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Requalification Exam Rept 50-219/86-10OL on 860509-15.Exam Results:All Reactor Operators & Senior Reactor Operators Passed Written & Operating Exams.Weaknesses Must Be Addressed During Next Training
	ML20203H378
Person / Time
Site:	Oyster Creek
Issue date:	07/22/1986
From:	Keller R, Kister H, Lange D; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20203H375	List: IR 05000219/1986010; ML20203H370;
References
	50-219-86-10OL, NUDOCS 8608040393
	Download: ML20203H378 (61)
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{{#Wiki_filter:, a U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Examination Report No.

50-219/86-10 Facility Docket No.

50-219 Facility License No.

DRP-16 Licensee: GPU Nuclear Corporation P.O. Box 388 Forked River, New Jersey 08731 Facility Name: Oyster Creek Nuclear Generating Station Examination Dates: Ma 9 thru Ma'r 15,

l' / f( PS Chief Examiner:

- ' dat(e - David J. Langh/ Rs' actor 9ngineer (Lead Examine Reviewed by: ) M ~///Ng Robert Keller', Chief, Projects Section 1C date 3-Approved by: ( date Hafry KisteMbief, Projects Branch No.1 Inspection Summary: On May 9, 1986, NRC administered six (6) Reactor Operator and eight (8) Senior Reactor Operator Written requalification examinations to members of your staff.

On M.y 13 thru 15, 1986, NRC administered four (4) Reactor Operator and four (4) Senior Reactor Operator ORAL (Operating) examinations to those members of your licensed staff who had taken the NRC written examination.

All Reactor Operators and Senior Reactor Operators passed the written and Operating Exams. Generic weaknesses have previously been discussed with members of your staff and are detailed in this report.

Individual weaknesses must be addressed during the next full cycle of requalification training.

8608040393 860722 PDR ADOCK 05000219 V PDR _

. , . REQUALIFICATION PROGRAM EVALUATION REPORT Facility: Oyster Creek . Examiner: Dave Lange, Lee Miller Date(s) of Evaluation: May 9 thru May 15, 1986 Areas Evaluated: x Written x Oral Simulator Examination Results: R0 SR0 Total Evaluation Pass / Fail Pass / Fail Pass / Fail (S, M or U) Written Examination 6/0 8/0 14/0 S Operating Examination Oral 4/0 4/0 8/0 S Simulator NA NA NA NA Evaluation of facility written examination grading Overall Program Evaluation Satisfactory x Marginal Unsatisfactory (List major deft-ciency areas with brief descriptive comments) Submitted: - Forwarded: Approved: hh Y Y % >- > Examind '

Section Chief f IfrYhch Chief 1.

Summary of NRC comments made during Exit Meeting.

A.

The Chief Examiner re-emphasized that an overall requalification program evaluation would be made once the written and operating i l examinations had been graded.

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B.

The Chief Examiner commented on the following generic weakness's noted from conducting the SRO operating examinations; 1) The SRO candidates were unfamiliar with the divisional Logic and power supply requirements for the ATWOS system.

' 2) The SRO candidates wre reluctant to make follow-up decisions concerning transients that required emergency classifications.

This hesitancy is probably due to the limited amount of time spent as the Emergency Director during pre planned drill exercises.

Increased emphasis must be placed on requalification training during simulator exercises to correct this deficiency.

C.

The Training material sent to the NRC for Preparation of the examina-tions, although adequate, was lacking in' substance to support the learning objective.

, The Chief Examiner also requested the handouts used for the Emer-gency Operating Procedure training be sent to Region I for use in the upcoming August replacement exams.

2.

Personnel Present at Exit Interview: NRC Personnel Dave Lange, Region I Chief Examiner Lee Miller, OLB, Headquarters Examiner Facility Personnel P. B. Fiedler - Vice Presdient and Director, Oyster Creek R. D. Fenton - Traning Manager D. McMillan - Training Supervisor W. V. Stewart - Operations Manager Attachments: 1.

Written Examination and Answer Key (RO) 2.

Written Examination and Answer Key (SRO) i -.. _. ,, _,

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,,, , . ~ . U. S. NUCLEAR REGULATORY CD'MMISSION ' REACTOR OPERATOR LICENSE EXAMINATION - FACILITY: ~ OYSTER CREEK . _________________________ REACTOR TYPE: BWR-GE2 _________________________ DATE ADMINISTERED: 86/05/09 _________________________ EXAMINER: MILLER, L.. _ _ _____________________ APPLICANT: ________________ _ .- INSTRUCTIONS TO APPLICANT: _______________ _____y_____te paper for Use separa 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 Stade 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 VALUE CATEGORY ________ ___________________________________ ___________ ________ ______ 10.00 25.00 1.

PRINCIPLES OF NUCLEAR PONER PLANT OPERATION, THERMODYNAMICS, ___________ _____--- ________ ______ HEAT TRANSFER AND FLUID FLOW ___I_0___ _'I_I_0 ________ 2.

PLANT DESIGN INCLUDING SAFETY 10 0 S0 AND EMERGENCY SYSTEMS _ ___________ ' T _ I i ________ 3.

INSTRUMENTS AND CONTROLS ___________ __ _ _ ___!__0__ _['5;_00 ________ 4.

PROCEDURES - NORMAL, ABNORMAL, 10 0 EMERGENCY AND RADIOLOGICAL _ _ ___________ CONTROL 40.00 100.00 TOTALS- . ________ ___________ ________ ______ . FINAL GRADE ________________;% All work done on this examination is my own. I have neither given nor received aid.

.( . ' APPLICANT'S SIGNATURE . . - l l > . _ - - __ _ _ .. - . -. ..

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PRINCIPLES OF-NUCLEAR POWER PLANT OPERATION, --- isEss557sKnici-sEAi isissFEE is5 FEDi5 FE5s ____________________________________________ . QUESTION 1.01 (1.50) - The reactor is operating at 75% power when a loss of power to How would the following parameters the EPR system occurs.

INITIALLY change and why? (0.50) A. Reactor pressure (0.50) B. Core flow (0.50) C. Reactor power 3, GUESTION 1.02 (2.00) For the following, choose the correct response in the parenthesis and explain your answer.

A. The reactor is operating at 100 % power and flow.

With a reduction in reactor power by driving control rods in and recire pump speeds remaining constant, core flow will (1.00) (increase, decrease or remain the same) B. The reactor is critical prior to void generation and reactor power is increase by control rod withdrawal. The core flow will (increase, decrease or remain the same) (1.00) GUESTION 1.03 (2.00) An ECP was calculated for a reactor startup to be done 20 hours ', ofter shutdown with an expected reactor temperature of 260 degrees F.

Explain how and why the actual critical position would vary from the calculated ECP under the following conditions.

(ANSWER EACH CONDITION SEPARATELY) (1.00) Start up does not commence until 25 hours after shutdown.

A.

B. The reactor temperature is 245 degrees F by the time the (1.00) reactor startup is commenced.

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PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, __ ~~~~iUEE5665AIE5C5,~UE T 5RIU5E5R dU6~ELU56"ELUE - ~ ~ ____________________________________________ __ - _ GUESTION 1.04 (1.00) Why is it necessary to density compensate the main steam flow indication? QUESTION 1.05 (1.50) Control rods toward the periphery of the core are normally expected to be low in rod worth.

During reactor startups shortly after a reactor scram from bigh power many plants hav,e experienced short. period conditions while withdrawing a peripheral control rod. Explain how this can occur? DUESTION 1.06 (1.00) The radition level in the vicinity of the HSIV's is normally very high due to the radioactivity caused by one particular isotope.

A. What is this isotope and why is it not present in any significant quantity in the Off-Gas holdup piping ? OUESTION 1.07 (1.00) As the fuel temperature increases the Doppler reactivity coefficient inserts negative reactivity in the core tending to shut the reactor down. Explain how the Doppler effect inserts negative reactivity as fuel temperature increases.

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PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS _ 2.

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~ . . - QUESTION 2.01 (1 00) If an operator causes a normal transfer of the Protective System P1 or P2 from its normal to its emergency power supply will this transfer cause any protective action? WHY or WHY NOT? QUESTION 2.02 (1.00) List two (2) methods by which an operator can increase the speed of a control rod drive mechanism from the CONTROL ROOM.

) GUESTIdN 2.03 (1.00) Below what power level is the Rod Worth Minimizer required to be operable and WHY ? QUESTION 2.04 (1.50) List two (2) ha:ards are involved with extended light load operation of a Diesel Generator and what operational restriction can minimize these hazards.

QUESTION 2 05 (1.50) If the main condenser and associated systems were absolutely AIR TIGHT would there be any need for the STEAh JET AIR EJECTORS during full power operation ? (Explain your answer) . QUESTION 2.06 (1.50) - Concerning the Generator Stator Cooling Water system: 1. List two (2) conditions that will cause a Turbine Governor (1.00)

'; )

Runbac.k.

h-+4../, fr 2. Will an automatic Reactor Scram occur upon receipt of a Governor runback signal? If yes, from what? If no, how could a subsequent (0.50) scram be prevented? , . (**xxx CATEGORY 02 CONTINUED'ON NEXT PAGE xxxxx) i -

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PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE

_____ _________________________________________________ _ M# QUESTION 2.07 (1.50) Once the Standby Liquid Control system has initiatedl list , six (6) control room indications the operator could use to verify that the Standby liquid control system is operating correctly and injecting into the reactor vessel.

-GUESTION 2.08 (1.00) Concerning the in-plant area radiation monitors (ARM) A.

What is the purpose for placing a source inside some of the -}, detectors? Do not c.onsider the installed check source which is installed ir, most area radiation monitors.

(0.50) B.

What kind of ARM indication would be indicative of a (0.50) detector gas leak ? . T . . (xxxxx END OF CATEGORY 02.marxx) . . e

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INSTRUMENTS AND CONTROLS _ ____________________________ _ .. - j QUESTION 3.01 (2.00) Is any manual rod motion possible in the event of a control rod drive timer switch malfunction? Explain your answer.

, Do not include a manual rod scram in this situation.

QUESTIDH 3.02 (1 50) Concerning the Reactor building to Torus Vacuum Breakers: List the condition which is required to cause the Vacuum A.

Breakers to AUTOMATICALLY open.

ASSUME the control (0.50) ,d, handswitch is in AUTO.

List two conditions which are required to cause an (0.50) B.

automatic isolation of the Vacuum Breakers.

In what position do the Vacuum Breakers fail on the C.

(0.50) loss of control air? QUESTION 3.03 (1 00) List two conditions which will result in a Recire pump motor generator scoop tube ' lock-up'. QUESTION 3.04 (1.50) For each of the following Oyster Creek Reactor Protection Scrams list the Scram Setpoints and the conditions that are required to . bypass the associated scram setpoints. (Indicate if the bypass '. is automatic) ~ 1. Scram Discharge volume 5. MSIV Closure 3. Shutdown on the Reactor Mode switch 4. Condenser Vacuum 5. Turbine Stop Valves . (xxxxx -CATEGORY 03 CONTINUED 'ON HEXT PAGE xxxxx) ! - .

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INSTRUMENTS AND CONTROLS - PAGE

" _____,______________________ _ .. _ - . QUESTION 3.05 (1.00) - ' jumpers are used to During a core fuel offload at Oyster Creek, defeat the one rod free movement permissive interlock for control ' rods in empty fuel cell locations.

What indication is available to warn the operator, in the control room, that a jumper is installed? QUESTION 3.06 (1.50) Match the following turbine control device which is normally ~ used to control the position of the turbine control valves evolutions.

witp the following turbine CONTROL DEVICE 1. EPR 2. Load limiter 3. Speed load changer 4. 42 stop valve internal bypass TURBINE EVOLUTION (0.50) A. Increasing turbine speed from 1100 - 1400 RPM.

