ML072980379

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Initial Examination Report No. 50-073/OL-08-01 General Electric Nuclear Test Reactor (Gentr)
ML072980379
Person / Time
Site: Vallecitos Nuclear Center
Issue date: 11/01/2007
From: Johnny Eads
NRC/NRR/ADRA/DPR/PRTB
To: Doreen Turner
General Electric Co
Doyle P, NRC/NRR/DPR/PRT, 415-1058
Shared Package
ml072140272 List:
References
50-073/OL-08-01 50-073/OL-08-01
Download: ML072980379 (31)
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Text

November 1, 2007 Mr. David Turner Vallecitos and Morris Operations Vallecitos Nuclear Center General Electric Company 6705 Vallecitos Road Sunol, CA 94586

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-073/OL-08-01, GENERAL ELECTRIC NUCLEAR TEST REACTOR (GENTR).

Dear Mr. Turner:

During the week of October 15, 2007, the NRC administered an operator licensing examination at your GENTR Reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors" Revision 2.

Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Paul V. Doyle, Jr. at (301)415-1058 or via internet e-mail pvd@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.50-073

Enclosures:

1. Initial Examination Report No. 50-073/OL-08-01
2. Facility comments on written examination with NRC resolution
3. Written Examination with Facility comments incorporated cc:

Please see next page

November 1, 2007 Mr. David Turner Vallecitos and Morris Operations Vallecitos Nuclear Center General Electric Company 6705 Vallecitos Road Sunol, CA 94586

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-073/OL-08-01, GENERAL ELECTRIC NUCLEAR TEST REACTOR (GENTR).

Dear Mr. Turner:

During the week of October 15, 2007, the NRC administered an operator licensing examination at your GENTR Reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors" Revision 2.

Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Paul V. Doyle, Jr. at (301)415-1058 or via internet e-mail pvd@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.50-073

Enclosures:

1. Initial Examination Report No. 50-073/OL-08-01
2. Facility comments on written examination with NRC resolution
3. Written Examination with Facility comments incorporated cc:

Please see next page DISTRIBUTION:

PUBLIC RidsNrrDprPrta RidsNrrDprPrtb Facility File (CHart) O-12 G-15 ADAMS ACCESSION #: ML072980379 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA PRTB:SC NAME PDoyle Chart JEads DATE 10/ 31/2007 10/ 31/2007 11/01/2007 OFFICIAL RECORD COPY

General Electric Company (NTR) Docket No. 50-73 cc:

Ms. Latonya Mahlahla, Manager Regulatory Compliance and EHS Vallecitos Nuclear Center General Electric Company 6705 Vallecitos Road Sunol, CA 94586 Mr. Dan Thomas Manager NTR Vallecitos Nuclear Center General Electric Company 6705 Vallecitos Road Sunol, CA 94586 Mr. Harold Neems General Electric Company Nuclear Energy Business Operations 175 Cutner Avenue Mail Code 123 San Jose, CA 95125 Commissioner California Energy Commission 1516 Ninth Street, MS-34 Sacramento, CA 95814 California Department of Health ATTN: Chief Radiologic Health Branch P.O. Box 997414, MS 7610 Sacramento, CA 95899-7414 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-073/OL-08-01 FACILITY DOCKET NO.: 50-073 FACILITY LICENSE NO.: R-33 FACILITY: GENTR EXAMINATION DATES: October 18, 2007 SUBMITTED BY: ____/RA/_________________________ 10/31/2007 Paul V. Doyle, Jr., Chief Examiner Date

SUMMARY

During the week of October 15, 2007, the NRC administered an operator licensing examination to 1 senior reactor operator candidate. The candidate passed all applicable sections of his operator licensing examination.

