IR 05000020/1986003
| ML20215M799 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 10/20/1986 |
| From: | Coe D, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20215M781 | List: |
| References | |
| 50-020-86-03OL, 50-20-86-3OL, NUDOCS 8611030304 | |
| Download: ML20215M799 (83) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
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- Examination Report N (0L)
- Facility Docket No.50-020 f
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i Facility License N R-37 l'
! Licensee: Massachusetts Institute of Technology
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, 138 Albany Street i i
! Cambridge, MA 02139
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l Facility Name: M.I.T. Research Reactor !
l i j Examination Dates: September 1-5, 1986 '
Chief Examiner: b// /o[N D. Cbt? Reactor ineer (Lead Examiner) ' da'te i Reviewed by: /#[/T [fff ,
! R. Keller, Chief, Projects Section 1C date I i Approved by: .
! 020 M l H.'KisEer; Chief, Projects Branch No. 1 / da1(e
i Summary: Operator licensing examinations were administered at MIT during the i j week of September 2, 1986. Three Reactor Operator candidates and one Senior '
Reactor Operator-candidate were examined. All candidates passed all portions of the examinations.
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B611030304 861027 i PDR ADOCK 05000020 V PDR l
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I j REPORT DETAILS TYPE OF EXAMS: Replacement
, EXAM RESULTS:
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i i l I ( l R0 l SR0 l l- l Pass / Fail l Pass / Fail l
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l Written Exam I 3/0 l 1/0 l i-
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1 I I i l l l l l 10ral Exam I 3/0 1 1/0 l l l l l l
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l 1 l l l0verall l 3/0 l 1/0 I I I I I I I -
1 I 1 CHIEF EXAMINER AT SITE: D. Coe 2. OTHER EXAMINERS: F. Crescenzo C. Shiraki L. Kolonauski J. D. Smith (PNL)
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3. Summary of generic strengths or deficiencies noted on oral exams:
It was noted that some candidates seemed reluctant to check or refer to normal evolution procedures (startup, shutdown). In one instance, a candidate did not place the differential galvanometer on the high scale (as required by procedure) prior to shutting down and had to be told to do this by the SRO on shif In another instance, a candidate did not announce " Reactor Startup" as required by procedure, prior to starting up. Although these individual instances are of minor significance, they probably would not have occurred had the candidates referred to the proper procedures prior to commencing the evolution . Personnel Present at Exit Interview:
NRC Personnel D. Coe, Lead Reactor Engineer (Examiner)
L. Kolonauski, Reactor Engineer (Examiner)
F. Crescenzo, Reactor Engineer (Examiner)
NRC Contractor Personnel
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J. Smith, PNL Facility Personnel Kwon Kwok - Training Coordinator Lincoln Clark - Director of Reactor Operations John Bernard - Superintendent, Research Reactor 5. Summary of NRC Comments made at exit interview: The facility was informed that the preliminary results of the operating exams were positiv The deficiency noted in Paragraph 1 above was discusse It was noted during startups that the instrumentation checklist, PM 3.1.1.2, had been changed to reflect a new procedure to check the main core tank level scram. This change was made with pen and ink and simply stated not to perform the original procedure and that the
"new" procedure should be used to perform the check. The examiners were concerned that this change was not specific enough to ensure proper documentation and traceability of performance of the check-list. This concern was discussed with the facilit It was noted during the facility walkthroughs that some radiation
" hot spots" and contaminated components were not locally labele Although the facility had complied with regulatory requirements
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se l regarding labeling of these areas, it was suggested that a more I I
localized labeling process be institute It was felt that this would assist the facility in accomplishing ALARA program goals by alerting personnel to high dose rates or contaminated area I Summary of facility comments and commitments made at exit interview: The facility acknowledged the comment regarding deficient use of procedures. The facility agreed that this was a potential problem and stated that corrective actions would be taken to instruct operators on the correct usage of procedure The facility stated that the main core tank level switch had been modified and a new procedure was now used. The new procedure was subsequently forwarded to Region I. In subsequent telephone conver-sations with facility personnel, the chief examiner was informed that the checklist would be changed to incorporate the new procedure and eliminate any pen and ink changes. They agreed to send the revised checklist upon ccmpletion of the revision. This will be followed by the responsible Lead Examine The facility felt it was within regulatory requirements and that additional radiological labeling was not necessary. This was justified by the temporary nature of the high dose rates and strict access requirements which control these area . All facility comments to the written examinations were resolved to the satisfaction of both the facility and the NRC. The following represent
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significant changes to the answer key made as a result of these comments.
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QUESTION NO.
i B.04 COMMENT: This answer is from p 3.3 of the MITR RS Unfortunately, our RSM is in error on this ite The N-16 is formed by converting 0-16 in the water molecules of the coolant. It's not in gaseous for The RSM should stress the items on page 3.4 which are (1) Provide means of monitoring fission product gas activity (2) Limit H 2production due to radiolytic decomposition (3) Remove Ar-41 I
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QUESTION N RESOLUTION: (1) Comment accepted. Answer changed to read:
"To prevent the accumulation of Ar**41 in the void above the primary water pool (+0.5). Provide means of monitoring fission product gas activity (+0.5)."
(2) No chang (3) No chang C.02(a) COMMENT: "This question is partially obsolete. On 2 April 85, NRC approved a license amendment changing (1) the limit to 1.8% AK/K, the maximum safe step reactivity addition, for controllers that do not incorporate the property of
' feasibility of control' and (2) removing the limit altogether for those that d (A period limit was added.) So, point of prompt criticality is no longer relevant. Purpose of the reviseo limit is tc avoid excessive power transients that neither the control or safety systems could halt before fuel damage occurre (Refer to T.S. #3.9.5 and 6.4.)"
RESOLUTION: Comment accepted. The following note was added to the answer key: " Note: Will accept answer that includes limiting period or power transient."
The following references were added to the answer key: MIT: Technical Specifications, 3. . MIT: Technical Specifications, C.03 COMMENT: Two answers are possible. The high flux tube (2 PHI) would heat up almost at once. We found this out the hard way. The intermediate flux
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tubes (IPH series) would take about 5 minute The low flux tube (2PH2) has no forced cooling.
. RESOLUTION: Comment accepted. Answer key changed to read:
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"(a. ) or (b. ) (+1.0)."
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QUESTION N C.07 COMMENT: This is really an SRO level question. As explained in our letter to NRC when test materials were submitted, senior shift super-visors do the refueling calculation Operators are required to know that the calculations must be done, but never do them. Operators are taught that as part of a refueling, they must evaluste hot channel factors, flow disparities, power distribution, anything that could cause boiling etc. The two limits referred to in the answer are the ' safety' and ' operating' limits respec-tively. Operators are NOT required to learn the formulas and therefore could not give the answer as written out because the answer contains one of the formulas. Also, another procedure (PM 1.15)
requires evaluation of reactivity change, shut-down margin etc. However, this procedure doesn't reference 1 Kw as did the questio RESOLUTION: Comment accepted. The following note was added to the answer key: " Note: Will accept answer that addresses power to flow ratio."
G.05 COMMENT: Answer shoulc be #c, surface contaminatio Both Beta and Gamma contamination are likely to be present. Answer #c covers both possibilities. (Note: We raised and NRC accepted this point previously.)
RESOLUTION: Comment accepted. Answer key changed to read:
(c.) (+1.0).
{ J.02 COMMENT: Answer is incorrect given current MITR
, checklists. It should say "... to transfer, l turn the gain to the 'off' position. Do NOT adjust the discriminator setting."
RESOLUTION: Comment accepted.
l J.0 COMMENT: Answer should read "... is filtered l and monitored." Monitoring is the crucial l function because that will detect any radiat*on
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RESOLUTION: Comment accepted.
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Attachment: Written Examination (s) and Answer Key (s) (SRO/RO)
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U. S. NUCLEAR REGULATORY COMMISSION t
REACTOR OPERATOR LICENSE EXAMINATION FACILITY: MASS. INSTITUTE OF TEC REACTOR TYPE: TEST DATE ADMINISTERED: 86/09/02 EXAMINER: SMITH, CANDIDATE: ANSWER KEY t
INSTRUCTIONS TO CANDIDATE:
I Use separate paper for the answers. Write answers on one side onl Staple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 15.00 15.00 A. PRINCIPLES OF REACTOR OPERATION 14.00 14.00 B. FEATURES OF FACILITY DESIGN 14.00 14.00 C. GENERAL OPERATING
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CHARACTERISTICS 15.00 15.00 D. INSTRUMENTS AND CONTROLS
_143.00 14.00 E. SAFETY AND EMERGENCY SYSTEMS 14.00 14.00 F. STANDARD AND EMERGENCY OPERATING PROCEDURES 14.00 14.00 RADIATION CONTROL AND SAFETY l
_100.00 Totals
, Final Grade '
l All work done on this examination is my ow I have neither given nor received ai t Candidate's Signature
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS
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During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . 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 cheatin . Use black ink or dark pencil only to facilitate legible reproduction . Print your name in the blank provided on the cover sheet of the examination.
, Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answers.
. Print your name in the upper right-hand corner of the first page of each j section of the answer sheet.
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- Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer shee . Number each answer as to category and number, for example,1.4, 6.3.
]i 10. Skip at least three lines between each answe ; 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literature.
i 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer require , 14. Shcw all calculations, methods, or assumptions used to obtain an answer
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sto mathematical problems whether indicated in the question or no . Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
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l 16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
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17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or heen given assistance in completing the examination. This must be done after the examination has been completed.
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~ 18. When you complete your examination,'hou shall: Assemble your examination as follows:
(1) Exam questions on to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are part of the answe Turn in your copy of the examination and all pages used to answer the examination question Turn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the examination area, as defined by the. examine If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoke .
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, PRINCIPLES OF REACTOR OPERATION PAGE 2
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QUESTION A.01 (.50)
ANSWER TRUE or FALS Xenon peaks earlier in MIT-II than most light water moderated reactors after shutdown due to a harder neutron spectru (0.5)
QUESTION A.02 (1.50)
If heavy water leaks into the light water system, WHAT type of reactivity effect (positive or negative) will it have if: The leakage of pure, uncontaminated heavy water is into either the light water reflector above the top of the core, or the light water reflector below the top of the core that is formed by the annular space between the core and the sides and bottom of the core tank? (0.5) The leakage of heavy water is into the core proper? (0.5) The in-leaking D(2)0 progressively replaced the entire light water system? (0.5)
QUESTION A.03 (2.00)
If the reactor is on a stable 25-second period, HOW long will it take to change the power level by 2 decades? SHOW your calculatio (2.0)
QUESTION A.04 (1.00)
WHY do delayed neutrons affect reactor control? (1.0)
QUESTION A.05 (3.00)
EXPLAIN the effect of the temperature coefficient on reactivity if the thermal power of the MIT II core increases. INCLUDE both light water moderator and the heavy water reflector effect (3.0)
(*****CATEGORYA CONTINUEDONNEXTPAGE*****)
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- PRINCIPLES OF REACTOR OPERATION PAGE 3
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QUESTION A.06 (3.00)
HOW much reactivity has been added to a subcritical reactor if the count rate has increased from 100 cps to 150 cps and if the initial value of Keff was 0.957 SHOW all calculations and assumption (3.0)
i QUESTION A.07 (2.00)
When calculating an estimated critical position, the operator uses the previous week's position and corrects for five (5) different delta K changes. LIST four (4) of those delta K change (2.0)
QUESTION A.08 (2.00)
INDICATE whether each of the following statements are TRUE or FALS (2.0) An increasing concentration in the reactor core of Xe-135 reduces the thermal utilization factor, f, and hence the multiplication factor, Keff, of the reactor cor Xe-135 is produced both directly as a fission product and as the result of a decay chain from other fission products.
