ML20202F149

Exam Rept 50-295/OL-86-03 for Units 1 & 2 on 860310-13.Exam Results:Six Senior Operator Candidates Passed Written Exam & Three Senior Operator Cnadidates Passed Oral/Operating Exam

ML20202F149
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	04/08/1986
From:	Burdick T, Hemming W, Picker B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20202F087	List: ML20202F083 ML20202F149
References
50-295-OL-86-03, 50-295-OL-86-3, NUDOCS 8604140115
Download: ML20202F149 (42)

Text

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a U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-295/0L-86-03 Docket No. 50-295; 50-304 Licenses No. DPR-39; DPR-48 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Zion Nuclear Power Station Examination Conducted: March {0-4,1986 Examiners: . C. Hemming

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Approved By:

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.M.BuIdick, Chief ~~

Operating Licensing Section D'a te l Examination Summary Examination administered on March 10-14, 1986 (Report No. 50-295/0L-86-03)

Examinatior.s were administered to six senior operator candidates.

Results: Six senior operator candidates passed the written examination and three senior operator candidates passed the oral / operating examination.

I ts604140115 860408 PDR ADOCK 05000295 y PDR

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, REPORT DETAILS

1. Examiners W. C. Hemming, INEL B. A. Picker, INEL

2. Examination Review Meeting At the conclusion of the written examination, the questions and answers I were given to the facility training staff for review and comment. At the l exit meeting the facility supplied the examiners with their comments to the Senior Reactor Operator (SRO) written examination. On the following pages are the facility comments and the examiner's response to each.

3. Exit Meeting On January 30, 1986, an exit meeting was held. The following personnel were present at this meeting ,

l Mr. P11ml, Station Manager T. Rieck, Services Superintendent j E. Furst, Production Superintendent l B. Kurth, Assistant Superintendent Operations )

N. Yalos, Operations Engineer l W. Stone, QA Supervisor i M. Carnahan, Training Supervisor '

R. Landrum, Operations Training Group Leader W. Hemming, INEL B. Picker, INEL R. Higgins, RIII, NRC l D. Hills, RIII, NRC I J. Kirsh, Resident NRC '

The facility was informed of those individuals who clearly passed the oral and/or simulator examinations. In addition, the examiners made the l following observations:

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a. Areas of common weakness were found in the use of procedures, especially during procedure transitions to other procedures, and understanding of what the procedure will accomplish,

b. System knowledge was weak, demonstrated both in the simulator operational exam and the walk-through oral.

Attachment:

Facility Examination Comments and Examiner Resolution 2

ATTACHMENT 4

ZION STATION SRO EXAMINATION REVIEW COMMENTS EXAM DATE 3-30-86 Section 5 5.07.c Facility Comment It should also be noted that over core life Control Rod Worth increases due to decreased competition from fuel, burnable poisons and boron. This may be used as an explanation of why the accident is more severe at EOL.

Reference:

Westinghouse Large Pressurized Water Reactor Core Control, pages 6-25 and 6-26 NRC Resolution Accepted. Answer Key will be changed to allow Doppler only Power Coefficient decreasing and Rod Worth increasing.

Section 6

, 6.03.d Facility Comment

) The common noun names for HCV 182 are " Backpressure Regulator" or "RCP Labyrinth delta P Control Valve." Please consider this while grading.

Reference:

MCB HCV 182 Nameplate, Zion System Description Chapter 5, Page Sa-6 NRC Resolution Accepted. The above noun names are acceptable and answer key will be changed.

6.04.b Facility Comment This question seems to imply that the PORV has failed open. Taken l cs such this may prompt candidates to respond with a means of transient termination such as recommending that the associated PORV block valve be shut. Please modify the answer key to permit this as an alternate response. Also note that the setpoint stated here should be changed to 2335.

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Reference:

Zion System Description Chapter 3c, Page 3c-22.

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Attachment 2 1

NRC Resolution n

Accepted. As asked the question could solicit the above answer.

i Therefore answer key will be modified to also except shutting the i block valve.

6.05 Facility Comment Reference stated gives 5 (five) conditions as follows:

Answer Key Responses Reference Responses 4, 5 1) The bus main and reserve feed breakers are open.

1,2,3 2) The bus and diesel generator are

, not faulted (overcurrent lockout not in effect).

8 3) The Diesel Generator is running at rated voltage and frequency.

For DG-0 output breaker the 4 following also apply:

9 4) The opposite unit must not have a safety injection signal.

7 5) The opposite unit's diesel generator circuit breaker must be open.

i Please consider this while grading since the detailed answer  ;

. appearing on the answer key breaks the above five conditions into l eight conditions. Also note that number six (Diesel "0" override i

relay energized) cannot be verified as a valid response.

Reference:

Zion S.D. Chapter 1 pp. 1-60, 1-61, Zion Electrical Schematic 22E-0-4840-AP-25.

NRC Resolution

. Partially Accepted. Items may be grouped as indicated provided that l all parts which are in present answer key are nentioned. ' Item 6 of answer key will be dropped. Points are redistributed to allow for grouping.

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l Attachment 3 Section 8 8.03.a Facility Comment T.S. Definitions Page 6 - Operable ". . . capable of performing its l specified function (s)." "The specified function" of the charging l pumps is to inject water from the RWST through the BIT and into the RCS during a need for ECCS. With the discharge valve failed closed

the charging pump must be considered inoperable. Also answer to f

part "C" would not be seven days if pump was considered operable.

Therefore the answer to part a. should be changed to No.

NRC Resolution Accepted. Part "a" to the answer key changed from yes to no.

8.06.b Facility Comment In addition to answer key please accept 10 CFR 50 as a document which would (does) require notification (due to EPIP declaration, the NRC would be notified).

NRC Resolution Accepted. .aued 10 CFR 50 to answer key as possible answer toi partial credit.

8.08 Facility Comment Please note that EPIP 360-1 is not referenced in EPIP 100-1 (Acting Station Direction Implementing Procedure) and the information needed to determine whether or not an evaluation is necessary would not ,

normally be available until the TSC is manned, and at that time the l Station Director would make that decision.

NRC Resolution j l

Not accepted. EPIP 100-1 does use EPIP 360-1 as a reference and by steps required in 100-1 an evacuation could be ordered by the Acting Station Director.

l 8.10 Facility Comment Question ZAP 1-51-1 (Typo) and Answer Reference NRC Resolution Accepted and Corrected. Question and reference.

