ML082630382

Initial Examination Report, No. 50-05/OL-08-01, Pennsylvania State University Reactor

ML082630382
Person / Time
Site:	Pennsylvania State University
Issue date:	09/23/2008
From:	Isaac P Research and Test Reactors Licensing Branch
To:	Unlu K Pennsylvania State Univ
Isaac P, NRC/NRR/DPR/PRTB, 301-415-1019
Shared Package
ML081990634	List: ML081990633 ML082630347 ML082630382
References
05000005/OL-08-01
Download: ML082630382 (25)

Text

September 23, 2008 Dr. Kenan Unlu, Director Breazeale Nuclear Reactor The Pennsylvania State University University Park, PA 16802-2301

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-05/OL-08-01, PENNSYLVANIA STATE UNIVERSITY

Dear Dr. Unlu:

During the week of August 25, 2008, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examination at your Pennsylvania State University reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2, published in June 2007. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.

In accordance with Title 10, Section 2.390 of the Code of Federal Regulations, 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 http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Patrick Isaac at 301-415-1019 or via email at patrick.isaac@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-05

Enclosures:

1. Examination Report No. 50-05/OL-08-01

2. Facility Comments with NRC Resolution

3. Corrected Written Examination cc : Mr. Mark Trump, Pennsylvania State University cc without enclosures: See next page

September 23, 2008 Dr. Kenan Unlu, Director Breazeale Nuclear Reactor The Pennsylvania State University University Park, PA 16802-2301

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-05/OL-08-01, PENNSYLVANIA STATE UNIVERSITY

Dear Dr. Unlu:

During the week of August 25, 2008, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examination at your Pennsylvania State University reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2, published in June 2007. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.

In accordance with Title 10, Section 2.390 of the Code of Federal Regulations, 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 http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Patrick Isaac at 301-415-1019 or via email at patrick.isaac@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-05

Enclosures:

1. Examination Report No. 50-05/OL-08-01

2. Facility Comments with NRC Resolution

3. Corrected Written Examination cc w/enclosures: Mr. Mark Trump, Pennsylvania State University cc without enclosures: See next page DISTRIBUTION w/ encls.:

PUBLIC PRTB r/f JEads Facility File CHart (O12-D19)

ADAMS ACCESSION #: ML082630382 OFFICE PRTB:CE IOLB:LA PRTB:BC NAME PIsaac pxi CHart cah JEads jhe DATE 9/22/08 09/19/2008 9/23/08 OFFICIAL RECORD COPY

Pennsylvania State University Docket No. 50-05 cc:

Mr. Eric J. Boeldt, Manager of Radiation Protection The Pennsylvania State University 304 Old Main University Park, PA 16802-1504 Dr. Eva J. Pell Vice President and Dean of the Graduate School Pennsylvania State University 304 Old Main University Park, PA 16802-1504 Director, Bureau of Radiation Protection Department of Environmental Protection P.O. Box 8469 Harrisburg, PA 17105-8469 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

ENCLOSURE 1 EXAMINATION REPORT NO:

50-05/OL-08-01 FACILITY:

Pennsylvania State University FACILITY DOCKET NO.:

50-05 FACILITY LICENSE NO.:

R-75 SUBMITTED BY:

__________/RA/_________

_9/22/08___

Patrick J. Isaac, Chief Examiner Date

SUMMARY

During the week of August 25, 2008, the NRC administered operator licensing examinations to three Reactor Operator (RO) candidates. The candidates passed the examinations.

REPORT DETAILS

1.

Examiner: Patrick J. Isaac, Chief Examiner

2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/0 N/A 3/0 Operating Tests 3/0 N/A 3/0 Overall 3/0 N/A 3/0

3.

Exit Meeting:

Mark Trump, Associate Director, OSU Nuclear Reactor Laboratory Patrick Isaac, NRC, Examiner The NRC Examiner thanked the facility for their support in the administration of the examinations.

ENCLOSURE 2 Facility Comments with NRC Resolution Question B.4 Which one of the following instruments should you use to survey a gamma source?

a. Thin window ion chamber.

b. GM tube.

c. Ion chamber (open window).

d. Neutron ball.