. A good approximation for determining the production in a reactor core of Xe-135 is to assume that the Xe-135 is produced from the decay of Cs-13 The removal rate of Xe-135 is due to the neutron absorption rate in Xe-135 atoms and due to the radioactive decay of Xe-135 atom .
(***** END OF CATEGORY A *****)
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. FEATURES OF FACILITY DESIGN PAGE 4
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QUESTION B.01 (1.00)
WHAT is the purpose of the secondary water treatment system? (1.0)
QUESTION B.02 (1.00)
EXPLAIN how the anti-syphon valves wor (1.0)
QUESTION B.03 (2.00)
LIST three (3) ways to reduce the degree of cooling tower efficiency on cold day (2.0)
QUESTION B.04 (1.00)
WHAT is the purpose of the OFF GAS SYSTEM 7 (1.0)
QUESTION B.05 (1.50)
LIST three (3) ways that the beam ports are seale (1.50)
QUESTION B.06 (1.00)
ASSUME a loss of external electrical power feeders occurs. When normal power is later restored, WHAT will happen to all the transfer switches and the motor generator set? (1.0)
QUESTION B.07 (1.25)
WHAT design safety feature ensures that fuel loaded into the core will normally have access to only one core position at a time? (1.25)
(*****CATEGORYB CONTINUED ON NEXT PAGE *****) 1 I
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- FEATURES OF FACILITY DESIGN PAGE 5
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QUESTION B.08 (1.25)
If the pressure relief system's charcoal filters become submerge WHAT problem will exist during filter housing anid exhaust dryout? (1.25)
QUESTION B.09 (2.00)
DESCRIBE the four (4) modes of operation (departure and destination points) for the 1-inch pneumatic tube syste (2.0)
QUESTION B.10 (2.00)
DESCRIBE two (2) ways to verify that the secondary system is properly lined up to cooling tower basins? (2.0)
(***** END OF CATEGORY B *****)
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' GENERAL OPERATING CHARACTERISTICS PAGE 6
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QUESTION C.01 (.50)
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ANSWER TRUE or FALS It is possible to operate at less than 100 kW with no forced circulation of primary coolant, but requires bypassing a number of safety function (0.5)
QUESTION C.02 (3.00)
GIVE the basis for the following technical specifications: The reactivity worth of the regulating rod connected to the automatic control system is less than 0.7% delta k/ (1.0) The maximum controlled reactivity addition rate is no more than
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5x10**-4 delta k/k/se (1.0) The reactivity worth of the D(2)0 reflector dump is greater than the reactivity worth of the most reactive shim blad (1.0)
QUESTION C.03 (1.00)
Approximately HOW long after a failure of the oneumatic blower (at full power), will the temperature in the pneumatic tubes reach 100 d grees C7 (SELECT best answer.) (1.0)
. 10 seconds
. 5 minutes
. 30 minutes
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DESCRIBE how to calculate the total thermal power output of the reacto (3.0)
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' GENERAL OPERATING CHARACTERISTICS PAGE 7
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QUESTION C.05 (1.00)
WHY is " blowdown" of the water in the Forced Draft Cooling Towers required?
(1.0)
QUESTION C.06 (1.00)
WHY does it take 24 hcurs for the reactor to be in thermal equilibrium, such that a heat balance can be conducted? (1.0)
QUESTION C.07 (2.00)
After each refueling or change in core loading, the reactor shall not be operated above a power level of 1.0 kW unless an evaluation is made to ensure that two Technical Specifications are satisfie WHAT are the two (2) Technical Specifications? (2.0)
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QUESTION C.08 (2.50) EXPLAIN how the reactivity effect of dumping the radial reflector varies with the position of the shim blades fully in or fully ou (1.5) WHY is the radial heavy water reflector pumped up with the shim bank in the fully inserted position? (1.0)
(***** END OF CATEGORY C *****)
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' INSTRUMENTS AND CONTROLS PAGE 8
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QUESTION D.01 (2.00)
The automatic control mode cannot be initiated until four (4)
requirements imposed by the " automatic-control-permit" circuit are met. LIST the four (4) requirement (2.0)
QUESTION D.02 (3.00)
LIST three (3) of the five (5) fuactional requirements that the shim blade control circuits are designed to meet, as referenced in the reactor control system section of the reactor sys,tems manua (3.0)
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QUESTION D.03 (1.50)
If a 3 GV hole that contains a nuclear instrument detector is flooded, WHAT will happen to the detector output? EXPLAIN wh (1.5)
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QUESTION b.04 (1.00)
"0W is flow measured in the reflector secondary coolant and shield
..)lant? (1.0)
QUESTION D.05 (1.50)
There are two (2) primary coolant conductivity cells: MC-1 and WHICH one is normally selected? EXPLAIN why it is selecte (1.5)
QUESTION D.06 (1.00)
In WHAT operating mode is the automatic rundown circuit not available? (1.0)
(***** CATEGORY D CONTINUEDONNEXTPAGE*****)
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' INSTRUMENTS AND CONTROLS
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QUESTION D.07 (3.00)
WHAT will result if any of the plenum particulate or gas monitors exceed their trip level? (3.0)
QUESTION D.08 (2.00)
EXPLAIN WHY the reading on the linear N-16 monitor would change as reactor power increase (2.0)
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(*****ENDOFCATEGORYD *****)
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' SAFETY AND EMERGENCY SYSTEMS PAGE 10
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QUESTION E.01 (2.00)
EXPLAIN the reason for shutting the reactor down if the compressed air system is lost? (2.0)
QUESTION E.02 (2.00)
When the reactor is operating above 100 kW, within WHAT time limit and flow rate must the emergency cooling system be capable of? (2.0)
QUESTION E.03 (3.00)
LIST six (6) of the eight (8) minimum pieces of equipment (listed in the Technical Specification) that will be supplied by emergency powe (3.0)
QUESTION E.04 (2.00)
If the level in the core tank cannot be maintained at the level of the reactor inlet penetration and the lost water is being collected in the equipment room sump when a source of makeup other than city water is immediately available, WHAT is the appropriate lineup to provide emergency core cooling? Include any valves or pump (2.0)
QUESTION E.05 (2.50)
DEFINE a major pnd minor SCRA (2.5)
QUESTION E.0 (2.50)
LIST five (5) of the eight (8) safety and emergency related alarm conditions that will transmit a signal to the Campus Patrol Alarm Syste (2.5)
(***** END OF CATEGORY E *****)
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- STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 11
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QUESTION F.01 (2.00)
GIVE two (2) conditions when an operating period is defined as terminatin (2.0)
QUESTION F.02 (2.00)
WHAT actuates the cooling tower sprinkler on alarm and WHAT does the alarm mean? (2.0)
J QUESTION F.03 (2.00)
DESCRIBE what the off-going console operator should do during a shift turnove (2.0)
f QUESTION F.04 (2.00)
WHAT is the most likely potential cause of an explosion within the MITR-II facility? (2.0)
QUESTION F.05 (2.00)
WHY is it important that the main secondary pump not be run if water in the cooling tower basins is being lost faster than it can be made up? (2.0)
QUESTION F.06 (2.00)
If the high pressure reactor inlet alarm annunciates, WHAT are four (4) of the flye (5) parameters that would require the reactor to be scrammed (minor)? (2.0)
(*****CATEGORYF CONTINUEDONNEXTPAGE*****)
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- . STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 12
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QUESTION F.07 (2.00)
DESCRIBE HOW personnel in the restricted area are accounted fo (2.0)
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' RADIATION CONTROL AND SAFETY PAGE 13
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QUESTION G.01 (2.00)
A mixed gamma and beta source in liquid form spills on the floo Readings at 10 feet indicate 1.0 mrem /hr on a beta-gamma survey meter. If betas are not detected further than 6 feet from the spill and if the combined beta-gamma dose rate at I foot is 120 mrem /hr, WHAT is the beta to gamma ratio at 1 foot? SHOW your calculatio (2.0)
QUESTION G.02 (1.00)
WHAT is the first action that the Operator-In-Charge should take if the rabbit radiation monitor trips? (1.0)
QUESTION ' 0 (2.00)
WHAT two (2) types of dosimetry are all personnel. working at the MIT reactor required to wear? (2.0)
QUESTION G.04 (2.00)
A 23-year-old individual has accumulated a lifetime occupational dose of 24 rem of whole body exposure documented in accordance with 10CFR20 and has received no exposure during the present calendar quarter. HOW many days may he work in a 3 mrem /hr area if he works an 8-hour day Monday through Friday? SHOW your wor (2.0)
QUESTION G.05 (1.00)
'There must be no direct contact with fingers on the irradiated container or samples because of: (SELECTbestanswer.) (1.0) high probable gamma radiation high probable beta radiation high probable surface contamination high probable alpha contamination (*****CATEGORYG CONTINUED ON NEXT PAGE *****)
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~ RADIATION CONTROL AND SAFETY
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QUESTION G.06 (1.00) t WHY is the spill of heavy water a radiological concern? (1.0)
QUESTION G.07 (.50)
ANSWER TRUE or FALS The purpose of the shield coolant system is to remove the heat deposited in the lead thermal shields by neutron radiatio (0.5)
QUESTION G.08 (1.00)
WHY is the Thermal Column Hohlraum maintained under a carbon dioxide purge?
(1.0)
QUESTION G.09 (1.50)
Does the number of disintegrations per minute (dpm) from a radioactive source equal the counts per minute (cpm) obtained from a survey instrument? BRIEFLY EXPLAI (1.5)
QUESTION G.10 (1.00)
WHAT is the reason for the maximum irradiation time limit on the rabbit (60-megawatt hours at a neutron flux of 10**13)? (1.0)
QUESTION G.11 (1.00)
If two (2) centimeters of lead placed at a certain location in a beam of gamma rays would reduce the gamma radiation level from 100 mR/hr to 50 mR/hr, WHAT thickness of lead placed in this beam would reduce the gamma radiation level from mR/hr to 50 mR/hr? (0.5)
50 mR/hr to 25 mR/hr? (0.5)
- END OF CATEGORY G *****)
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- PRINCIPLES OF REACTOR OPERATION PAGE 15
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ANSWERS -- MASS. INSTITUTE OF TECH. -86/09/02-SMITH, .
