Text

Exam Rept 50-223/86-03OL on 860916-17.Exam Results:One Candidate Received License & Other Candidate Failed Written Exam
	ML20211C043
Person / Time
Site:	University of Lowell
Issue date:	10/07/1986
From:	Keller R, Kister H, Norris B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20211C002	List: IR 05000223/1986003; ML20211B996;
References
	50-223-86-03OL, 50-223-86-3OL, NUDOCS 8610210257
	Download: ML20211C043 (57)
	v • d • e

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U. S. NUCLEAR REGULATORY COMMISSION REGION'I OPERATOR LICENSING EXAMINATION REPORT

. EXAMINATION REPORT N0. 86-03(OL)

FACILITY DOCKET N0. 50-223 FACILITY LICENSE NO. R-125 LICENSEE: University of Lowell 1 University Avenue Lowell, Massachusetts 01854 FACILITY: University of Lowell EXAMINATION DATES:

September 16-17, 1986 CHIEF EXAMINER:

///

h Barryf.'Norris Date React 6r Engineer ( aminer)

REVIEWED BY:

14/7 /W Robert M. Keller, Chief Date Projects Section IC

_/

APPROVED BY:

'

Harr Ki ster', \\ Chief Dafe'/ /

Projec Bran'ch 1 SUMMARY:

Two Reactor Operator candidates were examined during this period; one candidate received a license, the other failed the written examination.

8610210257 861014 PDR ADOCK 05000223 V

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REPORT DETAILS TYPE OF EXAMS: Replacement EXAM RESULTS:

l R0 l

l Pass / Fail l

l l

l l Written Exam i 1/1 l-l l

I I

l Oral Exam l

2/0 l

l l

l l0verall l

1/1 I

I I

I l

l I

I CHIEF EXAMINER AT SITE:

B. S. Norris (USNRC)

OTHER EXAMINERS:

R. M. Keller (USNRC)

1.

Summary of generic deficiencies noted on oral exams:

a.

The' candidates had not been trained in the use of the emergency breathing equipment (Scott Air-Pac).

b.

The candidates were not sure of the ' process for a manual start of the Emergency Generator.

2.

Summary of generic deficiencies noted from grading of R0 written exams:

a.

Candidates could not explain how neutron flux changes over core life.

b.

Candidates could not accurately describe the emergency electrical distribution supply to the nuclear instrumentation.

~

c.

Candidates could not describe the required approvals for a temporary change to a procedure, d.

Candidates could not accurately calculate how long an individual could work in a given radiation fiel [

.

3.

Personnel present at Exit Meeting:

NRC Personnel B. S. Norris - Chief Examiner Facility Personnel T. Wallace - Reactor Supervisor 4.

Summary of comments made at exit meeting:

a.

Concern was expressed by the examiner regarding the lack of training on use of the Scott Air-Pac.

b.

The examiner noted that the graph used by the Console Operator for determination of Integral rod worth was incorrectly labeled as Differential rod worth.

The facility corrected the graph, c.

Two of the four Safetv Analysis Report (SAR) communications systems available to the operators are inoperative; specifically, the inter-com system and the sound powered headset system. This essentially eliminates all communications into the Control Room except for face-to-face.

The facility committed to repairing or replacing the systems with a completion date no later than January 1,1987.

-This item remains unresolved pending further investigation by Region I (50-223/86-03-01).

d.

The examiner noted that the Technical Specifications require all procedures be reviewed and approved by the Reactor Safety Subcom-mittee (RSS).

Individual procedures do not show the required approval signatures; the only visible approval is on the Table of Contents by the Professor-in-Charge dated December 28, 1979; new procedures have been issued since that date with no visible evidence of approval.

The facility stated that the RSS approves the procedures by entry of such into the minutes of the RSS meetings, but that the minutes were not readily available. The facility further-stated that they would develop a system which would provide a visible approval signature for the procedure and which would allow the operators to readily l

determine the latest revision of any procedure. The facility committed to an implementation date of November 1, 1986.

This item remains unresolved pending further investigation by Region I (50-223/86-03-02).

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,

e.

The examiner noted that a procedure exists which allows the facility to operate with only one licensed operator instead of the SAR requirement of two licensed operators. The wording in the Technical Specification (TS) has been interpreted by the facility as requiring only one licensed operator. The SAR is more definitive as to the minimum shift complement and the two documents must be made consis-tent.

The facility stated that they would research the differences and submit to Headquarters a change request for either the SAR or the TS. The facility committed to submit this request by April 1, 1987.

This item remains unresolved pending further investigation by Region I and Headquarters (50-223/86-03-03).

f.

The facility stated that on a written examination, a Reactor Operator should not be responsible for the information contained in the Technical Specifications.

The examiner stated that material pertaining directly to the responsi-bilities of the Reactor Operator is considered required knowledge.

5.

Changes made to written examination during exam review:

a.

Questions A.01.b - answer key changed to reflect actual Am-Be reac-tion to produce source neutrons.

b.

Question A.04.b - answer key changed to reflect correct time for Xenon to reach equilibrium.

c.

Question A.05 - answer key changed to agree with a later revision of the Technical Specifications provided after the examination review.

d.

Question B.05 - additional acceptable response added to answer key.

e.

Question B.07.c - answer key changed to agree with a later revision of the Technical Specifications provided after the examination review.

f.

Question C.01 - answer key corrected to correspond to automatic mode of operation.

g.

Question D.01.a - answer key corrected to reflect actual plant conditions.

h.

Question D.02.b - answer key modified to allow alternate answer.

i.

Question G.06 - deleted last two parts of answer based on Technical Specification statement that no credible accident could result in these classification.

.

NOTE: It should be noted that most of the changes made to the answer key were due to additional information provided to the examiner during or

'after the examination review.

For the next set of examinations at the University of Lowell Reactor, a complete and updated set of reference

.

materials must be provided to the examiners.

e Attachments:

1)

Written Examination and Answer Key (RO)

s.

.

U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 86-03(0L)

FACILITY' DOCKET NO. 50-223 FACILITY LICENSE N0. R-125 LICENSEE: University of Lowell 1 University Avenue Lowell, Massachusetts 01854 FACILITY: University of Lowell EXAMINATION DATES: September 16-17, 1986 CHIEF EXAMINER:

Original signed sy, Barry S. Norris Date.

Reactor Engineer (Examiner)

REVIEWED BY:

Origina1 signed By:

Robert M. Keller, Chief Date Projects Section 1C APPROVED BY:

Original Sisned By:

Harry B. Kister, Chief Date-Projects Branch 1 SUMMARY:

Two Reactor Operator candidates were examined during this period; one candidate received a license, the other fai'&'t the written examination.

OFFICIAL RECORD COPY OL ER LOWELL - 0005.0.0 10/06/86

<-

.

REPORT DETAILS TYPE OF EXAMS:

Replacement EXAM RESULTS:

l R0

l Pass / Fail l

I I

l Written Exam i 1/1 l

l l

I I

I l0ral Exam i

2/0 I

I i

I I

i 10verall I

1/1 l

l l

l

CHIEF EXAMINER AT SITE:

B. S. Norris (USNRC)

OTHER EXAMINERS:

R. M. Keller (USNRC)

.1.

Summary of generic deficiencies noted on oral exams:

a.

The candidate.s had not been trained in the use of the emergency breathing equipment (Scott Air-Pac).

b.

The candidates were not sure of the process for a manual start of the Emergency Generator.