Answer: b Facility Comment:

a) Thin window ion chamber - valid answer, ion chambers are calibrated for gamma and window thickness will have no effect on performance with gamma b) GM tube - valid answer for some of our instruments that read out in mR, and are calibrated in a gamma field. Students are trained to use a RO-2 (ion chamber) for posting rad areas c) Ion chamber (open window)- valid answer, ion chambers are calibrated for gamma and window position will not affect performance with gamma d) Neutron ball

- invalid answer, neutron ball discriminates gamma Recommendation discard question NRC Resolution:

Comment accepted. Due to too many correct answers, question B.4 will be deleted from the examinations.

Question C.5 Which one of the following is a control rod interlock?

a. above reactor power of 1 kW, the transient rod cannot be operated in the pulse mode

b. only one standard rod at a time can be moved in the pulse mode

c. control rods cannot be withdrawn unless the count rate is greater than 1 CPS in the manual mode

d. two control rods cannot be moved at the same time above 1 kW in the manual mode

ENCLOSURE 2 Answer: a Facility Comment:

a. above reactor power of 1 kW, the transient rod cannot be operated in the pulse mode

- valid answer, the cylinder can be positioned, but the rod is interlocked (no pulse)

b. only one standard rod at a time can be moved in pulse mode

- invalid answer, no standard rod can be moved in pulse mode

c. control rods cannot be withdrawn unless count rate is greater than 1 CPS in the manual mode

- valid answer, the low source interlock prevents rod motion at somewhere below 1-5 cps. We believe this distracter made when we had a tech spec which stated 2 CPS as a limit associated with the interlock. That was changed years ago and the spec now refers to a low neutron-induced signal on the log power channel. No specific setpoint is supported in the training material.

d. two control rods cannot be moved at the same time above 1kW in the manual mode

- invalid answer interlocks prevent simultaneous manual withdrawal at any power level Recommendation - accept a and c NRC Resolution:

Comment accepted. The answer key for question C.5 will be modified to accept both a and c as correct.

Question C.20 Which one of the following is a correct description of the design response of the emergency lighting system when AC current is lost?

a. A relay closes so that the un-interruptible power supply (UPS) provides power to the emergency lighting system.

b. A relay closes so that emergency generator power is supplied to the emergency lighting system lights.

c. A relay closes so that emergency lighting system battery DC power is supplied to the emergency lighting system lights.

d. An alarm indication is sent to the DCC-X which initiates transfer to the facility transformer.

Answer: c

ENCLOSURE 2 Facility Comment:

b. A relay closes so that the diesel emergency generator power is supplied to the emergency lighting system lights.

We do not use the term emergency to describe the diesel as it serves no emergency function. Also note that we refer to the relay as the automatic transfer switch. Battery power backup was eliminated with addition of the diesel generator.

Recommendation b) is the most correct answer not c) as noted in the key.

NRC Resolution:

Comment accepted. The answer key for question C.20 will be modified to accept b as correct.

ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY:

Pennsylvania State University REACTOR TYPE:

Pool DATE ADMINISTERED:

August 25, 2008 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 parentheses 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 CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 %

TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

Section A  Theory & Fac. Operating Characteristics A N S W E R S H E E T Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

MULTIPLE CHOICE 001 a b c d ___

002 a b c d ___

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(***** END OF CATEGORY A *****)

B. NORMAL/EMERG PROCEDURES & RAD CON A N S W E R S H E E T Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

001 a b c d ___

002 a b c d ___

003 a b c d ___

004 a b c d ___

005 a ___ b ___ c ___ d ___

006 a ___ b ___ c ___ d ___

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011 a b c d ___

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(***** END OF CATEGORY B *****)

C. PLANT AND RAD MONITORING SYSTEMS A N S W E R S H E E T Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

001 a b c d ___

002 a b c d ___

003 a b c d ___

004 a b c d ___

005 a b c d ___

006 a b c d ___

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(***** END OF CATEGORY C *****)

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

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.

