ML20129E203

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Exam Rept 50-445/OL-85-03 on 850401.Exam Results:Three Senior Reactor Operators & One Reactor Operator Failed.All Other Candidates Passed
ML20129E203
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 07/11/1985
From: Colley R, Whittemore J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20129E184 List:
References
50-445-OL-85-03, 50-445-OL-85-3, NUDOCS 8507160754
Download: ML20129E203 (33)
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OPERATOR LICENSE EXAMINATION REPORT No. 50-445/0L-85-03 Licensee: Texas Utilities Electric Company 400 North Olive Street Lock Box 81 Dallas, Texas 75201 Docket: 50-445 Construction Permit: CPPR-126 l i

Examinations administered at Comanche Peak Station (CPSES)

Chief Examiner: 7 !/ o K -

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f. E. Whitt'tmore, Examiner Date Approved by: -
  • 7((((9[

R. A. Cooley, Se$ tion Chief D4te / ~

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' Summary Examinations conducted on April 1-3, 1985 Written and oral examinations were administered to seven (7) Senior Reactor Operators and three (3) Reactor Operators, all of whom were currently cold licensed to operate CPSES facility. Three (3) Senior Reactor Operators and one (1) Reactor Operator failed the examination. All others passed.

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2 CPSES OPERATOR LICENSE EXAMINATION REPORT Report Details

1. Examination Results Written and oral examinations were administered to seven (7) Cold Licensed Senior Reactor Operators and three (3) Reactor Operators. Three (3) Senior Reactor Operators and one (1) Reactor Operator failed the written examination. All examinees passed the oral examinations.
2. Examiners J. E. Whittemore (Chief Examiner)

R. A. Cooley S. L. McCrory

3. This examination report is composed of the sections below:

A. Examination Review and Comment Resolution This section reflects comments made by the facility during the written examination review meeting held after completion of the written examinations. In general, editorial comments or changes made during the exam and subsequent review are not addressed.

Modifications have been included in the master examination keys which are included elsewhere in this report. The following personnel were present for the written examination review.

NRC Utility _

D. N. Graves R. Hawkins J. E. Whittemore D. Hubbard T. Lichty M. Niemeyer C. Turner Comments and resolutions are listed by section question number.

COMMENTS

1. Question 3.03 Part c. asks for inputs used to calculate rod insertion limits. The answer key includes Tave. At CPSES the Tave input is set to zero which may cause examinees to ignore this input.

Resolution: Ag ree. Tave is not required for full credit answer.

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2. Question 4.01 Part a. asks for actions required for a dropped fuel assembly striking another assembly. The key assumes fuel assemblies involved were spent fuel. Actions required by referenced procedures differ significantly concerning new fuel versus spent fuel. Since CPSES has no spent or reconditioned fuel on site, the examiner may assume new fuel and answer accordingly. There are no "Immediate Actions" in the sense of memorizing operating procedures immediate actions:

Resolution: Key changed to reflect that assuming spent fuel is not required for full credit answer. The reference lists prompt or initial actions to be taken for a fuel handling accident involving spent or new fuel and these actions are not significantly different. It is expected that a marginally satisfactory operator would inherently possess the knowledge to: 1. Evacuate the area and, 2. Inform supervision. These minimum actions are required in either case.

3. Question 6.02 The question asks to list what inputs are supplied to Steam Generator Water Level Control.

At CPSES a constant level program is used; therefore, the input from turbine impulse has been removed.

Resolution: Agree. Key modified.

4. Question 7.03/ CPSES does not require memorization of procedures 7.07 or attachments other than immediate action steps. We require the individual to be familiar with the procedure and be able to use the procedures to operate the plant.

Resolution: Neither answer was changed to reflect the generic comment above. Question 7.03 did not solicit detailed knowledge, but rather conceptual knowledge.of how to determine the location of a leaking componint. Any viable method of locating the leak was acce'pted as a correct answer for full credit. Question 7.10 sought only to identify equipment operated to specifically proclude voiding and did not solicit detailed procedural knowledge, u____--_____-_.________--_--__-______--____________

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4 B. Exit Meeting Summary At the conclusion of the CPSES site visit the examiners met with utility representatives to discuss results of the examinations. The following personnel were present for the exit meeting.

NRC Utility R. Cooley L. Barnes D. Graves R. Jones D. Kelly R. Seidel S. McCrory C. Turner J. Whittemore All requalification candidates were reported to have clearly passed the oral examinations. It was explained to those present that the written examination grades would not be available for at least one month and that the oral exam evaluations did not necessarily reflect written examination performance.

Areas of general weakness were reported to the facility. The identified weaknesses were found to exist with more than one candidate. The identified weaknesses were as follows:

1. Candidates experienced difficulty in utilizing the Unit Curve and Data Book.
2. Candidates exhibited a lack of familiarity with portable radiation survey instruments.
3. Senior Reactor Operators exhibited poor conceptual knowledge of basic plant transients and plant response to abnormalities.
4. Senior Reactor Operators were not familiar with procedures for proper document control, how to assure that drawings are current, and how to tell if design changes have been incorporated.
5. Non-shif t operators do not always receive new spec 4 fic information or changes important to plant operations.
6. Senior Reactor Operators that are performing shift duties as Reactor operators exhibit weakness in knowledge ir requirements and performance of plant administrative duties.

The utility was informed that preliminary examination results would be available in approximately 30 day >.

The meeting concluded with the examiners tha.' king the utility for their efforts towards the examination effort.

5 C. Requalification Program Evaluation-Report Facility: Comanche Peak Examiner: J. E. Whittemore Date(s) of Evaluation: 4/1-3/85 Areas Evaluated: X Written X Oral Simulator Written Examination

1. Overall -evaluation of examination: Marginal Performance
2. Evaluation of facility examination grading: N/A Oral Examination
1. Overall evaluation Satisfactory
2. Number conducted 10 Simulator Examination
1. Overall evaluation N_A
2. Number conducted Overall Program Evaluation Satisfactory Marginal X* Unsatisfactory (List major def t-ciency areas with brief descriptive comments)
  • Pending completion of accelerated training and reexamination of licensed personnel who failed the written examination.

Submitted Forwarded Approved

?b Branch Chief gExaminer ection Chief (/

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D. CPSES Examination and Key Date Administered: 4/1/85 Exam Type: Reactor Operator and Senior Operator Requalification

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U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _QQM8NQUE_EE6K_1_________

REACTOR TYPE: _EWB-WEQd________________

DATE ADMINISTERED: _Q54Qil01________________

EXAMINER: _WBlIIEdQBEt_Ji__________

APPLICANT: _________________________

INSIBUGI1QU5_IQ_8EELIG8 NIL 000 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 grcde requires at least 70% in each category and a final grade of at locst 80%. Examination papers will be picked up six (6) hours after tho examination starts.

% OF CATEGORY  % OF APPLICANT'S CATEGORY

__YoLUE_ _IQIok ___5GQBE___ _V6LUE__ ______________Q6IEQQBl_____________

_1Zi20__ _2d120 ___________ ________ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

_12120__ _2diga ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS

_10i10__ _25155 ___________ ________ 3. INSTRUMENTS AND CONTROLS

_121Q5._ 25t12 ___________ ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

_ZQig5__ 100100 ___________ ________ TOTALS FINAL GRADE _________________%

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

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j IPPLiCAUTI5~55GUATURE 1

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11_ EBING1 ELE 1_QE_NUQLE88_EQWEB_EL6NI_QEEB8Il0Nt PAGE 2 IHEBBQQ1Ned191t_HE8I_IB8NSEEB_8NQ_ELu1D_ELQW QUESTION 1.01 (1.20) r Ccmplete the following table'by supplying the missing words or

! phrases. Indicate direction, magnitude, and rate where applicable.

Rx. Period Rx. Power Response Start Up Rate

c. Small positive Rapid increase ( )
b. ( ) Constant ( )
c. Large negative ( ) Small negative (1.2)

QUESTION 1.02 (3.00) i

o. Explain the terms beta bar and beta bar effective. Your answer ,

should include an explanation of which term is larger in magni-tude and why. (1.5) t b. Explain how and why the above mentioned terms will affect re-I actor response throughout cycle life. (1.5)

QUESTION 1.03 (2.50)

c. For an operator taking data for a 1/M plot, how will the Shut-down margin (SDM) affect the time elapsed before a stable count l rate can be obtained after withdrawing rods ? (0.75)

! b. How will the initial count rate affect the count rate at crit-  :

! icality ? (0.75) l c. If the speed of the control rods were to somehow increase. What l would be the effect be on l

1. Rod height at criticality ? (0.5)
2. Count rate at criticality ? (0.5) i l

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(***** CATEGORY 01 CONTINUE 0 ON NEXT PAGE *****)

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l QUESTION 1.04 (2.75)

o. How and why will the magnitude of the Fuel Temperature Coeffi-

! cient (FTC) change as fuel temperature changes ? (1.25)

b. Explain the effect on the magnitude of the FTC due to :
1. Core power (0.75)
2. Core burnup (0.75)

QUESTION 1.05 (1.75)

After 30 days at 50% power, plant power is raised to 100%. Explain the reactivity adjustments the operator may have to make due to fission product poisons until stable conditions are reached. Your cnswer should discuss both major poisons. (1.75)

QUESTION 1.06 (1.00) ,

A motor operated centrifugal pump is operating at rated flow when I the discharge valve is throttled towards the shut direction.

