ML12276A049

Examination Report No 50-193/OL-12-01, Rhode Island Atomic Energy Commission

ML12276A049
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	10/09/2012
From:	Gregory Bowman Division of Policy and Rulemaking
To:	Tehan T State of RI, Atomic Energy Comm
Isaac P
Shared Package
ML12160S301	List: ML12276A049
References
50-193/OL-12-01 50-193/OL-12-01
Download: ML12276A049 (40)

Text

October 9, 2012 Mr. Terence Tehan, Director Nuclear Science Center Rhode Island Atomic Energy Commission 16 Reactor Road Narragansett, RI 02882-1165

SUBJECT:

EXAMINATION REPORT NO. 50-193/OL-12-01, RHODE ISLAND ATOMIC ENERGY COMMISSION

Dear Mr. Tehan:

During the week of August 13, 2012, the NRC administered operator licensing examinations at your Rhode Island Nuclear Science Center 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 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. Patrick J. Isaac at (301) 415-1019 or via internet e-mail patrick.isaac@nrc.gov.

Sincerely,

/RA/

Greg Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-193

Enclosures:

1. Initial Examination Report No. 50-193/OL-12-01

2. Written examination cc w/o enclosures: See next page

October 9, 2012 Mr. Terence Tehan, Director Nuclear Science Center Rhode Island Atomic Energy Commission 16 Reactor Road Narragansett, RI 02882

SUBJECT:

EXAMINATION REPORT NO. 50-193/OL-12-01, RHODE ISLAND ATOMIC ENERGY COMMISSION

Dear Mr. Tehan:

During the week of August 13, 2012, the NRC administered operator licensing examinations at your Rhode Island Nuclear Science Center 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 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. Patrick J. Isaac at (301) 415-1019 or via internet e-mail patrick.isaac@nrc.gov.

Sincerely,

/RA/

Greg Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-193

Enclosures:

1. Initial Examination Report No. 50-193/OL-12-01

2. Examination and answer key cc w/o enclosures:

Please see next page DISTRIBUTION w/ encls.:

PUBLIC PROB r/f Facility File CRevelle (O12-D19)

ADAMS ACCESSION #: ML12276A049 TEMPLATE #:NRR-074 OFFICE PROB:CE IOLB:LA PROB:BC NAME PIsaac CRevelle GBowman DATE 10/07/2012 10/02 /2012 10/09/2012 OFFICIAL RECORD COPY

Rhode Island Atomic Energy Commission Docket No. 50-193 cc:

Governor State House Room 115 Providence, RI 02903 Dr. Stephen Mecca, Chairman Rhode Island Atomic Energy Commission Providence College Department of Engineering-Physics Systems River Avenue Providence, RI 02859 Dr. Jack Breen, Chairman Providence College 549 River Avenue Providence, RI 02918 Dr. Andrew Kadak 253 Rumstick Road Barrington, RI 02806 Dr. Bahram Nassersharif Dean of Engineering University of Rhode Island 102 Bliss Hall Kingston, RI 20881 Dr. Peter Gromet Department of Geological Sciences Brown University Providence, RI 02912 Dr. Tony Nunes University of Rhode Island 210 East Hall Kingston, RI 02881 Chief Office of Facilities Regulation Rhode Island Department of Health 3 Capitol Hill, Room 206 Providence, RI 02908-5097 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING EXAMINATION REPORT REPORT NO.: 50-193/OL-12-01 FACILITY DOCKET NO.: 50-193 FACILITY LICENSE NO.: R-95 FACILITY: Rhode Island Atomic Energy Commission EXAMINATION DATES: August 13-14, 2012 EXAMINER: Patrick Isaac, Chief Examiner SUBMITTED BY: /RA/ 09/7 /2012 Patrick Isaac, Chief Examiner Date

SUMMARY

During the week of August 13, 2012, NRC administered Operator Licensing Examinations to two Reactor Operator (RO) candidates. One candidate failed the operating test. The other candidate passed all portions of the examinations.

REPORT DETAILS

1. Examiners:

Patrick J. Isaac, Chief Examiner

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 N/A 2/0 Operating Tests 1/1 N/A 1/1 Overall 1/1 N/A 1/1

3. Exit Meeting:

Mr. Jeff Davis, Assistant Director, RINSC Patrick Isaac, Chief Examiner There were no generic concerns raised by the examiner.

ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: RINSC REACTOR TYPE: Pool DATE ADMINISTERED: 08/13/2012 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 Section  % of Candidates Section Value Total Score Value Section 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 ENCLOSURE 2

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

( )2 eff = 0.1sec 1 Q = m cP T = m H =UAT Pmax =

(2 )

S S t SCR = * =1x104 sec P = P0 e 1 K eff eff SUR = 26 .06 ( ) (

CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )

1 CR (1 ) M= = 1 P = P0 10SUR(t )

P= P0 1 K eff CR2 1 K eff1 1 K eff

• M= SDM = =

1 K eff 2 K eff

• T1 =

0.693 K eff 2 K eff1

+

eff 2 K eff1 K eff 2 K eff 1

= DR = DR0 et 2 DR1 d1 = DR2 d 2 2

K eff 6 Ci E (n ) ( 2 )2 = (1 )2 DR =

R2 Peak2 Peak1 DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf °F = 9/5 °C + 32 1 gal (H2O) 8 lbm °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lbm/°F cp = 1 cal/sec/gm/°C

A. RX THEORY, THERMO & FAC OP CHARS ANSWER SHEET 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 ___

007 a b c d ___

008 a b c d ___

009 a b c d ___

010 a b c d ___

011 a b c d ___

012 a b c d ___

013 a b c d ___

014 a b c d ___

015 a b c d ___

016 a b c d ___

017 a b c d ___

018 a b c d ___

019 a b c d ___

020 a b c d ___

(END OF SECTION A)

B. NORMAL/EMERG PROCEDURES & RAD CON ANSWER SHEET 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 ___

007 a b c d ___

008 a ___ b ___ c ___ d ___

009 a b c d ___

010 a b c d ___

011 a b c d ___

012 a b c d ___

013 a b c d ___

014 a ___ b ___ c ___ d ___ e ___

015 a b c d ___

016 a b c d ___

017 a b c d ___

018 a b c d ___

019 a b c d ___

020 a b c d ___

(END OF SECTION B)

C. PLANT AND RAD MONITORING SYSTEMS ANSWER SHEET 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 ___

007 a b c d ___

008 a b c d ___

009 a b c d ___

010 a b c d ___

011 a b c d ___

012 a b c d ___

013 a b c d ___

014 a ___ b ___ c ___ d ___

015 a b c d ___

016 a b c d ___

017 a b c d ___

018 a b c d ___

019 a b c d ___

(END OF SECTION 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 two (2) hours for completion of the examination.

Section A L Theory & Fac. Operating Characteristics QUESTION (A.1) [1.0]

A reactor is critical at 1 Watt. Subsequent rod motion causes a power increase at an indicated period of 30 seconds. Reactor power 2 minutes later will be approximately:

a. 55 Watts

b. 35 Watts

c. 15 Watts

d. 5 Watts Question (A.2) [1.0]

Which one of the following describes the response of the subcritical reactor to equal insertions of positive reactivity as the reactor approaches criticality at low power?

a. Each reactivity insertion causes a SMALLER increase in the neutron flux, resulting in a LONGER time to reach equilibrium.

b. Each reactivity insertion causes a LARGER increase in the neutron flux, resulting in a LONGER time to reach equilibrium.

c. Each reactivity insertion causes a SMALLER increase in the neutron flux, resulting in a SHORTER time to reach equilibrium.

d. Each reactivity insertion causes a LARGER increase in the neutron flux, resulting in a SHORTER time to reach equilibrium.

Question (A.3) [1.0]

Which one of the following is true concerning the differences between prompt and delayed neutrons?

a. Prompt neutrons account for less than one percent of the neutron population while delayed neutrons account for approximately ninety nine percent of the neutron population

b. Prompt neutrons are released during fast fissions while delayed neutrons are released during thermal fissions

c. Prompt neutrons are released during the fission process while delayed neutrons are released during the decay process

d. Prompt neutrons are the dominating factor in determining the reactor period while delayed neutrons have little effect on the reactor period

Section A L Theory & Fac. Operating Characteristics Question (A.4) [1.0]

Which one of the following statements describes why installed neutron sources are used in reactor cores?

a. To increase the count rate by an amount equal to the source contribution.

b. To increase the count rate by 1/M (M = Subcritical Multiplication Factor).

c. To provide neutrons to initiate the chain reaction.

d. To provide a neutron level high enough to be monitored by instrumentation.

