ML20129D627

Exam Rept 50-445/OL-85-02 on 850401-03.Exam Results:Two Senior Reactor Operators & Four Reactor Operators Passed Written & Oral Exams & One Reactor Operator Failed

ML20129D627
Person / Time
Site:	Comanche Peak
Issue date:	07/11/1985
From:	Cooley R, Whittemore J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20129D608	List: ML20129D603 ML20129D627
References
50-445-OL-85-02, 50-445-OL-85-2, NUDOCS 8507160601
Download: ML20129D627 (76)

Text

t J Examination Report No. 50-445/0L-85-02 Docket No. 50-445 Construction' Permit No. CPPR-126 Licensee: Texas Utilities Electric Company 400 North Oliver Street Lock Box 81 Dallas, Texas 75201 Examinations administered to Comanche Peak Station (CPSES)

Chief Examiner: U J/ E. Whittemore, Examiner 7!!O!kr Date Approved by: - -

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R. A. Cooley, Se(tion Chief Gate '

Summary Examinations Conducted on April 1-3, 1985.

Written and/or oral examinations were administered to two Senior Reactor Operators, and five Reactor Operators. One Reactor Operator failed the examination and all others passed.

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8507160601 850712 PDR ADOCK 05000445 0 PDR

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CPSES EXAMINATION REPORT DETAILS

1. Examination Results Written examinations were administered to five Reactor Operator candidates and oral examinations were administered to two of the five candidates taking the written examinations. Four candidates passed the written and both candidates passed the oral examinations. One candidate failed the writte.: examination.

Written examinations were administered to two Senior Reactor Operator candidates. One of the two Senior Reactor Operators was administered an oral examination. All Senior Operator examinations administered were passed by the candidates.

2. Examiners J. E. Whitten. ore (Chief Examiner)

R. A. Cooley D. N. Graves S. C. McCrory

3. This Examination Report is composed of the sections listed below:

A. Examination Review and Comment Resolutions This section reflects comments made by the facility during the examinations 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. The modifications have been included in the master examination keys which are included elsewhere in this report. The following personnel were present for the exam review:

NRC Utility i

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.

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,. -s Coments 1.10 Part c. asks how increasing circ-water flow can increase or decrease overall plant efficiency while the answer key regiiires the candidate to answer for both conditions. The wording of the question may induce the candidate to answer only half the question.

Resolutions: Accepted the correct reason for increasing or decreasing plant efficiency and allowed full credit for either answer.

3.03 Part c. asks for inputs used to calculate Rod Insertions Limits.

The answer key includes Tavg. At CPSES, the Tavg. input is set to zero which may cause examiners to ignore this input.

Resolution: Agree. Tavg. is not required for full credit answer.

3.05 Part b. asks for plant response to pressurizer level control l

channel failure low, with no operator action. The key indicates that charging pump suction will shift to RWST on decreasing VCT level. At CPSES, make up rate is sufficient to maintain VCT level and shiftover will not occur.

Resolution: Agree. Key modified.

4.01/7.04 Part a. asks for requirements to increase allowable dose to 3 Rem /

-Qtr. The question did not stipulate 10 CFR 20 or administrative requirements. The key list managerial approval as a requirement.

While proper managerial approval is a CPSES requirement, it is not a 10 CFR 20 requirement and may not be included as a full answer.

Resolution: Disagree. Facility personnel are expected to conform with approved facility procedures.

4.02 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 procedure differ significantly concerning new fuel versus spent fuel. Since CPSES has no spent or reprocessed fuel'on site, the examine may assume new fuel and answer accordingly. There are no "Immediate Actions" in the sense of memorized operating procedures imediate actions.

Resolutions: 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 by 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.

, .o 6.02 -The question asks to list what inputs are supplied to Steam Generator Water Fuel Control. At CPSES, a constant level program is used; therefore, the input from turbine impulse pressure has been removed.

Resolution: Agree. Key modified.

7.03/9.10. CPSES does not require memorization of procedures 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 component. Any viable method of locating the leak was accepted as a correct answer for full credit. Questions 7.10 sought only to identify equipment operated to specifically preclude voiding and did not solicit detailed procedural knowledge.

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 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 examinations 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.

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Candidates exhibited a lack of familiarity with portable radiation

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2.

survey instruments.

3. Senior Reactor Operator candidates exhibited poor conceptual knowledge of basic' plant transients and plant response to abnormalities.

4. Senior Reactor Operator candidates 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. ,

The ' utility was informed that preliminary examination results would be

.available in approximately 30 days.

The meeting concluded with the examiners thanking the utility for their

. efforts towards the examination effort.

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'CPSES' EXAMINATION REPORT No. 50-455/0L-85-02 C. CPSES EXAMINATION AND KEY Date dainistered: 4/1/85 Exam Type: Reactor Operator and Senior Operator

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10 . S. NUCLEAR REGULATORY COMMISSION

. SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _QQd8NQBE_EE8K_1_________

REACTOR TYPE: _EWB-WEQd_________________

'DATE ADMINISTERED:_Q5ZQalQ1________________

EXAMINER: _WBlIIEdQBEz_Jz__________

APPLICANT: _________________________

IW118UGI1QN1_IQ_8EELIQaNIl Uno 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 locst 80%. Examination papers will be picked up six (6) hours after

- tho examination starts.

% OF

CATEGORY ~% OF- APPLICANT'S~ CATEGORY

__V8LUE_._IQI8L ___1QQBE___ _V8LUE__ ______________G8IEQQBI_____________

.25z00__._25tDQ ___________ ________.5. THEORY OF NUCLEAR POWER PLANT' OPERATION, FLUIDS, AND THERMODYNAMICS

-_25t0D__ _25zQQ ___________, ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

_25t001_ 25tDQ ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL I ._25t09-_ _25tDQ ___________ ________ 8. ADMINISTRATIVE PROCEDURES,

