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Exam Rept 50-193/87-01OL on 871020-21.Exam Results:One Senior Reactor Operator Candidate Passed Written & Operating Exams & License Issued
	ML20237C654
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	12/14/1987
From:	Keller R, Norris B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20237C638	List: IR 05000193/1987001; ML20237C636;
References
	50-193-87-01OL, 50-193-87-1OL, NUDOCS 8712220055
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U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N /87-01(0L)

FACILITY DOCKET N FACILITY LICENSE N R-95 LICENSEE: Rhode Island Atomic Energy Commission Narrangansett, Rhode Island FACILITY: Rhode Island Nuclear Science Center EXAMINATION DATES: October 20-21, 1987

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CHIEF EXAMINER *

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b 4:?/ P77 t

tiarry ^ .'Norris Date '

Senio perations Engineer APPROVED BY:

Robert M. KelTer,~0'hief ll.//Md7 Date Pressurized Water Reactor Section Operations Branch, Division of Reactor Safety SUMMARY: Written and operating examinations were administer ed to one Senior Reactor Operator (SRO). One SRO license was issue ,

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REPORT DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS:

l SRO j l Pass / Fail I l i i i I l Written l 1/0 l 1 1 I I I I

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l Operating l 1/0 l 1 l I I I I 10verall l 1/0 l l l l EXAMINER'AT SITE: R. G. Clark (PNL) There was only one candidate; therefore, no generic weaknesses or strengths could be identifie . The written examination was reviewed by the facility after the candidate had completed the examination. Comments were submitted to the Region I offic The facility comments and the NRC resolution are enclosed as Attachment 2.

l l Attachments: , SRO Written Examination and Answer Key ' Facility Comments on Written Examination and NRC Resolution l

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U. $. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: RHODE ISLAND & PROV. P AEC

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REACTOR TYPE: TEST

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DATE ADMINISTERED: 87/10/20 EXAMINER: CLARK, CANDIDATE: ANSWER KEY INSTRUCTIONS TO CANDIDATE:

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 20.00 20.00 H. REACTOR THEORY 20.00 20.00 I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS 20.00 20.00~ J. SPECIFIC OPERATING CHARACTERISTICS 20.00 20.00 K. FUEL HANDLING AND CORE PARAMETERS 20.00 20.00 L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS 100.00 % Totals final Grade All work done on this examination is my ow I have neither given nor received ai Candidate's Signature

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS 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 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 section of the answer shee . Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write only on oiie side of the paper, and write "Last Page" on the last answer shee . Number each enswer 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 dova 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 '5. Partial credit may be given. 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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l 18. When you complete your examination, you shall:

1 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 questions, i

c. 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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. . REACTOR-THEORY PAGE 2

. QUESTION H.01 (1.00)

IF the initial neutron flux in a reactor was 10 neutron cm**-2 sec**-1-and if the reactor was on a 30-second, constant, positive period, WHAT would the flux be after 90 seconds?

SHOW your wor (1.0)

QUESTION H.02 (2.00)

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Fuel Core Distribution Across Core k Reflector

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. Use the above figure to show the fuel distribution at end of fuel load lif (0.5) On this same figure, DRAW the thermal neutron flux distributions (radial variations) for this fuel load-for both the start and end-of-life condition (1.5)

QUESTION H.03 (1.50)

When operating the RINSC reactor at 1.0 MW, IDENTIFY the modes of .

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heat transfer by which heat is removed from the fuel. INCLUDE the major components in the heat removal process starting with l the fuel and ending at the ultimate heat sin (1.5)

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L REACTOR THEORY PAGE 3 QUESTION H.04 (1.00)

Under steady-state operation, WHAT would be the difference between the control rod positions at 100 kW and 1000 kW7 EXPLAI (1.0)

QUESTION H.05 (1.00)

Assume a uniform distribution of fuel exists in the reactor during operation at 1 MW with a unifonn coolant flow through thereactor(noblockage). EXPLAIN WHAT could cause a fuel

. hot spot to develo (1.0)

QUESTION H.06 (1.00)

ANSWER TRUE or FALS The Doppler effect in the RINSC reactor is due to the broadening of the resonance absorption cross-section peaks for Xe and other fission fragment (0.5) For a reactor, the effective multiplication factor k-eff equals k-in#inity times P, where P is the total nonleakage probabilit (0.5)

QUESTION H.07 (2.00)

WHY is the pool temperature coefficient negative in the RINSC ~

reacto (2.0)

QUESTION H.08 (2.00)

DESCRIBE HOW and WHY the power level will change during the first 5 minutes into a scram ending an operating period of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at 2 M (2.0)

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li THEORY !

REACTOR l

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(3.00) reactivity to a t best '

y H.09 of positivewith a descriptor thaeach of three QUESTION low ulation for Considersource addition. TH a

/ ASSUME a occur small additionCOMPLETE the table bes of the (3.0)

describes the values of K.eff that resuof best K-eff with N0 sour description each value in plac associated with theeach cas opulation in SELECT the letterensuing neutron p

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increases linearly is in equilibriumexponentially

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. increasesdecreases linearlyexponentially With Source Present e. decreases No Source ...........

Present K.eff

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(1.00) a suberitical reactorand QUESTION H.10 s been f rom 100 cps to 150 cps added to ed HOW much reactivity ha the count rate has increasof k-eff was 0.957 initial value operations 7 (200) routine H.11 QUESTION reactivity needed for excess WHY is GIVE four (4) reason pppp

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. REACTOR THEORY PAGE 5 QUESTION H.12 (1.50)

If B-eff'for the RINSC reactor was reduced from the actual

.0.077% to 0.055%,.HOW and WHY would the reactor respond to a small addition of positive reactivit (1.5)

QUESTION H.13 (1.00)

DISCUSS the production and removal process for Xe in the reacto (1.0)

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' RADI0 ACTIVE MATERIALS' HANDLING DISPOSAL AND HAZARDS PAGE 6 'l

QUESTION' I.01 .(2.00)

'According to the Radiation Safety Guide and the Technical Specification, IDENTIFY the individual primarily responsible, for each of.the following:

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' Who has the primary responsibility for radiation safety at the Rhode-Island Nuclear Science Center? (0.5) During routine reactor operation, who on shift is responsible for all activities involving radiation hazards? (0.5)