REPORT DETAILS

1. Examiners: Paul V. Doyle, Jr., Chief Examiner
2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 0/0 1/0 1/0 Operating Tests 0/0 1/0 1/0 Overall 0/0 1/0 1/0

3. Exit Meeting:

Paul V. Doyle, Jr., NRC, Examiner Edward Ehrlich, GENTR, Reactor Training Coordinator The examiner thanked the facility staff for their support in the administration of the examination. The facility staff supplied the examiner with some minor changes to the examination which have been incorporated into the examination included with this report. The examiner did not identify any generic weaknesses on the part of the candidate.

Enclosure 1

ENCLOSURE 2 FACILITY COMMENTS ON NRC PREPARED WRITTEN EXAMINATION ADMINISTERED OCTOBER 18, 2007

NRC RESOLUTION OF FACILITY COMMENTS QUESTION A.05: Comment accepted as written. Question will be edited before next use.

QUESTION B.03: Comment not accepted. Answer key has b as correct answer.

QUESTION B.10: Comment accepted as written. Answer key changed from c to d, also choice d will be modified to a month.

QUESTION B.12: Comment accepted as written. Answer key changed from c to d.

QUESTION C.06: Comment accepted as written. Question will be edited before next use.

QUESTION C.08: Comment accepted as written. Answer key changed from c to b.

QUESTION C.12: Comment accepted as written. Question deleted due to no correct answer.

U.S. Nuclear Regulatory Commission Operator Licensing Examination WITH ANSWER KEY General Electric Nuclear Test Reactor October 18, 2007

Section A: Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 1 QUESTION A.01 [2.0 points, 1/2 each]

Match each term listed in column A with its correct definition from column B.

a. Delayed neutron 1. A neutron in equilibrium with its surroundings.
b. Fast neutron 2. A neutron born directly from fission.
c. Prompt neutron 3. A neutron born due to decay of a fission product.
d. Thermal neutron 4. A neutron at an energy level greater than its surroundings.

QUESTION A.02 [1.0 point]

Reactor Power is increasing on a 100 second period. How long will it take to double power?

a. 35 seconds
b. 50 seconds
c. 75 seconds
d. 100 seconds QUESTION A.03 [1.0 point]

During a fuel loading of the core, as the reactor approaches criticality, the value of 1/M:

a. increases towards 1
b. decreases towards 1
c. increases towards 0
d. decreases towards 0 QUESTION A.04 [1.0 point]

The number of neutrons passing through a square centimeter of target material per second is the definition of

a. Neutron Population (np)
b. Neutron Impact Potential (nip)
c. Neutron Flux (nv)
d. Neutron Density (nd)

QUESTION A.05 [1.0 point] Question changed per facility comment. TIME ACTIVITY Given the table to the right, the half-life of the material is approximately 0 2400 cps 0 min. 1757 cps

a. 11 seconds minutes 0 min. 1286 cps
b. 22 seconds minutes 0 min. 941 cps 60 min 369 cps
c. 44 seconds minutes
d. 55 seconds minutes

Section A: Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 2 QUESTION A.06 [2.0 points, 1/2 each]

Match the described plant conditions in column A, with the appropriate xenon conditions listed in column B.

Column A Column B (Xenon concentration is )

a. Four hours following a power increase 1. increasing to a peak
b. Two hours following a power decrease 2. decreasing to a trough
c. Sixteen hours following a clean startup 3. approximately zero (reactor is clean)
d. Seventy-two hours following a shutdown 4. at a non-zero steady-state value QUESTION A.07 [1.0 point]

The neutron cross-section for absorption S generally

a. increases as neutron energy increases
b. decreases as neutron energy increases
c. increases as target nuclear mass increases
d. decreases as target nuclear mass increases QUESTION A.08 [1.0 point]

With the reactor on a CONSTANT period, which ONE of the following evolutions would take the LONGEST time?

a. 5%, from 1% to 6%
b. 10%, from 20% to 30%
c. 25%, from 25% to 50%
d. 40%, from 30% to 70%

QUESTION A.09 [1.0 point]