EQUATION SHEET

( - )2 Q = m cp T Pmax = 2(k)

Q = m h SCR = S/(1-Keff)

Q = UA T CR1 (1-Keff)1 = CR2 (1-Keff)2 26.06 (eff)

(1-Keff)0 SUR =

M =

( - )

(1-Keff)1 SUR = 26.06/

M = 1/(1-Keff) = CR1/CR0 P = P0 10SUR(t)

SDM = (1-Keff)/Keff P = P0 e(t/)

Pwr = Wf m (1-)

P = Po

• = 1 x 10-5 seconds

= (*/) + [(-)/eff]

= */(-)

= (Keff-1)/Keff eff = 0.1 seconds-1

Keff/Keff 0.693 T1/2

= 0.0070 DR1D1 2 = DR2D2 2

DR = DRoe-t 6CiE(n)

DR =

DR R/hr, Ci Curies, E Mev, R feet R2 1 Curie = 3.7x1010 dps 1 kg = 2.21 lbm 1 hp = 2.54x103 BTU/hr 1 Mw = 3.41x106 BTU/hr 1 BTU = 778 ft-lbf F = 9/5C + 32 1 gal H2O 8 lbm C = 5/9 ( F - 32)

Section A:  Theory, Thermo & Fac. Operating Characteristics Page 1 Question A.1 [1.0 point]

A reactor scram has resulted in the instantaneous insertion of.006 K/K of negative reactivity.

Which one of the following is the stable negative reactor period resulting from the scram?

a. 45 seconds

b. 56 seconds

c. 80 seconds

d. 112 seconds Question A.2 [1.0 point]

The count rate is 50 cps. An experimenter inserts an experiment into the core, and the count rate decreases to 25 cps. Given the initial Keff of the reactor was 0.8, what is the worth of the experiment?

a. = - 0.42

b. = + 0.42

c. = - 0.21

d. = + 0.21 Question A.3 [1.0 point]

Given the lowest of the high power scrams is 110%, and the scram delay time is 0.5 sec. If the reactor is operating at 100% power prior to the scram, approximately how high will reactor power get with a positive 20 second period?

a. 113%

b. 116%

c. 124%

d. 225%

Section A:  Theory, Thermo & Fac. Operating Characteristics Page 2 Question A.4 [1.0 point]

Excess reactivity is the amount of reactivity:

a. associated with samples.

b. needed to achieve prompt criticality.

c. available above that which is required to make the reactor subcritical.

d. available above that which is required to keep the reactor critical.

Question A.5 [1.0 point]

Which one of the following is the MAJOR source of energy recovered from the fission process?

a. Kinetic energy of the fission neutrons

b. Kinetic energy of the fission fragments

c. Decay of the fission fragments

d. Prompt gamma rays Question A.6 [1.0 point]

Which statement illustrates a characteristic of Subcritical Multiplication?

a. As Keff approaches unity (1), for the same increase in Keff, a greater increase in neutron population occurs.

b. The number of neutrons gained per generation gets larger for each succeeding generation.

c. The number of fission neutrons remains constant for each generation.

d. The number of source neutrons decreases for each generation.

Question A.7 [1.0 point]

If reactor power is increasing by a decade every minute, it has a period of:

a. 13 sec

b. 26 sec

c. 52 sec

d. 65 sec

Section A:  Theory, Thermo & Fac. Operating Characteristics Page 3 Question A.8

[1.0 point]

Which one of the following statements describes Count Rate characteristics after a control rod withdrawal in a subcritical reactor as Keff approaches 1? (Assume the Rx remains subcritical.)

a. Count Rate will rapidly increase (prompt jump) then gradually increase to a stable value.

b. Count Rate will rapidly increase (prompt jump) then gradually decrease to the previous value.

c. Count Rate will rapidly increase (prompt jump) to a stable value.

d. There will be no change in Count Rate until criticality is achieved.

Question A.9

[1.0 point]

Given: Primary coolant flow rate is 500 gallons/minute and secondary flow rate is 700 gallons/minute. The T across the primary side of the heat exchanger is 13F and secondary inlet temperature to the heat exchanger is 73F. Assuming both the primary and secondary coolants have the same Cp value, which ONE of the following is the secondary outlet temperature?

a. 82 F

b. 85 F

c. 89 F

d. 91 F Question A.10

[1.0 point]

Which ONE of the following is NOT a major contributor to the prompt negative temperature coefficient at the Penn State TRIGA reactor?

a. the U-235 doppler effect

b. the U-238 doppler effect

c. the ZrH cell effect

d. the core leakage effect

Section A:  Theory, Thermo & Fac. Operating Characteristics Page 4 Question A.11

[1.0 point]

As the moderator temperature increases, the resonance escape probability:

a. increases, since the moderator becomes less dense.

b. decreases, since the time required for a neutron to reach thermal energy increases.

c. remains constant, since the effect of moderator temperature change is relatively small.

d. increases, since the moderator-to-fuel ratio increases.