[

CONDITIONS, AND. LIMITATIONS l

L L.109tDQ__190A00 ___________ ________ TOTALS-l l -FINAL GRADE _________________%

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

~~~~~~~~~~~~~~

APPL 50 UTI5~55GU TURE l--

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54,_IHEQBl_QE_NUQLE88_EQWEB_EL88I_QEE86IIQNt_ELu1Dat_aNQ PAGE 2

.IBEBdQQ1NedIQS QUESTION 5.01 (2.40)

e. How will differential boron worth vary with:

1. Increasing RCS temperature ? (0.4)

2. Increasing Concentration ? (0.4)

3. Core age ? (0.4)

b. How will power coefficient vary with:

1. Reactor power at'Beginning of life ? (0.4)

2. Core age ? (0.4)

c. How does the total power defect change with fue1 burnup ? C0.4)

QUESTION 5.02 (1.80)

c. Describe the most effective method for dampening Xenon oscilla-tions. (1.2)

b. At a constant power, what is the approximate period of time for a complete oscillation to occur-? (0.6)

QUESTION 5.03 (2.60)

A clean core is started up and taken to 50 % power, where it re-091ns for'30 days;

s. 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)

-NOTEl Indicate approximate time and duration of reactivity changes.

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

'11,_IHEQBY_QE_ NUCLE 88_EQWEB_EL8HI_QEEB8IIQNt_ELVIDSt_8NQ PAGE 3 IBEBdQQ1Ned1G1 QUESTION 5.04 (1.20)

Ccmplete the f ollowing table by supplying the missing words or phrases. Indicate direction, magnitude, and rate where_ applicable.

Rx. Period Rx. Power Response Sta.rt Up Rate

e. Small positive Rapid increase ( )

'b. ( ) Constant ( )

c. Large negative ( ) Small negative (1.2)

QUESTION 5.05 (2.50) l o. 'For en operator taking data for a 1/M plot, how will the Shut-down margin (SDM) 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 ? .(0.5)

2. Count rate at criticality ? (0.5)

QUESTION 5.06 (2.75)

s. 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)

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

Et,_IHEQBl_QE_NUQLE68_EQWEB_EL6NI_QEE86110Nt_ELVIDS t_6NQ PAGE 4 IHEBdQQ1Nad191 QUESTION 5.07 (1.90)

o. Why is it necessary to install neutron sources in the Comanche Peak cores ? (1.0)

b. Why is it desirable to incorporate overlap into the rod program-ming scheme ? (0.9)

QUESTION 5.08 (2.80)

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

a. The' ratio of peak to average value of power distribution is known as (peaking factcr, 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 no'rmal 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)

o. With a (higher, lower) value of Enthalpy Rise Hot Channel fact-or, the coolant is (closer to, further away from) DN8 conditions.(0.8)

QUESTION 5.09 (2.80)

o. Explain what happens to the enthalpy change (h= BTU /LBM) on the secondary side of the,wteam 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 *****)

52,_IBEQBl_QE_NuQLE88_EQWEB_EL8HI_QEEB8IIQNt_ELUIDSt_8NQ PAGE 5 IHEBdQQ1Ned101 QUESTION 5.10 (1.00)

A motor operated centrifugal pump is operating at rated flow when

'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-crease, NPSH increases.

c. Flow decreases, discharge pressure increases, motor amps in-crease, NPSH decreases.

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

QUESTION 5.11 (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-stor 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)

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)

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

hi,_EL8HI_SISIEMS_QESIGNi_GQNIBQLt_8NQ_INSIBUMENI8I1QN PAGE 6 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 foiled channel be defeated. Explain why the following actions cust 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)

c. 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 (2.70)

e. In the steam dump control system, what parameters or signals are sensed to provide arming signals for turbine trip and loss of load ? Provide logic where applicable. (1.2)

b. Describe how and when the steam dump valves will receive a trip

-open signal. (1.5)

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

Jt;_EL6NI_SYSIEd1_QESIGNt_QQNIBQLt_8NQ_IN11BudENIeIIQN PAGE 7 QUESTION 6.04 (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)

QUESTION 6.05 (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 saf e 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 6.06 (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 ? C0.8)

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

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

61. _ E L 8HI_ S 11IE d S _ Q E 110 N t _ G Q NI B Q L t _8 N Q _IN11B u d E NI8 I1Q N PAGE 8 QUESTION 6.07 (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 transf er ? (1.5)

QUESTION 6.08 (1.40)

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

QUESTION 6.09 (1.90)

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

c. What prevents lowering the Condensete 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 ? (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 ? (0.5)

QUESTION 6.10 (1.60)

c. What plant conditions are required before the Pressurizer Pres-sure Saf ety. Inj ection 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._EBQGEQUBE1_=_NQBd8Lt_8tNQBd8Lt_EMEBGENC1_8NQ PAGE 9 B8010LQGIG8L_GQNIBQL l

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)

e. 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 injecYion 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 *****)

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F 21._EBQGEQUBES_=_NQBd8Lt_6BUQBd6Lt_EMEBGEUQ1_60Q PAGE 10 88Q10LQQ198L_CQUIBQL QUESTION 7.04 (2.40)

o. Athough not a common occurrence, federal regulations will allow a radiation worker to receive a quarterly whole body exposure of 3 Rem. What conditions must be satisfied for an individual to be allowed this higher than normal exposure ? (1,2)

b. How are individuals at Comanche Peak normally prevented from in-advertantly removing temporary radiation shielding ? (0.4)

c. What is the immediate action required of an individual in a rad-istion area finding that his pocket dosimeter is off scale ? (0.8)

QUESTION 7.05 (2.80)

c. 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 7.06 (2.00)

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

c. 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)

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

.ZA _EBQQEQUBEl_=_NQBd8Lt_6ENQBd6Lt_EMEBGENQ1_8NQ PAGE 11 88Q19LQQ1Q8L_QQNIBQL QUESTION 7.07 (2.80)

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

b. State 4 actions that must be performed to isolate a steam gener-ator=with a tube rupture. (1.6)

QUESTION 7.08 (2.50)

During blackout conditions you are able to manually start an Emer-goncy Diesel Generator:

o. How will you manually load the safeguards bus if a Safety In-jection signal exists ? Why ? (1.5) b.-What is the first load you would place on the bus ? Why ? (1.0)

QUESTION 7.09 (1.50)

Fcr a Reactor coolant system water inventory balance (leak rate) test:

c. What are the time and plant conditions specified for a success-ful test ? (0.7)

b. Describe how the CVCS volume change is determined for the test ? (0.8)

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

, Zis_EBQGEQUBES_:_NQBdelt_8BNQBd8Lt_EdEBQENGl_6NQ PAGE 12 86DIQLQQ1G8L_GQNIBQL QUESTION 7.10 (2.40)

During natural circulation cooldown:

a. 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 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-zer temperature and level before and after attaining forced coolant flow ? (1.2) l l

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

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, Aza_8DdIN11188IIVE_EBQGEQUBEft_CQNDIIIQNit_8NQ_LIMII8IIQN1 PAGE 13

-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 l o c at i~o n .

b..What is the general nature of the Shif t -advisors r es p ons ib il-ities and to whom does he report ? (0.8)

QUESTION 8.02 (2.90)

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

b. What precaution must be exercised when disabling an annunciator for maintenance ? (0.8)

c. As the oncoming Shift Supervisor, how could you recognize an an-nunciator or instrument that was out of service ? (0.5)