Question (A.5) [1.0]

A reactor contains three safety rods and a control rod. Which one of the following would result in a determination of the excess reactivity of this reactor?

a. The reactor is critical at a low power level, with all safety rods full out and the control rod at some position. The reactivity remaining in the control rod (i.e. its rod worth from its present position to full out) is the excess reactivity.

b. The reactor is shutdown. Two safety rods are withdrawn until the reactor becomes critical.

The total rod worth withdrawn is the excess reactivity.

c. The reactor is at full power. The total worth of all rods withdrawn is the excess reactivity.

d. The reactor is at full power. The total worth remaining in all the safety rods and the control rod (i.e. their worth from their present positions to full out) is the excess reactivity.

Question (A.6) [1.0]

Which one of the following statements concerning reactivity values of equilibrium (at power) xenon and peak (after shutdown) xenon is correct? Equilibrium xenon is _________ of power level; peak xenon is _______ of power level.

a. INDEPENDENT INDEPENDENT

b. INDEPENDENT DEPENDENT

c. DEPENDENT INDEPENDENT

d. DEPENDENT DEPENDENT

Section A L Theory & Fac. Operating Characteristics Question (A.7) [1.0]

Reactor A increases power from 10% to 20% with a period of 50 seconds. Reactor B increases power from 20% to 30% with a period of also 50 seconds. Compared to Reactor A, the time required for the power increase of Reactor B is:

a. longer than A.

b. exactly the same as A.

c. twice that of A.

d. shorter than A.

Question (A.8) [1.0]

A control rod was withdrawn two (2) inches. The steady reactor period following rod withdrawal is observed to be sixty (60) seconds.

Which one of the following is the differential rod worth?

a. 1.0 x 10-3 delta k/k per inch

b. 5.6 x 10-3 delta k/k per inch

c. 1.12 x 10-4 delta k/k per inch

d. 5.0 x 10-4 delta k/k per inch Question (A.9) [1.0]

A reactor is subcritical with a shutdown margin of 0.0526 delta k/k. The addition of a reactor experiment increases the indicated count rate from 10 cps to 20 cps. Which one of the following is the new keff of the reactor?

a. .53

b. .90

c. .975

d. 1.02

Section A L Theory & Fac. Operating Characteristics Question (A.10) [1.0]

The reactor is operating at 100 KW. The reactor operator withdraws the control rod allowing power to increase. The operator then inserts the same rod to its original position, decreasing power. In comparison to the rod withdrawal, the rod insertion will result in:

a. a slower period due to long lived delayed neutron precursors.

b. a faster period due to long lived delayed neutron precursors.

c. the same period due to equal amounts of reactivity being added.

d. the same period due to equal reactivity rates from the rod.

Question (A.11) [1.0]

Which one of the following is the principal source of heat in the reactor after a shutdown from extended operation at 100 KW?

a. Production of delayed neutrons

b. Subcritical reaction of photoneutrons

c. Spontaneous fission of U238

d. Decay of fission fragments Question (A.12) [1.0]

Which one of the following factors is the most significant in determining the differential worth of a control rod?

a. The rod speed.

b. Reactor power.

c. The flux shape.

d. The amount of fuel in the core.

Question (A.13) [1.0]

The term "Prompt Critical" refers to:

a. the instantaneous jump in power due to a rod withdrawal

b. a reactor which is supercritical using only prompt neutrons

c. a reactor which is critical using both prompt and delayed neutrons

d. a reactivity insertion which is less than eff

Section A L Theory & Fac. Operating Characteristics Question (A.14) [1.0]

A rod with a reactivity of -0.003 K/K is inserted into a critical reactor. Which one of the following is the final stable reactor period?

a. -100 seconds

b. -90 seconds

c. -80 seconds

d. -70 seconds Question (A.15) [1.0]

Which one of the following conditions would INCREASE the shutdown margin of a reactor?

a. Inserting an experiment adding positive reactivity.

b. Lowering moderator temperature if the moderator temperature coefficient is negative.

c. Depletion of a burnable poison.

d. Depletion of uranium fuel.