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Who is responsible for ensuring that radiation surveys in the vicinity of radioactive sources and the reactor are accomplished? (0.5). Who is responsible for management of the waste disposal service? (0.5)

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According to the Radiation Safety Guide: STATEthelimitations(s).ondisposingofradioactivewaste

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by incineration or buria (0.5) STATE the method (s) to be used to dispose of radioactive liquid. waste (1.0)

QUESTION I.03 (1.00)

i DEFINE the following terms Transport Index (0,5) Biological Half-life (0.5)

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' RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 7 i

QUESTION I.04' ( 2.00)-

In each instance below, GIVE the external radiation exposure level- to a major portion of the body that is associated with defining or that is limiting in each of these four area . radiation zone (0.5) the contributing dose rate in an unrestricted area from a radioactive source in an adjacent (adjoining) permanent storage area (0.5)_ high radiation zon (0.5) unrestricted area (0.5)

QUESTION I.05 (1.50)

A radiation source emits 0.9 HeV gamma protons and produces a reading of 10 rad /hr on a detector which is 3 feet away. WHAT thickness of lead shielding will be required to reduce _ the reading to 5 mrad /hr at that point? [ ASSUME tenth value layer (TYL) for lead equals 1 inch.] (1.5)

QUESTION I.06 (1.00)

According to the Radiation Safety. Guide, in an event where an injured person is contaminated, WHAT should be done prior to loading and subsequent transportation in the ambulance to the hospital? (NAME two (2) steps.) (1.0)

QUESTION I.07 (2.00)

EXPLAIN HOW and WHY the determination of dose rates from a point source may not be valid in the following .for distances that are relatively close to the sourc (1.0) for distances that are especially far from the sourc (1.0)

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RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 8 j

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QUESTION I.08 (3.00)

Assume the reactor is operating at 1 MW. WHAT would an alarm ,

on each of the fixed gamma monitors indicate? Consider the condition at each monitor as an. independent event (unrelated). (3.0)

a QUESTION I.09 (1.00)

Briefly explain WHY the constant '(1.8 x 10**-12 delta C/t) used during emergencies to establish-limits on air particulate at ground level is LOWER than the constant (2.6 x 10**-12 delta C/t)

used during normal condition (1.0)

QUESTION I.10 (2.00)

From 10CFR20, WHAT are the maximum allowable exposure limits (whole body, extremities, and skin) for a radiation worker who has an NRC Form 4 on file.: (2.0)

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QUESTION I.11 (1.50)

ESTIMATE the dose rate 5 feet from a small aluminum vial con-taining about one-third (1/3) curie of Co-6 Express your answer both in mrad /hr and mrem /hr. Co-60 emits two gammas of 1.37 MeV and-1.19 MeV. You may ASSUME a reasonable single average energy MeV gamma from this source for this question. SHOW your wor (1.5)

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I. ' RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS' PAGE 9 QUESTION I.12 (1.50)

SELECT from the decay modes listed below, the closest to that,of EACH of the following (1.5) ; AR-41 Half Life Decay Mode

......... .......... .8 hr - beta decay /no gama .8 hr - beta decay /1-2 MeV gamma .3 sec + beta decay /608 MeV gama .7 min - beta decay /no gama N-16 .3 hr alpha decay /no gamma .3 hr - beta decay /1-2 MeV gamma .3 see - beta decay /6-8 MeV gamma .3 min + beta decay />-6 MeV gamma Na-24 min - beta decay /no gamma hr no beta decay /1-3 MeV gama hr - beta decay /no gamma sec - beta decay /1-3 MeV gamma

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" SPECIFIC OPERATING CHARACTERISTICS PAGE 10 QUESTION J.01 (2.50) NAME the reactor safety system protective functions which are bypassed when the Power Level Selector Switch is in the 0.1.MW sosition. INDICATE:those bypassed functions that would 1 ave provided trip signal (2.25) WHAT would be the effect of switching the Power Level Switch to the 5 MW position inadvertently during a reactor startup? (0.25)

QUESTION J.02 (2.00)

l WHAT functions should occur automatically if_the evacuation button is depressed? GIVE four (4). (2.0)

QUESTION J.03 (3.00)

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l WHAT three (3) automatic actions will occur if normal I

electrical power is lost when the reactor is at 500 kW7 (1.5) .WHAT electrical loads should be automatically energized following a loss of normal power 7 (1.5)

QUESTION J.04 (2.00)

Assuming the reactor is operating at 95% power, INDICATE for each of the following situations whether the reactor should be SCRAMMED, SHUT DOWN, REDUCED IN POWER, or could be MAINTAINED AT POWE Consider each situation separatel (2.0)

a.- Reactor power drops unexpectedly to 92%. Reactor power increases to 96% as the pool water inlet temperature increases to 110 degrees The alarm for the high neutron flux on one of the compensated ion chamber safety channels becomes inoperable due to a faulty rela )

l The temperature of the coolant leaving the core during forced convection cooling reaches 120 degrees I i

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.' SPECIFIC OPERATING CHARACTERISTICS PAGE 11 QUESTION J.05 (2.50)'

Refer to the accompanying figure depicting the power history of the RINSC' reactor for 175 hours0.00203 days 0.0486 hours 2.893519e-4 weeks 6.65875e-5 months . Assume the RINSC reactor has been shut down for a week prior to this operation. On the same !

I figure and time scale DRAW the resulting xenon reactivity curv (2.5)

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QUESTION J.06 (2.50)

IDENTIFY key changes to the reactor X the secondary circulating pump fails while the reactor is at 100% power with all rods in manual control. Assume that systems operate normally and no operator action is take (2.5)

i QUESTION J.07 (2.00)

Given the reactor parameters below, DETERMINE the reactor power in M (2.0)

Inlet: temp primary coolant: 108 degrees F Outlet temp primary coolant: 117 degrees F Flow rate primary coolant: 1500 gp i QUESTION J.08 (1.50)

ANSWER TRUE or FALS ! Inverting an irradiated fuel element would have no effect on core reactivity or differential control rod wort (0.5) Evacuating the aluminum cladding on the graphite reflector logs enhances heat transfer to the pool wate (0.5) The volume of water transferred from the pool into the primary is controlled primarily by flow paths in the control blade shroud (0.5)

