IR 05000134/1987002
| ML20245B970 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 06/18/1987 |
| From: | Coe D, Collins S, Keller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20245B958 | List: |
| References | |
| 50-134-87-02OL, 50-134-87-2OL, NUDOCS 8707010499 | |
| Download: ML20245B970 (18) | |
Text
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i ENCLOSURE !
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
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REQUALIFICATION EVALUATION REPORT (
l Evaluation Report No. 50-134/87-02 (0L)
Facility Docket No. 50-134
Facility License No'. R-61 i
Licensee: Worcester Polytechnic Institute 100 Institute Road Worcester, Massachusetts 01609 Examination Date: May 11, 1987 d!/f 87 Chief Examiner:
[Y JAC_. -
0. Coe, Lead Reactor Engineer-date
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i Reviewed By:
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J kW d
ffP7 R. Keller, Chief, Prt ects Section 1C dat/e /
Approved By:
M 6 ltkT
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M J. Co11fns, Deputy Director date Division of Reactor Projects
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Summary _: The NRC audited the facility licensee's administration of its
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May 11, 1987 requalification written examination to two 'out of three licensed-
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operators.
Fifteen percent of the examination questions were NRC supplied questions, and both examinations were reviewed for adequ' ate facility grading practices.
Both operators achieved a passing overall score and_ facility-administration of this examination was determined to be satisfactory.
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8707010499 870625-gDR ADOCK 05000134 PDR
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t DETAILS 1.
EXAMINATION RESULTS:
R0 SRO TOTAL Pass / Fail Pass / Fail Pass / Fail Written Examination 1/0'
1/0 2/0 Evaluation of Facility Written Examination:
Satisfactory Grading: Sati sfactory 2.
SCOPE:
The facility prepared requalification written examination was reviewed by the NRC prior to its administration.
The examination was administered to one senior operator and one operator.
The NRC was present to monitor the proctoring methods used by the facility.
Fifteen percent of the total examination value was NRC written to provide an independent check on examination validity. The NRC reviewed both facility graded examinations for adequate grading practices.
3.
WRITTEN EXAMINATION:
The facility written requalification examination consisted of a 52 point examination comprised of seven sections.
Examination content included
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both R0 and SR0 level questions.
Its format was identical to an NRC non power reacter RO written examinati.on. The review determined that the facility examination was adequate to determine individual as well as generic knowledge deficiencies.
However, the NRC added nine points worth of questions, increasing the total point value to that of a standard NRC requalification examination.
4.
CONCLUSIONS:
This auait found that the facility properly wrote, administered, and graded a satisfactory requalification written examination for its licensed operators. Operator performance on NRC substituted questions was not significantly different than that on facility writtan questions, thus providing an independent check on the validity of the examination results. The facility commitment to continue to administer its requali-fication examinations on a proctored basis and in accordance with the
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NRC policy expressed in Generic Letter 83-17 is noted and will be subject to future inspection and audit.
Since all operators fully passed the-examination, it can be concluded that previous unproctored examinations did not adversely affect the overall knowledge level of the licensed operators.
Attachment:
1.
May 11, 1987 Written Requalification Examination and Answers
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ATTACHMENT 1
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WPI OPEN P0OL TRAINING REACTOR Requalification Exam Category A.. Principles of Reactor Operation l
1..How long will it take to reach 1 kw from a power of 1 w with a period of 30 seconds?
(1)
d 2.
a)
Identifies three properties that make a. good moderator (1)
b) How does moderator ' differ from reflection? (. 5)
3.
a)
What would be the new value of Keff if a positive. reactivity of
$.25 was added to the just critical WPI reactor? (1)-
b) Given r = 0.08 sec~1land S = 0.0055, what would the resulting period tra with this reactivity addition?
(1)
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Explain _ the difference between prompt and delayed neutrons.
(1)
S.
What causes the WPI pool temperature coefficient to be negativc<t (1)
6.
Draw the log.N recorder normal trace for the following:
a) Operatin'g level at 1 kw and a scram occurs (.5)
b) Approaching and leveling at 500w and then an experiment with negative reactivity is inserted into the' core and the reactor is again leveled (without anticipation of the negative insertion on the operator's part).
(. 5)
j 7.
Explain the effect on reactor puwer of the beam port filling with water with the reactor critical.
(1)
8.
What is meant by a stable period? (1)
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Category B.
Features of Facility Design
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What is the maximum allowed withdrawal speed of j
a) Safety blades?. (. 5)
b) Regulating blade?
(. 5)
2.
Explain how the safety blades are scrammed, Include maximum time j
allowed for insetion of the first 24 inches...(1)
3.
List the. following pool water limits:
a) pH '(.5)
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b) Resistivity (purity)
(. 5)
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c) Activity (. 5) -
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d) Operation temperature (.5)
el Amount of water above the core (. 5)
Br',efly describe a fuel element (dimensions not required).