Attachment 4 I

Section 8 Facility General Comment In reviewing the written exam it was noted that five (5) points (20%) of Section 8 dealt with Standing Orders. The Station feels the three (3) questions (8.06, 8.07 and 8.11) are not valid or proper. The Standing Orders are typically short term and transient in nature. Their purpose is to provide a mechanism for the dissemination of instructions which are general and of continuing applicability to the conduct of operations. They are to be used in relation to approved operating procedures. Therefore, the Station requests that these three (3) questions be reevaluated as to point value assigned.

Reference:

ZAP 10-52-3, page 2.

1 NRC Resolution l Not Accepted. Point values to stand as assigned. We recognize that five  ;

points of Section 8 dealt with the Station's Standing Orders. Each question '

was analyzed to determine the pertinence of the subject and the impact on plant operations. The three questions specifically noted are critical safety 1 issues. I Question 8.06 deais with possible radiation release to the environment.

8.07 deals with the possibility of operations in an unanalyzed area not covered by the FSAR but allowed by Technical Specifications.

8.11 deals with reactor protection. Bistables which must be tripped per an AOP but could be overlooked due to a temporary piping jumper installed.

1 The critical nature of each of these items does make them valid and proper  ;

questions for the examination.

4 The Station also contends that the Standing Orders are " typically short term l and transient in nature" and then state that the standing orders are " general I and of continuing applicability to the conduct of operations." These statements are contradictory. In fact there are presently Standing Orders dating back to 1980 still in effect. Anything that deals directly with l

.echnical Specifications and unanalyzed FSAR conditions cannot be considered

" general." l l

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• w Il V V a U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION 1

FACILITY: ZION 1&2 l REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 86/03/10 l EXAMINER: PICKER, B. l APPLICANT:

IESIRUCTIONS TO APPLICANT: ,

Use separate paper for the answers. Write answers on one side only. ,

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

% OF CATEGORY  % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE 7ALUE CATEGORY 25.00 25.00 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 25.00 25.00 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 25.00 25.00 7. PROCEDURES - NORMAL, ABNORMAL, ,

EMERGENCY AND RADIOLOGICAL l CONTROL l 25.00 25.00 8. ADMINISTRATIVE PROCEDURES, I CONDITIONS, AND LIMITATIONS l

100.00 100.00 TOTALS FINAL GRADE  %

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

APPLICANT'S SIGNATURE

5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 2 IHERMODYNAMICS QUESTION 5.01 (2.00)

Concerning the Moderator Temperature Coefficient (MTC), state whether the MTC value would be MORE NEG., LESS NEG., or NOT EFFECTED by each of the following. CONSIDER EACH SEPERATELY.

a. BOC to EOC.

b. Fission Product poison buildup.

c. Burnable posion rod burnup.

d. Insertion of control rods.

QUESTION 5.02 (1.00)

TRUE OR FALSE 7 As Boron concentration increases:

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a. Moderator Temperature Coefficient becomes less negative due to increased neutron leakage. (0.5)

b. Moderator Temperature Coefficient becomes more negative due to the increased resonance absorption factor. (0.5)

QUESTION. 5.03 (1.50)

You have just completed a reactor startup and power level is at the point of adding heat. For the following situations, l l indicate if final stable power level will be HIGHER, LOWER, or l

THE SAME. Assume core is at mid-life. Treat each situation separately. ,

a. Steam dump pressure setting is raised by 20 psig while dumping steam.

b. A 1% steam leak develops outside of containment.

c. An inadvertant 20 ppm boron addition is made.

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

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5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 3 THERMODYNAMICS QUESTION 5.04 (1.00)

During a Xenon-free reactor startup, critical data was inadvertently taken two decades below the required Intermediate Range (IR) level (1xE-10 amps).

The critical data was taken again at the proper IR level (1xE-8 amps).

Assuming RCS temperatures and boron concentrations were the same for each set of data, which of the following statements is correct?

a. The critical red position taken at the proper IR level is LESS THAN the critical rod position taken two decades below the proper IR level.

b. The critical rod position taken at the proper IR level is THE SAME AS the critical rod position taken two decades below the proper IR level.

c. The critical rod position taken at the proper IR level is GREATER THAN the critical rod position taken two decades below the proper IR level.

d. The critical rod position taken at the proper IR level CANNOT BE COMPARED to the critical rod position taken two decades below the proper IR level.

QUESTION 5.-05 (1.50)

Compare the calculated Estimated Critical Position (ECP) for a startup 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after a trip to the actual Critical Rod Position (ACP) if the following events / conditions occurred. Consider each independently. Limit your answer to:

a. ACP higher than ECP.

b. ACP lower than ECP.

c. ACP would not be significantly different than ECP. ,

1. One Reactor Coolant Pump is stopped one minute prior to criticality.

N 2. The steam dump pressure setpoint is increased to a value just ,

below the code safeties setpoints. l

3. The startup is delayed 2 more hours.

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5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 4 THERMODYNAMICS QUESTION 5.06 (2.00) l a. If the reactor is operating in the power range, how long will l it take to raise power from 20% to 40% with a +0.5 DPM Start-l up rate?

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b. Will it take the same amount of time to raise power from 40%

to 60% if the same startup is maintained? EXPLAIN.

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QUESTION 5.07 (3.00)

Indicate at which time in core life (BOL or EOL) the following accidents are more severe (result in a longer time spent at higher power).

Briefly explain why.

a. Main steam line break

b. Total loss of coolant flow

c. Rod withdrawal accident from low in the source range prior to any significant reactor coolant temperature increase.

QUESTION 5.08 (1.00) l Which of the following conditions would cause a 1/M curve to predict criticality earlier than it will actually occur? )

a. Source located too near detector. )

b. Fuel assemblies loaded too far from detector.

l c. Highest worth fuel assemblies loaded first.

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! d. Control rod located between fuel assemblies loaded.and detector.

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5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 5 THERMODYNAMICS QUESTION 5.09 ( .50)

Which of the following conditions is NOT indicative of pump runout?

a. Abnormally high discharge pressure.

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b. Excessive current in the pump motor.

c. Failure of the coupling between the pump shaft and the motor shaft.

d. Available NPSH less than the required NPSH.

QUESTION 5.10 ( .50) i Choose the CORRECT response. In order to maintain a 200 F subcooling margin in the RCS when reducing RCS pressure to 1600 psig, steam generator pressure must be reduced to approximately:

a. 845 psig i b. 645 psig

c. 445 psig

d. 245 psig QUESTION 5.11 (1.00)

The Reactor Protection System would become unreliable for DNB protection from the OT delta T trip if voids were allowed to form in the Reactor Coolant System because:

a. the heat transfer coefficient of the cladding is reduced significantly.

b. the specific heat capacity of the reactor coolant inventory changes when voiding occurs and is not measurable by the RTDs.

c. the critical point if water is reached and is not measurable by the .