2.

Summary of generic deficiencies noted from grading of RO written exams:

a.

Candidates could not explain how neutron flux changes over core life, b.

Candidates could not accurately describe the emergency electrical distribution supply to the nuclear instrumentation.

c.

Candidates could not describe the required approvals for a temporary change-to a procedure.

d.

Candidates could not accurately calculate how long an individual could work in a given radiation field.

OFFICIAL RECORD COPY

~0L ER LOWELL - 0005.1.0 10/06/86

Q

-

3.

Personnel present at Exit Meeting:

NRC Personnel B. S. Norris - Chief Examiner Facility Personnel

T. Wallace - Reactor Supervisor 4.

Summary of comments made at exit meeting:

a.

Concern was. expressed by the examiner regarding the lack of training on use of the Scott Air-Pac.

b.

The examiner noted that the graph used by the Console Operator for determination of Integral rod worth was incorrectly labeled as-

Differential rod worth, The facility corrected the graph.

t c.

Two of the four Safety Analysis Report (SAR) communications systems available to the operators are inoperative; specifically,.the inter-

,

com system and the sound powered headset system. This essentially eliminates'all communications into the Control Room except for face-to-face.

The facility committed to repairing or replacing the systems with a

~

completion date no later than January 1, 1987.

<

This item remains unresolved pending further investigation by Region I (50-223/86-03-01).

d.

The examiner noted that the Technical Specifications require all procedures be reviewed and approved by the Reactor Safety Subcom-mittee (RSS).

Individual procedure's do not show the required approval signatures; the only visible approval is on the Table of Contents by the Professor-in-Charge dated December 28, 1979; new procedures have been issued since that date with no visible evidence of approval.

The facility stated that the RSS approves the procedures by entry of such into the minutes of the RSS meetings, but that the minutes were

,

not readily available. The facility further stated that they would develop a system which would provide a visible approval signature for the procedure and which would allow the operators to readily determine the latest revision of any procedure.

The facility committed to an implementation date of November 1,.1986.

This item remains unresolved pending further investigation by Region I (50-223/86-03-02).

OFFICIAL RECORD COPY OL ER LOWELL - 0006.0.0 10/06/86

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e.

The examiner noted that a procecure exists which allows the facility to operate with only one licensed operator instead of the SAR

requirement of two licensed operators. The wording in the Technical Specification (TS) has been interpreted by the facility as requiring only one licensed operator. The.SAR is more definitive as to the minimum shift complement and the two documents must be made consis-tent.

The facility stated that they would research the differences and submit to Headquarters a change request for either the SAR or the TS. The facility committed to submit this request by April 1, 1987.

This item remains unresolved pending further investigation by Region I and Headquarters (50-223/86-03-03).

f.

The facility stated that on a written examination, a Reactor Operator should not be responsible for the information contained in the Technical Specifications.

The examiner stated that material pertaining directly to the responsi-bilities of the Reactor Operator is considered required knowledge.

5.

Changes made to written examination during exam review:

a.

Questions A.01.b - answer key changed to reflect actual Am-Be reac-tion to produce source neutrons.

b.

Question A.04.b - answer key changed to reflect correct time for Xenon to reach equilibrium.

.c.

Question A.05 - answer key changed to agree with a later revision of the Technical Specifications provided after the examination review.

d.

Question B.05 - additional acceptable response added to answer key.

e.

Question B.07.c - answer key changed to agree with a later revision of the Technical Specifications provided after the examination review.

f.

Question C.01 - answer key corrected to correspond to automatic mode of operation.

g.

Question D.01.'a - answer key corrected to reflect actual plant-conditions.

h.

Question D.02.b - answer key modified to allow alternate answer.

1.

Question G.06 - deleted last two parts of answer based on Technical Specification statement that no credible accident could result in these classifications.

OFFICIAL RECORD COPY OL ER LOWELL - 0007.0.0 10/06/86

-

.

-

. -.

,--.

. -

. - -. - -

..

.

-

NOTE: It should be noted that most of the changes made to the answer key were due to additional information provided to the examiner during or after the examination review.

For the next set of examinations at the University of Lowell Reactor, a complete and updated set of reference materials must be provided to the examiners.

Attachments:

1)

Written Examination and Answer Key (RO)

0FFICIAL RECORD COPY OL ER LOWELL - 0008.0.0 10/06/86

k / T R C (7/ et)

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S.

NUCLEAR REGULATORY COMMISSION

.

REACTOR DPERATOR LICENSE EXAMINATION FACILITY:

_LINIVERSITY OF _LQWELL

_

REACTOR TYPE:

_IEST DATE ADMINISTERED: 86/09/17 EXAMINER:

_NQBBigt B.

S.

gS[FT CANDIDATE:

INg_TBUCTIONS_TD_GANpipAlgi Use separate paper for the answers.

Write answers on one side'only.

Staple question sheet on top of the answer sheets.

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 starts.

% OF CATEGORY

% OF CANDIDATE'S CATEGORY

__Ye6Ug_ _I9186 SQQBE

_yALUg__

C61gGQRY

_14.00

_13399

__

A.

PRINCIPLES OF REACTOR OPERATION

_15 00 -

14 99

___

_

_ _ _

B.

FEATURES OF FACILITY DESIGN

_13200 14.09 C.

GENERAL OPERATING CHARACTERISTICS

_14.10_

14.10 D.

INSTRUMENTS AND CONTROLS 14 39__

14.40 E.

SAFETY AND EMERGENCY SYSTEMS

_

_12429__

15.50 F.

STANDARD AND EMERGENCY DPERATING PROCEDURES

'

_Nx99__ _13299

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RADIATION CONTROL AND SAFETY 199290 Totals 43, Final Grade All work done on this examination is my own.

I have neither given nor received aid.

l Candidate's Signature

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e-NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS

.

During the administration of this examination the following rules apply:

1.

Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2.

Restroom trips are to be limited and only one candidate at a time may leave.

You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3.

Use black ink or dark pencil gely to f acilitate legible reproductions.

4.

Print your name in the blank provided on the cover sheet of the examination.

5.

Fill in the date on the cover sheet of the examination (if necessary).

6.

Use only the paper provided for answers.-

7.

Print your name in the upper right-hand corner of the first page of each section of the answer sheet.

G.

Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a agw page, write gely 90 903 sidg of the paper, and write "Last Page" on the last answer sheet.

9.

Nunber'each answer as to category and number, for example, 1.4, 6.3.

Skip at least th gg lines between each answer.

10.

t 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility LLigtature.

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 required.

14. Show all calculations, methods, or assumptions used to obtain an answer h;tomathematical problems whether indicated in the question or not.

m ow 15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE l

'

QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

i.

16. If parts of the examination are not clear as to intent, ask questions of the gxamingt only.

17.~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 completed.

_ _ - -

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18. When you complete your examination, you shall:

a.

Assemble your examination as follows:

(1)

Exam questions on top.

(2)

Exam aids - figures, tables, etc.

(3)

Answer pages including figures which are part of the answer.

b.

Turn in your copy of the examination and all pages used to answer the examination questions.

c.

Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.

d.

Leave the examination area, as defined by the examiner.

If after leaving, you are found in this area,while the examination is still in progress, your license may be denied or revoked.

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!h___PBINGIELES_QF REAgTOR QEEBATION PAGE

.

QUESTION A.01 (2.50)

a.

Describe TWO hazards of starting up a reactor without an adequate neutron source.

(1.00)

b.