Which of the following statements best describes the parameter changes that will occur ?

o. Flow constant, discharge pressure constant, motor amps in-crease, NPSH increases.
b. Flow decreases, discharge pressure increases, motor amps in- f
crease, NPSH increases.
c. Flow decreases, discharge pressure increases, motor amps in- i i crease, NPSH decreases.

l l d. Flow decreases, discharge pressure increases, motor amps de-i creases, NPSH increases. (1.0) i

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

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. It_'_EBINQIELE1_QE_NUQLE8B_EQWEB_EL6HI_QEEB6110Nt PAGE 4 IHEB59Q1NedIQ1t_HE8I IB8NSEEB_8NQ_ELu1D_ELQW QUESTION 1.07 (3.25)

Unit 1 is at 40% power when a single Reactor Coolant Pump (RCP) otops. Assume rod control in manual and no automatic or oper-ctor action occurs.

c. Describe what happens to the temperature of the affected loop and explain. (0.75)
b. Describe what happens to the delta T across all steam generat-ors'end the vessel or core. Explain. (1.0)
c. Describe what happens to unaffected steam generator pressure and explain. (0.75)
d. Explain the effect of stopping the RCP on individual loop and total coolant flow. (0.75)

QUESTION 1.08 (1.75)

c. How does requiring the operator to observe limits of Axial Flux Difference and Quadrant Power Tilt Ratio prevent exceeding core thermal limits ? (1.0)
b. Explain why significantly reduced RCS flow conditions will af-fact proximity to the Critical Heat Flux. (0.75)

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

. 2i_lEL8NI_ DES 10N_INGLUDINQ_18EEII_8NQ_EMEBGENQ1_11SIEd1 PAGE 5 QUESTION 2.01 (3.20)

c. What is the normal atmosphere inside the Pressurizer Relief Tank ? Why ? (0.8)
b. When relieving pressurizer safeties into the tank at approx.

650 degrees and 2250 psi, why isn't the safe operating pressure

(~100#) of the tank exceeded ? (1.0)

c. What are the 2 methods available to cool the tank and what is the DISADVANTAGE of each method ? (1.4)

QUESTION 2.02 (3.00)

c. For long term post accident cooldown, how might the ECCS lineup differ for a small versus a large coolant system rupture, and why would a different lineup be necessary ? (1.2)
b. What provisions are availaole to prevent overpressurization of the Residual Heat Removal (RHR) syctem ? (0.8)
c. Describe how the RHR pumps are protected from vibrating or over-heating when running for safety injection and RCS pressure in-creases above pump shut off head due to isolating the leak. (1.0) i QUESTION 2.03 (2.70)
a. Briefly describe how operation of the Reactor Coolant Pumps will be effected should the following inadvertant signals occur!
1. Phase "A" containment isolation. (0.6)
2. Phase "D" containment isolation. (0.6)
b. Briefly, in general terms, describe what action occurs fort
1. Control Room Emergency Recirculation signal. (0.5)
2. Control Room Emergency Ventilation signal. (0,5) l 3. Control Room Ventilation Inointion signal. (0.5) l l

NOTEl._ Mention of specific fans, dampers, filters, valves, ete; is NOT required to answer this question for full credit.

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

.'2x__EL8HI_QE11GN_INCLUQ1NG_18EEI1_6NQ_EMEBQENC1_11SIEd1 PAGE 6 QUESTION 2.04 (2.70)

o. Assume that one of the unit start-up transformers is out of ser-vice for maintenance and the other becomes disabled by a light-ning strike during an outage condition. Describe alternate meth-ods of supplying the unit class and non-class 6.9 KV buses. (1.2)
b. What determines if a 6.9 KV bus power supply will undergo a fast or slow transfer ? (1.5)

QUESTION 2.05 (1.40)

Briefly explain how to isolate a 118 VAC Class 1E inverter for cointenance and still maintain the inverter loads. (1.4)

QUESTION 2.06 (1.90)

Answer the following questions about the Auxiliary Feed System (AFW).

c. What prevents lowering the Condensate Storage Tank level below Technical Specification limit since it also supplies other systems ? (0.6)
b. What automatic action will occur upon AFW auto start and Safety injection to ensure maximum available water for the AFW system 7 (0.8)
c. Although the Service Water system is normally separated from the AFW system by 2 normally closed valves, what prevents contamina-tion of AFW due to valve leakage 7 (0.5) l QUESTION 2.07 (2.80)
c. List 8 major pieces of equipment used to remove a new fuel as-sembly from the shipping container, temporarily pince in storage, l and subsequently load it into the reactor. (1.6) l b. How does the manipulator operator know that the crane is posit-

! toned precisely for withdrawing or inserting a fuel assembly ? (1.2)

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

2t_llNSIBudENI1_8NQ_CQNIBQL1 PAGE 7 QUESTION 3.01 (2.20)

c. Briefly describe how the Nuclear instrument system is designed
to terminate inadvertent dilution of the Reactor Coolant Sys-tem, during shutdown or low power conditions. The answer should include setpoint(s), an explanation of how the feature is block- ,

ed or overridden, and automatic actions that occur. (1.2) i

b. Describe 2 circuits associated with the Power Range Nuclear Instrument that will alert the operator to abnormal flux distri-  !

bution. (1.0)

QUESTION 3.02 (2.70)

c. Control rod speed in automatic is determined by a " Total Error" l signal . What signals are used to determine the total error sig- i nel ? (0.8) 4
b. State the automatic rod speed for the following total error l l

signals: '

! 1. 1 Degree

2. 2.5 Degrees i

! 3. 4.5 Degrees (0.9) l

c. State where and why the non-linear and variable gain units are used in the automatic control of rod speed. (1.0) l l

QUESTION 3.03 L2.10)  !

c. What are the 2 separate rod position conditions that will gener-sta a rod deviation alarm ? (0.7) l
b. What are the 2 auto rod withdrawal blocks that are NOT manual l blocks ? (0.7) [

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c. What are the plant parameters used to calculate the control rod i insertion limits ? (0.7)  ;

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I i - 2t__INIIBWHENI1_8NQ_GQNIBQL1 PAGE 8 QUESTION 3.04 (2.70)

o. In the steam ditmp control system, what parameters or signals are sensed to provide arming signals f or turbine trip and loss lo f load ? Provide logic where applicable. (1.2)

! b. Describe how and when the staan dump valves will receive a trip i

open signal. (1.5) l QUESTION 3.05 (2.70) l O. What are 2 of the 3 reasons that make it necessary to control the speed of the Main Feed Pumps ? (0.8)

b. Other than manual, what 3 signals will override the level control signal and shut the feedwater control valves ? (0.9)

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c. How and why is reactor power used in controlling the feedwater control bypass valve ? (1.0)

QUESTION 3.06 (2.50) l I

c. What are the parameters that will very or modify the Overtemper- t J

ature N-16 trip setpoint. Explain how each parameter affects the setpoint. (1.5) i t

b. What is the purpose of the Overpower N-16 trip 7 (0.5) [

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c. What protection is afforded by the Power Range Negative Rate j trip 7 (0.5) t l

QUESTION 3.07 (3.20) l

a. Deserthe the instrument logio and setpoints necessary to insert f the Reactor Coolant low flow trips into the protection system i for 1 and 2 loop loss of flow. (1.2) (
b. Explain how and why the undervoltage ANO underfrequency low i flow reactor trips operate differently. (2.0) [

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  • 8t_'EBQQEQVBES_=_NQBd8Lt_8BNQBd8kt_EdEBQENQY_88Q PAGE 9 88DIQLQQIQ8L_QQNIBQL QUESTION 4.01 (2.00)
c. While acting as manipulator operator you observe the new fuel as-sembly that was j ust released fall over and strike another assem-bly:
1. What immediate action should you take ? (0.8)
2. After immediate action is carried out, what should be done with a fuel assembly in the vessel that appears to be dam-aged ? (0.6)
b. What should done if the hoist load starts decreasing before a fuel assembsy is bottomed in the vessel ? (0.6)

QUESTION 4.02 (3.05)

o. For low failures of a Source or Intermediate range nuclear in-strument channel the operator must take action dependent on power level at the time of fatture. Indicate how required actions vary, depending on power level, and explain why, for both instruments. (1.8)
b. For a power range channel failure, why is the operator required to remove " Control Power" fuses from the affected channel draw-er ? (0.75)
c. Why will a Power Range failure cause automatic control rod re-sponse if it fails high, but not when it fails low ? (0.5)