RTDs.

d. entropy becomes more limiting than enthalpy, which is not within the design considerations of the Reactor Protection System.

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5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 6 THERMODYNAMICS 4

4 QUESTION 5.12 (2.00) f l

- Will the Departure from Nuclear Boiling Ratio (DNBR) increase, decrease or remain the same if the following plant parameters increase during power operation? Consider each parameter independently,

a. Reactor Coolant System (RCS) Pressure.

b. RCS Temperature.

c. RCS Flow.

d. Reactor Power.

QUESTION 5.13 (1.00)

Which of the following describes the changes to the steam that occur between the inlet and outlet of a real (not ideal) turbine?

a. Enthalpy decreases, entropy decreases, quality decreases.

b. Enthalpy increases, entropy increases, quality increases,

c. Enthalpy constant, entropy decreases, quality decreases.

d. Enthalpy decreases, entropy increases, quality decreases.

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1 QUESTION 5.14 (1.00)

The 2200 degrees F maximum peak cladding temperature limit is used because

a. it is 500 degrees F below the fuel cladding melting point.

b. any clad temperature higher than this correlates to a fuel center line temperature at the fuel's melting point.

x4 c. a sircalloy-water reaction is accelerated at temperatures above 2200 F.

d. the thermal conductivity of zirealloy decreases at temperatures above 2200F causing an unacceptably sharp rise in the fuel centerline temperature.

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5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 7 THERMODYNAMICS 7

QUESTION 5.15 (2.00)

. Assume one Reactor Coolant Pump trips at 30% power, without a i reactor protective system actuation or a change in turbine load.

Indicate whether the following parameters will INCREASE, DECREASE j or REMAIN THE SAME.

j a. Flow in the OPERATING reactor coolant loops.

r b. Reactor vessel Delta P

c. Core Delta T 4

d. An OPERATING: LOOP steam generator steam flow r QUESTION 5.16 (1.00) 1

! The reactor is producing 100% rated thermal power at a core delta T l"

of 42 degrees and a mass flow rate of 100% when a blackout occurs.

Natural circulation is established and core delta T goes to 28 degrees. If deca ~y heat is 2%, what is the core mass flow rate (in %)?

, QUESTION 5.17. (2.00)

Explain why a dropped rod is worth approximately 200 pcm and a stuck i rod is worth 1000 pcm even though the same rod could be considered in both cases.

I QUESTION 5.18 (1.00) 4 At BOL and as fuel temperature increases, WHY does the magnitude of the Fuel Temperature Coefficient decrease as fuel temperature increases?

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6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 8 j

QUESTION 6.01 (2.00)

Indicate which of the Excore Nuclear Instrumentation Ranges (SOURCE, INTERMEDIATE, or POWER), will correctly match with the following statements. More than one may apply to each.

a. Provides a direct input to the Rod Control System.

b. Has a reactor trip function that is blocked at some time between startup and full power operation.

c. Utilizes a Boron-10 coating in it's detectors.

d. Operates in the " Ion Chamber" region of the " Gas Filled "

Detector Characteristic Curve".

QUESTION 6.02 (2.00)

If the available Feedwater Pump NPSH decreases to 275 psig, an alarm sounds. What other FOUR actions automatically occur when a low FWP suction pressure condition exists?

QUESTION 6.03 (2.50)

The following concern the CVCS at Zion.

a. What are the TWO functions (purposes) of the Letdewn Pressure Flow Control Valve (PCV-131)? (1.0)

b. If left in automatic control, what position should PCV-131 be found in two minutes after a safety injection initiation? (0,5)

c. Why is letdown flow limited to 120 gpm? (0.5)

d. With only the PD pump operating at power, which valve (s) is/are utilized to vary RCP seal injection flow? (Either noun name or numbers acceptable.) (0.5)

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6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 9 QUESTION 6.04 (2.00) 4 PCV 455C (PORV) control switch is a 3 position switch located on the Main Control Board. Answer the following.

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a. What is the purpose of each position?

b. How is an uncontrolled depressurization prevented on a failure of

' 455C in the full open position?

QUESTION 6.05 (3.00) t What are Ks conditions required for ACB 1473 Emergency Feed to bus 147 from Diesel Generator "O" to automatically close?

QUESTION 6.06 (2.50) 1 I a. With the Component Cooling Water Pump Control Switch in

the " AUTO" position

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1) What conditions will automatically START the pump? .,

- 2) What conditions will automatically TRIP the pump? '

b. What TWO signals will isolate the CCW return water from the

, Excess LDHX by closing valve 1AOV-CC94377 (Setpoints are

not required.)

c. Why do the piping lines on the RCP Thermal Barrier Heat

, Exchanger Return Header upstream of valve ICC685 have a i design pressure of approximately 2485 psig?

QUESTION 6.07 (2.50)

I a. The flowrate through the RCP #1 seal is not constant for all plant conditions. EXPLAIN when AND why the flowrate will be at it's highest.and lowest value, i l

l b. What is/are the flowpath(s) for the RCP #1 seal leakoff during a safety injection?  !

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c. What determines the differential pressure across the RCP #1 seal?

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6. PLANT SYSTEMS DESIGN. ' CONTROL. AND INSTRUMENTATION PAGE 10 QUESTION 6.08 (3.00)

Show what happens to the Rod Control System (RODS IN, RODS OUT or NO CHANGE) and BRIEFLY EXPLAIN why the change will or will not occur for the following instrument failures. Assume that the plant is at 50% load with all systems controlling in automatic.

a. Loop B(2) Cold Leg RTD fails LOW.

b. Turbine Impulse Pressure (PT-505) fails LOW.

c. Power Range lower detector (NI-44) fails'HIGH.

QUESTION 6.09 (3.00)

List FOUR signals that will initiate a safety injection. Include with each any permissive that will block or allow blocking of the signal.

Setpoints not required.

QUESTION 6.10 (1.50)

a. Define " Coincidence" as it applies to the Reactor Protection System (RPS).

b. What is the minimum degree of redundancy that is allowed for protection instrumentation?

! c. Protective signals that initiate Reactor Protection and Engineering Safety Features use a "de-energine to operate" bistable principle.

State the one protective feature that does not use this principle and explain why.

1 QUESTION 6.11 (1.00)

I The THREE input signals to the Steam Generator Water Level Control t are:

a. Tavg, compensated feed flow, uncompensated steam flow,

b. Feed flow, compensated steam flow, water level error,

c. Compensated feed flow, water level, compensated steam flow.

d. Uncompensated feed flow, compensated steam flow, water level.