ANSWER A.01 (.50)
Tru [+0.5]
REFERENCE MIT: RSM 1 ANSWER A.02 (1.50)
- positive ;+0.5[ negative + negat;'!e ,_+0.5.,
REFERENCE MIT: RSM 10.1 AN5WER A.03 (2.00)
From equation sheet:
P = P e t/T o
t/25 sec P/P = 100 = e [+1.0]
o in 100 = t/25 see t = (25 sec)(in 100)
= 115.13 seconds = 1.92 minutes [+1.0]
[+2.0]
REFERENCE MIT: GlasstoneandSesonske(MITTrainingProgramReference),
PM 1.16.2, p. . . . - . ._ - . - . -, . .-. __ _-- - . .- . . - . _. .
.
' PRINCIPLES OF REACTOR OPERATION PAGE 16
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ANSWERS -- MASS. INSTITUTE OF TECH." - 86/09/02-SMITH, ANSWER A.04 (1.00)
The delayed neutrons increase generation time which increases the period and thus the reactor can be controlled. [+1.0]
REFERENCE Generic: Lamarsh, " Introduction to Nuclear Engineering,"
Ch. 7, p. 24 ANSWER A.05 (3.00)
Increasing the temperature of the light water will insert negative reactivity by causing the neutrons to take longer to thermalize so there are fewer fissions. [+1.5] Heating of the heavy water reflector will add negative reactivity by allowing neutron leakage to increas [+1.5]
REFERENCE MIT: RSM, p. 1 ANSWER A.06 (3.00)
crl/cr2 = (1-Keff2)/(1-Keff1) /150 = (1-Keff2)/(1-0.95) [+[+0.5]]
1-Keff2 = 10/15 x 0.05 Keff2 = 0.967 [+0.1]
.
Change in reactiv ty = Keff2-1)/Keff2 - (Keff1-1)/Keffl
=
Keff2 - Keff1)/(Keff1 x Keff2 [+ =
0.967 - 0.95)/(0.95 x 0.967) )[+0.5] ]
= 1.85% delta k/k [+0.1]
.
REFERENCE MIT: Reactor Physics Notes (Reactor Subcritical Multiplication).
. _ . _ - - - - _ . _ . _ _ - . _ . _ _ _ _ _ - . . - _ _ _ _ ___ . - - - - - - _ _ - - . _
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. l PRINCIPLES OF REACTOR OPERATION PAGE 17
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ANSWERS -- MASS. INSTITUTE OF TECH.<--86/09/02-SMITH, .
.
ANSWER A.07 (2.00) Delta K due to temperature change Delta K dse to sample loading Delta K due to xenon Delt: K due to fuel loading Delta K due to burnup Any four (4) [+0.5] each, +2.0 maximum REFERENCE MIT: PM 3.1.1.2, p. 1 ANSWER A.08 (2.00)
' True True False
] True
!
[+0.5] each REFERENCE Generic: Academic Program for Nuclear Power Plant Personnel, Volume II, General Physics Operation, 4.38 (Xenon and Samarium Poisoning),p.14 . Technical Education Research Center-Southwest, " Nuclear Technology," pp. 12-7-12 .
h t
. , _ . . . _ _ _ _ _ _ _ . _ _ _ _ . _ . . _ . _ . _ _ . . _ , _ _ _ _ _ _ _ _ _ _ . . , _ . , . . . . _ _ _ _ . _ _ . _ _ . , . _ . . _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . _ _ _ . . . _ _ _ ,
.___ -
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'. FEATURES OF FACILITY DESIGN PAGE 18 ANSWERS -- MASS. INSTITUTE OF TECH. -86/09/02-SMITH, ANSWER B.01 (1.00)
To inhibit corrosion in the secondary system piping to keep heat transfer surfaces clean and to control the growth of algae in the basins. [+1.0]
REFERENCE
' MIT: RMS 3.4.4, p. RMS 3.1 ANSWER B.02 (1.00)
Ball float valve is installed at the top of the core shroud. Inlet flow forces ball up closing outlet at top; w/o flow gravity forces ball down to break sypho [+1.0]
REFERENCE MIT: RSM 1.7.
! ANSWER B.03 (2.00) the yard booster pumps can be bypassed partially or completely, as can the towers themselves.
1 one of the cooling tower fans can be operated at half-speed the pitch of the fan blades can be changed
, the air admitted to the towers can be restricted by rearranging the external boards and flap Any three (3) [+0.66] each, +2.0 maximum REFERENCE MIT: RSM.3.1 ,
. - , _ - -
, - - ._ _ - . , ..-.__r.- , . . _ , _ _ _ _ . _ _ _ . . , _._,._,,s , . _ . _ .-.~.___._-..,,..,-.,_.7,-.
.
- FEATURES OF FACILITY DESIGN PAGE 19
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ANSWERS -- MASS. INSTITUTE OF TECH. -86/09/02-SMITH, J.
.
ANSWER B.04 (1.00)
To prevent the accumulation of N10 and Ar**41 in the void above M "'~'" "-"a the g.. primary
,~,cr. ,,, water pe .<e- pool. cj+:J.4]Fd*"'~^'fj'-
xc,,oa (* *~ 1 REFERENCE MIT: RMS 3.2.5, pp. RMS 3.3, ANSWER B.05 (1.50) a plug is placed in port [+0.5] gas seals [+0.5] gasketed cover boltec over beam port's opening [+0. 5]
REFERENCE MIT: RSM ANSWER B.06 (1.00) transfer switches return to normal [+0. 5] relay at the motor-generator set is energized, thereby stopping the unit [+0.5]
REFERENCE MIT: RSM 8.3 ANSWER B.07 (1.25)
Hold-down grid latch must be released and the grid rotated to permit core access. Grid design prevents multiple position access. [+1.25]
REFERENCE MIT: PM 2.7, p. _
- . - - . - - .
_ . . . . _ _ . . _ _ _ . ._ _ __ __- . - . _ _ - _ _ . - _ _ _. - - _ - - . - - _ _ _ - - _ _
.
, FEATURES OF FACILITY DESIGN PAGE 20 ANSWERS -- MASS. INSTITUTE OF TECH. --86/09/02-SMITH, ANSWER B.08 (1.25)
The charcoal generates heat while drying out and may cause spontaneous combustion. [+1.25]
REFERENCE MIT: PM 5.2.14, p. ANSWER B.09 (2.00) insertion and removal at the hot cell or primary chem room in '
the reactor basement insertion at the hot cell and transfer of the irradiated sample to the NW-13 hot lab via the connecting pneumatic tube insertion from the NW-13 hot lab, into the reactor, and transfer of the irradiated sample back to the NW-13 hot lab transfer of a rabbit from the basement hot cell to the NW-13 hot lab
[+0.5] each REFERENCE MIT: PM 1.16, p. ANSWER B.10 (2.00) checking HV-14 of HV-14A open [+1.0] checking HM-1A running with flow through HF-3 at 60% of scale
[+1.0] Ae:s - :s mt ,; .. . . ;;ca r,. , . .
thri REFERENCE MIT: PM 3.1.1.1, p. 2.
.
. . - . - - -- , ,e- , - , , , - - - ,
.
~ GENERAL OPERATING CHARACTERISTICS PAGE. 21
.
ANSWERS -- MASS. INSTITUTE OF TECH.'--86/09/02-SMITH, ANSWER C.01 (.50)
True [+0.5]
REFERENCE MIT: PM ANSWER C.02 (3.00) The total worth of the rod is to be limited such that the complete withdrawal of the rod will not make the reactor prompt critica [+1.0] ffc iffff,f"fyg~jff ;,c ' "a ' L ir r uu d
_ ^
P'N 'R This value is conservatively within the range of reactivity insertion rates normally accepted for reactor operation. Control systems in this range give ample margin for proper human response during approach to critical and power operation [+1.0] The additional independent capability for reactivity control provided by the D(2)0 reflector dump gives added assurance that the reactor can be made subcritical under an adverse condition of fuel loading or control blade malfunction. [+1.0]
REFERENCE MIT: Technical Specifications, 3.9, pp. 3-32 to 3-3 y -
,: . :. ,
2 , 6. a .
ANSWER C.03 (1.00)
(Als6(b.) [+1.0]
REFERENCE MIT: PM 5. . . - . . . - .-. . . - - - . .
- - . - - . _ -
.
.
, GENERAL OPERATING CHARACTERISTICS PAGE 22 ANSWERS -- MASS. INSTITUTE OF TECH.'--86/09/02-SMITH, ANSWER C.04 (3.00)
Primary Power = (2.62 x 10**-4)(Primary Flow).(Primary delta T)
Reflector Power = (2.91 x 10**-4)(D(2)0 Flow)(D(2)0 delta T)
Shield Power = (2.62 x 10**-4)(Shield Flow)(Shield delta T)
Total Power = Primary + Reflector + Shield Power Numbers are not important, just the parameters and three constituents of total power. [+3.0]
REFERENCE MIT: PM 2.4, p. ANSWER C.05 (1.00)
Forced draft cooling towers concentrate the solids in the makeup water and collect atmospheric dust. Hence, a feed-and-bleed purge is maintained while they are in operation in order to keep the level of dissolved solids within a factor of three to five times that of the makeup water. A small portion of the water is diverted through a flow accumulation meter directly to the sewer. This flow is called
" blowdown." [+1.0]
REFERENCE MIT: RSM 3.12.
ANSWER C.06 (1.00)
Graphite reflector has a large heat capacity and is slow to attain an equilibrium temperature distribution. [+1.0]
REFERENCE - MIT: RSM 6.4.
!
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.
, GENERAL OPERATING CHARACTERISTIC 3 PAGE 23
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ANSWERS -- MASS. INSTITUTE OF TECH.'--86/09/02-SMITH, ANSWER C.07 (2.00) The ratto F(HC)F(p)/d(f)F(f) is predicted to be less than [+1.0] A cci/9 AM"U war 4 "=* * c M " I' 'N '" ' ~ O ' ' "
- The core is predicted to operate below incipient boiling at every point in the cor [+1.0]
REFERENCE MIT: Technical Specifications, 3.1, p. 3- ANSWER C.08 (2.50) In as much as the shim blades also operate in the region between the core and the radial heavy water reflector, the reactivity worth of dumping this radial reflector is dependent on the position of the shim blade bank. This effect can be considered as being due to the shadowing influence that the blade bank exerts on the reflector. These results show that the reactivity worth of dumping the radial heavy water reflector when the shim bank is fully inserted is about two-thirds that of the corresponding value when the bank is at the top of the active Cor [+0.5] for reason, [+1.0] for knowing more reactivity with rods at to This ensures that the reactivity insertion for this process will not occur when the reactor is or could go critical. [+1.0]
REFERENCE MIT: RSM 10.6.
t
_ . _ _ _ _ . - . _ _ _ _ _ . . _ _ _ - , _ _ . _ . _ . _ _ _ _ _ . _ . _ _ _ , _ _ _ . _ _ , . . - - . _ . _ _ _ _ , _ _ . , . . _ _
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~ INSTRUMENTS AND CONTROLS PAGE 24
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ANSWERS -- MASS. INSTITUTE OF TECH.'--86/09/02-SMITH, .