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' SPECIFIC OPERATING CHARACTERISTICS PAGE 12 QUESTION J.09 (1.00)

EXPLAIN the design feature of the coolant circulation system in the core that minimizes the radiation level at pool surface from N-1 (1.0)

QUESTION J.10 (1.00)

ANSWER TRUE cr FALS The RINSC fully reflected reactor will not' go critical even if the entire 7 x 9 grid of the core were filled with fuel element (0.5) Full flow through the fuel elements will probably not-be turbulent at lower temperature (0.5)

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'* 1 FUEL HANDLING AND CORE PARAMETERS PAGE 13-QUESTION K.01 (1.50) Briefly DESCRIBE a procedure necessary to obtain an on-scale reading on-the linear level safety channel compensated ion ]

chamber during an initial core loadin (1.0) ' HOW many vacant' fuel element positions within the periphery of the active section of the core can exist in a fully loaded core?- (0.5)

QUESTION K.02 (2.50)

The initial count rate for a RINSC reactor core with fuel elements and source installed is ten (10) counts per secon For the following loading sequence and corresponding count rates, PREDICT the number of fuel elements for a critical loading. (USE the attached graph paper for a 1/H plot.)

LABEL the axis. SHOW your wor (2.5)

No. Fuel Count Elements Rate, cps

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1 13 7 17 13 25 19 50 QUESTION K.03 (1.50) GIVE the maximum total RESIDUAL reactivity permitted in the core during core loadin (0.5) HOW is this level of reactivity assured? (1.0)

QUESTION. K.04 (1.00)

When loading for CRITICAL EXPERIMENTS,

' WHAT should be the status of the core cooling system? (0.5) WHAT is the minimum water level in the pool? (0.5)

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... ,' ' FUEL HANDLING AND CORE PARAMETERS PAGE 14 QUESTION K.05' .(2.25)

In accordance with Rhode Island Operating Proceedures, FILL in the following blanks regarding required reactivity value , The shut-down margin required for. movement of any fuel is-

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(0.75) MANUAL changes-in experimental equipment which can affect reactivity by more than prior to the move-ment _of the equipment require a shut-down margin of .

(1.5)

QUESTION K.06 (2.00)

WHAT four (4) systems and/or instrumentation must be operable prior to preparing and shipping of spent fuel elements to reprocessing?- (2.0)

QUESTION' K.07 (1.25)

STATE two (2) reasons why white cottca gloves are to be worn when handling the plates of new fuel element (1.25)

QUESTION K.08 (2.00)

HOW is inadvertent criticality prevented during irradiated'

fuel handling and storing? GIVE four (4) mean (2.0)

QUESTION K.09 (3.00)

STATE four (4) of the limitations that exist on the experiments conducted at the RINSC reacto (3.0)

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, FUEL HANDLING AND CORE PARAMETERS PAGE 15 QUESTION X.10 (1.50)

ANSWER TRUE or FALSE regarding reactivity limitations or core conditions, For any core in the reactor, the cold clean excess reactivity shall not exceed 0.04 (0.5) All reactor cores used shall be such that they must be subcritical by at least 1% with the least reactive element withdraw (0.5) Pool water temperature shall not exceed 150 degrees (0.5)

QUESTION K.11 (1.50)

WHAT are the consequences to a fuel loading procedure if the detector is too close to a neutron sourc (1.5)

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L .- ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS, PAGE' 16 QUESTION L.01 (3.00)

FILL in the blanks in the following statements with the proper term l (according to the Operating Procedures) selected from the listing i belo )

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Assistant. Director Senior Reactor Operator Reactor Operator The , under the is responsible for the operation.of the reactor according to the approved operating procedure (1.0) i For.a given shift, the is designated by and reports directly to the . (1.0) { The or the is authorized to make minor changes to the operating procedure (1.0)

QUESTION L.02 (1.25)

ANSWER TRUE or FALSE if each of the following ABNORMAL conditions requires a reactor shut down or a reactor scra Consider each independentl (1.25) regulating blade sticks high magnet current reading, > 430 ma stack monitor reading low startup counter sticks high conductivity alarm on delay tank QUESTION L.03 (2.00)

According to tne Operating Procedures, the SRO has several post-scram responsibilities and options. NAMEfour(4). (2.0)

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QUESTION L.04 (2.25) An ex)erimenter calls to say contents of an irradiated vial las leaked onto him. WHAT basic immediate action should be take NAME two (2). (1.5) HOW would the reactions be different if the radiation monitor at the rabbit receiving station alarme (0.75)

QUESTION L.05 (2.00)

Assume you are emergency coordinator. WHAT two (2) conditions must exist for you to authorize re-entry into a radiation area? (2.0)

QUESTION L.06 (1.50)

According to the RINSC Technical Specifications, at WHAT three (3)

times is the SR0 required to be at the facility? (1.5)

i QUESTION L.07 (3.00) HOW is the facility notified of an off-normal condition after working hours? (1.0) SPECIFY four (4) off-normal conditions that should trigger this notificatio (2.0)

QUESTION L.08 (1.00)

Assume two (2) Remote Area Monitors are alarming and you are the i SRO on shift. WHAT is your response assuming no other procedures 1 have been initiated? GIVE two (2). (1.0)

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' ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 18 QUESTION L.09 (1.50)

ANSWER TRUE or FALSE relative to emergencies at RINS The Emergenc3 Coordinator has the authority to initiate recovery operation (0.75) The Emergency Coordinator must have the concurrence of the Emergency Director to terminate an emergency classificatio (0.75)

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QUESTION L.10 (2.50)

You are on shift SRO at 2 a.m. and the operator receives a phone call of a bomb threat, WHAT five (5) actions must be

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taken? (2.5)

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~ REACTOR THEORY PAGE 19 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.

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ANSWER- H.01 (1.00) ,

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N = (10) (e 90 sec/30 sec) = (10) (e**3) [+0.5]

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.AND N = (10) (20.1) = 201 N cm**-2 sec**-1 [+0.5]

REFERENCE i 'Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, p. 11 ANSWER H.02 (2.00)

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[N N 'N j ] Distribution C Startup

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Distribution End --

At Startup

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+1.0; if neutron flux at end is greater than at startup j

_+ for shape of curves relative to fuel distribution !

REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 197-19 .