Question (A.16) [1.0]

A reactor with an initial population of 24000 neutrons is operating with Keff = 1.01. Of the CHANGE in population from the current generation to the next generation, how many are prompt neutrons?

a. 24

b. 238

c. 240

d. 24240 Question (A.17) [1.0]

Following a significant reactor power increase, the moderator temperature coefficient becomes increasingly more negative. This is because:

a. as moderator density decreases, less thermal neutrons are absorbed by the moderator than by the fuel.

b. the change in the thermal utilization factor dominates the change in the resonance escape probability.

c. a greater density change per degree F occurs at higher reactor coolant temperatures.

d. the core transitions from an under-moderated condition to an over-moderated condition.

Section A L Theory & Fac. Operating Characteristics Question (A.18) [1.0]

The following data was obtained during a reactor fuel load.

No. of Elements Detector A (cps) 0 60 6 80 12 120 18 400 22 1200 Which one of the following is the closest number of fuel elements required to make the reactor critical?

a. 18

b. 22

c. 24

d. 26 Question (A.19) [1.0]

Which one of the following will be the resulting stable reactor period when a $0.25 reactivity insertion is made into an exactly critical reactor core?

a. 18 seconds

b. 30 seconds

c. 38 seconds

d. 50 seconds Question (A.20) [1.0]

Which alteration or change to the core will most strongly affect the thermal utilization factor.

a. Build up of fission products in fuel.

b. Removal of moderator.

c. Addition of U238

d. Removal of a control rod.

(End of Section A)

Section B Normal/Emerg. Procedures & Rad Con QUESTION (B.1) [1.0]

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]

Safety Limits are Y

a. limits on important process variables which are established to protect the integrity of the fuel clad.

b. settings for automatic protective devices related to those variable having significant safety functions.

c. settings for ANSI 15.8 suggested reactor scrams and/or alarms which form the protective system for the reactor or provide information which requires manual protective action to be initiated.

d. the lowest functional capability or performance levels of equipment required for safe operation of the reactor.

QUESTION (B.3) [1.0]

Based on the Requalification Plan for operators, each licensed operator must complete a minimum of reactivity manipulations during each 2 year cycle.

a. 4

b. 10

c. 20

d. 28

Section B Normal/Emerg. Procedures & Rad Con QUESTION (B.4) [1.0]

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) [1.0]

What is the best type of shielding material to protect from a thermal neutron beam?

a. Lead

b. Heavy clothing

c. Rubber

d. Boron-10 QUESTION (B.6) [1.0]

Which one of the following is the definition of Committed Dose Equivalent?

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

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

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

d. The 50 year dose equivalent to an organ or tissue resulting from an intake of radioactive material.

QUESTION (B.7) [1.0]

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

Section B Normal/Emerg. Procedures & Rad Con Section B Normal/Emerg. Procedures & Rad Con QUESTION (B.8) [2.0]

Identify each of the actions listed below as either a Channel Check, Channel Test, or Channel Calibration.

a. Verifying overlap between Nuclear Instrumentation meters. 1. Channel Calibration

b. Replacing an RTD with a precision resistance decade box, 2. Channel Check to verify proper channel output for a given resistance.

3. Channel Test

c. Performing a calorimetric (heat balance) calculation on the primary system, then adjusting Nuclear Instrumentation to agree.

d. During shutdown you verify that the period meter reads

-80 seconds.

QUESTION (B.9) [1.0]

A room contains a source which, when exposed, results in a general area dose rate of 175 millirem per hour. 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 ADanger-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 QUESTION (B.10) [1.0]

Which one of the following lists the four reactor scrams associated the Technical Specification Safety Limits for the forced convection mode of operation?

a. Reactor thermal power.

Reactor short period.

Reactor coolant flow rate.

Reactor pool temperature.

b. Reactor thermal power.

Reactor coolant flow rate.

Reactor coolant outlet temperature.

Height of water above the top of the core.

c. Reactor short period.

Reactor coolant outlet temperature.

Primary coolant system operable.

Reactor pool temperature.

d. Reactor coolant inlet temperature.

Reactor coolant outlet temperature.

Primary coolant system operable.

Height of water above the center line of the core.

QUESTION (B.11) [1.0]

During performance of a power calibration, indicated power differed from calculated power by 15 Kwatts. Which one of the following actions is required for the Linear Power and Percent Power channels?

a. Adjust the detector high voltage on the detectors.

b. Adjust the compensating voltages on the detectors.

c. Adjust the detector heights.

d. No adjustment necessary.