QUESTION 4.03 (2.80)

o. The procedure for a dropped control rod directs the operator to stabilize the plant before attempting retrieval. How is the plant stabilized ? (0.75)
b. When withdrawing a high worth rod from a dropped condition, how should the reactivity be compensated for ? (0.75)
c. How can the operator verify the position of a control rod with failed position indication 7 (0.5)
d. With a unit at full power, what must be done if a non-indicating control rod position cannot be verified ? Why ? (0.8)

(***** CATC00RY 04 CONTINUCD ON NEXT PA00 *****)

. it _ESQGEQWBER_=_NQBd8La_8tNQBd8Lt_EdEBGENC1 8NQ PAGE 10 86010LQ91G8L_GQNIBQL QUESTION 4.04 (2.00) f In the event it becomes necessary to evacuate the control roomt

o. Where will the various control room licensed personnel for unit (1.2) 1 proceed to ?
b. How will the Shift Supervisor communicate with other plant oper-ations personnel ? (0.8)

QUESTION 4.05 (2.80) I

o. State 4 parameters that should be monitored to aid in identify-ing a steem generator with a tube rupture. (1.2)

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b. State 4 octions that must be performed to isoiste a steem gener- l stor with a tube rupture. (1.6) l i

QUESTION 4.06 (2.70)

c. Explain the term " Adverse Containment" that appears in the Emer- ,

gency procedures and why the operator is given dif f erent limit- l stions with adverse conditions. (1.5)  ;

b. For deoressurization after a tube rupture, how will the operator depressurize ift l
1. Reactor Coolant Pumps (RCP's) running.
2. RCP's stopped, letdown in service.
3. RCP's stopped, letdown isolated. (1.2) i

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QUESTION 4.07 (2.50) l During blookout conditions you are able to manually start en Emer-l goney Olesel Generatort  !

I O. How will you manually load the safeguards bus if a Gafety In- 6 jection signal existe ? Why ? (1.5) .

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b. What is the first load you would piece on the bus ? Why ? (1.0)

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

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ANSWER 1.01 (1.20)

o. Large positive (0.3)
b. Infinite, zero (0.6)
o. Slow decrease (0.3)

REFERENCE WJE 1 W:stinghouse Fundamentals of Nuclear Physics, P. 7-17 ANSWER 1.02 (3.00)

o. Data bar is the average delayed neutron fraction or the weighted average fraction for the different fissionable materials present.

(0.5) Data bar effective is the effective fraction (0.25) and is smaller as it is the product of beta bar and an importance fac-tor. (0.25] The importance factor is generally less than one as delayed neutrona are less likely to cause fission. (0.51 (Will accept an explanation of how the importance factor is affected by Fast Fission and Non-leakage factors) (1.5)

b. Data bar and Data Der effective will decrease in value over cy-cle life (0.5) due to the changing concentrations of the differ-ent fissionable isotopes in the core. [0.5) Smaller values of the effective fraction means that the reactor period will be smaller or the reactor will respond quicker for a Given react-ivity change, as the core ages. (0.51 (1.5)

REFERENCE WJE 2 W:stinghouse Fundamentals of Nuclear Physics, Pp./-31,33,J4,36,40 l

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ANSWER 1.03 (2.50)

c. The closer to criticality, (less SOM) the longer time required to reach a stable count rate. (0.75)
b. A higher initial count rate will result in a higher count rate at criticality. (0.75)
c. 1. Critical rod height is not affected. (0.5)
2. Critical count rate will be lower. (0.5)

REFERENCE WJE 4 W:stinghouse Fundamentals of Nuclear Physics, Pp. 8-55,58,59 ANSWER 1.04 (2.75)

c. The magnitude of FTC decreases as fuel temperature increases [0.5) because the self shielding of the fuel decreases as the renonce peaks decrease in height. (0.75) (1.25)
b. 1. Fuel temperature increases as power increases ,(0.5) thus the magnitude of FTC decreases. (0.25) (0.75)
2. Fuel temperature decreases as core ages (0.5) no the FTC will decrease. (0.25) (0.75)

REFERENCE WJE 5 W:stin0 house Fundamentale of Nuclear Physics, P.6-41 ANSWER 1.05 (1.75)

The operator should only have to compensate for Xenon which will initially dip (0.51 and then attain it's 100% equilibrium concen-tration in 45-55 hours. (0.75) Snmortum (may initially experience o slight dip in concentration) but should and up et the same equil-ibrium value. (0.51 (1.75)

It_'EBINQ1ELES_QE_NuQLE88_EQWEB_EL8NI_QEEB8IlQNt PAGE 13 IUEBdQQ1N8dIQSt_UE81_IB88SEEB_880_ELu1D_ELQW ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

REFERENCE ,

WJE 7 CPSES Curve Book, Fig's 1.12, 1.13, 1.14 ANSWER 1.06 (1.00)

ANSWER----- d.

REFERENCE WJE 6 W stinghouse Thermal-Hydraulic Principles, Pp. 10-36 thru 10-47 ANSWER 1.07 (3.25)

c. Most of the coolant from the operating loops flows through the core, but some will flow backwards through the idle loop (due to the delta P across the core). (0.25] The not result is that the idle loop temperature becomes Toold of the operating loops.

(0.51 (0.75)

b. Since power demand has not changed, the remaining loops must make up for power not being supplied by the idle loop. (0.5)

With delta T across the idle steam generator essentially zero l (may be slightly reversed), the delta T ocross the operating S/O's and the core will increase. (0.5] (1.0)

c. With no heat transfer across the idle S/0, delta T (Tave.- Totm) must increase for the operating S/O's. (0.5) This means that operating S/0 temperature and pressure must decrease. (0.25) (0.75)
d. Total flow will stabilize somewhere above 75% [0.51 as the loss of 1 pump will decrease total head, increasing the flow rate of the operating pumps. (0.25) (0.75)

REFERENCE WJE g W:stinghouse Thermal-Hydraulic Principles, Pp. 12-15,16 l

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ANSWERS __ COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

j ANSWER 1.08 (1.75)  !

o. By controlling power (flux) distribution within the core, the I maximum heat generation and fuel temperature is limited. (0.5)

By limiting the difference in flux between portions of the core, the maximum heat generation in an area is limited. (0.5) (1.0)

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b. A reduction in flow rate causes an increase in coolant tempers- I ture. (0.75) i i

REFERENCE WJE 12 '

W stinghouse Thermal-Hyd sulic Principles, Pp.13-11,12,13 8

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ANSWER 2.01 (3.20) i c. Nitrogen, [0.4] to prevent inleakage of air and accumulating a j mixture of H2 & 02. [0.4) (0.8)

b. Steam is discharged into the tank through a sparger underwater.

l (0.5) The steem is cooled and condensed by mixing with water near ambient temperature. (0.5] (1.0)

c. 1. Spraying with cool reactor makeup water (0.4) produces radio-

! active liquid waste. (0.3] (0.7)

2. Circulating water through the RCOT HX (0.4] takes an abnor-l melly long time to cool the tank. (0.3] (0.7) l l

REFERENCE WJE 22 System Description 11-1, P.S.6 l

2.02 (3.00)

ANSWER

o. During conditions where RCS pressure is above RHR pump shut off l head and the RWSf to at low level. (0.6) The RHR pump discharge i can be directed to the auction of the S1 and Centrifugal Charg-l ing pumps, or RHR pumpo may be stopped. (0.61 1/2 credit fort Hot leg rectro. (1.2)
b. System inlet valves close on increasing preneure. (0.4)

High capacity pump suction relief valves. (0.41 (0.8)

c. Part of the heat exchanger outlet flow is rectreed back to the RHR pump suction. (0.5) A rectro flow control valve opens on low flow (G75 OPM) and clones on increased flow (12000PM). (0.S) (1.0)

REFERENCC l WJC 24 System Dencription 11-6, Pp. 7,0,14 i

l l

l l

l._______________._______

2t__EL8HI_QES1Q6_INGLWQ1NQ S8EEIl_880_EdEBQENC1_SYSIEd3 PAGE 16 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 2.03 (2.70)

c. 1. RCP seal return will isolate, [0.3] but a relief valve will direct return flow to the PRT until normal seal flow can be re-established. [0.31 (0.6)
2. Virtually all cooling will be lost to the RCP's (0.3] which must be restored quickly or the pumps must be tripped. (0.31 (0.6)
b. 1. The system gons on closed loop recirculation. (0.5)
2. Aligns control room ventilation for Oxygen replenishment. (0.5)
3. Totally isolates control room from out side air (to preclude entry of toxic gas). (0.5)

REFERENCE WJE 25 System Description !!-7, Pp. 15,16,27,36 ANSWER 2.04 (2.70)

e. The non-class buses can be supplied by opening the 22 KV Main Generstor disconnect (0.31 and feeding back from the main trans-formers to the Auu. transformers. (0.3) The class buses can be supplied by the non-class buses after they are powered as above (0.3] or supplied by the diesels. (0.31 (1.2)
b. A niow transfer will occur ift
1. Normal breaker open.
2. Running bus voltage < 35% normal.
3. Hus feeders tripped.
4. Alternate bus voltage > 05% (0.375 es.