You are assigned to check the operation of a nuclear instrument channel. You know that a few minutes after shutdown, the reactor period will stabilize at -80 seconds. Given this constant the time for the power to decrease by a factor of 10 should be approximately

a. 45 seconds (3/4 minute)
b. 90 seconds (1-1/2 minutes)
c. 135 seconds (2-1/4 minutes)
d. 180 seconds (3 minutes)

Section A: Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 3 QUESTION A.10 [1.0 point]

Which ONE of the following statements correctly describes the difference between prompt and delayed neutrons? Prompt neutrons

a. account for less than 1% of the total number of neutrons, and delayed neutrons makeup the rest.
b. are released ONLY during FAST fission events, and delayed neutrons are released during the decay process.
c. are released during the fission process, and delayed neutrons are released during the decay process.
d. are the dominant factor in controlling the reactor, while delayed neutrons have very little effect.

QUESTION A.11 [2.0 point, 2/5 each]

87 The listed isotopes are all potential daughter products due to the radioactive decay of 35Br . Identify the

+ -

type of decay necessary [Alpha (), Beta plus ( ), Beta minus ( ), Gamma () or Neutron () emission)]

to produce each of the isotopes.

83

a. 33As 86
b. 35Br 87
c. 35Br 87
d. 36Kr 87
e. 34Se QUESTION A.12 [1.0 point]

Which ONE of the listed isotopes will cause a neutron to lose the most energy in an ELEASTIC collision?

9

a. Be 12
b. C 1
c. H 16
d. O QUESTION A.13 [1.0 point]

Several processes within the core increase or decrease the number of neutrons in a generation. Which ONE of the following six-factor terms describes a process which results in an INCREASE in the number of neutrons during the cycle?

a. Thermal Utilization Factor (f)
b. Resonance Escape Probability (p)
c. Thermal Non-Leakage Probability (TH)
d. Reproduction Factor ()

Section B: Normal, Abnormal, Emergency & Radiological Procedures and Technical Specifications Page 4 QUESTION B.01 [2.0 points, 1/2 each]

Match type of radiation (a thru d) with the proper penetrating power (1 thru 4)

a. Gamma 1. Stopped by thin sheet of paper
b. Beta 2. Stopped by thin sheet of metal
c. Alpha 3. Best shielded by light material
d. Neutron 4. Best shielded by dense material QUESTION B.02 [1.0 point]

A four inch thick steel plate reduces the gamma radiation dose rate from 60 mrem/hr to 6 mrem/hr. If a one inch plate of the same composition steel is added, the new dose rate will be

a. 0.56 mrem/hr.
b. 1.50 mrem/hr.
c. 2.62 mrem/hr.
d. 3.37 mrem/hr.

QUESTION B.03 [1.0 point]

10CFR50.54(x) states: A licensee may take reasonable action that departs from a license condition or a technical specification (contained in a license issued under this part) in an emergency when this action is immediately needed to protect the public health and safety and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent. 10CFR50.54(y) states that the minimum level of management which may authorize this action is

a. Any licensed Reactor Operator
b. Any licensed Senior Reactor Operator
c. Facility Director (or Equivalent at facility)
d. NRC Project Manager QUESTION B.04 [1.0 point]

An experimenter removes a short half-life (~10 seconds) radio-isotope from the pool. If he allows the experiment to decay for 100 seconds, then the dose due to the experiment will be reduced (approximately) by a factor of (Note: Neglect any reduction in dose rate due to shielding.)

a. 20
b. 100
c. 200
d. 1000 QUESTION B.05 [1.0 point]

The CURIE content of a radioactive source is a measure of

a. the number of radioactive atoms in the source.
b. the amount of energy emitted per unit time by the source
c. the amount of damage to soft body tissue per unit time.
d. the number of nuclear disintegrations per unit time.

