ML20202F774

Exam Rept 50-298/0L-86-01 on 860303-07.Exam Results:Eight Candidates Passed All Portions of Exam & Three Failed

ML20202F774
Person / Time
Site:	Cooper
Issue date:	04/02/1986
From:	Cooley R, Graves D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20202F715	List: ML20202F712 ML20202F774
References
50-298-0L-86-01, 50-298-L-86-1, NUDOCS 8604140221
Download: ML20202F774 (75)

Text

-

EXAMINATION. REPORT 50-298/0L-86-01 v.

Facility Licensee:

Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 Facility Docket No.:

50-298 Facility License No.:

DPR-46 Operator License examinations administered at Cooper Nuclear Station (CNS)

Chief Examiner:

J //

h vA/,3 6 D. R. Graves Date b/f

(.

A>

Approved By:

H. A. Cooley, Chip r, Operator Licensing Ddte ' ~

Section U

Summary Examinations were administered to seven Reactor Operator candidates and four Senior Reactor Operator candidates.

Eight of the candidates passed all portions of the examination and have been issued the appropriate license.

pgTen Wi"g=

V

i DETAILS 1.

Persons Examined Pass Fail Total SRO Candidates 4

0 4

R0 Candidates 4

3 7

2.

Examiners D. N. Graves, (Chief Examiner), NRC J. L. Pellet, NRC J. E. Whittemore, NRC 3.

Examination Report Performance results for individual candidates are not included in this report.

a.

Examination Review Comments and Resolutions This section reflects the comments made by the facility during the examination review conducted following the written examination. The comments accepted by the NRC reviewers have been incorporated into the master copfes of the examinations included in this report.

Comments and resolutions are listed by section and question number.

Question Number Comment 1.01e and 5.01e Question could be misinterpreted to think that control rod pattern change to being the same as control rod adjustn.ents and an answer of FALSE could be accept-able with this assumption. We use control Rod Sequence change rather than pattern change in our terminology.

Resolution:

Accept if above assumption stated by candidate.

1.02c An answer of increase could also be justified by an increase in available NPSH due to increase in subccoling form the decrease in power. Part b of the question assumes that this can occur.

Recommend also accepting this explana-tion.

Reference:

HTfF manual page 7-96 l

L

o

~9 f l l

Resolution:

Agree. Answer key modified 1.04 The answer could also be explained using factors of the 6 factor formula.

Resolution:

Acceptable 1.09 and 5.03 The void change is insignificant of this change in power. Figure 52 of the reference material showns insignificant changes at higher power levels.

(

Recomend accepting no change based on candidates justification.

Reference:

Rx Physics Review figure 52.

Resolution:

Disagree. Question and answer stand as.

written.

2.03 and 6.02 A recent plant change has included an interlock that if the valve is not I

partially open within 1 minute after a pump start the pump will trip.

The candidates have been infonned of this change.

Recomend accepting this as a possible answer.

Reference:

Attached letter from Senior Engineer.

Resolution:

Accepted. Answer key modified.

2.05c Question implied a single interrelation-ship, however, answer required three responses. Recomend accepting any one of the three responses for full credit.

Resolution:

Disagree. Not accepted.

2.05d

" Backup scram valves" should be acceptable for valves 140A and 1408.

SDV isolation test valve is powered from CCP vice 125V DC.

(lessonplanisincorrect) Recomend removing SDY isolation valve as a required answer.

Reference:

RPS Elementary Diagram 791E256. These interrelationships are not required by the objectives of the student text.

Resolution:

Accepted. Answer key modified.

L

s 2.06a and 6.04a Loss of plant air would cause a failure of the hotwell level control systems which will cause a decrease in hotwell level and would result in a decrease in vacuum.

Recomend accepting this answer.

Reference:

Plant Air page 16.

Resolution:

Disagree. Not accepted 2.06b and 6.04b A loss of plant air would cause the filter demineralizer flow control valve to close.

This will result in the pumps tripping on low flow.

No isolation will result from loss of plant air.

Recomend accepting a pump trip as an answer.

Reference:

RWCU Lesson Plan, page 18, section b.1.

Resolution:

Agree. Answer key modified.

2.09a The coolers on the RHR pumps cool both seal water and bearing water.

The lesson plan is incorrect and has been recently changed.

Recomend accepting either seal water cooling or bearing water cooling.

Reference:

RHR pump technical manual.

Resolution:

Agree. Answer key modified 2.11 If a locked valve is opened it must be unlocked first. Recomend deleting requirement to state unlock the valve first.

Resolution:

Accepted 2.12 Answer lists loads or uses upstream of the pressure maintenance pressure control valves and with this in mind the following additional uses should be acceptable which are also upstream:

1.

Source of water to the vessel per E0P's.

2.

Dryer separator pit 3.

Various Reactor Building loop seal maintenance.

4.

Refueling floor service boxes.

5.

Torus water makeup i

s I :

The core spray lesson plan cnly lists some general uses and is not a complete list of uses.

Reference:

Burns and Roe Drawing 2049.

I-Resolution:

Agree. Answers added to key.

3.01 and 6.01 Answer states in part "and provides a signal to the count circuit." The reference states "... sends a signal i

to the count circuit, indicating whether or not its input is operable." The examiner should realize that this is a t

simplified explanation and the important part of the answer is that the count circuit considers the input "not operable." The excerpt from the GEK shows that in actuality, a signal is L

provided when the input is considered operable and removed when the input is l

considered not operable. Recomend not requiring the student state that a signal is sent to the counting circuit

'for full credit.

Reference:

RBM l

Student Text page 9.

RBM GEK-34550 (attached).

Resolution:

Agree. Answer key modified.

l i

3.02b For the NORMAL position the candidate L

may respond as when using group notch control instead of 50% rud density.

These are the same terms. Recomend accepting this answer.

Resolution:

Considered during grading.

3.05 The question did not require setpoints.

Recomend not requiring setroints for correct answer.

I j

Resolution:

Setpoints are not required.

3.06b The question did not specify an operating mode. Operation of the OPC test switch will also cause an OPC action to occur.

Recomend accepting placing OPC test switch to test.

Reference:

Deli Student Text page 13.

Resolution:

Agree. Answer key modified.

i 3.07a Answers a and f should be accepted because individual APRMs can be bypassed with the joystick.

Reconsnend accepting answers a and f with manual bypass.

Resolution:

Not accepted. The RPS SCRAM functions from the above inputs still function and have a sufficient number of active inputs to actuate.

3.08a and 6.06a A group I isolation causes the Main Steam Line Isolation valves and Main Steam Line Drain Yalves to close.

Reconsnend allowing (0.6 points) for stating group I isolation.

Reference:

Technical Specifications page 52.

Resolution:

Accepted.

3.09 and 6.07 The answer is correct, however, the candidate may discuss that the tripping logic is a two out of three tip logic.

Reconsrend not requiring this information but not deducting for candidates who use this information to explain thcir answer.

Reference:

Nuclear Boiler Instrumentation page 16.

Resolution:

Accepted.

4.02 and 7.09 This information is taken from the discussion and supplementary action portion of the procedure and should riot be required knowledge for a written examination.

Resolution:

Disagree. The information is consicered pertinent for emergency operation of the plant and is well within the field of required knowledge.

4.07b and 7.07b Question talks of "A Core Density." We always talk about quantity of rods withdrawn in terms of " Rod Density" which is the inverse of " Core Density."

Candidates may not have recognized " Core Density" as being different from " Rod Density." Recontrend deleting part b of the question, i

i

~7-Resolution:

Not accepted.

Information is directly from plant material.

4.08b and 7.11b There are other indications of a relief valve closing such as steam flow indica-tions changing, reactor level changing (transient), variations in reactor pressure occurs, suppression pool level stops increasing, unusuel load rumbling in reactor building stor.s. etc. 'lecommend accepting any reasonable answer.

Resolution:

Accepted. Answer key mcdified.

5.02 Chapter 9 of the Heat Transfer and Fluid Flow Text lists the following factors that affect PCI:

1.

Absolute Power 2.

Increase in Power 3.

Duration of Power Increase 4.

Previous Power History 5.

Fuel Exposure The text also discusst.s that an embrittling agent (Iodine or Cadnium) is required for PCI to occur. Stress must also be present for PCI to occur.

Recommend accepting item included on this list also as acceptable answers.

Reference:

HTFF pages 9-107 and 9-108.

Resolution:

Agree. Answer key modified.

5.04 The curve at point "C" may be higher than point "A" depending on fuel load.

This is referred to in Technical Specification basis as "R" factor.

Recomend accepting curves that show point "C" higher than point "A".

Reference:

Technical Specifications Basis for Sections 3.3 and 4.3.

Resolution:

Accepted.

5.05a Answer will be dependent upon whether the candidate assumes that the recircu-lation pump is adding heat or not.

Recomend accept answers based on candidates assumptions concerning whether the pump is adding heat or not.

l

=.-

l l

Resolution:

Agree. Answers were graded based on any stated assumption.

5.06 SR0 candidates should only be required to discuss the theory of the plant on which they are licensing and not theoretical reactors.

Recommend deletion-of the question.

Resolution:

Not accepted. The theory knowlerige required is identical, as is the application of that theory.

5.06a Formula T = ti/In2 is not listed in the stated reference and should not be required knowledge for correct answer.

Recomend not requiring the formula specified but allow credit for any correct means used by the candidate.

Resolution:

Agree. Answers graded accordingly.

5.06c The size of the experimental reactor was stated so candidates answers will be based on the size that they assumed.

Recommend basing answer on size of reactor assumed by the candidate.

Reference:

Reactor Physics page'22.

Resolution:

Agree. Answers graded based on any assumptions made.

5.08 Tritium is not a fission product. BWR chart of the nuclides indicates that Tritium is caused by neutron activation of a hydrogen atom. Recommend deleting Tritium as a required answer for full credit. Reference BWR Chart of the Nuclides.

Resolution:

Disagree. The provided reference states that tritium is produced in ternary fission. Answer stands as written.

6.10 There are 2 EPA's per power supply for a total of eight. Candidate may answer as 2 per power supply. Recommend accepting

[

2 per power supply.

Reference:

RPS Student Text page 7.

l

o 4 Resolution:

Not accepted. _Two per power supply does not provide the desired information.

7.01 Five separate actions must occur even though they are listed as three steps in the procedure. Recommend accepting stopping MG set-lube oil. pumps after the MG set stops as a separate acceptable answer.

Reconwend accepting 4 of 5 for full credit.

Reference:

Emergency Procedure 5.2.3.

~ Resolution:

Considered during grading.

7.05 Performing an 00-7 is another means of verifying rods fully inserted even though it is not listed in the procedure.

Reconwend accepting performance of an 00-7.

Reference:

E0P-1 page 3 of 46.

Resolution:

Not accepted. 00-7 is not listed in the question-referenced procedure.

8.02c Since the Key Custodian maintains control to the main key depository he will have to be contacted to obtain duplicate keys.

Reconnend accepting contact key custodian also.

Reference:

Administrative Procedure 1.3 page 1.

Resolution:

Agree. Answer key modified.

8.08 Specific examples which demonstrate a knowledge of what types of things have to have temporary modifications should be accepted.

(i.e. spool pieces for mechanicaljumpers)

Reference:

Conduct of Operations Procedure 2.07 page 2.

Resolution:

Agree.

Candidates responses evaluated for applicability to tie temporary modifications criteria, b.

Exit Meeting Summary At the conclusion of the site visit, the examiners met with utility 1

l representatives to discuss the results of the examinations. The l

following personnel were present at the exit meetings:

o

.. NRC Facility C N. Graves R. D. Blain J. E. Whittemore R. Brurgardt G. R. Horn R. 4. Jansky M. Parrish i

K. P. Patek D. Shallenberger Mr. Graves started the meeting by informing the attendees of the preliminary results of the oral operating examinations.

Three Reactor Operator candidates were not clear passes as of the exit meeting. Other items discussed were as follows:

(1) The SR0 candidates, in general, had difficulty determining which systems were safety-related or where this was specified for clearance order purposes.