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- REACTOR THEORY- PAGE 20 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, . ANSWER H.03 (1.50)- .

conduction through the fuel conduction through the cladding .

natural convection away from core to ultimate heat sink (pool)

[+0.5] each A ~ '" # " ' ' ' "" ' " "' ' ' ' ' ' ' ' " ' " ' " ' ' ' ~ ""'Y ?"'# ]

cor e o REFERENCE- J' < n. d n) lo::] n ) e r k" Q- [ o..c ~] Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. ANSWER H.04 (1.00)

i No difference [+0.4] because the reactor is below the power level at which the power coefficient begins adding negative reactivity

-[+0.6].

REFERENCE Rhode Island: Safeguards Report, 1962, p. 4 , ANSWER, H.05 (1.00)

a peaking of neutron flux [+0.75] which could result from a partially dropped control rod [+0.25] --0R-- a faulty experimental rig near fuel which moves to make a positive reactivity change [+0.25], et [+1.0] maximum i

REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 4, p. 87.

l j

!

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i

- - _ _ - _ _ _ - _ - _ _ _ - _ .. (

_ _ _ _ _ _ _ _ _ _

. '.* ,

. .

- REACTOR THEORY PAGE 21 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER H.06 (1.00) False (the Doppler effect is provided by U-238 atoms primarily) [+0.5] True [+0.5]

REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, p. 190 Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, p. 7 ANSWER H.07 (2.00)

As pool water temperature increases, the water becomes less dense (reducing the atom density of hydrogen H2/cc) [+0.5]. This results in less thermalization (and ;;he neutron spectrum hardens) [+0.5].

Neutron leakage thus increases [+0.5], thereby reducing net reactivity [+0.5] .

REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. i ANSWER H.08 (2.00)

Due to a loss of prompt neutrons E+0.5] an immediate substantial (>85%) drop in power occurs [+0.5?. After the initial drop the power level will continue to drop with a -80 second period [+0.5]

due to the effects of delayed neutrons [+0.5].

REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, p. 13 _ _ _ _ _ _ _ _

-__ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . _ _ - _ _ _ . _ _

_ , . .

ld * *, a

' '

'

H.- REACTOR THEORY PAGE 22 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, '

ANSWER H.09 (3.00)

No Source With Source K-eff Present- Present

........ ......... ........... <1 . 1 . >1 [+0.5] each REFERENCE- Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 81 and 8 ANSWER H.10 (1.00)

i CR1/CR2 = [1 - (k2)]/[1 - (k1)]

100/150 = - (1 - k2/(1 - 0.95)

k2 = 0.967 [+0. 5)

Change in reactivity = (1 - k1)/k1 - (1 - k2)/k2

= k2 - k1/k2 x kl

= 1.8% [+0.5)

REFERENCE Rhode Island: Equation Shee . Rhode Island: Reactor Operator Study Handbook, ORNL-TH-2034, Vol. 3, p. 13 .

I

!

_ _ __ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

__ - _ . .-_ ____ _ _ _ - _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - _ _ _ _ _ _ _

_ _ _ _ _ _ _ - _ -

,. '.. ..

,

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' REACTOR THEORY PAGE 23

. ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER H.11 (2.00). . to overcome negative power coefficients 'to overcome neutron losses (poisons / leakage) to give operating flexibility rate; (i.e., permit power increases at a reasonable rate) to_ compensate for fuel burn-up to accommodate negative reactivity of experiments Any four (4) -[40.5] each, +2.0 maximu REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 55 and 5 ANSWER H.12 (1.50)

The reactor would respond faster [+0.5], because of the shorter average neutron lifetimes [+1.0].

REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 134-13 .

- _ _ _ _ _ - . - - _ - - - _ - ~ _ _ _ . _ _ _ - - _ _ - - -

- - _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _

.

. . .

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, REACTOR THEORY PAGE 24 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER H.13 (1.00)

Production xenon is produced as a direct fission product during operation

[+0.25)

xenon is produced from the decay of another fission product

'

I-135 (5.6f; of all fission products) generated during reactor operation [+0.25]

Removal xenon-135 is removed by absorption of thermal neutrons [+0.25]

xenon-135 is removed by its own radioactive decay [+0.25)

REFERENCE NUS, Vol. 3, p. 10, 2- .

A

_ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ __ _ __

_ _ _ _ _ _ _ - - _ - _ _ _ _ _ _ _

F

~ RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 25 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER I.01 (2.00) . theindividual(s)-utilizing. radiation the SRO on duty theRadiationSafetyOfficer(R50) the Radiation Safety Officer (R50)

[+0.5]each REFERENCE Rhode Island: Radiation Safety Guide,Section I, paragraph 3.C, parts a., c., and d, p. . Rhode Island: Technical Specifications, Section J, paragraph 3, part b, p. 2 ANSWER I.02 (1.50) Under N0 circumstances shall materials be disposed of by burial or by incineratio [+0.5] Use approved drains and the laboratory sink syste [+0.5]

Convert to solid and release to waste disposal contracto [+0.5]

REFERENCE Rhode Island: Radiation Safety Guide,Section IV, p. 1 . Rhode Island: Radiation Safety Guide, Sections C1 and C2, pp. 18 and 1 *

l

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,

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.

' ' ' S RADI0 ACTIVE MATERIALS HANDLING DISPOSAL'AND HAZAR_D_S PAGE 26 ANSWERS -- RH00E ISLAND & PROV. P AEC-87/10/20-CLARK,. ANSWER I.03 (1.00)

. dose in mrem /hr [+0.25] at 3 ft [+0.25] time required for 1/2 of an isotope to be removed from critical organ (body is acceptable) [+0.25] by biological processes [+0.25]

REFERENCE Rhode Island: Radiation Safety Guide, Opening Statements, paragraph 2, p. 1 . Rhode Island: Radiation Safety Guide, Appendix F, Table ANSWER I.04 (2.00) more than 5 millirems /hr .5 millirems /hr more than 100 millirems /hr less than 2 millirems /hr

[+0.5] each REFERENCE Rhode Island: Radiation Safety Guide,Section V, paragraph C.2.a, p. 3 . Rhode Island: Radiation Safety Guide,Section III, paragraph D.I.a, p. 1 . Rhode Island: Radiation Safety Guide,Section V, paragraph C.2.b, p. 3 {

i

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-

3. .. .. .