Section B Normal/Emerg. Procedures & Rad Con QUESTION (B.12) [1.0]

Which one of the following is NOT a guidance/recommendation under APlanned Occupational Exposure under Emergency Conditions@ for Life Saving Actions?

a. Planned whole body dose not to exceed 100 rems.

b. Persons receiving exposures under the planned actions should avoid procreation for a few months.

c. Planned dose to hands and forearms not to exceed 300 rems.

d. The younger volunteers should perform the rescue.

QUESTION (B.13) [1.0]

At the RINSC the Emergency Support Center (ESC) is ...

a. located outside the EPZ.

b. located at the South County Hospital in Wakefield, RI.

c. the geographical area within the site boundary where the Emergency Coordinator has direct authority over all activities.

d. the control room.

QUESTION (B.14) [2.0, 0.4 each]

Match the abnormal condition listed in Column A with the appropriate action from Column B.

COLUMN A COLUMN B

a. Pottermeter and primary T readings abnormal for 1. Shutdown only operating conditions.

2. Maintain L at power

b. Reactor power unexpectedly drops from 95% to 92%. 3. Automatic Scram

c. The alarm for the high Neutron flux on one of the ion 4. Manual Scram chamber safety channels becomes inoperable due to a faulty relay.

d. Loss of one stack monitor. Repair parts expected to arrive in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

e. Emergency Generator fails to start

Section B Normal/Emerg. Procedures & Rad Con QUESTION (B.15) [1.0]

Which one of the following is an Emergency Action Level for an Alert condition at the RINSC?

a. Radiation levels at the site boundary is 80 mrem whole body over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. Building air monitor reading 10 times higher than normal.

c. Radiation levels at the site boundary is 100 mrem/hr for one (1) hour whole body.

d. Projected dose at site boundary is 50 times higher than normal.

Section B Normal/Emerg. Procedures & Rad Con QUESTION (B.16) [1.0]

Which one of the following statements is TRUE concerning experiments?

a. The reactivity insertion rate of experiments will not exceed 0.02 % K/K.

b. The reactivity worth of any experiment NOT fixed in place shall not exceed 0.6% K/K.

c. Samples measuring >200 mrem/hr on contact are not allowed out of the reactor room without special permission.

d. The reactivity worth of all experiments shall NOT exceed 3.0% K/K.

QUESTION (B.17) [1.0]

It is April 1, 2012. You have stood watch for the following hours during the last quarter:

Jan. 11 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Feb. 24 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Mar. 16 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.

QUESTION (B.18) [1.0]

Calculate the T.S. Shutdown Margin. Assume the following worths:

worth %K/K Blade #1: 2.38 Blade #2: 2.56 Blade #3: 2.40 Blade #4: 2.37 Regulating Blade: 0.084 Excess Reactivity: 1.64 Experiments (Max Worth)

a. 4.83%

b. 4.91%

c. 7.39%

d. 8.07%

Section B Normal/Emerg. Procedures & Rad Con (End of Section B)

Section C Plant and Rad Monitoring Systems QUESTION (C.1) [1.0]

While operating in the Natural Convection Flow Mode which one of the following will result in a reactor scram?

a. Primary Coolant Flow = 40 gpm

b. Coolant Outlet Temperature = 123EF

c. Log N amplifier high voltage at 40 volts

d. Reactor Power = 110 kw QUESTION (C.2) [1.0]

Which of the following choices is NOT an interlock prohibiting withdrawal of safety blades during startup? Assume all scram conditions are cleared.

a. NI read less than 3 cps

b. Startup counter drive off

c. Master switch is in test

d. Mode switch is in rundown QUESTION (C.3) [1.0]

The "TEST" position of the Master Switch allows:

a. insertion of scram signals without de-energizing the scram magnets.

b. control power and lamp indication operability testing.

c. control blade drive motion without energizing the scram magnets.

d. control blade drive motion with energized scram magnets.

QUESTION (C.4) [1.0]

The thermal column design prevents radiation streaming by:

a. a movable lead shutter that is normally closed.

b. installation of portable shielding around the experiment.

c. alternately stacked graphite logs and a stepped closure door.

d. concrete filler plugs.

Section C Plant and Rad Monitoring Systems QUESTION (C.5) [1.0]

Which one of the following actions should NOT automatically occur when the evacuation button is depressed?

a. The air conditioning and normal ventilation fans turn off.

b. All dampers on ventilating ducts leading outside close.

c. The building cleanup system air scrubber and fresh air blower turn off.

d. The off-gas blower and rabbit system blower turn off.