(2) The terrporary alteration sheet had no blank for a verification (second) signature, even though it may be required for safety-related system restoration.

(3) The operating crews were very helpful in the control room.

(4) The plant was very clean which made the plant walkthrough portion of the oral examination easier.

No generic or widespread candidate weaknesses were noted during the site visit and the utility was so informed.

The meeting concluded with the examiners thanking the facility staff for their cooperation and efforts during the site visit and informing them that results would be forthcoming as soon as possible.

l l

l

EQUATION SHEET f = ma v = s/t Cycle efficiency = (Networu out)/(Energy in) 2

~

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

[ =,%

KE = 1/2 my a = (Vf - V,)/t A = AN, A = A,e' PE = mgn Vf = V, + at w = e/t A = An2/t1/2 = 0.693/t1/2 u = y. ap t

eff = [(tv>)(tll ifz a

[(t1/2)*I*b))

aE = 931 am I' = I,e * *

~

Q = aCpat Q = UAat.

I = I,e'""

I = I, 10**/U L Pwe = W ah y

TYL = 1.3/u sur(t)

P = P 10 HYL = -0.693/u p = p e /T t

o SUR = 25.06/T SCR = S/(1 - K,ff)

CR, = S/(1 - K,ff,)

SUR = 25s/1= + (s - o)T CR (1 - K,ffj) = CR II ~ eff2)'

4 j

Z T = (t=/a) + [(s - s)71o]

M = 1/(1 - K,ff) = CR /G, j

T = 1/(o - s)

M = (1 - K,ff,)/(1 - K,ffj)

T = (a - s)/(le)

SDM = (1 - K,ff)/K,ff a = (K,ff-1)/K,ff = AK,ff/K,ff 1* = 10-5,,,,,q, T = 0.1 seconds ~I e = [(1*/(T K,ff)] + [i,ff (1 + AT)]

/

Idlj=Id 2,2 7 P = (reV)/(3 x 1010)

Id gd j

22 2

I = oN R/hr = (0.5 CE)/d (meters)

R/hr = 6 CE/d2 (feet)

Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lbs.

I curie = 3.7 x 1010dps 1 ga:. = 3.78 liters 1 kg = 2.21 lbm 1 f t- = 7.48 gal.

I hp = 2.54 x 103 8tu/hr censity = 62.4 lbs/ft3 1 mw = 3.41 x 100 stu/hr Density = 1 gm/c.9 lin = 2.54 cm i

Heat of vaporization = 970 stu/lem

'F = 9/S*C + 32 Heat of fusion = 144 Stu/lbm

'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg.

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

2

U.

S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

_QQQEER__________________

REACTOR TYPE:

_RWB:6El_________________

DATE ADMINISTERED:_Rh40220$________________

EXAMINER:

_GB8VEft_Qi______________

APPLICANT:

INSIBWQIl0N1_IQ_8EELIQ8 nil Uao separate paper for the answers.

Write answers on one side only.

Stcple question sheet on top of the answer sheets.

Points for each qu:stion are indicated in parentheses after the question. The passing gecde requires et least 70% in each categor; and a final grade of et 1ccet 80%.

Examination papers will be picked up six (6) hours after tha examination starts.

% OF CATEGORY

% OF APPLICANT'S CATEGORY

__V8LUE

_IQI6L

___lGQBE___

_V8LUE__ ______________Q8IEQQBl_____________

_2EAQQ _ _25t00

________ 1.

PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

_21A00__ _25t99

________ 2.

PLANT DESIGN INCLUDING SAFETY f

AND EMERGENCY SYSTEMS

_25AQQ__

25t0E

________ 3.

INSTRUMENTS AND CONTROLS

_2EAQQ-- _25AQQ

________ 4.

PROCEDURES - NORMAL, ABNORMAL, i

EMERGENCY AND RADIOLOGICAL CONTROL r

\\

1DQiGQ__ 100t0D

________ TOTALS j

FINAL GRADE _________________%

All tork done on this examination is my own. I have neither given nor received sid.

APPLICANT'S SIGNATURE

Iz__EBINGIELE1_QE_NUGLEeB_EQWEB_ELeNI_QEEB8110Ni PAGE 2

IBEB50Q1NadlGit_BE61_IB6HSEEB_8NQ_ELulD_ELQW QUESTION 1.01 (3.00)

Answer the following with regard to the Control Cell Core (CCC) operating otrategy:

o.

What constitutes a CONTROL CELL 7 (0,5) b.

How many control cells will be used at CNS?

(0.5) c.

While operating at power, what is the position of the non-control cell control rods?

(0.5) d.

Why do control rod movements result in a lower kw/ft change per notch in a CCC than in a conventional core?

(1.0) o.

TRUE or FALSE.

Using the CCC operating strategy eliminates the need for control rod pattern changes.

(0.5)

QUESTION 1.02 (3.00) l For each of the following parameter changes, indicate the effect l

Cincrease, decrease, or no change) it has on AVAILABLE net positive ouction head to the Main Condensate Pumps.

Briefly EXPLAIN your l

cnswer.

Consider each change separately.

l o.

Lower condenser hotwell level (1.0) b.

Change in condensate subcooling from 1 deg F to 2 deg F (1.0) l c.

Reduction in plant power level (1.0) l l

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

It__EBINQ1 ELE 1_QE_NUQLE68_EQWEB_EL6NI_QEEB6I1QNt PAGE 3

IBESdQQ1Nad1Q1t_BE6I_IB6H1EEB_6NQ_ELulD_ELQW i

QUESTION 1.03 (2.00)

M3tch er.ch of the four lettered items with one of the numbered items.

A letter-number sequence is sufficient.

(2.0) 1.

MAPRAT 5.

PCIOMR 2.

APLH6R 6.

CHF l

3.

CPR 7.

TOTAL PF 4.

FLPD 8.

LH6R

_____a.

Parameter by which plastic strain and deformation are limited to less than 1%.

_____b.

Ratio of bundle power required to produce onset of transition boiling somewhere in the bundle to actual bundle power.

_____c.

Parameter by which peak clad temperature is maintained less than 2200 degrees F during postulated design basis accident.

_____d.

Contains guidelines restricting power ramp rates above the threshold power.

QUESTION 1.04 (3.50)

An increase in void content in an operating reactor causes a negative roactivity insertion.

Describe three (3) eff,ects that cause the roactivity insertion to be negative.

Include WHICH of the three offects is the largest.

(3.5)

QUESTION 1.05 (2.00) o.

The reactor is operating at 100% power and flow.

Explain what happens to core flow, and why, with a reduction in power by control rod insertion.

Assume recirculation pump speed remains constant.

(1.0) i b.

At low power conditions, an increase in reactor power by control rod withdrawal will (INCREASE, DECREASE, or NOT CHANGE) flow through the core.

Choose the correct answer and BRIEFLY explain your choice.

Assume recirculation pumps are running.

(1.0)

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

Iz__EBINQ1 ELE 1_QE_NUQLEaB_EQWEB_EL8NI_QEEBaIIQNt PAGE 4

IBEBdQQIN8510ft_BEeI_IB6HEEEB_eND_ELVlQ_ELQW QUESTION 1.06 (2.00)

The reactor is operating at high power under steady state conditions.

I A control rod is withdrawn one notch.

The time required for power to otabilize is noted.

Now the control rod is inserted one notch.

The time for power to again stabilize is noted.

Which transient should tcke longer for neutron power to stabilize and why?

(2.0)

QUESTION 1.07 (2.00) l In Operating Procedure 2.1.3, Approach to Critical, it is stated that roactor period can be calculated by multiplying the time (in seconds) that it takes the power to double by 1.443.

How is this factor datermined?

(2.0) l l

QUESTION 1.08 (2.00) l For each of the following, choose the correct word in parentheses:

(2.0) o.

The moderator temperature coefficient can be positive at (HIGH/ LOW) moderator temperatures.

b.

The moderator temperature coefficient is (LESS/MORE) negative l

at EOL.

c.

The Doppler coefficient tends to be (LESS/MORE) negative at high fuel temperatures, and (LESS/MORE) negative at high moderator i

temperatures.

d.

The Doppler coefficient is more negative at (BOL/EOL).

o.

The void coefficient is (LESS/MORE) negative at high void fractions.

f.

The void coefficient is (LESS/MORE) negative at high fuel temperatures.

g.

The void fraction is nost negative near (BOL/EOL).

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

Ix__EBINCIELEl_QE_NWGLE88_EQWEB_EL6NI_QEEBSIIQNt PAGE 5

IBEBdQQ1NadIG1t_BE6I_IB8NSEEB_aNQ_ELUID_ELQW QUESTION 1.09 (3.00)

Indicate HOW (increase, decrease, unaffected) control rod worth changes for each of the situations listed below.

EXPLAIN WHY the rod worth is affected, if applicable.

c.

The reactor is heated f rora 100 deg F to 200 deg F (1.0) b.

Reactor power is increased from 20% to 40% by control rod withdrawal (1.0) c.

Reactor power is increased from 70% to 90% by increasing recirculation flow (1.0)

QUESTION 1.10 (2.00)

During a reactor shutdown, the vessel pressure decreased from 800psig to 350 psig in one hour.

Does this violate any operational limit?

SHOW your work and JUSTIFY your answer.

(2.0)

QUESTION 1.11

(.50)

Which of the following describes the principle that takes place in the throat of a venturi flow element.

(0.5) c.

The fluid velocity increases and the fluid pressure increases.

b.

The fluid velocity increases and the fluid pressure decreases.

c.

The fluid velocity decreases and the fluid pressure increases.

d.

The fluid velocity decreases and the fluid pressure decreases.

(***** END OF CATEGORY 01 *****)

2t__EL8HI_DE11GN_INGLUDING_18EEII_8NQ_EMEBGENGl_111IEdi PAGE 6

QUESTION 2.01 (2.00)

What are four (4) functions of the venturi-type flow restrictors welded in occh main ateam line, between the last relief valve and the inboard main oteam isolation valve?

(2.0)

QUESTION 2.02 (2.00)

What are four (4) methods or sids for checking fuel orientation when fuel is positioned at the final stage during refueling?

(2.01 QUESTION 2.03 (2.00)

Describe two (2) interlocks that are associated with the Reactor Rocirculation System motor operated recirc pump discharge valves.

(2.0)

QUESTION 2.04 (1.00)

What would happen if the recirc pump MG set voltage regulator did not roduce the generator output voltage when generator frequency (pump speed) decreased?

Why does this effect occur?

(1.0) 4 QUESTION 2.05 (3.00)

Explain for each system given below, the relationship or interface uith the Control Rod Drive Hydraulic system (CRDH).

Be specific cbout CRDH components which interface with each.

a.

Domineralized Water System.

(0.75) b.

Reactor Equipment Cooling System.

(0.75) c.

Reactor Building Equipment Drain System.

(0.75) d.

125 V DC.

(0.75)

(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2t__EL8HI_QE11EN_INCLUDINE_18EEI1_eNQ_EdEBEENCX_111IEd1 PAGE 7

QUESTION 2.06 (3.00)

Explain how AND why a complete loss of the plant air system, while cperating at full power, with no operator action, would affect the following plant parameters or components.

a.

Main condenser vacuum.

(0.75) b.

RWCU operation.

(0.75) c.

Main Steam Isolation Valves.

(0.75) d.

Control Rod position.

(0.75)

QUESTION 2.07 (2.50)

List the six (6) components which constitute a filter train of the Standby Stanoby Gas Treatment System (SGT), in the correct flow path.

(2.5)

QUESTION 2.08 (1.50)

What are three (3) conditions which will cause an automatic transfer from the inverter to the AC supply in the No-Break Power System?

(1.5)

QUESTION 2.09 (3.00) c.

The REC system provides essential cooling to what critical equipment?

(2.0) b.

Briefly describe how cooling to the critical loads is accomplished if the REC system is incapable of providing sufficient cooling.

(1.0)

QUESTION 2.10 (3.00) e.

What condition (s) must be met in order for a manual isolation of HPCI to be performed?

(1.0) b.

A LOCA has occurred and HPCI initiated, operated, and tripped on high level.