B. Paralleling and picking up initial turbine load.

(0.50) (0.50) C. Load increase from 300 MWE to 400 MWE.

QUESTION 3.07 (1.50) trip signals and associated setpoints that will List five (5) . cause the.MSIV's to automatically isolate.

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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY,AND.

PAGE

~~~~ E656E665CAE~66 iR6E------ 7 ------ T ---- -- R____________________ ' _ ' . . QUESTION 4.01 (1.00) (attached) - Refer to the Heat Capacity Temperature Limit Curve What is the purpose of the curve? Include in your answer the specific phenomena it is used for protection against.

QUESTION 4.02 (1.00) EMG-3200.04, the In the Emergency Depressurization Procedure, is directed to open all ENRV's only if torus level is operator inches. What is the significance of 90 inches torus level above 90 in' relation to the dire'etion requiring the opening of all EMRV's? (Be specific.)

GUESTION 4.03 (1.50) The plant is operating at 85% of rated power with only four (4) recirc pumps operating. Then one (1) of the operating pumps trips. The non-operating loop is not isolated, but the pump is not available. Answer each part below separately.

(1.00) A. If the pump cannot be restarted, is a plant shutdown required and why? (0.5) B. If a fourth recire pump is placed in service shortly after the trip occurs, how could this effect the status of plant operation? ' ' . ' QUESTION 4 04 (1.50) ' What procedural limitations are invoked by Procedure 201.1, Approach to Criticality, if the Rod Worth Minimizer becomes inoperable before the first 12 control rods are withdrawn? , ' answer-to notifications and/or operator actions.

Note: limit your . l QUESTION 4.05 (1.00) ,

' is accompanied by a 6 rip of all recirc pumps, If a reactor scram what limitations are procedurally placed on both the recire pumps and the reactor by Procedure 203,2, ' Plant Cooldown from Hot Standby to Cold Shutdown'? ( Briefly explain.)

l CATEGORY 04 CONTINUE & QN NEXT PAGE xxxxx) (***** J ' . m l . . . ,ewr- -- y-w ,-v- , - - = ,yg y,- y.-,mn------------w - - - -, e---- ,

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PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE

~~~~ A656Lb5 5 AL E6NTRUL"- -~~~~~~~~~I~- ~~~ - R ____________________

. QUESTION 4.06 (1 50) The primary containment pressure. control section of EMG-3200.02 directs the operator to opetate the standby gas treatment and drywell purge systems only when the space being evacuated is below 212 de3rees F ( maximum non-condensible evacuation temperature ). Why is the action limit of 212 degrees F established for operation of these systems? QUESTkO,N 4.07 (1.50) List the five (5) entry conditions with their setpoints for the ' Containment Control' Emergency Operating Procedure.

QUESTION 4.08 (1.00) How can the operator determine by looking at a control room panel that an alarm circuit on an associated panel has been defeated? . t . _ (**xxx END OF CATEGORY 04 xxxxx) (xxxxxxxxxxxxx END OF EXAMINATION xxxxxxxxxxxxxxx) . ( -

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PRINCIPLES OF NUCLEAR POWER PLANT OPERATION: --- isEss557AisiEE-REAi iEAssFEE ARB FEUi5 FE5E _ ____________________________________________ ANSWERS -- OYSTER CREEK . . -86/05/09_-MILLER, L.

- ANSWER 1 01 (1 50) A. Increases (0.25)due to the control valves going shut in response to the HPR becoming the controlling signal. (0 25) Increases (0.25)due to the reduction in the void content of B. the two phase mi>:ture in the core. (0 25) C. Increases (0.25)due to the collapse of voids from the higher-( 0. 25 ) ,j pressure which adds positive reactivity.

REFERENCE Oyster Creek LP-73 Turbine Control System ANSWER 1.02 (2.00) A. Core flow increasese(0.5) due to the decrease in the total resistance to flow in the core (decrease in the two phase j flow).(0.5) B. Increase (0.5), increase the thermal driving head of the . .

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( 0. 5 )d f'e==. % M.e w $4 Jam km w.Md**~1 natural convection.

nieusa a se r cm.nge me4ca4t s. rempam=4 4te-s g A-J G** e 6 F% mit.. M (I.0) REFERENCE GE Thermodynamics Heat Transfer and Fluid Flow pg.9-45 to 48, 9-116 to 121 ANSWER 1.03 (2.00) A.

The actual critical position would be reached prior to the ECP (0.5) due to the decrease in Xenon concentration.(0.5) . B. - The actual critical position would be reached prior to the ECP (0.5) due to the positive reactivity added by the moder.ator temperature decrease.(0.5) REFERENCE Oyster Creek Reactor Theory LP-300 08 pg.13-16,37-39.

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PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE_.11 --- isiis557sisi5s-sEKi fiAssFEE As5 FEUi5 FE5s ____________________________________________ ARSWERS -- DYSTER CREEK-86/05/09-MILLER, L.

ANSWER 1.04 (1.00) 4La The measured change in pressure acrossAsteamlines is proportional to the volumetric flow rate. Volumetric flow rate is compensated with the fluid density to provide mass flow rate.

REFERENCE GE Thermodynamics Heat Transfer and Fluid Flow pg.7-13 and 7-81 > ANSWE'R - 1.05 (1.50) of High xenon concentrations formed in the high powered regions (0.5) during normal power operation tend to push the core the thermal neutron flux towards the periphery of the core.(0.5) This creates higher rod worths for the Peripherial rods. (0.5) REFERENCE Oyster Creek Reactor Theory chapter 8 pg. 61,62 ANSWER 1.06 (1.00) A.

N-16 (0.5) (produced by activation of' oxygen in the reactor water)(0.5) N-16 decays with a half life of 7 seconds so it is decayed by the time it leaves the hotwell.

(0.50) REFERENCE . ',CAF ANSWER - 1.07 (1.00)

As the fuel temperature increases the resonant peaks of theIU-238 absorbed and the(Fu-240) broaden which cause more neutrons to be during the slowing down process.

REFERENCE Oyster Creek Reactor Theory chapter 8 pg. 41-50 .

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ANSWERS-~OYSTERbREEK-86/05/09-MILLER L.

~ ' - . _ _ ANSWER 2.01 (1 00) - Yes(0.25), because the transfer is a dead bus transfer.(0.75) REFERENCE Oyster Creek LP-57 Vital Electrical Distribution ANSWER 2.02 (1.00) 1. By adjusting the motor-operated pressure control valve for ,j second stage pressure (drive water pressure).

(0.5) _ 2. By varying the flow control valve setpoint ( adjusting the system flow) (0.5) REFERENCE Oyster Creek LP-9 Control Rod Drive Hydraulics pg 12-14 ANSWER 2.03 (1.00) ,Af Less than or equal to 10 % reactor power (0.5) ,Rc Significant voiding at greater than 10% power makes a rod drop accident the reactivity addition from less severe during the transient.

(0.5) REFERENCE section 1 pg.2 Oyster Creek LP-49 Rod Worth Minimi=er \\, , ANSWER 2.04 (1.50) ! 1. The. accumulation of oil carbon deposits in the engine exhaust . ! could result in a fire.(0.5) 2. Extended light loading of the diesel generator can cause excessive wear on the turbocharger gear train. (0.5) The engine operation is restricted to a minimum of JAP % load .e ? cre k u.

to minimize these hazards. (0.5) .

REFERENCE Osyter Creek LP-65 Standby Diesel Generators PS.30 -{ . .

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PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS __ _______________________________________________________ . _ ANSWERS -- OYSTER CREEK ~ -86/05/09-MILLER, L.

~ - . , ANSWER 2.05 (1.50) Yes (0.5), To maintain the removal of non-condensable gases producedfromthedecompositionofwater,[activationproducts - and noble gases [ produced in the fuel and Ieaning into the coolant via cladding cracks. (1 0) . REFERENCE Oyster Creek LP-68 Air Extraction and Off gas pg.4 and 5 -- . . ANSWEk, 2 06 (1.50) a. High temperature >95 degree #'(0.5) 1.

b. Low pressure < 13 psig (0.5) 2. No.(0.25), Immediately reduce reactor recire flow to minimum. (0.25) REFERENCE Oyster Creek LP-54 Stator Cooling Phase Duct Cooling section 4 objective 18 and 19 ANSWER 2 07 (1.50) 1. Continuity lights so out 2. Alarm indication 3. RWCU isolates 4.

Decrease in reactor power ( . 5. Selected pump has red light indicating pump is running 6. SBLC pressure > reactor pressure ' l 7. SBLC tank level decreasing , ( any six of the seven at 0.25 each ) REFERENCE , Oyster Creek LP-53 section D f, b..a r, wv.% dw.> sent .

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_____.__________________________________________________ _ ANSWERS -- OYSTER CREEK-86/05/09-MILLER, L.

- . _ . ANSWER 2.08 (1 00) - A.

To provide a detector base level. CThis prevents a downscale alarm unless a circuit problem develops.3 (0.5) , ,._ _. _ s__ _..=__ ,- -, _ __ ' B.

Indication downscale Edue to the loss of gas amplification 3 (0.5) REFERENCE ' Oyster Creek LP-4 Area Radiation Monitors Section B CAF4, . - , . l . . e b

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. INSTRUMENTS AND CONTROLS __ - 3.

_. ____,_______________________ ANSWERS -- OYSTER CREEK-86/05/09-MILLER, L.

~ - - . . , ANSWER 3 01 (2.00) Yes (0.5) This is accomplished by positioning switch 4S3 to - EMERGENCY ROD IN, which bypasses the timer switch and its associated relays and applies power directly to the drive-in circuit until switch 433 is spring-returned to 0FF. (1.5) ' [ switch number is not required for full credit 3 REFERENCE .0yster Creek LP-45 Reactor Manual Control pg.9 b

ANSWER 3.02 (1.50) A. 0.5 psid Reacter Building to Torus B. Low low Reactor level or high drywell pressure C. Open (0.5 each) REFERENCE Oyster Creek LP-40 Primary Containment System'ps.11 ANSWER 3.03 (1.00) A.

Control air failure (0.5) B.

Loss of instrument Electrical (0.5) REFERENCE -, Oyster CreeR LP-48 Recire Flow Control section c.6

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3.

INSTRUMENTS AND CONTROLS __ --

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ANSWERS -- OYSTER CREEM-86/05/09-MILLER, L, ' _ -. ANSWER 3,04 (1.50) - Setpoint Bypass 1.

29 gallons vs Mode switch in refuel or shutdown and bypass switch in bypass "'**'

- 2._ <90 % open Mode switch not in run and <600 psis Reactor pressure 3.

Mode switch in Auto bypass 20 see after placing in - shutdown shutdown , .)4 '. * 23*Hg - Mode switch not in run and <600 psig Reactor pressure 5.

<90 % open Mode switch not in run and <600 psis Reactor pressure or 3 rd stage pressure < 40% power level (each setpoint 0.1 each complete bypass answer 0.2) REFERENCE Oyster Creek LP-46 Reactor Protection System, KR # 4.

TCR-828 0.37, BLO-7.

ANSWER 3.05 (1.00) The rod position indication backlighting will be ' red - green'. REFERENCE Oyster Creek Proc. 205.7.1 Control cell reloading _ , IANSWER 3 06 (1.50) A. 2 load limiter B. 3 Speed load changer C.

1 EPR (0.5 ea'ch) REFERENCE Oyster Creek LP-73 Turbine Control , i

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3.