Question A.12

[1.0 point]

An element decays at a rate of 20% per day. Determine its half-life.

a. 3 hr.

b. 75 hr.

c. 108 hr.

d. 158 hr.

Question A.13 [1.0 point]

Which ONE of the following is the reason for the -80 second period following a reactor scram?

a. The negative reactivity added during a scram is greater than á-effective

b. The half-life of the longest-lived group of delayed neutron precursors is approximately 55 seconds

c. The fuel temperature coefficient adds positive reactivity as the fuel cools down, thus retarding the rate at which power drops

d. The amount of negative reactivity added is greater than the Shutdown Margin Question A.14 [1.0 point]

A reactor has been operating at full power for one week when a scram occurs. Twelve hours later, the reactor is brought critical and quickly raised to full power. Considering xenon effects only, to maintain a constant power level for the next few hours, control rods must be:

a. inserted

b. maintained at the present position

c. withdrawn

d. withdrawn, then inserted to the original position

Section A:  Theory, Thermo & Fac. Operating Characteristics Page 5 Question A.15 [1.0 point]

Which ONE of the following describes the difference between reflectors and moderators?

a. Reflectors decrease core leakage while moderators thermalize neutrons

b. Reflectors shield against neutrons while moderators decrease core leakage

c. Reflectors decrease thermal leakage while moderators decrease fast leakage

d. Reflectors thermalize neutrons while moderators decrease core leakage Question A.16

[1.0 point]

Experimenters are attempting to determine the critical mass of a new fuel material. As more fuel was added the following fuel to count rate data was taken:

Fuel Counts/Sec 1.00 kg 500 1.50 kg 800 2.00 kg 1142 2.25 kg 1330 2.50 kg 4000 2.75 kg 15875 Which one of the following is the amount of fuel needed for a critical mass?

a. 2.60 kg

b. 2.75 kg

c. 2.80 kg

d. 2.95 kg Question A.17

[1.0 point]

With the reactor on a constant period, which transient requires the LONGEST time to occur?

A reactor power change of:

a. 5% power going from 1% to 6% power

b. 10% power going from 10% to 20% power

c. 15% power going from 20% to 35% power

d. 20% power going from 40% to 60% power

Section A:  Theory, Thermo & Fac. Operating Characteristics Page 6 Question A.18

[1.0 point]

The reactor has scrammed following an extended period of operation at full power. Which one of the following accounts for generation of a majority of the heat one (1) hour after the scram?

a. Spontaneous fissions

b. Delayed neutron fissions

c. Alpha fission product decay

d. Beta fission product decay Question A.19

[1.0 point]

The term "reactivity" is described as:

a. a measure of the core's fuel depletion.

b. negative when Keff is greater than 1.0.

c. a measure of the core's deviation from criticality.

d. being equal to $0.66 when the reactor is prompt critical.

Question A.20

[1.0 point]

Which one of the following is NOT a reason for or benefit of operating with a flat neutron flux profile?

a. A higher average power density is possible.

b. More even burn up of fuel results.

c. Moderator temperature is equalized throughout the core.

d. Control rod worth is made more uniform.

Section B: Normal/Emerg. Procedures & Rad Con Page 7 Question B.1 [1.0 point]

In order to ensure the health and safety of the public, in an emergency, 10CFR50 allows the operator to deviate from Technical Specifications. What is the minimum level of authorization needed to deviate from Tech. Specs?

a. USNRC

b. Reactor Supervisor

c. Licensed Senior Reactor Operator.

d. Licensed Reactor Operator.

Question B.2 [1.0 point]

The maximum power level shall be no greater than 1.1 MW. This is an example of a:

a. safety limit.

b. limiting safety system setting.

c. limiting condition for operation.

d. surveillance requirement.

Question B.3 [1.0 point]

Which one of the following statements defines the Technical Specifications term "Channel Test?"

a. The adjustment of a channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures

b. The qualitative verification of acceptable performance by observation of channel behavior

c. The introduction of a signal into a channel for verification of the operability of the channel

d. The combination of sensors, electronic circuits and output devices connected to measure and display the value of a parameter

Section B: Normal/Emerg. Procedures & Rad Con Page 8 Question B.4 [1.0 point]

DELETED Which one of the following instruments should you use to survey a gamma source?

a. Thin window ion chamber.

b. GM tube.

c. Ion chamber (open window).

d. Neutron ball.