QUESTION (C.6) [1.0]

Based upon the LOCA analysis, which one of the following is NOT assumed in order to conclude that the loss of coolant event would not cause core damage?

a. All beamport fixed experiments are designed to withstand a minimum of 25.09 feet of water pressure.

b. No beamport experiment will be installed with a barrier having an opening greater than the equivalent area of a 1/2 inch diameter hole.

c. The capacity of the normal pool make-up system shall exceed the loss of coolant flow rate.

d. The maximum loss of coolant flow rate is 20 gallons.

QUESTION (C.7) [1.0]

Which one of the listed tanks is the normal collection point for non-sanitary liquid waste from the reactor building?

a. Delay Tank

b. Radiation Waste Tank

c. Retention Tank

d. Resin Tank

Section C Plant and Rad Monitoring Systems QUESTION (C.8) [1.0]

Which ONE of the following scrams is an 'electric' scram?

a. Gate

b. Seismic

c. High Voltage failure

d. Reactor Period QUESTION (C.9) [1.0]

Which ONE of the following CORRECTLY describes a signal in the automatic power level channel?

a. A reactor period signal is supplied to the circuit which prohibits automatic control if reactor period is less than 20 seconds.

b. The servo amplifier provides a gain function signal which varies directly with reactor power.

c. The servo amplifier supplies a reference voltage used as the system power demand.

d. The servo amplifier receives a signal from the Rod Position system which is used to slow the motor when approaching the upper or lower rod limit.

QUESTION (C.10) [1.0]

Which ONE of the following conditions will cause a HIGH CONDUCTIVITY reading at the INLET of the demineralizer?

a. Failure of the cooling water heat exchanger.

b. Pool water temperature low.

c. Reactor water system pressure greater than secondary water pressure.

d. High reactor water pump flow.

QUESTION (C.11) [1.0]

Which of the following electrical loads is POWERED by the Nuclear Center Generator when normal power is lost?

a. Sump Pump

b. Stack Monitor (CAM)

c. Primary Coolant Pump

d. Console Power

Section C Plant and Rad Monitoring Systems QUESTION (C.12) [1.0]

Which one of the following conditions will generate an alarm when the Power Level Selector switch is in the A0.1 MW@ position?

a. Thermal Column flow sensor reads zero.

b. Bridge movement is detected by sensor.

c. Secondary coolant flow rate is 750 gpm

d. Core outlet temperature is 122 EF QUESTION (C.13 [1.0]

Which one of the following nuclear instrumentation amplifiers sends a signal to the servo system?

a. Start-up preamplifier 10AR1

b. Log-N Period Amplifier 11AR1

c. Stable Picoammeter 12AR1

d. Stable Picoammeter 12AR2 QUESTION (C.14) [2.0]

For each of the parameters listed in column a, list the correct plant response from column b.

COLUMN A COLUMN B

a. Bridge movement 1. Alarm only

b. One safety blade disengaged from magnet 2. Scram only

c. High conductivity (primary) 3. Alarm and Scram

d. High Voltage failure 4. No response QUESTION (C.15) [1.0]

Which one of the following statements is TRUE?

b. Inverting an irradiated fuel element would have no effect on core reactivity or differential control rod worth.

c. The RINSC fully reflected reactor will NOT go critical even if the entire 7 x 9 grid of the core were filled with fuel elements.

a. The volume of water transferred from the pool into the primary is controlled primarily by flow paths in the control blade shrouds.

Section C Plant and Rad Monitoring Systems

a. Full flow through the fuel elements will probably not be turbulent at lower temperatures QUESTION (C.16) [1.0]

Which of the following safety system scrams is NOT bypassed when the Power Level Selector Switch is in the 0.1 Mwatt position?

a. High Temperature Primary Coolant leaving Core

b. Primary Coolant Low Flow Rate

c. Bridge Low Power Position

d. Low Pool Water Level QUESTION (C.17) [1.0]

Which one of the following describes a condition that will prevent the operator from withdrawing control blades?

a. The Power Level Selector switch is in the 5 MW position.

b. The Log N amplifier switch is in the Aoperate position@.

c. Reactor period is 30 seconds.

d. The startup channel neutron count rate is 8 counts per second.