(1)
Where'are the three area radiation monitors located, what is a typical'
5.
10 kw reading; and what is.the alarm. setting of each? (1)
6.'a)
What is the composition of the neutron source?. '(.5)
b) What i:s the purpose of the neutron source? (. 5)
7.
Give the values for; a) Void ccefficient of reactivity (. 5)
b) Temperature coefficient.of reactivity (. 5)
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I Category C.
General Operating Characteristics What must be the minimum regulating blade worth if it is designed to
.j 1.
hold the reactor suberitical ua44s hil three safety blades withdrawn?
wi%
(1)
2.
What is the' minimum number of instrumentation channels requireo to obtain subcritical multiplication plots during a critical experiment of a new core configuration?
(1)
3.
Name three important cautions for experiments (1.5)
4.
What is the normal flow rate through the demineralizer pump?
(1)
5.
Describe the beam port.
(1)
What are the types and ranges of the followingIdetectors:
a) Startup channel detector (. 5)
b) Log N period detector- (. 5)
c) Linear safety channel detector _( 5)
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Category D.
Instruments and Control 1.
Sketch blar.k diagrams for the following:
a) Startup channe?
(1)
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b) Log N period (1)
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c) -Safety Channels 1 & 2 (1)
2.
Identify the three limit switches associated with the drive mechanism -
for a control blade as to their purpose, location of indication and
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control function (if any).
(1. 5)
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3.
Explain the principle of operation of a compensated ion chamber.
(1)
Name 4 conditions that cause the control blade drive motors to be
. interlocked against withdrawal of blades.
(2)
5.
What is the difference between a fast and a slow scram? -(1)
Category E.
Safety and Emergency Systems 1.
Give 6 reasons for a relay scram.
(1. 5)
2.- Give 2 reasons for an electronic scram.
(1)
3.
While operating at full power, a loss of all electrical power to the facility occurs. What automatic action (s) occur and how is. core cooling maintained?
(1)
List 6 conditions tnat will activate a panel alarm but not a scram at the WPI reactor console.
(1. 5)
)
5.
Two safety system functions may be bypassed.
Identify them and the conditions for each that must be satisfied in order to bypass.
(1)
Category F.
Standard and Emergency Operating Procedures 1.
If one of the safety blades is to be removed for maintenance, what must first be done to the core? (1)
2.
When more than one grid position is involved in a loading change, what physical evolutions does the core experience and what ' calculations are made during the alteration and subsequent reloadir,9? (1. 5) -
3.
What extra procedures / actions are necessary when operation above 1 kw-is planned? (1)
What steps must be reactor operator take while evacuating in the case of an evacuation alarm? (1)
.5.
Now often are the following measurements / procedures' performed?
a)
Excess reactivity measurement (. 5)
b) Reactor power level calibration (.5)
c)
Area monitor calibration. (.5)
d) Drive maintenance and inspection (.5)
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Category G.
Radiation Control and Safety
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1.
a) What is the normal maximum permissible dose per quarter? (. 5)
b) What is the maximum NRC permissible dose per quarter? (. 5)
c)
What is the once-in-a-lifetime dose and under what conditions can
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one receive it? (. 5)
j 2.
Explain the difference betwen the units of Curies, Roentgens and Rems.
k ( 1. 5)
3.
Explain why the following statement is true:
" Alpha radiation poses no i
serious external radiation hazard to humans but it is one of the most serious internal hazards."
(1).
4.
A point source with a half life of 5 minutes has a dose rate such that a high radiation area exists up to 1 meter away.
)
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a) How long do you have to wait until the boundary at 1 meter is considered the outer edge of a radiation area? (1)
b) How close to the source does a high radiation area exist at this time?
('1)
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p f)fC Ac&nbw fo WPI requal w,a id
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l DUE.ST!ON B.Ol (l.00)
What design f eat ures are pr ov i deci to assure SPcur i t v for any fuel Plements-not loaded in the reactor c or e7 QUESTION C.01 (2.00)
Technical Speci f i cati ons. requi r e that
'ri o e>' p er i men t shalI tm i n s,t a l i ed ' i n the reactor in such a rnanner that it could shadow the nuclear 1nstrumentation.
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a.
Explain what is meant by " shadowing."
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b.
Why is this undesirable?
DUESTION D.07 (1.00)
What is the function of the " trip mixer",with respect to the reactor safety. l1 circuit 7
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i OUESTION E 06 (2.00)
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f ea C t O'
si a4 f may nia n t ia i ) / set-of4 the w*'er w,'C 4 btate twe t2 w a y y.
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l evacuation alarm,
QUESTION F.0?