Level is now 37 inches and decreasing.

How can the system be restarted?

TWO METHODS REQUIRED.

(2.0)

(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2i__INSIBudENI1_8ND_CQNIBQL1 PAGE 9

QUESTION 3.01 (2.50) o.

List three (3) ways that the Rod Block Monitor (RBM) may be bypassed.

Include automatic and/or manual bypasses.

(1.5) b.

How does the RBM utilize the input from a LPRM detector that is failed HIGH or failed LOW 7 DISCUSS BOTH cases, but limit your answer to how the LPRM input is considered in the averaging and counting circuits.

Assume the LPRM recently failed and has NOT been bypassed with its individual bypass switch.

(1.0)

QUESTION 3.02 (2.00) o.

How does the Rod Sequence Control System (RSCS) indicate that all rods in a group have beer.- moved as desired?

(0.5) b.

When is the RSCS sequence mode selector switch placed in each of its three positions (withdraw, insert, & normal)?

(1.5)

QUESTION 3.03 (2.00)

What are five (5) systems or places to which the Rod Position Information System (RPIS) provides position information?

(2.0)

QUESTION 3.04 (2.50) o.

How can all rods be manually de-selected by the operator?

(1.0) b.

When is this action normally performed?

(1.0) c.

What equipment problem is avoided by de-selecting all rods?

(0.5)

QUESTION 3.05 (3.00) o.

What are 4 conditions that can cause a scoop tube lockout?

(1.0) b.

What must be: done to reset a scoop tube lockout?

(1.0) c.

How can the MG set speed be changed when a lockout is present?

(1.0)

(*****

CATEGORY 03 CONTINUED ON NEXT PAGE *****)

2t__ELeNI_DE11EN_ INCLUDING _18EEII_8ND_EMEBEENCX_111IEdi PAGE 8

QUESTION 2.11 (1.00)

What is the alternate source of water for the Core Spray system and that action (s) is(are) necessary to line it up?

(1.0)

QUESTION 2.12 (1.00)

Give four (4) uses for the CSCS Pressure Maintenance System?

(1.0) 4

(***** END OF CATEGORY 02 *****)

21__IN1IBW5ENI1_6ND_CQNIBQL1 PAGE 10 QUESTION 3.06 (3.00)

Answer the following with regard to the DEH System:

o.

What are the three (3) inputs to the pressure controller (s)?

(1.0) b.

Other than overspeed, what will activate the Overspeed Protection Control (OPC) system?

Include conditions necessary for the system to activate.

(1.0) c.

The plant is operating at full power.

Briefly describe the plant response to a failing pressure controller (controller output is INCREASING slowly to maximum).

(1.0)

QUESTION 3.07 (3.00)

Which of the following REACTOR PROTECTION SYSTEM scrams can be bypassed?

Describe HOW each is bypassed.

(3.0) c.

APRM high flux or power b.

Scram discharge volume high level c.

MSIV closure d.

Manual o.

Turbine control valve fast closure f.

APRM inoperable QUESTION 3.08 (3.00)

For each of the process radiation monitors listed below, state what type of detector is used and any automatic actions directly initiated by that radiation monitoring system.

EXCLUDE ANNUNCIATORS.

(3.0) c.

Main steam line radiation monitor b.

RBCCW (REC) c.

Air ejector off gas radiation monitoring system

(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

21__IN11BudENI1_8HQ_CQNIBQL1 PAGE 11 l

1 QUESTION 3.09 (2.00)

During operation of the Feedwater Control System, level control chould be selected to channel B to ensure overfill protection is in effect.

How does selecting channel B for level control ensure overfill protection is provided?

(2.0)

QUESTION 3.10 (2.00)

Match each of the following actions / interlocks with the RPV level oystem it uses for actuation.

(2.0) c.

RCIC initiation 1.

Wide Range Yarway b.

HPCI turbine trip 2.

Narrow Range Yarway c.

Diesel Generator start 3.

Narrow Range GEMAC d.

RPS level scram 4.

Bartons o.

Main turbine trip f.

Feedwater level control g.

RHR containment spray control h.

Recirculation pump trip l

(*****

END OF CATEGORY 03 *****)

4 __PBQQEQUBE1_ _NQBd8Lt_8tNQBd8Lt_EMEBQENQ1_8NQ PAGE 12 t

8801QLQQIQ8L_GQNIBQL QUESTION 4.01 (1.00)

Match the class of fires listed below (A - D) with the materials (1.0) involved (1 - 4).

CLASS OF FIRE MATERIALS INVOLVED

______A.

Alpha 1.

flammable liquids, gases, or gresses

______B.

Bravo 2.

combustible metals

______C.

Charlie 3.

ordinary combustibles (paper, wood, etc.)

______D.

Delta 4.

energized electrical equipment QUESTION 4.02 (2.50)

A loss of all site AC power has occurred. Answer the following questions concerning E0P 5.2.5.1, Loss of All AC Power Station Blackout.

c.

What reactor water level indication (s) are available in the control room following this event?

(1.0) b.

What reactor water level indication (s) are available outside the control room following this event?

(0.5) c.

Why should reactor pressure NOT be reduced below the saturation pressure corresponding to the maximum drywell temperature?

(1.0)

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

di__EBQGEQUBE1_=_NQBd8Lt_8BNQBd8Lt_EdEBGENGY_8NQ PAGE 13 B8DIQLQGIQ8L_GQNIBQL QUESTION 4.03 (2.00)

The plant is operating at power with a reactor pressure of 1000 psig.

State whether each of the following (a - e) would indicate a failure of the outer (#2) seal on a reactor recirculation pump.

(2.0) c.

Seal cavity #2 prussure indicates 50 psig b.

OUTER SEAL LEAK FLOW DET. HIGH alarm c.

Increase in drywell floor drain sump flow d.

Seal cavity #2 pressure of 800 psig o.

Increase in drywell equipment drain sump flow QUESTION 4.04 (2.00)

Indicate whether each of the following statements is TRUE or FALSE:

(2.0) o.

A reactor startup is NOT permissible under natural circulation flow conditions.

b.

A reactor startup is NOT permissible with only one recirculation pump in operation.

c.

If the reactor is operating at power (both recirculation pumps in operation) and one recirculation pump trips, reactor operation may continue for no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

A reactor recirculation pump may not be started if the reactor is in natural circulation flow and reactor power is greater than 1%.

4

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

. _ - - ~

at__EBQQEDMBE1_=_NQBd8Lt_8tNQBd8Lt_EMEBEENQ1_8NQ PAGE 14 B8DIQLQElG8L_QQNIBQL QUESTION 4.05 (2.00)

Answer the following questions concerning GOP 2.1.5, Emergency Shutdown from Power:

o.

After the manus 1 scram buttons are depressed, what two (2) checks should the operator make to verify all control rods inserted?

(1.0) b.

If it becomes necessary to shut the MSIV's after the scram, what are the two (2) methods stated in the procedure for accomplishing this?

(1.0)

QUESTION 4.06 (3.00)

MATCH each of the events (a - f) with the pressure at which the ovent may be performed during a cold plant startup per GOP 2.1.1,

" Cold Startup Procedure".

Items may be used more than once or not at all as appropriate.

(3.0)

_____e.

Begin placing feed pump in service 1.

25 psig

_____b.

Open HPCI steam isolation valves 2.

50 psig

_____c.

Steam seals placed in service 3.

100 psig

_____d.

Roset and unisolate RCIC 4.

150 psig

_____e.

Startup the SJAE 5.

350 psig

_____f.

Initially open the bypass valves 6.

500 psig s

QUESTION 4.07 (2.00) c.

What three (3) conditions determine when the plant is operating in HOT STANDBY?

(1.5) b.

In proceeding from power operation to Hot Standby operation, the normal shutdown procedure is followed except that rods are inserted to 1/4 core density.

What is meant by 1/4 core density?

(0.5)

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

I

at__EBQGEQQBE1_=_NQBd8Lt_8tNQBd8Lt_EdEBGENGl_8ND PAGE 15 88DIQLQGIC8L_GQNIBQL QUESTION 4.08 (3.00)

The plant is operating at power when an SRV inadvertently opens.

The operator cycles the SRV control switch to OPEN and back to AUTO.

The red light goes out and the green light for that valve illuminates.

a.

Is the above occurrence positive indication that the SRV has reclosed?

EXPLAIN.

(1.0) b.

Give four (4) other control room indications that can be used to verify closing of the SRV.

EXCLUDE ANNUNCIATORS.

(2.0)

QUESTION 4.09 (2.00)

The plant is operating at power with the A0G system operating.

The off-gas dilution fan trips and the standby fan will not start.

e.

What automatic action should occur due to the above condition?

(1.0) b.

How can the automatic action above be prevented?

(0.5) c.

What system can be used to provide dilution flow while attempting to restore the dilution fans?

(0.5)

QUESTION 4.10 (3.50) o.

EOP - 1, RPV Control, provides the operator with actions to control what three (3) maj o r RPV parameters?

(1.5) b.

What four (4) parameters are controlled by E0P - 2, Primary Containment Control?

(2.0)

QUESTION 4.11 (2.00) c.

How long can an operator stay in a 25 MREM /hr radiation field without exceeding a CNS administrative radiation exposure limit?

(1.0) b.

What action (s) should be taken by an individual who finds his/her pocket chamber dosimeter is reading greater than full scale?

(1.0)

J

(***** END OF CATEGORY 04 *****)

(************* END OF EXAMINATION ***************)

it__EBINQIELEl_QE_NUQLE6B_EQWEB_EL6NI_QEEB8IIQNt PAGE 16 IBEBdQQ1NedIQ1t_BE8I_IB8BIEEB_8ND_ELu1D_ELQW ANSWERS -- COOPER 86/03/04-GRAVES, D.

ANSWER 1.01 (3.00) e.

Four fuel bundles and a control rod (0.5) b.

25 (0.5) c.

Fully withdrawn (0.5) d.

All control rod movements are associated with low reactivity cells (1.0).

o.

True (0.5)

REFERENCE Fuel System Description, pg 18 ANSWER 1.02 (3.00) o.

Decrease (0.25).

The pressure to the pump suction is a function of the height of the water above the pump suction.

Less height means less pressure at the pump suction (0.75).

b.

Increase (0.25).

Available NPSH is actual pressure minus saturation pressure.

Increasing the subcooling reduces the saturation pressure, thus increasing available NPSH (0.75).

c.

Increase (0.25).

Reducing power reduces the flow rate and velocity in the suction line, thus line losses are reduced (0.75).

Also accept increase in subcooling as in part "b"

as explanation.

REFERENCE GE HTFF manual, pg 7-93 through 7-96 ANSWER 1.03 (2.00) c.

8 b.

3 c.

2 d.

5 (0.5 each)

REFERENCE GE Thermodynamics, Heat Transfer, and Fluid Flow, Chapter 9

li__EBING1 ELE 1_QE_NUGLE88_EQWEB_EL8NI_QEEB8I1QNm PAGE 17 IBEBdQQ1N851 Git _BE81_IB8NSEEB_88Q_ELu1D_ELQW ANSWERS -- COOPER

-86/03/04-6 RAVES, D.

ANSWER 1.04 (3.50) 1.

More neutrons will be captured in the resonant peaks of uranium and plutonium (1.0) as the slowing down length increases.

2.

More neutrons will be absorbed in control rods and other core structural materials (1.0) as the slowing down length increases.

3.

Neutron leakage increases (1.0).

This is the largest factor causing the coefficient to be negative (0.5).

REFERENCE Roactor Physics Review, pg 26, 27, 32 ANSWER 1.05 (2.00) o.

Core flow would increase (0.5) due to a decrease in two phase flow resistance (0.5).

b.

Core flow would increase (0.5) due to an increase in natural circulation (0.5).

REFERENCE Rocirculation System Description, Figure 19, Rev 0 ANSWER 1.06 (2.00)

The downpower transient should take longer to stabilize (0.5).

On a dewnpower transient, the rate of power change is limited to the rate of decay of the longest lived delayed neutron precursors (1.5).