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7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 11 RADIOLOGICAL CONTROL QUESTION 7.01 (1.50)

Per E-0, REACTOR TRIP OR SAFETY INJECTION, what is/are the criteria for l stopping the RCP's in an accident condition?

QUESTION 7.02 (3.00)

During refueling operations, RT-AR03 alarms indicating high -

radiation in the Fuel Building Pool Area.

a. What automatic actions take place?

h. What are the Fuel Handling Supervisors immediate responsi-bilities as stated in E0P-6 (Fuel Handling Emergency)? ,

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c. If Health Physics reports there is a high level of tritium l in the area, what protective measures must be taken prior to entry into this area?

QUESTION 7.03 (1.00)

Briefly explain why the Caution Note in AOP-5, " Radiation Monitor-High i Activity Process Monitoring" requires the operator to ensure that the computer room doors are shut?

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QUESTION 7.04 (3.00)

a. What are FOUR plant conditions that require emergency boration, according to EOP-5, " Emergency Boration"?

b. Describe the LEAST preferred method / flow path for emergency boration.

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QUESTION 7.05 (1.00) l 1

i During a recovery from an inadvertant Safety Injection, under what conditions must the Safety Injection be manually reinitiated? j l

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7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AEQ PAGE 12 RADIOLOGICAL CONTROL l

QUESTION 7.06 (3.00)

Zion Unit 1 is operating at 85% power and utilising the Motor Driven Feed-water pump due to a Steam Driven FW pump being out of service. With all plant systems in normal / auto, answer the following questions concerning a MDFW pump / Reactor trip:

a. What are 5 conditions that could cause the MDFW pump to trip.

b. What are the immediate actions to be done for E-0 REACTOR TRIP.

i QUESTION 7.07 (2.50)

a. Describe the immediate action steps to determine which instrument bus is lost according to AOP-15, " Loss of Instrument Bus".

i b. How is power restored to the bus?

i QUESTION 7.08 (2.00)

Per E-0 " Reactor Trip or Safety Injection":

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a. What TWO conditions consitute ADVERSE CONTAINMENT conditions?

b. If ADVERSE CONTAINMENT conditions had been present, when would it be premissible to again use normal parameter

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(1.50)

QUESTION 7.09 According to AOP-6 Charging or Letdown Line Failure", what actions are required if:

l Seal Water outlet temperature is > 210 F RCP Radial Bearing Temperature > 200 F i

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i 7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 13 i

B&DIOLOGICAL CONTROL QUESTION 7.10 (1.50)

a. What precaution must be taken before stopping a RHR pump when solid according to GOP-4.

b. What is the minimum pressure that the RCS can be operated at when solid with one RCP running?

c. When Nitrogen pressure control is used instead of solid plant control what provides RCS overpressurisation protection?

l QUESTION 7.11 (2.00)

Answer the following according to GOP-2.

a. The shutdown banks do not need to be withdrawn prior to dilution if what condition is met?

b. Which SI must be unblocked prior to diluting below the required cold shutdown boron concentration?

c. Why must the startup of Main Feedwater Pump B or C be done only when ready to go off Auxiliary Feedwater?

d. Why is it required that the Main Turbine bea n- lift pump j control switch be placed in the AUTO (after- ) position j at the end of the turbine oil pump interlock checks?

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QUESTION 7.12 (2.00)

According to E-0 FOLDOUT PAGE, what are FOUR conditions that indicate adequate Natural Circulation Flow?

QUESTION 7.13 (1.00) i GOP-1 states that 1C RCP on Unit i must be started first on a startup. Why is this precaution necessary?

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8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 14 I

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l QUESTION 8.01 (1.00) I l

Whose authorisation is required for non-routine valve lineups per i ZAP 3-51-4B7 )

l QUESTION 8.02 (1.50)

! What are THREE conditions that a procedure must meet such that logging of wires and jumpers is not required according to ZAP 3-51-4

" Procedure Governing the Use of Temporary Jumper cables, Lifting of I l

Terminated Wires, the Bypassing of Alarms, or the Installation of Mechinal Blocks or Bypasses"?

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QUESTION 8.03 (1.50) J 1

On May 5th a valve lineup was performed on No.1 Centrifugal Charging pump to place it in service following routine maintenance. An entry is included in the Standing Orders to minimize useage of the pump. On May 18th an Auxiliary Operator reports that the discharge valve is closed and can not be physically opened. Answer the following.

a. Is the pump OPERABLE per Tech Specs?

b. Has the Tech Spec LCO been violated?

c. How long can the pump be left in this condition?

QUESTION 8.04 (1.00)

Per the Tech Spec's interpretations, explain what the intent of "IMMEDIATELY SHUTDOWN" is when it is found in the action statements.

QUESTION 8.05 (1.50)

Per ZAP 5-51-4, PROCEDURE CONTROL AND APPROVAL, what is the difference between a SPECIAL PROCEDURE CHANGE and a TEMPORARY PROCEDURE CHANGE 7 1

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

8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 15

. QUESTION 8.06 (2.00)

a. What actions must be taken, according to Standing Order #236 if l during a release the Release Path Monitor reaches the HIGH ALARM?

i I b. If the release exceeds 2.5 times 10CFR20 limits, what is the

! maximum time lapse between the release and notification to the NRC operations center and what document directs this notification?

i QUESTION 8.07 (2.00)

Zion Standing Order #268 requires that the reactor trip breakers are open or the MG sets deenergized when the RCS is between 350 and 547 F with less than four RCPs operating.

a. What is the basis for this requirement?

b. What necessitated the Standing Order to be issued?

1 i

QUESTION 8.08 (2.00)

Per EPIP 360-1, site evacuation SHALL commence following the completion of personnel accountability unless 4 conditions exist. List the 4 conditions.

c QUESTION 8.09 (2.00)

What is the responsibility of the Shift Engineer in regard to HIGH I

RADIATION AREA ACCESS CONTROL? List 4.

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

1

8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS ' PAGE " 16 QUESTION 8.10 (3.00) 4 Indicate whether the following is a primary function of'the Shift Engineer

{

OR Shift Foreman (licensed), according to ZAP 14 51-1, Station Organization.

a. Authorize Surveillance.

b. Act as Fire Chief.

c. Submit work requests and coordinate operations /maintanence activities.

d. Placing equipment in or out of service.

e. Review Unit logs.

f. Ensure unqualified operating personnel perform evolutions in the presence of qualified personnel, i

QUESTION 8.11 (1.00)

What happens AND what action must be taken if 1 LT 529 transmitter is valved out of service according to Standing Order #272?

t

QUESTION 8.12 (1.00) 4 Which of the following statements concerning Shutdown Margin (SDM) considerations is correct?

a. With Tavg less than 200 degrees, the SDM require 6ents are increased because of the possibility of a positive MTC.

i i b. The most restrictive condition for SDM re'quirements occur at EOL, with Tavg at no load temperature, and is associated with j a rod ejection accident.

c. When in Mode'2 with keff less than 1.0, adequate SDM is ensured by verifying the predicted critical rod position is above the rod insertion limits.

