ML042080380

Retake Examination Report No. 50-020/OL-04-01, Mit

ML042080380
Person / Time
Site:	MIT Nuclear Research Reactor
Issue date:	07/30/2004
From:	Madden P NRC/NRR/DRIP/RNRP
To:	Bernard J Massachusetts Institute of Technology (MIT)
Doyle P, NRC/NRR/DRIP/RNRP, 415-1058
Shared Package
ML041730525	List: ML041740087 ML042080380 ML042080447
References
50-020/OL-04-01 50-020/OL-04-01
Download: ML042080380 (20)

Text

July 30, 2004 Dr. John Bernard, Director of Reactor Operations Nuclear Reactor Laboratory Massachusetts Institute of Technology 138 Albany Street Cambridge, MA 02139

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-020/OL-04-01, MASSACHUSETTS INSTITUTE OF TECHNOLOGY

Dear Dr. Bernard:

During the week of July 12, 2004, your staff administered an NRC prepared operator licensing examination at your Massachusetts Institute of Technology Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

In accordance with 10 CFR 2.790 of the Commissions 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 NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Paul Doyle at (301) 415-1058 or via internet e-mail at pvd@nrc.gov.

Sincerely,

/RA/

Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.50-020

Enclosures:

1. Initial Examination Report No. 50-020/OL-04-01

2. Examination and answer key. (Corrected) cc w/encls:

Please see next page

July 30, 2004 Dr. John Bernard, Director of Reactor Operations Nuclear Reactor Laboratory Massachusetts Institute of Technology 138 Albany Street Cambridge, MA 02139

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-020/OL-04-01, MASSACHUSETTS INSTITUTE OF TECHNOLOGY

Dear Dr. Bernard:

During the week of July 12, 2004, your staff administered an NRC prepared operator licensing examination at your Massachusetts Institute of Technology Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

In accordance with 10 CFR 2.790 of the Commissions 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 NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Paul Doyle at (301) 415-1058 or via internet e-mail at pvd@nrc.gov.

Sincerely, Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.50-020

Enclosures:

1. Initial Examination Report No. 50-020/OL-04-01

2. Examination and answer key. (Corrected) cc w/encls:

Please see next page DISTRIBUTION w/ encls.:

PUBLIC RNRP R&TR r/f PMadden Facility File (EBarnhill) O-6 F-2 AAdams EXAMINATION PACKAGE ACCESSION NO.: ML041730525 EXAMINATION REPORT ACCESSION #: ML042080380 TEMPLATE #: NRR-074 OFFICE RNRP:CE IROB:LA E RNRP:SC NAME PDoyle:vmj EBarnhill PMadden DATE 7/ 25 /2004 7/ 27 /2004 7/ 29 /2004 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

Massachusetts Institute of Docket No. 50-20 Technology cc:

City Manager City Hall Cambridge, MA 02139 Department of Environmental Quality Engineering 100 Cambridge Street Boston, MA 02202 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.: 50-020/OL-04-01 FACILITY DOCKET NO.: 50-020 FACILITY LICENSE NO.: R-37 FACILITY: Massachusetts Institute of Technology EXAMINATION DATES: July 14, 2004 SUBMITTED BY: __________/RA/________________ 7/16/04______

Paul Doyle, Chief Examiner Date

SUMMARY

The NRC prepared a written examination (Section B) for one Reactor Operator candidate who had failed the examination administered February, 2004. The examiner mailed the examination to the facility, who then administered the examination to the candidate. The candidate passed the examination.

REPORT DETAILS

1. Examiners:

Paul Doyle, Chief Examiner

2. Results:

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

3. Exit Meeting:

There was no exit meeting.

ENCLOSURE 1

MASSACHUSETTS INSTITUTE OF TECHNOLOGY With Answer Key OPERATOR LICENSING EXAMINATION Week of July 12, 2004 Enclosure 2

Section B Normal, Emergency and Radiological Control Procedures Page 2 QUESTION B.1 [1.0 point]

(NOTE: For this question assume all attenuation is due to shielding, and ignore any changes in dose due to distance.) Holding a probe at the surface of a pool, an experiment in the pool reads 50mr/hr at 2 feet below the pool surface and 100 mr/hr at 1 foot below the pool surface. You decide to place the experiment at 20 feet below the surface of the pool. Based on the attenuations you noted between the 2 foot and 1 foot levels, you would expect the shielding at 20 feet below the surface of the pool to reduce the dose by a factor of approximately

a. 1000

b. 10,000

c. 100,000

d. 1,000,000 QUESTION B.2 [1.0 point]

The air purge above the reactor is secured. If H2 concentration increases to above 1.0% Technical Specifications require you to A. insert a Major Scram.

B. insert a Minor Scram.

C. reduce power to less than 200 Kw.

D. perform a normal reactor shutdown.

QUESTION B.3 [2.0 points, D each]

Match the experiment type listed in column A with the corresponding Technical Specification limit listed in column B. (Notes: Only one answer for each item in column A. Items in column B, may be used more than once, or not at all.)