REFERENCE Roactor Theory Review, og 21 i

1 e

-w- - - -

v-

,v-_w.,,,.,-,n-n---,nn---n,--,.-

,,,,v.

,n

,,,,,,-----.-,----r-,.

11__EBINQIELE1_QE_NuQLE88_EQWEB_EL8NI_QEEB8Il0Gt PAGE 18 IB E Bd Q Q1NedIQ1t_B E 81_IB 8N S E E B _8B D _ EL VI Q _ E '.QW ANSWERS -- COOPER

-86/03/04-GR.4VES, D.

ANSWER 1.07 (2.00)

Solving P = (PoleE(t/T) (0.5 pts), where P = 2Po (0.5 pts) 2Po = (PoleE(t/T) 2 = eE(t/T)

In 2 = t/T (0.5]

.693 = t/T T = t/.693 = t (1/.693) 1.443t (0.5)

=

REFERENCE Roactor Theory Review, pg 20 ANSWER 1.08 (2.00) c.

Low i

b.

Less c.

Less, More d.

EOL o.

More f.

More g.

BOL (0.25 each) l REFERENCE l

Roactor Physics Review, pg 26 - 34 i

l t

11__EBINGIELES_QE_NWGLE8B_EQWEB_ELaNI_QEEB8IIQNt PAGE 19 IBEBdQQ1N8 digit _HE61_IB6NSEEB_8NQ_ELulD_ELQW ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 1.09 (3.00) c.

Increase (0.25).

As the moderator density decreases, the neutrons travel a greater distance and are more likely to interact with a control rod (0.75).

b.

Decrease (0.25).

The voids depress the thermal neutron flux which in turn decreases the rod worth (0.75).

c.

Increase (0.25).

Rod worth decreases as void content increases.

A slight decrease in void content means the thermal flux is not quite as depressed and control rod worth subsequently increases (0.75).

REFERENCE GE Reactor Theory Review, pg 37 ANSWER 1.10 (2.00)

(

800 psig = 814.7 psia = 520.3 deg F (0.5) 350 psig 364.7 psia = 435.5 deg F (0.5)

=

l 520.3 - 435.5 = 84.8 deg/hr (0.5)

No limit was exceeded (0.5)

REFERENCE l

Steam Tables i

ANSWER 1.11

(.50) b (0.5)

REFERENCE GE Thermodynamics, Heat Transfer, and Fluid Flow, pg 7-78

2t__EL8HI_QE11GN_ INCLUDING _18EEII_8NQ_EMEBEENGl_111IEd1 PAGE 20 ANSWERS -- COOPER

-86/03/04-6 RAVES, D.

I ANSWER 2.01 (2.00)

(Any 4/7 0 0.5 ee.)

- Limit steem flow to less then 200%.

[

- Limit diff. pressure across reactor internals during a steem break.

- Provide a steem line hi flow signal to the Primary Contain. Isol. Sys.

- Provide flow indication on panel 9-5.

- Provide flow signal to Feedwater Level Control.

- Input to the steem leak detection system.

- Provide low power setpoint interlock to the RWM.

REFERENCE Main Steam Lesson Plan, p.

MS-7 ANSWER 2.02 (2.00)

(Any 4 below e 0.5 es.)

- Channel fastener ensemblies all meet in a control cell.

- Lifting handle boot, or protrusion, faces the rod in the control cell.

- Serial # on the fuel channel / lifting handle can be read from the center of the control cell.

- The channel spacer buttons are adj acent to the control 'od blades.

- There is cell-to-cell symmetry.

REFERENCE Fuel Lesson Plan, p.

Fuel-20 ANSWER 2.03 (2.00)

Any 2/5 below e 1.0 es.

- Valve must be closed to start the pump.

l

- Valves automatically close on a LPCI start signal after reactor pressure i

has decreased to 185 235 psig.

i

- Velve must be fully open for pump speed > 20%.

- Valve < 90% open, more then 2 minutes after pump start, trips pump.

- Velve must be partially open within 60 seconds after RR pump starts, or the pump trips.

REFERENCE Roactor Recirculation System Lesson Plan, p.

Recirc-10

=

2i__EL8NI_ DESIGN _INCLUQ1NE_leEEII_eNQ_EMEBEENC1_1111Ed1 PAGE 21 ANSWERS -- COOPER

-86/03/04-6 RAVES, D.

ANSWER 2.04 (1.00)

A constant voltage output with decreasing frequency requires increasing oxcitation current (0.67).

This would cause exciter / voltage regulator overheating (0.33).

REFERENCE Roactor Recirculation System Lesson Plan, p.

Recirc-14 ANSWER 2.05 (3.00) o.

Backup water source for CRDH pump suction (0.75).

b.

Cooling for CROH pump oil cooler and pump thrust bearing (0.75).

c.

Collects water drainage from the SDV & leakage from the HCU valves.

Collects discharge from the HCU accumulator when recharging (0.75).

d.

Power to valves 140A & 1408 (backup scram valves) (0.75).

REFERENCE.

Control Rod Drive Hydraulic System Lesson Plan, p.

CRDH-30, 31 ANSWER 2.06 (3.00) c.

Decrease (0.25) due to loss of steam supply to SJAE (0.5).

b.

RWCU pumps trip (0.25) due to low flow as F/D FCV fails closed (0.5).

c.

Outboard MSIV's drift closed (0.25) as accumulators discharge (0.5).

d.

Rods indiscriminate 1y scram (0.25) as scram valves open under spring pressure (0.5).

REFERENCE Plant Air System Lesson Plan, p.

PA-16 i

l l

l

2i__EL8NI_ DESIGN _INCLUDINE_leEEII_8NQ_EMEBGENGl_111IEd1 PAGE 22 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 2.07 (2.50)

(Six answers e 0.33 ea.,

5 sequence values e 0.1 es.)

Moisture separator, Rough pre-filter, olectric heating element, Inlet HEPA, Charcoal adsorber, Final HEPA.

REFERENCE Standby Gas Treatment System Lesson Plan, p.

SGT-7~10 ANSWER 2.08 (1.50)

(Any 3/4 0 0.5 ea.)

- Inverter failure.

Inverter is turned off.

- Over/undervoltage (+/-

10%).

- Over/underfrequency

(+/- 2 cycles).

REFERENCE AC Electrical Distribution System Lesson Plan, p.

AC-19 ANSWER 2.09 (3.00) c.

RHR pump seal water and bearing water coolers HPCI pump area cooling coils RHR pump area cooling coils Core spray area cooling coils (0.5 each)

)

b.

The REC critical loops are isolated and service water is supplied (1.0)

REFERENCE Roactor Equipment Cooling Lesson Plan, Rev 0, pg REC-26 i

2i__EL8NI_QE11GN_INGLVQ1NG_18EEII_8NQ_EMEBGENQ1_111IEd1 PAGE 23 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 2.10 (3.00) o.

HPCI initiation signal must be present (0.5) and the manual isolation pushbutton on Panel 9-3 is depressed (0.5).

b.

- The system will automatically restart when level decreases to the initiation setpoint (1.0).

- The high level trip signal may be reset and the system will restart (1.03 REFERENCE HPCI Lesson Plan, Rev 0, pg HPCI-8, 32 ANSWER 2.11 (1.00)

The Condensate Storage Tank is the alternate source (0.5).

The manual volve in the suction line must be opened (0.5).

REFERENCE Core Spray Lesson Plan, Rev 0, pg CS-4 ANSWER 2.12 (1.00)

- Ensure the discharge lines of the CSCS's are filled

- Flushing the RHR Steam Condensing heat exchangers

- Filling the Fuel Pool Cooling and Cleanup System

- Filling the RHR system interconnection lines

- Backwashing the RWCU filter demineralizer resin strainers

- Source of water to the RPV per E0P's

- Dryer / separator pit

- Various Reactor Building loop seal maintenance

- Refueling floor service boxes

- Torus water makeup C4 required at 0.25 each)

REFERENCE Core Spray Lesson Plan, Rev 0, pg CS-10 i

- ai__INSIBudENI1_6NQ_QQNIBQL1 PAGE 24 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 3.01 (2.50) o.

- Manual operation of the RBM BYPASS switch (0.5)

- < 30% power (0.5)

- Edge rod selected (0.5) b.

Failed Low:

Removes the LPRM input from the averaging circuit (0.25) and indicates to the counting circuit that the input is INOP (0.25).

Failed High:

The higher input is averaged with the other inputs and processed as if it were a valid signal (0.5).

REFERENCE Red Block Monitor Subsystem Lesson Plan, Rev 0, pg RBM-9, 16 ANSWER 3.02 (2.00) c.

All the push button lights in that RSCS group extinguish except the selected rod (1.0).

b.

Withdraw:

At 100% rod density during startup (0.5).

Insert:

At 50% rod density during shutdown (0.5).

Normal: At 50% rod density (0.5).

REFERENCE Red Sequence Control System Lesson Plan, p.

RSCS-3, 5 ANSWER 3.03 (2.00)

Any 5/8 0 0.4 es.

Full Core Display Process Computer Four Rod Display Scram Timing Recorder RSCS Orift Circuitry Codd reed switches)

RWM Rod Select Logic (Refuel all rods in information)

REFERENCE Rasctor Manuel Control System and Rod Position Information System Lesson

Plan, p.

RMC-2

li__INSIBudENI1_8ND_CQNIBQLS PAGE 25 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 3.04 (2.50) c.

Turn the Rod Select Power Switch off (momentarily) (1.0) b.

When no rod movement is expected for extended periods (1.0).

c.

The matrix push button may stick if left selected (due to heating by the indication lights) (0.5).

REFERENCE Rcactor Manuel Control System and Rod Position Information System Lesson

Plan, p.

RMC-8 ANSWER 3.05 (3.00) c.

(Any 4/7 below e 0.25 es.)

- High fluid drive oil temperature (210 F).

- Control signal failure to tube positioner.

- Low lube oil pressure (28 psig for 6 seconds).

- Low voltage on the MG set motor supply bus.

- Loss of power to the scoop tube positioner.

- Tube positioner external limit switches.

- Manual switch on 9-4.

b.

Match the speed demand and actual MG set speed (0.5), then depress manual reset push button on 9-4 (0.5).

c.

Speed can be changed manually (0.5) with a locally operated handcrank at the scoop tube positioner motor (0.5).

REFERENCE Roactor Recirculation System Lesson Plan, p.

Recirc-21, 22 1

--n 7

2t__IN11BudENI1_6ND_QQNIBQL1 PAGE 26 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 3.06 (3.00) c.

- steam header pressure (0.25)

- pressure setpoint (0.25)

- bias signal (0.25) on one channel (0.253 b.

If the generator output breakers open (0.5) and turbine load is greater than 22% (0.5), OR OPC TEST Switch to TEST Celso full credit).

e.

The governor valves open (0.25) to control the false pressure increase.

Reactor pressure decreases (0.25) to the MSIV isolation setpoint, where the MSIV's will close (0.25) and the reactor will scram (0.25).

REFERENCE DEH Lesson Plan, Rev 0, pg DEH-4, 14, 31 ANSWER 3.07 (3.00)

- b may be bypassed (0.5) by a key switch if the mode switch is in Shutdown or Refuel (0.5).

- c may be bypassed (0.5) if the mode switch is not in Run (0.5).

- e may be passed (0.5) when reactor power is less than 30% (0.5) by turbine first stage pressure.

REFERENCE Roactor Protection System Lesson Plan, Rev 0, Table 2

2i__INRIBudENI1_6NQ_CQNIBQL1 PAGE 27 ANSWERS

- COOPER

-86/03/04-GRAVES, D.

ANSWER 3.08 (3.00) o.

detector:

ion chamber (0.3).

actions:

reactor scram (0.3)

MSIV closure (0.3) main steam line drains shut (0.3) recirc loop sample valves shut (0.3) condenser air removal valves shut (0.3) mechanical vacuum pumps trip (0.3) b.

detector:

scintillation (0.3) actions:

none o.

detectors ion chambers (0.3) actions:

isolates the air ejector off gas line (0.3)

REFERENCE Instrumentation Operating Procedures:

4.7.1, Main Steam Line Radiation Monitoring System, Rev 8, pg 1 4.7.2, Air Ejector Off Gas Radiation Monitoring System, Rev 9, pg i 4.7.4, Process Liquid Radiation Monitors, Rev 6, pg 1 j

ANSWER 3.09 (2.00)

Channels A and C level use the same sensing taps from the RPV.