List the TWO neutron sources available in the ULR and describe how l

each reacts to produce neutrons.

(1.50)

QUESTION A.02 (2.00)

A reactor startup is in progress.

A systematic withdrawal of rods is in progress, and currently the count rate is' level; this procedure is repeated until the reactor is critical.

j Assume that K is initially 0.995 and each rod withdrawal results in an increase in K of O.001.

a.

Draw a graph of count rate vs. time until K=1.OO.

(1.00)

b.

When the reactor is called critical, what is the indication on

'

the startup channel?

State any assumptions.

(1.00)

QUESTION A.03 (1.50)

The ULR critical mass has been calculated at 2.8 kg of U-235g however, the core is loaded with 3.5 kg of U-235.

List THREE reasons why it is necessary to load excessive fuel.

RJgBTION A.04 (2.00)

,

The two most common fission product poisons are Xenon and Samarium.

-( a.

List the production and removal processes for Xenon and Samarium.

(1.50)

b.

What are the approximate times for Xenon and Samarium to reach equilibrium if power is increased from 10 kW to i NW7 (0.50)

!

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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82.__E81t!!GlPt,F,@_QF RE_8GTQR OPERATION PAGE

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QUESTION A.05 (2.00)

a.

Per the ULR Technical Specifications, define Shutdown Margin.

(1.00)

b.

What is the minimum Shutdown Margin per Technical Specifications?

State all associated assumptions.

(1.00)

QUESTION A.06 (2.25)

The reactor is critical at 2x10E1 watts 2 minutes later power is observed to be 7x10E2 watts.

'

a.

What is the reactor period?

(O.75)

b.

Given a delayed neutron fraction of 6x10E-3 and an average delayed neutron life of 12.7 seconds, how much reactivity was added for the reactor period in part a?

(1.50)

QUESTION A.07 (1.75)

As the temperature of the pool water increases, will the neutron leakage increase, decrease, or not change?

Explain your answer.

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l (***** END OF CATEGORY A

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.

QUESTION B.01 (3.00)

The reactor is operating at 1 MWp using Figure B.1, answer the followings a.

Identify all of the NUMBERED items.

(2.00)

b.

Indicate the flow paths.

(0.30)

c.

For each of the LETTERED instruments, indicate what kind of parameter is being measured (i. e. pressure, temperature, flow).

(0.70)

DUESTIDN B.02 (1.50)

There are TWO major short-lived isotopes' produced during reactor operations.

What are these TWO isotopes and what TWO design features are provided at the ULR to minimize the effects of the radiation from the two isotopes?

,

QUESTIDN B.03 (2.00)

Using the attached Figure B.2, show where the following components are located:

a.

Proportional counter (s)

b.

Compensated ionization chamber (s)

c.

Startup source (s)

d.

Graphite reflector element (s)

e.

Fuel element (s)

f.

Servo contral element (m)

g.

Control element (s)

h.

Radiation basket (s)

b TION B.04 (2.00)

"W f'

a.

Spent fuel is stored in the reactor pool.

Describe the geometric

,o array utilized and why that particular array was selected.

(1.25)

b.

Describe the fuel handling tool.

(O.75)

QUESTION B.05 (1.50)

What are THREE functions of the water in the reactor pool?

(***** CATEGORY B CONTINUED ON NEXT PAGE

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i t

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B.

FEATtJ3EE_QF_ FACILITY DESI@N PAGE

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,

1 QUESTION B.06 (1.00)

TRUE or FALSE:

During power operations, the bridge cannot be moved.

Justify your answer.

QUESTION B.07 (3.00)

In accordance with the ULR Technical Specifications:

a.

What in the objective of Safety Limits?

(0.50)

b.

What is the relationship between Safety Limits and Limiting Safety System Setpoints?

(0.50)

c.

What are the FOUR variables measured in the forced convection mode of operation to assure Safety Limits are not violated, and what is the associated Limiting Safety System Setpoint (minimum or maximum) for each variable?

(2.00)

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13 [b y

(***** END OF CATEGORY B

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GEt!EBOL _QPEB811W_Gt!@B9GIEBigILGE PAGE

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QUESTION C.01 (2.50)

Assume the ULR is operating at 1MW with all controls in the normal mode of operation and no operator action.

,

Describe the sequence of events which would cause-the reactor to scram if the SECONDARY pump were secured.

QUESTION C.02 (2.00)

What THREE reactivity effects are compensated for by the burnable poison filler in the control blades?

.

!

QUESTION C.03 (2.00)

Indicate what effect (increase, decrease, or no change) each of the following has upon the Keff of the ULR.

Consider each case separately.

I a.

Placing a large air-filled steel canister next to the core.

b.

Irradiating an Argon gas sample via the rabbit system.

!

c.

Removing a graphite reflector element from the core periphery.

d.

Flooding a beamport with water.

i GUESTIDN C.04 (2.00)

The reactor is operating at full power, over a period of time the temperature of the coolant increases from 22 C to 31 C.

Assuming a temperature cooefficient of -0.815E(-4) Delta K/K/C and a rod worth of 0.3% Delta K/K/ inch and a rod speed of 78 inch / minute for the regulating rod, how far and in what direction will the (k- *sontrol rod move?

.

u v <b, SJESTION C.05 (2.50)

-

Figure C.1 is a graph of INTEGRAL rod worth for a single control blade.

a.

Label the axis and show approximate values for the points shown. (1.50)

b.

Why is the slope of the curve steeper at Point i than Point 27 (1.00)

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

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GEtLEBL4_QPE_ RATING CHARACTERI@TIG@

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QUESTION C.06 (2.00)

If the reactor is operated at a constant power level, explain how and why neutron flux changes over core life.

Include in your discussion both fast and thermal neutron flux.

Assume no fuel changes are made.

QUESTION C.07 (1.00)

Fill in the missing information, show your work and state any assumptions:

Tube side Shell side

___

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114 F T in 82 F

'

103 F T out 1600 gpm Flow 1500 gpm i

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I (***** END OF CATEGORY C

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D.

INgJRUMENTS_AND_GQNTRAS

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PAGE B

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QUESTION D.01 (2.10)

For the below listed conditions, state whether there is an alarm only, an alarm and scram, a scram only, or none of the above:

a.

Pool temperature (natural convection mode) - 104 F b.

High flux (2 detectors) - 1.10 ratio c.

High temperature of primary coolant entering core - 106 F d.

Low flow rate of primary coolant - 0.7 ratio

.e.

High conductivity of primary coolant

'f.

Coolant gates half open g.

Regulating rod at uper limit of travel

'

QUES. TION D.02 (2.50)

a.

Describe the operation of the Compensated Ion Chamber (CIC).

(2.00)

b.

Which CIC detectors feed the Safety Channels?

(0.50)

QUESTION D.03 (2.50)

a.

What is the purpose of the servo-controlled regulating element drive system?

(0.50)

b.

What are the THREE components of the system?

(1.50)

c.

Under what conditions of critical operations is the use of the automatic mode prevented.

BUESTION D.04 (1.50)

N nwiis the temperature of the primary coolant automatically controlled?

A QUESTION D.05 (2.50)

,

a.

Briefly describe HOW a conductivity cell works.

(1.00)

b.

List the location of THREE conductivity cells at the ULR.

(1.50)

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D.

INgIByt!gNIg_9ND_ggNTROLE PAGE

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QUESTION D.06 (2.00)

a.