ORI A fast transfer will occur ift

1. Sufflotent alternate power supply voltage.
2. Phases matched within 40 degrees.
3. Non 10 bue (0.0 so.)

Accept wither answer for full credit. (1.51 l

l _ _ _ __ -

  • 2t_'_EL8HI_QES10N_INCLWQ1NQ_S8EEII_8NQ EdEBQENC1_SISIEUS PA0E 17 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

REFERENCE WJE 27 System Gescription VII-1, Pp. 17,40,41 ANSWER 2.05 (1.40)

It will be necessary to open the DC and AC feeders to the inverter.

(0.5) Power con be supplied to the AC loads via the By-pass trans-former. [0.51 by operation of the panel transfer switch. [0.41 (1.4)

REFERENCE WJE 28 0:ng. # 2323-El-0018 ANSWER 2.06 (1.00)

e. Other systems supplied by the tank are prevented from lowering the tank level below minimum by the elevation of their supply nozzles. (0.6)
b. Auto start - !solates condensate make-up and reject lines. (0.4)

S.I. - De-energizes condensate transfer pump. (0.4)

c. There is a normally open h10h point leak off between the normel-ly shut valves. (0.5)

REFERENCE WJE 20 System Description V!!!-0 Pp. 6-0 i

l l

i l

. 2i__tL8HI_QE1198_INCLUQ1NQ_18EEll_8NQ EBEBGENC1_S11IEUS PAGE 18 l

ANSWERS _- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 2.07 (2.80)

o. 1. Fuel Oldg. overhead crane. 6. Transfer Car.
2. Inspection Machine. 7. Fuel 81dg. Opender.
3. New Fuel Elevator. 8. Containment Uponder.
4. Fuel Sidg. Bridge Crane. 9. Manipulator Crane (0.2 es.]
5. RCCS change fixture. (any 8, 0.2 ea.) (1.6)
b. The bridge and trolley are positioned in relation to a pre-es-tablished grid pattern referenced to the core by an X-Y coord-l inste servo system, read directly by the operator. (1.0) A Video l system allows the operator to view fuel assemblies position and l movement. [0.2] (1.2)

REFERENCE WJE 30 System Description X-1, Pp. 5,6,17 l

l l

l I

I

a 2x_'_INSIBudENIS_8NQ_QQNIBQLS PAGE 19 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 3.01 (2.20)

o. The source range provides a doubling signal set to actuate when flux doubles (within 9 minutes).[0.6) The signal will shif t charging pump suction from the VCT to the RWST. (0.3) The fee-ture is manually blocked for approach to criticality, with a back up block provided by P-6. (0.3] (1.2)
b. Detector current comparator compares each upper and lower det- ,

ector with the average of the other upper and lower detector currents. (0.25) a (2%) deviation will cause an storm. (0.25) (0.5)

The output of each channel is compared with the other 3 channels.

(0.25] If 1 channel deviates (by more than 2%) from the lowest of the other channels an alarm will occur. (0.25] (0.5) '

REFERENCE WJE 13 System Description !!!-1, Pp.0,11 ANSWER 3.02 (2.70)

c. 1. Temperature error signal.
2. Power mismatch signal. (0.4 en.)

OR)

1. Auct. Teve.
2. Tref.
1. Auct. Hi Power. (0.27 ea.) Accept either answer. (0.8)
b. 1. May be 0 or o steps / min.
2. O steps / min.
3. 56 steps / min. (0.3 each) (0.9)  ;
o. Both are used in the power mismatch circuit. (0.4) The non-lin-ear gain unit causes a larger change in power to have a larger effect on rod apeed. (0.3) The variable gain unit imposes a lower gain at higher power levels. (provento overshoot) (0.31 (1.0) l R[rCRCNCC WJC 14 l l

System Description !!!-3, Pp.11,12  ;

t i

I

(

1

I 21__INSIBudENI1_6NQ_QQNIBQL1 PAGE 20 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 3.03 (2.10)

O. 1. Any shutdown rod < 210 steps. (0.35)

2. any 2 rods in a bank > 6 steps apart. (0.35)
b. 1. Low power auto rod withdrawal block. (0.35)
2. Bank "0" auto rod withdrawal block. (0.35)
o. 1. Tave. (0.35)
2. % N-16 power. (0.35)

NOTE! Teve set to "0", allow full credit if omitted.

REFERENCE WJE 15 System Description !!!-3, P.13 & !!!-4,Pp. 9,17 ANSWER 3.04 (2.70)

o. Loss of loadt Turbine impulse pressure rate of decrease. (0.4)

Turbine tript 4 turbine stop valves closed. (0.4) 2/3 turbine control oil pressures low. (0.4)

b. Only in the Tave mode (0.4) when sufficient Tave-Tref deviat-ion exist to require high (50% or 100%) steam dump demand. (0.6)

Air is routed directly to valve actuators (through arming sole-noids) bypassing the pneumat ic pos it ioner. [0.51 (1.5)

REFERENCE WJE to System description !!!-7, Pp. 4,7,0

Sz__INSIBudENI1_860_GQNIBQL1 PAGE 21 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 3.05 (2.70)  !

FR03.NSP.T4AEaWAma661W01DeWNoist5oHIWole80UIinear range at low power.

2. Reduce pump power requirements.
3. Reduce feed control valve erosion. [any 2, 0.4 each] (0.8)
b. 1. High S/G 1evel.
2. Rx. trip and low Tave.
3. Safety inj ect ion. [0.3 each] (0.9)
c. Auctioneered high power [G.3] is used to anticipate changing load on the S/G. [0.3] This will improve the response of the bypass valve. [0.4] (1.0)

REFERENCE WJE.19 System Description III-8, Pp.2,5,6 ANSWER 3.06 (2.50)

c. T-cold [0.3] acts to lower trip setpoint when t-cold is above normal full power value. [0.23 (0.5)

RCS pressure [0.3] lowers setpoint when pressure is below rated pressure. [0.2] (0.5)

Delta-q [0.33 lowers setpoint if flux difference. increases. [0.2][0.5)

b. Protects against high power density (KW/FT.) (0.5)
c. DNB, [0.3] in the event of multiple rod drops. [0.23 (0.5)

REFERENCE WJE 20 System Description III-9, Pp.6-8

az__INSIBudENIS_ANQ_QQNIBQL1 PAGE 22 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 3.07 [3.20]

a. 1. Single loop loss of flow will insert if 2/4 power ranges are above 48%. [0.4]
2. Two loop loss of flow will insert if 2/4 power ranges >10%

[0.3] OR; [0.2] 1/2 impulse pressures > 10% [0.33 [0.8)

b. The undervoltage trip is to provide a trip signal on loss of-power to the RCP's. [0.4] The reactor will trip and RCP's contin-ue to provide coastdown flow. [0.4] The underfrequency trip pro-vides protection for a grid disturbance. [0.43 The.RCP breakers and reactor are tripped [0.4] to prevent deceleration and loss of coastdown flow. [0.43 [2.01 REFERENCE WJE 21 System Description III-9,, Pp.9,10,48 1

i

.Jst__EBQGEQMBEl_ _NQBd8Lt_8tNQBd6Lt_EMEBGENGl_8NQ PAGE 23 B8DIQLQQIGeL_GQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 4.01 (2.00)

s. 1. (Assume that the assembly struck may be spent fuel), notify Shift Supervisor (0.4] and immediatly evacuate. [0.4] (0.8)
2. If practical, place in the containment fuel storage racks or in a location specified by supervisor as an interim measure. (0.6)
b. Lift assembly clear of the vessel for inspection. (0.6)

REFERENCE

-WJE 32 RF0 103, p.3 & RF0 302, P.4 ANSWER 4.02 (3.05)

c. Source Range-- With power below the P-6.setpoint, the channel must be repaired before any positive reactivity addition (0.3]

as it is not considered safe to increase power from this level with 1 channel of' indication and protection, thus it is a Tech.

Spec. requirement. [0.3] Above the P-6 setpoint, continue op-eretion as protection from Source Range is already blocked.[0.3)

Intermediate Range-- The operator must not add positive react-ivity if the failure occurs < the P-10 setpoint (0.3] as Tech.