QUESTION (C.18) [1.0]

Which one of the following is the reason for the technical specification regarding height of pool water in the Natural convection Mode?

a. To prevent fuel temperatures from exceeding NRC temperature limits of 530 °C.

b. To provide adequate safety margin in the event of a Loss of Coolant Accident.

c. To prevent nucleate boiling in the hot channel of the core.

d. To provide protection for the cleanup system resin.

Section A L Theory & Fac. Operating Characteristics QUESTION (C.19) [1.0]

Identify the control blade assembly component that provides the AStop@ signal to the drive assembly at either end of blade travel.

a. Drive shaft worm gear.

b. Helical potentiometer

c. Motor limit switch

d. Electromagnetic clutch (End of Examination)

Section A L Theory & Fac. Operating Characteristics ANSWER: (A.01) a REFERENCE P=Poet/ = 1e120sec/30sec = 54.6 ANSWER: (A.02) b REFERENCE Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, 3.161 C 3.163, pp. 190 C 191.

Burn, R., Introduction to Nuclear Reactor Operations, 8 1988, Chapt. 5, pp. 5-1 C 5-28.

ANSWER: (A.03) c REFERENCE Lamarsh, J.R., Introduction to Nuclear Engineering, - 1983. ' 7.1, pp. 280 C 284.

Burn, R., Introduction to Nuclear Reactor Operations, 8 1982, 3.2.2 C 3.2.3, pp. 3-7 C 3-12.

ANSWER: (A.04) d REFERENCE Standard NRC Question Burn, R., 8 1982, '5.2, p. 5-1 ANSWER: (A.05) a REFERENCE T.S. Definition 1.8 Burn, R., Introduction to Nuclear Reactor Operations, 8 1988, 6.2.1, pp. 6-2.

ANSWER: (A.06) d REFERENCE Lamarsh, J.R., Introduction to Nuclear Engineering, - 1983. ' 7.4, pp. 316 C 322.

Burn, R., Introduction to Nuclear Reactor Operations, 8 1988, 8.1 C8.4, pp. 8-3 C 8-14.

ANSWER: (A.07) d REFERENCE The power of reactor A increases by a factor of 2, while the power of reactor B increases by a factor of 1.5. Since the periods are the same (rate of change is the same), power increase B takes a shorter time.

Section A L Theory & Fac. Operating Characteristics ANSWER: (A:08) d REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, 8 1988, ' 7.2 &

eff- eff 7.3, pp. 7-1 C 7-9.

= eff Y = ( )+1

= 0.007/((0.1 60) + 1) = 0.007/7

= 1 x 10-3 delta k/k

/inch = 1 x 10-3 delta k/k/2 inches = 5.0 x 10-4 delta k/k per inch ANSWER: (A.09) c

REFERENCE:

SDM = 1-Keff/Keff 6 Keff = 1/SDM + 1 6 Keff = 1/0.0526 + 1 6 Keff = .95 CR1/CR2 = (1 - Keff2) / (1 - Keff1) 6 10/20 = (1 - Keff2) / (1 - 0.95)

(0.5) x (0.05) = (1 - Keff2) 6 Keff2 = 1 - (0.5)(0.05) = 0.975 ANSWER: (A.10) a REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, 8 1982, 3.2.2 C 3.2.3, pp. 3-7 C 3-12.

ANSWER: (A.11) d.

REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, 8 1982, ' 4.9, pp. 4-23 C 4-26.

ANSWER: (A.12) c REFERENCE Lamarsh, J.R., Introduction to Nuclear Engineering,1983. ' 7.2, p. 303.

Burn, R., Introduction to Nuclear Reactor Operations, 8 1982, ' 7.2 & 7.3, pp. 7-1 C 7-9.

ANSWER: (A.13) b REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, 8 1982, ' 4.2 pp. 4-1 ANSWER: (A.14) c REFERENCE Intro. to Nuclear Operation, p. 4-16

Section A L Theory & Fac. Operating Characteristics ANSWER: (A.15) d REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, 8 1988, ' 6.2.3, p. 6-4.

ANSWER: (A.16) b REFERENCE 24000 neutrons in current generation 1.01 = 24240 neutrons in next generation 240 neutrons added - 0.7% delayed neutron fraction = 238 prompt neutrons added ANSWER: (A.17) c REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, 8 1982, ' 6.4.1, pp. 6-5.