INSTRUMENTS AND CONTROLS __ _____,______________________ ANSWERS -- OYSTER CREEK-86/05/09-MILLER, L.

. - _ . ANSWER 3.07 (1.50) - 1. Main steamline high radiation 10 x background (600 units) 2. Main Steamline low pressure Less than 850 psig and in run mode or IRM range 10 - 3. Main Steamline high flow 120% rated . 4. Main Steamline high temperature +50 degrees F above normal (180 F) 5. Reactor low low level 86 inches above TAF 4,0.2 each trip 0.1 e.ach complete setpoint) REFERENCE Cyster Creek LP-46 Reactor Protection System .

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- . /* n ' j?) . r,- 4 _ 4.hROCEDURES-NORMALe~ ABNORMAL, EMERGENCY AND PAGE

- MEK5i5E55iE AE 55i&E5E------------------------

Alt'S'WERE'- ' OYSTER CREEK-86/05/09-MILLERr L.

sy2____________________ ) ,. - ANSWER 4.01 (1 00) Prevents unstable steam condesation by depressurizing the A.

reactor while the torus has sufficient hear capacity. (1 0) B.

In order to prevent kyclic fatique) damage to the torus walls.

(0.5) . _ REFERENCE 3200.02 OsyyrCreekProcedureENG-Torus water temperature control pg. 14-16 Osytig Creek Handout 1202.-06 ANSWER 4.02 (1.00) At less than 90 inches torus levele steam from the EMRV downcomers will not be fully condensed by the water in the torus and torus pressure will increase significantly due to putting steam in the torus.

REFERENCE Oyster Creek Procedure EMG - 3200.04 RPV control emergency RPV depressurization CAF ANSWER 4.03 (1.50) A. A plant shutdown is required.(0.5) Plant operation with less than , four (4) recire loops in service is prohibited.

(0.5) i - B. Power operations may be resumed. (0.5) ' REFERENCE f Oyster Creek Procedure 20000-ABN-3200.02 Recirevlation pump trip step 3.2 ' . ANSWER 4.04 (1.50) ' (./) / -1. Stop rod movement (4r54 ' ' - N , 1.4. Notify the Manager - Plant operations and the Core Manager i., ,u. . . g- . a - -:. out .s.

. 4-j 3) s y.. g,,_ 3 g.

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

._. . . , , , , . . , ' ' s .. , , 4.' PROCEDURES - NORMAL, ABNORMAL, ENi.RGENCY AND PAGE

i RA65 EU656AL 66NTR6L~~~~~~~~~~~~I~~~~~~~~~~ ~ ~~~~ ____________________ ANSWERS -- OYSTER CREEK-86/05/09-MILLER, L.

' REFERENCE i - Oyster Creek Procedure 201.1 Approach to Criticality pg 7 ANSWER 4.05 (1.00) The recite pumps should not be started until the reactor has been depressurized to atmospheric pressure. (shutdown and cooled down)(0.5) - The likitations are provided to prevent thermal over-stresses in in,the bottom head region of the vessel. (0.5) REFERENCE - Oyster Creek Procedure 203.2 Plant Cooldown from Hot Standby to Cold Shutdown pg 4 ANSWER 4.06 (1.50) At drywell temperatures greater than 212 degrees Fe steam can replace the non-condensibles being evacuated and maintain a high containment pressure.(1.5) REFERENCE Oyster Creek Procedure EMG 3200.02 Primary Containment Control Handout 1202.08 Primary Containment Pressure Control pg.5 , i ANSWER 4.07 (1.5,0) l 1. Torus' water temperature above 90 degrees F . , l 2. DW temperature above 150 degrees F - 3. DW pressure above 2 0 psis j 4. Torus level above +10.9' , j 5. Torus level below -1.9' i (0.3 each) REFERENCE Oyster Creek Procedure EMG-3200.02 Containment Control Handout for EMG-3200.02 , l ~ I

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- . . . . .. . 4.