Specs. require 2 channels at this power level. [0.3] Above P-10, continue normal operation as there is adequate' protection available (from the Power Range). [0.3] (1.8)

b. To insert certain trips into the protection system and preserve the required tripping logic. (0.75)
c. The control signal uses auctioneered high power. (0.5)

REFERENCE WJE 33 ABN 701A, 702A, 703A

-41__EBQQEQUBE1_=_NQBdeLt_8BNQBd6Lt_EMEBGENQ1_8NQ PAGE 24 88Q10LQEIG8L_QQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 4.03 (2.80)

c. Manipulate turbine load to match Teve and Tref.

(Accept dilution for 3/4 credit as dilution is not feasible at EOL.) (0.75)

b. Increase turbine load as Tave increases to match Tave/ Tref [0.4) or borate (0.35) (0.75)

~

c. Determine position with in-core detector measurements. (0.5)
d. Reduce' power (to 50%) [0.6) to ensure _ power distribution peaking factor limits are not exceeded. [0.2)

(Allow full credit for any conservative action) (0.8)

REFERENCE.

WJE 34 ABN 712A

. ANSWER ~4.04 (2.00)

e. Shift Supervisor and RO to hot shutdown panel. [0.81 Relief RO.

to the switch transfer panel. [0.4) [1.2)

b. Gaitronics [0.4) and the Safe Shutdown sound powered phone system. [0.43 (0.8)

REFERENCE WJE 35 ABN.905A

e at__EBQQEQUBE1_=_NQBd8Lt_8ENQBd8Lt_EMEBGENQ1_8NQ PAGE 25 88DIQLQQ108L_QQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER -4.05 (2.80)

c. ~ 1. Narrow range level
2. Blowdown rad. monitor

'3. S/G sample activity

4. Steam line rad monitor
5. Feed flow > steam flow- [any 4, 0.3 es.] (1,2)
b. 1. Isolate AFW
2. Close MSIV's
3. Verify PORV's closed
4. Isolate steam to AFW pump
5. Isolate feedwater j
6. Isolate B/D and sample [any 4, '

0.4 es.] (1.6)

REFERENCE WJE 37

'Fecility question bank, ERG 21,22, ANSWER 4.06 (2.70)

c. Containment pressure > 5 psig [0.3], > 5 REM /Hr. [0.3], Inte-grated contaiment dose > 10CE-6) RAD [0.33 Instrumentation used during emergencies will be affected by these adverse conditions.

[0.6] (CAF for more complete answer) (1.5)

b. 1. Normal spray.
2. Auxiliary spray.
3. Pzr. PORV'S [0.4 each] (1.2)

REFERENCE WJE 38 EOS 3-1, Step 8

~ iz__ E B Q Q E Q U B E1_=_N Q Bd 8 Li_8 RU Q B d 8 Li_ E tlE B G E N Q1_8N Q PAGE 26 88019LQQIQ8L_QQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

l ANSWER 4.07 (2.50)

-o. Roset'the SI signal OR, . place control switches in " Pull To Lock"- [either method 0.75] to prevent energizing unwanted loads and jeopardizing newly acquired power source. [0.75] (1.5]

b..A station service water pump [0.53 to supply diesel cooling water. [0.5] (1.0)

REFERENCE

,WJE 39

'ECA'O.0, P.5 4

s 4

k

_ _ . ,,,.r.-- , _ - . . , - - - _ _ _ , - . _ _ _ _ _ _ . , _ , , ,,,,.___.e, . _ _ _ . - _ . _ . . , , . .t , ,, , , , . . - - _ , . . _ . , , . _ . , - - . - -

e U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _QQMANQHE_EE6K_1_________

REACTOR TYPE: _EMB-WEQd________________

DATE ADMINISTERED: _Q52Q3/Q1________________

EXAMINER: _WB11IEdQBEz_Jz__________

APPLICANT: _________________________

IN11BQQIlQNS_IQ_6EELIQ6 nil Vao 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 grade requires at least 70% in each category and a final grade of at locst 80%. Examination papers will be picked up six (6) hours after the examination starts.

% OF CATEGORY  % OF APPLICANT'S CATEGORY

__ VALVE _ _IQIaL ___SQQBE___ _YoLVE__ ______________QoIEQQBl_____________

_1Zz2D__ _25tZ2 ___________ ________ S. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

_1Zz2D__ _2dzZ1 ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

_1ZzaQ__ _24tak ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

_1Zz2D__ _24zZ1 ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS

_kHzkD__ 100z00 ___________ ________ TOTALS  ;

i d

FINAL GRACE _________________%

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

PPL50 UT 5~55GU5TURE~~~~~~~~~~~~~~

, 5t_'_IBEQBY_QE_NUGLE88_E9 WEB _EL8MI_QEEB8Il0Nt_ELu1QSt_8NQ PAGE 2 IBEBdQQ188 DIGS QUESTION 5.01 (2.60)

A clean core is started up and taken to 50 % power, where it re-moins for 30 days:

o. Describe the reactivity changes the operator must compensate for due to fission product poisons. (1.4)
b. After 30 days power is increased to 100%. Explain any further reactivity changes required. (Specific reactivity values are NOT required) (1.2)

NOTEI Indicate approximate time and duration of reactivity changes.

QUESTION 5.02 (1.20)

Complete the following table by supplying the missing words or phrases. Indicate direction, magnitude, and rate where applicable.

Rx. Period Rx. Power Response Start Up Rate

c. Small positive Rapid increase ( )
b. ( ) Constant ( )
c. Large negative ~ ( ) Small negative (1.2)

QUESTION 5.03 (2.50)

c. For an operator taking data for s 1/M plot, how will the Shut-down margin (SOM) affect the time elapsed before a stable count rate can be obtained after withdrawing rods ? (0.75)
b. How will the initial count rate affect the count rate at crit-icality ? (0.75)
c. If the speed of the control rods were to somehow increase. What would be the effect be on:
1. Rod height at criticality ? C0.5)
2. Count rate at criticality ? (0.5)

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

. Hi__IBEQB1_QE_NUQLE88_EQWEB_EL8HI..QEEB8Il0Nt_ELu1Q1t_8NQ PAGE 3

'IBEBdQQ1Ned1GS QUESTION 5.04 (2.75)

e. How and why will the magnitude of the Fuel Temperature Coeffi-cient (FTC) change as fuel temperature changes ? (1.25)
b. Explain the effect on the magnitude of the FTC due to :
1. Core power (0.75)
2. Core burnup (0.75)

QUESTION 5.05 (2.80)

From the statements below, choose the most correct words or phrases (in parentheses) and write them on your answer sheet:

e. The ratio of peak to average value of power distribution is known as (peaking factor, thermal limit). (0.4)
b. The value of the Heat Flux Hot Channel factor will (increase, decrease, remain constant ) when power is decreased. (0.4)
c. The Heat Flux Hot Channel factor limit (assures, does not assure) that DNB will not occur during normal operation. (0.4)
d. Calculation of Enthalpy Rise Hot Channel factor assumes core power is (uniform, not uniform) and flow through each channel is (the same, different) throughout the core. (0.8)
c. With a (higher, lower) value of Enthalpy Rise Hot Channel fact-or, the coolant is (closer to, further away from) DNB conditions.(0.8)

QUESTION 5.06 (2.80)

o. Explain what happens to the enthalpy change Ch= BTU /LBM) on the secondary side of the steam generator as power is increased. (1.2)
b. Theoretically, if RCS flow were doubled, the core delta T would halve, resulting in less complicated reactivity effects and bet-ter core power distribution. Why wouldn't this design change be cost effective ? (1.6)

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

St__IbiDB1_QE_NVQLE68_EQWEB_EL6HI_QEE86Il0Nt_ELulD$t_68Q PAGE 4 INEBdQQYN6dIQS QUESTION 5.07 (3.25)

Unit 1 is at 40% power when a single Reactor Coolant Pump (RCP) ctops. Assume rod control in manual and no automatic or oper-otor action occurs.

c. Describe what happens to the temperature of the affected loop and explain. (0.75)
b. Describe what happens to the delta T across all steam generat-ors and the vessel or core. Explain. (1.0) l
c. Describe what happens to unaffected steam generator pressure and explain. (0.75)
d. Explain the effect of stopping the RCP on individual loop and total coolant flow. (0.75) 1

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

l

. ht__EL6HI_11SIEMS_QESIGNt_GQNIBQLE_8NQ_INSIBudENI8I1QN PAGE 5 QUESTION 6.01 (2.40)

During normal operation at 75% power a single Power Range channel upper detector fails high. Procedures ABN-703A requires that the feiled channel be defeated. Explain why the following actions Gust be taken.

o. Place the Rod Stop Bypass switch in bypass. (0.6)
b. Place the Power Mismatch switch in bypass. (0.6)
c. Place the Upper and Lower Section Selector switches to the failed channel. (0.6)
d. Select the failed channel on the Comparator Channel Defeat switch. (0.6)