If a leak occurred in the sensing line causing indicated leve l t'o b e Icw, the RFP would speed up, increasing level, and could not trip due to high level (2.0 for explanation and concept).

REFERENCE System Operating Procedure 2.2.28, Feedwater System, Rev 35, pg 6 Nuclear Boiler Instrumentation Lesson Plan, Rev 0, figure 4 ANSWER 3.10 (2.00) c.

2 b.

4 c.

2 d.

4 o.

3 f.

3 g.

1 h.

2 (0.25 each)

2t__IN1IBut!ENI1 6NQ_GQNIBQL1 PAGE 28 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

REFERENCE Nuclear Boiler Instrumentation Lesson P.'.an, Rev 0,.pg N81-24, 25 l

l l

s

\\

9 i -

at__EBQQEDUBE1_=_NQB58Lt_8BNQBU8Lt_EMEBGENC1_8NQ PAGE 2g B8D1QLQEIG8L_GQNIBQL ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 4.01 (1.00) f A.

3 f

8.

1 C.

4 D.

2 REFERENCE CNS EP 5.4.1, General Fire Procedure, Rev ig, pg 1 ANSWER 4.02 (2.50)

I c.

The 3 GEMAC's and associated recorder on panel g-5 (1.0).

b.

The Yarways may be monitored locally in the Reactor Building (0.5).

c.

The reactor vessel level reference legs will begin to flash when the RPV pressure approaches saturation pressure for the drywell temperature, causing erroneous high reactor level indication (1.0).

}

l REFERENCE CNS E0P 5.2.5.1, Loss of All Site AC Power Station Blackout, Rev 3, pg 3 ANSWER 4.03 (2.00) c.

yes b.

yes c.

no d.

no o.

yes (0.4 each)

REFERENCE AP 2.4.2.2.3, Recirculation Pump Seal Failure, pg 1 l

o

4 __EBQQEQUBER_=_NQBd8Lt_8BNQBd8Lt_EdEBGENQX_8ND PAGE 30 1

88010LQQIQ8L_QQNIBQL ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 4.04 (2.00) a.

True b.

False c.

False d.

True (0.5 each)

REFERENCE GOP 2.1.15, Reactor Recirculation Pump Startup and Shutdown CNS Technical Specifications 3.3.F.

ANSWER 4.05 (2.00) a.

Place the mode switch in REFUEL C0.25) and check the Refuel Permissive Light (0.25) illuminated.

Observe all green full-in lights on Panel 9-5 illuminated (0.5).

b.

Shut with individual control switches (0.5).

Place the mode switch to RUN (0.25) when reactor pressure is less than 825 psig (0.25).

REFERENCE GOP 2.1.5, Emergency Shutdown from Power, pg 2 ANSWER 4.06 (3.00) a.

5 b.

3 c.

1 d.

2 e.

6 f.

4 (0.5 each) l REFERENCE CNS GOP 2.1.1, Cold Startup Procedure, Rev 41, pg 8,9

fi__EBQGEQUBEf_=_NQBd8Li 8BNQB58Lt_EMEBEENGI_8NQ PAGE 31 B8DIQLQEIG8L_GQNIBQL ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 4.07 (2.00) o.

Hot Standby is a condition where reactor pressure is less than 1000 psig (0.5), coolant temperature is greater than 212 deg F (0.5),

and the mode switch is in the Startup/ Hot Standby position (0.5).

1 b.

1/4 core density means that 25% of the control rods are full withdrawn from the core (0.5).

REFERENCE GOP 2.1.g, Hot Stand 5y Condition, Rev 5, pg 1, 2

ANSWER 4.08 (3.00)

O.

No (0.25).

The red and green lights indicate whether the actuating solenoid for the SRV is energized or deenergized (0.75).

b.

- The blue pressure switch light will be illuminated.

- Decreasing tailpiece temperature

- Megewatt load or steam flow returns to original value

- Suppression pool pressure, level, and/or temperature stops increasing

- Reactor pressure fluctuations as the SRV closes

- RPV level transient or level returns to normal

- Grader may accept other indications if they are appropriate (4 required at 0.5 each)

REFERENCE AP 2.4.2.3.1, Relief Valve Stuck Open, Rev 14, pg 1-2 ANSWER 4.09 (2.00) c.

After a 5 minute time delay (0.25), the offgas system will isolate with no dilution flow (0.75).

I b.

By depressing and holding the 254 AV Reset button (0.5).

I c.

Standby Gas Treatment System (0.5)

REFERENCE AP 2.4.8.4.6, Loss of Stack Dilution Fans, Rev 4

Az__EBQQEQWBE1_=_NQBd8Lt_8BNQBd8Lt_EMEBGENQY_8NQ PAGE 32 B&QIQLQEIQ8L_QQNIBQL ANSWERS -- COOPER

-86/03/04-GRAVES, D.

1 l

ANSWER 4.10 (3.50) o.

Level, Pressure, Power (0.5 each) b.

Suppression pool level and temperature (0.5 each)

Drywell temperature (0.5)

Primary containment pressure (0.5) l REFERENCE EP 5.8, Emergency Operating Procedures, Rev 1, pg 2, 3

ANSWER 4.11 (2.00) c.

150 MREM /25 MREM per hour = 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (0.5 for the 150 MREM limit, 0.5 for the stay time) b.

Remove self from the radiation field (0.5).

Report the incident (0.25) to individual's immediate supervisor (0.125) and to Health Physics (0.125).

REFERENCE HPP 9.1.1.3, Personnel Dosimeter Program, Rev 18, pg 3 HPP 9.1.2.1, Radiation, Contamination, and Airborne Radioactivity Limits, Rev 15, pg 5

s U.

S.

NUCLEAR REGULATORY COMMISSION SENIOR-REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

_QQQEEB__________________

REACTOR TYPE:

_RWB-QEi_________________

DATE ADMINISTERED:_thtQ24Qi________________

EXAMINER:

_gB&VEft_Qt______________

APPLICANT:

INSIBUQIIQN1_IQ_6EELIQ8HIl U30 separate paper for the answers.

Write answers on one side only.

Stcple 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 and a final grade of at i

locat 80%.

Examination papers will be picked up six (6) hours after tho examination starts.

% OF CATE60RY

% OF APPLICANT'S CATEGORY

__VALUE_ _IQI6L

___1QQBE___

_V8LUE__ ______________Q&IEQQBl_____________

_21199__ _2510Q

________ 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

_2119Q__ _25tQQ

________ 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

_25tRQ__ _25tDQ

________ 7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

_25100__ _2510Q

________ 8.

ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 100100__ 100100

________ TOTALS FINAL GRADE _________________%

All work done on this examination is my own. I have neither given nor received aid.

APPLICANT'S SIGNATURE

Ei__IHEQBl_QE_NVGLE8B_EQWEB_EL8HI_QEEB8110Ni_ELU101t_8NQ PAGE 2

IHEBdQQ1NadIG1 QUESTION 5.01 (3.00)

Answer the following with regard to the Control Cell Core (CCC) operating otrategy:

o.

What constitutes a CONTROL CELL?

(0.5) b.

How many control cells will be used at CNS?

(0.5) c.

While operating at power, what is the position of the non-control cell control rods?

(0.5) d.

Why do control rod movements result in a lower kw/ft change per notch in a CCC than in a conventional core?

(1.0) o.

TRUE or FALSE.

Using the CCC operating strategy eliminates the need for control rod pattern changes.

(0,5)

QUESTION 5.02 (1.50)

The Pellet-Cladding Interaction (PCI) failure mechanism is dependent upon four factors.

List three (3) of these factors.

(1.5)

QUESTION 5.03 (2.00)

Indicate HOW (increase, decrease, unaffected) control rod worth changes for each of the situations listed below.

EXPLAIN WHY the red worth is affected, if applicable.

c.

The reactor is heated from 100 deg F to 200 deg F (1.0) b.

Reactor power is increased from 70% to 90% by increasing recirculation flow (1.0)

QUESTION 5.04 (2.50)

Draw a typical graph of Keff vs. Core Life and explain the reasons for major changes in curve slope or direction.

(2.5)

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

Iz__IBEQBl_QE_NWQLE88_EQWEB_EL8NI_QEEB8IIQNt_ELUIQ1t_8NQ PAGE 3

IHEBdQQ1NedIG1 QUESTION 5.05 (3.00)

A reactor startup is in progress.

You have been given the Gotimated critical rod position for the conditions at 0800.

You start to pull control rods at 0800 for the approach to critical.

HOW WOULD EACH OF THE FOLLOWING conditions or events AFFECT the ACTUAL CRITICAL ROD POSITION Cmore rod withdrawal, loss rod withdrawal, or no significant effect)?

c. One reactor recirculation pump is stopped (Hypothetical situetion only)

(0.5)

b. Xenon is changing due to extended power operation, terminated 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> previouly.

(0.5)

c. Shutdown cooling is stopped (significant decay heat)

(0.5) d.

Reactor head vent is inadvertently closed.

(0.5)

o. Moderator temperature is gradually decreasing.

(0.5) f.

Reactor Water Cleanup System isolates (significant decay heat).

(0.5)

QUESTION 5.06 (3.00)

A new experimental reactor uses a new fuel that has 5 delayed neutron precursor groups. The longest has a half life of 40 seconds and the cverage is 8.5 seconds.

o.

For'this reactor, what is the stable period (rate of power decrease) after shutdown from the power range?

Explain and show any calculations as necessary.

(1.25) b.

What specific information is needed to determine a beta fraction for this reactor?

(0.75) c.

HOW and WHY will the EFFECTIVE bate fraction diffar from the ACTUAL beta fraction?

(1.0)

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

Ez__IHEQB1_QE_NVQLE88_EQWEB_EL8HI_QEEB8110Nt_ELU101&_8NQ PAGE 4

IBEBHQQ1N8HIQ1 QUESTION 5.07 (2.00)

What adj ustment is made to the MCPR limit for:

o.

Core flows less than rated flow?

(1.0) b.

Single loop operation?

(1.0)

QUESTION 5.08 (2.00)

A reactor water sample indicates the following isotopes present:

Tritium (1H3)

Kr 87 Mn 56 1 131 Ni 57 Xe 133 i

Fe 59 Cs 137 Co 60 Ba 140 c.

Which of the above are fission products and which are corrosion products?

(1.0) b.

Does the presence of fission products in the coolant mean a fuel element failure or defect exists?

If not, account for their presence in the reactor coolant.

(1.0)

QUESTION 5.09 (2.00)

Using the Steam Tables, calculate how long it will take to cooldown from 1000 psig to O psig at the maximum allowable cooldown rate allowed per GOP 2.1.4, Normal Shutdown from Power.

(2.0)

QUESTION 5.10 (2.00) o.

The reactor is operating at 100% power and flow.

Explain what happens to core flow, and why, with a reduction in power by control rod insertion.

Assume recirculation pump speed remains constant.

(1.0) b.

At low power conditions, an increase in reactor power by control rod withdrawal will (INCREASE, DECREASE, or NOT CHANGE) flow through the core.

Choose the correct answer and BRIEFLY explain your choice.

Assume recirculation pumps are running.

(1.0)

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

It__IHEQBl_QE_NUQLE88_EQWEB_ELeNI_QEEB8IIQNt_ELUIDSt_8NQ PAGE 5

ItiEBdQQ1N8dIQ1 QUESTION 5.11 (2.00) 4 In Operating Procedure 2.1.3, Approach to Critical, it is stated that roactor period can be calculated by multiplying the time (in seconds) that it takes the power to double by 1.443.

How is this factor dotermined?

(2.0)

(***** END OF CATEGORY 05 *****)

ht__ELeNI_111IEMS_QE11GNt_QQNIBQLt_8NQ_IN11BWMENI6IIQN PAGE 6

QUESTION 6.01 (2.50) o.