Question B.5 [2.0 points, 0.5 each]

Match the type of radiation in column A with its associated Quality Factor (10CFR20) from column B.

Column A Column B

a. alpha 1

b. beta 2

c. gamma 5

d. neutron (unknown energy) 10 20 Question B.6 [2.0 points, 0.5 each]

Match the radiation reading from column A with its corresponding radiation area classification (per 10 CFR 20) listed in column B.

COLUMN A COLUMN B

a. 10 mRem/hr

1. Unrestricted Area

b. 150 mRem/hr

2. Radiation Area

c. 10 Rem/hr

3. High Radiation Area

d. 550 Rem/hr

4. Very High Radiation Area

Section B: Normal/Emerg. Procedures & Rad Con Page 9 Question B.7 [1.0 point]

A radioactive source generates a dose of 100 mr/hr at a distance of 10 feet. Using a two inch thick sheet of lead for shielding the reading drops to 50 mr/hr at a distance of 10 feet. What is the minimum number of sheets of the same lead shielding needed to drop the reading to less than 5 mr/hr at a distance of 10 ft?

a. 1

b. 3

c. 5

d. 7 Question B.8 [1.0 point]

Which one of the following is the 10 CFR 20 definition of TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)?

a. The sum of the deep dose equivalent and the committed effective dose equivalent.

b. The dose that your whole body receives from sources outside the body.

c. The sum of the external deep dose and the organ dose.

d. The dose to a specific organ or tissue resulting from an intake of radioactive material Question B.9 [1.0 point]

A room contains a source which, when exposed, results in a general area dose rate of 175 mr/hr. This source is scheduled to be exposed continuously for 25 days. Select an acceptable method for controlling radiation exposure from the source within this room.

a. Post the area with words Danger-Radiation Area.

b. Equip the room with a device to visually display the current dose rate within the room.

c. Equip the room with a motion detector that will alarm in the control room.

d. Lock the room to prevent inadvertent entry into the room.

Section B: Normal/Emerg. Procedures & Rad Con Page 10 Question B.10

[2.0 points, 0.5 each]

Match the requirements (10 CFR 55) for maintaining an active operator license in column A with the correct time period from column B.

Column A Column B

1. Renewal of license

a. 4 months

2. Medical examination

b. 1 year

3. Console manipulation evaluation

c. 2 years

4. Requalification exam (written)

d. 6 years Question B.11

[1.0 point]

Which one of the following statements describes the basis for the Safety Limit?

a. Excessive gas pressure may result in loss of fuel element cladding integrity.

b. High fuel temperature combined with lack of adequate cooling could result in fuel melt.

c. Excessive hydrogen produced as a result of the zirconium-water reaction is potentially explosive.

d. High fuel temperature could result in clad melt.

Question B.12

[1.0 point]

The Safety System channels required to be operable in all modes of operation are:

a. fuel element temperature scram, reactor high power scram, and manual scram

b. fuel element temperature scram and manual scram

c. manual scram and reactor high power scram

d. reactor high power scram, detector power supply scram, and fuel element temperature scram

Section B: Normal/Emerg. Procedures & Rad Con Page 11 Question B.13

[1.0 point]

In accordance with the Technical Specifications, which one situation below is permissible when the reactor is operating?

a. The Emergency Exhaust System is inoperable for three days for repairs

b. A single secured experiment with a reactivity worth of 2.31 % k/k

c. The reactivity insertion rate for standard control rods is 0.90% k/k per second

d. The reactor bay truck door is open for ten minutes Question B.14

[1.0 point]

Which one of the following does NOT require NRC approval for changes?

a. Facility License

b. Requalification plan

c. Emergency Implementation Procedures

d. Emergency Plan Question B.15

[1.0 point]

In the event of a bomb threat, the person receiving the threat should...

a. ask the person making the threat for his name and address.

b. call 911 after the call has ended.

c. immediately activate the Emergency Plan.

d. immediately evacuate the reactor building and proceed to the facility gate.

Question B.16

[1.0 point]

SELECT the condition under which a reactor bay personnel door may be blocked open.

(NOTE: Consider each choice separately.)

a. The reactor is shutdown and the console key removed.

b. At least one person capable of following written instructions is in the Control Room.

c. The PSBR Director is in the Control Room.

d. One member of the Penn. State University Campus Police is in the Control Room.