Section B: Normal, Abnormal, Emergency & Radiological Procedures and Technical Specifications Page 5 QUESTION B.06 [2.0 points, 1/2 each]

Identify each of the following as a Safety Limit (SL), a Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO).

a. The reactor shall be subcritical whenever the four safety rods are withdrawn from the core and the three control rods are fully inserted.
b. The linear neutron power monitor channel set point shall not exceed the measured value of 125 kW.
c. The True limit of the reactor thermal power shall not exceed 190 kW under any operating condition
d. The average scram time (inflight time) of the four safety rods shall not exceed 300 msec.

QUESTION B.07 [2.0 points, 1/2 each]

Identify each of the four surveillances listed as a channel CHECK, a channel TEST, or a channel CALibration.

a. During shutdown you verify operation of period channel by verifying power decreases by a factor of 10 in three minutes
b. Following maintenance on Nuclear Instrument channel 1 you compare its readings to Nuclear Instrument channel 2 readings.
c. You verify a temperature channel's operation by replacing the RTD with a precision variable resistance and checking proper output.
d. You perform a heat balance (calorimetric) on the primary system and based on Nuclear Instrumentation readings you make adjustments.

QUESTION B.08 [1.0 point]

Which ONE of the following statements correctly describes the relationship between a Safety Limit (SL) and a Limiting Safety System Setting (LSSS)?

a. An SL is a maximum operationally limiting value that prevents exceeding an LSSS during normal operations.
b. An SL is a limit on a parameter that assures the integrity of the fuel cladding. An LSSS initiates protective action to preclude reaching a SL.
c. An LSSS is a limit on a parameter that assures the integrity of the fuel cladding. An SL initiates protective action to preclude reaching the LSSS.
d. An SL is a maximum setpoint for instrumentation response. An LSSS is the minimum number of channels required to be operable.

Section B: Normal, Abnormal, Emergency & Radiological Procedures and Technical Specifications Page 6 QUESTION B.09 [1.0 point]

A radiation survey of an area results in a general radiation reading of 1 millirem/hour. However a small section of pipe (point source0 reads 10 millirem at 1 meter. Which ONE of the following is the posting requirement for the area in accordance with 10CFR20?

a. CAUTION RADIATION AREA
b. CAUTION HIGH RADIATION AREA
c. CAUTION RADIOACTIVE MATERIAL
d. GRAVE DANGER, VERY HIGH RADIATION AREA QUESTION B.10 [1.0 point] Question and answer key changed per facility comment.

The maximum amount of time (duration) a Radiation Work Permit may be used is

a. one day
b. five days
c. seven days
d. fourteen days one month QUESTION B.11 [1.0 point]

Which ONE of the following conditions would be a Technical Specifications violation while the reactor is operating?

a. Operation at 0.1 kilowatt with reactor cell pressure at 1.0 inch H2O negative pressure w/respect to the control room.
b. Operation at 0.1 kilowatt with the stack particulate monitor inoperable.
c. Shutdown margin equal to 0.76$
d. Core outlet temperature equal to 230°F.

QUESTION B.12 [1.0 point]

A physically damaged experiment caused the reactor operator to declare an emergency, classifying the reactor cell area as an Airborne Radioactivity Area. Which ONE of the following correctly describes the minimum level of staff who may return the area to its normal classification?

a. The reactor operator, since he originally established the temporary classification.
b. The senior reactor operator, acting as emergency director, with the concurrence of the reactor operator.
c. Any radiation monitoring technician, after completing a survey of the area and obtaining concurrence from the senior reactor operator.
d. The Director, NTR, after a survey by a radiation monitoring technician with concurrence from the NS Supervising Engineer.