d. Where could you obtain information on the disabled. indication ? (0.8)

QUESTION 8.03 (2.90)

c. Who are the 3 individuals that must review and approve a Radia-tion Work Permit (RWP) for anticipated exposure in excess of 1 Man-Rem ? (0.9) .

b. For how long may RWP's and General Access Permits (GAP's) be active ? (1.0)

c. Under what specific conditions may an individual enter a Radia-tion Controlled Area without a GAP /RWP ? (1.0)

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

, Aia_8051811IB6IIVE_EBQCEQuBEft_GQNDIIIQNit_8NQ_LIMII6IIQN1 PAGE 14

-QUESTION 8.04 (2.50)

o. 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)

QUESTION 8.05 (2.50)

O. While touring the facility you suspect that a visible electri-

, cal jumper may be modifying or bypassing a saftey system. Ex-plain why this j umper SHOULD or SHOULD NOT be tagged. (1.0) l b. Who is responsible for removing a temporary bypass from a safety system, who verifies removal, and where is removal documented ? (1.5) i

QUESTION 8.06 (3.10)

o. Upon activation of the emergency plan, what are the 2 basic dut-les to be. performed by the Shift Advisor 7 (0.8)

b. Describe how the responsibility for Emergency Coordinator would shift after declaring an Unusual Event that gradually escalates i to a Site Emergency. (1.0)

I c. Name all individuals by (title) who can assume responsibility as:

I

1. Technical Support Center Manager ?

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2. Operations Support Center Manager ? (1.3) i f

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

lis_& QUIN 111BeIIVE_EBQGEQUBEli_GQNQ1Il0 Nit _8NQ_LidlI8IIQN1 PAGE 15 QUESTION 8.07 (2.40)

o. List the 3 different evacuation' alarm sounds and what they are used for. (0.9)

b. What 3 items of information should be included in a Site Evacu-ation announcement ? (0.9)

"'c. After a site evacuation, what 2 individuals can authorize entry for essential personnel ? (0.6)

QUESTION 8.08 (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 min. -74

4. 10% 1 hour- +9% (0.8)

QUESTION 8.09 (1.80)

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

c. What are the specific safety limits of concern ? (0.8)

b. Why is the above scenario very unlikely to ever occur ? (1.0)

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

, Ata_8DdlNISIB8IIVE_EBQGEQUBEft_GQNQIIIQNEt_8NQ_LidlI8IlQNS PAGE 16 l

QUESTION 8.10 (1.50)

o. What comprises Non-Compliance with a Technical Specification ? (0.75)  !

b.'Is it ever allowable to enter an operational mode without meet- I ing'the Limiting Conditions for Operation for the mode being entered ? Explain. (0.75) l l

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

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

Sta_IBEQBl_QE_ NUCLE 88_EQWEB_EL8NI_QEEB8IIQNt_ELVIQSt_8NQ PAGE 17 IHEBdQQ1N8dICS ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 5.01 (2.40)

a. 1. Decreases

2. Decreases

3. Increases (0.4 ea.) (1.2)

b. 1. Becomes more positive

2. Becomes more negative (0.4 ea.) (0.8)

c. Increases (0.4)

REFERENCE WJE 52 W:stinghouse Thermal-Hydraulic Principles, Pp. 12- 36,37,50, ANSWER 5.02 (1.80)

C. Hold delta I at the target value when it is on the upswing by inserting control rods (0.6) and compensate for insertion by boron dilution. [0.6) (1.2)

b. 24-28 hrs. accept 22-30 hrs. (0.6)

REFERENCE WJE 54 IPO-003A, P.18 ANSWER 5.03 (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 l

. Sta_IBEuB1_QE_NUGLE88_EQWEB_EL8NI_QEEB8IIQNt_ELulQHt_8UQ PAGE '18 IBEBUQQ1N851G1 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

.i ANSWER 5.04 (1.20)

c. Large positive (0.3)

b. Infinite, zero (0.6)

c. Slow decrease , (0.3)

REFERENCE WJE 59 W0stinghouse Fundamentals of Nuclear Physics, P. 7-17 ANSWER 5.05 (2.50) c.-The closer to criticality, Class SOM) the longer time required to reach a stable count rate. (0.75)

b. A higher inttial 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 Wcstinghouse Fundamentals of Nuclear Physics, Pp. 8-55,58,59 ANSWER 5.06 (2.75)

o. The magnitude of FTC decreases as fuel temperature increases [0.53 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)

. It2_IHEQBl_QE_NUQLE88_EQWEB_EL8HI_QEEB8IIQNt_ELUIDSt_8NQ PAGE 19 IHEBdQQ1885101 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

REFERENCE WJE 5 Westinghouse Fundamentals of Nuclear Physics, P.6-41 ANSWER 5.07 (1.90)

O. Sources are necessary so the operator is able to monitor sub-critical multiplication, [0.5) and to ensure that instruments are reliable. [0.5] (1.0)

b. Overlap improves differential rod worth (more linear), (0.5] and minimizes severe axial flux peaking (during transients). (0.43 (0.9)

REFERENCE WJE 64 Fccility question bank, NSSM-1 and CP-21 ANSWER 5.08 (2.80)

o. Peaking Factor (0.4)

b. Increase. (0.4)

c. Does not assure. (0.4)

d. Not uniform, [0.4) The same (0.4] (0.8)

o. High, [0.4] further away from (0.4] OR Lower, [0.4] closer to (0.4] (0.8)

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

a

.. Sta_IBEQBl_QE_NUGLEaB_EQWEB_EL8NI_QEEB8IIQNt_ELUIQSt_68Q PAGE 20 18E80001885103 L

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

ANSWER 5.09 (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 net smaller increase across the S/G with increasing power. [0.3] (1.2)

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

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

OR;

2. Higher pump speed, (0.8) changing flow in this manner would result in pumping power requirements increasing expo-nentially. [0.8)

Accept either answer for full credit. (1.6)

REFERENCE.

WJE 53 Westinghouse Thermal Hydraulic Principles, Pp. 12-12,13 ANSWER 5.10 (1.00)

ANSWER----- d.

REFERENCE WJE 8 Westinghouse Thermal-Hydraulic Principles, Pp. 10-36 thru 10-47

. Si__IHEQBl_QE_NUGLE88_EQWEB_EL8HI_QEEB8Il0Nt_ELUIQ1t_8NQ PAGE 21 IHEBdQQ1HedIGH ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 5.11 (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 net result is that the idle loop temperature becomes Tcold of the operating loops.

[0.5]' (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 (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/G 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 9 W stinghouse Thermal-Hydraulic Principles, Pp. 12-15,16

e, n

,1 r b.

, , fri :_ELeNI_SIRIEd1_DESIQNA_QQNIBQLt_6NQ_INSIBMMENI6IIQN .g PAGE 22 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

f:

t ,\

ANSWER 6.01 (2.40)- ,

\

0. Defeat-the 103% 3overpower rod stop. ,

(0.6) y

b. Defeats the failed P/R channel input to Rod Control. g.6) e, Removes the faulty input to th'e Detec%r Current Comparator (Current Deviation Alarm) (axial) i ,

(0.6) t

'd. Removes the faulty channel input to the Channel Current ,'

Comparator (Channel Deviation Alarm) (quadrant) (0.6) s I

REFERENCE ., s . .

WJE,74 's' t

ABNi703A, P. 3 & System Deseription III-1, Pp.20-24 4

ANSWER 6.02 (2.90)

}.

c. 1.. Nee'dwater Flow. 3 i  !

2. Steam Flow. '

'u.

3. S/G Water Level. (Error signal) (0.3 es.) (0.9)

b. To provido 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 systom should maintain S/G 1evel. (0.53 (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 4-

,3 l \

\

I k,

', t s.

k , s c

. 6t__EL8HI_111IEd1_DESIGNt_GQNIBQLt_8NQ_INSIBudENI8IIQN PAGE 23 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 6.03 ~C2.70) c.-Loss of load: Turbine impulse pressure rate of decrease. (0.4)

Turbine trip: 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 pneumatic positioner. [0.53 (1.5)

REFERENCE WJE 18 System description III-7, Pp. 4,7,8 ANSWER 6.04 (3.20)

o. 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%

[0.33 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. [0.41 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-9,, Pp.9,10,48

. 65 _EL8NI_SISIEME_DESIGNt_QQNIBQLt_8NQ_INSIBudENI6110N PAGE 24 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 6.05 (3.20)

c. Nitrogen, [0.4] to prevent inleakage of air and accumalating a mixture of H2 & 02. [0.4] C0.8)

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

[0.5] The steam is cooled and condensed by mixing with water near ambient temperature. [0.51 (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 RCDT HX [0.4] takes an abnor-mally long time to ecol the tank. [0.3] (0.7)