Section B: Normal/Emerg. Procedures & Rad Con Page 12 Question B.17

[1.0 point]

It is April 1, 2008. You have stood watch for the following hours during the last quarter:

Jan. 11, 2008 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Feb. 24, 2008 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Mar. 16, 2008 1.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> What requirements must you meet in order to stand an RO watch today?

a. None. You've met the minimum requirements of 10 CFR 55.

b. You must perform 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of shift functions under the direction of a licensed operator or licensed senior operator as appropriate.

c. You must perform 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of shift functions under the direction of a licensed operator or licensed senior operator as appropriate.

d. You must submit a new application form to the NRC requesting a waiver to reactivate your license.

(*** End of Section B ***)

Section C Plant and Rad Monitoring Systems Page 13 Question C.1

[1.0 point]

Reclaimed water from the Liquid Waste Evaporator System is transferred to the reactor pool as makeup water by the:

a. makeup pump

b. processed water pump

c. distillate pump

d. storage tank transfer pump Question C.2

[1.0 point]

Carbon dioxide is used in the pneumatic transfer system instead of compressed air because:

a. it is more compressible

b. it does not retain moisture

c. it minimizes Ar-41 production

d. it minimizes N-16 production Question C.3

[1.0 point]

The top grid plate in the reactor:

a. supports the weight of the fuel assemblies

b. aligns and supports the nuclear detectors

c. maintains lateral fuel alignment

d. serves as a reflector over the top of the core Question C.4

[1.0 point]

The Wide Range power monitor uses a (an):

a. uncompensated ion chamber

b. compensated ion chamber

c. fission chamber

d. boron-trifluoride detector

Section C Plant and Rad Monitoring Systems Page 14 Question C.5

[1.0 point]

Which one of the following is a control rod interlock?

a. above reactor power of 1 kW, the transient rod cannot be operated in the pulse mode

b. only one standard rod at a time can be moved in the pulse mode

c. control rods cannot be withdrawn unless the count rate is greater than 1 CPS in the manual mode

d. two control rods cannot be moved at the same time above 1 kW in the manual mode Question C.6

[1.0 point]

SCRAM logic is designed to meet the single failure criterion. Which one pair of parameters below are in the correct circuits?

Scram Circuit #1 Scram Circuit #2

a.

Fuel temperature High Fission Chamber Power High

b.

Manual Scram Pulse Timer Scram

c.

Pulse Timer Scram GIC Power High

d.

Keyswitch Off Fuel Temperature High Question C.7

[1.0 point]

In the PSBR Water Handling System, pool water conductivity is measured:

a. at the suction of the purification pump

b. downstream of the skimmer

c. between the filter and purification pump

d. at the inlet of the demineralizer Question C.8

[1.0 point]

Streaming of radiation from the central thimble is prevented by:

a. a graphite shield box over the top of the tube

b. the tube being filled with water

c. a boral plug inserted into the top of the tube

d. large radius bend in the tube

Section C Plant and Rad Monitoring Systems Page 15 Question C.9

[1.0 point]

A reactor stepback is initiated by:

a. east or west bay monitor high radiation

b. east and west facility exhaust fans off

c. high fuel temperature

d. pulse timer timed out Question C.10

[1.0 point]

When energized, flow through the Emergency Exhaust System is verified by:

a. the red power-on light on the Cobalt-60 lobby control panel.

b. a DCC-X message Emerg Ventilation Flow On.

c. the red pilot light on the circuit box on the east wall of the reactor bay.

d. the Absolute Filter pressure gauge reads 0.2 inches H2O.

Question C.11

[1.0 point]

Which one of the following is correct for the air compressors?

a. Compressed air for the facility is provided by two air compressors located in the demineralizer room.

b. Either air compressor can supply the entire system through valve repositioning in the mechanical equipment room.

c. Normally, the 20 horsepower air compressor supplies the reactor transient rod, and the 1.5 horsepower air compressor supplies the rest of the facility.

d. Both compressors are set to start at 60 psig and stop at 120 psig, are equipped with a low pressure alarm at 55 psig, and deliver air at about 80 psig to both the transient rod and the rest of the facility.