Section C: Reactor Plant Components, Systems and Integrated Plant Operations Page 7 QUESTION C.01 [1.0 point]

Which ONE of the listed Area Radiation Monitors has two different set points?

a. Reactor Cell
b. North Room
c. South Cell
d. Control Room QUESTION C.02 [1.0 point]

In order to add water to the primary you must open V-143 in bldg 105, verify ___ then enter reactor cell and open V-140.

a. reactor secured
b. console key lock switch ON,
c. primary system operating
d. purification system off-line QUESTION C.03 [1.0 point]

The purpose of the Hoffman blower is to provide

a. air to operate the south cell door.
b. suction of various air sample stations throughout the facility.
c. circulate air to the ventilation system.
d. air to operate the south shutter QUESTION C.04 [1.0 point]

Which ONE of the following is the correct method used to control pH in the primary? The purification system

a. sample sink is used to add Ammonium Hydroxide to maintain it negative.
b. sample sink is used to add Hydrochloric acid to maintain it positive.
c. filter is used to keep the conductivity to a minimum, resulting an a neutral pH.
d. ion exchangers are used to keep the conductivity to a minimum, resulting an a neutral pH.

QUESTION C.05 [2.0 points, 1/2 each]

Match the neutron absorbing reactor components in column A, with the correct neutron absorbing material from column B.

Column A Column B

a. Coarse Control Rod 1. Boron Carbide
b. Fine Control Rod 2. Cadmium
c. Poison Sheets 3. Graphite
d. Safety Rods 4. Silver-Indium-Cadmium Alloy

Section C: Reactor Plant Components, Systems and Integrated Plant Operations Page 8 QUESTION C.06 [1.0 point] Question changed per facility comment.

Upon a low core DP signal in the primary system

a. a solenoid will open increasing flow to the reactor core
b. the reactor will scram
c. an alarm will energize at the console
d. nothing will happen.

QUESTION C.07 [1.0 point]

Upon a low differential pressure signal for the DP between the reactor cell and the control room

a. the reactor will scram.
b. an interlock will prevent the opening of the north and south cell doors.
c. and power is greater than 0.1 kilowatt, the operator must reduce reactor power below 0.1 kilowatt.
d. and power is greater than 0.1 kilowatt, reactor power will be automatically decreased below 0.1 kilowatt.

QUESTION C.08 [1.0 point]

Holes on the primary coolant flow distributor tube are designed to distribute the flow

a. uniformly
b. based on power distribution
c. based on temperature distribution
d. based on pressure distribution QUESTION C.09 [1.0 point]

The primary purpose of the graphite reflector is to

a. minimize shadowing effects on the neutron detectors
b. minimize shadowing effects on the control rods.
c. provide biological shielding (reduction of fast neutrons)
d. increase the neutron population in the core.

QUESTION C.10 [1.0 point]

Which ONE of the following signals will NOT cause the non-coincident logic unit to deenergize the power switches?

a. a high trip signal from one picoammeter
b. high trip signals from two picoammeters
c. loss of high voltage on the two Compensated Ion Chambers
d. loss of voltage on one coincident channel with a high trip on the other.

Section C: Reactor Plant Components, Systems and Integrated Plant Operations Page 9 QUESTION C.11 [1.0 point]

Which ONE of the following is the method used to prevent spurious picoammeter channel trips during reactor startup?

a. Temporarily place the coincident logic circuit in 1 out of 2 mode.
b. Repositioning the RESET/BYPASS switch on the picoammeters
c. Depressing PICO CIC TRIP pushbutton
d. Placing the drawer in the TEST position prior to ranging up the instrument.

QUESTION C.12 [1.0 point] Question deleted per facility comment.

During operation at 100 kilowatts, closing the south cell shutter will reduce the combined neutron/gamma dose rate by a factor of about

a. 10
b. 25
c. 40
d. 50 QUESTION C.13 [1.0 point]

On a power failure during reactor operations

a. all safety rods will scram the control rods will remain as-is.
b. all control rods will scram the safety rods will remain as-is.
c. all safety and control rods will scram.
d. all safety and control rods will remain as-is.