REFERENCE WJE 22 System Description II-1, P.S.5 ANSWER 6.06 (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. [0.43 (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

, 6ta_EL8HI_1111Eul_DE11GNt_GQNIBQLt_8NQ_IN11BUBENI6I1QN PAGE 25 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

i ANSWER ~6.07 (2.70)_

c. The.non-class buses can be supplied by opening the 22 KV Main Generatorudisconnect (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 if:

1. Normal breaker open.

'2' Running bus voltage < 35% normal.

3. Bus feeders tripped.

4. . Alternate bus voltage > 85% [0.375 ea.]

OR; ?A fast' transfer will occur ~if:

'1. Sufficient alternate power supply voltage.

2. Phases matched within-40 degrees.

3. Non IE bus (0.5 es.]

Accept either answer for full credit. (1.5)

REFERENCE.

WJE-27 System Description VII-1,'Pp.'17,40,41 ANSWER .6.08 (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...[0.53'by' operation of the panel. transfer switch. [0.43 (1.4)

REFERENCE

'WJE 28

.~0wng.'# 2323-El-0018 49

1 s'

. 6t__EL6MI_111IEd1_QE11GNt_QQNIBQLt_8NQ_INSIBudENI611QN PAGE 26 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 6.09 (1.90)

c. 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 - Isolates consendete make-up and reject lines (0.4)

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

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

REFERENCE WJE 29 System Description VIII-8, Pp. 6-8 ANSWER 6.10 (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)

c. Increasing pressure (above 1960 psig) automatically opens the accumulator discharge valves. (0.6)

REFERENCE WJE 83 Facility question bank, Log-4 u

. Zi _EBQQEQWBE1_=_NQBd8Lt_8BNQBd8Lt_EMEBGENQ1_8NQ PAGE 27 B8DIQLQEIQ8L_QQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

-ANSWER 7.01 (3.00)

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

b. 1. Determine a new ICRR reference value. (0.5)

2. Perform a response check'on all neutron indication. (0.53 (1.0)

c. 1.-Fuel Bldg. .

2. Containment

3. Contr,ol room (0.3 es.] (0.9)

d. It has a neutron source. (0.5)

REFERENCE 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 (0.53 (1.0)

b. Leaving the system in auto does not require the operator's con-stant attention, (0.43 and the heater./ level interlock is over-ridden in local. (0.43 (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)

' REFERENCE WJE56 IPO-008A, Pp. 3,10,15

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

_. Zi__EBQGEQUBER_=_NQBd6Lt_8HNQBd8Lt_EMEBGENGl_6NQ PAGE 28-B6010LQQ1C8L_GQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 7.03 (3.00)

c. CCP, SI Pump, RHR Pump, CS Pump, Control Rm. A/C units, Safety Chill Water System. -

[0.15 ea.] (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 es.] (0.9)

REFERENCE WJE 57 ABN 502A,Pp.5,7 ANSWER 7.04 (2.40)

a. 1. Proper managerial approval.

2. Lifetime permissible exposure not exceeded. (5{N-18})

3. Exposure history documented. [0.4 each] (1.2)

b. All temporary shielding is identifiable by an attached shielding evaluation tag. (0.4) c., Inform co-workers, [0.4] exit area and report to Radiation Protection. [0.4] (0.8).

REFERENCE

'WJE 84 Radiation Worker Training, Pp. 23,29,34

, Zia_EBQQEQUBES_=_NQBd8Lt_8BNQBd8L&_EdEBGENQX_8NQ PAGE 29 88Q10LQQ1Q8L_QQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER '7.05 (2.80)

o. Manipulate turbine load to match Tave 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 7.06 (2.00)

c. Shift Supervisor and RO to hot shutdown panel. (0.8) Relief RO to the switch transfer panel. (0.4]. (1.2)

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

REFERENCE WJE 35 ABN 905A

. ZA_'_EBQQEQUBEl_=_NQBd8Lt_8ENQBM8Lt_EdEBGENQ1_8NQ PAGE 30

.B8Q19LQGIQ8L_GQNIBQL i ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J. 1 ANSWER 7.07 (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 ea.] (1.2)

b. 1. Isolate AFW

2. Close MSIV's

3. Verify S/G PORV's closed

4. Isolate steam to AFW pump

5. Isolate feedwater

6. Isolate B/D and sample Cany 4, 0.4 ea.] (1.6)

REFERENCE WJE 37 Fccility question bank, ERG 21,22, ANSWER 7.08 (2.50)

c. Reset 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 [0.5) to supply diesel cooling water. [0.5] (1.0)

REFERENCE WJE 39 ECA 0.0, P.5 ANSWER 7.09 (1.50)

-e. 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 [0.4] and the VCT volume change.

[0.41 (0.8) i t

i

P

. Z2 _EBQQEQUBE1_:_NQBdeLz_8BNQBdekt_EMEBQENQ1_8NQ PAGE 31

-88Q10LQQ108L_QQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

REFERENCE WJE 40 OPT 303

- ANSWER 7.10 (2.40)

e. The procedure requires a slow cooldown rate (50 degrees /hr.)(0.43 and maintaining a high (60 degree ) subcooling margin. (0.43 (0.8)

b. Must 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. (0.33 After start-ing, adj ust level to normal (0.33 and pressurizer temperature to provide normal required subcooling of the RCS. (0.33 (1.2)

REFERENCE WJE 90 EOS-0.2, Pp.4,5 & EOS-0.4, Pp.3,4

^

1

. Az_'_8DMINISIB8IIVE_EBQQEQUBESi_QQNQ1IIQNat_8ND_LidII6110NS PAGE 32 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J. I I

l ANSWER 8.01 (2.60)

o. 1. Two SRO's on site, [0.33 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. [0.3]

3. Same as #2 above. [0.6] (1.8)

b. Responsible to assist the Shift Supervisor in evaluating oper-ating activities [0.4] reports to the Operations Supervisor [0.4](0.8)

REFERENCE WJE 41 ODA 103, Pp. 8,10 ANSWER 8.02 (2.99)

c. Yes, [0.4) if the dnift Supervisor feels it is a detriment to proper plant operation. [0.43 (0.8)

b. An annunciator card can affect 2 alarms [0.4] and a required alarm might be disabled. [0.43 (0.8) c.:Should have an out of service sticker attached. (0.5) d.'Off going Shift Suaervisor.

OR; The Annunciator / Instrument outof service log.

(Full credit for either answer) (0.8)

REFERENCE WJE 42 ODA 401 i

1 l

1

_ _ _ _ _ __ _ ___ _.__. . ~ .

, 12._8QdlN11188IIVE_EBQQEQMBElt_GQNQlIlQN1t_6NQ_LIdlI611QN1 PAGE 33 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 8.03 (2.90)

c. l. Radiation Protection Supervisor -

2. ALARA Coordinator

3. Shift Supervisor (0.3 each] (0.9_

b. 1. GAP's are normally effective for a calendar year.[0.4]

2. RWP's are active for the duration of the specific task [0.3]

or a calendar month, whichever is least. [0.3] (1.0)

c. During emergencies [0.5] the Shirt Supervisor may authorize en-try into a RCA withott paper work if continuous radiation pro-tection coverage is provided. [0.5] (1.0)

REFERENCE WJE43 HPA 112, Pp.4,5 ANSWER 8.04 (2.50)

c. 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 [0.2] (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

..At _8QUINISIB6IIVE_EBQGEQUBEft_GQNDIIIQNat_8ND_ lid 1I6IIQNS PAGE 34 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

1

-ANSWER 8.05 (2.50)

c. All temporary bypasses on safety systems should be tagged (0.5) unless it is installed and removed by an approved station proce-dure. [0.5) (1.0)

b. Removal- a person responsible for the modification, or indivi-dual designated by the Shift Supervisor. (0.5)

Verification- Supervisor of person performing the work or de-signated member of operations. (0.5)

Documentation- Temporary Modification and Safety Function By-pass log. (0.5)

REFERENCE

-WJE 45 STA- 602, Pp. 3,4,6 ANSWER 8 .~ 0 6 (3.10)

e. 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. [0.2) The TSC

-Mgr. becomes responsible (0.3) until the EOF is manned and the EOF Mgr. becomes responsible. (0.3) (1.0)

.c._TSC-----Mgr. Plant Operations 1 Eng. Superintendent Operations Superintendent Maintenance Superintendent (0.2-each) (0.8)

OSC----' Mech. Maint. Engr.

Elec. Maint. Engr.

Mech. Maint. Sup. (0.167 ea.) (0.5)

REFERENCE.

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

. At2_6 QUIN 11186IIVE_PBQQEQQBEft_QQNQlllQN$t_6NQ_LidlI611QN1 PAGE 35 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER '8.07 ~(2.40)

o. 1. Siren - Radiological emergencies

-2. Steady - Fire emergencies

3. Pulse - Other emergencies [0.3'ea.) (0.9)

b. 1. Procedure

2. Route

3. Any hazards to be avoided [0.3) (0.9)