Column A Column B A. Single movable 1. 0.2% K/K B. Total movable 2. 0.5% K/K C. Single Non-secured 3. 1.0% K/K D. Total Non-secured 4. 1.5% K/K E. Single secured 5. 1.8% K/K F. Total secured

Section B Normal, Emergency and Radiological Control Procedures Page 3 QUESTION B.4 [1.0 point]

Which ONE of the following classifications for an emergency is not credible for the MIT reactor? (Note: Items are listed alphabetically, NOT in order of severity!)

a. Alert

b. General Emergency

c. Notification of Unusual Event

d. Site Area Emergency QUESTION B.5 [1.0 point]

While working on an experiment, you receive the following radiation doses: 100 mrem ( ), 25 mrem ( ), and 5 mrem (thermal neutrons). Which ONE of the following is your total dose?

a. 175 mrem

b. 155 mrem

c. 145 mrem

d. 130 mrem QUESTION B.6 [1.0 point]

Pump MM-1 is LOCKED OUT to support corrective maintenance on the pump (replace packing). During performance of the work the key will remain in the custody of the A. person performing the work.

B. Operator-in-Charge.

C. Senior Reactor Operator.

D. Reactor Supervisor or his designee.

QUESTION B.7 [1.0 point]

Following a change in fuel configuration, measurements must be made to determine the conditions of Technical Specification 3.1 are met prior to exceeding A. 1 kilowatt B. 10 kilowatts C. 100 kilowatts D. 1 Megawatt

Section B Normal, Emergency and Radiological Control Procedures Page 4 QUESTION B.8 [1.0 point]

During the performance of an Abnormal Operating Procedure, a temporary change to the procedure is required. Select the minimum complement of personnel required to approve this temporary change.

a. Two members of the reactor staff, at least one of whom holds a Senior Reactor Operator License.

b. The Duty Shift Supervisor and an appropriate group Supervisor.

c. A licensed Senior Reactor Operator and a member of the Reactor Safeguards Committee.

d. Two licensed Senior Reactor Operators and the Director of Reactor Operations.

QUESTION B.9 [2.0 points, 0.5 each]

Identify whether each of the following experiments has no special requirements (NSR), requires Double encapsulation (DBL), requires Pressure Test (PT) or is Not Authorized (NA).

a. Corrosive Materials

b. Metastable Materials

c. contains 3 milligrams of explosive material, and will not cause rearrangement or damage to the reactor.

d. the calculated surface temperature of a submerged experiment will be high enough to cause nucleate boiling within the coolant, but not cause bulk boiling.

QUESTION B.10 [1.0 points, 0.25 each]

Identify the source for the listed radioisotopes. Irradiation of air, water, structural material or fission product.

a. N16

b. Na24

c. Ar41

d. Xe188 QUESTION B.11 [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, Emergency and Radiological Control Procedures Page 5 QUESTION B.12 [1.0 point]

Consider two point sources, each having the SAME curie strength. Source As gammas have an energy of 0.5 MeV, while Source Bs gammas have an energy of 1.0 MeV. Using a Geiger-Müller detector the reading from source B will be (NOTE: Ignore detector efficiency.)

a. four times that of source A.

b. twice that of source A.

c. the same.

d. half that of source A.

QUESTION B.13 [1.0 point]

Which ONE of the following conditions is an Reportable Occurrence per the Technical Specification definition?

a. Five shim blades are operable. The inoperable blade is fully out.

b. Operation of the reactor with one shield coolant scram failed. It has been out of service for five hours.

Personnel working on it anticipate having it repaired within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

c. During operation at full power you find both Emergency cooling jumper hoses sabotaged.

d. Operation of the reactor with a height of water above the core 2" below the overflow pipe.

QUESTION B.14 [1.0 point]

In response to a "COOLING TOWER FANS OFF" alarm an attempt to restart the fans was unsuccessful.

With the reactor operating at 4 MW the immediate action required is to:

a. perform a minor scram.

b. perform a major scram.

c. shut the secondary blowdown valves and monitor primary coolant flow.

d. depress the "ALL RODS IN" pushbutton and lower power to 1 MW or less.

QUESTION B.15 [1.0 point]

Which ONE of the following is the definition of a CHANNEL TEST?

a. the combination of sensor, line, amplifier, and output devices which are connected for the purpose of measuring the value of a parameter.

b. an adjustment of the channel such that it output corresponds with acceptable accuracy to known values of the parameter which the channel measures.

c. a qualitative verification of acceptable performance by observation of channel behavior.

d. the introduction of a signal into the channel for verification that It Is operable.

Section B Normal, Emergency and Radiological Control Procedures Page 6 QUESTION B.16 [1.0 point]

Which one of the following Film Badge colors identifies the wearer as someone who is permitted to escort members of the general public through the reactor building?

a. Blue

b. Red

c. Yellow

d. Green QUESTION B.17 [1.0 point]

Administrative controls for rabbit irradiations state that all samples after irradiation must be handled by tongs.

Which one of the following is the reason there must be no direct contact with fingers on the irradiated container or samples?

a. high gamma radiation

b. high beta radiation

c. to prevent the spread of contamination

d. high probable surface temperature of polyethylene container.