QUESTION 6.02 (2.90)

e. What are the three plant parameter input signals used by the three element Steam Generator Feedwater Control System? (Do not include turbine impulse pressure or steam pressure.) (0.9)
b. . What is the purpose of the turbine impulse pressure signal used in the S/G Level Control System? (0.5)
c. Considering the Steam Generator Level Control System, indicate the effects of a high failure of the Steam Header Pressure de-tector. Assume power at 50%, and no operator action. Consider instrument failure with Feed Pump speed control in automatic AND in manual. (1.5)

QUESTION 6.03 (3.20)

c. Describe the instrument logic and setpoints necessary to insert the Reactor Coolant low flow trips into the protection system for 1 and 2 loop loss of flow. (1.2)
b. Explain how and why the undervoltage AND underfrequency low flow reactor trips operate differently. (2.0)

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

ht__EL8HI_111IEMS_QE110!k_QQNIBQLt_8NQ_IN11BWMENI8I1QN PAGE 6 QUESTION 6.04 (3.00)

c. For long term post accident cooldown, how might the ECCS lineup differ for a small versus a large coolant system rupture, and why would a different lineup be necessary ? '(1.2)
b. What provisions are available to prevent overpressurization of the Residual Heat Removal (RHR) system ? (0.8)
c. Describe how the RHR pumps are protected from vibrating or over-heating when running for safety injection and RCS pressure in-creases above pump shut off head due to isolating the leak. (1.0)

. QUESTION 6.05 (2.70)

a. Assume that one of the unit start-up transformers is out of ser-vice for maintenance and the other becomes disabled by a light-ning strike during an outage condition. Describe alternate meth-ods of supplying the unit class and non-class 6.9 KV buses. (1.2)
b. What determines if a 6.9 KV bus power supply will undergo a fast or slow transfer ? (1.5)

QUESTION 6.06 (1.40)

Briefly explain how to isolate a 118 VAC Class 1E inverter for nointenance and still maintain the inverter loads. (1.4)

QUESTION 6.07 (1.60)

e. What plant conditions are required before the Pressurizer Pres-sure Safety Injection signal can be blocked ? (0,5) b.-How is the signal unblocked ? -(0.5)
c. Name any other function (s) generated by this signal ? (0.6)

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

Zi__EBQQEQUBER_:_NQBU8Lt_6BNQBU8Lt_EUEBGENQX_66Q PAGE 7 88Q10LQQIQaL_GQNIBQL QUESTION 7.01 (3.00)

During initial fuel load:

c. After inserting a fuel assembly into the core, when can the grip-pers be released ? (0.6)
b. If loading is suspended for a 10 hr. period due to problems with vessel level, what are 2 requirements that must be satisfied be-fore continuing fuel load ? (1.0)
c. Where are fuel status boards maintained ? (0.9)
d. What is unique about the first fuel assembly inserted into the vessel, after the temporary neutron detectors are in place ? (0.5)

QUESTION 7.02 (2.60)

c. For control of the plant in hot standby from outside the control room, what are the general guidelines to be used in the decision to transfer control of equipment to the Hot Shutdown Panel ? (1.0)
b. Why is it not desirable to transfer control of pressurizer pres-sure and level upon control room evacuation ? (0.8)
c. If access to the control room or cable spreading room is not possible, how can safety inj ection be blocked for cooldown ? (0.8)

QUESTION 7.03 (3.00)

c. For leakage INTO the Component Cooling System (CCW), initial action required of the operator is to stop safeguards equipment in the affected train. What equipment is affected ? (0.9)
b. Describe how the system is manipulated to find which loop has the leaking component. (1.2)
c. Once the loop is identified, what are 3 checks that can be per-formed to identify the leaking component ? (0.9)

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

. Zi__EBQGEQUBE1_ _NQBdaLt_8BNQBdebt EdEBQENGI 6NQ PAGE 8 '

88DIQLQQIC8L_CQNIBQL l

QUESTION 7.04 (2.80) i

o. The procedure for a dropped control rod directs the operator to stabilize the plant before attempting retrieval. How is the plant stabilized ? (0.75)
b. When withdrawing a high worth rod from a dropped condition, how should the reactivity be compensated for ? (0.75)
c. How can the operator verify the position of a control rod with failed position indication ? (0.5)
d. With a unit at full power, what must be done if a non-indicating control rod position cannot be verified ? Why ? (0.8)

QUESTION 7.05 (2.00)

In the event it becomes necessary to evacuate the control room:

O. Where will the various control room licensed personnel for unit (1.2) 1 proceed to ?

b. How will the Shift Supervisor communicate with other plant oper-ations personnel ? (0.8)

QUESTION 7.06 (1.50)

For a Reactor coolant system water inventory balance Cleak rate) test:

o. What are the time and plant conditions specified for a success-ful test ? C0.7)
b. Describe how the CVCS volume change is determined for the test ? (0.8)

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

. - Zz _*_EB Q Q EQ U B E R _:_N Q BB8L t_8 BN Q BM 8 L t_ EM E B Q ENQ1_8N Q PAGE 9 88Q19LQQ1Q8L_QQNIBQL QUESTION 7.07 (2.40)

During natural circulation cooldown*

o. What are 2 restrictions imposed by the procedure to minimize the possibility of void formation ? (0.8)
b. What equipment is required to be operating by EOS-02 to minimize the possibility of vessel head void formation ? (0.4)
c. When cooling down with a void and it becomes possible to restore forced flow, where (relative values) would you adj ust pressuri-zor temperature and level before and after attaining forced coolant flow ? (1.2)

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

. Ax_*_8DMINISIB8IIVE_EBQQEQVBEft_QQNQlIl0NSt_8NQ_ Lid 118Il0NS PAGE 10 QUESTION 8.01 (2.60)

c. What are the minimum requirements for licensed personnel when :
1. Two units are in mode 5 ?
2. One unit in mode 6, no fuel movement in progress, and the other in mode 1?
3. Both units in mode 1? (1.8)

NOTEI Be specific as to the type of license required and required location.

b. What is the general nature of the Shift advisors responsibil-l ities and to whom does he report ? (0.8)

QUESTION 8.02 (2.00)

O. Is it permissible at Comanche Peak to disable a " Nuisance" an-nunciator ? Explain. (0.8)'

b. E at precaution must be exercised when disabling an annunciator
foi maintenance ? (0.8)
c. As the oncoming Shift Supervisor, how could you recognize an en-nunciator or instrument that was out of service ? (0.5) i
d. Where could you obtain information on the disabled indication ? (0.8)

QUESTION 8.03 (2.50)

c. Explain the 3 types of temporary changes to procedures. Include time limits or expiration times where appropiate. (1.5)
b. Explain the different terms in the following procedure design-ation:

OPT-TP-85A-2 (1.0)

[***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

. Atf_6DMINISIB6IIVE_EBQQEQUBEft_CQNDIIl0NSt_6NQ_L1dII6IlQNE PAGE 11 QUESTION 0.04 (3.10)

o. Upon activation of the emergency plan, what are the 2 basic dut-ies to be performed by the Shift Advisor ? (0.8)
b. Describe how the responsibility for Emergency Coordinator would shift after declaring an Unusual Event that gradually escalates to a Site Emergency. (1.0)
c. Name all individuals by (title) who can assume responsibility as:
1. Technical Support Center Manager ?
2. Operations Support Center Manager 7 (1.3)

QUESTION 8.05 (2.80)

c. How is a valid Quadrant Power Tilt Ratio (QPTR) obtained with one Power Range instrument inoperable ? (1.2)
b. Why are the detector current values normalized in the calcula-tion ? (0.8)
c. How many penalty minutes would be assessed for the following Axial Flux Difference conditions at Beginning of life ?