c. Emergency coordinator [0.3) and Security Supervisor [0.33 (0.6)

REFERENCE WJE 47 EPP-208, P.4 & EPP-210, P.7 ANSWER 8.08 (2.80)

a. 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 consistancy so that problems will be detected at lower power levels. (0.8).

c. 1. 10 min.

2. O.

3.' 6 min.

4. 0 [0.2ea.) (0.8)

REFERENCE WJE 48 OPT-302, P.2 & OPT-403, P.4

F' E.Lat__8DMIN11IB8IIVE_EBQQEQUBEft_QQNDIIIQN1t_8ND_LIMII6IIQN1 PAGE 36

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

ANSWER _ 8.09 (1.80)

c. 1. Core safety limit.

2. RCS pressure limit. [0.4 es.] (0.8)

b. Limitibg 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 ANSWER- 8.10 (1.50)

a. Non-compliance exists when the LCO's [0.25] and any associated Action Statements (0.25]'are not met within the specified time interval. [0.251- (0.75)

~

-b. Yes, [0.5] when it is necssary to pass through or to a mode to-

. comply with an action statement. [0.25] (0.75)

0EFERENCE WJE 50 T.S.-3.01 & 3.04 I

i

o

-~

h U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _QQd8NQHE_EE8K_1_________

L REACTOR TYPE: _EWB-WEQa________________

DATE ADMINISTERED:_Q54QalD1________________

EXAMINER: _WHIIIEdQBEt_Ji__________

APPLICANT: _________________________

-1NSIBUCIIQN5_IQ_8EELIQ8HIl

._ Uso separate paper for -the answers. Write answers on one side only.

Staple question sheet'on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at logst 80%. Examination papers will be picked up six (6) hours after tho examination starts.

% OF OATEGORY  % OF' APPLICANT'S CATEGORY

__Y8LUE_ _IQI8L ___500BE___ _Y8LUE__ ______________Q8IEQQBl_____________

_25100__ _25tDQ' ___________ ________ 1. PRINCIPLES OF NUCLEAR POWER -

PLANT OPERATION, THERMODYNAMICS,

- HEAT TRANSFER AND FLUID FLOW

._ 2510D__ _25&QQ ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS

._ 25100__ _25tgQ ___________ ________ 3. INSTRUMENTS AND CONTROLS

_ 25100__ _25100' ___________ ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

190x0R__ 100100 ___________ ________ TOTALS

- FINAL GRADE _________________%

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

APPLICANT'S SIGNATURE i

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'li__EBING1 ELE 1_QE_NdCLE88_EQWEB_EL8NI_QEEB8I1QNm PAGE 2 IMEBdQQ1Ned1GHt_HE8I_IB8NSEEB_8NQ_ELMIQ_ELQW QUESTION 11.01 (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.-C -) Constant (- )

c. Large' negative ( ) Small negative (1.2) -

QUESTION 1.02 (3.00)

e. 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)

b. Explain how and why the above mentioned terms will affect re-

-actor' response throughout cycle life. . (1.5)

QUESTION 1.03 (2.00)

o. For-a reactivity change in a subcritical reactor, show how the Subcritical Multiplication Factor-(M), Keff, and initial and final. count rates are related. (1.0)

b. A reactor has a source count rate of 100 neutrons /second and a

-Keff of10.6. What.is the total or final stable count rate ? (1.0)

.Show how the answer is obtained.

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

. li__EBINCIELER_QE_NUGLE88_EQWEB_EL6NI_QEEBaIIQNt PAGE 3 IHEBdQQ1N6MIGit_BE6I_IB8N1EEB_eNQ_ELu1D_ELQW-QUESTION 1.04 '(2.50)

.a. .

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 rate'can be obtained after withdrawing rods ? (0.75)

~

b'. How will the initial count rate affect the count rate at crit-icality ? C0.75)

c. If the speed'of the control rods were to somehow increase. What would be the effect beHon:

- 1. Rod height at criticality ? (0. 5) .

2. Count rate at criticality ? (0.5) t QUESTION 1.05 (2.75)

a. How and why'will the magnitude of the Fuel Temperature Coeffi-cient (FTC) change as fuel temperature changes ? (1.25)

~

b. Explain lthe effect on the magnitude of the FTC due to :

1. Core power (0.75)

I i

'2. Core burnup (0.75) i

! . QUESTION 1.06 (1.80)

e. Explain how the Moderator Temperature Coefficient (MTC) can vary exially within the core. (0.8) b.-What effect will adding boric acid to the Reactor Coolant System

(- (1.0)

[

have on the MTC ? EXPLAIN.

I I

L f

. QUESTION 1.07 (1.75)

After 30 days at 50% power, plant power is raised to 100%. Explain the reactivity adj ustments the operator may have to make due to j

> " fission product poisons until stable conditions are reached. Your enswer should ~ discuss both major poisons. (1.75) l.

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

li__EBINQIELE1_QE_NUQLE68_EQWEB_EL6NI_QEEB6Il0Nt PAGE 4 IBEBdQQXNed10st_NgeI_Ig6NsEEB_6NQ_ ELM 10_ELQW QUESTION 1.08 (1.00)

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

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

s. Flow constant, discharge pressure constant, motor amps in-crease, NPSH increases.

b. Flow decreases, discharge pressure increases, motor amps in-crease, NPSH increases.

c. Flow decreases, discharge pressure increases, motor amps in-crease, NPSH decreases.

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

QUESTION 1.09 (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-ator 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)

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)

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

li__EBINGIELER_QE_NVQLEeB_EQWEB_EL8NI_QEE86IIQNt PAGE 5 IBEBMQQIN85101t_HE6I_IB6NSEEB_8NQ_ELMIQ_ELQW QUESTION 1.10 (2.25)

a. What is the maj or reason that nuclear steam plants do not have a constant overall plant efficiency at all power levels ? (0.5)

b. How does the_ extraction steam system specifically. affect plant efficiency at high versus low power levels ? Why ? (0.75)

c. Explain how increasing condenser circulating water-flow may act to improve OR' decrease overall plant efficiency. (1.0)

QUESTION 1.11 (1.75)

e. Positive displacement pumps can be classified as either recip-rocating or rotary. What are 2 of the 3 types of Rotary Posit-ive Displacement pumps ? (1.0)

b. The ideal performance curve for a positive displacement pump would be a straight line. Why is this not true in an actual sit- I untion ? (0.75)

-QUESTION 1.12~ (1.75)

a. 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) l l

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

l-

2t__EL8NI_QESIGN_INCLUDINQ_S8EEII_8NQ_EMEBGENQ1_SYSIEd1 PAGE 6 QUESTION 2.01 (3.20)

c. What is the normal atmosphere inside the Pressurizer Relief Tank ? Why ? C0.8)

b. When relieving pressurizer safeties into the tank at approx.

650 degrees and 2250 psi, why isn't the saf e 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 (3.90)

e. 1. What conditions'(interlocks) must be met to open the letdown isolation valves (LCV 459 a460) ? C0.6) 2..What will cause closure of the isolation valves ? (0.6)

3. What will cause closure of the ORIFICE isolation valves ? (0.9)

b. Besides seal return water, what other fluid streams might be affected should the Seal Water Heat Exchanger be placed out of service ? Disregard cooling water flow. (0.8)

c. Explain how recirc flow is provided for the centrifugal charg-ing pumps after the receipt of a Saf ety Inj ection signal. (1.0)

QUESTION' 2.03 (3.00)

e. 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 ? CO.8)

c. Describe how the RHR pumps are protected from vibrating or over-heating when running for safety inj ection and RCS pressure in-creases above pump shut off head due to isolating the leak. (1.0)

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

21__EL8HI_QESIGN_INGLUDINQ_S8EEIX_8NQ_EMEBGENQ1_SYSIEd1 PAGE 7 QUESTION 2.04 (2.70)

c. Briefly describe how operation of the Reactor Coolant Pumps will be affected should the following inadvertant signals occur:

1. Phase "A" containment isolation. (0.6)

2. Phase "B" containment isolation. -(0.6)

b. Briefly, in general terms, describe what action occurs for:

1. Control Room Emergency Recirculation signal. (0.5)

.2. Control Room Emergency Ventilation signal. (0.5)

3. Control Room Ventilation Isolation signal'. (0.5)

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

QUESTION 2.05 (3.40)

s. Explain the difference between the Normal and Emergency Diesel Generator Start /Stop Switches on the Main Control Board. (1.2) b._What specific Diessel Generator controls are located on the Re-mote Shutdown Panel ? (0.8) c.-What specific conditions cause the diesels to auto start ? C0.9)