QUESTION B.18 [1.0 point]

During a reactor startup you reach 0.5 inches above the Estimate Critical Position for the Shim Bank and the reactor is still subcritical. Which one of the following action is incorrect?

a. Immediately drive bank in to 1.0" or more below ECP.

b. Drive each blade out and check neutron level to ensure blade coupled.

c. Recheck sample reactivities.

d. If no discrepancy found notify the Superintendent.

Section B Normal, Emergency and Radiological Control Procedures Page 7 B.1 d REF: 220 = 1,048,756 . 1,000,000 B.2 c REF: MITR-II Tech. Spec. § 3.4, p. 3-14 B.3 a, 1; b, 2; c, 2; d, 3; e, 5; f, 5 REF: MITR-II Tech. Spec. § 6.1, Table within specification 1, p. 6-1.

B.4 b REF: Emergency Plan §§ 4.4.1.1 through 4.4.1.4.

B.5 d REF: A rem is a rem is a rem.

B.6 a REF: MITR-II PROCEDURE MANUAL Chapter 1 Administrative Procedures § 1.14.3 Equipment Tagout and Lockout Procedure.

B.7 a REF: MITR-II, PM 1.15 ¶3, pg. 1 of 5 B.8 a REF: PM 1.5 B.9 a, DOUBLE; b, PT; c, NR; d, NA REF: Technical Specifications § 6, Limitations on Experiments B.10 a, water; b, structural material; c, air; d, fission product REF:

B.11 d REF: Standard Health Physics Definition.

B.12 c REF: Standard NRC Health Physics Question. G-M detector is not sensitive to incident energy levels.

B.13 c REF: Technical Specification 3.9, 3.7, 3.6, 2.2.

B.14 d REF: PM 5.4.12 B.15 d REF: Technical Specifications § 1.13 B.16 c REF: PM 1.12, p. 1 B.17 b REF: PM 1.10, p. 10 B.18 b REF: MITR PM 2.3 Step (11) on page 2 of 7.

Section B Normal, Emergency and Radiological Control Procedures Page 8 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: Massachusetts Institute of Technology REACTOR TYPE: MITR-II DATE ADMINISTERED: 2004/07/12 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% is required to pass the examination.

Examinations will be picked up one (1) hour after the examination starts.

% of Category % of Candidates Category Value Total Score Value Category 20.00 100.0 B. Normal and Emergency Operating Procedures and Radiological Controls 20.00  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidates Signature

Section B Normal, Emergency and Radiological Control Procedures Page 9 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.

12. There is a time limit of one (1) hour 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.

Section B Normal, Emergency and Radiological Control Procedures Page 10 EQUATION SHEET



Q0 ' mc 0 p T ' m0 H ' UA T ( & )2 Pmax ' R( ' 1 x 10&4 seconds 2 (k)R eff ' 0.08 seconds &1 SCR '

S S R1(1&Keff ) ' CR2(1&Keff )

1 2

& 1&Keff CR1(& 1) ' CR2(& 2) eff 1&Keff 1 CR1 SUR ' 26.06 M ' 0 M ' '

& 1&Keff 1&Keff CR2 1

P ' P0 10SUR(t) t (1& )

P ' P0 e P ' P0 (1&Keff) R( R( -&

SDM ' ' '  %

Keff & - eff Keff & Keff 0.693 (Keff&1)

' 2 1 T1/2 ' '

keff xKeff Keff 1 2 6CiE(n) DR1d12 ' DR2d22 DR '

DR 'DR0 e& t R2 DR - Rem, Ci - curies, E - Mev, R - feet

( 2& ) 2 ( 1& ) 2 Peak2 Peak1 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 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 B Normal/Emerg. Procedures & Rad Con Page 11 B.1 a b c d ___ B.9c NSR PT DBL NA ___

B.2 a b c d ___ B.9d NSR PT DBL NA ___

% K/K B.3a 0.2 0.5 1.0 1.5 1.8 ___ B.10a air water F.P. S.M. ___

Note the choice of S.M. was inadvertently left off the copy given to the candidate. He wrote it in where appropriate.

B.3b 0.2 0.5 1.0 1.5 1.8 ___ B.10b air water F.P. S.M. ___

B.3c 0.2 0.5 1.0 1.5 1.8 ___ B.10c air water F.P. S.M. ___

B.3d 0.2 0.5 1.0 1.5 1.8 ___ B.10d air water F.P. S.M. ___

B.3e 0.2 0.5 1.0 1.5 1.8 ___ B.11 a b c d ___

B.3f 0.2 0.5 1.0 1.5 1.8 ___ B.12 a b c d ___

B.4 a b c d ___ B.13 a b c d ___

B.5 a b c d ___ B.14 a b c d ___

B.6 a b c d ___ B.15 a b c d ___

B.7 a b c d ___ B.16 a b c d ___

B.8 a b c d ___ B.17 a b c d ___

B.9a NSR PT DBL NA ___ B.18 a b c d ___

B.9b NSR PT DBL NA ___