) d. If one rod is known to be partially inserted and untrippable

, an increased allowance for the entire rod worth shall be made to the SDM requirements.

1

8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 17 d

QUESTION 8.13 (1.00) i Which of the following statements concerning the AFD requirements is j correct?

a. Above 90%, within 30 minutes of going outside the target band, either restore indicated AFD to within the target band or reduce power to less than 90%.

b. If the axial flux difference alarms are out of service, the AFD shall shall be logged every hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and half-hourly thereafter until the alarms are returned to operable.

, c. Below 50% power, penalty points are accumulated at one point for every

minute outside the target band.

i

, d. Power level shall not be increased above 50% unless the AFD is within i the target band.

QUESTION 8.14 (2.50)

What FIVE means of protection must be taken in accordance with Technical Specifications to prevent a low temperature over i

' pressurization accident when RCS temperature is below 250 F and the vessel head is installed?

QUESTION 8.15 (2.00) l

a. What SIX items must be reviewed by the Shift Engineer prior to i shift turnover per ZAP 10-52-3, " Shift Manning, Relief and Turnover"? l l

b. What is the retention period for the turnover checklist by the Shift Engineer AND what happens to the checklist at the end -

of the retension period?

)

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

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

EQUATION SHEET f =.na v = s/t Cycle efficiency = (tier work cut)/(Energy in) 2 w = ng s = V,t + 1/2 at 2

E = mc ,

~*

XE = 1/2 mv a = (Vf - Va )/t A = Att A=Ae3 PE = mgn vf = V, e at * = e/t x = tn2/t;fg = 0.693/t1/2 4,,j A= 204 2 1/28 " " U *U'

[( ) + ( 3)]

.E = 931 m -

m = V,yAo ,

-Ex Q = mCoat 6 = UAa7 I = I 3

e~"*

• Pwe = Wf d. I = I,10-* N L TIL = 1.3/u P = P,10 sur(t) HVL = -0.693/u P = Pe e*/I SUR = 26.06/T SG = S/(1 - Kg)

Gx= S/(1 - Kg x)

SUR = 2So/t* * (s - o)T G;(1 - Kg)) = G (I 2 ~ kW 2)

T = ( A*/o ) + ((a - o /' Io ] M

• 1/(I - Kg) " U 1/G o i = V(o - a) M = (1 - Kw o)/(I - Keff1)

T = (a - o)/(Ta) SOM = ( -Keff}/Keff a = (K ,ff-l}/Kg = !Xeff/Keff 10 secuc I*=0.1 A= seconds _

a = [(L*/(T Kg)3 * [ig/(1+IT)]

Idlt"Id2 P = (uV)/(3 x 1010) I4 3 2 ,2 gd 22 t=N 2 R/nr = (0.5 CZ)/d (meters)

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

Watar Partmeters Miscellaneous Conversions 1 gal. = 3.345 lem. 1 curie = 3.7 x 1010:g, 1gja.=3.7811:ars 1 kg = 2.21 lem 1 f. = 7.48 gal . I no = 2.34 x 103 Stu/hr Density = 52.4 lerp/ft3 i mw = 3.41 x 100 Stu/hr Density = 1 gm/c9 lin = 2.54 cm Heat of vaporization = 970 Stu/lem V = 9/5'C + 32 Heat of fusion = 144 Stu/lem 'C = 5/9 ( ?-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H 2O = 0.4335 lbf/in. ,

._a 1.__ ._.

5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 18 THERMODYNAMICS ANSWERS -- ZION 1&2 -86/03/10-? ICKER, B.

ANSWER 5.01 (2.00)

GI!RC:PY

a. MORE NEG.

b. MORE NEG.

c. LESS NEG.

d. MORE NEG.

REFERENCE ROWE Reactor Operator Training Manual, pp 3-202 211 ZION - Westinghouse Fundamentals of Nuclear Reator Physics, pp 6-42 to 6-50 ANSWER 5.02 (1.00)

a. False

b. False REFERENCE IP-3 ECI Rx Theory; Chapter 7, Pages 21, 22, and 27 DCC Rx Theory Review Text, pp. I-5.42 .50 SHNP, RT-LP-1.13, Pp. 11-18.

Rowe Reactor Operator Training Manual, p. 3-233 ZION - Westinghouse Fundamentals of Nuclear Reator Physics, pp 6-42 to 6-50 ANSWER 5.03 (1.50)

a. LOWER

b. HIGEER

c. LOWER REFERENCE McGuire Plant Summary Manual, (MC-RT-RCO, ig, #6-9).

ZION Westinghouse Reactor Core Control for Large PWRs

5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 19 THERMODYNAMICS ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

l ANSWER 5.04 (1.00) b REFERENCE NUS, Nuclear Energy Training, Module 3, Unit 6 Westinghouse Reactor Physics, Sect. 3, Neutron Kinetics and Sect. 5, Core Physics HER, Reactor Theory, Sessions 20 and 24 - 31 Zion, NUS book 3, sections 6.5, 6.6. 6.7, 12.4, 12.5.

ANSWER' 5.05 (1.50)

1. c (same)

2. a (ACP higher)

3. b (ACP lower) [0.5 ea.]

REFERENCE SQNP, Review of Core Poisons, pp. 4-7 KA001/000,K5.18,4.2.

Cook Theory, Pp. I-36-45.

Zion, NUS book 3, section 12.5.

ANSWER 5.06 (2.00)

a. 36 seconds. (+/- 2)

b. No.[.25] Power esca11ation is a log function and therefore increases at an increaseing rate. [.75] (2.0)

REFERENCE Cook Theory, Pp. I3.15-16. KA001/010,K5.37,3.2.

Zion, NUS book 3, section 6.4

-.a==- p--. - _...a,. - . . - . , . . - . ,

...m.. . _ _ _ . . , , _ . . . , , _. ,, . , _ _ , , , , , ,

-- n - :... .. - - _. . - . . . . ..