d. What is(are) the power supply (ies) for diesel control power and field flashing power ? (0.5)

QUESTION 2.06 (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) l

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

2t__EL6NI_QE11GN_INCLUDINQ_18EEII_6NQ_EMEBQENC1_111IEd3 PAGE 8 QUESTION 2.07 ('l.40)

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

QUESTION 2.08 (1.90)

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

e. 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 ? (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 ? (0.5)

QUESTION 2.09 (2.80)

c. List 8 maj or pieces of equipment used to remove a new fuel as-sembly from the shipping container, temporarily place in storage, and subsequently load it into the reactor. (1.6)

b. How does the manipulator operator know that the crane is posit-ioned precisely for withdrawing or inserting a fuel assembly ? (1.2)

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

at__INSIBudENI1_8NQ_GQNIBQL1 PAGE 9 QUESTION 3.01 (2.20)

e. Briefly describe how the Nuclear instrument system is designed to +erminate 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)

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

QUESTION 3.02 (2.70)

e. Control rod speed in automatic is determined by a " Total Error" signal . What signals are used to determine the total error sig-nel ? (0.8)

b. State the automatic rod speed for the following total error signals:

1. 1 Degree

2. 2.5 Degrees

3. 4.5 Degrees (0.9)

c. State where and why the non-linear and variable gain units are ,

used in the automatic control of rod speed. (1.0)

QUESTION 3.03 (2.10)

c. What are the 2 separate rod position conditions that will gener-ate a rod deviation alarm ? (0.7)

b. What are the 2 auto rod withdrawal blocks that are NOT manual blocks ? (0.7) i

c. What are the plant parameters used to calculate the control rod insertion limits ? (0.7) i l (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

f 2i__INRIBWHENII_eNQ_CONIBQL1 PAGE 10 QUESTION 3.04~ C3.80)

a. List the control and protection outputs of the following sig-nels. State logic where appropiate. Disregard alarms and ind-ication.

1.-Individual loop Tave. (0.8)

2. Auctioneered low Tave. (0.3)

3. Auctioneered high Tave. (1.2)

b. List the outputs for the following. State logic where appropiate and disregard indication and alarms.

1. Loop N-16 power. (1.2) 2.'Auctioneered N-16 power. (0.3)

QUESTION -3.05 (3.10)

e. The pressurizer pressure controller is described as a.proport-ional plus. integral plus derivative controller. Explain' what the various. terms mean. (1.5) b'. Describe what would occur if Pressurizer Level Transmitter-LT-459 failed in the low direction while selected for control. Assume no operator' action before p*otective action' occurs. (1.6)

. QUESTION .3.06 (2.70) s.,In the steam dump control system, what parameters or signals are sensed to provide arming signals for turbine trip and loss of_ load ? Provide' logic where. applicable. ,(1.2) b.' Describe how end when the steam dump valves will receive a trip .

open signal. (1.5)

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

I l

St__INSIBudENI1_8NQ_GQNIBQL1 PAGE 11 l

l i

QUESTION- 3.07 (2.70)

a. 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)

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

QUESTION 3.08 (2.50)

a. What are the parameters that will vary or modify the Overtemper-ature N-16 trip setpoint. Explain how each parameter affects the setpoint. (1.5)

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

c. What protection is afforded by the Power Range Negative Rate trip ? (0.5)

QUESTION 3.09 (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 loon loss of flow. (1.2)

b. Explain how and why the undervoltage AND.underfrequency low flow reactor trips operate differently. (2.0) l l

(***** END OF CATEGORY 03 *****)

it__EBQQEQUBEl_=_NQBd8Lt_aQNQBd6Lt_EMEBGENQ1_6NQ PAGE 12 88Q10LQQIG6L_QQN18QL QUESTION 4.01 (2.40)

c. Athough not a common occurrence, federal regulations will allow a radiation worker to receive a quarterly whole body exposure of 3 Rem. What conditions must be satisfied for an individual to be allowed this higher than normal exposure ? (1.2)

b. How are individuals at Comanche Peak normally prevented from in-advertantly removing temporary radiation shielding ? (0.4)

c. What is the immediate action required of an individual in a rad-istion area finding that his pocket dosimeter is off scale ? (0.8)

QUESTION 4.02 (2.00)

c. While acting as manipulator operator you observe the new fuel as-sembly that was just 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 assembly is bottomed in the vessel ? C0.6)

QUESTION 4.03 (3.05)

e. 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 failure. 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)

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

4 t__EBQQEQMBEl_ _NQBd8Lt_6BNQBdekt_EMEBGENQ1_6NQ PAGE 13 88Q19LQQIQaL_GQNIBQL QUESTION 4.04 (2.80)

e. 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 ? C0.8)

QUESTION 4.05 (2.00)

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

e. 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 4.06 (3.25)

Answer the following questions about plant start up:

o. How and why do Shutdown Margin requirements change when going from mode 4 to mode 5? (0.75)

b. Why do precautions NOT allow admitting steam to the Main or Feed Pump turbines when the reactor is~ critical below 1% power ? (0.75)

c. Why must the highest reading source range read at least 2 counts before withdrawing rods for start up ? (0.75)

d. What action should be taken if the reactor achieves criticality with rods below the insertion limit ? (1.0)

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

k_

1 .

,' s s az__EBQQEQUBE1.:_NQBdakt_6HN9Bd6Lt_EMEBQENQ1_6NQ PAGE 14 88Q10LQQ198L_QQNIBQL a

n QUESTION 4.07 (2.80)

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

b. State 4 actions that must be performed to isolate a steam gener-ator with a tube rupture. (1.6)

QUESTION 4.08 (2.70)

e. Explain the term " Adverse Containment" that appears in the Emer-gency procedures and why the operator is given different limit-ations with adverse conditions. (1.5)

b. For depressurization after a tube rupture, how will the operator depressurize if:

1. Reactor Coolant Pumps (RCP's) running.

2. RCP's stopped, letdown in service.

3. RCP's stopped, letdown isolated. (1.2)

QUESTION 4.09 (2.50) -

During blackout conditions you are able to manually start an Emer-goney Diesel Generator:

o. How will you manually load the safeguards bus if a Safety In-jection signal exists ? Why ? (1.5)

b. What is the first load you would place on the bus ? Why ? (1.0) l QUESTION 4.10 (1.50)

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

e. What'are the time and plant conditions specified for a success-ful test ? (0.7)

b. Describe how the CVCS volume change is determined for the test ? (0.8)

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

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

lt__EBINQIELE1_QE_NUQLEaB_EQWEB_EL8HI_QEEB611QNt PAGE 15

-IBEBdQQINedIQSt_BE6I_IB6NSEEB_8ND_ELUIQ_ELQW n ANSWERS -- COMdNCHE PEAK 1 -85/04/01-WHITTEMORE, J.

.3 ANSWER 1.01 (1,20)

-c. Large positive (0.3)

b. Infinite, zero (0.6)

c. Slow decrease (0.3)

REFERENCE WJE 1 W0stinghouse Fundamentals of Nuclear Physics, P. 7-17 ANSWER 1.02 (3.00)

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

[0.53 Beta bar effective is the effective fraction (0.25] and is smaller as it is the product of beta bar and an importance fac-tor. [0.251 The importance factor is generally less than one as delayed' neutrons are less likely to cause fission. [0.53 (Will, accept an explanation of how the importance factor is affected by Fast Fission and Non-leakage factors) (1.5)

~

b. Beta bar and Beta Bar effective will decrease in value over cy-cle life (0.53 due to the changing concentrations of the differ-ent fissionable isotopes in the core. [0.51 Smaller values of the effective frection means that the reactor period will be smaller or the re ictor will respond quicker for a given react-ivity change, at the core ages. [0.5] (1.5)