List three (3) ways that the Rod Block Monitor (RBM) may be bypassed.

Include automatic and/or manual bypasses.

(1.5) b.

How does the RBM utilize the input from a LPRM detector that is failed HIGH or failed LOW 7 DISCUSS BOTH cases, but limit your answer to how the LPRM input is considered in the averaging and counting circuits.

Assume the LPRM recently failed and has NOT been bypassed with its individual bypass switch.

(1.0)

QUESTION 6.02 (2.00)

D3 scribe two (2) interlocks that are associated with the Reactor Recirculation System motor operated recirc pump discharge valves.

(2.0)

QUESTION 6.03 (1.00) t What would happen if the recirc pump MG set voltage regulator did not roduce the generator output voltage when generator frequency (pump speed) docreased?

Why does this effect occur?

(1.0)

QUESTION 6.04 (3.00)

Explain how AND why a complete loss of the plant air system, while operating at full power, with no operator action, would affect the following plant parame'ers or components.

O.

Main condenser vacuum.

(0.75) b.

RWCU operation.

(0.75) c.

Main Steam Isolation Valves.

(0.75) d.

Control Rod position.

(0.75)

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

hi__ELANI_111IEUS_QE11GNt_GQNIBQLt_8NQ_IN11BUBENI8IIQN PAGE 7

QUESTION 6.05 (3.00) l O.

What condition (s) must be met in order for a manual isolation of j

HPCI to be performed?

(1.0) l b.

A LOCA has occurred and HPCI initiated, operated, and tripped os, high level.

Level is now 37 inches and decreasing.

How can the system be restarted?

TWO METHODS REQUIRED.

(2.0)

QUESTION 6.06 (3.00)

For each of the process radiation monitors listed below, state what type of detector is used and any automatic actions directly initiated by that radiation monitoring system.

EXCLUDE ANNUNCIATORS.

(3.0) c.

Main steam line radiation monitor b.

RBCCW (REC) c.

Air ejector off gas radiation monitoring system QUESTION 6.07 (2.00)

During operation of the Feedwater Control System, level control chould be selected to channel B to ensure overfill protection is in effect.

How does selecting channel B for level control ensure overfill protection is provided?

(2.0)

QUESTION 6.08 (2.00)

Match each of the following actions / interlocks with the RPV level oystem it uses for actuation.

(2.0) o.

RCIC initiation 1.

Wide Range Yarway b.

HPCI turbine trip 2.

Narrow Range Yarway c.

Diesel Generator start 3.

Narrow Range GEMAC d.

RPS level scram 4.

Bartons o.

Main turbine trip f.

Feedwater level control g.

RHR containment spray control h.

Recirculation pump trip

(***** CATEGORY,06 CONTINUED ON NEXT PAGE *****)

Ez__EL8NI_1XIIEd1_QE11GNt_GSNIBQLt_680_181IBudENIeIl0N PAGE 8

QUESTION 6.09 (2.50)

What are five (5) methods or sids for checking fuel orientation when fuel is positioned at the final stage during refueling?

(2.5)

QUESTION 6.10 (2.00) c.

How many Electrical Protection Assemblies (EPA's) are on the RPS Power Supplies?

(0.5) b.

What three conditions will cause a trip of the EPA's?

Setpoints NOT required.

(1.5)

QUESTION 6.11 (2.00)

The blowdown flow control valve (FCV-55) in the Reactor Water Cleanup Oystem is tripped closed when either of two abnormal conditions exist.

What are these two conditions and what do they prevent?

(2.0) l a

(***** END OF CATEGORY 06 *****)

Zz__EBQGEQuBE1_=_NQBdeLi_8BNQBdakt_EMEBEENCY_6ND PAGE 9

E8DIQLQQ1C8L_GQNIBQL QUESTION 7.01 (2.50) c.

A loss of the Service Water System has occurred and it is not expected that the system will be restored within a short period of time.

What are four (4) actions that must be performed?

(2.0) b.

What should be used as the initial heat sink for the REC system following the loss of Service Water?

(0.5)

QUESTION 7.02 (3.00)

For each of the following conditions, state which E0PCs), if any, chould be entered:

(3.0) c.

Suppression pool level +1.2 inches b.

Drywell pressure 2.3 psig o.

Reactor Building exhaust plenum radiation 12 mr/hr AND site boundary radiation 0.5 mr/hr d.

RPV level 15 inches AND suppression pool temperature 97 deg F o.

Reactor power 5% AND RPV water level 8 inches AND Drywell temperature 165 deg F f.

RPV pressure 1035 psig AND secondary containment differentail pressure -0.25 in. H2O AND suppression pool level -1.5 inches.

QUESTION 7.03 (2.00) f The plant is operating at power with a reactor pressure of 1000 psig.

State whether each of the following (a - e) would indicate a failure of the outer (#2) seal on a reactor recirculation pump.

(2.0) o.

Seal cavity #2 pressure indicates 50 psig b.

OUTER SEAL' LEAK FLOW DET. HIGH alarm c.

Increase in drywell floor drain sump flow d.

Seal cavity #2 pressure of 800 psig o.

Increase in drywell equipment drain sump flow

(*****

CATEGORY 07 CONTINUED ON NEXT PAGE *****)

_=

Zi__EBQGEDWBE1_=_NQBd8Li_8BNQBd8Li_EMEBGENGl_8NQ PAGE 10 88DIQLQEIG8L_GQNIBQL QUESTION 7.04 (2.00)

Indicate whether each of the following statements is TRUE or FALSE:

(2.0) o.

A reactor startup is NOT permissible under natural circulation flow conditions.

b.

A reactor startup is NOT permissible with only one recirculation pump in operation.

i j

c.

If the reactor is operating at power (both recirculation pumps

)

in operation) and one recirculation pump trips, reactor operation i

may continue for no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4 d.

A reactor recirculation pump may not be started if the reactor is in natural circulation flow and reactor power is greater then 1%.

QUESTION 7.05 (2.00)

Answer the following questions concerning GOP 2.1.5, Emergency Shutdown from Power:

t i

o.

After the manus 1 scram buttons are depressed, what two (2) checks should the operator make to verify all control rods inserted?

(1.0) b.

If it becomes necessary to shut the MSIV's after the screm, what are the two (2) methods stated in the procedure for accomplishing this?

(1.0)

QUESTION 7.06 (3.00) i MATCH each of the events (a - f) with the pressure at which the l

cvent may be performed during a cold plant startup per GOP 2.1.1,

" Cold Startup Procedure".

Items may be used more then once or not at all as appropriate.

(3.0)

_____e.

Begin placing feed pump in service 1.

25 psig

_____b.

Open HPCI steem isolation valves 2.

50 psig 4

_____c.

Steam semis placed in service 3.

100 psig

_____d.

Reset and unisolete RCIC 4.

150 psig

_____e.

Startup the SJAE 5.

350 psig j

_____f.

Initially open the bypass valves 6.

500 psig

(*****

CATEGORY 07 CONTINUED ON NEXT PAGE *****)

Zi__EBQQEDWBE1_=_NQBd8Li_8BNQBd8L&_EdEBGENQ1_88Q PAGE 11 88Q10LQB108L_QQNIBQL QUESTION 7.07 (2.00) o.

What three (3) conditions determine when the plant is operating in HOT STANDBY?

(1.5) b.

In proceeding from power operation to Hot Standby operation, the normal shutdown procedure is followed except that rods are inserted to 1/4 core density.

What is meant by 1/4 core density?

(0.5)

QUESTION 7.08 (1.00)

Match the class of fires listed below ( A - D) with the materials (1.0) involved (1 - 4).

CLASS OF FIRE MATERIALS INVOLVED

______A.

Alpha 1.

flammable liquids, gases, or gresses

______B.

Bravo 2.

combustible metals

______C.

Charlie 3.

ordinary combustibles (paper, wood, etc.)

______D.

Delta 4.

energized electrical equipment QUESTION 7.09 (2.50)

A loss of all site AC power has occurred. Answer the following questions concerning E0P 5.2.5.1, Loss of All AC Power Station Blackout.

o.

What reactor water level indication (s) are available in the control room following this event?

(1.0) b.

What reactor water level indication (s) are available outside the control room following this event?

(0.5) c.

Why should reactor pressure NOT be reduced below the suturation pressure corresponding to the maximum drywell temperature?

(1.0)

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

1 Zt__EEQQEQWBE1_=_NQBueL&_8BNQBueL&_EMEBGENQ1_8NQ PAGE 12 B8DIQLQEIQ8L_QQNIBQL QUESTION 7.10 (2.00)

The plant is operating at power with the A0G system operating.

The off-gas dilution fan trips and the standby fan will not start.

c.

What automatic action should occur due to the above condition?

(1.0) b.

How can the automatic action above be prevented?

(0.5) c.

What system can be used to provide dilution flow while attempting to restore the dilution fans?

(0.5)

QUESTION 7.11 (3.00)

The plant is operating at power when an SRV inadvertently opens.

The operator cycles the SRV control switch to OPEN and back to AUTO.

The red light goes out and the green light for that valve illuminates.

o.

Is the above occurrence positive indication that the SRV has reclosed?

EXPLAIN.

(1.0) b.

Give four (4) other control room indications that can be used to verify closing of the SRV.

EXCLUDE ANNUNCIATORS.

(2.0) i l

4

(***** END OF CATEGORY 07 *****)

Ri__eQUIN11IB8IIVE_EBQGEQWBEli_GQNQ1IIONit_6NQ_LIMII8Il0N1 PAGE 13 i

QUESTION 8.01 (2.50) i o.

Give two (2) general examples of NONCOMFORMANCE conditions that would require completion of a Noncomformance Report (specific i

examples not required).

(2.0) b.

True or False.

Observation of any event reportable under 10CFR50.72 one hour reporting criteria shall require writing a Noncomformance Report.

(0.5)

QUESTION 8.02 (3.50) o.

The Operations Department has two (2) key depositories.

What types of keys are in each of the depositories?

(1.0) b.

Who has control over key checkout in each of these depositories?

(1.0) l c.

Where may a duplicate of any key in the above key depositories be obtained?

(0.5) d.

During power operation, where is the key to the Reactor Mode Switch kept?

(0.5) o.

The Reactor Mode Switch key is under the direct control of whom?

C0.5)

QUESTION 8.03 (3.00)

Conduct of Operations Procedure 2.0.6, Reactor Post Trip Review cnd Restart Authorization Procedure, lists five (5) criteria that cust be satisfied prior to restarting the reactor following a ocram.

LIST THREE (3) of these criterie.

(3.0)

QUESTION 8.04 (2.00)

Por the Technical Specifications Limiting Safety System Settings, chat are four (4) protective actions designed to prevent exceeding the Reactor Coolant System pressure safety limits?

SETPOINTS NOT REQUIRED.

(2.0) i 3

(***** CATEGORY 08 CONTINUED ON NEXT PAGL *****)

Ri__8051N11IB8I1YE_EBQGEQUBEft_GQNQIIl0 Nit _880_LIU1I611QN1 PAGE 14 QUESTION 8.05 (2.00)

Portaining to CNS Procedure 0.9, Equipment Clearance and Release Orders:

c.

List the three (3) methods given that may be used for verifying the position of manual valves in the main flow path of safety related equipment when they are returned to service.

(1.5) b.

Who may sign the CLEARANCE RELEASED BY blank when the person who signed the CLEARANCE ISSUED TO blank is not on site and the l

tags need to be picked up?

(0.5)

QUESTION 8.06 (1.50) c.

Under what plant conditions is the Shift Technical Advisor (STA) required to be manned?

(1.0) b.-

The STA must be sveilable in the Control Room within _______ of being summoned.

(0.5)

QUESTION 8.07 (1.00) 1 What is the PRIME function of the Communicator during any emergency cituation or condition?

(1.0) l I

QUESTION 8.08 (3.00) c.

List five (5) devices / actions that would be considered temporary modifications per Conduct of Operations Procedure 2.0.7, Plant l

Temporary Modification Control.

(2.5) b.

Describe a temporary modification tag.