ANSWER: (A.18) c REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, 8 1982, ' 5.5, pp. 5-18 C 5-25.

ANSWER: (A.19) b REFERENCE Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, 1991, ' 5.18, p. 234.

T = (-)/ T = (.0070 - .00175)/.1 x .00175 = 30 seconds ANSWER: (A.20) d REFERENCE Lamarsh, J.R., Introduction to Nuclear Engineering, - 1983. ' 7.2, p. 300 Burn, R., Introduction to Nuclear Reactor Operations, 8 1982, ' 3.3, pp. 3-13 C 3-18.

(End of Section A)

Section B Normal/Emerg. Procedures & Rad Con ANSWER (B.1) c REFERENCE 10CFR50.54(y)

ANSWER (B.2) a REFERENCE TS Definitions pg. 6 ANSWER (B.3) b REFERENCE Requalification Plan ANSWER (B.4) b REFERENCE Nuclear Power Plant Health Physics and Radiation Protection, Ch. 10 ANSWER (B.5) d REFERENCE Nuclear Power Plant Health Physics and Radiation Protection, Ch. 9 ANSWER (B.6) d REFERENCE 10CFR20.1003 ANSWER (B.7) c REFERENCE Two inches = one-half thickness (T2). Using 5 half-thickness will drop the dose by a factor of (2)5 =

1/32 Y 100/32 = 3.13 ANSWER (B.8) a 2, b 3, c 1, d 2 REFERENCE RINSC Tech. Specs, Definitions pg. 2 ANSWER (B.9) d REFERENCE 10 CFR 20.1601 ANSWER (B.10) b REFERENCE RINSC T.S. 2.1

Section B Normal/Emerg. Procedures & Rad Con ANSWER (B.11) c REFERENCE 1997 NRC Exam ANSWER (B.12) d REFERENCE Emergency Plan '7.5.1 Life Saving Actions ANSWER (B.13) a REFERENCE E-Plan pg. 2 ANSWER (B.14) a 4; b 2; c 1; d 1; e 1 REFERENCE Abnormal Procedures ANSWER (B.15) a REFERENCE E-Plan; Emergency Classification System Section 4.0 ANSWER (B.16) c REFERENCE T.S. 3.1 Procedures for Dispatching and Receiving Rabbits, pg. 12-4 ANSWER (B.17) c REFERENCE 10CFR55.53(e) & (f)

ANSWER (B.18) b REFERENCE 1997 NRC Exam SDM = SDM (cold/clean) - Max worth blade - Reg Blade - Max Experiment SDM (cold/clean) = Total Blade worth - Kexcess = 9.794% - 1.64% = 8.154%

SDM = 8.154% - 2.56% - 0.084% - 0.60% = 4.91%

(End of Section B)

Section C Plant and Rad Monitoring Systems ANSWER (C.1) c REFERENCE T.S. Table 2.1.2g. 22 ANSWER (C.2) b REFERENCE Facility provided question ANSWER (C.3) c REFERENCE General Electric Operation and Maintenance Manual ANSWER (C.4) c REFERENCE SAR ANSWER (C.5) c REFERENCE Facility provided question ANSWER (C.6) c REFERENCE SAR (HEU to LEU Conv.); Loss of Coolant Analysis pg. 17-18 ANSWER (C.7) c REFERENCE 1993 NRC Exam ANSWER (C.8) d REFERENCE General Electric Operation Manual ANSWER (C.9) c REFERENCE General Electric Operation Manual ANSWER (C.10) a REFERENCE General Electric Operation Manual

C. PLANT AND RAD MONITORING SYSTEMS ANSWER (C.11) a REFERENCE Facility supplied question ANSWER (C.12) b REFERENCE SAR (HEU - LEU) Table F.1 ANSWER (C.13) c REFERENCE Operation and Maintenance Manual Table 1-2 pg. 1-47 ANSWER (C.14)

a. 3; b. 1; c 1; d 3 REFERENCE Facility supplied question ANSWER (C.15) a REFERENCE SAR ANSWER (C.16) d REFERENCE Facility supplied question ANSWER (C.17) a REFERENCE SAR (HEU to LEU) pg. 11 ANSWER (C.18) c REFERENCE T.S. 2.1.2 Bases ANSWER (C.19) c REFERENCE SAR for HEU to LEU Conversion; Appendix F pg. 43 (End of Section C)

(*** End of Examination ***)