-REFERENCE WJE 2 Wcstinghouse Fundamentals of Nuclear Physics, Pp.7-31,33,34,36,48 ANSWER 1.03 (2.00)

c. 1/M = Co/Ci = 1- Keff (1.0)

-b. Total-count rate = S/ 1-Keff = 100/1-0.6 = 250 neutrons /sec. (1.0)

It__EBINQIELEE_QE_NVQLE88_EQWEB_EL8NI_QEEB811QNt ' PAGE 16 IHEBdQQ1N8510Et_BE81_IB8NEEEB_8NQ_ELMIQ_ELQW ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

REFERENCE WJE 3 W0stinghouse Fundamentamentals of Nuclear Physics, Pp.8-18, 27 ANSWER 1.04 (2.50)

e. The closer to criticality, Cless 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)

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

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

REFERENCE WJE 4 Westinghouse Fundamentals of Nuclear Physics, Pp. 8-55,58,5g ANSWER 1.05 (2.75)

c. The magnitude of FTC decreases as fuel temperature increases (0.5) because the self shielding of the fuel decreases as the resonce l peaks decrease in height. (0.75) (1.25) l b. 1.= Fuel temperature increases as power increases ,(0.5) thus the magnitude of FTC decreases. (0.25] (0.75)

I 2. Fuel temperature decreases as core ages (0.5) so the FTC will l decrease. (0.25] (0.75)

REFERENCE WJE 5 W stinghouse Fundamentals of Nuclear P hys ics , P.6-41 l

~ .. .

it__EBINQ1 ELE 1_QE_NUGLE68_EQWEB_EL6SI_QEEB6IIQNt PAGE 17 IBEBdQQ1NedlGit_BE6I_IB6NEEEB_6NQ_E(ylQ_E(QW

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

ANSWER 1.06 (1.80)

2. The higher temperature at the core outlet and the non-linear change in density (0.43 means that the MTC will be higher at top of the core. (0.4] (0.8)

b. Decrease the magnitude (0.5] as at a higher concentration, more boron will be expanded from the core for a temperature change, adding positive reactivity. (0.53 (1.0)

REFERENCE WJE 6 W stinghouse Fundamentals of Nuclear Physics, P.6-42 AND Curve Book Fig.1.8

~ ANSWER 1.07 (1.75)

The operator should only have to compensate for Xenon which will initia11y' dip (0.51 and then attain it's 100% equilibrium concen-tration in 45-55 hours. (0.75) Samarium (may initially experience e slight dip in concentration) but should end up at the same equil-ibrium value. (0.5] (1.75)

REFERENCE WJE 7 CPSES Curve Book, Fig's 1.12, 1.13, 1.14 ANSWER 1.08 (1.00)

ANSWER----- d.

REFERENCE WJE 8 Wastinghouse Thermal-Hydraulic Principles, Pp. 10-36 thru 10-47

It__EBINGIELER_QE_NUGLE88_EQWEB_EL8NI_QEEBeIIQNi PAGE 18 IBEBMQQ1NedIGat_BE81_IB8HSEEB_6ND_ELVlQ_ELQW ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 1.09 (3.25)

e. 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.

[0.5] (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/G temperature and pressure must decrease. [0.25] (0.75)

d. Total flow will stabilize somewhere above 75% [0,53 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 Westinghouse Thermal-Hydraulic Principles, Pp. 12-15,16 ANSWER 1.10 (2.25)

e. The plant is designed to be most efficient at full power. (0.5)

b. At high power _ levels, extraction steam pressure (and flow rate) increase. [0.25] This causes more heat to be transferred across heaters, increasing efficiency. [0.51 (0.75) c.. Increased heat transferred may result in a lower condenser pres-sure, increasing' efficiency. OR* Incresaing heat transfer past the point of minimum condenser pressure will subcool the condensate and decrease efficiency.

Accept either answer for full credit. (1.0)

REFERENCE

'WJE 10 Wcstinghouse_ Thermal-Hydraulic Principles, Pp. 12-24,25,26

'It__EBINCIELEl_QE_NUGLE88_EQWEB_EL8HI_QEEB8I1QNm PAGE 19 IBEBdQQ1Ned1G1t_HE8I_IB8N1EEB_8NQ_ ELM 1Q_ELQW ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

' ANSWER 1.11 (1.75)

e. 1. Rotary Vane

-2. Gear Pump

3. Screw Pump Cany 2, _0.5 each) (1.0)

b. At the pump's design pressure limit back leakage past moving parts will occur ~and volume flow rate decreases. (0.75)

REFERENCE WJE 11 Wcatinghouse Thermal-Hydraulic Principles, Pp.10-49,50 ANSWER 1.12 (1.75)

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

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

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

REFERENCE WJE'12

'Wcstinghouse Thermal-Hydraulic Principles, Pp.13-11,12,13

2x__EL8HI_ DESIGN _INCLUQ1NQ_SaEEIY_8ND_EMEBGENC1_SYSIEd$ PAGE 20 ANSWERS --' COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 2.01 (3.20]

c. Nitrogen, [0.4] to prevent inleakage of air and accumulating a mixture of H2 & 02. [0.43 (0.8)

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

[0.5] The steam is cooled and condensed by mixing with water near anbient temperature. [0.53 (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 RCDT HX [0.4] takes an abnor-mally long time to cool the tank. [0.33 (0.7)

REFERENCE WJE 22 System Description II-1, P.S.5 ANSWER 2.02 (3.90) s . - 1. All orifice isolation. valves must be shut. [0.33 Pressurizer level > 17%. [0.33 (0.6)

2. Pressurizer level - 17%. [0.33 Loss of air or power. [0.3] (0.6)

3. Pressurizer level - 17%.

LCV 4598460 close.

Loss of air or power. [0.3 each] (0.9)

b. 1. Excess letdown. [0.4]

CCP miniflow recirc. [0.4] (0.8)

c. Normal recirc valves will close on an "S" signal [0.33 and emer-gency recire valves will open. [0.3] Downstream of emergency re-circ re 2 relief valves which will open to provide a recirc pcth to the RWST. [0.4] (1.0)

REFERENCE WJE'23 System Description II-2, Pp. 6,7,8,19

- , ., n.- , - . , . . . , - - . . . - -

c.

2t__EL8HI_QE11GN_INGLMQ1NG_18EEII_8ND_EMERGENQ1_111IEd1 PAGE 21 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

' ANSWER 2.03 (3.00) e.10uring conditions where RCS-pressure is above RHR pump shut off I 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-cing pumps, or RHR pumps may be stopped..[0.63 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 recire flow control valve opens on low flow-C575 GPM) and closes on increased flow (1200GPM). [0.53 (1.0)

REFERENCE WJE 24 l System Description II-6, Pp. 7,8,14 ANSWER 2.04 (2.70)

n. 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. [0.3) (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. [0.33 (0.6)

b. .1. The system goes on. closed loop recirculation. (0.5) i 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 11-7, Pp. 15,16,27,36

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

' 2z__EL8NI_ DESIGN _ INCLUDING _S8EEll_8ND_EMEBGENGl_SYSIEMS PAGE 22 l ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

l ANSWER 2.05 (3.40) c.-Normal-- This switch places the unit in parallel mode on start-ing [0.2] and the generator breaker must be open before stopping.

[0.23 All trips are in effect. [0.2] (0.6)

Emergency-- This switch will bypass all trips except differen-tial and ove'rspeed. [0.33 and will open the generator breaker prior to stopping the engine. [0.3] (0.6)

b. 1. D/G output breaker control.

2. Remote / local transfer switch. [0.4 each] (0.8)

c. 1. Undervoltage.

2. Blackout.

3. Safety inj ection. [0.3-each] (0.9)

d. 125 VDC. (0.5)

REFERENCE WJE 26 System Description VII-4, Pp.37,42 1

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

-2i__EL8HI_QE11GN_INGLUDINQ_18EEII_8NQ_EMEBQENC1_SYSIEd1 PAGE 23 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

' ANSWER 2.06 [2.70]

c. The non-class buses can be supplied by opening the 22 KV Main Generator disconnect (0.33 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. [0.3] [1.2)

, b. A slow transfer will occur if:

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 es.]

Accept either answer for full credit. (1.5]

REFERENCE WJE 27 System Description VII-1, Pp. 17,40,41 ANSWER 2.07 [1.40)

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

[0.53 Power can be supplied to the AC loads via the By-pass trans-former. [0.53 by operation of the panel transfer switch. [0.4] [1.4]

REFERENCE WJE 28 Dwng. # 2323-El-0018

22_;EL8NI_ DESIGN _INGL901NQ_18EEII_8ND_EMEBGENQ1_1111 gds PAGE 24 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 2.08 (1.90)

o. 0ther 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 - Isolates condensate make-up and rej ect lines. (0.4)

