 MARIETTA STREET N.W., SulTE 2000 5            g
+I
-* a                                              ATLANTA, GEORGIA 30323
+/t>3 E8 Coq'g UNITED STATES NUCLEAR REEULATORY COMMISSION E
-   \ ,,, /
+E
+'g REGION 11 5
+g 101 MARIETTA STREET N.W., SulTE 2000 a
+ATLANTA, GEORGIA 30323
+\\,,, /
-i
+i 7.
-: 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                      PAGE 40.
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 40.
-  ~~~~R5656L5siEEE E6UTRUL~~~~~~~~~~~~~~~~~~~~~~~~
+~~~~ 5656L5siEEE E6UTRUL~~~~~~~~~~~~~~~~~~~~~~~~
-ANSWERS -- OCONEE 1,          2&3         -86/04/21-TOM ROGERS ANSWER                   7.21 (1.00)
+R 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)
+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.
+REFERENCE OP/1/A/1104/10, Encl.
-ANSWER                   7.23 ( .50) 3.
+.6, p.1.
-REFERENCE ONS, OP/1/A/1104 ANSWER                   7.24 (1.50)
+ANSWER 7.23
-: 1. Select group control and group to be aligned.
+(.50) 3.
-: 2. Select SED OVERRIDE.
+REFERENCE ONS, OP/1/A/1104 ANSWER 7.24 (1.50) 1.
-: 3. Select J0G.
+Select group control and group to be aligned.
-: 4. Press Latch Switch and drive in for 15 sec.
+.
-: 5. Compare absolute and relative positions.
+Select SED OVERRIDE.
-: 6. Select desired CRD and use PI RESET RAISE / LOWER for adjustment.
+.
+Select J0G.
+.
+Press Latch Switch and drive in for 15 sec.
+.
+Compare absolute and relative positions.
+.
+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.
+REFERENCE ONS, OP/0/A/1105/09, Encl.
+.3.
-i f "8%                             UNITED STATES
+i f "8%
-              <*           a           NUCLEAR REauLATORY COMMISSION
+UNITED STATES a
-                     ~
+NUCLEAR REauLATORY COMMISSION
-y,    g                         REGION il
+~
-            -                a           101 MARIETTA STREET, N.W., SUITE 2000 o,                                 ATLANTA, GEORGIA 30323 s,
+g REGION il y,
-                           /
+a 101 MARIETTA STREET, N.W., SUITE 2000 ATLANTA, GEORGIA 30323 o,s,
+/
 I t
 i
@@ Line 1,786: / Line 2,484: @@
 I i
-: 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                                          PAGE  41
-       ~~~~R dDi5E55iEAE 55ATRU[~~~~~~~~~~~~~~~~~~~~~~~~
+.
-ANSWERS -- OCONEE                  1,  2&3                  -86/04/21-TOM ROGERS ANSWER                7.25             (1.00)
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 41
+~~~~ dDi5E55iEAE 55ATRU[~~~~~~~~~~~~~~~~~~~~~~~~
+R ANSWERS -- OCONEE 1,
+&3
+-86/04/21-TOM ROGERS ANSWER 7.25 (1.00)
 Any 4 0 0.25 points eacht:
-: 1. Anti Cs
+.
-: 2. Respirators
+Anti Cs
-: 3. MPC hours
+: 2. Respirators 3.
-: 4. Do not take anything by mouth in contaminated area
+MPC hours 4.
-: 5. Keep hands or any contaminated item away from face REFERENCE ONG, OP-0C-CPG-RAD-RPT, p.27.
+Do not take anything by mouth in contaminated area 5.
-ANSWER                7.26             (1.00)
+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.
+Verify it is in cal.
-: 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].
+Battery check.
+.
+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)
+~~' ANSWER 7.28 (1.00)
-Isolate                  al f1    and leakoff paths.        *U"'
+*U"'
-,       YYRE DNS, OP/1/A/1103/06,
+Isolate al f1 and leakoff paths.
-                                     $$h -
+YYRE
-nel. 4.3, tos p.1.
+$$h tos NoI % l2Grungi p-,
-p-,                  NoI % l2Grungi
+DNS, OP/1/A/1103/06, nel.
+.3, p.1.