PROCEDURES - NORMAL, ABNORMAL-EMERGENCY AND PAGE

~~~~~~~~~~~~~~~~~~~~~~~~ RA656EU556AL"65UTRUL ~~~~ _________.__________ _ ANSWERS -- OYSTER CREEK _ -86/05/09-MILLER, L.

, ANSWER 4.08 (1 00) The defeated alarm will be clearly marked with an orange information tag.

REFERENCE Oyster Creek Procedure 108 Equipment Control . 4- . . . - t . e e a h . O e . - ( - J -

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EQUATION SHEET .{ g { {() ' f = ma v = s/t Cycle efficiency n (Net work out)/(Energy in) ,

s = V t + 1/2 at ' w = mg o

, , ' E- = mc A = IN A=Ae' _ 'KE = 1/2 mv - a = (Vf - V,)/t n PE = mgn ~ w = e/t-1 = an2/t1/2 = 0.693/t1/2 ~ . Vf = V, + at 1/2*" " U* M * d

- g,y 3p nD - A= ((t1/2) * (*b33

4E = 931 am - -Ex a = V,yA, ,

. . Q = mCpat I=Ie'# 6 = UAaT n I = I,10-*/ M i P,wr = W ah . TVL = 1.3/u f 5Ur(t) HVL = -0.693/u P = P 10 P=Pe* SCR = S/(1 - K,ff) o SUR = 25.06/T CR = S/(1 - K,ffx) x SUR = 26a/t* + (s - o)T CR)(1 - K,ff)) = CR (I - eff2)

T = (t*/o) + [(a - oV Io] M = 1/(1 - K,ff) = CR /CR, j M = (1 - K,ffg)/(1 - K,ff)) T = 1/(o - s) SOM = ( - K,ff)/K,ff T = (s - o)/(Io) tw = 10 secone o = (Keff-l)/K,ff * Meff/K,ff I = 0.1 seconds-I , . o.= [(t*/(T K,ff)] + [a,ff (1 + IT)] / I)d) = I d P = (reV)/(3 x 1010) I d) 2,2 2 gd j

2 R/hr = (0.5 CE)/d (meters) I = eN '.R/hr = 6 CE/d2 (f,,g) . '. Miscellaneous Conversions Water Parameters

1 curie = 3.7 x 10 dps 1 gal. = 8.345 lbm.

1 kg = 2.21 lbm 1 gal. = 3.78 liters 1 hp = 2.54 x 103 Btu /hr 1 ftd = 7.48. gal.

.i 6 5tu/hr

' 1 nw = 3.41 x 10 . ' Density = 62.4 lbg/ft Density = 1 gm/c:9 .' lin = 2.54 cm

F = 9/5"C + 32 Heat of vaporization = 97'l Stu/lom
C = 5/9 (*F-32)

Heat of fusion = 144 Btu / ibm 1 Atm = 14.7 osi = 29.9 in. Hg.

- 1 BTU = 778 ft-lbf-1 ft. H O = 0'.4335 lbf/in.

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j ~l ' ! , S & . . . - . .. Table 1.

Saturated Steam: Temperature Table

' Ahs Press.

3pecific Volume Enthalpy Entropy Sat.

Sat.

Temp Temp tb per Sat.

Iatir SqIn.

liquid Ivap Vapor Li uid Evap Vapor liquid Evap Vapor Fahr ,' t _ i._. vg g h eg hg s, seg se V . l.

p 't t j 32 8 0 08859 0 016022 33047 3304.7 0.0179 1075.5 1075.5 0.0000 2.1873 2.1873 32.0 i l 34 0 0 09600 0 016021 3061 9 3061.9 1.996 1014.4 1076.4 .0.0041 2.1762 2.1802 34.9 l 38 8 010395 0 016020 2839 0 2839 0 4.008 1073.2 1077.2 0.0081 2.1651 2.1732 36.e

3e s a11749 0 016019 76341 7634.2 6.018 1072.1 1C78.1 0.0122 2.1541 2.1663 30.8 ! 40 0 1.17163 0 016019 2445 8 2445.8 8.027 1071.0 1079.0 0.0162 2.1432 L1594 40.0 l 47 8 0 13143 0 016019 2272 4 / 2272.4 10.035 1069.8 1079.9 0.0202 2.1325 2.1527 C.* i 44.s - 0 14192 0 016019 2ll2 8 2112.8 12.041 1068.7 1080.7 0.0242 2.1217 2.1459 44.8 l 48 0 0 15314 0 016020 1965.7 19657 14.047 1067.6 1081.6 0.0282 2.1111 2.1393 48.9 ? 4e e 016514 001 A021 In30 0 1810 0 16.051 1066.4 1082.5 0.032I 2.1006 2.1327 48.9 . . l 59 8 017796 0 016023 1704 8 1704 8 18.054 1065.3 1083.4 0.0361 2.0901 2.1262 50.0 , i Sie 019165 0 016024 1589.2 1589.2 20.057 1064.2 1984.2 0.0400 2.0798 2.1197 52.0 ! 54.9 - 0 20625 0 016026 1482.4 1482.4 22.058 1063.1 1085.1 0.0439 2.0695 2.1134 54.8 ' , ! 58 8 0 22183 0016028 1383 6 1383.6 24.059 1061.9 1086.0 0.0478 2.0593 2.1070 56.5

j 58 0 0.23843 0016031 17972 1292.2 26.060 1960.8 1086.9 0.0516 2.0491 2.1000 58.8

l . II O O25611 0 016033 1201.6 1707.6 28.060 1059.7 1087.7 0.0555 2.0391 2.0946 88.8 6 7.0 ... 0 27494 0 016036 1129.2 1129.2 30.059 1058.5 1088.6 0.0593 2.0291 2.0885 62.0 l .

, j $4 8 0 29497 0 016039 1056 5 1056 5 32.058 1057.4 1089.5 0.0632 2.0192 20824 64.0 i' . 34.056 1956.3 1090.4 0.0670 2.0094 2.0764 68.8

$18 0 31626 0 016043 989.0 989.1 ' 36.054 1055.2 1091.2 0.0708 1.9996 2.0704 68.8 ' II I O31889 0 016046.

976 5 926 5 I 10 9 0 36292 0 016050 ~ 868 3 868.4 38.052 .1054.0 1092.1 0.0745 1.9900 2.0645 78.9 , - l 12 0 0 38844 0 016054 814 3 514.3 40.049.

1052.9 1093.0 0.0783 1.9804 2.0587 72.5 ! ' 14 I 041550 0 016058 1641 1641 42.046 1051.8 1093.8 0.0821 1.9700 2.0529 74.9 75 I O44420 0 016063 7I74 117.4 44.043 10507 1094.7 0.0858 1.9614 2.0472 78.9 re s 0 414r,I u ni6ur,1 61.1 R 673 9 46.040 1049.5 1095.6 0.0895 1.9520 2.0415 78.8 ' I III 0 50683 0 016072 633.3 633 3 48.037 1048.4 1096.4 0.0932 1.9426 2.0559 80.0 , II 8 054093 0 016077 595 5 595 5 50.033 1047 3 1097.3 0.0969 1.9334 2.0303 02.0 ' 84 9 0 57702 0016082 560 3 560 3 52.029 1046.1 1098.2 0.l006 1.9242 2.0248 84.0 18 0 0 61518 0 016087 2275 527.5 54.026 1045.0 1099.0 0.1043 1.915I 2.0193 86 0 ' es e 06s551 0 016093 4%8 496 8 56.022 1043.9 1099.9 0.1079 1.9060 2.0139 80.0 99 0 0 69813 0016099 468I 4681 58018 1042.7 1100.8 C.lilS 1.8970 2.0086 90.9 . I!l 014313 0016105 441 3 441 3 60 014 1041.6 1101 6 0.1152 1.8881-2.0033 92.0 ' 94 0 0 79062 0 016111 416 3 416.3 62.010 1040.5 1802 5 0.1184 1.8792 1.9980 94.0 i - > 98 9 0 84077 0 016117 392 8 392.9 64.006 1039.3 1103.3 0 1224 1.8704 1.9928 95.8 i ' l L, 98 8 0 893 % 0 016173 310 9 370 9 66 003 1038 2 1104 2 012G0 1.8617 1.9876-98.e ' ' , - ...

' ', ' - * , _ ' , , ' j . ) P Ahs P ess.

Specific vnlume Enthalpy Entropy i ' " j Temp tb per Sal.. Sal.

Sal.

Sat.

Sal.

Temp '

'

j iahi Sq in t ielulil ' Ivan Vapor Lic vid Ivap Yapor lliivit! Evap Vapor Fahr _ s

h is h s, sig s I l i p vi v ig, v g a f.

IetI O94924 0.016130 350.4 3504 67.999 1037.1 1105.1 0.1295 1.8530 1.9825 100.0 l le!I i00789 0 016137 331 1 331 1 69.995 1035.9 1105.9 0.1331 1.8444 1.9775 102.8 184 I I 06 % 5 0 016144 313 1 3131 11.992 1034.8 1106.8 0.1366 1.8358 I.9725 104.0 , l les I i1341 0 016151 296 16 29618 13.99 1033.6 1107.6 0.1402 1.8??3 1.9675 1Et IIII 1.2030 0 016158 280 28 780 30 75.98 1032.5 1108.5 0.1437 1.8184 1.9626 Int ' \\ i 119.9 1.2750 0 016165 26537 26539 71.98 1031.4 1109.3 01472 1.8105 1.9577 110.0 l 112 8 13505 0 016173 251 37 25138 79.98 1030.2 1110.2 0.1507 1.8021 1.9528 112.0 114e i4299 0 016180 238 21 23822 81.97 1029I 1111.0 0.1542 1.7938 1.9440 114.0 11I e 15133 0 016188 225 84 225 85 83 97 1021.9 1111.9 0.1577 1.1856 1.9433 115.0. l lie e 16009 0 016196 ?I4 70 f 214.?! 85.97 1026.8 1112.1 0.1611 1.7774 1.9386 118.0 i 129 0 I6927 0 016204 203 25 203 26 87.97 1025 6 1113.6 0.1646 1.7693 1.9339 128.8 i 1228 17891 0 016213 192.94 19255 89.96 1024.5 1114.4 0.1680 1.7613 1.9293 122.0

1248 I8901 0 016221 18323 183 24 91.% 1023.3 1115.3 0.1715 1.7533 1.9247 124.5 128 9 I9959 0 016229 174 08 174 09 93.96 1022.2 1I16.1 0.1749 1.7453 1.9202 IMS ! IIII 2.1068 0 016738 16545 165.47 95.% 1021.0 1117.0 0.1783 1.7374 1.9157 128.9 . - , l 198.8 - 2 2230 0 016247 15732 157 33 97.96 1019.8 1117.8 0.1817 1.1295 1.9182 12e j 1)78 2.3445 0 018256 149.64 149.66 99.95 1018.7 1118.6 0.1851 1.7217 I.9068 132.9 134 9 24711 0 016265 14240 142.41 101.95 1017.5 1119.5 0.1884 1.1140 1.9024 Int - l 138 0 2 6047 0 016214 13555 135 57 103.95 1016.4 1120.3 0.1918 1.7063' l.0980 1E0 l 138 8 2 7438 0016784 179 n9 129 11 105.95 1015 2 1121.1 0.1951 I.6986 I.8937 1Et ' let I ~ "~ 28892 0 016293 122 98 123 00 107.95 1014.0 1122.0 0.1985 1.6910 1.8895 148.8

! 142 8 3 0411 0 016303 11721 117 22 109.95 1012.9 1122.8 0.2018 I.6534 I.8852 142.9

1448 3 1997 0 016312 Ill 74 Ill 16 111.95 1011.7 1123.6 0.205I 1.6759 I.8810 144.9 Its t 3 3653 0 016322 106 58 106.59 1.13.95 1010.5 1124.5 0.2084 I.6644 1.8769 148.0

I4e e 3 5181 0 016312 10168 101.70 115.95 1009.3 1125.3 0.2117 I.6610 1.87M 148.9 f Ils e 3 1884 0 016343 9705 97.07 117.95 1000 2 1826.1 0.2150 1.6536 1.0686' 198.9 ' 151 8 3 9065 0 016353 9266 92 68 119.95 1001.0 1126.9 0.2183 1.6463 it.8646 152.s 1548 4 1025 0 016363 I850 88 52 121.95 11005.8 1127.7 0.2216 I.6390 1.8606 Int

~ 4 3068 0 016374 84 56 84 57 123.95 1004.6 1128.6 0.2248 1.6318 1.8566 150.0 156 8 ] 15e e 4 5197 0016.184 30 82 A0 83. 125.96 1003.4 1129.4 0.2281 1.6245 1.8526 1E0 ! ] Iet t 4 7414 0 016395 7727 11 29 127.96 1002.2 1130.2 0.23I3 I.6174 1.8487 IES '

161 8 4.9722 0 016406 13 90 13 92 129.96 1001.0 1131.0 0.2345 1.6103 1.8448 182.0 j 164 8 52124 0016411 10 10 10.12 131.96 999.8 1131.8 0.2377 1.6032 1.8409 104.0

Ise I b4623 0 016428 6767 6768 133.97 998.6 1132.6 0.2409 1.596I 1.837I Int i ist I 5 1723 0016440 64.18 64.80 135.97 997.4 1133.4 0.2441 1.5492 I.8333 1Es

i Ilt I 5 9926 0 016451 62 04 62 06 137.97 996.2 1134.2 0.2473 1.5822 I.8295 1ES

I!!I 6 2736 0018463 59 43 5945 139.98 995.0 1135.0 0.2505 1.5753 1.6258 - 172.0

174 8 6 5656 0 016474 56 95 56 97 141.98 993.8 1135.8 0.2537 1.5684 1.8221 174.0 till 6 8690 0 016486 54 59 54.61 143 99 992.6 1136.6 0.2568 1.5616. l.8184 170.0 Ill e 71840 0 016499 5735 57.36 145.99 991.4 1137.4 0.2600 1.5548 1.8147 178.e Q / ., ,

. _ _ - - _ ._- _ _ _ _ -

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.

..

~

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Ahs Press Specilic Volume [nthalpy Entropy ' i Temp lb per Sal ' Sat Sal.

Sal.

Sat.

Temp i rahr sqIn.

' ligmil [v,ap Vapor Liquid Evap Vapor liquid Evan Vapor l'ahr hg h si sig sg i j i p vi vig vg he i g I Ist t 7.5ti0 0016510 5021 50 22 148.00 990.2 1138.2 01631 'I.5480 1.8111 198.4 ! 182.8 7 850

0016522 44 172 18.189 150 01 989.0 1139.0 0.2662 1.5413 1.8075 102.9

' 134 8 ' I203 0016534 46 232 46 249 152.01 987.8 1839.8 0.2694 1.5346. 1.8040 184.9 l 13e g 8 568 0 016547 44 383 44.400 154 02 986.5 1140.5 0.2725 1.5279 1.8004 106.8 - - - IIe s 8 941 0 016559 42.671 42 638 156.03 985.3 1141.3 0.2756 1.5213 13%9 100.8 l i igeg 9340 0.016512 40 94 [ 40 957 158 04 984.1.'1142.1 0.2787' l.5148 11934 198.8 192 0 9147 0016585 39331 39 354 160.05 982.8 1142.9 0.2818 1.5082 13900 192.0 ! ! 134.0 10.168 0 016598 37 808 37.024 162.05 981.6. 1143.7 0'.2848 1.5017 13865 194.0 l 138.0 10 605 0016611 36 348 36 364 164.06 980.4 1144.4 0.2479 3.4952-1.7831 196.8 Itt.g 11 058 0 016674 34 954 34.970 166.08 979.1 1145.2 0.2910 1.4888 IJ798 198.8 ! .

~ 11764 206.8 ! !$g 3 11 526 0016637 33.622 33.639 168.09 977.9 1146.0 0.2940 1.4824 284 3. 12 512 * 0016664 31 135 31151 172.11 9 75.4 1147.5 0.3001 I.4697 11698 284.8 , ! 298 9 13 568 0 016691 28 862 28 818 176.14 972.8 1149.0 0J061 1.4571'.I1632 298.9 ~ ' '

! fili 14 696 0 016119 26 182 26 199 180.11 970.3 1150.5 0.3121 1.4447 13568 212.0 ! JIs e 15 9n1 0 016741 74 R18 24 894 184.20 967.8 1152.0 03181 1.4323.13505 216.8 i

I' 0.8 17.186 0.016175 23 131 23.148 188.23 965.2 1153.4 0.3241. l.4201.1J442'. 229.8 l