POWER LEVEL TIME AFD

1. 90% 10 min. +6%
2. 60% 20 min. -5%
3. 45% 12 -7%
4. 10% 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> +9% (0.8) e

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

. At_'_8Dd1N11IB8IIVE_EBQGEDWBEft_QQNQII1QN1t_8NQ_LIMII8IIQN1 PAGE 12 QUESTION 8.06 (1.80)

During operation at full power the Reactor Operator informs the SRO in the control room that the plant is being operated in violet-ton of a safety limit.

c. What are the specific safety limits of concern 7 (0.8)
b. Why is the above scenario very unlikely to ever occur ? (1.0)

QUESTION 8.07 (1.50)

c. What comprises Non-Compliance with a Technical Specification 7 (0.75)
b. Is it ever allowable to enter an operational mode without meet-ing the Limiting Conditions for Operation for the mode being entered ? Explain. (0.75) l l

i

(***** END OF CATEGORY 08 *****)

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

. 51_'_IHEQB1_QE_NWQLE88 EQWEB_EL8NI_QEEB6IIQNt_ELUIDS&_8NQ PAGE 13 IHEBdQQ1NedIQS ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 5.01 (2.60)

c. The operator must withdraw rods or dilute the RCS to compensate for the build up of Xenon to equilibrium in 45-55 hours (0.8) and Samarium in 400-500 hours. [0.6) (1.4)
b. Again Xenon will increase to a new higher equilibrium value in 45-55 hours. (0.6) Samarium reactivity will not change. [0.6]

(Both may undergo a slight dip before increasing to or returning to equilibrium) (1.2)

REFERENCE WJE 58 Curve Book fig;s 1.12, 1.13, 1.16 ANSWER 5.02 (1.20)

c. Large positive (0.3)
b. Infinite, zero (0.6)
c. Slow decrease (0.3)

REFERENCE WJE 59 W3stinghouse Fundamentals of Nuclear Physics, P. 7-17 ANSWER 5.03 (2.50)

c. The closer to criticality, (less SDM) the longer time required to reach a stable count rate. (0.75)
b. A higher initial count rate will result in a higher count rate at criticality. (0.75) i

! c. 1. Critical rod height is not affected. (0.5)

2. Critical count rate will be lower. (0.5) i L

l

. Et_'_IHEQBl_QE_NVQLE68_EQWEB_EL6HI_QEEB6IIQNt_ELVIQS&_8NQ PAGE 14 IHEBBQQ1N8BIQ1 l ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

I REFERENCE WJE 4 W0stinghouse Fundamentals of Nuclear. Physics, Pp. 8-55,58,59 ANSWER 5.04 (2.75)

o. The magnitude of FTC decreases as fuel temperature increases [0.5) because the self shielding of the fuel decreases as the resonce peaks decrease in height. [0.75) (1.25)
b. 1. Fuel temperature increases as power increases ,[0.5] thus the magnitude of FTC decreases. [0.25] (0.75)
2. Fuel temperature decreases as core ages (0.5) so the FTC will decrease. [0.25] (0.75) l l

REFERENCE WJE 5 l

W:stinghouse Fundamentals of Nuclear Physics, P.6-41 i

I ANSWER 5.05 (2.80) j o. Peaking Factor (0.4) l l b. Increase. (0.4) l l c. Does not assure. (0.4) l l d. Not uniform, (0.4] The same (0.4] (0.8)

o. High, (0.4] further away from (0.4]. OR l

Lower, (0.43 closer to (0.4] (0.8)

REFERENCE l WJE.51 l Thermal-Hydraulic Principles, Pp. 13- 30 thru 36

. St _IBEQBl_QE_NuGLE88_EQWEB_EL8HI_QEEB8IIQNt_ELulDft_8NQ PAGE 15 IHEBdQQ1N8 MIGS ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

l ANSWER 5.06 (2.80)

o. Although saturation temperature of the S/G exit steam decreases slightly as power increases (0.3] the feedwater temperature in- ,

creases (0.3] due to improved effectiveness of the feedwater heaters. [0.3) This results in a not smaller increase across the S/G with increasing power. (0.33 (1.2)

b. In order to achieve more flow you would need:

More flow paths (0.4] or larger pumps and pipes [0.6] which result in more engineering and material cost. (0.6]

OR; Higher pump speed, (0.8) changing flow in this manner would result in pumping power requirements increasing expo-nontially. (0.8)

Accept either answer for full credit. (1.6)

REFERENCE WJE 53 W0stinghouse Thermal Hydraulic Principles, Pp. 12-12,13

l

. Iz_'_IHEQBl_QE_NuGLE88 EQWEB_EL88I_QEEB8Il0Nt_ELU10St_8NQ PAGE 16 IBEBdQQ1N851Q1 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 5.07 (3.25)

o. Most of the coolant from the operating loops flows through the core, but some will flow backwards through the idle loop (due to the delta P across the core). [0.25] The net result is that the idle loop temperature becomes Tcold of the operating loops.

(0.51 (0.75)

b. Since power demand has not changed, the remaining loops must make up for power not being supplied by the idle loop. (0.51 With delta T across the idle steam generator essentially zero (may be slightly reversed), the delta T across the operating S/G's and the core will increase. [0.5] (1.0)
c. With no heat transfer across the idle S/G, delta T (Tave.- Tstm) must increase for the operating S/G's. [0.5] This means that operating S/0 temperature and pressure must decrease. (0.25] (0.75)
d. Total flow will stabilize somewhere above 75% (0.5] as the loss of 1 pump will decrease total head, increasing the flow rate of the operating pumps. [0.25] (0.75)

REFERENCE WJE 9 Wostinghouse Thermal-Hydraulic Principles, Pp. 12-15,16

6t__ELANI_111IEd1_QE110Nt_CQNIBQLt_8ND_INSIBudENI611QN PAGE 17 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 6.01 (2.40)

o. Defeat the 103% overpower rod stop. (0.6)
b. Defeats the failed P/R channel input to Rod Control. (0.6)
c. Removes the faulty input to the Detector Current Comparator (Current Deviation Alarm) (exist) (0.6)
d. Removes the faulty channel input to the Channel Current Comparator (Channel Deviation Alarm) (quadrant) (0.6)

REFERENCE WJE 74 ABN-703A, P. 3 & System Description III-1, Pp.20-24 ANSWER 6.02 (2.90)

o. 1. Feedwater Flow.
2. Steam Flow.
3. S/G Water Level. (Error signal) (0.3 es.) (0.9)
b. To provide a level setpoint. (0.5)
c. With the feed pumps in manual, there.is no effect to consider.

[0.5) With the pumps in auto the initial effect will be for pump speed to increase and FCV's to close down. [0.5) The system maintain S/G 1evel. [0.5) (Allow full credit for Rx. trip due to high S/G 1evel.) (1.5)

REFERENCE WJE 75 System Description IV-8, P.14 & IV-3, P.10 l

l s

L

. 65_'_EL8HI_SYSIEdS_DESIGNt_CQNIBQLt_8ND_INSIBudENI6I1QN PAGE 18 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 6.03 (3.20)

c. 1. Single. loop loss of flow will insert if 2/4 power ranges are above 48%. (0.4)
2. Two loop loss of flow will insert if 2/4 power ranges >10%

[0.3) OR, [0.21 1/2 impulse pressures > 10% [0.3] (0.8)

b. The undervoltage trip is to provide a trip signal on loss of power to the RCP's. (0.41 The reactor will trip and RCP's contin-ue to provide coastdown flow. (0.4) The underfrequency trip pro-l vides protection for a grid disturbance. [0.4] The RCP breakers  ;

and reactor are tripped (0.4] to prevent deceleration and loss of coastdown flow. [0.4] (2.0)

REFERENCE WJE 21 System Description III-g,, Pp.g,10,48 ANSWER 6.04 (3.00)

c. During conditions where RCS pressure is above RHR pump shut off head and the RWST is at low level. [0.6] The RHR pump discharge can be directed to the suction of the SI and Centrifugal Charg-ing pumps, or RHR pumps may be stopped. [0.6] 1/2 credit for:

Hot leg recirc. (1.2)

b. System inlet valves close on increasing pressure. (0.4]

High capacity pump suction relief valves. [0.4] (0.8)

c. Part of the heat exchanger outlet flow is recirced back to the RHR pump suction. [0.5) A recirc flow control valve opens on low flow (575 GPM) and closes on increased flow (1200GPM). [0.5] (1.0)

REFERENCE WJE 24 System Description II-6, Pp. 7,8,14 l

. st__2L6HI 1111Edi_QE119No_GQNIBQLt_6ND_INSIBudENI8IIQN PAGE ig ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

. ANSWER 6.05 (2.70)

c. The non-class buses can be supplied by opening the 22 KV Main Generator disconnect (0.3] and feeding back from the main trans-formers to the Aux. transformers. (0.3) The class buses can be supplied by the non-class buses after they are powered as above (0.3] or supplied by the diesels. [0.33 (1.2)
b. A slow transfer will occur ift
1. Normal breaker open.
2. Running bus voltage < 35% normal.
3. Bus feeders tripped.
4. Alternate bus voltage > 85% [0.375 es.

OR; A fast transfer will occur if:

1. Sufficient alternate power supply voltage.
2. Phases matched within 40 degrees.
3. Non 1E bus. [0.5 ea.)

Accept either answer for full credit. (1.5)

REFERENCE WJE 27 System Description VII-1, Pp. 17,40,41 ANSWER 6.06 -(1.40)

It will be necessary to open the DC and AC feeders to the inverter.

[0.5) Power can be supplied to the AC loads via the By-pass trans-former. [0.5) by operation of the panel transfer switch. [0.4] (1.4)

REFERENCE WJE 28 Dang. # 2323-El-0018

t

.Ei_yEL6HIIIIIEU8_DE110Nt_GQUIBQL&_6ND.INSIBWHENI6Il0N PAGE 20 ANSWERS'-- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.  :

i

! i l

l ANSWER 6.07 (1.60)

c. May be blocked when PZR pressure is below 1960 psig. (0.5) .