ANSWER D.01 (2.00) All shim blades must be above subcritical interlock positio . The deviation between power-set and actual power must not exceed 1.5%. The regulating rod control switch must be in the neutral positio . The regulating rod must be withdrawn beyond its near-in position (1.6 inches).
[+0.5] each REFERENCE MIT: RSM 4, p. RSM- ANSWER D.02 (3.00) Only one shim blade can be withdrawn at a tim . The shim blade absorbers may be dropped from the racks at any pos1 tio .vew f, p , x ,vn..,o m t ri. : 7 ' % . . Each shim blade may be run in at its normal speed without interrupting its magnet curren /, A*t d arz > " c ad ev ' ' **'* # " All six shim blades may be run in simultaneously at their normal speed without interrupting their magnet current . The fine control regulating rod operates independently of the shim blade Any three (3) [+1.0] each, +3.0 maximum REFERENCE MIT: RSM 4, p. RSM 4.3.
i
_ _ _ . _ _ _ _ _ .- ___- _
..-__ -._ .. - _ _ _ _
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' INSTRUMENTS AND CONTROLS PAGE 25
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ANSWERS -- MASS. INSTITUTE OF TECH. --86/09/02-SMITH, .
ANSWER D.03 (1.50)
Output will decrease [+0.5] due to the increased attenuation of the neutrons [+1.0]. ,
REFERENCE MIT: PM 5.4.1 ANSWER D.04 (1.00)
Orifice plates and d/p cell \
AcCGP7 An: v, y , r, p. [+1.0}tt
,fge FL.Ow c ( Wpphis :}
REFERENCE MIT: RSM ANSWER D.05 (1.50)
Conductivity cell MC-1, which is positioned in a filter line at the inlet to the ion exchange column, is normally selected [+0.5]. The other cell, MC-2, is positioned in the outlet filter return lin The inlet measures highest and most conservative conductivity, unless the ion exchanger is leaching out. [+1.0]
REFERENCE MIT: RSM ANSWER D.06 (1.00)
only during operation in the manual mode. [+1.0]
REFERENCE MIT: RSM 4, p. RSM-4.5.
.
. . - __ _ _ _ _ _ . - . . , , - - . . . _ . ,
.
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. INSTRUMENTS AND CONTROLS PAGE 26
,
ANSWERS -- NASS. INSTITUTE OF TECH. --86/09/02-SMITH, J.
,
ANSWER D.07 (3.00)
Initiate an alarm on the annunciator panel [+1.0], secure the ventilation system l:+1.0], and close the intake and exhaust dampers automatically [+1.0:1 REFERENCE MIT: RSM 7, p. RSM- ANSWER D.08 (2.00)
N-16 production is directly proportional to the fast neutron flux, therefore if the primary flow was constant, the radiation reading on this monitor would directly indicate reactor power. [+2.0]
REFERENCE MIT: RSM 7.3.
f i
f i
,
-
,
_ . . _ . _ , _ _ _ _ . _ _ _ _ _ . _ - - , _ - _ . . _ _ _ _ _ - . . . , _ . , _ _ _ , . -
_ _ _ . _ . ,_ _ . . - - , , _ - _ _ _ _ _ _ _ _
.
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' SAFETY AND EMERGENCY SYSTEMS PAGE 27 ANSWERS -- NASS. INSTITUTE OF TECH.'--86/09/02-SMITH, ANSWER E.01 (2.00)
If neither compressor is capable of maintaining system pressure, the dump valve will open, the pneumatic instrumentation will be lost, and all airlock gaskets will deflate once the air within them leaks out past system check valves. Containment integrity will eventually be lost. [+2.0]
REFERENCE MIT: PM 5. ANSWER E.02 (2.00)
It must be capable of providing the fuel elements with a minimum total emergency cooling flow rate of 10. gal / min [+1.0] within 5 minutes after a low level main tank scram [+1.0].
REFERENCE
- MIT: Technical Specifications 3.6.1, p. 3-1 ANSWER E.03 (3.00) one neutron flux level channel main tank coolant level indicator reactor primary coolant outlet temperature radiation monitors required by Specification . containment intercom system primary coolant auxiliary pump DC lights self-contained battery operated lights Any six (6) [+0.5] each, +3.0 maximum REFERENCE MIT: Technical Specifications 3.7, p. 3-2 .
- - . , -w-, , - . , - - - , - - . - ,,-en-,- - . , - . - - . . ,- - - -.-- -.-. - - - - , . - , - - - , . , , , - -
- , . , . , . -
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' SAFETY AND EMERGENCY SYSTEMS PAGE 28 ANSWERS -- MASS. INSTITUTE OF TECH. --86/09/02-SMITH, .
ANSWER E.04 (2.00)
MM-2 will be aligned to take a suction on either the equipment room sump through the portable hose and strainer, or the other source of makeup [+1.0], and discharged directly to the 8-inch reactor inlet line vthrough the spray nozzles at the top of the core tank [+1.0].
ok REFERENCE MIT: RSM 3. ANSWER E.05 (2.50)
All automatic reactor scrams cause the current to the magnets holding the shim blades to be interrupted. This causes the absorber sections to drop into the core and shut the reactor down. This action is defined as a minor scram. [+1.25] A major scram is initiated by depressing a major scra.n pushbutto This action secures the ventilation system, seals the containment shell, dumps the top part of the D(2)0 reflector, and interrupts the withdraw permit circuit thereby dropping the shim blades. [+1.25]
REFERENCE MIT: RSM ANSWER E.06 (2.50) high temperature reactor outlet, MTS-1 low level core tank i . low pressure HM-1A high level radiation monitor smoke detector system waste tanks Iow pressure helium supply leak primary and D(2)0 system
,
Any five (5) ['+0.5] each, +2.5 maximum REFERENCE MIT: RSM 9.15.
,
. . _ _ _ _ _ _ _ _ . . _ . , _ _ _ , _ _ , _ _ _ _ _ _ _ . _ . - _ _ _ _ _ _ _ _ _ _ _ __,,__,____.m____..___,.,m____ _ _ _ _ . . . , , . , , _ _ , , , _ _ _ , _
.
.
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' STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 29 ANSWERS -- MASS. INSTITUTE OF TECH.<--86/09/02-SMITH, ANSWER F.01 (2.00) The reactor will be continuously shutdown for more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. [+1.0] The mode of operation (full-power,' half-power or 100 kW) is to be change [+1.0)
REFERENCE MIT: PM 2.2.1.1-8, p. 4.
,
ANSWER F.02 (2.00)
This alarm is actuated in response to the flow of water in the main between check valve CTV-8 and the fusible heads that are in the cooling tower sprinkler lines. [+1.0] This alarm means either that the cooling tower is on fire or that one of the fusible heads has cracked. [+1.0]
REFERENCE MIT: PM 5. ANSWER F.03 (2.00)
Check the log entries of his shift for completeness and accuracy
[+0.5]; wait until his replacement has read the log [+0.5], checked the bypass log sheet [+0.5], and until any questions he might have are answered [+0.5].
REFERENCE MIT: PM 1.7.1, p. PM 1.7.
,
ANSWER F.04 (2.00)
Buildup of D(2) [+1.0] due to a D(2)0 reflector recombiner malfunction
[+1.0].
REFERENCE MIT: PM 5.8.1, p. PM 5. _ - - _ _ _
. _ . - - - . - - _ _ - - _
- _ - . .. -__ _--_ _- - - -
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" STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 30
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ANSWERS -- MASS. INSTITUTE OF TECH. --86/09/02-SMITH, J.
.
ANSWER F.05 (2.00)
Cavitation will damage the pump [+1.0] and such operation will suck air and mud into the heat exchanger [+1.0].
REFERENCE MIT: PM 5.4.5, p. PM 5. ANSWER F.06 (2.00) Any change in reactivit . Any decrease in primary coolant flo . Any increase in core purge or primary conductivity reading . Any increase in core outlet temperature or core delta . Any increase in heat exchanger outlet pressure as indicated by MPS-3, 3A or 3 Any four (4) [+0.5] each, +2.0 maximum REFERENCE MIT: PM 5.2.11, p. PH 5.2.1 ANSWER F.07 (2.00)
An accountability board is located immediately inside the single normal entrance to the restricted area. This board consists of a name plate, indicator light and toggle switch for each person issued a film badge and authorized to enter the restricted are [+1.0] Each person is required, on entry, to turn on the indicator light opposite his or her name and to turn it off on exiting the area. [+1.0]
REFERENCE MIT: PM 4. .
~
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'G RADIATION CONTROL AND SAFETY PAGE 31
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ANSWERS -- MASS. INSTITUTE OF TECH. --86/09/02-SMITH, ANSWER G.01 (2.00)
d x (r)^2 = D x (R)^2 1 mr/hr x (10)^2 = D x (1)^2 D = 100 mr/hr [+1.0]
Beta dose = 120 mr/hr - 100 mr/hr
= 20 mr/hr [+0. 5]
Beta to gamma ratto = 20/100 = 1/5 [e0.5]
REFERENCE Generic: J. R. Lamarsh, " Introduction to Nuclear Engineering,"
Ch. 9, p. 409 and 41 ANSWER G.02 (1.00 (, ,, ' r 3 0 c 7p ,r.fc h J; O ,.0 e c) t n r: H
~
Jnfor= +ha -ehif+ supervis@feminuactin2+Mr ud r;;;hth h
&W REFERENCE MIT: PM 1.1 .
ANSWER G.03 (2.00)
' beta-gamma monitoring badge [+1.0] pocket dosimeter (gamma) [+1.0]
REFERENCE MIT: PM 2.5, p. ANSWER G.0 (2.00)
5(N-18)=5(23-18)=25 25 - 24 = 1.0 rem = max. dose [+1.0]
max. dose = dose rate x time 1.00 rem = 0.003 rem /hr x 8 hr/ day x no. of days no. of days - 41.6 days [+1.0]
,
. ~ ___ _ _ _ _ _ _ _ - - - _ _ _ . _ . _ _ _ _ . ., _ _ .-_ _ _ . ._ _ _ - _ . _ _ - _ _-
.