(l.00)
In. order to protect the public health and.riafety,'a faci 3ity licensee may take reasonable actlon which departs from.the Technical. Specifications or license conditions under emergency conditions. Who may authorize this
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action'
t DUEET]ON G.06 (2.00)
Give the types'and ranges of the portable survey iristruments that must be located at the facility to meet Technical Specification requirements.
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DATA SHEET NEUTRON Fwx Dose EourvAuvrs Hunse on e
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D* = 10 8 SEC A
7.5 24 x to*
to 24 x 1o *
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t Answer Key A.
1.
1000 w = 1 e T/T (30 sec) in 1000 = T
207 sec = T i
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2.
a) small atomic wt.
large scattering cross sect.
small absorption
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chemically stable single phase b) moderator--shows down (thermalize) neutrons in core to reduce energy.
relector--reflect neutrons that have escaped core back. into Core.
a)
p=K
e f f-1/Keff K
= 1/.2 5(.006 5)-1 = 1.0016 eff f
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b)
l + % 7'
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Prompt neutrons are released during the fission process with virtually no time delay. Delayed neutrons appear later as decay imissions of certain radioactive fission fragments.
5.
The WPI core is undermoderated, so any decrease in water density with an increase in temperature, adds negative reactivity.
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6-n.
1.
0A h
/ t
So*W Uffbf'
lkw goo w 7.
Will add some positive reactivity,.but most'probably will be negligible.
8.
When all of the delayed neutron effects are consistent with the
flux level, the period is constant with a given reactivity,. there--
fore the.' period 'is s' table..
B.
1.
a) 7.5 inches / min, b) 4 inches / min.
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2.
During a scram, electronic or relay, the current in the magnet.
attached to the blade decays away, dropping the blade into the co re. Maximum time allowed for decay + 24" insertion = 600 msec.
3.
a)
<8,
>6 b) > 5 x 105 G-cm
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c)
<10-5 pCi/ml
d)60-100 F e)
10 ft..
4 93% enriches, Al clad plates type 1-10 plates /elem.
i type 2-18
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type.3-10 8 removable
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5.
above pool, 25 mR/hr, alarm - 50 mR/hr ther' al-col., ~ 1. 5 mR/hr, alarm -- 20 mR/hr -
m beam port, ~ 3 mR/hr, alarm - 20 mR/hr-7-
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6.
a)
Pu-Be
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b) provide indications of neutrons' for. start up channel and used during checkout to check linear safety channels and period on in N channel.
7.-
a)
-2 x 10-3 AK/% void
'b)
-2 x 10-5 AK/ F
-1 C.
1. 'if maximum loaded excess reactivity - 0.5%
2.
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3.
moving experiments worth < $.25 double encapsulated if experiments could cause corrosion will not shadow instrumentation will not interfere with control blade will not release airborne contamination will not block coolant flow.
4.
10 gallons / min.
5.
6" dia. air filled port extending from face of biological shield'to face of core box with lead shutter and concrete plug or large removable shield.
6.
a) B-10 proportional background (or 3000 1pn) to about I watt
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b) compensated ion chamber.03 w to 15 kw c)
.03 w (or 1w.on chart)1to > 15.kw.
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upper limit switch - prevents withdrawal, "out" light near digicon.
lower : limit switch - prevents driving in, "in"
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magnet engaged switches - indication only, "ma9.eng'd" light near digicon..
.1 3., A CIC has two concentric ion chambers with opposite high voltage supplies. One chamber contains.B-10 and.' counting-gas, the outer-just counting gas.
An n, a reaction 1n the B-10 chamber gives a current component which 'a'dds to the y induced ccrrent. The other-
' chamber has only a current. induced by Ys..The two currents are subtracted. leaving only the neutron induced' current.
4.
< 3000 cpm on start up channel (B-10)
> 106 cpm, "
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reg. blade off in. limits scram condition normal rundown is activated during 8 second alarm horn.
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fast-electronic scram - bias reversed to interrupt current j
slow-relay scram - relay breaks circuit for connect.to. magnets.;
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E.
1.
>15kw on in N chart
<5 sec. period (now set at 7 sec.)
Hv failure manual scram upscale past 10 kw on safety channels a
disable in N amp.
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.HV monitor fails 2.
<3 sec. period
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>150% of scale on linear channels.(now set at.120%)'-
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magnet currents decay and blades = drop in, core cooled by natural connection
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'41Ar monitor above set point linear channels above 115% of. scale i
period ~'<15 sec blade disengaged j
master' switch to on position upstairs. rooms unsecured at power above 1 kw
area radiation (building evacuation)
<
5.
rod withdrawal interlock on startup channel if Keff <.9 (fuel unloaded partially)
pool wate'r level alarm if SR0 present.
F 1.
' fuel. completely unloaded 2.
core unloaded to less than 1/2 the estimated critical loading.
immerse multiplication curves plotted, 1/2 of each estimated step
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to critical loaded.