-i UNITED STATES f K8809 3
+i f K8809 UNITED STATES ft NUCLEAR RE20LATORY CO''MISS13N REGION H 3
-ft    f, g
+f, g
-NUCLEAR RE20LATORY CO''MISS13N REGION H 3            g   101 MARIETTA 8TREET, N.W., SUITE 2000
+g
-* 4 o,                    ATLANTA, GEORGIA 30323 s,...../
+MARIETTA 8TREET, N.W., SUITE 2000 4
-: 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND                    PAGE 42
+ATLANTA, GEORGIA 30323 o,s,...../
-  ~~~~E5656EUU565E'U6UTRUE~~~~~~~~~~~~~~~~~~~~~~~~
-ANSWERS -- OCONEE 1,       2&3         -86/04/21-TOM ROGERS ANSWER                7.29 (1.00)
+.
+PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 42
+~~~~E5656EUU565E'U6UTRUE~~~~~~~~~~~~~~~~~~~~~~~~
+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)
+ANSWER 7.30 (1.00)
 Startup must beSin within 8 hours of the tripCO.5]
 A plant cooldown was not initiatedCO.5]
@@ Line 1,826: / Line 2,537: @@
 i l
-g                         UNITED STATES
+# p >2K'009'o,,
-      # p >2K'009'o,,
+g UNITED STATES NUCLEAR RECULATORY COMMISSl2N 8*
-NUCLEAR RECULATORY COMMISSl2N 8*    ,,    o                    REosON 11 5
+REosON 11 o
-    *           \
-101 MARIETTA STREET, N.W., SulTE 2000 s                           ATLANTA, GEORGIA 30323
+\\
-              /
+MARIETTA STREET, N.W., SulTE 2000 8
+ATLANTA, GEORGIA 30323 s
+/
 l
 l
-: 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
-p2 E849                  UNITED STATES
+.
-     +y         ,g  NUCLEAR REEULATORY COMMISSION E              o                 RE000N il 2              a   101 MARIETT A STREET. N.W., SUITE 2000 8         ATLANTA.OEORGIA 30323
+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.
+ANSWER 8.02 (1.00) b REFERENCE ONS, Directive 3.3.2 (TS),
+p.
+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.
+ANSWER 8.05 (1.00) b REFERENCE ONS, TS, p.
+.0-1 ANSWER 0.06 (1.00) d 3
+p2 E849 UNITED STATES
++y
+,g NUCLEAR REEULATORY COMMISSION E
+RE000N il o
+a
+MARIETT A STREET. N.W., SUITE 2000 8
+ATLANTA.OEORGIA 30323
+\\,..... /
 I l
 i i
@@ Line 1,845: / Line 2,572: @@
 l l
 k
-: 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
-usseTE3 STATES (pga2 atrug[g NUCLEAR RE20LATORY COMMISSION
+.
-             . f,    o                   REGION il 5
+ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 44 ANSWERS -- OCONEE 1,
-             *            \    101 MAntETT A STREET, N.W., SulTE 2900
-                         $           ATLANTA, GEORGIA 30323
+-86/04/21-TOM ROGERS REFERENCE ONS, TS, p.
-              *% ...../
+.1-6a ANSWER 8.07 (1.00) b REFERENCE ONS, Emergency Plan ANSWER 0.00 (1.50) a.
-L.~.........                                                          i
+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.
+(0.25) 2.
+(+/-
+.44) (1040 +/- 30 cubic feet)
+(0 25) 3.
+(0 25) 4.
+(+/- 25)
+(0.25)
+REFERENCE ONS, TS, p.
+.3-2 I
+I J
+c
+(pga2 atrug[g usseTE3 STATES NUCLEAR RE20LATORY COMMISSION o
+REGION il f,
+\\
+MAntETT A STREET, N.W., SulTE 2900 ATLANTA, GEORGIA 30323
+*%...../
+L.~.........
+i
-O. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS                             PAGE  45 ANSWERS -- OCONEE 1,             2&3                     -86/04/21-TOM ROGERS ANSWER          8.11              (1.00)
+O.
+ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 45 ANSWERS -- OCONEE 1, 2&3
+-86/04/21-TOM ROGERS ANSWER 8.11 (1.00)
 (a) 30 min E0.53.
 (b) Tech Spec Interpretation 00.53.
 REFERENCE ONS, TS Interpretations, 1 1.