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, 'G . RADIATION CONTROL AND SAFETY PAGE 32
,
ANSWERS -- MASS. INSTITUTE OF TECH.'--86/09/02-SMITH, REFERENCE CFR 20.10 ,
AN R G.05 (1.00)
M [+1.0]
REFERENCE MIT: PM 1.10, p. 1 ANSWER G.06 (1.00)
tritium content [+1.0]
REFERENCE MIT: PM 4.5, p. ANSWER G.07 (.50)
False (gamma) [+0.5]
REFERENCE MIT: RSM 3.1 ANSWER G.08 (1.00)
To prevent activation of argon that would result if air entered the facilit [+1.0]
REFERENCE MIT: RSM _ _
-
,
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' RADIATION CONTROL AND SAFETY PAGE 33
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ANSWERS -- NASS. INSTITUTE OF TECH. --86/09/02-SMITH, .
ANSWER G.09 (1.50)
No. [+0.5] The cpm must be corrected for efficeincy of the detector 50.5'
and the location of the source in relation to the detecto /,+0. 5,'
REFERENCE MIT: RSM, pp. 5.2 and ANSWER G.10 (1.00)
Embrittlement of the polyethylene container [+1.0]
,
REFERENCE
) MIT: PM 1.10, p. 1 ANSWER G.11 (1.00) cm 100.51 cm l+0.5
'
REFERENCE Generic: Technical Education Research Center-Southwest, pp. 1-24, 1-25, 2-1, and 2- . Academic Program for Nuclear Power Plant Personnel, Volume III, Nuclear Power Plant Technology, p. 2-22 .
.
O
--
, - . , - , ->,,--_c . ,. - . - - . . .- - - - .--n. ,-. -.- ,.. . -.-- --,., -. ,-- --- --- . - . . - - . - - - - - - _ , - - - .
, .- . . - _ . -. -_ . . - - ._ . - _ -
s'
d 8 ,
i *
_____________________________.... ___.... _______......._________________ .
I~ EQUATION SHEET i
........__ _________________________________________. ___________ ... _____
l
'
Where mi = m2 s
(density)i(velocity)1(area)1 = (density)2(velocity)2(area)2
.. _. ___.....______________________________. . __________... ______ .. ____
PE = mgh PEi + KE +P Y KE = % l 1 1 = PE2+KE2+P Y22 where V = specific volume i
P = Pressure
_________ ... ____ ........__________________________________ .________ ....
Q=mc(Tout-Tin)
p Q = UA (T,y,.Tstm) Q=m(h-h)
t 2
.
......... . ____ .....__ ._. ___........ _________________________ ________
a
P = Po10(SUR)(t) P = Po et /T SUR = 26.06 T = (B-p)t
.,
T p
__ .........________....._................ __________________________ ....__
, delta K = (K,ff-1) CRg(1-Keff1) = CR2 (I~Keff2) CR = S/(1-K,ff)
i
'
M (1-Keff1) (1-K,ff)x100%
SDM =
I II'Keff2) K eff 4-
................ _____ ........___________..__... ___________________.......
'
decay constant = in (2) " 0.693 A A e-(decay constant)x(t)
t t 1 g 1/2 1/2
.. __________...._______......................_______.... ________ .........
Water Parameters Miscellaneous Conversions I'
1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 10 dps
.
-
1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 ft 3= 7.48 gallons I hp = 2.54 x 103 Btu /hr 3 6
.
Density =62.4lbg/ft 1 MW = 3.41 x 10 Btu /hr Density = ,1 gm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm DegreesF=(1.8xDegreesC)+32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec 2
.....__.....__.........._______..________..._________......__...............
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_- ----- - - - - -- -
.s Arrachmenf / h Ent/ocun
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. U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: MASS. INSTITUTE OF TEC _ - -
REACTOR TYPE: _TE9T__ __
__
DATE ADMINISTERED: _96[O9[Og_ __
_ !
EXAMINER: _CRESCENZ92_F._____
CANDIDATE: __, _
____ __
_ INS _TRUCTIONS TO CANDIDATE:
_ _-------------------
Use separate paper for the answers. Nrite answers on one side onl Ctaple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. The passing trade requires at least 70% in each category. Examination papers will b] picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE
------
TOTAL SCORE
VALUE
-----------------------------------
CATEGORY
_39199__ _39199 ___________ ________ REACTOR THEORY
_39199__ _29199 ___________ ________ RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZAHDS
_39199__ _39199 ___________ ________ SPECIFIC OPERATING CHARACTERISTICS 29299__ 29 99 ___________ ________ FUEL HANDLING AND CORE PARAMETERS
_2_7 2 90__ _gg 09 ___________ ________ ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS 199199-- -----___--_
Tota 1=
Final Grade I
,
AII work done on this examination is my ow I have neither given nor received ai ~~ ~
CAnUidAte s Signature"~~~~~~~~~~~~~
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l
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NRC RULES AND GUIDCLINES FOR LICENSE EXAMINATIONS
- During the administration of this examination the following rules apply: l Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . Restroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil gnly to facilitate legible reproduction . Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each nection of the answer shee Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gne side of the paper, and write "Last Page" on the last answer shee . Number each answer as to category and number, for example, 1.4, . Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no . Partial credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner onl . You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been complete .--
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10. When you complete your examination, you shall:
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o. Assemble your examination as follows:
(1) Exam questions on to (2) Exam aids - figures, tables, et f (3) Answer pages including figures which are part of the answe ! Turn in your copy of the examination and all pages used to answer the examination questions.
l Turn in all scrap paper and the balance of the paper that you did
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not use for answering the question Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still
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in progress, your license may be denied or revoke >
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th__BEAgIDg,,IgggY PAGE 2
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QUESTIDN H.01 (3.00)
How much reactivity has been added to a subcritical reactor if the count rate has increased from 100 cps to 150 cps and if the initial value of Keff was .95? (3.00)
DUESTIDN H.02 (3.00)
Explain the effect of the temperature coefficient on reactivity if the thermal power of the MITR 11 core increases. Include both light and heavy water effect (3.00)
QUESTION H.03 (3.00) If neutron flux diminishes during each successive generation when Keff is less than 1.00, why does the count rate increase after each incremental withdrawal of the control rods? (1.00) Briefly explain why the time to reach a stable count rate after each incremental withdrawal of the control rods is not a constant? Assume reactor does not reach criticalit Include in your answer an explanation of both how the time changes, (increase or decrease), and why the time change (2.00)
DUESTION H.04 (2.00)
c. Explain what shutdown margin in and the core conditions for which shutdown margin is calculate (1.00)
b. Explain what excess reactivity is and what factors it is designed to accomodat (1.00)
(88888 CATEGORY H CONTINUED ON NEXT PAGE $$$$$)
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H, __ REACTOR THEDRY PAGE 3
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DUESTIDN H.05 (3.00)
Consider two identical reactors except that reactor "A" has a shim blade speed that is ten times that of reactor "B". I? lade withdrawal begins at the same moment for bot c. Which reactor will achieve criticality first? (0.50) Do they go critical at the same heights? Why or why not? (1.25)
c. Which has the higher power level when criticality is attained? Why? (1.25)
DOESTIDN H.06 (2.00)
Explain why there is a difference between the Delayed Neutron Fraction and the EFFECTIVE Delayed Neutron Fractio (2.00)
QUESTION H.07 (1.00)
Explain why the rate of power decrease following blade insertion 10 finite as opposed to a power increase which can have a variable which is dependent on the amount of positive reactivity inserted? (1.00)
DUESTION H.08 (3.00)
Suppose a control rod is to be withdrawn until 100 millibeta are added to the reactor. If the blade speed is such that the rcactivity addition rate is 10 millbuta/second, what will the reactor period be immediately before rod motion ctops and immediately after it stops? (3.00)
($$$$$ END DF CATEGDRY H *****)
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I _R,ADIDACTIVE MATERIALS HANDLI_NG DISPOSAL AND HAZARDS PAGE 4
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QUESTION I.01 (3.00)
List the three (3) basic factors which affect an individual's dose in a radiation area AND describe how the dose would vary with c change in each of the factor Assume a point sourc (3.00)
GUESTIDN I.02 (3.00)
A reactor sample has a disintegration rate of 5 X 10E12 disintegrations per secon Each disintegration emits a .6 Mev gamma. What is the dose rate expected five (5) feet from the above cample (assume point tource)? (3.00)
GUESTION I.03 (1.50)
Explain how the radiation level from an experiment sample of a single isotope could be greater than one-half the original radiation level cfter passage of more than one half-life of the activated isotop (1.50)
QUESTION I.04 (3.00)
An irradiated component measuring approximately 1"x 6" long is sur-voyed with a portable instrument. The open window indication is 2.65 Rem /Hr. and the closed window reading is 1.75 Rem /Hr. at a distance of two fee SHOW ALL CALCULATIDNS!
c. What is the beta dose rate 7 (1.00)
b. How long could you remain at the survey distance without exceed-ing 10CFR2O quarterly WHOLE BODY limits 7 (1.00)
c. What 10CFR2O guidelines must be followed if it becomes necessary to ex-ceed the quarterly whole body limit 7 (1.00)
($$$$8 CATEGORY I CONTINUED DN NEXT PAGE **888)
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11 =RADIDACTIVE_ MATERIALS _ HANDLING DISPOSAL AND_ HAZARDS PAGE 5
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QUESTIDN I.05 (3.00)
Match a Duality Factor to each Radiation Type. (Each QF may be used more than once or not at all)
RADIATIDN TYPE QUALITY FACTORS c. Gamma rays 1. 20 b. Thermal neutrons c. Fast neutrons d. Alpha particles o. X-rays f. Beta particles . O QUESTION I.06 (2.00)
Indicate whether the following statements concerning radioactive decay are TRUE or FALS When an element decays by beta emission, the new element will have increased in atomic number by one and the mass number will remain the same as the original elemen (0.50) When an element decays by alpha emission, the new element will have decreased in atomic number and mass number by two, from the original elemen (0.50) When an element decays by neutron emission the new element will have increased in atomic number by one and decreased in mass number by one, from the original elemen (0.50) When an element decays by gamma emission, the new element will have increased in atomic number by one and the mass number will remain the same as the original elemen (0.50)
(***** CATEGORY I CONTINUED ON NEXT PAGE $4888)
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- I, *,,__R,AD I DACT I VE_ MATER I %S_HANDL I NG _ D I SPOSAL _ AND __ HA Z ARDS PAGE 6
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DUESTION 1.07 (3.00)
c. According to procedure PM-4.7.2 the EAL for a General Emergency can be determined by using the following formulae:
1. For stack release... (1.58E7)(Permissible Concentration) For containment release...(S.26E7)(Permissible Concentration)
Explain the basis for allowing a larger factor in containment release calculation than for stack releases (two required). (2.00)
b. The above formulae assume that the particular radioisotope being released is known. Explain how the EALs account for the fact that the limiting radioisotope being released may not be known? (1.00)
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W QUESTION I.08 (1.50)
Why is a spill of heavy water a radiological concern? (1.50)
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. J.,_ SPECIFIC OPERATING _ CHARACTERISTICS PAGE 7
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QUESTION J.01 (2.00)
Automatic control of the regulating rod can not be initiated .