(0.5)

(***** JATEGORY 08 CONTINUED ON NEXT PAGE *****)

i Az__8DdlN11IB8IIVE_EBQQEQUBEft_CQNDIIIQNit_8NQ_LIdlI6Il0NA PAGE 15 QUESTION 8.09 (2.50)

Indicate if the folowing statements are TRUE or FALSE per Procedure 10.26, Working Over or In Reactor Vessel Requirements.

(2.5) o.

Film badges and dosimeters are to be worn on the outside of the protective clothing and securely taped.

b.

Eye glasses shall not be worn unless a safety band is installed on the bow ends.

c.

Contact lenses are permitted only if the individus1 is also I

wearing safety glasses.

d.

Hand held tools, used over the reactor vessel, do not need to 7

be secured by a lanyard as long as the person using it has en SRO license.

l o.

Hand held tools and equipment which are used in the reactor vessel should be recorded at en established control point.

QUESTION 8.10 (2.00)

Rcdiological Technical Specifications offers three options, any one of which is to be met in case that a limiting control rod pattern cxists.

List two (2) of the three options.

(2.0)

QUESTION 8.11 (2.00)

During refueling operations individual responsibilities are assigned ca indicated in Procedure 10.21, Special Nuclear Materials (SNM)

Control and Accountability.

c.

Who must direct the SNM handling operations involving SNM movement BETWEEN Item Control Arees?

(0.5) b.

Who may direct the SNM handling operations involving SNM movement WITHIN Item Control Areas?

(0.5) c.

Who functions as the SNM Executor?

(0.5) d.

Who functions as the SNM Checker?

(0.5)

(*****

END OF CATEGORY 08 *****)

(************* END OF EXAMINATION ***************)

EQUATION SHEET 0

f = ma v = s/t Cycle efficiency = (Networx f

out)/(Energy in) 2 w = mg s = V,t + 1/2 at 2

E = mc 2

KE = 1/2 mv

,, (yf, y )fg A = AN, A = A e'**

o g

PE = agn Vf = V, + at w = e/t A = sn2/t1/2 = 0.693/t1/2 1/2'##

• EI*U)I*h))

t y,yg

[(tifz) + (t )]

o

'aE = 931 am

~

I'= I,e"**

Q = aCpat Q = UAat.

I = I e'"*

~

g I = I, 10**/ M Pwr = W.*

7 TVL = 1.3/u sur(t)

P = P 10 HVL = -0.693/u P = P e*/I o

SUR = 25.06/T SCR = 5/(1 - K,ff)

)

CR, = 5/(1 - K,ffx)

SUR = 25e/t= + (s - o)T CR (1 - K,ffj) = CR (I ~ "eff2) '

j 2

rc(1*/a)+[(s-o)/ Sol M

• I/(I ~ Xaff) = CA /CR, g

T = 1/(o - s)

M " II ~ Keffo)/II~Kaffl}

T=(s-o)/(to)

SOM * (I ~ Kaff)/Keff a = (X,ff-1)/K,ff " AXeff eff

/K

["0.1 seconds,$

8#

A=

o = [(t*/(T K,ff)] + [I

/(1 + AT)3 nff t

Idjj=1d P = (r+V)/(3 x 1010)

I d) 2,2 2 gd j

22 2

s = oN R/hr = (0.5 CE)/d (meters)

R/hr = 6 CE/d2 (feet)

Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem.

I curie = 3.7 x 1010dps 1 ga:. = 3.78 liters l kg = 2.21 lbm

~

1 f t- = 7.48 gal.

I hp = 2.54 x 103 Btu /hr Density = 62.4 lbm/ft3 1 nw = 3.41 x 100 Stu/hr Density = 1 gm/c:rr3 lin = 2.54 cm Heat of vaporization = 970 Stu/lom

• F = 9/5'C + 32 Heat of fusion = 144 Stu/lbm

• C = 5/9 ('F-32) 1 Atm = 14.7 psi = 29.9 in. Hg.

1 BTU = 778 ft-lbf 1 ft. H O = 0.4335 lbf/in.2 2

Ei__IHEQBl_QE_NUGLE88_EQWEB_EL8NI_QEEB8IIQNt_ELulQit_8NQ PAGE 16 IHEBBQQ1NedIGE ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 5.01 (3.00) c.

Four fuel bundles and a control rod (0.5) b.

25 (0.5) c.

Fully withdrawn (0.5) d.

All control rod movements are associated with low reactivity cells (1.0).

c.

True (0.5)

REFERENCE Fuel System Description, pg 18 ANSWER 5.02 (1.50) o.

Fuel rod power level Fuel rod exposure l

Rate of power increase Fuel pellet design Previous power history Presence of embrittling agent (3 required at 0.5 each)

REFERENCE Fuel System Description, pg 15, 16 GE HTFF pg 9-107, 108 ANSWER 5.03 (2.00) o.

Increase (0.25).

As the moderator density decreases, the neutrons travel e greater distance end are more likely to interact with a control rod (0.75).

b.

Increase (0.25).

Rod worth decreases es void content increases.

4 A slight decrease in void content means the thermal flux is not quite as depressed and control rod worth subsequently increases (0.75).

REFERENCE GE Reactor Theory Review, pg 37

E A__IB E Q Bl_ Q E_N U Q L E 88_ E Q W E B _ E L 8 NI_ Q E E B 8Il0 N t _ E L UID a t_8 H D PAGE 17 IBEBdQQ1NedIGE ANSWERS -- COOPER

-86 / 0 3 / 04-O R AVE S, D.

ANSWER 5.04 (2.50) 1 I

I IA l

-u I

I Keff l______________________________________________________

l D

I I

I I

I I

l_________________________________________________________ (1.0)

BOL EOL A.-B.

Xenon and Samarium buildup (0.5)

B.-C.

Poison burnout f aster than f uel depletion (0.25)

Buildup of Plutonium (0.25)

C.-D.

Fuel depletion (0.5)

REFERENCE R3 actor Physics Review, pg 47, Figure 62 ANSWER 5.05 (3.00)

O.

No significant effect

b. Less rod withdrawal

c. More rod withdrawal

d. No significant effect

o. Less rod withdrawal

f. More rod withdrawal (0.5 each)

REFERENCE R actor Physics Review, Reactivity Coef ficients

Ei__IBEQBl_QE_NWGLE8B_EQWEB_EL8HI_QEEB8IIQNi_ELU101t_8NQ PAGE 18 IHEBdQQ1N8dICS ANSWERS _- COOPER

-86/03/04-GRAVES, D.

ANSWER 5.06 (3.00)

O.

T = t1/2 /In2 = 40/.6g3 = 57.7 sec's. (accept 56.7-58.7)

(0.5 pt for the correct formula, 0.25 pt for the 40 sec half life, 0.5 pt for the correct answer) 4 b.

Specific yield of each precursor group (0.75) o.

The effective bets fraction will be essentially the same value as the core delayed neutron fraction (1.0).

If leakage is assumed to be significant, effective B fraction will be larger than the B frac.

REFERENCE Rosctor Physics Review, pg 23 ANSWER 5.07 (2.00) o.

The operating limit at rated flow times kf (1.0).

b.

0.01 higher than comparable two loop values (1.0).

REFERENCE CNS Technical Specification 3.11.C. pg 212 ANSWER 5.08 (2.00) o.

Fission products:

Tritium, I, Kr, Xe, Cs, Be (0.1 each)

Corrosion products:

Fe, Ni, Co, Mn (0.1 each) b.

No (0.25).

The activity is due to tramp uranium fission (0.75).

REFERENCE Mitigating Core Damage, Chart of the Nuclides

i li__IHEQBl_QE_NWGLEeB_EQWEB_EkeNI_QEEBel10Ni_ELWIQ1t_eNQ PAGE 19 IHEB5001NeUIG1 ANSWERS -- COOPER

_86/03/04-GRAVES, D.

ANSWER 5.09 (2.00)

O psig = 14.7 pois = 212 deg F (0.5) 1000 psig = 1014.7 pais = 546.3 deg F (0.5) 546.3 _ 212 = 334.3 334.3 deg F / 90 deg per hour = 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (0.5 for the 90 deg/hr limit and 0.5 for the final time)

REFERENCE Steam Tables ANSWER 5.10 (2.00)

O.

Core flow would increase (0.5) due to e decrease in two phase flow resistence (0.5).

b.

Core flow would increase (0.5) due to en increase in natural circulation (0.5).

REFERENCE R0 circulation System Description, Figure 19, Rev 0 ANSWER 5.11 (2.00)

Solving P = (PoleE(t/T) (0.5 pts), where P = 2Po (0.5 pts) 2Po = (PoleE(t/T) 2 = eE(t/T)

In 2 = t/T (0.5)

.693 = t/T T = t/.693 = t (1/.693) 1.443t (0.5)

=

REFERENCE Rosctor Theory Review, pg 20

6t__EL&NI 111IEdi_DE119Ni_GQNIBQLi_6NQ_INSIBWHENI8IIQN PAGE 20 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 6.01 (2.50)

O.

- Manus 1 operation of the RBM BYPASS switch (0.5)

- < 30% power (0.5)

- Edge rod selected (0.5) b.

Failed Low:

Removes the LPRM input from the everaging circuit (0.25) and provides indication to the counting circuit that the input is INOP (0.25).

Failed High:

The higher input is averaged with the other inputs and processed es if it were a valid signal (0.5).

REFERENCE Rod Block Monitor Subsystem Lesson Plan, Rev 0, pg RBM-g, 16 ANSWER 6.02 (2.00)

Any 2/5 below e 1.0 es.

- Valve must be closed to start the pump.

- Velves automatically close on a LPCI start signal after reactor pressure has decreased to 185~235 psig.

- Valve must be fully open for pump speed > 204.

- Valve < g0% open, more than 2 minutes after pump start, trips pump.

- Velve must be partially open within 60 seconds of RR pump starting or the pump will trip.

REFERENCE Rosctor Recirculation System Lesson Plan, p.

Recirc-10 ANSWER 6.03 (1.00) 2 A constant voltage output with decreasing frequency requires increasing cxcitation current (0.67).

This would cause exciter / voltage regulator everheating (0.33).

REFERENCE Roactor Recirc'ulation System Lesson Plan, p.

Recirc-14 1

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

6t__EL8HI_IIIIEd1_QE11GNt_QQNIBQL&_8NQ_INSIBudENI8IlQN PAGE 21 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 6.04 (3.00)

O.

Decrease (0.25) due to loss of steam supply to SJAE (0.5).

b.

RWCU pumps trip (0.25) due to low flow as F/D FCV fails closed (0.5).

o.

Outboard MSIV's drift closed (0.25) as accumulators discharge (0.5).

d.

Rods indiscriminately scram (0.25) as scram valves open under spring pressure (0.5).

REFERENCE Plant Air System Lesson Plan, p.

PA-16 ANSWER 6.05 (3.00) o.

HPCI initiation signal must be present (0.5) and the manual isolation pushbutton on Panel g-3 is depressed (0.5).

b.

- The system will automatically restart when level decreases to the initiation setpoint (1.0).

- The high level trip signal may be reset and the system will restart (1.0).

REFERENCE HPCI Lesson Plan, Rev 0, pg HPCI-8, 32

1 I

ti__EL8HI_111IEdi_DE119Nt_GQNIBQLa_6NQ_INSIBudENI8IIQN PAGE 22 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 6.06 (3.00) o.

detector:

ion chamber (0.3).

actions:

reactor scram (0.3)

MSIV closure (0.3) main steem line drains shut (0.3) recirc loop semple valves shut (0.3) condenser air removal valves shut (0.3) mechanical vacuum pumps trip (0.3) b.

detector:

scintillation (0.3) actions:

none o.

detectors:

ion chambers (0.3) actions:

isolates the mir ejector off gas line (0.3)

REFERENCE Instrumentation Operating Procedures:

4.7.1, Hein Steam Line Radiation Monitoring System, Rev 8, pg 1 4.7.2, Air Ejector Off Gas Radiation Monitoring System, Rev g, pg 1 4.7.4, Process Liquid Radiation Monitors, Rev 6, pg 1 ANSWER 6.07 (2.00)

Chennels A and C level use the same sensing tops from the RPV.