List FIVE conditions which will achieve a General Reaction of the Ventilation System (GRVS).

(1.25)

b.

Two of the valves that close on a GRVS will automatically open when the GRVS signal is cleared.

What are those TWO valves?

(0.50)

.

'

c.

Which valve is not affected by a GRVS7 (0.25)

QUESTION D.07 (1.00)

The process of determining an instrument's accuracy by visually comparing that indication to other independent instrument channels measuring the same parameter is defined in Technical Specifications as as (Choose the BEST answer)

A.

Channel Calibration B.

Channel Check C.

Channel Measurement D.

Channel Test

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(***** END OF CATEGORY D

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.

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-. _ _ _ _ _ _ _ _ -

_ _ _

.

E.

BAFETY AND EMERggNCY SYSTEM PAGE

.

QUESTION E.01 (1.00)

In accordance with the ULR Technical Specifications, a Control Rod is considered saf ety equipment but a Regulating Rod is NOT saf ety equipment. Why?

QUESTION E.02 (2.00)

~'a.

How is containment integrity maintained during access.

(1.20)

b.

In the event of failure of all power, how can a containment entry be made?

(0.00)

,

QUESTION E.03 (2.40)

Draw the electrical distribution to the Nuclear Instrumentation during a loss of the normal power supply.

Include in your drawing the power source, the distribution panels, and all necessary breakers.

QUESTION E.04 (2.50)

Answer the following questions about the Scram Circuits:

a.

Briefly describe the difference between an electronic scram and a relay scram.

(1.50)

b.

List TWO conditions which will cause an electronic scram.

Include setpoints.

(1.00)

!

$

-

x:,

,

GUESTIDN E.05 (2.50)

,

m.

What will cause automatic initiation of the Emergency Exhaust System?

(0.50)

b.

After an automatic start of the Emergency Exhaust system, what TWO conditions will cause the system to auto-stop?

(1.00)

c.

Describe, or sketch, the flowpath for Emergency Exhaust.

(1.00)

(***** CATEGORY E CONTINUED DN NEXT PAGE *****)

._. - _ -.. _ - -

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.

-

.

E-EAF_gTY ANQ_gMER_GENCY SYSTEMS PAGE

.

QUESTION E.06 (2.00)

a.

The control room, the reactor basement and the Reactor Supervisor's office can all communicate simultaneously using the Intercom system. TRUE or FALSE.

Justify your answer.

(1.00)

i b.

The best system for communications during refueling operations would be the system.

Fill in the blank.

Justify your answer.

(1.00)

,

s QUESTION E.07 (2.00)

Reactor power is 100kW in the natural circulation mode of operation.

One of the flanges on one of the inlet bypass valves to the Hold-up Tank begins to leak.

Describe, in detail, the sequence of events which will or will not cause the core to become uncovered.

!

t 'lN'N jfinje h &5 h

o.

i

$h

!

l (*****

END OF CATEGORY E

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. _. _ _ _ _

_ _ _..

.

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.

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.

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. -

-

.

E __SIOND8BD AND_EMEBGELCY E EB811NG_PBQGEDyBgg PAGE.12

.

GUESTION F.01 (2.00)

In accordance with the ULR Technical Specifications and the Authority Section of your procedures manual:

If a temporary change is required for an existing procedure, what approvals are required prior to

,

implementation of the change?

Discuss changes that alter intent and changes'that do not alter intent.

!

. A..

DUESTION F.02'

(1.00)

' In accordance with R.O.1 " Critical Experiments":

how is minimum shutdown capability ensured?

.

DUESTIDN F.03 (2.00)

j

Fill in the blanks in accordance with E.O.1,

" Radiation Emergency":

If the cause of a radiation level in excess of or an airborne level in excess of ___

in a personnel accessible area cannot bethe cause of determined within

_ _ _

_,

the reactor must be shut down.

If the reactor shutdown is not effective in reducing the levels, then

-

______

GUESTION F.04 (1.00)

In accordance with E.D.7,

" Stuck Rod or Safety Blade":

what is the

.

immediate action of the Console Operator if a rod or blade becomes

'

stuck or appears to be stuck?

I b !ON F.05 (2.00)

'*

+

'The ULR Technical Specifications require that surveillances be perf ormed

--

, von the pool water.

What are the TWO surveillances and why is each performed?

l SUESTION F.06 (2.10)

~

In accordance with S.P.12, " Calibration of Temperature Monitoring Devices":

Describe the procedure for the Pool Temperature Channel Calibration.

(***** CATEGORY F CONTINUED DN NEXT PAGE *****)

i

)

, - _ - - - -

.

. -

- - - -. -

.. -

-.

__._-

. -..

.

. _.

-

_.

-

.-.

-

.

_

.

E __HT_ANDARD AND EMERGENCY _QPERATING PROCEDURgg PAGE

.

QUESTION F.07 (2.00)

Answer the following questions TRUE or FALSE per R.O.16, " Movement of Co-60 Source in the Reactor Pool":

a.

The Co-60 source may be moved to the reactor end of the pool while the reactor is in operation.

b.

It is not recommended to put the Co-60 in a frame while moving them.

c.

In no circumstance should the Co-60 sources be moved or handled while the reactor primary coolant system is in forced circulation operation.

d.

The sources may be handled above the 8 foot level when a dedicated radiation monitor is present.

,

e.

The reactor pool gate should be open when handling individual strips.

QUESTION F.OO (1.50)

A Fire Alarm sounds concurrently with a report of a fire in the area of the Beam Tubes while experiments are under way.

In accordance with E.O.2,

" Fire" list FIVE actions you, as the Console Operator, should take.

GUESTION F.09 (1.90)

Power is 1 kW, you are the Console Operator, and the following ALARMB are received simultaneously:

water temperature - high

!

stack monitor activity - high t

'"

primary coolant conductivity - high iMichalarmshouldbeinvestigatedfirst?

Justify your answer." *

A (***** END OF CATEGORY F

- - - - )

I

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.

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.

- -

-

. - -.-

.

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-.

_ -. _ _ _ _.

_

.

G __BegleligN_ggNIB9L AND SAFETY PAGE

i e

.

QUESTION B.01 (2.50)

A maintenance man is working inside the containment while the reactor is at power.

He is working in a radiation field of 850 mrom/hr gamma and 30 mead /hr thermal and fast neutron.

The maintenance man is 28 years old and has a lifetime exposure through last quarter of 48 Rem on his NRC Form 43 additionally, he has accumulated 1.0 Rem so f ar this quarter.

>e.

How long can the man work in the area before he exceeds his 10CFR2O limits?

Show all work and state all assumptions.

(1.50)

b.

During a declared emergency, this individual volunteers to entsr a high radiation area and perform work necessary to prevent further effluent release.

In accordance with the Emergency Plan, what is his maximum allowed whole body exposure?

(0.50)

c.

Whose authorization is needed in part b.

(0.50)

QUESTION G.02 (2.00)

A small piece of metal on the flocr near the pool is reading 1800 mrem /hr of gamma at a distance of 2 meters.

What is the minimum distance f rom the source you can stand and not exceed a dose. rate of 80 mrem /hr?

Show all work and state all assumptions.

,

QUESTIDN G.03 (1.50)

In accordance with the ULR Emergency Plan, list THREE responsibilities

,of the Reactor Operator during a declared emergency?

uf. *

..,

(*****

CATEGORY G CONTINUED ON NEXT PAGE *****)

--

-

.

_

.