-224.9 "~ 18 556-0016805 21 529 21 545 192.27 962.6 1154.9 OJ300 I.4081' IJ300 224.0 . ' ' 228.5 20 015 .0016834 20 056 20 013 196.31 900.0 1156 3 0J359 I.3961 * IJ320 - 225.0 232.0 21 567 0016864 18701 18718 200.35 957.4 1157.8 0.3417 1.3842.11260 232.0 22s e 23 216 0 016895 17 454 17 411 204.40 954.8 1159.2 03476 IJ725 1J201 233.8 249.8 24 968 0016926 le304 16 321 208.45 952.1 1160.6 0.3533 ~1.3609 'l1842 240.0 , { 244.8 26 876 0016958 15 243 15 260 212.50 949.5 1162.0 03591 l.3494 13085 244.3

248 8 28 196 0016990 14 264 14 281 216.56 946.8 1153.4 03649 ~ I.3379A IJ028 248.9 i 252.0 0 883 0011012 13 358 13 375 220 62 944.1 11643 0.3706 13266 'I.6972 252.8

255.0 31 091 0el1055 17 570 12 538 224 69 941.4 1166.1 103763 1.3154 1.6987 256.8 i l 200 0 35 427 0017089 11145 11362 ' 22816 938.6 1167.4 0.3819 13093 i1.6862 268.9 284 3 31 894-0017123 11.025 11.042 232.83 935.9 11683 03876 1.2933 16808 264.0 ' '

198 9 40 500 0.017151 10 358 10 375 236.91 933.1 1170 0 03932 1.2823 1.6755 268.0 212.8 43 249 0 017193' 9138 9 755 240.99 ' 930.3 1871 3 03987 1.2715 1.6702 272.s ' 218.8 46 141 0 031278., 9 162 9 181) 245 08 927.5 1112.5 04043 1.2607 1.6650 276.8 , , 2:s s 49 200 0.01f264. '8 627 8644 249.1).

924.6 1173.8 0.4098 1.2501 1.6599 289.9 284 J 52 414 ODI130.81280 8.1453 2533-9211 1175.0 0.4154 I.2395 1.6548 284.0 . 200 0 55 795 0 01734 7 6634. 7.6007 251.4 918.8 1176.2 0,4208 1.2290.l.6498 ~ 288.0 . 792.0 59 350 0 01738 72301 7.2415 261.5 915 9 1877.4 0.4263 1.2186 1.6449 292.0 3" 298 9 63 084-0 01741 6R759 6.8433 265.6 913.0 1I78.6 0.4317 1.2082 l6400 296.9 , .

- - - . J - , .

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.,, , ! Abs l'ress.

Specific Yolume Enthalpy - Entropy

Temp tbper Sal.

Sal.

Sat.

Temp Fahr SqIn.

Ilquit! .[vap Vapor 1.1 wid Evsp Vapor liquid Evsp Vapor Fahr V8 I h ig h s, s,, s, t I p VI vig g .

f 30s O 67005 0 01745 6 4483 6 4658 269.7 910 0 1179.7 0.4372 1.1979 1.6351 300.e

_ i ^ 394 I 11 119 001749 6 0955 6 1130 273.8 901.0 1180.9 0.4426-1.1877 1.6303 304.0 390 g 15 433 001153 5 1655 5 7830 278 0 904.0 1182.0 0.4479 1.1776 -l.6256 300.0 ' 312 0 79 953 0 01757 54566 54142 2821 901.0 1183.1 0.4533 'l.1676 1.6209 312.8

. 316.8 318 I 84 688 0 01761 5 1613 51849 286.3 891.9 1184.I 0.4586 1.1576 1.616: Mt9 89643 001766 4 8961 4 9138 290.4 894.8 1185.2 0.4F40 1.1477 1.6116 329.8 j 374 I 94 826 001770 4 6418 4 6595 294.6 891.6 1186.2 0.4692 1.1378 't.6071 324.8 ! 178 9 100 245 0 01774 4 4030 4 4208 298.7 888 5 1881.2 0.4745 1.1280 1.6025 378.9 i j ! 132 0 105 901 0 0l179 4.1788 4 1966 302.9 885 3 1188.2 0.4798 1.1183 1.5981 337.8 111 870 0 01783 3.96Al 3 9859 307.1 882.1 1189.1 0.4850 1.1086 s.5936 335 0 l 336 8 . 348 0 117.992 0 01187 3 7699 3 7878 3113 878 8 1190.1 0.4902 1.0990 1.5892 348.0 j.

3440 124 430 0 01192 3 5834 3 6013 315.5 875.5 1191.0 0.4954 1.0894 1.5849 344.0 > 348 9 131.142, 001791 3 4078 3 4258 319 7 872.2 1191.1 0.5006 1.0799 1.5806 348.8 ,

352 O 138 138 001001 3 2423 3 2603 323 9 868.9 1192.7 0.5058 1.0705 1.5763 352.0

354 e . 145 474 0Olan6 3 0R63 3.1044 328.1 865 5 1193.6 0.5110.l.0611 1.5121 355.5 . I 3ee 8 153.010 0 01811 2 9392 29573 332.3 862.1 1194.4 0.5161 1.0517 1.5678 380.e I 384 e 160 993 0 01816 28002 2 8184 336 5 858.6 1195.2 0.5212 1.0424 1.5637 364.0 ) 3ss.e 169 !!3 0 01821 2 6691 2 6813 340.8 855.1 1195.9 0.5263 1.0332 1.5595 36s.e ' 372 0 177 648 0 01826 2 5451 2 5633 345.0 851.6 1896.1 0.5314 1.0240 1.5554 372.0 ' 310's - ' ~ 186 517-0 01811 2 4219 2 4462 349 3 848.1 1197.4 0.5365 1.0148 I.5513 376.0 '

300 0 195 129 0.01836 2.3170 2 3353 353 6 844.5 1198.0 0.5416 'I.0057 1.5473 380.0 ' 354.8 205 294 0 01842 2 2120 2 2304 357.9 840.8 1198.7 0.5466 0.9966 1.5432 3s4.0 300 0 215 220 0 01847 2.ll26 2 1311 362.2 837.2 Il99.3 0.5516 0.9876 1.5392 3s8.e 312 0 225 516 0 01853 2.0184 2.0369 366.5 833.4 1199.9 0.5567 0.9786 1.5352 392.0 j 398.0 236 193 001858 1.979! l9477 370 8 829.7 1200.4 0.5617 0.9696-1,5313 396.0 ! 400.0 247259 00lb64 I8444 I8630 375.1 825.9 1201.0 0.5667 0.9607 1.5274 400.0 i 404.0 258125 0 01870 17640 11827 379.4 822.0 1201.5 0.5717 0.9518 1.5234 484.0

400 I 270 600 0 0l075 I6877 11064 3818 818.2 1201.9 0.5766 0.9429 1.5195 40s.8

4129 282 894 0 01881 16152 16340 388.1 814.2 1202.4 0.5816 0.9341 1.5157 412.8 i 418 e 295 617 0 011187 15461 15651 392.5 810.2 1202.8 0.5866 0.9253 1.5118 416.0 ' 428 9 308 700 0 01894 1.4808 14997 396.9 006.2 1203.1 0.5915 0.9165 I.5000 429.8 424 8 322 391 001900 1.4184 1.4374 401.3 802.2 1203.5 0.5964 0.9077 1.5042 424.0 i 471 I 336 463 0 01906 13591 1.3182 405.7 198.0 1203.7 0.6014 0.8990 1.5004 428.8 . 437 8 351 00 0 01913 i.30266 1.32179 410.1 793.9 1204.0 0.6063 0.8903 1.4966 432.s ] 436 e 366 03 001919 I24RR7 126R06 414 6 789.7 1204.2 0.6112 0.8816 1.4928 436.9 ) 448.9 301 54 0 01926 1.19761 121687 419.0 785.4 1204.4 0.6161 0.8729 1.48") 440.0 ' 4448 397 56 0 01933 1.14874 1.16806 423.5 781.1 1204.6 0.6210 0.8643 14853

444.0 448I 414 09 001940 1.10712 1.12152 428.0 716.7 1204.7 0.6259 0.8557 1.4815 448.9 l

!!!b !N! !!b l!) N!$ ! ' '- ,

_ _ _ _ _ - _ - _ _ _ _. __ _ _ _ _ _ _ _ _ _ - _ _ __ _ _ _ __ f. ' ', ,, - , , , . - ' ' i, j

. , - v

l ' ~~~~~ Alis Mess Specific Volume Enthalpy intropy Temp lb per Sal Sat Sat.

Sat.

Sa't.- Temp i i i Iain SnIn liquirl Ivan Vapor liquid Evap Vapor Liquid Evap Vap0r - Fahr . I p vg v ig, vg hg h rg h 5, 5,g 5, I g est e 466 87 0 01961 0 97463 0 99424 441.5 163.2 1204.8 0.6405 0.8299 -1.4704 488.9 ' j 454 I 485 56 0 01969 0 93588 0 95557 446.1 758.6 1204.7 0.6454 0.8213 1.4667 444.9 i 468 O 504 83 001916 0R98R$ 091862 450.7 754.0 1204.6 0.6502 0.8127 1.4629 468.9

4J2 8 524 67 0019R4 0 86345 0 88329 455 2 749.3 1204.5 0.6551 0.8042 1.4592 472.9 elle 54511 0n1997 0 R7954 OR4950 459.9 744.5 1204.3 0.6599 '01956 1.4555 4 76.8 l 4Il 9 566 15 0 02000 0 19716 / 0 81717 464.5 739.6 1204.1 0.6648 01871 1.4518 488.9

414 8 58181 0 02009 0 76613 0.18622 469.1 '7341 1203.8 0.6696 01785 1.4481 484.9 . 411 I 610 10 0 07011 013641 0 15658 473 8 '7291 1203.5 0.6745 01700 1.4444 488.9 ' i 497 8 633 03 0 07026 0 10194 0 12820 478.5 724 6 1203.1 0.6793 01614 1.4407 492.0 496 8 6% El un/014 (16RnrA 0 10100 483.2 719 5 1202.7 O.6842 01528 l.4370 496.9 ' ] l 598.8 580 86 0 02043 0 65448 0 67492 487.9 114.3 1202.2 0.6890. 01443 1.4333 588.5

594 8 105.18 0 07053 052938 0 64991 492.7 709.0 12013 0.6939 01357 1.4296 504.9 ' 500 0 - 731 40 0 02062 0 60530 0 62592 497.5 7033 1201.1 0.6987 01271-1.4258 500.8 , ' 517 I 157.72 0 02012 0 58218 0 60289 502.3 698 2 1200.5 01036 01185 1.4221 512.9 51s t 7R415 0 n7081 0 % 991 0 58019 507.1 6923 1899.8 03085 0.1099 1.4183 516.9 578 8 812 53 0 02091 0 53864 0 55956 512.0 687.0 1199.0 01133 01013 1.4146 529.9 574 0 841 04 0.02102 0 51814 0 53916 516.9 681.3 1198.2 0.7182 0.6926 1.4108 524.0 , .. . 570 0 870 31 0 02112 0 49843 0 51955 521.8 675.5 1197.3 01231 0.6839 1.4070 528.0 ,

5328 900 34 0 02123 0 41947 0.50010 526.8 669.6 1196.4 0,7280 0.6752 1.4032 532.8

51s e 931.11 n07134 0 46173 0 48757 5313 663.6 1195.4 01329 0.6665 1.3993 536.0 540.5 96279 0 02146 644367 046513 536.8 657.5 1194.3 01378 0.6577 1.3954 500.9 544 8 995 22 002151 0 4?617 044834 541.8 651.3 1193.1 03427 0.6489 l.3915 544.0 548 I 1028 49 0 02169 0 41048 043217 546.9 645.0 1191.9 01476 0.6400 3.3876 548.9 5570 .3062.59 0 02182 039479 0 41660 552.0 638.5 1190.6 03525 0.6311..l.3837 552.0

556 I 1091 55 007194 0 31966 0.40150 557.2 632.0 1189.2 01575 0.6222 1.3797 556.9 l 500.0 1133 38 0 02207 0 36507 038714 562.4 625 3 1187J 01625 0.6132 1.3757 588.9 584 8 1110 10 0 02221 0 35099 037320 567.6 618.5 1186.1 03674 0.4041 1.3716 564.8

! 568.8 120712 C O2235 0 33141 0.35975 572.9 611.5 1184.5 03125 0.5950 1.3675 568.8 ' 577.8 1246 26 0 02249 037429 0 34678 578.3 604.5 1182.7 07715 0.5859 1.3634 572.9 Sig.I 1285 74 0 02764 0 31167 0 33426 5831 597.2 1180.9 0.7825 0.5766, 1.3592 578.9 I 500.8 1326 17 0 02279 0 29937 0.32216 589.1 589.9 1179.0 01876 0.5673 1.3550' 588.8 - 584 0 13677 0 02295 0 28153 0.31048 594.6 582.4 1176.9 03927 0.5500 1.3507 504.0 500.9 1410 0 0 02311 0 21600 0 29919 600.1 574.7 1174.8 01978 0.5485 1.3464 588.0

' i 597.0 1453 3 0 02328 0 26499 028827 605.7 566.8 1172.6 0.8030 0.5390. 1.3420 592.8 " 500 0 14918 0 07345 0?5425 0.27770 611.4 558.8 1170.2 0.8082 0.5293 1.3375 598 9 ! - - - - - -- - - -

s > . - . . ... . . .. , , .* { .;,c - ' , , i.

. l Ahs Press.

Specific Volume Enthalpy Entropy ' Sal.

~ . remp tb pei Sat.

Set.

Sat.

Sal.

Sat.

Temp ' ' fah SqIn liquid Evap Vapor lic vid Evap Yapor liquid. Evap Vapor Fahr , t J vfg,,,,,__,V 1f hg h i s, sig s i g I p V

see s 1543 2 0 02364 0 74384 0 26747 817.1 550.6 1167J 0.8134 0.5196 1.3330 les.s . set 8 15891 0C2382 0 23314 0 25757 622.9 542.2 1165.1 0.8187 0.5097 I.3284 564.8.

800 8 1637 3 0.02402 0 22394 0.24796 628.8 533.6 1162.4 0.8240 0.4997 13234 688.9 et7 e 16861 0 02422 0 ?!442 0 23865 634.8 5243 1159.5 0.8294 0.4896 1.3190 612.0 818 5 1735 9 0 07444 0 20516 0 22960 640.8 515.6 1156.4 0.8348, 0.4794 13141 lit.t

01961! 0.22081

646.9 506.3 1153.2 0.8403 0.4689 1.3092 829.9

520 8, 1786.9 002466 l 874 3 1839 0 0 02489 0.18737 0.21226 653.1 4?6.6 1149.8 0.8458 0.4583 1.3041 824.0 - ! 828 s - 1892 4 0 02514 011880 0.20394 659.5 486J 1146.1 0.8514 0.4414 I.2988 828.9 832 8 1947 0 0 02539 0 17044 0.19583 665.9 476.4 1142.2 0.8571 0.4364 I;2934 532.8

83s 3 2007R 0 07566 0 16726 0.18792 672.4 4653 1138.I 0.8628 0.4251 1.2879 ' 434.9 840 h 2059 9 0.02595 0 15427 0.18021 679.1 454.6 1133.7 0.8686 0.4134 1.2821 648.8 544.8 2118 3 0 02625 0 14644 0.17269 685.9 443.1 1129.0 0.8746 0.4015 1.2761 844.s ' 548 8 2118 1 0.02657 013810 0 16534 692.9 431.1 1124.0 0.8806 0J893 1.2699 548.9 852 8 2239 2 0.02691 0 13124 0.15816 700.0 4181 11181 0.8868 03767 12634 652.0 - 858.5 23017.

0.02778 0173R7 0.15115 707.4 4051 1113.1 0.8931 03637 1.2567 654.9 002768 0 11663 0.14431 714.9 392.1 1107.0 0.8995 03502 11490 tot.t 889.8 - -- 2365 7 ' es4.s 2431.1 0.02811 010947 0 13757 722.9 377J 1100.6 0.9064 OJ361 1.2425 564.0 - 888.8 24981 0 02858 010229 013087 731.5 362.1 1093.5 0.9137 032I0 1.2347 668.0.