until certain requirements imposed by the " Automatic-Control-Permit" circuit are met. List these four requirment (2.00)
DUESTION J.02 (1.50)
Nuclear instrumentation channels 1 and 2 are referred to as
" Dual Fission /lon Chamber Channels". What is the approximate range of indication for each detector and describe how indication on these channels is shifted from one type of neutron detector to cnothe (1.50)
GUESTION J.03 (3.00)
Regarding the Convection and Anti-Syphon valves within the core tanks c. Give the purpose of both these valves and describe how they function to carry out their purpose. (simplified sketch acceptable) (2.00)
b. What potential problem would exist if either of these valves could not perform its intended function during reactor power operations? (1.00)
(esses CATEGORY J CONTINUED ON NEXT PAGE 88888)
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J.?.7_ E IEIC__DPERATING_CHARACTERIOTICS
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QUESTIDN J.04 (2.00)
Indicate whether the following statements concerning the main core tank level indicator system are TRUE or
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FALS c. Main core tank level indicator ML-3A is an electrically driven transmitter which is supplied by emergency power (0.50) ML3B is a pneumatically powered system and indicates on linear scale meters that are mounted in the control room and the emergency instrumentation cabinet in the utility roo (0.50)
! c. A reactor scram on low main tank water level will occur I only if both ML-3 and ML-2 level probes are uncovere (0.50) Instruments ML-3A and ML-3B utilize D/P transmitters which measure the difference between static pressure in the area of the top of the fuel, and a water filled reference leg (0.50)
GUESTIDN J.05 (3.00)
c. Describe the two interlocks which will auto trip the cump pumps associated with the liquid radioactive waste system. Include the I purpose of eac (2.00)
b. List the automatic action which will occur given a high level in DNE of the liquid waste tanks. Include the purpose of this actio (1.00)
GUESTION J.06 (2.00)
o. When would it be necessary to utilize the containment pressure relief system? (1.00)
b. What functions does the containment pressure relief system blower perform? (1.00)
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di__BEEEIElg_DggRATING_gHARAgTERISTIQS PAGE 9
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DUESTIDN J.07 (2.50)
Regarding the heating and ventilation systems c. Explain the purpose of the " Weekend Open" position of the main intake damper control switc (1.00)
b. Discuss the problems associated with improper flow rates from the Pipe Tunnel Blower. Address both too much flow, and too little flo (1.00) Describe the interlock between the gravity operated auxiliary exhaust damper and the main exhaust dampe (0.50)
QUESTION J.OO (2.00)
Discuss the response of the MITR electrical system upon a loss of 13.0 KV to the site. Limit your discussion to those components d; signed to maintain emergency power. Also describe any operator cctions which must be performed to restore forced coolant flow through the reactor cor (2.00)
QUESTION J.39 (2.00)
What does the "subcritical position" interlock circuit do and give three reasons why it is incorporated into the shim blade control circui (2.00)
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(88888 END OF CATEGORY J $$488)
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. Ka___{UE1., HANDLING _AND CORE PARAMETER ,
PAGE 10
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QUESTIDN K.01 (3. C;O)
o. Describe how, and explain why, differential control rod worth (shim blade) varies with axial positio (1.00)
b. Describe how, and explain why, integral control rod worth varies with an increase in coolant temperatur (1.00)
c. Explain why differential rod worth of the regulating rod is maximum at low rod heigh (1.00)
DUESTION K.02 (3.00)
During refueling, what are two designed safety features associated with the hold-down grid plate and what do they prevent? (3.00)
QUESTIDN K.03 (2.00)
c. Under what condition, during refueling, is the heavy water reflector not dumped? (1.00) What Technical Specification requirement must be checked if the heavy water reflector is not dumped? (1.00)
GUESTIDN K.04 (1.00)
c. According to MITR Technical Specifications, approximately how many MITR fuel elements would be required for criticality assuming optimum conditions? (0.50)
b. What is the maximum number nf fuel elements allowed by Technical Specifications to be outside designated storage areas at any one time? (0.50)
(888ss CATEGORY K CONTINUED ON NEXT PAGE $$$$$)
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( FUEL HANDLING __AND CORE PARAMETERS PAGE 11
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i QUESTION K.05 (3.00)
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Consider the removal of spent fuel from the reactor vessel to the transfer cas c. What two people must review and approve, in advance, this removal? (1.00)
- b. What two Technical Specification requirements must be met before this approval is given? (2.00)
QUESTION K.06 (2.00)
i c. When loading a new 445 gram U-235 fuel element during refueling, which ring (A,8 or C) will give you the highest mbeta/ gram of U-2357 (1.00)
b. If you load a 506 gram element instead of a 445 gram element in the same fuel location, will the mbeta/ gram of U-235 be greater, less than, or the same? Briefly explai (1.00)
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QUESTION K.07 (3.00)
According to MITR Technical Specifications, what safety channels must be operable to move fuel in the core? Include in your answer, what the required I ceram setpoints are for each channel if applicabl (3.00)
l QUESTIDN K.00 (3.00)
Descibe how to calculate the total thermal power output of the reactor per procedure PM 2.4.2. Limit your answer to a listing cf the parameters invloved and the riuplified equation for total thermal powe (3.00)
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(88888 END DF CATEGORY K 88888)
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L 3,_ ADMINISTRATIVE _PRDCEDURES3 _CDNDIT_I_DNS AND LIMITATIONS PAGE 12 e
GUESTION L.01 (3.00)
To assure that experiments in the reactor do not affect the safety of the reactor, Technical Specifications demand that all experiments within the reactor shall conform to a set of categorie List six of the seven categories set forth in the Technical Specification (3.00)
GUESTIDN L.02 (2.00)
Tcchnical specification 3.7 requires two period scram channels to be operable at all times. To ensure this specification is met, PM 2-3, Normal Startup, specifies four rules to be followed when transferring input detectors for NI channels 1 and Briefly discuss these four rule (2.00)
QUESTION L.03 (3.00)
Indicate whether or not the following are violations of procedures cnd/or technical specification (0.50 each)
c. Operating with five shim blades, the sixth shim blade is fully inserte Operating at 2 MW with one primary pump and 100 gpm primary coolant flow rat c. Operating at 150 KW with the emergency cooling system inoperabl d. Operating at 100 KW without emergency power availabl c. Operating at full power with one of the reactor floor area radiation monitors inoperable, Increasing the reactor power from 200 KW to 300 KW with the duty shift supervisor in the utilities roo (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
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. Lg__hDMINigTRATIVE__ PROCEDURE @t_ CONDITIONS AND LIMITATIONS PAGE 13
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QUESTIDN L.04 (3.00)
j Define the following terms as they apply to useage of the MITR cmergency plan procedure c. Shall (1.00) Should (1.00)
c. May (1.00)
'r QUESTION L.OS (1.50)
c. State the guideline maximum exposure limit for saving a human lif (0.50)
b. State the guideline maximum exposure limit for " establishing nuclear safety of the reactor". What specific provision aplies to the authorization of this exposure limit? (1.00)
QUESTION L.06 (2.50)
Indicate whelhur the following s.tatements regarding reactor operations are TRUE or False:
a. Reactor operations may continue if a required member of the shift must leave for emergency personal problem (0.30)
b. The shift supervisor must always be within call of the operator in charge. This is without exceptio (0.50) It is not required that the operators be familiar with the experimental apparatus used at the facilt (0.30)
d. Work shall not be conducted in the reactor building unless a reactor supervisor or a reliable person appointed by a reactor supervisor is presen (0.50)
o. The shift supervisor may grant permission to an experimenter to irradiate acids or other corrosive liquid (0.50)
(88884 CATEGORY L CONTINUED ON NEXT PAGE *****)
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'L.__ ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 14
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QUESTIDN L.07 (2.50)
c. Whose permission is required to post a warning tag on facility equipment and who may post a warning tag? (1.00)
b. List three requirements which must be observed when
" locking out" facility equipmen (1.50)
QUESTION L.08 (2.50)
UTILIZE THE ATTACHED EAL's TO ANSWER THE FOLOWING: Given the events below, state which emergency classification should be declare (0.50 pts each)
1. A large crowd of protesters marching around the reactor buildin . A fire damaging an experiment which causes the release of radio-active material . A tornado damaging the containment buildin . A slow and uncontrollable decrease in core tank level such that level remains above the anti-syphon valve What criteria is used for classifying emergency conditions? (0.50)
(***** END OF CATEGORY L *****)
(************* END OF EXAMINATION ***************)
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,f a ca v o s/t Cycle efficiency o (Matwort
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. out)/(Energy in)
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w . og s = V,t + 1/2 at E = ac *
KE = 1/2 av
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a = (Vf - V,)/t A = AN A =-Ag e **
PE = ogn !