92__B8918TigN_QDNTROL AND SAFETY PAGE

e QUESTION G.04 (2.50)

The following is a quotation from the ULR SAR:

"The simultaneous tripping... of different detectors, each from a different category (I, II, III) is intended to be indicative of a potentially hazardous situation which would warrant initiation of the L'eneral Radiation Emergency Alarm. "

Category I:

Airborne Radioactivity List ODE of the two monitors

,

Category II:

Gror,s Radiation List THREE cf the four monitors Category III:

Fission Product Release

,

List DNE of the two monitors QUESTION G.05 (2.00)

Explain the operation of a Tracerlab " Snoopy" NP-2 portable radiation detector.

Include in your discussion the type of detector used and the type of radiation detected.

QUESTION G.06 (1.50)

i Tft ree.

In accordance with the ULR Emergency Plan, what are the-f4MEi-emergency

classifications in order of least severe to most severe.

QUESTION G.07 (2.00)

w.-

ga.

The major Source Term for GASEOUS Radioactive Weste is due to what

. wrF* nuclear reaction to f orm what radionuclide?

',*#

(1.00)

4 b.

What are the TWO major Source Terms f or LIQUID Radioactive Weste?(1.OO)

srr, l

..

(*****

END OF CATEGORY G

- - - - )

(************* END DF EXAMINATION ***************)

.

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EQUAT:Cil 5HEET

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f =.ma v = s/t Cycle efficiency = (.'let work cut)/(Energy in)

, = mg s = 1,t + 1/2 at

s 30*

.

KE = 1/2 mv 3,(y,, 7,)j; 4, 1;,

3, g,-u g

PE = mgn Vf = V, + at

= e/t t = In2/t1/2 = 0.593/t1/2

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.

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'

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x CR (1 - K,ffj) = CR II ~ *eff2)

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.

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M = (1 - Kg,)/(1 - Kg j)

T = (a - o)/(Io)

SCM = ( -Kg )/Kg a = (X,ff-1)/K,ff = M,f,/K,ff 1= = 10 secanos I = 0.1 secones-I o = [(1*/(T K,ff)] + [i,f,/(1 + IT)]

Ij j = I d d

P = (av)/(3 x 1010)

!)d) 2,2 2

g822

I t = rt R/hr = (0.5 C2)/d (meters)

R/hr = 6 CE/d2 (f,,g)

,

Watar Parmeters Miscellaneous Ccnveniens 1 gal. = 8.345 lem.

1 curie = 3.7 x 1010cp3 1 ga]. = 3.78 liters I kg = 2.21 lem 3 8tu/hr I ftd = 7.48 gal.

1 no = 2.54 x 10 i

Oensity = 62.4 lem/ft3 1 m = 3.41 x 106 5tu/hr

,

Density = 1 g:n/c::r3 lin = 2.54 c:a Heat of vacortration = 970 Stu/lem

F = 9/5'c + 32'

Heat of fusion = iu Stu/ lcm

'C = 5/9 (*F-32)

1 At:n = 14.7 psi = 29.9 in. Hg.

1 BTU = 778 ft-lbf 1 ft. H O = 0.4335 lbf/in.

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A.__EBINCIELES_QE_SE8CIQB_QEEB8119N PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

~-

.,

.

ANSWER A.01 (2.50)

a.

By the ti me power is indicated on the NI's the reactor would be supercritical (0.50)

resulting in a large power excursion before the protective system could react.

(O.50)

b." Americium-Beryllium (Am-Be)

(0.25)

21i

' C: 211 e====

Q.; y)._

..,g3 7., j;1

^-

7g

/

(0.50)

S e:r 2

' 2Hr a

,cutr r

"

Oc ~9 r /}/j'luu ->C %7 tA)e W/ny Antimony-Beryllium (Sb-Be)

sO.25)

Sb-124 ---> Te-124 + Gamma Be-9 + Gamma

> 2He-4 + neutron (0.50)

.

REFERENCE SAR, paragraph 4.1.6, pg 4-6 TVA Introduction to Nuclear Power, pgs 156-157 ANSWER A.02 (2.00)

a.

Graph must show 5 distinct increases in count rate with a leveling off at each new count rate (0.2O)

Each increase in count rate must be lagrithmically larger (0.40)

Each increase must take a progressively longer period of time (0.40)

b.

Count rate increasing on a.teady slope (0.50)

with no rod motion (O.50)

REFERENCE TVA Introduction to Nuclear Power, pgs 170-173 ANSWER A.03 (1.50)

1.

buildup of Xe and Sm (fission product poisons)

2.

increase in temperature 3.

fuel burnup (0.50 each)

REFERENCE SAR, paragraph 4.5.3, pgs 4-84 to 4-89

_

--

.-

m

-

.m,_

.

.n 62__EBJNCIELES_k_BEOCIQB_QEEB6119N PAGE "17

,-

_

-86/09/17-NORRIS, B.

S.

ANSWERS -- UNIVERSITY OF LOWELL Q a-

-

. "

.. _

ANSWER A.04 (2.00)

a.

Xenon-production removal 1.

directly from fission 1.

decay to Cs-135 2.

decay of I-135 2.

neutron absorption Samarium-production removal 1.

decay bf Pm-149 1.

neutron absorption (0.25 each)

b.

Xenon *10-12 'unr-s-

..g, M. r d Samarium 2-3 days (0.25 each) i REFERENCE Lamarsh. Introduction to Nuclear Engineering, pgs 284-291 ANSWER A.05 (2.00)

a.

The r eunt e2 "egati"e -eactivity by -Sich the r:ctor in subtriticc.1.

[

(1.00)

.t.7'7e b.

Minimum SDM is W4-delta k/k (0.55)

Cold (0.15), xenon-free (0.15), and most reactive safety rod stuck out (0.15)

(0.45)

REFERENCE ULR TS, pgs IV-4 & IV-12 bubbtuvt ef <t c kY,' ly 'ry PW.Jfn ry SJ pm </t Ct. Wit oni rir aw &

.6 e en S<L,,< < pk m., &< on be n,<4 s.,L.,,%;,. r.

w

.;x

?,

3 -.._

n;

-

.

A __E81NGLELES_QE_8E6GlQB_QEE8811QN-PAGE

t

ANSWERS -- UNIVERSITY OF LOWELL-06/09/17-NORRIS, B.

S.

._

ANSWER A.06 (2.25)

a.

t/T P = Po(e)

'O.25)

120/T 7x10E2 = (2x10E1)(e)

(0.25)

120/T 35 = e 3.555 = 120/T T= 120/3.555 = 33.75 sec (0.25)

0.006 (0.40)

b.

Beta-eff

=

1/12.7 = 0.08 (0.40)

Lambda-eff

=

T=

(Beta

. rho) / rho (lambda)

(0.30)

33.75 = (0.006 - rho)/ rho (0.08)

rho = 0.006/3.70 = 0.00162

(0.40)

REFERENCE Lamarsh, Introduction to Nuclear Engineering, pgs 241-256 ANSWER A.07 (1.75)

Increase (0.75)

Increased pool temperature causes moderator density to decrease (0.50)

which increases the average neutron diffusion length and slowing down length, thus increasing leakage.

(O.50)

REFERENCE Lamarsh, Introduction to Nuclear Engineering, pg 279

__

_

s,

_

.,,

_

-

.

,

..

.

02__EEglyBES_OE_EOCJL11X_DE@l@N PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

<

..

ANSWER B.01 (3.00)

a.