~ RADIOACTIVE-MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 27 ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, !

ANSWE I.05 (1.50)

I 10 rad /hr x 1/10 x 1/10 x 1/10 = 10 mrad /hr [+0.5]

half value layer = 0.3 x TVL = 0.3 inch [+0.5] !

Therefore 3.3 inches of lead required [+0.5]

l REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, 1968, Volume 2, p. 10 ANSWER I.06 (1.00) ' DECONTAMINATE ANY VICTIM as thoroughly as possible [+0.5] ContaminatedCLOTHINGSHOULDBEREMOVEDIFPOSSIBLE[+0.5] d4 M '" "'"" "' " " " " 6 b## 3 REFERENCE Rhode Island: Radiation Safety Guide, 1954,Section VIII.A, p. 4 ANSWER I.07 (2.00) The calculated dose rate may be LOWER [+0.5] than the actual dose rate when close to the source because the source will show characteristics of a plane source rather than a point source [+0.5]. The calculated dose rate may be HIGHER [+0.5] than actual dose rate when far from the source because the inverse square law does not include a factor for attenuation by air [+0.5].

REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Volume 2, pp. 123-12 .

______._.m._._._-_.._.__.________m_____ . _ _ _ _ _ - .__ _ _ ____.m _ _ _ - _ _ - _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ - _ = - - - - . - _ _ - _ _ _ - - _ _ _ _ _ - . - _ _ .

_,

'*

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* RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 28 ANSWERS'-- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, )

.

ANSWER I.08 (3.00)

L At the bridge monitor [+0.5], radioactivity in the pool (such as N-16, leaking fuel elements or experiments, radioactive 4 crud, etc.) has developed and exceeds the technical i specification of < 10 mrem /hr at 1 meter above the surfac [+0.5]

, At the biological shield between beam port and thermal column l

'

[+0.5], protection of personnel is inadequate from plugs, shutters, and doors not in place [+0.5]. Above storage container for new fuel elements [+0.5], elements are not in place and may be in a critical array [+0.5].

REFERENCE Rhode Island: Technical Specifications, Section IC, paragraph 3, p. 2 . Rhode Island: Safe Guards Report, p. 3 ANSWER I.09 (1.00)

The sampling point for normal operation is stack air sampling point in horizontal duct inside the EPZ [+0.5]. The sampling point during emergencies is un stack DOWNSTREAM of air clean-up system

[+0.5] (of absolute t.nd charcoal filters with the assumption made that the filters are effective).

Op r , ea n /)ps esor12. ().o 0) A ' ' " ' T' "' ' ' ' ' ' " W REFERENCE

.,, .

,, [p g , , ,. m ,, g ,,,, ,) Rhode Island: Emergency Plan, Appendix con m e d ,

ANSWER I.10 (2.00)

Whole Body: 3 rem / quarter [+0.5], not to exceed 5 (N-18) [+0.5]

where N = workers age Extremities: 18.7 rem / quarter- [+0.5]

Skin: 7-1/2 rem / quarter [+0.5] )

)

.

_ _ . - . - - - - . - _ _ - _ _ _ _ . - - . - - - _ - - \

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' ' RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 29 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, .

REFERENCE Rhode Island: Radiation Safety Guide, Appendix \

ANSWER I.11 (1.50)

Dose in R/hr at 1 ft = 6 CE Dose in R/hr at i ft = 6 (1/3) ti-2ft (acceptable value for 5 /2 gamma energy 1.25 +/- a

= tift R/h at 1 ft 0.05 Mev) {

[+0.5] -

Dose in R/hr at 5 ft - D/2.5 (distance)**2 5, / 2-

= t d R/hr/25 cc a/2I t te n

=NR/hr [+0.5] OR

=hhmR/hr zoo

= 40& mrem /hr [+0.5]

REFERENCE Rhode Island: Reference Sheet, Radiation Safety Guide, Appendix E, paragraph . Rhode Island: ORNL-TM-2034, Vol. 2, p. 5 ANSWER I.12 (1.50)

I [+0.5] each REFERENCE Rhode Island: Radiation Safety Guide, Appendix F, Table . Rhode Island: Safeguards Report, p. 5 _ - __-_-- -______ _ ____-__________________-___.---_______.-____ ______._ ______._.-----_-_.-__.-___ .______.._--_________-_-__ _ - --

- _ - _ _ - _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _

.;..

SPECIFIC OPERATING CHARACTERISTICS PAGE 30 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER J.01 (2.50) . Hi Temp - Primary Coolant Entering Core [+0.25]

Hi Temp

[+0.25 -] Primary Coolant Leaving Core [+0.25] - Reactor Trip Primary Coolant Low Flow Rate [+0.25] - Reactor Trip [+0.25]

Bridge Misalignment [+0.25] - Reactor Trip [+0.25]

Coolant Gates Open [+0.25] - Reactor Trip [+0.25]- the reactor scrams [+0.25]

REFERENCE l Rhode Island: Reactor Technical Specifications, Table F.1, p. 12.

l ANSWER J.02 (2.00) the evacuation horn blows the air conditioning and normal ventilation (fans) turn off the dampers on all ventilating ducts leading to the outside close l the building cleanup system air scrubber and fresh air blower l comes on l J

' Off Gas Blower and Rabbit System Blower have shut off

[ Any.four (4) [+0.5] each, +2.0 maximu l REFERENCE Rhode Island: Technical Specifications, K.3.b.(2), p. 2 . Rhode Island: Operating Procedures, p. 1 i

.

I

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,.

.. SPECIFIC OPERATING CHARACTERISTICS PAGE 31 ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER J.03 (3.00) reactor scrams [+0.5]

propane gas generator unit starts [+0.5]

automatic transfer switch operates [+0.5]

*' f#' 'O m[r nc'y 11ghts '+0. 5' Sv r4 e /"o b' /"" ' 2 '" "^ '" c auxi$iaryblower '+0. 5' M d d d '3 * N '2 e-btri4 ding cleanup is be/ f*0$J /e c'"'c b e e

/ tX (o r 19/t tf) tw To t/H F f > &0 REFERENCE h" ' '3 "'" ' T Jo k e' 0""" D 0 Rhode Island: Operating Procedures 10.lc,d, 10.2a.b, 10.3, pp. 10-1 and 10- ANSWER J.04 (2.00) shut down maintainedpower(CAF) maintained at power maintained at power

[+0.5] each REFERENCE Rhode Island: Operating Procedures, 8.2, p. 8- . Rhode Island: Technical Specifications, p. 1 .