If a leek occurred in the sensing line causing indicated level to be Icw, the RFP would speed up, increasing level, and could not trip due to high level (2.0 for explanation and concept).

REFERENCE System Operating Procedure 2.2.28, Feedwater System, Rev 35, pg 6 Nuclear Boiler Instrumentation Lesson Plan, Rev 0, figure 4 ANSWER 6.08 (2.00)

O.

2 b.

4 o.

2 d.

4 o.

3 f.

3 g.

1 h.

2 (0.25 each)

64__EL8HI_111IEdi_DE11GNi_GQNIBQLa_8NQ_INSIBWHENI6Il0N PAGE 23 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

REFERENCE 3

Nuclear Boiler Instrumenteilon Lesson Plon, Rev 0, pg N81-24, 25 ANSWER 6.09 (2.50)

(0.5 each)

- Channel festener ensemblies all meet in a control cell.

- Lifting handle boot, or protrusion, faces the rod in the control cell.

- Serial 9 on the fuel channel / lifting handle can be read from the center of the control cell.

- The channel spacer buttons are adj acent to the control rod blades.

- There is cell-to-cell symmetry.

REFERENCE s

Fuel Lesson Plan, p.

Fuel-20 ANSWER 6.10 (2.00) c.

8 (0.5) b.

- overvoltage (0,5) undervoltage (0.5)

- underfrequency (0.5)

REFERENCE RPS Lesson Plan, Rev 0, pg RPS-7

^

ANSWER 6.11 (2.00)

The flow control valve is tripped closed when pressure upstream of the velve is low (0.5) (less then 5 psis) to prevent drawing a vccuum on the RWCU system (0.5).

Vhen pressure between the flow ocntrol valve and the drain velves to the main condenser and redweste oystem is high (0.5) (greater then 140 psig), the valve trips to prevent overpressurizing the piping downstream of the FCV (0.5).

REFERENCE Reactor Water Cleanup lesson Plan, Rev 0, pg RWCU-9

Zi__EBQCEDUBER_=_NQBU8Li_8BNQBd8Li_EMERGENGl_8NQ PAGE 24 88Q10LQE1Q8L_GQNIBQL ANSWERS -- COOPER

-86/03/04-GRAVES, D.

6 ANSWER 7.01 (2.50)

O.

- Scram the reactor

- Trip the turbine Isolate the RWCU system

- Shut down both recirculation pumps and associated oil pumps when the MG sets have stopped (4 at 0.5 each) b.

Fuel pool (0.5)

REFERENCE CNS E0P 5.2.3, Loss of All Service Water, Rev 8 ANSWER 7.02 (3.00)

O.

None (0.5) b.

E0P-1 (0.25), E0P-2 (0.25) c.

E0P-3 (0.5) d.

E0P-2 (0.5) o.

E0P-1 (0.5) f.

None (0.5)

REFERENCE Ecergency Procedure 5.8, E0P/C, Rev 1, pg i 1

ANSWER 7.03 (2.00)

I o.

yes b.

yes o.

no d.

no o.

yes (0.4 each)

REFERENCE AP 2.4.2.2.3, Recirculation Pump Seal Failure, pg 1

~

Zi__EBQGEQuBE1_=_NQBd8Lt_8tNQBd8Lt_EMEBGENC1_8NQ PAGE 25 88Q19LQEIG8L_GQNIBQL ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 7.04 (2.00)

I Q.

True b.

False c.

False d.

True (0.5 each)

REFERENCE 60P 2.1.15, Reactor Recirculation Pump Startup and Shutdown CNS Technical Specifications 3.3.F.

I ANSWER 7.05 (2.00) o.

Place the mode switch in REFUEL (0.25) and check the Refuel Permissive Light (0.25) illuminstad.

Observe all green full-in lights on Panel 9-5 illuminated (0.5).

b.

Shut with individual control switches (0.5).

I Place the mode switch to RUN (0.25) when reactor pressure is less than 825 psig (0.25).

REFERENCE l

GOP 2.1.5, Emergency Shutdown from Power, pg 2 ANSWER 7.06 (3.00) c.

5 b.

3 c.

I d.

2 c.

6 f.

4 (0.5 each)

REFERENCE CNS GOP 2.1.1, Cold Startup Procedure, Rev 41, pg 8,9 h

Z2__EBQGEQWBE1_=_NQBU8La_8BNQBd8Lt_EUEBEENC1_8NQ PAGE 26 88DIQLQEIG8L_GQNIBQL ANSWERS -- COOPER

-86/03/04-6 RAVES, D.

ANSWER 7.07 (2.00)

]

o.

Hot Standby is a condition where reactor pressure is less than 1000 psig (0.5), coolar.t temperature is greater than 212 deg F (0.5),

and the mode switch is in the Startup/ Hot Standby position (0.5).

b.

1/4 core density means that 25% of the control rods are full withdrawn from the core (0.5).

REFERENCE 60P 2.1.9, Hot Standby Condition, Rev 5, pg 1, 2

l l

ANSWER 7.08 (1.00)

A.-

3 i

B.

1 l

C.

4 0.

2 REFERENCE CNS E0P 5.4.1, General Fire Procedure, Rev 17, Attachment "B",

pg 1 ANSWER 7.09 (2.50) o.

The 3 GEMAC's and associated recorder on panel 9-5 (1.0).

b.

The Yarways may be monitored locally in the Reactor Building (0.5).

c.

The reactor vessel level reference legs will begin to flash when l

the RPV pressure approaches saturation pressure for the drywell temperature, causing erroneous high reactor level indication (1.0).

REFERENCE CNS E0P 5.2.5.1, Loss of All Site AC Power Station Blackout, Rev 3, pg 3 l

Zz__EBQGEQWBER_=_NQBd6L&_8BNQBd8L&_EMEBGENGl_6NQ PAGE 27 88DIQLQEIGAL_GQNIBQL ANSWERS -- COOPER

-86/03/04-6 RAVES, D.

ANSWER 7.10 (2.00) o.

After a 5 minute time delay (0.25), the offges system will isolate with no dilution flow (0.75).

b.

By depressing and holding the 254 AV Reset button (0.5).

c.

Standby Gas Treatment System (0.5)

REFERENCE AP 2.4.8.4.6, Loss of Stack Dilution Fans, Rev 4 ANSWER 7.11 (3.00) o.

No (0.25).

The red and green lights indicate whether the actuating molenoid for the SRV is energized or deenergized (0.75).

b.

- The blue pressure switch light will be illuminetsd.

- Decreasing tailpiece temperature

- Megawatt load or steam flow returns to original value

- Suppression pool pressure, level, and/or temperature stops increasing

- Reactor pressure fluctuations as the SRV closes RPV level transient or level returns to normal

- Grader may accept other indications if they are appropriate (4 required at 0.5 each)

REFERENCE AP 2.4.2.3.1, Relief Valve Stuck Open, Rev 14, pg 1-2 e

n. -

..+.---

---,----,-wn a-

.,-m.-,.,e a

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

,,,,w-

,---s-

-,s---

w--s-.

~

Az__8tdIN11188IIVE_EBQQEQWBEtt_GQND1Il0 Nit _8NQ_LIdlI8IlQN1

.PAGE 28 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 8.01 (2.50) o.

- A deficiency in physical characteristics of a system or component which renders the item unable to perform to the design intent and operating license commitment for that system or component.

- Lack of required documentation to assure that the component in-service conforms to requirements.

- Noncomformance with an authorized operating procedure or instruc-tion.

- A deficiency in administrative controls intended to meet the Q.

A.

Program commitments or NRC Regulatory criteria.

(Any 2 at 1.0 each, wording need not be exact, but concepts should be similar) b.

True (0.5)

REFERENCE CNS Administrative Procedure 0.5, Nonconformance and Corrective Action, Rov 1, pg 1, 2

ANSWER 8.02 (3.50) o.

One depository, #1, contains keys necessary for operational controls, area access doors, and panel doors (0.5) or cimilar type wording.

The other depository, # 2, will contain keys necessary for operation of systems bypass switches normally within the control room (0.5).

b.

Depository #1 is under the control of the Shift Superviser (0.5).

Depository #2 is under the control of the Shift Supervisor (0.25) and the Control Room Operators (0.25).

c.

The CNS main key depository (0.5).

Also accept Key Custodian.

d.

The key will be inserted into the Mode Switch (0.5).

o.

Reactor Operator (0.5)

REFERENCE CNS Administrative Procedure 1.3, Key Control, Rev 0, pg 2

Az__8DMIN11188IIVE_EBQQEQUBEft_CQND111QNit_8ND_LIdlI8IIQN1 PAGE 29 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 8.03 (3.00)

- The plant is in a safe condition.

- The cause of the scram is understood or it is attributed to a spurious trip and is unlikely to reoccur.

- Corrective action has been identified and appropriately implemented.

- The proper automatic operation of plant safety-related systems has been observed.

- The Division Manager of Nuclear Operations approves the restart of the plant.

(3 required at 1.0 each)

REFERENCE Conduct of Operations Procedure 2.0.6, Reactor Post Trip Review and Rostart Authorization Procedure, Rev 1, pg 6-7 ANSWER 8.04 (2.00)

- Reactor vessel high pressure scram Relief valve actuations Safety valve actuations Shutdown cooling valve isolation on high pressure (0.5 each)

REFERENCE CNS Technical Specification 1.2 CNS Technical Specification 2.2 ANSWER 8.05 (2.00) e.

1.

Position light indication in the control room if the valve is so equipped (0.5) 2.

Locally by a second operator (0.5) 3.

Satisfactory performance of a flow operability surveillance (0.5) b.

One of the individual's supervisors (0.5)

REFERENCE CNS Procedure 0.9, Equipment Clearance and Release Orders, Rev 2, pg 2, 3

~

Az__8 QUIN 11IB8IIVE_EBQGEQUBEli_GQNDIIIQNit_88Q_L151I8I1QN1 PAGE 30 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 8.06 (1.50) a.

The STA must be manned whenever the reactor is not in cold S/D (1.0).

b.

10 minutes (0.5)

REFERENCE CNS Procedure 0.21, Shift Technical Advisor, Rev 0 ANSWER 8.07 (1.00)

To notify the DMNO or designated alternate during an emergency (1.0).

REFERENCE Conduct of Operations Procedure 2.0.5, Shift Communicator Responsibilities, Rov 0, pg 5 ANSWER 8.08 (3.00) e.

- jumpers lifted leads

- fuse removal

- blocked relay

- booted contacts

- installed breaker test blocks / actuator links

- mechanical j umper installed / removed blank flanges (5 required at 0.5 each) b.

Red plastic tag with a permanent number on it (0.5)

REFERENCE Control of Operations Procedure 2.0.7, Plant Temporary Modifications Control, Rev 0, pg 2, 3

Az__8DMIN11IB811VE_EBQQEQUBEft_QQNQIIl0 Nit _8NQ_LIdlI6IIQN1 PAGE 31 ANSWERS -- COOPER

-86/03/04-GRAVES, D.

ANSWER 8.09 (2.50) o.

Falso b.

True c.

False d.

False o.

True (0.5 each)

REFERENCE Nuclear Performance Procedure 10.26, Working over or In Reactor Vessel Rcquirements, Rev 0 ANSWER 8.10 (2.00)

- Both RBM channels shall be operable.

_ Control rod withdrawal shall be blocked.

- The operating power level shall be limited so that MCPR will remain above the safety limit, assuming a single error results in complete withdrawal of any single operable control rod.

(2 required at 1.0 each)

REFERENCE CNS Technical Specification 3.3.B.5 ANSWER 8.11 (2.00) c.

An individual holding an SRO license (0.5).

b.

An individual holding an R0 license (0.5).

c.

Control Room Refueling Monitor or Control Room Operator (accept either 0.5) d.

Refueling Floor Supervisor or SRO on the Refuel Floor (accept either 0.5)

REFERENCE Nuclear Performance Procedure 10.21, Special Nuclear Materials Control and Accountability Instructions, Rev 0, pg 2, 3