1.

pool 6.

secondary pump 2.

core 7.

blowdown path 3.

hold-up tank 8.

raw water supply 4.

primary pump 9.

sump tank 5.

heat exchanger 10.

cooling tower (0.20 each)

b.

Primary flowpath & Secondary flowpath (0.10 each)

Blowdown flowpath & raw water flowpath (0.05 each)

c.

A.

temperature E.

temperature D.

temperature F.

temperature C.

flow G.

flow (0.10 each)

D.

pressure REFERENCE SAR, figure 4-11 ANSWER B.02 (1.50)

1.

N-16 & 0-19 (O.40 each)

2.

Hold-up tank allows for decay of the isotopes (O.40)

and it is vented under water to the reactor pool (0.30)

.

REFERENCE SAR, pgs 4-26 to 4-27 ANSWER D.03 (2.00)

a.

P oportional counter (0.25)

6.

Three compensated ion chambers (O.25)

c.

Proper positioning of startup source (0.25)

d.

Proper positioning of Reflector elements (0.25)

e.

Proper positioning of fuel elements (0.25)

f.

Proper positioning of servo control element (0.25)

g Proper positioning of control elements (O.25)

h.

Proper positioning of radiation baskets (0.25)

See attached drawing

. -

.

__

.

.. - _ -

--

..

,g

,

s.....

.-

.

B___ FEATURES OF FACILITY DESIGN PAGE

'

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

REFERENCE SAR, figure 4.1

.

ANSWER B.04 (2.00)

a.

Spent fuel is stored in the pool in a planar array (0.50)

to prevent the possibility of inadvertent criticality.

(O.75)

b.

The fuel handling tool is a bayonet-type fitting (0.75)

REFERENCE ULR SAR, pgs 6-1 to 6-4 s

ANSWER B.05 (1.50)

(g,,gg, / gj p f,7,, f,)

1.

Moderate 2.

Cool 3.

Reflect

'

Y.

6hW//

REFERENCE SAR, pg 1-5

.

ANSWER B.06 (1.00)

.

True (0.25)

The bridge is interlocked to prevent any movement while the reactor control blades are withdrawn.

(0.75)

REFERENCE SAR, pg 4-16

a

_,

-%

s

~~Y-

.

-.

Bz FEATURES OF FACILITY DESIGN PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

.

-

ANSWER B.07 (3.00)

a.

Safety Limits assure that the integrity of the fuel cladding is maintained.

(0.50)

b.

LSSS's assure that protective action is initiated in order to prevent a Safety Limit from being exceeded.

(0.50)

-

...

.

c.

Reactor thermal power (P)

=,,1_.25 MWt (max)

1170 gp.T.

' T,i r.) /_,/f F < p,n [mf,1)

,

Coolant flow rate (W)

=

j Reactor coolant inlet temperature (Ti)

108F (max)

=

Height of water above the center line of the core(L) = 24.25 ft (min)

,

(0.25 for each variable & O.25 for each limit)

REFERENCE

,o

_

ULR TS, pgs IV-5 & IV-9 ts IV 7 s

'

\\

-

.

Gt__GENEBOL_QPEB8IlNG_GU688CIEBl@ILCS PAGE

<

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

.4;

~

ANSWER C.01 (2.50)

Pool temperature will increase adding negative reactivity (0, 70 ) (0.75)

rSet-g g p(0.50)

or2ctr p~ :r-uii i d=~=> s Primary coolant high temperature alarm (either entering or leaving)n Scram on primary coolant high temperature (o,poj!O.75)

.

REFERENCE

-

ULR SAR, pg 4-73

, _ _

..

ANSWER C.02 (2.00)

Minimizing the negative reactivity effects resulting from the buildup of fission products (0.67)

Negative reactivity due to burnup of the fuel (0.67)

Allows for more excess fuel to be~added (0.66)

REFERENCE ULR, SAR pgs 4-6 to 4-7, and 4-84 ANSWER C.03 (2.00)

a.

Decrease

,

b.

No change c.

Decrease d.

Increase (O.50 each)

REFERENCE ULR SAR, pgs 4-89 & 4-91 ANSWER C.04 (2.00)

Rod will move out (0.50)

Reactivity added by temperature increase:

E-O.815E(-4) Delta K/K/C3 x [9 C3 = -7.335E(-4) Delta K/K (O.75)

To compensate, rods must move out by:

E7.335(-4) Delta K/K3/EO.OO3 Delta K/K/ inch] = 0.24 inches (0.75)

r

.

<

- -

_

.

Gz__QENEBOL_QEEB8IJN9_gH888gIEBISIlgS PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

~

REFERENCE ULR SAR, pg 4-89 ANSWER C.05 (2.50)

See ULR SAR Figure 9.8, pg 9-45 for graph:

basic chapc cf cur"~

'O.50?

- labeling of the axis 6. 'Td ' O. 50 ;

- approximate values (O.50)

Slope of the curve is steeper in the center of the core due to larger neutron flux.

(1.00)

REFERENCE ULR SAR, pg 9-45 ANSWER C.06 (2.00)

Since fast neutron flux is proportical to power (0.50)

the fast neutron flux will reamin constant.

(0.50)

Since the concentration of fuel decreases over core life (0.50)

the number of thermal neutron available for fission must increase to cause to same power.

(0.50)

REFERENCE CAF ANSWER C.07 (1.00)

Eflow 1][ delta T 13 = [ flow 2][ delta T 2]

(0.25)

[1600 gpm][114 F - 103 F] = E1500 gpm][ delta T 2]

(0.25)

11.73 F (0.25)

[1600/15001011 F]

=

Therefore, T out on the shell side = 82 F + 11.73 F = 93.73 F (0.25)

-

<

'

REFERENCE ULR SAR, pg 4-26

%

.

Dz__LNSIBUdENIS_AND_CONIBOLS PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

-

ANSWER D.01 (2.10)

i a la r rra a.

Scram -en4y (setpoint 104F)

(0.30 each)

b.

Alarm only (setpoint for alarm 1.1, for scram 1.2O)

c.

Scram & alarm (setpoint for alarm 100 F, for scram 104 F)

d.

Scram & alarm (setpoint for alarm O.9, for scram O.8)

" ' "

e.

Alarm only (no setpoint)

f.

Scram & alarm (off c)csed seat)

g.

Alarm only (no setpoint)

REFERENCE ULR SAR, pgs 4-72 to-4-73 ANSWER D.02 (2.50)

a.

Two concentric cans, the outer can is lined with baron to detect neutrons (0.50)

and filled with gas to detect gammas (0.50)

the inner can is only filled with the gas and detects only gammas (O.50)

The voltages to the two cans is adjusted such that the current is proportional only to the neutron flux.

(0.50)

12Z4) ///,//77 (Detectors (0.25 each)

12Z3 and b.

REFERENCE ULR SAR, pg 4-67 ANSWER D.03 (2.50)

a.

Provides automatic control of reactor power level (0.50)

b.

CIC/picoammeter (O.50 each)

Servo amplifier Power schedule device (reference power level)

c.

Cannot shift to automatic control if the reactor period is less

'

than 30 seconds.

(0.50)

REFERENCE ULR SAR, pgs 4-61 to 4-62

-- - - - _ -

'~

., ' y

_

,-

..,.

.

Dz__INSIBUMENIS_6ND_CONIB06S PAGE

'

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

ANSWER D.04 (1.50)

The heat exchanger motor operated outlet valve (0.50)

receives a signal from the temperature controller (O.50)

when the temperature of the primary coolant out of the heat exchanger exceeds the preset setpoint.