QUESTION C.14 [1.0 point]

Which ONE of the following control rod position indicating devices is interlocked to prevent energizing the electromagnets unless all rods are fully inserted?

a. Separation Switch
b. Drive-Out Limit Switch
c. Drive-In Limit Switch
d. Safety-Rod-In Position Switch

Section A: Reactor Theory, Thermodynamics and Facility Operating Characteristics Page 10 A.01 a, 3; b, 4; c, 2; d, 1 REF: Standard NRC Reactor Theory Question A.02 c t/T REF: P = P0 e --> ln(2) = time ÷ 100 seconds -> time = ln(2) x 100 sec. 0.693 x 100 0.7 x 100 70 sec.

A.03 d REF: Standard NRC question on startup control A.04 c REF:

A.05 b REF: Obvious, look a 20 minutes activity.

A.06 a, 2; b, 1; c, 4; d, 3 REF: Standard NRC Xenon question A.07 b REF: Standard NRC question regarding neutron interactions with matter.

A.08 a -t/T REF: Give P = P0 e, to maximize time you must maximize the ratio between P and P0.

A.09 d REF:

A.10 c REF:

- +

A.11 a, ; b, ; c, ; d,  ; e, REF: Standard NRC Reactor Theory Question A.12 c REF: Standard NRC Reactor Theory Question A.13 d REF: Standard NRC Reactor Theory Question

Section B: Normal, Abnormal, Emergency & Radiological Procedures and Technical Specifications Page 11 B.01 a, 4; b, 2; c, 1; d, 3 REF: Standard NRC Health Physics Question B.02 d ln(0.1)

REF: A f = A0e x ln( 606 ) = (4inches) = = 0.5756 A f = 60 e 0.5756 (5 inches ) = 3.374 4

B.03 b REF: 10CFR50.54(y)

B.04 d REF: ( 12 )10 = 1 210

= 1 1024 1024 . 1000 B.05 d REF: Standard NRC Health Physics Question B.06 REF: a, LCO; b, LSSS; c, SL; d, LCO; B.07 a, CHECK; B, CHECK; C, TEST; D, CAL REF: Tech Spec. §§ 1.2.1, 1.2.2 & 1.2.3 B.08 b REF: TS §§ 1.2.10 and 1.2.23 B.09 b REF: 10CFR20.1003 AND 20.1902, at 30 cm, the point source is > 100 mrem/hr so it is a HIGH radiation area.

B.10 c d Answer changed per facility comment REF: Rewrite of previously administered NRC examination question. Also SOP 7.0, Procedure 7.9, step 7.5.

B.11 d REF:

B.12 c d Answer changed per facility comment REF: SOP Chapter 7.0, procedure 7.9, step 7.5

Section C: Reactor Plant Components, Systems and Integrated Plant Operations Page 12 C.01 a REF: GENTR SAR § 7.4, Table 7-2.

C.02 b REF: SAR § 5.x, also SOP 1.0 Procedure 1.2, Primary Makeup System C.03 b REF: Facility provided requalification examination Question # 12.

C.04 d REF: Rewrite of facility provided Requalification examination Question #17.

C.05 a, 1; b, 1; c, 2; d, 1 REF: SAR § 4.6, also rewrite of old NRC administered examination.

C.06 c REF: Rewrite of NRC previously administered question C.07 c REF: SAR § 6.7, also rewrite of old NRC administered examination.

C.08 c b Answer changed per facility comment REF: SAR § 6.7, also rewrite of old NRC administered examination.

C.09 d REF: Rewrite of old NRC administered examination.

C.10 a REF:

C.11 b REF: SOP chapter 2.0, Procedure 2.4 Steps 3.4 and 6.3.2.

C.12 b Question deleted per facility comment REF: SAR § 10.6 C.13 a REF: SOP Chapter 8, procedure 8.2, steps 4.4.1 and 4.4.5 C.14 c REF: GENTR SAR, § 8.5.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: General Electric NTR REACTOR TYPE: NTR DATE ADMINISTERED: 10/18/2007 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination.