5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 20 THERMODYNAMICS ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

ANSWER 5.07 (3.00)

\

o.D

a. EOL - MTC is more negative and thus imparts greater positive reactivity from the drop in coolant temperature. [1.0]

(Doppler only Power coefficient (DOPC) is less negative and thus imparts less reactivity from the power increase.)

c. 0

b. BOL - MTC is less negative and thus imparts less negative reactivity from the coolant heat-up. [1.0]

(DOPC is more negative and thus imparts more positive reactivity as power drops which tends to hold power up.)

(.4

c. EOL - (Beta-eff is less, making SUR greater).

DOPC is less negative and thus imparts less negativp reactivity af ter the fuel temperature begins to increa.s on.h6 God woe 4 w.u ceo .

2 4 Y. 2.so n -

Wedmgkom N,.b M fg d,,% d lg (,

ANSWER 5.08 (1.00) c REFERENCE Westinghouse Nuclear Training Operations, pp. I-4.19 - 21 ZION - Westinghouse Fundamentals of Nuclear Reator Physics, Chapter 8 001/010; K5.16 (2.9/3.5)

ANSWER 5.09 ( .50) a REFERENCE Westinghouse Thermo-Hydraulic Principles, Ch 10, pp 32-44 ANSWER 5.10 ( .50) d REFERENCE Steam Tables

. ,_ - = . .

O

5. THEORY OF NUCMAR POWER PLANT OPERATION. FLUfDS. AND PAGE 21 THERMODYNAMICS ANSWERS -- ZICN 1&2 -86/03/10-PICKER, B.

ANSWER 5.11 (1.00) b i

REFERENCE

MNS Thermo, para. 2.6.

Westinghouse Thermal-Hydraulic Principles and Applications to PWR II Chapter 13, pp 53-56

.W I ANSWER 5.12 (2.00)

a. Increase.

b. Decrease.

c. Increase,

d. Decrease. [0.5 ea.]

REFERENCE THERMAL HYDRAULIC PRINCIPLES AND APPLICATION TO THE PWR CHAPTER 13-41 i

l ANSWER 5.13 (1.00) d

, REFERENCE MNS OP-SS-HT-2, p.12. 1 Westinghouse Thermal-Hydraulic Principles and Applications to PWR II i Chapter 7 ANSWER 5.14 (1.00) c REFERENCE MNS Thermo-Core Performance, p.2.

Westinghouse Thermal-Hydraulic Principles and Applications to PWR II Chapter 13, p. 15 i

- - , _ _ . , , ,,,___m m. ._ _m.,__.__ _

O

5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 22 THERMODYNAMICS

~

ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

ANSWER 5.15 (2.00)

a. Increase

b. Decrease

c. Increase

d. Increase [0.5 each]

REFERENCE Summer Plant Systems Descriptions, Auxiliary Building Systems, Chapter AB-4, p 16; Summer Heat Transfer Thermodynamics and Fluid Flow Book, pp 180, 211, 322, 328 GLJ 175 ROWE Reactor Operator Training Manual, Sec. 2, pp 40-44 Westinghouse Thermal-Hydraulic Principles and Applications to PWR II Chapter 12, pp 15-18 ANSWER 5.16 (1.00)

To determine flow in NC:

Q = m cp deltaT => 100 = 100

• cp

• 42 => cp = 100 100

• 42 cp = .0238

. . I THEREFORE 2% = m * .0238

• 28 => m= 2%

---

= 3.0012%

.0238

• 28 REFERENCE l General Physics, HT & FF, Section 3.2 '

ROWE Reactor Operator Training Manual, Sec. 2, pp 54-63 l Westinghouse Thermal-Hydraulic Principles and Applications to PWR 11 Chapter 14, pp 15-29 l

._ _ , _ . . = . ,

1 .

3

5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 23

. THERMODYNAMICS i

i I ANSWERS -- ZION 1&2 -86/03/10-PICKER, B. l t

i ANSWER 5.17 (2.00)  ;

When a rod is stuck out with all other rods inserted, that rod " sees" i a much higher flux than the rest of the core. Because rod worth is a function of the relative flux difference between the rod and the core average flux, the rod is worth about 1000 pem which is much more than normal. [1.0]

If a rod is dropped just the opposite happens. The rod depresses the

'- the flux in the area it is in relative to the rest of the core and so is

. only worth about 200 pcm. [1.0]

REFERENCE i IP2 Reactor Theory pg 7-59,60.

ZION Westinghouse Fundamentals of Nuclear Reactor Physics, chapter 6,

. pp 6-24 to 6-27 2

ANSWER 5.18 (1.00)

FTC becomes less negative as fuel temperature increases because resonant band widening is reduced at higher temperatures.

REFERENCE

• HO-RTR-76 to-78,-85 4

ZION Westinghouse Fundamentals of Nuclear Reactor Physics, chapter 6, pp 6-35 to 6-42

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

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 24 ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

ANSWER 6.01 (2.00)

a. INTERMEDIATE and POWER

b. SOURCE, INTERMEDIATE and POWER

c. INTERMEDIATE and POWER

d. INTERMEDIATE and POWER [0.5 each]

REFERENCE Zion SD, 6a,6b,and 6c.

SENP NIS-LP-1.0, pp 8-19 ANSWER 6.02 (2.00)

- Gland seal condenser bypass valves trip open

- Standby Cond./Cond. Booster Pump starts

- Cond. Booster Pump recire valves trip shut

- Heater Drain Level Control overrides (to allow full HDTP flow to go to the FWP). [0.5 each]

REFEPINCE Zion System Descriptions, Chapter.25a, p. 44 ANSWER 6.03 (2.50)

a. - Maintain backpressure on orifices to prevent flashing.

- Maintain RCS pressure when solid. [0.5 each] (1.0)

b. GHUT (0.5)

c. Prevent (resin channeling due to) excess flow through demin resin. (0.5)

d. HCV-18,2 (Charging flow control valveN 6eak.p% $M.,. ,, gp (0.5)

My na+k Jal4. P mbol mJoe.)

REFERENCE WBLP; CVCS, pages 11 and 16 ZION System Descriptions Chapter 5, pp 5-6, 39 and Fig. Sa-I-Ci  !

.____----____.--___-.-_.-_.._.__.-___--_---___-__i-* _ _ _ . - _ - - - - _ - - - _ - _ . _.:-__.--__----___.--_._----_:-_---_-_.

• ._.-----_a_.- a u2-. __r___

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 25 ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

ANSWER 6.04 (2.00)

a. OPEN-opens valve AUTO-set to open at 2335 psig AUTO-LOW-setat435by(PT403)whenRCSis < 250 degrees F. [0.5 each]

b. Interlockedwithchannel458tocloseat23k5psig. [0.5]

y At emocAW Toto medt vahe.