(0.50)

REFEREhCE ULR SAR, pg 4-79 ANSWER D.05 (2.50)

a.

Conductivity = 1/ resistivity (0.50)

Resistivity is determined by applying a voltage across electrode immersed in water and measuring the current (0.50)

b.

1.

Holdup tank (0.50 each)

2.

Pool cleanup 3.

Makeup system REFERENCE ULR SAR, pg 4-81 ANSWER D.06 (2.00)

a.

1.

Activation of the LREA/GREA in the Control Room 2.

Activation of the GREA in the Reactor Supervisor's office 3.

Manual operation of the switches in the Control Room 4.

Loss of power 5.

Activation of the ventilation freeze alarm (0.25 each)

b.

Valve G (Sanitary system vent - CR)

(0.25)

Valve H (Acid vent - basement)

(0.25)

c.

Valve D (Emergency exhaust)

(O.25)

I REFERENCE l

SAR, pgs 3-10, & 3-23 to 3-24

!

l t

__

._

.,

. _ _ _. _

... -. _ _.

_ _ _ _ _ _ _ -.

.

. _,.

_ _..

._ _ j

_ _ _.. _. _ _

_

,

.

- D.

. I NS_TRt_JP!ENTS.__ AND _C_QN_TRQL_S PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

i

,

I ANSWER D.07 (1.00)

-

.

B.

Channel Check (1.00)

!

,

i REFERENCE ULR TS, pgs IV-1 & IV-2

!

.-

.

,

i i

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4

.

h

,

t

i i

i I.

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+

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.

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- ~.

-.

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-

J l

.

Ez__S6EEIY_6ND_ EMERGENCY _SYSIEMS PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

l

ANSWER E.01 (1.00)

A Control Rod has SCRAM capability while a Regulating Rod does not.

(1.00)

REFERENCE ULR TS,~ pgs IV-2 & IV-4 ANSWER E.02 (2.00)

a.

By means of a double door system, (O.60)

only one of which can be opened at a time.

(0.60)

b.

By manual operation of the doors.

(0.80)

REFERENCE ULR SAR, pgs 3-2 to 3-8 ANSWER E.03 (2.40)

Drawing must include the following:

- Emergency generator (0.30)

- Automatic line transfer switch (0.30)

- Emergency Distribution Switchboard (0.30)

- Breaker to ELPL-R1 (0.2O)

- ELPL-R1 distribution panel (0.30)

- Breaker to Console and Nuclear Instrun4entation Cabinet (0.2O)

- Console and NI Cabinet (0.30)

- Breaker to Nuclear Instrumentation (0.20)

- Nuc! ear Instrumentation (O.30)

(See attached figure E.1)

REFERENCE ULR SAR, Figures 5.2 - 5.4

-.

- -.

Twg -

-

Ez__ SAFETY _AND_EMERBENCY SYSTEMS PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

ANSWER E.04 (2.50)-

-

a.

The electronic scram deenergizes the scram magnets via the logic unit and trip actuator amplifier.

(0.75)

The relay trips are series connected in the safety chain which leads to two master scram relays which deenergize the logic and trip amplifier.

(0.75)

b.

High flux (1257.)

Short period (&Iseconds)

(0.30 each fcr name of scram, 0,20 each for. correct setpoint)

REFERENCE ULR SAR, pg 4-69 ANSWER E.05 (2.50)

a.

Pcontainment - Pambient

>or= 0.25 inch water (0.50)

b.

Pcontainment - Pambient <-O.25 inch water (0.50)

Pcontainment - Pambient

>or= 0.50 inch water (0.50)

i c.

Roughing & Charcoal & Absolute filters (0.10 each)

Emergency Exhaust fan (EF-14)

(0.25)

Valve D (0.25)

Taps into main exhaust header DOWNSTREAM of all other valves (0.20)

REFERENCE ULR SAR, pgs 3-10, 3-21, & 3-24 to 3-25 ANSWER E.06 (2.00)

a.

False (0.40)

The system only allows two stations to communicate at a time.

(0.60)

b.

Sound powered headset system.

(0.40)

The system allows all stations to communicate simultaneously (0.30)

and is a continuous bidirectional system.

(O.30)

REFERENCE ULR SAR, pgs 6-5 & 6-6

,

I I

i

.

_

._

,

_

_ _.

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

_ _. _

.-

~

.

Ec__SOEEIY_QND_EDERGENCY_SYSIEMS PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

ANSWER E.07 (2.00)

Antisiphon lines are connected to the primary piping.

(O.75)

Loss of the backpressure on the check valves causes them to open (0.30)

when pool level decreases to the piping penetration (0.40)

the vacuum is broken thus stopping the siphon effect (O.30)

thereby, keeping the core covered.

(0.25)

REFERENCE ULR SAR, pgs 4-24 to 4-25'

.

G

>

!

(

i

,

,

-

- - - - - _

,,-.m_.

....

_.

_. _ _ - _

_.,. _ _,... _ _,

,

,_, _ _ _ _,

, _ _ _.,

.,.

,

_.

.,

.

Ec__SIONQ@BQ_QNQ_EME8QENCY_QPE86IINQ_P8QCEQUBES PAGE

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

ANSWER F.01 (2.00)

If the change does not alter the intent of the original procedure, the change may by approved by the Reactor Supervisor (0.50)

and implemented at once.

(O.50)

If the change is substantive in nature, the change shall be approved by the Reactor Safet~y Subcommittee

'

(0.25)

and the_Er.ofessor in Charge of Reactor (PICR)

(O.25)

and the change shall not be implemented prior to such approvals.

(O.50)

REFERENCE ULR TS, pg IV-42 ULR Authority Section of the Procedure Manual, pg 3 ANSWER F.02 (1.00)

At least two safety blades shall be withdrawn (0.50)

to at least 12 inches.

(0.50)

REFERENCE R.O.1, pg 4 ANSWER F.03 (2.00)

1 rem /hr (0.50 each)

100 times MPC 15 minutes all but essential personnel must be evacuated REFERENCE E.O.1, pg 1 ANSWER F.04 (1.00)

Shut down the reactor by running in the unstuck blades and the regulating rod.

(1.00)

_

y--

-

.,

-

.

,

.

Ez__SleND@BD_6ND_EMEBGENCY_QEE8811NG_EBOCEDUBES PAGE

.

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

REFERENCE E.O.7, pg 1 ANSWER F.05 (2.00)

i 1.-

Conductivity (0.50)

Minimize chances of corrosion (O.50)

2.

Radioactivity (O.50)

Allow early determinati'an of significant buildup of radioactivity due to reactor operation or the Co-60 source.

(0.50)

REFERENCE ULR TS, pgs IV-33 & IV-34 ANSWER F.06 (2.10)

1.

Immerse RTD and thermometer into ice bath (0.30)

As necessary adjust the zero setting of the recorder (O.30)

2.

Immerse RTD and thermometer into hot bath (0.30)

As necessary adjust ~the span' control of the recorder (0.30)

3.

Repeat steps 1 & 2 until no furth'er adjustments are necessary (0.30)

4.

Check linearity by allowing both to come to room temperature (0.30)

Repeat above process until no further adjustments are required (0.30)

REFERENCE S.P.12, pgs 1-2 ANSWER F.07 (2.00)

a.

False (0.40 each)

b.