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_ - _ _ ___ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . . _ - _ _ _ _ _ _ _ - _ . _ _ - - _ _ _ .

.. : .,

'~ SPECIFIC OPERATING CHARACTERISTICS PAGE 32 ANSWERS -- RHODE ISLAND &~PROV. P AEC-87/10/20-CLARK, ANSWER J.05 (2.50)

/cd bwett LEytt-O ,

.

fnw/UIJ ,

SM /PE fD 5)

'

/]m:.t - /Sg r /]s n l' f t p r L - D e u o, /2py - Lew a f- 0 -

4~ '

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..

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femN 7;,, a v r ,. *'^% i- , r, ( ~~

eni >> er \

. hWM'Y nyalp '

(0,y ) ( 0' 5 } y

!

s rga 3:

co.:)

r 3 Q,$^~

O f AS 30 JS /to /25 (s o

/Gise - / (25 REFERENCE Rhode Island: Reactor,0perator Study Handbook, ORNL-TM-2034, J

_ - _ - _ _ _ - _ _ _ _ _ _ _ . _ _ _ - _ - _ _ _ _ _ _ _ _ -

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[.:..

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'J . SPECIFIC OPERATING CHARACTERISTICS PAGE 33 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, Vol. 3, Reactor Physics, pp. 165 through 169.

l

'

ANSWER J.06' (2.50)

Pool inlet temperature increase raising pool temperature [+0.5] adding negative reactivity [+0.5].

Primary coolant inlet temperature goes up, alarm set point reached [+0.5].

Primary coolant exit temperature goes up to alarm pt [+0.5] .and then reactor scram set point [+0.5].-

REFERENCE Rhode Island: Technical Specification, p.12, Table F- . Rhode Island: Safeguards Report for Rhode Island Open Pool Reactor, paragraph 2.2.3, p. 2 ANSWER J.07 (2.00).

h=mCp(deltaT) [+0.5]

m = 1500 gpm x 8.345 lb/ gal x 60 min /hr [+0.25]

Cp = 1 BTU /lb-degree F [+0.25]

delta T = 9 degrees F [+0.25]

Thenh=6.76x10**6 BTU /hr [+0.25]

. 6.76 x 10**6 BTV/hr Q ............----------

[+0.25]

3.41 x 10**6 BTU /hr/MW h=1.98MW [+0.25]

REFERENCE Rhode Island: Safeguards Report, 1962, 3.2.2, p. 5 . Rhode Island: Operating Procedures, 1984, 8.1.2, p. 8- . Rhode' Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 4, p. 1 . Rhode Island: Reactor 0perator Study Handbook, ORNL-TM-2034,

,

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-- 1

.- (*. . . ,

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'* SPECIFIC OPERATING CHARACTERISTICS PAGE 34 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, Vol. 4, p. 64.

I ANSWER J.08 (1.50)

- False (control rod worth could change) True False (controlled by cleanup loop pump)

[+0.5] 'each REFERENCE Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Vol. 3, pp. 197 through 202.

l Rhode Island: Safeguards Report for the Rhode Island Open Pool

'

Reactor, Section 2,. paragraph 2.1.3, p. 7.

I Rhode Island: Safeguards Report.for the Rhode Island Open Pool Reactor, Section 2, paragraph 2.2.2, p. 1 _

ANSWER J.09 (1.00)

Forced coolant flow containing N-16 returning to the core is directed downward so that only by diffusion around the core cover plates can any of-this water reach the pool surface to contribute to the dose rate at the surface. [+1.0]

REFERENCE Rhode Island: Safeguards Report, paragraph 3.1.1c, p. 5 ANSWER- J.10 (1.00) True [+0.5] False [+0.5] (the flow through fuel element has a Reynolds number > 6400)

REFERENCE Rhode Island: Safeguards Report, paragraph 3.2.1, p. 5 .

- _ - _ _ _ - _ - _ _

.

)..

FUEL HANDLING AND CORE PARAMETERS PAGE 35 ANSWERS .- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, A ANSWER K.01 (1.50) Move the linear level safety channel compensated ionization chamber from the corner post [+0.5] and hang it in the grid Ir box above position B-1 [+0.5]. one [+0.5]

REFERENCE

' Rhode Island: Operating Procedures, 2.2.9, p. 2- . Rhode Island: Technical Specifications, Operating Limitations, '

paragraph 2.12, p. 2 ANSWER K.02 (2.50)

See Figure on next pag No. Fuel Count Elements Rate-CPS 1/M

........ ........ ....

.

0 10 1.00 1 13 0.77 7 17 0.59 13 25 0.40 19 50 0.20 REFERENCE Rhode Island: Operating Procedures, 2.2.9.e, p. 2- \

ANSWER K.03 (1.50) .05% delta k/k [+0. 5] By using new or irradiated fuel elements in which the effect of xenon poisoning has sufficiently decayed (to 0.05% delta k/k or less). [+1.0]

~

REFERENCE Rhode Island: Operating Procedures. 2.1, p. 2- .

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - - _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . . . . .

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ANSUER K.02

. . SECTION K RHODE ISLAND

.

C/20 CRx 7A'f"'

l0 y < {. oao)

.

. 71

. , Tant Pts on Curve

'3" f0,20)

7#/f

,0Vf (LO g

.zs \ x T/+c N/r-lfD,2d)

N 5 /0 /7 f. 0 2 C'

D Cf f4 LJ Mih*H f',

,r ui n ~ > (. s >

kia - 25 tz.c m a n ic (0,5)

p,. ,, , , ,),,.~,,a ,4,,,, c - z , , , , , ye,

, fr/2Arcrt ///ve;y j p rF 7/ F l 2 i f j rpirn7.) /Z f tTo /2.! /> f5" }

I

.

- _ - _ _ _ - _ _ _ t a n ot anw . <,,n }

. .

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FUEL HANDLING AND CORE PARAMETERS PAGE 36 ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER K.04 (1.00) For critical experiments the core cooling system should NOT be operating [+0.5]. The water level in the pool must be at least high enough to permit shock absorber action for falling control blades

[+0.5].