REbsncNCE Zion System Descriptions Chapter 3c, p. 22 and Fig. 3c-II-C1 and C2 ANSWER 6.05 (3.00)

{ g 3/kg at 0.5 ea

1. Main Feed ACB1471 over current trip relay reset Z 2. Reserve Feed breaker ACB1472 over current trip relay reset

3. Diesel Generator differential current relay reset Main Feed breaker ACB 1471 open I $4.

[5. Reserve Feed breaker ACB 1472 open A/ ele: pog be gm* Ped E_ :ic:ci "C" :c rride rel2r energ*::d % as maicded bJail 3- 7. DG "O" supply breaker to bus 247,ACB2473 open %h =s+ I MM. )

y -8. DG at speed and voltage. l er - 9 . No SI on opposite Unit. 1 REFERENCE Zion System Descriptions Chapter 1, pp. 60-61 ANSWER 6.06 (2.50) l a.1) - Low pump discharge pressure (80 psig)

- Blackout Sequence

- SI Sequence a.2) - UV

- OC [0.3 each) (1.5)

b. - Phase A Isolation

- SI (0.5)

c. It may be subjected to RCS pressure if a Thermal Barrier HX leak occurred (after the leak is isolated). (0.5)

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 26 ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

REFERENCE Zion SD; 15-11 and 12, 15-30 and 31 ANSWER 6.07 (2.50) l

a. As the plant pressure changes so will the delta-P across the

1. 1 seal thus changing the seal flowrate. [.5] Flow is high at high pressures and low at low pressures. [.5] (1.0)

b. Through #2 seal to the RCDT and the #1 seal return line relief valve to the PRT. (1.0)

c. RCS pressure compared to the backpressure created by the VCT. (0.5)

REFERENCE Millstone System Descriptions, topic 1, lesson 2, Pp 15 and figure RP 14 Zion S.D. 3b, Pp 9-11 and drawing M-54.

ANSWER 6.08 (3.00)

a. NO CHANGE; Results in a low loop Tavg, Rod Control utilizes *-

l a Auctioneered High Tavg. (1.0) i i

b. RODS IN; Pimp will generate a minimum Tref, a large temperature I error will cause rods to insert. (1.0)

c. RODS IN; Nuclear power > turbine power (mismatch), rods in 4 to compensate for anticipated high Tavg. (1.0)

REFERENCE Zion SD; Sa-11 through 13 l

f I

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 27 ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

i ANSWER 6.09 (3.00)

- - Low Pressurizer Pressure [.25), P-11 [.25].

- High Steam Flow with Low Steam Pressure or LoLo Tavg [.25), P-12 [.25].

- High Steamline Differential Pressure [.25], R.C. Loop Isolation Valve Permissive [.25]. l i

- High Containment Pressure [.25], No Permissive [.25]. (2.0)

(Manual, no permissive is acceptable as an answer)

REFERENCE Zion SD; 12b-31 and 32 ANSWER 6.10 (1.50)

a. Coincidence is the number of input channels required to l initiate a protective action as compared to the total number

< of input channels. (0.5)

b. Minimum is one more channel than is required to initiate the (0.5) protective action.

c. High-high containment pressure,[.5] to prevent inadvertant initiation of containment spray if power is lost. [.5] (0.5)

REFERENCE j Millstone Systems Descriptions, topic 7, lesson 1,2, and 3, Pp 8-11, 73 j and topic 8, lesson 4, p 6. ,

Zion S.D. 9, p.13, S.D. 12b, p.3. l 1

ANSWER 6.11 (1.00)

b. ,

I REFERENCE

, VCS Plant System Descriptions, IC-2, p. 10 Zion S.D.25b, Pp. 2-3.

I i

l I l 2 __ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _- _ . _ .

.. - . . . . - . . - . ... . - . -.~ . .

7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 28 RADIOLOGICAL CONTROL ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

ANSWER 7.01 (1.50)

At least 1 CCP or SI pump running AND wide range RCS pressure drops below 1250 PSIG (1550 for adverse containment)

OR Within 5 minutes after losing CCW to RCP's.

REFERENCE ,

ZION E-0 Foldout page i

ANSWER 7.02 (3.00)

a. 1. Fuel building ventilation diverts through the charcoal filters.

2. Charcoal booster fans auto start. [0.5 each]

l b. 1. All personnel accesses to the affected area are closed.

2. All personnel have evacuated the affected area. [0.5 each]

c. 1. Shield against injestion.

2. Air feed respirators. .

3. Use of a plastic or rubber suit. [0.33 each] I REFERENCE ZION EOP-6 p.4, 5 & Rad Con Considerations ANSWER 7.03 (1.00) l To maintain proper pressure in the computer room [0.33] to prevent high activity entering the control room directly [0.33] through the pressure relief damper on the computer high vac [0.33].

REFERENCE ZION AOP-5, Section SA

7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 29 RADIOLOGICAL CONTROL ANSWERS -- ZION 1&2 -86/03/10-PICKER. B.

ANSWER 7.04 (3.00)

a. 1. Control bank below RIL low-low limit.

2. Failure of two or more rod clusters to insert on trip or S/D.

3. Unexplained or uncontrolled reactivity increase.

4. Failure of reactor makeup such that bypass is necessary to accomplish boration. [0.5 each] (2.0)

b. Through BIT via cold leg injection on loops A, B, C or D. (1.0)

REFERENCE ZION EOP-5, Emergency Boration ANSWER 7.05 (1.00)

1. Pressurizer level cannct be maintained >4%

OR

2. RCS subcooling < 30 degrees F [.50 ea]

REFERENCE ZION E-1 Foldout page 1

ANSWER 7.06 (3.00)

a. 1. Loss of all condensate / condensate booster pumps )

2. Hi-Hi S/G level or SI

3. Lo Lube Oil pressure at 4 psig l

4. 4KV bus under voltage 1

5. electrical overload 1

6. System Aux Transformer 142 trips

7. Generator 86-G1 (G2) or 86-G1B(G2B) relay trip

8. SI [5/8 at 0.3 each]

b. 1. Verify reactor trip

2. Verify turbine trip

3. Verify 4KV ESF busses energised

4. Check SI acturated.  ;

5. Verify ESF lineup. [0.3 each] '

REFERENCE ZION System Descriptions, Chapter 25a ZION E-0

~ "~ *

7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 30 RADIOLOGICAL CONTROL ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

ANSWER 7.07 (2.50)

a. 1. Check AC amps and/or output vcltage on inverter.