IT2 8 2566 6 0 02911 0 09514 0.12424 740.2 3453 1085.9 0.9212 OJ054 1.2266 572.0 878.8 2636R 0 02970 0 08799 C.11769 749.2 328.5 ~ 1077.6 0.9287, 0.2892 1.2179 576.8 88f.8 21086 0.03037 0 04080 0.11117 758.5 310.1 1968.5 0.9365 0.2720 1.2005 ' 000.0 - 1.1984 584.0 884.0 27821 0.03114 0 01349 0 10463 768.2 290.2 1058.4 ~0.9447 0.2537f 888 9 28574 0.03204 0 06595 0.09799 778.8 268.2 1047.0 0.9535 0.2337.l.1872 688.8 0.9634 0.2110 1.1744 8s2.8 802.0 2934 5 0.03313 0 05797 0 09110 790.5 243.1 1033.6 - 998.s 3013 4 0.03455 0 04916 0.08371 804.4 212.8 1017.2 0.9749 0.1841 1.1591 SM.8 , 70s.8 3094 3 0.03662 0 03857 0.07519 822.4 1723 995.2 0.9901 0.1490 1.1390 788.9 - ' 182.5 3135 5 0.03824 0.03173 0.06997 835.0 1441 9791 1.0006 0.1246 1.1252 I 782.8 ' ' 194.8 3171.2 0 04108 0 02192 0.06300 854.2 102.0 956.2 1.0169 0.0876 1.1046 704.0 795 9 3198 3 0 04427 001304 0.05130 873.0 61.4 934.4 . 1.0329 0.0527 1.0856 705.0.

105.47* 37082 0 05075 0 00000 0.05078 906.0 0.0 906.0 1.06I2 0.0000 1.0612 705.47'

. ' !

Critical temperature

. -] g

___ - . . . . ! .

. , l , .!

. Table 2: Saturated Steam: Pressure Table i i l Specifidfolum7 Enthalpy Entropy ~ ' "~ ! Abs Press.

Temp Sal Sat.

Sat.

Sal.

. Abs Press.

i IblSO In.

Fahr liquid tvan Vapor Lic vid Evap Vapoi liquid Evap Vapor LblSq In.

' p t v, y,, v, 1g hgg h sg s gg s .P g g

i .. _ . -. ...... ... _. l 808865 32 018 0 016022 3302 4 3302 4 0.0003 1075.5 1075.5 0.0000 2.1872 2.1872 9.88885 ~ Id 9 25 59 323 00lr032 1235 5 1235 5 27.382 1060.1 1087.4 0.0542 2.0425 2.0967 9.25 l 9 59 79 586 0 016011 641.5 641.5 47.623 1048.6 1096.3 0.0925 1.9416 2.0370 8.54 .

I8 101 14 0016136 331 59 333 60 69.13 10361 1105.8 0.1326 1.8455 1.9781 1.8 S9 162 24 0016401 13 515 13 532 130 20 1000.9 1131,1 0.2349 1.6094 I.8443 5.0 , III 193 21 0 016592 38404 38.420 161.26 982.1 1143.3 0.2836 1.5043 1.7879 18.8 ! l 14 598 21200 0 016119 26 182 /26 199 180.17 970.3 1150.5 0.3121 1.4447 1.1568 14.598

15 e, 21.1 03 oolt,776 76714 26 290 181.21 969.7 1150.9 0.3137 1.4415 l.7552 15.0 l 20 0 227 96 0 015834 20.070 20.087 196.27 9601 1156.3 0.3358 1.3962 1.7320 20.8

38 s 250 34 0 011009 13 1766 13 7436 218.9 945.2 1164.1 0.3682 1.3313 1.6995 30.9 i 4e 8 267 25 0011151 .J 4794 10.4965 236.1 933.6 1169.8 0.3921 1.2844 1.6765 48.8

Se e 28102 0 017274 8 4961 8.5140 250.2 923.9 1174.1 0.4112 1.2474 1.6586 50.0 i le 8 - 29211 0 011383 1.1562 7.1736 262.2 915.4 1177.6 0.4273 1.2167 !.6440 84.9 j Is t 302.93 0 017482 6 1875 62050 272.7 907.8 1180.6 0.4411 1.1905 1.6316 10.5 i es e 312 04 0 011573 5 4536 5.4111 282.1 900.9 IIB?.I 0.4534 1.1675 1.6208 88.0 i et e 320 28 o011659 4 8179 4 8953 290.7 894.6 1185.3 0.4643 1.1470 1.6113 99.9 l ' 199 8 327.82 0.017740 4 4133 4 4310 298.5 888.6 1187.2 0.4743 1.1284 1.6027 188.8 lit 0 - 334 79 001182 4 0306 4 0484 305.8 883.1 1188.9 0.4834 1.1115 1.5950 110.8 < . 128 I 341 21 001181 3 1097 3.7215 312.6 877.8 1190.4 0.4919 1.0960 1.5879 129.8 l 130 8 347.33 0 01796 3 4364 3 4544 319.0 872.8 1191.7 0.4998 1.0815 1.5813 138.8 } tes e 353 04 001803 3 2010 3 2190 325.0 868.0 1193.0 0.5071 1.0681 1.5752 140.0 l 150 0 358 43 0 0l809 79958 3 0139 310.6 863.4 1894.1 0.5141 1.0554 1.5695 150.0 j 158 8 363 55 0U1815

2 8155 2 8336 336.1 8590 1195.1 0.5206 1.0435 1.5641 Ile e i

lig I 368 42 0 0182I 2 6556 2 6138 341.2 854.8 1196.0 0.5269 1.0322 1.5591 178.I i IIIs 313 08 0 01827 2 5129 25312' 346.2 850.7 1196.9 0.5328 1.0215 / 1.5543 1ss.s ' j Ice e 37153 0 014.13 2 3841 2 4030 350.9 8461 1197.6 0.5384 1.0113 I.5498 190 0 ! 29e 0 38180 001839 22689 2 2873 355.5 842.8 1198.3 0.5438 1.0016 1.5454 res.e i 218 I 385 91 001844 216313 218211 359.9 839.1 1199.0 0.5490 0.9923 1.5413 Ils e ' 228 8 389 88 0 01850 206/19 2.08629 364.2 835.4 Il99.6 0.5540 0.9834 1.5374 2Fe.e ' 239 3 393 10 0 01855 191991 1.99846 368.3 831.8 1200.1 0.5588 0.9748 1.5336 23e e 240 8 391 39 001860 199909 I91769 372.3 828.4 1200.6 0.5634 0.9665 1.5299 240.0 250 0 400 91 0 0l865 IO2452 1.84317 376.1 825.0 1201.1 0.5679 0.9585 1.5264 254.0

!se s 404 44 001810 115548 I11418 379.9 821.6 1201.5 0.5722 0.9508 1.5230 250.9 2is e 401 80 001875 169131 1.71013 383.6 818.3 1201.9 0.5764 0.9433 1.5197 270.0 .

> 100 I til 01 0 01880 163169 I65049 '387.1 815.1 1202.3 i 0.5805 0.9361 1.5166 200.8 d, 19e e 414 25 0nl8RS-151591 1.59482 390.6 8I2.0 1202.6 0.5844 0.9291 1.5135 29e.e

l 300 0 417 35 0 01889 1.52384 154274 394.0 808.9 1202.9 0.5882 0.9223 1.5105 30s.8 { 350 0 43113 001912 130642 1.32554 409.8 194.2 1204.0 0.6059 0.8909 1.4968 358.8 400 8 444 60 0 n19.14 1.14I67 1.16095 424.2 780 4 1204.6 0.6217 0.8630 1.4847 4ee e

_ ___

. -. Specilic Volvene lnihalpy Entropy Abs Pam Temp Sai Sal.

Sat.

Abs Press.

, , iP lb/Sq In Fabi liquiel fynp Vapor liquid Ivap Vnpor liquid Evap Vapor.

lblSq In.

l I V: ia 't hg h h s, s,g 's, p V ig g 3 ?$ p 458 8 456 28 0 01954 101224 103119 437.3 167.5 1204.8 0.6360 0.8378 1.4738 459.0 500 0 461 01 001915 0 90187 0 92162 449.5 755.1 1204J 0 6490 0.8148 1.4639 50s.9 , 558 8 416 94 001994 0 8/183 0 84117 460.9 143.3 1204.3 0.6611 03936 1.4547 558.8 600 0 486 20 0 020l3 0 14907 ' 0 16915 411 ] 732 0 12033 0 6723 01738 14461 ses.g ! 050 8 494 89 0 07032 0 68811 0 10843 481.9' 720.9 1202.8 0.6828 01552 1.4381 550.3 , 100 4 503 08 0 07n50 0 63505 0 65556 (491.6J 710 2 1201.8 0.6928 03377 1.4304 106.0 j.

l-750 8 510 84 0 07069 0 58880 0 60949 500.9 699 8 12003 01022 01210 1.4232 750.9 F IOO O 518 21 0 0/081 0 54809 0 56896 509.8 689 6 1199 4 01111 03051 1.4163 800.8 j 850 8 525 24 0 02105 0 51191 0 53302 518.4 619.5 1198.0 03197 0.6899 1.4096 850 0

900 I 53I 95 0 07173 0 41968 050091 526.7 6697 1196.4 03279 0.6753 1.4032 90s s ! 958 I 538 39 0 07141 0 45064 0 47205 5343 660 0 11943 03358 0.6612 1.3970 958 e ! 1000 0 544 58 0 07159 0 42436 0,34596 542.6 650.4 1192.9 01434 0.6476' l.3910 1900.9 i 1958 I 550 53 0 02111 0 40041 042224 550.1 640.9 1191.0 01507 0.6344 1.3851 1950 g j lige I 55628 0 02195 0 31863 040058 557.5 631.5 1189.1 03578 0.6216 1.3194 1180.0 '

1158 I 561 82 0 02214 0 35859 0 38013 564 8 622.2 1187.0 03647 0.6091 1.3738 1150.8 I 1788 8 56119 11072.12 0 14013 0 36245 571.9 613 0 1184.8 01714 0.5%9 1.3683 1200.9 i 17589 512 38 0 02250 0 32306 0 34556 578.8 603 8 1182.6 01780 0.5850 1:3630 1250.0 i l 1300 0 57142 0 07269 0 30722 ' 0 32991 585 6 594.6 1180.2 03843 0 5733 1.3577 13es.s l 1350 0 582 32 0 07288 0 29250 0 31531 592.3 585 4 1177.8 01906 0.5620 1.3525 135g e

1409 8 58101 0 02101 0 21811 0 30118 598 8.

516 5 1175.3 03966 0.5507 1.3474 1486.9 ! 1450I 591 70 0 02327 0 26584 028911 605.3 567.4 1172.5 0.8026 0.5397 13423 I45s.9 1508 8 596 20 0 02346 0 25312 0 21119 6113 558 4 1170.1 0.8085 '0.5288 1.3373 1500.8 618 0 549.4 1167.4 0.8142 0.5182 1.3324 1556 0 1550I 600 59 0 07366 0 24235 0 26601 - l.

' 1600 0 -- 604 81 00/187 023159 0 25545 624 2 540.3 1164.5 0.8199 0.5076-1 3274 Isse s , 1656 8 609 05 0 07407 0 22143 024551 630.4 531.3 1161.6 0.8254 0.4971 13225 isse.s - 110e e 613 13 0 07428 021118 023601 636.5 522.2 1158.6 0.8309 0.4861 13176 1700.0 , 1759 I 611.12 0 02450 0 20283 0 2??13 642.5 513.1 1155.6 0.8363 0.4765 1.3128 1750.0 1983 8 821 02 0 02472 OI9390 0 21861 648.5 503.8 1852.3 0.8417 0.4662 1.3079 1890.0 , l 18558 624 83 0 02495 0 18558 0 21052 654.5 494.6 1149.0 0.8470 0.4561 1.3030 1850.0 - i 1980 8 628 56 0 02517 0 11761 0 20218 660.4 485.2 1145.6 0.8522 0.4459 1.2941 190s.9

1958 I 632 22 0 02541 0 16999 0 19540 666.3 415.8 1142.0 0 8574 0.4358 A 1.2931 19508 2005I 635 80 0 07565 0 16266 0 18831 672.1 466.2 1838.3 0.8625 0.4256 1.2881 2898.8 l 2109 3 642 16 00/615 014885 011501 683 8 4463 1,I30.5 0.8727 0.4053 12780 210s.8

! 2780 8 64945 0 07669 0 13603 0 16772 695 5 '4267 1I22.2 08828 0.3848 1.2676 2200.8 i 2300 0 655 89 0 0/121 0 12406 0 15113 107.2 406.0 1113.2 0 8929 0.3640 1.2569 230s.9 i 7400 e 667II n0/190 0117RI O14016 719 0 3R4.8 1103.7 0.9031 0.3430 1.2460 2400.8 i 0 02859 0 10209 9 13088 7313 361.6 1093.3 0.9139 0.3206 1.2345 2588.9 ! 2500 0 66R 11 - j 2000 I 613 91 002938 0 091/2 C12110 144.5 3376 1082.0 0 9247 0.2977 1.2225 2680 0 ! 2iOO I 619 53 0 03029 0 08165 011194 157.3 312 3 1069.7 0.9356 0.2741 11997 2798.8 20008 684 96 0 03134 0 01111 0 10305 110 7 2851 1055.8 0.9468 - 0.2491 1.1958 2000.0 ' l 2900 0 690 22 0037G2 0 06158 0 09420 785.I 2547 1039.8 0.9588 0.2215 1.1803 23es.e j 30008 695 33 0 03428 0 05013 0 08500 801.8 218 4 1020.3 0.9728 0.1891 .I.1619 3ess.O 3100 0 70028 0 0ERI 003111 0 01452 824.0 169 3 993.3 0.9914 0.1460 .l.1373 3100.8 l 3200 5 105 08 0 04412 0 01191 0 05663 815.5 56.1 931.6 1.0351 0.0482 1.0832 370s.8 i 3700 I* 70541 0 0'.n 1R 000000 0 05018 906.0

906.0 1.0612 0.0000 1.0612 3298J' ' f , q

- -~,

'~ lFICbn7 C./7 $ . _ ~ . . t - I NUCLEAR REGULATURY COMMISSION .U.

S.

SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: Di3TER. CREEK

_-__--__-__-----

REACTOR TYPE: BWR-GE2

_--_-__-_--__________

DATE ADMINISTERED: 86/05/09 _-_-_---_-____--___-_-_-- EXAMINER: LANGE, D.

- - APPLICANT: _J . kp__________________ - INSTRUCTIONS 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

question 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 CATEG0F:Y VALUE TOTAL SCORE VALUE CATEGORY

-------------------_---------_-----

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

14 5 23 7 ________ 5.

THEORY OF NUCLEAR POWER PLANT -- l 0_-_ _-_!_7_ ___________ OPERATION, FLUIDS, AND THERMODYNAMICS !_ __ _ 1 3 ___________ ________ 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION ,. _ C ___I_5___ ___1_' ________ 7.

PROCEDURES - NORMAL, ABNORMAL, 13 7 25 8 EMERGENCY AND RADIOLOGICAL ___________ CONTROL ___I_0--- _- I_9 ________ 8.

ADMINISTRATIVE PROCEDURES, 15 0 24 5 CONDITIONS, AND LIMITATIONS -__---_____ TOTALS 61.00 100 00 _-____-_ --_-__--_-- ______-_ -____- FINAL GRADE _________________% ~ . I have neither All work done on this examination is my own.

given not received aid.

~ '

_---_-_---

_---_-----GNATURE APPLICANT'S SI

_ \\ . . - - - - - -. _, _., - -, _,,,, - - - - - - - -,., _,.,.,., -,., -., _ - -. -. -., - _..,,.., - - - -- . . -- - -- ,--..._,..-.-_.-..,.e ..,,,_ , _ -, -,, _.,, -,, -,,--

. . '

. . . . 5.

THEORY OF NUCLEAR POWER PLAN:T OPERATION, FLUIDS, AND PAGE

_____ _ ______________;________________________ ______________ QUESTION 5.01 (2.50) The Reactor has been at 100 % p*ower for 90 days when a Reactor Scram occurs.

10 min.

The temperature is maintained a't 540 des.Feand the Shutdown Margin Describe what happens to the Shutdown after the scram is 1% delta K/K . Margin during the next three.(3) days if the temperature is maintained at (2.50) 540 degF.

GUESTION 5 02 (2.25) At Oyster Creek Fuel thermal safety limits are established for ~ the purpose of protecting fuel clad integrity during accident or steady state operation.