Vf = V, + at w = e/t x = sn2/t1/2 = 0.693/t1/2 y , y ap
- t 1/28## * EI*U?)(*hI l
[(t1/2) * I*b)3 '
aE = 931 am
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I'= I,e# *
Q = mCpat ,
(j = UAat -
I=Ie"# g
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Pwr = Wyah -
I = I,10" E TVL = 1.3/u P = P,10 sur(t) HVL = -0.693/n
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p = p et /T o -
SUR = 26.06/T SCR = S/(1 - Kgf)
CR, = S/(1 - K,gx)
_ SUR = 26o/ s* + (s - s)T CR j (1 - Kgf)) = CR 2 (1 - kaff2 '
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y .[+Ap+d_e 8-p ~[ M = 1/(1 - X,g) = CR j/CR, o
dt N * (I * Kdfo)/(1 ~ Ke#l)
SDM = (1 - Kgf)/K,ff
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o = (Kgf.1)/Kgf = aKgf /K gf 1* = 10-5 seconds
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T = 0.1 seconds-I e = [(1*/(T Kgf)]+[igf(1+-AT)] /
Id jj=Id Id 2 ,2 gd
P = (z6V)/(3 x 1010) jj 22
- 2 x = eN '
R/hr = (0.5 CE)'/d (meters)
R/hr = 6 CE/d2 (feet)
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Water Parameters Miscellaneous Conversions
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1 gal. = 8.345 lb curie = 3.7 x 1010dps 1 ga:. = 3.78 liters
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1 kg = 2.21 lba 1 ft' = 7.48 ga I hp = 2.54 x 103. 8tu/hr Density = 62.4 lbe/ft3 l as = 3.41 x 106 Stu/hr
' Density = 1 ge/ce8 . lin = 2.54 cm Heat of vaporization = 970 Stu/lem 'F = 9/5'C + 32 Heat of fusion = 144 Stu/lbe *C = S/9 (*F-32)
1 Ata = 14.7 psi = 29.9 in. H BTU = 778 ft-lbf 1 ft. H 2O = 0.4335 lbf/i , . ~ Da. 8@ of 13
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Table 4.5.3-1: EALs for Motification of Unusual Events
- Confirmed' abnormal radiation levels leading to actuai or projected radiological effluents at the site boundary exceeding 10 MFC for unrestricted areas uben averaged over 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> This level corresponds to an exnosure of 15 mren whole body accumulated over 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (PP 4.4.4.15h) .. Report or observation that severe natural phenomena are either imminent or ex-istin These include scorns with tornado or hurricane force winds that could strike the facility, earthquakes that could adversely affect the reactor's safety systems, and floods that could adversely af fect the reactor's safety system (P." 4.4.4.2) Threats to or breaches of security. ' (PM 4.4.4.5/4.4.4.6) A reactor safety limit's being exceeded such that a fuel damage accident that could release radionuclides to the containment building is possibl (PM 4.4.4.1) A fire within the containment building that lasts beyond the incipient stage or for more thsn ten rinute (PM 4.4.4.3) Receipt of a bomb threa (PM 4.4.4.7)
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SRf-0-82-19 AUG 6 1982
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Table 4.5.3-2: EALs for an Alert
. Confirmed abnormal radiation levels leading to actual or projected radiological effluenhat the site boundary er.ceeding 50 MPC for unrestricted areas when averaged over 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> This level corresponds to an exposure of 75 mrem whole body accurulated over 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (PM 4.4.4.15b) Same as #1 except the effluents could cause an in*fegrated exposure of 100 mrem thyroi (PM 4.4.4.15b) Radiation levels at the site boundary of 20 arem/ hour sustained for one hou (PM 4.4.4.14b/4.4.4.11) . Abnormal loss of prinary coolant such that the core tank level remains at or
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above the anti-syphon valve (PP 4.4.4.4) Loss of radioactive material control that causes radiation dose rates or air '
borne radionuclides to increase above pern.issible exposure levels by a factor of 1000 throughout the containment buildin (PF 4.4.4.12) Radiation dose rates throughout the containment building in excess of 100 mrem /
hour sustained for one hour. These levels would necessitate evacuation of all personne (PM 4.4.4.12)
l A fire leading to loss of radioactive material control within the containment
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buildin (PM 4.4.4.3) An imminent or existing hazard such as:
l (a) Missile (s) impacting on the containment buildin (b) An explosion that affects facility operatio (c) An uncontrolled release of toxic or flammable gases into the containment
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Tabic 4. 5.3-1: FALs for a Site Area Emergency
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- Confirmed. abnormal radiation levels leading to actual or projected radiolori-cal effluents at the site boundary exceeding 250 MPC for unrestricted areas when averaned over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This level corresnonds to an exposure of 375 mrem whole body accumulated over 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (PP 4.4.4.15b) Same as #1 except the effluents could cause an integrated exposure of 500 mren thyroi (PP 4.4.4.15b) Radiation levels at the site boundary of 100 nrem/ hour sustained for one hou (PM 4.4.4.14b/4.4.4.ll) Abnormal loss of primary coolant such that the core tank level drops below the anti-syphon valve (Note: This accident is not considered credible, but procedures exist for coping with it.) (PP 4.4.4.4) Imminent loss of physical control of the reacto (PM 4.4.4.6) Severe natural events being experience These include:
(a) An earthquake that is causing observable damage to the reactor safety equipment within the containment buildin (b) A flood that is affecting the operability of any reactor safety syste (c) Tornado or hurricane force winds that are damaging the containment buildin (PM 4.4.4.2)
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SRf-0-82-19 AUG 6 1982
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Table 4.5.3-4: EALs for a General Emergency
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- Actual or. projected doses at the site boundary in the exposure pathway of '1 rem whole body or 5 ren thyroid for unrestricted areas when averaged over one hou Note: Figure 4.7.2.2-1 lists the conditions and instrument readings correspond-ing to a projected off-site dose of 1 rem / hou (PF 4.4.4.15a)
~ Sustained actual or projected radiation levels at the site boundary of 500 mrer/
hour whole bod (PM 4.4.4.14 a/4. 4.4.11/4. 4.4.12) Blockage of fuel element channels thereby causing a loss of coolant to the affected channels and a fuel melt. This is the design basis acciden (PM 4.4.4.15a) ..
~ Loss of physical control of either the containment building which includes the control roo or of auxiliary area that house vital equipmen (PF 4.4.4.5/
4.4.4.6). Events that have caused or will cause massive facility and/or reactor system damage that could lead to the melting of fue (PP 4.4.4.15a)
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SRf-0-82-19 AUG 6 1982
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, Hj[_REACTDR, THEORY PAGE 15
. . 1 ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, *
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ANSWER H.01 (3.00)
cr1 /cr2 = (1-Keff2) / (1-Keff1) [0.93 100/150 = (1-Keff2) / (1-0.95) [O.53 1-Keff2 = 10/15 x O.05 Kaff2 = 0.967 [O.13 change in reactivity = [Keff2-1/Keff23 - [Keff1-1/Keff13
= Keff2 - Keff1 / Keff1 x Keff2 [O.93
= 0.967 - O.95 / O.95 x O.967 [O.53
= 1.85 */. delta K/K [O.13 REFERENCE BIsic Reactor Theory ANSWER H.02 (3.00)
Increasing the temperature of the light water will insert negative reactiv-ity by causing the neutrons to take longer to thermalize so there are iswer fissions (1.5). Heating of the heavy water reflector will add nega-tive reactivity by allowing neutron leakage to increase (1.5).
REFERENCE RSM pg. 1 ANSWER H.03 (3.00)
c. Count rate is increased by the multiplication of source neutron For each Keff there is a unique neutron count. [1.03 (With each incremental rod withdrawal, Keff is increased toward a value of 1.00.) The larger the value of Keff the longer it will take to reach a new higher equilibrium neutron level since more generations wi 1 have significance. [2.03 REFERENCE $
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MITR Reactor Physics nbtes " Reactor Subcritical Multiplication" l
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ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, . ,<
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ANSWER H.04 (2.00)
a. Shutdown margin assures the reactor can be shutdown from any operating condition [O.53 based on cold Xe free, with most reactive operable rod and the regulating rod full withdrawn from the core. [O.53 Excess reactivity is the reactivity above that that required to maintain the reactor critical. CO.53 It accomodates for -
fuel burnup, xenon and samarium buildup, experiments, and control requirements. [O.53 REFERENCE T.S. 3.1, p 20, 21
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ANSWER H.05 (3.00)
c. Reactor A (0.5)
b. The same. The height of the rods when just critical is a function of SDM. Rate of reactivity addition is independent of reactivity. (1.25)
c. Reactor B since suberitical multiplication will have a longer time to raise count rat (1.25)
REFERENCE MITR Reactor Theory Notes ANSWER H.06 (2.00)
Delayed neutrons are born at close to thermal energies hence f ewer delayed neutrons are lost f rom the neutron cycle during the thermalization proces (2.00)
REFERENCE MITR Reactor Theory note .-. . - _ _ _ _ . _ _ _ _ _ .
. _ ,. - _ _ . . . _ _ _ _ - _ . _-_-__ . __ _ . . . - _ . REACTOR THEDRY PAGE 17
' ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, *
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ANSWER H.07 (1.00)
Negative reactivity does not affect delayed neutrons hence once prompt neutron populati on has diminished, period can not be lower than -80 secs due to the decay rate of the longest lived neutron precursors 55 sec (1.00)
REFERENCE MITR Reactor Theory Notes ANSWER H.OB (3.00)
Prior to stopping the blade motion, the reactivity is O.1 beta and the j term is O.01 beta per second. therfore,
- _
di T 0-0
= E-0 + Ap + d 2 dt
~
,1*10 1 .1
.1 - ,C.08)(.1) + .o1
= 50 seconds'
After stopping the jf; term is now zero. Therfore, REFERENCE dr -4 0 1 l'
MITR Reactor Physics Notes =
, ,7
, + (.NI)(.1) + 0
= 112.5 seconds l
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RADIDACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 18
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ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, *
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ANSWER I.01 (3.00) Time (0.5). Dose varies linearly (0.5). Distance (0.5). Dose varies as the inverse of the distance squared (0.5).
e Shielding (0.5). Dose varies exponentially (0.5).
REFERENCE
" Introduction to Nuclear Engineering", Lamarsh ANSWER I.02 (3.00)
(5 X 10E12 dps)/3.7 X 10E10 dps per Ci = 135 Ci (1.5)
DR = (6 X Ci X E)/dE2 = (6 X 135 X .6)/25 = 19 R/Hr (1.5)
REFERENCE Radiation Protection by Shapiro, pg. 62 ANSWER I.03 (1.50)
If the parent isotope decays to a radioactive daughter (1.5).
REFERENCE
" Nuclear Power Reactor Safety", E.E. Lewis Radiation Protection by Shapiro, pg 62 ANSWER I.04 (3.00)
c. Beta dose rate = closed window - open window = 0.9 Rem /hr (1.0) Stay time: 10CFR2O 1.25 R/1.75 R/Hr = .71 hr. x 60 = 4 minute (1.0)
c. May receive up to 3 Rem /Qtr. [O.23 if previous exposure is doc-mented [O.43 and lifetime dose < 5(N-18) [O.43 (1.0)
REFERENCE 10 CFR 20
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RADIDACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 19
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ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, F.
ANSWER I.05 (3.00) c.- 3 d . = -- -- - =- 1 CO.5 each] (3.0)
REFERENCE
" Introduction to Nuclear Engineering" Lamarsh ANSWER I.06 (2.00)
a. TRUE b. FALSE c. FALSE d. FALSE (0.50 each)
REFERENCE Standard Nuclear Principles ANSWER I.07 (3.00) The dilution factor for the containment release is greater because:
1. The point of maximum concentration is adjacent to the building but the point of concern is 21 meters awa (1.00)
2. The flow rate for a containment release is known and is used in calculation fo the dilution factor (1.00)
b. The EALs are based on the assumption that the most limiting MPC is being release (1.00)
REFERENCE MITR PM 4. ANSWER I.OB (1.50)
Tritium content (1.5)
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Ig_RADIDACTIVE__ MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 20
- 1 ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, l
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REFERENCE MITR PM 4.5 ,
r
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, . SPECIFIC _ OPERATING CHARACTERISTICS
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ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, *
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ANSWER J.01 (2.00)
1. All shim blades must be above subcritical interlock positio . The deviation between power-set and actual power must not exceed 1.5% The regulating rod control switch must be in neutral position 4. The regulating rod must be withdrawn beyond its near-in position.(1.6 inches) (0.5 each)
REFERENCE MITR RSM- ANSWER J.02 (1.50)
Fission chambers indicate first four decades of power increas (0.25)
Ion chambers indicat from O.1% to 100%. (0.25)
To transfer, turn the gain =ad "a +h= discri-i ztier er f i r- uii c t. _..im. J ;;crinir.stm, -.,g l i s i m leaving ion chamber as sole input to channel.(or vice versa) (1.00)
REFERENCE MITR RSM 5-3 ANSWER J.03 (3.00)
c. Anti syphon valves prevent syphon draining of the core tank following a break of the reactor coolant inlet lin (0.50)
Convection valves permit convection cooling during periods of no forced flo (0.50)
See attached sketches of valve (1.00)
b. Significant amounts of coolant flow could bypass the cor (1.00)
REFERENCE MITR PM 5. . _ _ - - _ . _ _ , . . _ - . _
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, SPECIFIC DPERATING CHARACTERISTICS PAGE 22
ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZD, .