2. Check " power supply", lights on the RPS or Safeguards status lights.

3. Check any common 4 channel indication. [0.5 each]

b. 1. Open the inverter feed breaker.

2. Close dirty power feed breaker. [0.5 each]

REFERENCE ZION AOP-15 ANSWER 7.08 (2.00)

a. >= 5 psig or Radiation >= 10E5 R/hr.

b. When pressure decreases below 5 psig and evaluation of total intergrated dose by the TSC.

REFERENCE ZION E-0, p. 2, Rev. O ANSWER 7.09 (1.50)

1. Trip Reactor

2. Trip affected RCP(s)

3. Follow E-0 and monitor NC if all pumps are tripped.

REFERENCE ZION AOP-6, p. 3 ANSWER 7.10 (1.50)

a. Place PCV131 in manual BEFORE stopping the pump.

b. High enough to maintain >= 200 psid on the #1 seal or 375 psig.

c. PRT rupture disc.

[0.5 each part]

7. PROCEDURES - NORMAL. ABNORMAL EMER'3ENCY AND PAGE 31 RADIOLOGICAL CONTROL ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

REFERENCE ZION GOP-4 pp 38 & 42 ANSWER 7.11 (2.00)

a. Minimum S/D margin is not violated.

b. HI STEAM FLOW.

c. Prolonged idling may damage the turbine due to high moisture content in the steam at low powers.

d. Auto stop of the pump at ~ 600 RPM.

[0.5 each]

REFERENCE ZION GOP-2, pp 9, 10, 22, 26 ANSWER 7.12 (2.00)

4 of 5 required. [0.5 each]

! 1. Core exit TCs - stable or decreasing

2. RCS Subcooling - > 30 F

3. SG pressure - stable or decreasing ,

4. RCS hot leg temperature - stable or decreasing  !

5. RCS cold leg temperature - at approx. saturation temp for SG pressure .

REFERENCE ZICN E-0 FOLDOUT PAGE I ANSWER 7.13 (1.00)

May trip against backflow when other pumps are in operation ,

i REFERENCE l ZION GOP-1, p. 23 l l

. . . . _ . . . - . . . . _ . . . . . _ _ _ . . .__ . _ . _ _ _ . . _ _ _ . . _ _ _ . _ _ . ._ . 1

8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 32 ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

ANSWER 8.01 (1.00)

Shift Engineer AND Shift Forman.

REFERENCE ZION ZAP 3-51-4B ANSWER 8.02 (1.50)

+ 1. Inst. and removal record is kept as part of test or maint. procedure.

2. Test or maint. procedure record has specific sign off for reter-mination of each wire or jumper.

3. Test or maint. procedure is reviewed for completeness prior to returning system to operable status.

+ .J, N "M 3p h .

% N

• b A '" % k ** 7 fe* 4 REFERENCE ZION ZAP 3-51-4 ANSWER 8.03 (1.50)

a. TSEMo

b. No

c. 7 days (0.5 each]

REFERENCE ZION TS, 3.8, p. 165 ANSWER 8.04 (1.00)

Hot Shutdown within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> REFERENCE ZION TS Interpretations 79-1 ANSWER 8.05 (1.50)

Temporary Procedure change-intent of existing procedure SHALL not be changed.

Special-SHOULD be used when an intent change is necessary. .

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_._________________._____.______.___.__2.___..______._________~___________.5 ______._-_____._~'-_

^E__'_._I _' ' '

A

8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 33 l

ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

l REFERENCE '

ZION ZAP 5-51-4 ANSWER 8.06 (2.00)

a. 1. Immediately call out HP to quantify.

2. Pull grab sample without delay. [0.5 each]

b. One hour. /

EPIP 330-1 [0.4 each]

toe #Lsu W t'orset Emergency PhnaheaM) Plan.e J oR. gr REFERENCE O

ZION Standing Orders #236 4/10/84 EPIP 330-1 l

ANSWER 8.07 (2.00)

a. Uncontrolled rod withdrawal accident would be worse per Safety Analysis.

b. Technical Specifications allowed operation in an unanalysized area.

[1.0 each part]

REFERENCE ZION Standing Order #268 4/11/85 ANSWER 8.08 (2.00)

1. Severe weather conditions threaten safe transport.

2.A signficiant radiological hazard would be encountered.

3.There is a security threat occuring which would have an adverse impact on I the personnel while leaving the site.

4. Conditions similar to these in magnitude which in the opinion of the ,

Station Director would adversely affect the site personnel. '

REFERENCE i ZION EPIP 360-1 )

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8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 34 ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

I ANSWER 8.09 (2.00) l 1

1. Control of the "R" keys issued through his office

2. Maintenance of a log book / clipboard for each "R" key l

3. Accounting for each "R" key at end of shift l

4. Forwarding filled out log sheets to the Office Supervisor )

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REFERENCE ZION ZAP 5-51-15 ANSWER 8.10 (3.00) 1

a. Shift Engineer i

b. Shift Foreman l

c. Shift Foreman J

! d. Shift Engineer

e. Shift Foreman

f. Shift Engineer [0.5 each]

REFERENCE

,,.3 ION ZAP 1- 51-1, p 4-6.

ANSWER 8.11 (1.00) 1 This renders 1 FT 522 inoperable.

I Appropriate bistables per AOP must be tripped.

REFERENCE ZION Standing Order #272 i

ANSWER 8.12 (1.00) c REFERENCE SHNPP, TS, pp. 3/4 1-1 and B 3/4 1-1.

ZION TS, pp. 39-42 and 64,65.

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8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 35 ANSWERS -- ZION 1&2 -86/03/10-PICKER, B.

ANSWER 8.13 (1.00) b REFERENCE SHNPP, TS 3/4 2.1 ZION TS, p 46a-47.

ANSWER 8.14 (2.50) g g 7- ,

1. Two PORVs operable 0.2] or one PORV shall be open [0.2] or Par level shall be <25% and pressure <100 psig [0.2] (0.6)

2. Only one of three charging pumps operable. (0.5)

3. No safety injection pumps. (0.4)

4. No Accumulators. (0.4)

5. The first RCP shall not be started with associated SG temperature

>50 F above RCS temperature. (0.6)

REFERENCE ZION Technical Specifications pp 82, 83 ANSWER 8.15 (2.00)

a. 1. Standing Order Book

2. Forms on any release of Rad. Waste.

3. Plant Surviellance sheets.

4. Unit and Center Desk log books.

5. Out of Service Logs.

6. Jumper and Lifted Lead Log.

One week b.

Sent to Ops. Eng. )

[0.25 each response] i REFERENCE ZICN ZAP 10-52-3 l 1

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