Question C.12

[1.0 point]

Which one of the following would be an indication of a leak in the Pool Heat Exchanger?

a. Increased radioactivity in the pond water.

b. Decreased delta T across the Pool Heat Exchanger.

c. Excessive makeup to the pool.

d. Increased pool level.

Section C Plant and Rad Monitoring Systems Page 16 Question C.13

[1.0 point]

Which one of the following will initiate a Reactor Scram AND a Reactor Operation Inhibit?

a. High pool temperature.

b. Both East and West Bay Radiation Trips defeated.

c. High Radiation Co-60 Lab Monitor

d. Reactor Bay Truck Door open.

Question C.14

[1.0 point]

Which one of the following describes an RSS operational interlock function while in the PULSE mode of operation?

a. Prevents manual withdrawal of more than one rod.

b. Prevents application of air to the transient rod if the drive is not fully down.

c. Prevents manual withdrawal of any rod.

d. Prevents movement of all rods except the transient rod.

Question C.15

[1.0 point]

The DCC-X bulk pool temperature alarms at ~100F to ensure that:

a. there is an adequate heat sink for the full thermal power of the reactor.

b. the anion bed in the demineralizer is not damaged.

c. the expansion of pool water at higher temperatures does not reduce the moderating capability of the coolant.

d. nucleate boiling does not occur on fuel element surfaces.

Question C.16

[1.0 point]

Which one of the following is true for ALL control rods (i.e., the safety, the shim, the regulating and the transient rods)

a. A stroke of about 15 inches.

b. A length of about 43 inches.

c. A fuel follower of about 15 inches.

d. They contain graphite reflector sections.

Section C Plant and Rad Monitoring Systems Page 17 Question C.17

[1.0 point]

Which one of the following is true for the rod drive interlocks?

a. The rod drive interlock logic is fail safe on loss of power since power is not required for the motor controller digital inputs to perform the inhibit function.

b. The rod drive pushbuttons provide normally closed contacts for interlock functions and normally open contacts for inputs to DCC-X.

c. The interlock validation in RSS and the use of redundant software interlocks for the demand velocity signal provide a diverse control rod withdrawal interlock.

d. If more than one up pushbutton is pressed at one time, the logic blocks manual withdrawal of the last selected rod or rods and all rods in the automatic mode of control.

Question C.18

[1.0 point]

Which one of the following initiates a reactor operation inhibit by DCC-X?

a. Emergency exhaust system operating.

b. Reactor pool level below normal.

c. Radiation hazard from the neutron beam ports.

d. Fuel temperature is high.

Question C.19

[1.0 point]

Which one of the following is one of the several sources of water that are available for adding water to the reactor pool by permanently installed piping?

a. Water from the Co-60 pool can be pumped by the primary cooling system pump to the reactor pool.

b. The University water system can supply the pool through the demineralizer.

c. The University water system can supply a high flow rate to the emergency pool flooding system.

d. The heat exchanger secondary side can supply the pool drain lines.

Section C Plant and Rad Monitoring Systems Page 18 Question C.20

[1.0 point]

Which one of the following is a correct description of the design response of the emergency lighting system when AC current is lost?

a. A relay closes so that the un-interruptible power supply (UPS) provides power to the emergency lighting system.

b. A relay closes so that emergency generator power is supplied to the emergency lighting system lights.

c. A relay closes so that emergency lighting system battery DC power is supplied to the emergency lighting system lights.

d. An alarm indication is sent to the DCC-X which initiates transfer to the facility transformer.

(*** End of Examinatiuon ***)

Section A:  Theory, Thermo & Fac. Operating Characteristics Page 19 A.1 c

REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, § 4.6, p. 4-16.

A.2 a

REF: CR1 / CR2 = (1 - Keff2) / (1 - Keff1) 50 / 25 = (1 - Keff2) / (1 - 0.8)

Therefore Keff2 = 0.6

= Keff2 - Keff1 / Keff2

• Keff1 = (0.6 - 0.8)/(0.6

• 0.8) = - 0.41667 A.3 a

REF: P = P0 et/ Po = 110% = 20 sec. t = 0.5 P = 110 e 0.5/20 = 112.78%

A.4 d

REF: Glasstone and Sesonske, Nuclear Reactor Engineering, Chapter 5, Section 5.114 A.5 b

REF: Standard NRC Reactor Theory Question A.6 a REF: Standard NRC Reactor Theory Question A.7 b

REF: Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, P = Poet/T 10 = 1e60/T ln 10 = 60/T 2.3 = 60/T T = 60/2.3 T = 26 seconds A.8 a

REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, § 5.7, pp. 5-28 5-38 A.9 a

REF: Tsec= (Flowpri/Flowsec) x Tpri Tsec= (500/700) x 13F = 9.28F Secondary outlet = 73F + 9.28F = 82.3F A.10 a

REF: PSBR Training Manual A.11 b

REF: Lamarsh, Introduction to Nuclear Engineering, 2nd Edition, pg. 313.