REFERENCE Rhode Island: Operating Procedures, 2.2.1, p. 2- ANSWER K.05 (2.25) % delta k/k [+0.75] .8 % delta k/k [+0.75]

3% delta k/k [+0.75]

REFERENCE Rhode Island: Operating Procedures, paragraph 3, p. 3- . Rhode Island: Operating Procedures, paragraph 4, p. 4-1.

l ANSWER K.06 (2.00)

All operations pursuant to the preparation and shipment of spent fuel require that the BUILDING CLEANUP SYSTEM [+0.5], BUILDING VENTILATION SYSTEM [0.5], AREA MONITORS [+0.5] and AIR MONITORS

[+0.5] be operabl REFERENCE Rhode Island: Operating Procedures, 11, p. 1 .

- - - - - . - - - - - _ _ _ _ _ _ - ~ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ , _ _ _ _

.~...

'

- FUEL HANDLING AND CORE PARAMETERS PAGE 37

ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWE K.07 ~(1.25)

to avoid contaminating hands [+0.5]

'

to avoid fingerprints [+0.25] on the plates that could possibly affect heat transfer characteristics [+0.5]

REFERENCE 1. - Rhode Island: Operating Procedures, 2.2.2, p. 2- ANSWER K.08 (2.00) only one fuel assembly moved at a time the number of' assemblies per storage rack is limited 3.- adequate spacing between racks'is required- each rack shall be covered with a cadmium lined aluminum cover

[+0.5] each REFERENCE Rhode-Island: Technical Specifications, pp. 17 and 3 .

- _ _ _ - _ _ _ _ . _ _ . . - . _ _ . _ _

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- FUEL HANDLING AND CORE PARAMETERS PAGE 38 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER K.09 (3.00) Absolute worth of any single experiment or the combined worth of connected or otherwise related reactivity that could result in a simultaneous addition shall not exceed 0.00 . For single or combined connected experiments NOT RIGIDLY FIXED in place, their single or combined worth shall not exceed 0.000 . Experiments shall not be installed so that it could shadow nuclear system monitor i Free movement of control rod shall not be compromised by interference from installation failures of experiment . Fuel element damage must not result if installation of experiments fail . No experiment shall permit materials to contaminate reactor pool water to cause corrosive action on reactor components OR that can credibly result in an explosio Any four (4) [+0.75] each, +3.0 maximu REFERENCE Rhode Island: Technical Specifications, p. 2 ANSWER K.10 (1.50) True [+0.5] False [+0.5] (the most reactive element withdrawn AND the servo regulating element must also be withdrawn) False [+0.5] (must not exceed 130 degrees F)

REFERENCE Rhode Island: Technical Specifications, pp. 27 and 2 .

m______ _ _ . . _ . _ - _ _ . _ _ _ _ _ _ _

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' FUEL HANDLING AND CORE PARAMETERS PAGE 39 ANSWERS -- RHODE ISLAND & PROV P AEC-87/10/20-CLARK, ANSWER K.11 (1.50).

The source. output will dominate the shape of the.1/M plot [+0.5],

making it concave downward [+0.5], overestimating critical mass '

'[+0.5] resulting in a non-conservation [+0.5] estimate of fuel required for criticalit Any.three (3), +1.5 maximu REFERENCE 1. . Rhode Island: Reactor Operator Study Handbook, ORNL-TM-2034, Volume ,

e I

_ _ - _ - - _ - _ _ _ - . _ _ _ _ _ _ _ . . _ _ . _ _ _ . - _ _ _ _ . . - _ _ _ _ - _

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' ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 40 ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, I l

ANSWER L.01 (3.00) ) Reactor Operator; Senior Reactor Operator Senior Reactor Operator; Assistant Director, on, 2t#'7#d O' /

a, g )].,,7,, h Director; Assistant Director j

[+1.0] each REFERENCE Rhode Isisnd: Operating Procedures, Section 1, " General,"

paragraph 1.14, p. 1-3; paragraph 1.4, p. 1-1; and paragraph 1.31, p. 1- ANSWER L.02 (1.25)

I

' False (switchtomanual,notifySRO) True True False (lower power, inform SRO, check drive) True

[+0.25] each REFERENCE Rhode Island: Abnormal Procedures, Nos. 11, 5, 6, 15 and 3.

.

!

l \

l l - !

l i

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, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _

. .- ..

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- ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 41 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER L.03 (2.00) .

.1. - Assure actions required for the safety of personnel or protection of equipment have been take . Determine cause of scra . Assure correction of the abnormal conditio . Assure applicable portions of the checkout procedures are repeate . ' Authorize a startup under his (SR0's) direct supervisio . Assure that actions taken are recorded in the lo Any four (4) [+0.5] each, +2.0 maximu REFERENCE Rhode Island: Operating Procedures, Section 9, paragraph 9.2, p. 9- ANSWER L.04 (2.25) rinse contaminated skin area [+0.75], call-wait for health physicist to arrive [+0.75] leave the area immediately [+0.75]

REFERENCE R'hode Island: Operating Procedures, Section 12, paragraph 12.4, p. 12- ANSWER L.05 (2.00) 'an immediate need exists to save a life [+1.0] the emergency director is not available [+1.0]

I REFERENCE Rhode Island: Emergency Plan, paragraph 3.1.1.2, p. .

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L.. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 42 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, ANSWER L.06 (1.50) l initial. start up and approach to power . recovery from an unplanned shutdown or power reduction 3 refueling

[+0.5] each REFERENCE Rhode Island: Technical Specifications, J.3.b.2, p. 2 ANSWER L.07 (3.00) By an alarm [+0.5] at a continuously manned control station in Providence, Rhode Island. [+0.5] . a fire in the reactor room a fire in other than the reactor room a decrease of 2 inches in reactor pool water level a power failure in the reactor building an alarm condition from the radiation monitors with readings in the control room an alarm condition from any other selected feature Any four (4) [+0.5] each, +2.0 maximu REFERENCE Rhode Island: Technical Specifications, paragraph 2.b, p.10 and paragraph f., p. 29.

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$ ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 43 ANSWERS -- RH0DE ISLAND & PROV. P AEC-87/10/20-CLARK, R.