ANSWER J.04 (2.00)
a. TRUE b. FALSE c. FALSE d. FALSE (0.50 each)
REFERENCE MITR RSM ANSWER J.05 (3.00) . Sump pumps trip on high rads in line to the storage tanks to prevent exceeding site perimeter rad levels (1.00)
2. High waste tanks alarms in BOTH tanks. This will preclude overflow of tanks to environmen (1.00)
b. The city water solenoid shutoff valve will close to prevent overfill of the tanks due to an open water faucet or leak (1.00)
REFERENCE MITR RSM 8-5 ANSWER J.06 (2.00) If building pressure exceeds 2 psig, and if radiation levels and/or structural damage preclude opening the main or auxiliary damper (1.00)
b. Draws air thru system prior to reactor startup to both clean and activate the charcoa (1.00)
REFERENCE MITR RSM 8-4, PM 5. _ __
. . . .n v
, SPECIFIC DPERATING_ CHARACTERISTICS PAGE 23 ,
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ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZD, *
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ANSWER J 07 (2.50)
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a. This position will close the damper if ventilation flow is lost h~8 to ensure all air exhausted f rom the building is filtered.und 0** (1.00)
b. Too much flow will draw excessive amcunts of fresh air into the tunnel thereby causing unecessarily high levels of AR-41 activation and releas (0.50)
Too lttle flow may allow AR-41 to diffuse to reactor floor creating radiation hazard (0.50)
c. Auxiliary damper will close if main damper does not close within 10 seconds of a trip signa (0.50)
L~ raLW REFERENCE MITR RSM 8-11 ANSWER J.08 (2.00)
Emergency lighting transfer switch immediately connects the bettery to the emergency lighting (.50). The motor generator is immediately started (.50), but output breaker will not close for 12 seconds at which time emergency AC loads are supplied (.50). The operator must reset the LVP on the auxiliary pump MM-2(0.50)
REFERENCE MITR RSM 8- ANSWER J.09 (2.00)
It limits shim blade withdrawl motion to four inche . It maintains shim blade bank programmed at a uniform height during the final approach to criticalit . It establishes a level, below the critical position, to which the shim blades may be individually withdrawn in one ste . It provides a convenient reference point at which the operator can pause to make a complete instrument check before bringing the reactor critica (0.50 each)
REFERENCE MITH RSM 1 ,
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i k VALVE OPEN VALVE CLOSED FIGURE l.17 , Q/A NO. 0 'M-3 DATE NATURAL C ONVEC TION VALVES APPROVED _ w 31. die . . .
4/A APP' 40___ _ _ p dy_/s
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K._ FUEL HANDLING AND CORE PARAMETERS PAGE 24 a
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ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, ,
ANSWER K.Ol (3.00)
a. Rod worth is lower at the top and bottom of the core due to a higher flux and greater neutron "importance" near the core midplan (1.00) Rod worth increases as temperature increases. This is due increased thermal diffusion length which increases the probability of control blade interactio (1.00)
c. Full in position is six inches above the bottom of the fuel elements and also because once the regulating rod is withdrawn it is heavily shadowed by adjacent shim blade (1.00)
REFERENCE MITR Reactor Theory notes. RSM-1 ANSWER K.02 (3.00)
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1. The grid is designed so that there is normally access to only one core position at a time (.75). This limits the amount of water that can be in the core at any one time by making it difficult, though not impossible, for more than one core position to be defueled at time.(.75) The grid's latch is interlocked with the primary coolant pumps so that if the latch is released, the coolant pumps stop and remain off until the grid is latched again (.75). This protects the fuel elements from damage and the reactor as a whole from inadvertent criticality (.75)
REFERENCE PM 2.7, pg. 3 ANSWER K.03 (2.00)
- If dumping would cause the nuclear instrumentation startup channels to indicate less than 10 counts per minut (2.0)
] The shutdown margin would have to be checke (1.0)
REFERENCE PM 2.7, pg. 3
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, K. __ FUEL HANDLING AND_ CORE PARAMETERS PAGE 25
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ANSWERS -- NASS. INSTITUTE OF TEC /09/02-CRESCENZO, *
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ANSWER K.04 (1.00)
a. 8 1/3 (+,- 1) (0.50)
b. 4 (0.50)
REFERENCE MITR TS 3.10 ANSWER K.05 (3.00)
c. Senior Reactor Operator (0.50)
Reactor Superintendent (0.50)
b. 1. Element to be removed cannot be moved unless it has not been in the core at a power level above 100 KW for at least four day (1.00)
2. The Keff of any storage area outside of the reactor core shall be less than 0.90 (1.00)
REFERENCE MITR PM 1.15.1 i
ANSWER K.06 (2.00)
f \
c. A-ringl because the flux is highest due to less leakage) (1.00)
b. Less, dhe decrease is due to the self shielding of the more heavily loaded element (1.00)
REFERENCE MITR RSM 1 ANSWER K.07 (3.00)
c. Period, Neutron flux level, D20 dump valve selector switch manual major scra (2.00)
b. Period than 3 sec (0.50)
Neutron flux 100KW (O.50)
I w g- .. . _ _ . . - . . _- . - - __ - __-_ _ _ . -
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, FUEL _ HANDLING AND CORE PARAMETERS PAGE 26
ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, .
REFERENCE MITR Tech specs pg 3-22 ANSWER K.OB (3.00)
Primary power = (primary flow) (primary delta T)
Reflector power = (D20 flow) (D20 delta T)
Shield power = (shield flow) (shield delta T)
Total power = Primary + Reflector + Shield power (0.75 each)
REFERENCE MITR PM 2.4 p. 5 l
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, ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 27 l'
ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, *
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ANSWER L.01 (3.00)
Reactivity Effects Thermal-Hydraulic Effects
Chemical Effects Radiolytic Decomposition Experiment Scram Prototype Testing ,
Radioactive Release (9 0.5 pts, any six for 3.0)
REFERENCE Technical Specifications (T.S.) 6.1, pg. 6-1 to 6-7 ANSWER L.02 (2.00) Do not shift detectors until channel #3 is onscale and rese . Transfer only one channel at a tim . Allow time between transfer of first channel for its indications to settle ou . Transfer both channels prior to either channel's fission chamber reaching saturatio (0.50 each)
REFERENCE MITR PM 2-3 ANSWER L.03 (3.00)
a. violation of TS (3-32)
b. No violation c. Violation of TS (3-19)
d. Violation of TS (3-21)
o. No violation f. Violation of PM1.3,(SS must observe increases in power) (O.50 each)
REFERENCE MITR Technical specifications and PM .
bi _ ADMINISTRATIVE _ PROCEDURESt _ CONDITIONS AND LIMITATIONS PAGE 28 ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, F.
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ANSWER L.04 (3.00) Shall denotes a requiremen Should denotes a recomendatio c. May denotes permission and is neither a recomendation nor a requiremen (1.00 each)
REFERENCE PM 4.2 p. 4 ANSWER L.05 (1.50) REM (0.50) REM. (0.50). Should only be authorized if this action is to protect the public.(0.5)
REFERENCE MITR PM 4-7-5-1
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ANSWER L.06 (2.50) false true false true false (0.50 each)
REFERENCE MITR PM 1.14 pg 5-6 ANSWER L.07 (2.50)
c. On duty console operator; any member of the NRO/RPO staff (1.00)
b. 1. SRO will witness lockout 2. Person performing work will perform lockou . Person performing work will retain the key on his person 4. A notation as to the system being locked out shall be made on the status boar (3 required at O.50 each)
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hi__AEMINISTRATIVE PROCEDURESt _ CONDITIONS AND LIMITATIONS PAGE 29
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ANSWERS -- MASS. INSTITUTE OF TEC /09/02-CRESCENZO, .
REFERENCE MITR PM 1-14 pg 9 of 9 ANSWER L.08 (2.50) . Notification of Unusual Event Alert .c O An4 Site Area Emergency Alert (0.5 pts each) Potential radiological consequences (0.5)
REFERENCE PM 4.5, pgs. 10 to 12 PM 4.4, pg. 2
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TEST CROSS REFERENCE PAGE 1 QUESTION VALLIE REFERENCE
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H.01 3.00 FJCOOOO336 H.02 3.00 FJCOOOO338 H.03 3.00 FJCOOOO342 H.04 2.00 FJCOOOO343 H.05 3.C0 FJCOOOO355 H.06 2.00 FJCOOOO356 H.07 1.00 FJCOOOO357 H.08 3.00 FJCOOOO384
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20.00 I.01 3.00 FJCOOOO334 I.02 3.00 FJCOOOO335 I.03 1.50 FJCOOOO337 I.04 3.00 FJCOOOO340 I.05 3 . O Ci FJCOOOO341 I.06 2.00 FJCOOOO345 I.07 3.00 FJCOOOO382 I.08 1.50 FJCOOOO383
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20.00 J.01 2.00 FJCOOOO359 J.02 1.50 FJCOOOO361 J.03 3.00 FJCOOOO362 J.04 2.00 FJCOOOO363 J.05 3.00 FJCOOOO364 J.06 2.00 FJCOOOO367 J.07 2.50 FJCOOOO368 J.08 2.00 FJCOOOO369 J.09 2.00 FJCOOOO370 20.00 K.01 3.00 FJCOOOO358 K.02 3.00 FJCOOOO365 K.03 2.00 FJCOOOO366 K.04 1.00 FJCOOOO371 K.05 3.00 FJCOOOO372 K.06 2.00 FJCOOOO373 K.07 3.00 FJCOOOO374 K.OB 3.00 FJCOOOO373
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20.00 L.01 3.00 FJCOOOO339 L.02 2.00 FJCOOOO360 L.03 3.00 FJCOOOO376 L.04 3.00 FJCOOOO377 L.05 1.50 FJCOOOO378 l
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