-AMSWER          0.12              (1.00)
+AMSWER 0.12 (1.00)
 : 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)
+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
+ANSWER 0.14 (1.50) 0 0.5 points eacht
 : 1. Activity.
 : 2. Sump level.
-: 3. Inventory.
+.
+Inventory.
 REFERENCE ONS, TS, p. 3.1-14 & 16.
-ANSWER          0.15              (1.00)
+ANSWER 0.15 (1.00) a.
-: a. 2500 MREM                                                                           (0.5)
+MREM (0.5) b.
-: b. 4500 MREM                                                                           (0.5)
+MREM (0.5)
-. . .                                                                               _______-_-_______J
+J
-UNITEo sT .TEs
+p2 28 tog,o,,
-    ., p2 28 tog,o,,
+UNITEo sT.TEs NUCLEAR REIULATORY COMMISSION f,
-NUCLEAR REIULATORY COMMISSION
+o RE080N H
-  .       f,     o                   RE080N H
+\\
-  *              \
+tOf MAmetTTA STREET,N.W., SUITE 3900 2
-tOf MAmetTTA STREET,N.W., SUITE 3900 ATLANTA,0 EOR 04A 30323        -
+ATLANTA,0 EOR 04A 30323
-    %,        ,o L
+,o L
-r
+r 8.
-: 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)
+ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 46 ANSWERS -- OCONEE 1, 2&3
-: 1.       Daniel High School (Central, SC)                                        (0.5)
+-86/04/21-TOM ROGERS REFERENCE ONS, Directive 3.3 1 (TS), p. 2 ANSWER 8.16 (1.00) 1.
-: 2.       Keowee Elementary School (Seneca, SC)                                   (0.5)
+Daniel High School (Central, SC)
-REFERENCE ONS, .. Emergency Plan, p. H-4 ANSWER                 8.17                     ( .50)
+(0.5) 2.
-Oconee Memorial Hospital                                                         (0.5)
+Keowee Elementary School (Seneca, SC)
-REFERENCE ONS, Emergency Plan, p. L-1 ANSWER                 0.18                     (1.50)
+(0.5)
-(Any FIVE at 0.3 points each)
+REFERENCE ONS,.. Emergency Plan, p. H-4 ANSWER 8.17
-: 1. Technical Support Center
+(.50)
-: 2. Field Monitoring Team (Leader, A - F)
+Oconee Memorial Hospital (0.5)
-: 3.       Crisis Management Team (Training Center)
+REFERENCE ONS, Emergency Plan, p. L-1 ANSWER 0.18 (1.50)
-: 4.       Pickens County (LEC, Courthouse, C.D. Office)
+(Any FIVE at 0.3 points each) 1.
-: 5. Oconee County (LEC)
+Technical Support Center 2.
-: 6.       State of SC (Clemson National Guard Armory)
+Field Monitoring Team (Leader, A - F) 3.
-REFERENCE ONS, Emergency Plan, pp. F-2 & 6 ANSWER                0 19                      (1.00)
+Crisis Management Team (Training Center) 4.
-: a.       1 Hour                                                                  (0.5)
+Pickens County (LEC, Courthouse, C.D.
-: b.       10%/hr                                                                  (0.5)
+Office) 5.
-REFERENCE ONS, OMP 1-4,                   p. 1 i
+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.
+Hour (0.5) b.
+%/hr (0.5)
+REFERENCE ONS, OMP 1-4, p.
+i
 1
 i
-p gse Ka4                  UNITED STATES d          'o,  NUCLEAR REOULATORY COMMISSION
+gse Ka4 UNITED STATES p
-['      y,     'n                RE040N il 5
+d
-                  \   101 MARIETTA STREET, N.W., SulTE 2900 ATLANTA, GEORGIA 30323 I
+'o, NUCLEAR REOULATORY COMMISSION
-s.,...../
+['
+'n RE040N il y,
+\\
+MARIETTA STREET, N.W., SulTE 2900 I
+ATLANTA, GEORGIA 30323 s.,...../
 (
-T
+T 8.
-: 8.        ADMINISTRATIVE PF.0CEDURES, CONDITIONS, AND LIMITATIONS                 PAGE  47 ANSWERS -- OCONEE in 2&3                                  -86/04/21-TOM ROGERS ANSWER                   8.20                         (1.50)
+ADMINISTRATIVE PF.0CEDURES, CONDITIONS, AND LIMITATIONS PAGE 47 ANSWERS -- OCONEE in 2&3
-: 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)
+-86/04/21-TOM ROGERS ANSWER 8.20 (1.50) 1.