Points for each question are indicated in brackets for each question. A 70% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% of Category  % of Candidates Category Value Total Score Value Category 16.00 34.8 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 15.00 32.6 B. Normal and Emergency Operating Procedures and Radiological Controls 15.00 32.6 C. Facility and Radiation Monitoring Systems 46.00  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.
3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
4. Use black ink or dark pencil only to facilitate legible reproductions.
5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.
6. Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
7. The point value for each question is indicated in [brackets] after the question.
8. If the intent of a question is unclear, ask questions of the examiner only.
9. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition turn in all scrap paper.
10. Ensure all information you wish to have evaluated as part of your answer is on your answer sheet.

Scrap paper will be disposed of immediately following the examination.

11. To pass the examination you must achieve a grade of 70 percent or greater in each category.
12. There is a time limit of three (3) hours for completion of the examination.
13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.

EQUATION SHEET

Q& = m& c p T = m& H = UA T ( - )2 P max = * -4 l = 1 x 10 seconds 2 (k)l eff = 0.1 seconds-1 S S CR1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

- 1 - K eff CR1 (- 1 ) = CR 2 (- 2 )

1 - K eff 0 SUR = 26.06 eff M= 1 CR1

- 1 - K eff 1 M= =

1 - K eff CR 2 P = P0 10 SUR(t) t (1 - )

P = P0 e P= P0 (1 - K eff ) l SDM = = =

l

+

K eff -

eff K eff 2 - K eff 1 0.693 ( K eff - 1)

T=

k eff 1 x K eff 2 K eff 6CiE(n) 2 2 DR = DR0 e- t DR = 2 DR1 d 1 = DR 2 d 2 R

2 2

( 2 - ) ( 1 - )

=

Peak 2 Peak 1 DR B Rem, Ci B curies, E B Mev, R B feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 3

1 Horsepower = 2.54 x 10 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32) cP = 1.0 BTU/hr/lbm/EF cp = 1 cal/sec/gm/EC

Section A L Theory, Thermo, and Facility Characteristics Page 16 A.01a 1 2 3 4 ___ A.07 a b c d ___

A.01b 1 2 3 4 ___ A.08 a b c d ___

A.01c 1 2 3 4 ___ A.09 a b c d ___

A.01d 1 2 3 4 ___ A.10 a b c d ___

A.02 a b c d ___ A.11a + - ( ___

A.03 a b c d ___ A.11b + - ( ___

A.04 a b c d ___ A.11c + - ( ___

A.05 a b c d ___ A.11d + - ( ___

A.06a 1 2 3 4 ___ A.11e + - ( ___

A.06b 1 2 3 4 ___ A.12 a b c d ___

A.06c 1 2 3 4 ___ A.13 a b c d ___

A.06d 1 2 3 4 ___

Section B Normal/Emerg. Procedures & Rad Con Page 17 B.01a 1 2 3 4 ___ B.07a CHECK TEST CAL ___

B.01b 1 2 3 4 ___ B.07b CHECK TEST CAL ___

B.01c 1 2 3 4 ___ B.07c CHECK TEST CAL ___

B.01d 1 2 3 4 ___ B.07d CHECK TEST CAL ___

B.02 a b c d ___ B.08 a b c d ___

B.03 a b c d ___ B.09 a b c d ___

B.04 a b c d ___ B.10 a b c d ___

B.05 a b c d ___ B.11 a b c d ___

B.06a SL LSSS LCO ___ B.12 a b c d ___

B.06b SL LSSS LCO ___

B.06c SL LSSS LCO ___

B.06d SL LSSS LCO ___

C.01 a b c d ___ C.07 a b c d ___

C.02 a b c d ___ C.08 a b c d ___

C.03 a b c d ___ C.09 a b c d ___

C.04 a b c d ___ C.10 a b c d ___

C.05a 1 2 3 4 ___ C.11 a b c d ___

C.05b 1 2 3 4 ___ C.12 a b c d ___

C.05c 1 2 3 4 ___ C.13 a b c d ___

C.05d 1 2 3 4 ___ C.14 a b c d ___

C.06 a b c d ___

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