3.
upstairs rooms secured
)
41Ar monitor on noted in log book
open master power switch to reactor assist others in evacuation turn ventilators off in case of fire
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evacuate, closing door behind him i
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.a) semi-annually b) semi-annually
.1 c) quarterly
.j d) annually
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a) 1.25 rem b) 3 rem-c) 2 5 rem--1f' a life is at stake 2.
Curie-activity unit such that 1 ci= 3.7 x 1010 dps Roentgens - exposure unit of energy deposition in air Rem..- dose with adjusted for relative biological effectiveness of
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'different radiations'
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externally, alphas cannot-penetrate the dead skin layer, causing little' concern internally, alphas are much' more damaging than other
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forms of radiation.
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--- ANSWER ---
(DHCOOOO/20) ---
Fuel elements stored in the underwater racks can be locked in place (.5) and a locked storage cabinet is pr ovi ded for " cold
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(l.00)
fuel elements.
--- REFERENCE - -- ( DHCOOOO7 2<-))
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WPI, SAR, S ecti on 4,
Facility Description, Page 17~
C,ol ANSWER ---
(DHCOOOO721) - - - -
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a) In the question context," shadow" means to interpose betweea
'I the neutron detectors and the reactor fuel, material that will absorb or deflect neutrons so that the detector reading reads f
i lower than expected for a given power level.
(1.00)
b) Operator would be reading power instruments inaccuratel y l ow.
(1.00)
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!I REFERENCE --- (DHCOOOO721) ---
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WPI - TS - 2.3 Page ti D. O '7 ANSWER
--
(DHCOOOO722)
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The trip mixer function is to scram the reactor on either a high (1.00)
flun (.5)or short period signal (.3).
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REFERENCE
- (DHCOOOO722)
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WP1 - SAR - 4.3.6 Page 23
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ANSWER
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(DHCOOOO723) ---
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1.
Switching off a fail saf e radi ation station at the (1.00)
console.
2.
Tripping a low water alarm device adjacent to the (1.00)
reactor bridge.
3. Posh,%asnDdp/q3/ source-ganof Me AMMoe G"
N REFERENCE -- (DHCOOOO723) -
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WPI, SAR, Section 6.5.4, page 37.
s
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,- - ANSWER ---
(DHCOOOO724)
---
The NRC Licensed Senior Reactor Operator (SRO)(Rc/l/
Dir-ec or)
( 1. 00).
--- REFERENCE ---- (DHCOOOO724) - - - -
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-.m G O(-
(DHUUUUU/Zb) ---
4 / <u %c io 700 /Ar-
--- ANSWER
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R Beta-gamma' measuring devices with ranges.01 c
mc/h* (1.) and
" ' '
neutron measuring devices with ranges.04 ta 1000 mrems/1,r (1.).
(2.00)
REFERENCE -- (DHCOOOO725) --
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l WPI - Technical Specifications - 3.3 Pg 7.
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ENCLOSURE 2
.TO ALL POWER AND NON-POWER REACTOR LICENSEES, APPLICANTS FOR AN OPERATING LICENSE AND HOLDERS OF A CONSTRUCTION PERMIT Gentlemen:
Subject:
Integrity of the Requalification Examinations for Renewal of Reactor Operator and Senior Reactor Operator Licenses (Generic Letter 83-17)
Recently, an investigation was completed which determined that a senior offi-cial at a nuclear power plant certified to the NRC that a licensed individual had successfully completed the licensed operator requalification program, when in fact, that individual had cheated by submitting another person's work in response to some examination questions.
Such an individual has not successfully completed the requalification program and has not discharged his licensed responsibility in a safe and competent manner, as required by 10 CFR 55.
Furthermore, it should be noted that cheat-ing on examinations which are used to certify individuals to the NRC will result in an automatic denial of a license application or license renewal and could result in more severe penalties.
J The purpose of this letter is to highlight the need for you to ensure that the validity of the certifications required by 10 CFR Part 55 and the integrity and honesty of the requalification program are adequately addressed in facility l
procedures.
You should review your procedures on this subject to ensure that i
an applicant's individual performance can be determined.
Your procedures j
should include provisions to detect and prevent instances of cheating.
In particular, unproctored examination, take-home quizzes and on-shift tests allow I
ample opportunity for cheating which could go undetected and, therefore, are
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not an acceptable means for certifying individual performance. While some i
portions of examinations may be conducted in an open-book format (e.g. use of steam tables on thermodynamics problems or use of facility procedures and i
drawings during oral examinations), adequate monitoring provisions are essen-tial to ensure that the persons being evaluated are working independently and
,
are using only authorized instructional or reference materials.
No submittals of procedures or results of your procedure reviews are required I
by this letter; however, we will review these procedures as a part of our audits of the licensed reactor operator and senior reactor operator requalifi-cation programs.
Original Signed by Darrell G. Eisenhut, Director Division of Licensing