! b. Unblocked automatically when pressure goes above 1960 psig. (0.5) l c. Increasing pressure (above 1960 psig) automatically opens the ,

I accumulator diccharge valves. (0.6) l REFERENCE i WJE 83 l

Fccility question bank, Log-4 f

t I

l l t'

t l

l

.f l

t t

i . It_'_EBQGEQUBEl_=_NQBU86t_8tWQBd8Lt_EdEBGENGX_8NQ PAGE 21 88010LQGIG8L_GQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

t l

l i

l ANSWER 7.01 (3.00) '

l l c. Only after ICRR reference data has been taken and found not to l indicate any abnormalities. (0.6) ,

! b. 1. Determine a new ICRR reference value. (0.5) l 2. Perform a response check on all neutron indication. (0.51 (1.0)

o. 1. Fuel Bldg.

j 2. Containment t

3. Control room (0.3 es.) (0.9) 1 i
d. It has a neutron source. (0.5) l l REFERENCE i

WJE 55 ISU-001A, Pp. 12,35,39,40 ANSWER 7.02 (2.60)

c. Should not be transferred unless control of the equipment is needed (0.5] or evacuation was due to a fire (0.5] (1.0)
b. Leaving the system in auto does not require the operator's con- i stant attention, (0.4] and the heater / level interlock is over-ridden in local. (0.41 (0.8)
c. The affected equipment must have control shifted to the "HSP".

OR, Power supply breakers must be racked out.

(Either answer for full credit.) (0.8) l REFERENCE WJE56 l IP0-008A, Pp. 3,10,15 l

f g ~ >

ZI_'_EBQQEQVBES_:_NQ8d8Lt_8BNQBd8Lt_EDEBQENQ1.6NQ PAGE 22 l 88Q10LQQIc8L_cQNIBQL l

ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 7.03 (3.00)

o. CCP, S1 Pump, RHR Pump, CS Pump, Control Rm. A/C units, Safety Chill Water System. [0.15 es.) (0.9)
b. Shift to the standby loop and equipment supplied by it. [0.3) If surge tank level increase stops, leak was in the affected safe-guards or the non-safeguards loops. [0.3) Shift the non-safe loop to the stand by loop. [0.3) If level increases, the leak is in the non-safeguards loop. [0.3] (1.2)
c. Check CCW outlet temp, activity, or boron. [0.3 en.] (0.9)

REFERENCE WJE 57 ABN 502A,Pp.5,7 ANSWER 7.04 (2.80)

c. Manipulate turbine load to match Teve and Tref.

(Accept dilution for 3/4 credit as dilution is not feasible at EOL.) (0.75)

b. Increase turbine load as Tave increases to match Tave/ Tref (0.4]

or borate (0.35) (0.75)

c. Determine position with in-core detector measurements. (0.5)
d. Reduce power (to 50%) [0.6] to ensure power distribution peaking factor limits are not exceeded. [0.2]

(Allow full credit for any conservative action) (0.8)

REFERENCE WJE 34 ABN 712A i

l

- SI_EBQCEQUBE1_=_NQBM8Lt_8tNQBM8Lt_EMEBEENGl_6NQ' PAGE 23 88DIQLQ9108L_GQNIBQL-JANSWERS'- cCOMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

-ANSWER . '7 . 0 5 ~C2.00)

-c. Shift Supervisor and RO to hot shutdown panel. [0.8) Relief RO to the switch-transfer panel. . [0.43 (1.2)

"b.: Gaitronics (0.43 and the Safe Shutdown sound powered phone system. [0.4] (0.8)

I- REFERENCE WJE135 ABN~905A

~ ANSWER' 7.06 (1.50)

o. Steady state [0.35] for a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. [0.35] (0.7)

.b.-Add the total amount of make up [0.43 and the VCT volume change.

~Co.4] (0.8)-

. REFERENCE WJE 40 OPT.303 ANSWER 7.07 (2.40) e.: The procedure requires a slow cooldown rate (50 degrees /hr.)[0.4]

-and maintaining a high (60 degree 3 subcooling margin. [0.4] (0.8)

,b.lMust:run all available CRDM cooling fans. (0.4) c._Before starting RCP's, pressurizer temperature should be adj usted

-so~that RCS temperature will.be subcooled (when bubble shifts to

pressurizer), [0.33 and level should'be high. [0.3] After start-Ling, adj ust ~1evel to normal [0.33 and pressurizer temperature to provide normal = required subcooling of the RCS.~CO.3] (1.2)

REFERENCE.

WJE 90~

EOS-0.2,.Pp.4,5 & EOS-0.4,- Pp.3,4 k

- B't__6051N1118611YE_EBQQEDMBES&_GQNDIIIQNat_8NQ_LIMII811QNg PAGE 24 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 8.01 (2.60)

c. l. Two SRO's on site,-[0.3] and one RO in each control room.

[0.3]

2. One SRO in control room, and another on site, [0.3] .two RO's in control room,and another on site. [0.33
3. Same as #2 above. [0.63 (1.8)
b. Responsible to assist the Shif t Supervisor in' evaluating oper-ating activities [0.43 reports to the Operations Supervisor [0.4][0.8)

REFERENCE WJE'41 ODA 103, Pp. 8,10 ANSWER 8.02 (2.90)

c. Yes, [0.4) if the Shift Supervisor feels it is a detriment to proper plant operation. [0.4] (0.8)
b. An annunciator card can affect 2 alarms [0.4] and a required

. alarm might be disabled. [0.4] (0.8)

c. Should have an out of service sticker attached. (0.5)
d. Off going Shift Supervisor .

OR; The Annunciator / Instrument out of service log.

-(Full credit for either answer.) (0.8)

REFERENCE WJE 42 ODA 401 t a

  • l't__8DMINISIB8IIVE_EBQQEQUBESt_QQNQ1IIQNat_8NQ_LIMII611QN1 PAGE 25 ANSWERS.-- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 8.03 (2.50)

o. 1. One time only, [0.3] for-when it is anticipated that the pro-dure will not be used again. [0.2]
2. Extended, [0.3) required for a limited period of time, but may be used several times for 30 days. [0.2)
3. Permanent, [0.3] is a change to a procedure that will become permanent and is effective for 90 days [0.21 (1.5)
b. OPT------Manual affected by temporary procedure TP-------Temporary Procedure 85-------Year issued A--------Unit 1 (B= unit 2) 2--------Sequential # affecting OPT manual in 1985 [0.2 ea.] (1.0)

REFERENCE WJE 44 STA-204, P.3 & STA 205, Pp. 2,4 ANSWER 8.04 (3.10) c.. Advise and assist the Shift Supervisor as directed or needed. (0.8)

b. Initially the Shift Supervisor will act as Emergency Coordin-ator until augmentation when the TSC is manned. [0.21 The TSC Mgr. becomes responsible [0.3) until the EOF is manned and the EOF Mgr. becomes responsible. [0.33 (1.0)
c. TSC-----Mgr. Plant Operations Eng. Superintendent Operations Superintendent Maintenance Superintendent [0.2 each] (0.8)

OSC----Mech. Maint. Engr.

Elec. Maint. Engr.

Mech. Maint. Sup. [0.167 es.] (0.5)

REFERENCE WJE 46 EPP-112, P.4 & Epp-204 P.4 i

~

.fi_i8 QUIN 11IB8IIVE_EBQQEQUBEft_QQNQ1110NSt_8NQ_LidII8IIQN1 PAGE 26 ANSWERS -- COMANCHE PEAK.1 -85/04/01-WHITTEMORE,~J. .

ANSWER 8.05 (2.80)

o. The calculation is performed using operable detectors (0.6] and

-QPTR is verified consistant with tilt factors using the in-core detectors-[0.6] (1.2) b Always normalized to the same high power value for consistency so that problems will be detected at lower power levels. (0.8)

c. l. 10 min.
2. 0 3.-6 min.
4. 0 [0.2ea.] (0.8)

REFERENCE

.WJE 48

.0PT-302, P.2 & OPT-403, P . 4, ANSWER 8.06 (1.80)

e. 1. Core safety limit.
2. RCS pressure limit. [0.4 ea.] (0.8)
b. Limiting Safety System setpoints will cause automatic shutdown to preclude operating outside of safe envelope, [0.5] and the RCS over pressure protection system will prevent exceeding RCS safe pressure limit. [0.5 (1.0)

REFERENCE WJE 49

_T.S. 2.1

'O 'IA__8Dd1N11IBeIIVE_EBQGEDUBEli_CQNDII1QNit_8NQ_ Lid 1I8I1QNE. PAGE 27 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 8.07 (1.50)

e. Non-compliance exists when the LCO's (0.25] and any associated Action Statements [0.25] are not met within the specified time interval. [0.25] . (0.75]

b..Yes, [0.5]'when it is n'ecssary to pass through or to a mode to comply with an action statement. [0.25] (0.75]

. REFERENCE WJE 50

~T.S. 3.01 & 3.04 m

l l

k_-

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