A.12 b

REF: A = Ao e-t =.693 / T2 Ln A/Ao = -.693 t / T2 T2 = -.693

• 24hr / ln 0.8 = 75 hr A.13 b

REF: Introduction to Nuclear Reactor Operations, Reed Robert Brown, Section 3.2.2.

A.14 a

REF: PSBR Training Manual, Pages 2-28 through 2-32 A.15 a

REF: Introduction to Nuclear Reactor Operations, Reed Robert Brown, Section 5.4 A.16 c

REF: Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, §§ 3.161 3.163, pp. 190 & 191.

A.17 a

Section A:  Theory, Thermo & Fac. Operating Characteristics Page 20 REF: Introduction to Nuclear Reactor Operations, Reed Robert Brown, Section 4.3, Reactor Period and Reactor Power A.18 d

REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1988 pg. 3-4.

A.19 c

REF: Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. §, p. 282.

A.20 c

REF: Reactor Physics Notes

Section B Normal/Emerg. Procedures & Rad Con Page 21 B.1 c

REF: 10CFR50.54(y)

B.2 c

REF: TS 3.1.1 B.3 c

REF: TS 1.1.6 B.4 b

DELETED REF: Nuclear Power Plant Health Physics and Radiation Protection, Ch. 10 B.5 a, 20; b, 1; c, 1; d, 10 REF: 10CFR20.100x B.6 a, 2; b, 3; c, 3; d, 4 REF: 10 CFR 20.1003, Definitions B.7 c

REF: Two inches = one-half thickness (T1/2). Using 5 half-thickness will drop the dose by a factor of (1/2)5 = 1/32  100/32 = 3.13 B.8 a

REF: 10 CFR 20.1003 Definitions B.9 d

REF: 10 CFR 20.1601 B.10 1 d 2 c 3 b 4 c REF: 10CFR55 B.11 a

REF: T.S. 2.1 - Basis B.12 b

REF: T.S. 3.2.4 B.13 b

REF: T.S. 3.7 B.14 c

REF: 10 CFR 50.54 q; 10 CFR 50.59; 10 CFR 55.59 B.15 a

REF: PSBR EP-8 B.16 a

REF: T.S. 3.4 B.17 c

REF: 10CFR55.53(e) & (f)

(*** End of Section B ***)

Section C: Plant and Rad Monitoring Systems Page 22 C.1 b

REF: PSBR Training Manual, Page 3.20 C.2 c

REF: PSBR Training Manual, Section 3.20.

C.3 c

REF: PSBR Training Manual, Section 3.2 C.4 c

REF: PSBR Training Manual, Section 4.9 C.5 a, c REF: CCP-4 C.6 c

REF: PSBR Training Manual, Section 4.20.7.2a C.7 d

REF: PSBR Training Manual, Page 3-13.

C.8 b

REF: PSBR Training Manual, Section 3.25 C.9 c

REF: PSBR Training Manual, Section 4.20.6.1b C.10 b

REF: PSBR Training Manual, Section 3.17 C.11 b

REF: PSBR Training Manual, Section 3.14.

C.12 d

REF: PSBR Training Manual, Section 3.11 C.13 d

REF: PSBR Training Manual, Section 4.20.6.1b C.14 d

REF: PSBR Training Manual, Section 4.20.4.2 C.15 b

REF: PSBR Training Manual, Section 3.9 C.16 a

REF: PSBR Training Manual, Section 3.5 C.17 b

REF: PSBR Training Manual, Section 4.20.7.2c C.18 c

REF: PSBR Training Manual, page 4-29

Section C: Plant and Rad Monitoring Systems Page 23 C.19 b

REF: PSBR Training Manual, Section 3.8 C.20 b

REF: PSBR Training Manual, Section 3.16

(***** End of Examination *****)