-: 2.       Change documentta on working copy (0.3) and initia11ed by SRO (0.3).                                                              (0.6)
+(Verbal) approval of two operators (0.3), one of whom is a supervisor (0.3) who holds an SRO license (0.3).
-REFERENCE ONS, OMP 1-9,                      p. 9 ANSWER                   0.21                         (1.00)
+(0.9) 2.
-: 1.        Suberitical by 1% delta K/K                                             (0.5)
+Change documentta on working copy (0.3) and initia11ed by SRO (0.3).
-: 2.        Tava at or -less than 525 degrees F                                     (0.5)
+(0.6)
-C. tu G' REFERENCE                            /
+REFERENCE ONS, OMP 1-9,
-ONS, TS,              p.      1-1 ANSWER                   8.22                         (1.00)
+: p. 9 ANSWER 0.21 (1.00) 1.
-Loss of Load REFERENCE ONS, TS, p. 3.13-1 ANSWER                   0 23                         (1.00)
+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 ANSWER 8.22 (1.00)
+Loss of Load REFERENCE ONS, TS, p.
+.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
+REFERENCE ONS, TS, p.
+.16-1
-                                                          )
+)
-gseEsto                  UNITED STATES NUCLEAR RECULATORY CO/.!MISSICN
+gseEsto UNITED STATES NUCLEAR RECULATORY CO/.!MISSICN
-!'      ,,   'i                  REoloNil 3
+'i REoloNil 3
-*               \
+\\
-101 MARIETTA STREET, N.W.. SulTE 2900 ATLANTA, OEORGIA 30323 o,
+MARIETTA STREET, N.W.. SulTE 2900 8
-s,
+ATLANTA, OEORGIA 30323 o,s,
-             /
+/
-f
+f 8.
-: 8.       ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS                              -PAGE  48 ANSWERS -- OCONEE 1,                            2&3          -86/04/21-TOM ROGERS ANSWER                 8.24                     (1.50)
+ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS
-: 1.       1 SS(SRO)                                                                             (0.3)
+-PAGE 48 ANSWERS -- OCONEE 1, 2&3
-: 2.       2 SRO                                                                                 (0.3)
+-86/04/21-TOM ROGERS ANSWER 8.24 (1.50) 1.
-: 3.       1 STA(SRO)                                                                            (0.3)
+SS(SRO)
-: 4.       5 R0                                                                                  (0.3)
+(0.3) 2.
-: 5.       5 NEO                                                                                 (0.3)
+SRO (0.3) 3.
-REFERENCE ONS, TS,            p. 6.1-6 ANSWER                 8.25                     (1.00)
+STA(SRO)
-: 1.       Its curresponding normal or emergency source is operable, and                         (0.5)
+(0.3) 4.
-: 2.       All its redundant components are operable.                                            (0.5)
+R0 (0.3) 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)
+NEO (0.3)
-REFERENCE ONS, TS,            p. 3.5-33 3
+REFERENCE ONS, TS, p.
-ANSWER                0.27                      (1.00)
+.1-6 ANSWER 8.25 (1.00) 1.
-A continous fire watch (0.4) with backup fire suppression equipment (0.3) in the area within one hour (0.3).                                                       (1.0)
+Its curresponding normal or emergency source is operable, and (0.5) 2.
-[                    PEFERENCE ONS, TS, p.                3 17-2 i
+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.
+.5-33 ANSWER 0.27 (1.00) 3 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.
+17-2 i
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+,ew----,_,___ _
-T UNITED STATES
+T p2 Ef oog'o UNITED STATES NUCLEAR REauLATORY COrMISSitN
-         # p2 Ef oog'o      NUCLEAR REauLATORY COrMISSitN
+['
-['      .f,       'n                REGION il 3                  g   101 MARIETTA STREET, N.W., SulTE 2000
+'n REGION il
-* 4         ATLANTA, GEORGIA 30323
+.f, 3
-         's, . . . . . $
+g 101 MARIETTA STREET, N.W., SulTE 2000 4
+ATLANTA, GEORGIA 30323
+'s,..... $
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+{
+1
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ML20209H628: Difference between revisions

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