False c.

True d.

True e.

False REFERENCE R.O.16, pg 1

-

.

. *

~~Ec__SIOND66D_QND_EMEBGENCY OPERATING PRQCEDURES PAGE 32

' ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

ANSWER F.08 (1.50)

1.

Scram and secure the reactor.

(0.30 each)

2.

Notify Health Physics.

3.

Close the containment system.

4.

Evacuate the building.

5.

Account for all personnel that were in the cantainment building.

REFERENCE E.O.2, pg 1

.

' ' ANSWER F.09 (1.90)

Stack monitor activity high should be investigated first (0.90)

as this could result in an immediate release to the public (1700)-

REFERENCE CAF

,

.

e Gr__RODIOTION_ CONTROL _AND_SQFETY PAGE

e ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

ANSWER G.01 (2.50)

a.

5(N-18)

50 REM (O.30)

=

Total lifetime to date = 48 + 1 = 49 REM Total lifetime available = 50 - 49 = 1 REM (0.30)

Total this quarter available = 3 - 1 = 2 REM (0.30).

Lifetime is more restrictive than quarterly limit O.85 REM /HR gamma + (.03 RAD /HR) (10 OF) neutron =1.15 REM /HR dose rate (0.30)

1.0 REM /1.15 REM /HR = 0.87 HRS = 52 MIN (0.30)

EO.2 for using the conservative quality factor]

b.

25 REM whole body one time exposure (0.50)

c.

Emergency Director & Radiation Safety Officer (0.25 each)

REFERENCE 10 CFR 20 E Plan, pg 8 ANSWER G.02 (2.00)

Assume a point source (0.50)

D1 D2 (0.60)

________ =

=____

(R2)(R2)

(R1) (R1)

1800 mrem /hr 80 mrem /hr (0.60)

____________ = __

(R2)(R2)

(2m)(2m)

R2 = 9.49 meters (0.30)

REFERENCE Glasstone & Sesonske, Nuclear Reactor Engineering, pg 569 l

. - -

__

_

.

,

.

G __B0010II9N_CQNIBQL_8NQ_SOEEIY PAGE

'

"

.

ANSWERS -- UNIVERSITY OF LOWELL-86/09/17-NORRIS, B.

S.

ANSWER G.03 (1.50)

1.

Safe shutdown and securing of the reactor (any 3 at 0.50 each)

2.

Inform the on-duty SRO of observed action levels 3.

Take immediate actions as necessary to minimize reactor damage 4.

Take immediate actions as necessary to minimize radioactive release REFERENCE E Plan, pg 5 ANSWER G.04 (2.50)

Category I (any one)

'

(O.50 each)

Stack Monitor Reactor Constant Air Monitor (CAM)

Category II (any three)

Building Exhaust Planum Bridge Opposite Thermal Column Control Room

,

.

Category III (any one)

,

F.

P.

Monitor Core Exit Line REFERENCE ULR SAR, pgs 10-18 & 10-19 l

ANSWER G.05 (2.00)

l CAF

_(ryxMA (0.50)

Type of detector 2y_cz-[rp<a g_ty_[jn_3azm_y_q(Qe k}_cf_r fpdf)'.CC)

!

Operation of detector b Sit 3&-4212.2LbgF L ocW-An.rl.c2c.d cluY}]]p-cA27-St.rc//u'

--

(C' f.D---

2 nam-t v dt2clu-rfc1cf1.- w]:du 2Z2L vr1drem-ta--

--- c.& le s RJi.c zef-cacr~2-

_

fe:scL--

-

I Neutron radiation (0.50)

I

'

REFERENCE l

ULR SAR, pg B-8

-

.

-

Ge__ RAD 16IlgN_CQNIRQL_6ND_S@EEIY-PAGE

,

-.

-86/09/17-NORRIS, B.

S.

ANSWERS -- UNIVERSITY OF LOWELL ANSWER G.06 (1.50)

1.

Non-Reactor Safety Related Events 2.

Notification of Unusual Events 3.

Alert

".

Site ^ rc Errr;rncy

-

o, q o o, j c,

.

(&dMF each, {h4MFfor correct order)

',

5.

Ernrral E r geary s-2.

REFERENCE ULR E-Plan, pgs 8-11 ANSWER G.07 (2.00)

a.

Ar-40 + n (0.50)

--> Ar-41 (0.50)

b.

Radioactive corrosion products (0.50 each)

Fission products REFERENCE 21 & 7-2 ULR SAR, pgs 7

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-

,

.-.

,

i

!

l

_.

. - _ _..

-_

,

.

,

a

L

-

.__

.i

..-_n

.,!

.

_

,

..

emum y----

-_----.w.

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

--

g,p

,.,

, - - - - - - - - - - - - -

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

.,,__

,

a

TEST CROSS REFERENCE PAGE

0 QUESTION VALUE REFERENCE

- - - _

__

--

,

A.01 2.50 BSNOOOO312 A.02 2.00 BSNOOOO313 A.03 1.50 BSNOOOO314 A.04 2.00 BSNOOOO315 A.05

~i'.' OO BSNOOOO316

-

--

A.06 2.25 BSNOOOO317 A.07 1.75 BSNOOOO318

-_

14.00 B.01 3.00 BSNOOOO321 B.02 1.50 BSNOOOO322 B.03 2.00 BSNOOOO323 B.04 2.00 BSNOOOO344 D.05 1.50 BSNOOOO325

.

B.06 1.00 BSNOOOO326 B.07 3.00 BSNOOOO327

__

14.00 s

C.01 2.50 BSNOOOO329 -

C.02 2.00 BSNOOOO330 C.03 2.00 BSNOOOO331

C.04 2.00 BSNOOOO332 C.05 2.50 BSNOOOO333 C.06 2.00 BSNOOOO335 C.07 1.00 BSNOOOO341

___

14.00 D.01 2.10 BSNOOOO336 D.02 2.50 BSNOOOO337 D.03 2.50 BSNOOOO338 D.04 1.50 BSNOOOO340 D.05 2.50 BSNOOOO342 D.06 2.00 BSNOOOO324 D.07 1.00 BSNOOOO345

______

14.10 E.01 1.00 BSNOOOO346 E.02 2.00 BSNOOOO347 E.03 2.40 BSNOOOO348 E.04 2.50 BSNOOOO349 E.05 2.50 BSNOOOO350 E.06 2.00 BSNOOOO351 E.07 2.00 BSNOOOO352 14.40 F.01 2.00 BSNOOOO353

-

O

!

TEST CROSS REFERENCE PAGE

c OUESTION VALUE REFERENCE

__

______

__________

F.02 1.00 BSNOOOO354 F.03 2.00 BSNOOOO356 F.04 1.00 BSNOOOO357 F.05 2.00 BSNOOOO358 F.06 2.10 BSNOOOO359 F.07 2.00 BSNOOOO360 F.OB 1.50 BSNOOOO361 F.09 1.90 BSNOOOO362 15.50 G.01 2.50 BSNOOOO363 G.02 2.00 BSNOOOO364 G.03 1.50 BSNOOOO365 G.04 2.50 BSNOOOO366 G.05 2.00 BSNOOOO367 G.06 1.50 BSNOOOO368

--

G.07 2.00 BSNOOOO369

______

14.00

______

100.00

v t e Inspection Report - University of Lowell - 1986003
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 \| 25 \|
1986 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle Security Operator Exams Emergency Planning Other

IR 05000223/1986003

Text

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