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ANSWER L.08 (1.00) shut down the reactor conduct or direct a survey of the area replace any faulty monitor with portable instrumentation-Any two (2) [+0.5] each, +1.0 maximu REFERENCE Rhode Island: Abnormal Procedures, No. 1 ANSWER L.09 (1.50) True [+0.75] False [+0.75] (the Emergenc initiate recovery operations)y Coordinator has authority to REFERENCE Rhode Island: Emergency Plan, Section 3, paragraph 3.1.1, pp. 4 and .

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ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 44 ANSWERS -- RHODE ISLAND & PROV. P AEC-87/10/20-CLARK, R.

ANSWER L.10 (2.50) notify the Director, Assistant Director or Reactor Supervisor i 1 notify the NRC l shutdown the reactor evacuate facility notify Site Security (campus police, etc.) notify Narragansett Police and State Police arrange for search of facility buildings notify FBI Any five (5) [+0.5] each, +2.5 maximu REFERENCE Rhode Island: Emergency Plan Implementing Procedures, Appendix .

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. .....................__........___..________ ..................__ ....____ EQUATION SHEET

..._____....______..___..._____......____..___......___....___..............

. .

Where mi = m2 l (density)1(velocity)1(area)1 = (density)2(velocity)2(area)2

_______ ...........__............______ .....____.. ___.........._______....

PE + KE +P V where V = specific KE=*{2 PE = mgh l l 1 1 = PE +KE 2 2+P Y22 volume P = Pressure

.....__ ._____............._______.____________....._ .____....._________ Q=mcp(T out -Tin) Q = UA (T ave -Tstm) Q = m(hl-h2)

________....__........... __..__....._______ .._____..._________..........__

P = Po10(SUR)(t) P = Po et /T SUR = 26.06 T = (B-p)t T p

..................................__________......__ ......__________.......

delta K = (Keff-1) CR1(1-Keff3) = CR2 (1-Keff2) CR = S/(1.Keff)

(1-Keff1) (1-Keff) x 100%

M= 1-K SDM =

K eff2 eff

.....________...___...........__....__......______________......._________ decay constant = In (2) = 0.693 A 1 = Ag e-(decay constant)x(t)

t t 1/2 373

..__.....__...........................__..____.........................__ Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 f t3 = 7.48 gallons 1 hp = 2.54 x 103 Btu /hr Density = 62.4 lbm/ft3 1 MW = 3.41 x 106 Btu /hr Density = 1 gm/cm3 1 Btu = 778 ft_lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 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-sec2

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t N = No e /T Dose (D) in R/hr at l' , D = 6 CE [C in curie, E in gamma energy in MeV]

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EXAM REVIEW Question N Facility Comment Examiner Comment / Resolution H.03 As stated, this cuestion will Agree. Answer key changed prompt the candic ate into prior to grading to provide a an explanation of the primary description of primary-secondary and secondary coolant loops cooling tower syste with the ultimate heat sink being the atmosphere through

.the cooling tower. A correct description-is an acceptable answe H.07 An alternative acceptable Disagree. Answer key not answer is "so as to limit change the power level reached during the temperature increase associated with an excursion reactivity by(because ofdecreasing temperaturecoefficient)".

H.12 The stated betas are not Comment is correct. Answer correct. This would not, key not change however, necessarily affect answe I.05 There is a typographical Comment is correct. Answer error in the first line of key not change the question. " Gamma should read " gammas."This protons" is probably not serious enough to affect the candidate's respons I.09 The correct answer is "because Agree. Answer key modified to the flow rates are different include this comment, as an under these conditions." option, prior to gradin .11 There is an error in the Agre The answer key corrected answer key. The gamma rays prior to gradin from Co60 are each emitted per disintegratio Therefore, E in the equation i is the sum of 1.17 and 1.33 !

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Question J N Facility Comment Examiner Comment / Resolution )

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I.1 There is no correct answe Disagree--Answer key not l change J.03 The building cleanup blower Agree. Answer key changed for is not energized following grading to reflect this a loss of normal powe information which was not ONLY if an evacuation button available (or not noted) during has been pressed. Other loads exam preparatio automatically energized are the sump pump, chem lab blower, reactor room electric door lock, air compressor to valves and several emergency duplex outlet i

J.06 The word "is" in the first This typo pointed out during line should be "if". An exam to candidate. The additional key change (in additional key change; namely Answer Key) is "a decrease a decrease in reactor power, in reactor power." is not an additional key change but an alternative way to note .

" negative reactivity added."

Answer key not change J.09 It should be noted that this Disagre Reference material reactor has never operated does not note the operational with cover plates over the conditions, only the design core. An acceptable answer feature. No change to answer to this question is "down ke draft cooling and the depth of the pool."

K.01 Position B-1 is an appropriate Disagre Reference material position for the critical is explicit as to position B-1 experiment used as an example being preferred and not merely in the operating procedure an optional location. Answer for an intended, different, key not change final core configuration the appropriate position may be at a different locatio i e

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Question N Facility Comment Examiner Comment / Resolution ,

K.02 The first line of the question Agree. Answer key change (based on the answer) should read "The initial count rate for a RINSC reactor -

core with N0 fuel ..." A correct answer which ignores the first sentence is acceptabl K.0 This question is ambiguous Comment has meri However and does not lead to a wording for the question quoted discussion of the performance directly from reference material, of critical experiments l with a dirty (Xe containing) Answer key not change core. An acceptable answer is "4.7% delta k/k."

K.0 Based on the answer to Answer to K.03a not change K.03.a., an acceptable answer Answer to K.03b not change is "by rod calibrations using inhour method."

L.0 An acceptable answer is Valid commen Answer key

" Reactor Operator" and " Senior change Reactor Operator."

L.04 This question is confusing Disagree. Answer key not ,

because the candidate knows change that an experimenter at the pneumatic irradiation facility can only communicate with the reactor operator in the control room. Therefore, answer contains the directions most likely provided by operator, not senior operato .c 'i ; '? ,

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Question N Facility Comment Examiner Comment / Resolution L.0 While it is true that the Disagree. No change to answer Emergency Coordinator does ke have the authority to initiate recovery operations, the authority is severely limited as described on pages 4 and 31 of the emergency pla Therefore, false is also an acceptable answer.

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v t e Inspection Report - Rhode Island Atomic Energy Commission - 1987001
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \|
1987 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle Security Operator Exams Emergency Planning Other

IR 05000193/1987001

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