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

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

REFERENCE WJE 29

-System Description VIII-8, Pp. 6-8 ANSWER 2.09 (2.80)

c. 1. Fuel Bldg. overhead crane. 6. Transfer Car.

2. Inspection Machine. 7. Fuel Bldg. Upender.

3. New Fuel Elevator. 8. Containment Upender.

4. Fuel Bldg. Bridge Crane. 9. Manipulator Crane (0.2 ea.)

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-inste servo system, read directly by the operator. (1.0) A Video system allows the ope ator to view fuel assemblies position and movement. (0.2) (1.2)

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

1 4

, - 21__INSIBudENI1_8NQ_GQNIBQL1 PAGE 25 ANSWERS -- COMANCHE PEAK-1 -85/04/01-WHITTEMORE, J.

ANSWER 3.01 (2.20)

a. The source range provides a doubling signal set to actuate when flux doubles (within 9 minutes).[0.6] The signal will shift charging pump suction from the VCT to the RWST. [0.3) The feat-ure is manually blocked for approach to criticality, with a back up block provided by P-6. [0.33 (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 alarm. [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 III-1, Pp.8,11 ANSWER 3.02 (2.70)

e. 1. Temperature error signal.

2. Power mismatch signal. [0.4 ea.]

C:R; 1.'Auct. Tave.

~2. Tref.

3. Auct. Hi Power. [0.27 es.] Accept either answer. (0.8)

b. 1. May be 0 or 8 steps / min.

2. 8 steps / min.

3. 56 steps / min. [0.3 each] (0.9)

c. 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 speed. [0.31 The variable gain unit imposes a lower gain at higher power levels. (prevents overshoot) [0.33 (1.0)

REFERENCE WJE 14 System Description III-3, Pp.11,12

,c .'

St__IN11BudENI1 8NQ_GQNIBQL1 PAGE 26 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. 3 5) ~

c. 1. Tave. (0.35)

2. % N-16 power. (0.35)

NOTE: Tave set to "0", allow full credit if omitted.

REFERENCE WJE 15

' System Description III-3, P.13 & III-4,Pp. 9,17 ANSWER 3.04 (3.80)

c. 1. Low Teve for feedwater isolation. -- 2/4 (0.4)

Low Low Tave for steam dump block. -- 2/4 (0.4)

2. C-16, Stop turbine loading. (0.3)

3. RIL (0.3)

Steam dump control.. (0.3)

Rod control. (0.3)

Pressurizer level control. (0.3)

'(Reactivity computer nat required)

b. 1. OT N-16 trip--2/4 (0.3)

OT N-16 runback--2/4 (0.3)

OP N-16 trip--2/4 (0.3)

OP N-16 runback--2/4 (0.3)

2. RIL (0.3)

REFERENCE WJE 16 Syctem Description III-5, P.11

21__INSIBudENI1_8NQ_GQNIBQL1 PAGE 27 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 3.05 (3.10)

c. Proportional- Controller output is proportional to input. (0,5)

Integral- Output is modified by the amount of time a deviation exists between pressure and setpoint. (0.5)

Derivative- Output is-modified by the rate of change between pressure and setpoint. (0.5)

b. Charging flow will increase, and pressurizer heaters will turn off. [0.6) Letdown isolates. [0.3) ~ Auto make up will maintain VCT level. Reactor will trip due to high pressurizer level.[0.7) (1.6)

REFERENCE WJE 17 System Description III-6, P.4 &IV-13, p.12 ANSWER 3.06_ (2.70)

c. Loss of load: Turbine impulse pressure rate of decrease. (0.4)

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

b. Only in the Teve 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 pneumatic positioner. [0.53 (1.5)

REFERENCE WJE ~ 18 System description III-7, Pp. 4,7,8

2t__INSIBudENI1_8NQ_CQNIBQL1 PAGE 28 ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 3.07 (2.70)

o. 1. To maintain valve position in the linear range at low power.

2. Reduce pump power requirements.

3. Reduce f eed control valve erosion. [any 2, 0.4 each] (0.8)

b. 1. High S/G level.

2. Rx. trip and low Tave. .

3. Safety injection. [0.3 each) (0.9)

c. Auctioneered high power [0.3] 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 3.08 -(2.50)

c. T-cold [0.3] acts to lower trip setpoint when t-cold is above normal full power value. [0.2] (0.5)

RCS pressure (0.3] lowers setpoint when pressure is below rated pressure. [0.23 (0.5)

Delta-q [0.31 lowers setpoint if flux difference increases. [0.2]CO.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 i

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

2t__IN11BMMENI1_8NQ_GQNIBQL1 PAGE 29 ANSWEP.S -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 3.09 (3.20)

s. 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 lf 2/4 power ranges >10%

[0.33 OR; [0.2] 1/2 impulse pressures > 10% [0.3] (0.6)

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. [0.4] 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-9,, Pp.9,10,48

-I a_

iz__EBQGEQUBER_=_NQBM8(t_8RNQBM8Lt_EMERQENGl_8NQ' PAGE 30 B801960f1G8L_GQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 4.01 (2.40) c.: 1. Proper manager'isi approval.

2. Lifetime permissable exposure not exceeded.-(5(N-18))

-3.iExposure history-documented. (0.4 each) (1.2)

'b. All temporary shielding is identifiable by an attached shielding evaluation tag. (0.4) c.' Inform co-workers, (0.4) exit area and report to Radiation Protection.,-(0.4] (0.8)

, REFERENCE WJE-31 Rcdiation Worker Training, Pp. 23,29,34 ANSWER' 4.02 (2.00)

e. 1. ( Assume that the assembly struck may be spent f uel), notify Shift Supervisor (0.4] and immediatly evacuate. (0.43 (0.8)

2. If practical, place in the containment f uel 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.9

3t;_EBQGEQWBE1_=_NQBM86t_8tNQBM8Lt_EMEBGENGl_6NQ PAGE '31 86DIQLQ91G86_GQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER' 4.03 (3.05)

o. 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-eration 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 ANSWER 4.04 (2.80)-

o. Manipulate turbine load to match Tave 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/TrefCO.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

f

o st__EBQQEQUBEl_ _NQBd6Lt_6ENQBd6Lt_EMEBGENQ1_68Q PAGE 32 B6010LQQIQ6L_QQNIBQL

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

ANSWER 4.05 (2.00)

c. Shift Supervisor and RO to hot shutdown panel. [0.8) Relief RO to the switch transfer panel. [0.4] (1.2)

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

REFERENCE WJE 35 ABN 905A ANSWER 4.06 (3.25)

O. SDM increases from 1% in mode 5 to 1.6% in mode 4 [0.5] so there more negative reactivity available in case of a steam line break above 200 degrees. [0.25] (0.75)

b. Steaming these units may cause reactivity addition from cool-  !

down [0.5] and result in an unwanted power excursion. [0.25] (0.75)

c. There is a possibility of attaining criticality below the ind-icating range [0.5] and entering the source range with an uncon-trollable start up rate. [0.25] (0.75)

d. Emergency borate 100 PPM [0.5] and commence inserting all con-trol rods. [0.5] (1.0)

REFERENCE WJE 36 IPO-001A, P. 8 & IPO- 002A,Pp.5,6,11

-at__EBQQEDVBE1_=_SQBd8Lt_8HNQBd8Lt_EMEBQENC1_8NQ PAGE 33 B8DIQLQQ1G86_GQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER 4.07 (2.80)

o. 1. Narrow range level

2. Blowdown rad. monitor

3. S/G sample activity

4. Steam line red monitor

5. Feed flow > steam flow (any 4, 0.3 es.] (1.2)

b. 1. Isolate AFW

2. Close MSIV's

2. Verify PORV's closed

4. Isolate steam to AFW pump

5. Isolate feedwater

6. Isolate B/D and sample Cany 4, 0.4ea.] (1.6)

REFERENCE WJE 37 Fccility question bank, ERG 21,22,

(

ANSWER 4.08 -(2.70)

c. Containment pressure > 5 psig (0.3], > 10(ES) REM /Hr. [0.33, In-tegrated contsiment dose > 10(E-6) RAD [0.3]. Instrumentation used during emergencies will be affected by these adverse condi-tions (0.6] (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

of ;*

dt__EBQGEQQBE1_:_NQBM8Lt_8tNQBM8Lt_EMEBGENGl_8NQ PAGE 34

'B8Q10LQEIG8L_QQNIBQL ANSWERS -- COMANCHE PEAK 1 -85/04/01-WHITTEMORE, J.

ANSWER '4.09' (2.50)

o. Roset the SI signal OR; place control switches 'in " Pull To Lock"'[either reason 0.75].to prevent energizing unwanted loads and j eopardizing newly acquired power source. [0.75] (1.5)

b. A station service water pump (0.51 to supply diesel cooling water. [0.5] (1.0)

REFERENCE WJE 39 ECA 0.0, P.5 ANSWER 4.10 (1.50)

c. 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 [0.4] and the VCT volume change.

[0.4] (0.8)

REFERENCE WJE 40 OPT 303 o