a. For the 8x8 fuel, what is the LHGR limitrand why was it (1.00) specifically established ? 6. The actual LHGR of a fuel rod is dependent upon what (0.75) three (3) variables ? c. Why was the (H)APLHGR thermal limit established ? (0.50) QUESTION 5.03 (3.00) Indicate whether the following will INCREASE or DECREASE reactivity during operation AND briefly EXPLAIN why, a. Moderator temperature increases while below saturation (.75) , temperature.

(.75) . 6.

Fuel temperature increases.

L(.75) , c. Loss of a feedwater heater.

' (.75) d. A sudden reduction in reactor primary system pressure.

GUESTION 5.04 (2.00) Concerning the tern NPSH i How would you account for the fact that the NPSH 100 % a recirculation pump with the plant operating at is different for ? Include in your answer at which power level will power versus 4 % power the NPSH be higher, the operating conditions that are affecting the change, (2 00) and tne reason why.

!

(xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx) , i . I .. _. - . - - - -. _, . -..,., -,. - _, -. _ ., _.,. - -.. - -., -. -,,. - -,., - - - -

"

. , ., , . - 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, ann PAGE

----.

- --

___-_---__---- QUESTION 5.05 (1 75) - With the plant in cold shutdodn, conditions in the reactor should be maintained to prevent thermal s'tratification of the reactor water level and inadvertent repressurization. List two (2) operating methods, briefly explaining how they are used, to maintain this cold stable (1.75) condition.

GUESTION 5.06 (1.00) Why is it necessary to density compensate the main steam flow - indication? OUESTION 5.07 (1.00) E:< plain WHY chloride ion concentration limits for reactor coolant are lower during start up than at full power operation.

QUESTION 5.08 (1.00) Describe how pulling a shallow-shaping rod will sometimes result in a slight reduction in reactor power level. (Reverse power effect) . c I ' l l

. (xxxxx END OF CATEGORY 05 xxxxx) . i - t _ ,,.+wy . .av.._ .___,._3-- w-- -. -,. - - - - -,,- - w. - - - -,. - - - - - - -.,-w- - -. - - - - y w g .

. .- . ~ 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE

______._________________________ _____________________ , GUESTION 6.01 , (2.00) Concerning the Isolation Condenser: s. Why would it be necessary to. manually remove A and E Recirculation pumps from service after a manual initiation of the Isol. Cond? (0.75) b. All automatic isolation valves for the Isol. Cond. can be manually over-riden,(opened or closed), regardless of what is bein3 called for by the (0.50) logic circuitry ( TRUE or FALSE ) . c. Why is there a caution that directs you to maintain Reactor water level (0.75) below 180' above TAF? . . QUESTION 6.02 (2.50) During the 4:00PM-12:00 MID shift you experience a total loss of all 125 VDC power; a.For each of the following components listed below, indicate whether there is a loss of position indication, control power, and/or reset capability.

NOTEi If more than one condition applies, indicate so.

(2.50) 1. Shutdown cooling system isolation valves.

2. Main Steam Isolation Valves.

3. Isolation Condenser, isolation valves.

4. All 4160 V and 460 V breakers . 5.

EMRV's . QUESTION 6.03 (3.00) Concerning the Reactor Level and Feedwater Control System * ' (Reactor Power 100 %, steady state) t For the following loss of signal failures to the Feedwater Control System, indicate in which direction reactor water level will respond (increase or decrease), the reason for the change, and the probable automatic action (3.00) that will occur with no operator action.

a. Feedwater Flow l b. Steam Flow I c. Reactor Water Level d. Steam Pressure e. Feedwater Temperature - . (xxxxx CATEGORY 06 CONTINUED ON NEXT PAGE'*xxxx) _ --- --

. . ' ., . _ . . 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE

________________________________7_____________________ QUESTION 6.04 (2.25) Concerning the Standby Diesel Generators: a. Explain the automatic sequen.tial actions of the Diesel Generator for the following two conditions: liait answer to operation of D/G only.

' 1. Inadvertant LOCA signal, immediately clearing, with no loss of off-(0.75).

site power.

2. Loss of off-site power followed by a LOCA signal, with the~ Core Spray system loads already picked up, and then additional loading causes the Diesel Generator to stall and output breaker to trip.(0.75) b. If an inadvertant false start signal is received by the D/G, how can ' it be manually shut down? Would you want to do this immediately? (0.75) ( YES or NO and WHY ) QUESTION 6.05 (1.00) Operating Procedure 4 308, ( Emergency Core Cooling Operation ), provides direction on controlling Core Spray injection to maintain reactor water level.

a. What action must be taken to manually take control of the Core Spray (0.50) System? b. Once manual control of the Core Spray system has been taken, what C/S components are used to control injection to the vessel? (0.50) GUESTION 6.06 (1.50) For each of the following Oyster Creek Reactor Protection Scramse, L, list the Scram Setpoints and the conditions t hat are pequired to bypass the associateo scram setpoints. (Indicate if the bypass is automatic) 1.

Scram Discharge volume 2. MSIV Closure j 3. Shutdown on the Reactor Mode switch 4. Condenser Vacuum 5. Turbine Stop Valves t

' . (xxxxx CATEGORY 06 CONTINUED ON NEXT PAGE zuuzz) l l ~ .

l _. -.. _ _. ._ - -.. - ..- . . .. .. _.

l . . - .. ,. . . . _ ' 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE

____________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _, QUESTION 6.07 (1.50) . On a loss of Instrument / Service Air, e:< plain how the following valves / components will fall. (,d e., Open, Close, Fail as is ) ' c. Hotwell Hakeup Valves b. CRD Flow Control - c.

Isolation Condenser Makeup.

. d.

MSIV's e. Feedwater Regulating Valves _ f.

Recire M/G set (0.25 each) , '. . GUESTION 6.08 (2.00) 1. While at 100% power, an operator holds the control for Main Stop valve 42 Internal Bypass in the Fast Lower (close) position.

Which of the following best describes how the Turbine Stop Valves (0.50) will respond? a. 42 internal bypass and ti, 42, 43 and 44 stop valves will close.

41, 43 and 44 b. 42 internal bypass closes and 42 stop valve closes.

stop valves will remain open.

c. 42 internal bypass closes. The four main stop valves will remain open.

d. The four main stop valves will remain open and the 42 internal bypass will remain open.

' .(1.5) 2. Which of the following turbine control devices: . 1.

EPR 2. Load Limiter 3. Speed load changer - - 4.

42 stop valve-internal bypass is normally used to control the position of the turbine control valves during the following turbine evolutions? a. Increasing turbine speed from 1100-1400 RPM.

b. Paralleling and picking up initial turbine load.

c. Load increase from 300 MWE to 400 MWE.

. . _ > _ ~ (xxxxx END OF CATEGORY 06 xxxxx) ~ . __ . - O n - -. - - -, _ - ---- - - - - - -,. - ,-n---.----..-, ,, -,, -.. ,,. ,. -. . -. -, - ,, - -.. -,. --.. - - - -

. . . .. .. , - . 7.

PROCEDURES - NORhAL, ABNORhAL, EMERGENCY AND PAGE

R D5ULUGICEL C UTRUL'~~~~~~~I~~~~~~~~~~~~~~~ ~ ~~~~ ____________________ . QUESTION 7.01 (2.00) According to procedure ABN-320'O.13,(Response to Loss of All 125 VDC), a caution e::ists, that directs you to either maintain the plant in a steady irrespective of the Tech-ctate condition or enter a prompt reactor scram, nical Specification requirements. What two (2) specific criter.is are used to make this determination ? - QUESTION 7.02 (2.50) the Emergency Dir-; According to procedure EPIP-2 ( Emergency Direction ), octor has certain responsibilities and/or authorities that may NOT be del-List five (5) of these osated to a subordinate during emergency conditions.

(2.50) octions that may not be delegated.

GUESTION 7.03 (2.75) Concerning procedure ABN-3200.01,(Control Room Evacuation): o. Following a control room evacuation, how is reactor level controlled? (0.75) (Include location and components.)

room, an attempt should made to Being forced to evacuate the control b. bring the plant to a safe shutdown condition before leaving. List eight (8) operator actions / verifications to be attempted prior to(2.00) leaving.

'c QUESTION 7.04 (1.00) i Refer to the Neat Capacity Temperature Limit Curve (attached) What is the purpose of the curve? (Include in your answer the specific phenomena it is used for protection against.)

l l l l , (xxxxx CATEGORY 07 CONTINUED ON NEXT PAGE

- - - - )

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r - . . .. . -. -... _ - - - _ _ _ _ -- - - - -. . .

. _ _ - __, ... _ _ . . . . , . . , PAGE

7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND R 656[655Cd[~CEUTEUE~~~~~~~~I~~~~~~'~~~~~~~~ ~~~~

- QUESTION 7'.05 (1.50)' The primary containment pressure control section of EMG-3200.02 directs the operator to operate the standby gas treatment and drywell purge systems cnly when the space being evacuated is below 212 degrees F ( makimum non-condensible evacuation . temperature ). Why is the limit action of 212 degrees F < established for operation of these systems? _ . QUESTION 7.06 (1 00) . ' . (EMG-01) attached, the operator In step RC/P-2 of the RPV Control Procedure is directed to remain in this step and not proceed to cooling down the RPV unless the reactor is shutdown. Why is the operator directed to remain in this step under this condition? ! l QUESTION 7.07 (2 00) Entry into procedure EMG-3200.05 ' Steam Cooling' will occur only if all possible injection to the RPV becomes unavailable. If during steam ' cooling, RPV pressure drops below 700 psige the procedure directs the operator to emergency depressurize. What is significant about 700 psig i cnd why is RPV depressurization required when pressure drops below (2.00) 700 psig? .

2-QUESTION 7.08 (1.50) If the Oyster Creek unit is operating at 80% power with only four , recirc pumps running and one (1) of the operating recire pumps tripsi' s required in regard to plant operation if the pump cannot s. What i i be restarted immediately AND why is this required? , is placed in service shortly after the b. If a fourth recirc pump ' how would.this affect the status of plant operation? l trip occurse - , l , a (mmmma CATEGORY 07 CONTINUED ON NEXT PAGE'ammmm) - - . e ~ l -

l - .--.-__.__m._..__..._-~,.,,.____..m.,,,-_ . _. _. _,. _,.., _., _ - -, - - - _ _.,. _ _, -, _ _,. -,, _,. ~ - _ _ _ _..

. .. . , . - . _ . 7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE

~~~~ A5i5E55iCAE 55srR5E------- M ---- T-------- R____________________ v% . QUESTION 7.09 (1.50) - Provide the following action l'evels or limits for plant operation.

' . Maximum permitted heatup or cooldown rate.

a.b. Maximum AT for recirc pump startup.

' c. Maximum AP for open MSIVs'. d. Minimum reactor water temperature for criticality.

e. Maximum power level for Mechanical Vacuus pump operation.

_ f. Maximum AT between the reactor head metal and head flange.

.

. . . t C.

i (***** END OF CATEGORY 07 ****x) . I

. - e

-m . -- _ e - -. -. _ _. _.. _.,, _ .. _ _. _,. _. _... _ _ _.. _ _ _ _ _.,. _ _. _. _ -,.. - _ _. _ _ , _, _, _. _ _..., _,, - . - - ~ _.. _ _ _ _. _ _ - _,

- . ' . .. . . - . 8.

ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE

__________________________________________________________ OUESTION 8 01 (2.00) ( Operability Requirements) Concerning the Limiting Condition For Operation os described in Technical Specifications. When a system, subsystem, train, component or device is determined to be incperable solely because its emer-gency power source is inoperable, or solely because its normal power source for the purpose of satisfying it may be considered operable is inoperable, its applicable Limiting Condition for Oper~ation only if the requirements of two (2) conditions are satisfied. LIST THESE TWO CONDITIONS.

QUESTION 8.02 (3.00) . Concerning Technical Specifications---> Safety Limits and Spec,ifications: _4 c. What is the basis for keeping a minimum of two (2) Recire Loop suction valves and their associated discharge valves open at all times? (1.00) 6. During all modes of reactor operation with irradiated fuel in the vessel, what is the minimum water level to be maintained, and how ses this level compare to the lowest point at which water level (1 00) can be monitored? c. What are the Tech. Spec. requirements for SRh operability during a core alteration involving the removal of one (1) control rod ? (1.00) DUESTION B.03 (2.00) List two conditions under which radioactive liquid effluent can be released to the discharge canal if the process radiation monitor is inoperative.

- QUESTION 8.04 (2.00) C a. In accordance with 107 ' Procedure Control", state the actions that should be taken if an operator, while performing an evolution, (0.50) finds he cannot follow the procedure as written.

b. A ' temporary change' to a procedure requires the signature of a and a CSS. What do the signatures of both ' cognizant supervisor' individuals mean with regard to the procedure change? of these (1.00) (That is, what does each person check before signing?) According to Procedure 107, ' Procedural Control *, the originator ' of a temporary change must ensure the change is entered on the c.

' working copy' and all " field copies' of the affected procedure.

Describe what is meant by the terms " working copy * and 'f ield copy'. - (0.50) ' (xxxxx CATEGORY 08 CONTINUED ON NEiT PAGE xxxxx) - - - . _ __.. _ _ ._

. . , s . . o . . . . 8.

ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE

________________________________7_ _____,__________________ _ QUESTION 8.05 (2 00) What Administrative control governs the allowable bypassing of APRM's and LPRM's in order to meet the. requirements of Technical Specification 3.1.6 and 3.1.c (Failure criteria for LPRM's and APRM's) ? Briefly 4 ;,,. g explain how this is accomplished.

l ,, b J Mns '.r. -

a....

QUESTION 8.06 (2.00) identified in Throughout numerous abnormal operating procedures and Technical Specfications for fuel clad integrity is a specification that requires at least two (2) Recirculation loop suction valves and '.

their associated discharge valves be in the open position during all modes of operation ( except shutdown, with the Rx head off and water level above the steam lines).

What are the Bases for this specification ? OUESTION 8.07 (2 00) Following a three month refueling / maintenance outage, a startup is scheduled for your shift. All required surveillance and operational prerequisites have been completed.

IAC reports a surveillance logic functional test of the High Drywell pressure trip function for the Containment Spray Logic indicated that one half of the logic was inoperative. (The troubleshooting and repair will take about 16 hours.)

According to Technical Specifications, can you take the Mode Switch to Start Up and start pulling control rods? Justify your answer by fully referencing ALL applicable T.S . . , , .

(xxxxx END OF CATEGORY 08 xxxxx) (xxxxxxxxxxxxx END OF EXAMINATION xxxxxxxxxxxxxxx) . -

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_ - . ' W-32oo,o racs 20 or 46 RPV CONTROL \\ "" ~ - RC/P PRESStJRE.CONTFOL~ ~ %=. o.= 9/3,/a4

.(9/1/s4) o

.

, . - RC/P-2 . ~ Stabilize RPV Pressure.below 1050 psig IF MsIv's are open THEN Control RPV Pressure with Main Turbine Bypass Valves - pm . Main Condenser available . . IF MsIVs are closed THEN Augment RPV pressure with OR

- - f*ll'"i"9 Al**'"'tiV'

Pressure Control Systems: Main Condenser not available . Isolation Condensers l . - l OR Tri A and E I Turbine Bypass Valves N m lation pumps ' inadequate Depressurize reactor 150 psi .

EMRV's

~ ,, ~ CHLY if Torus Water , - Level is above 90 inches ' Depressurize reactor 150 psi in sequence ADBCE -

Clasnup

, ONLY if Baron Injection - is not required .

Main Steam Line Drains ' C only if main condenser

. available . See Table 2 for system line ups , IF All Control Rods are THEN Proceed to Step RC/P-3, inserted to at least position 02 OR 273 pounds o't Baron In:yted (SLC Tank Level at yt) . OR - ~ ' Reactor is shutdown and no. .' .%' Baron has-been injected ~ '" "~ OTHERWISE Continue to control RPV Pressure per RC/P-2 - , . - ,

e -

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Procedure Procedure No.

l.

. .. pgc(' ' MG-32OO.01 W e ll-of 46 ' ' E RPV CONTROL RC/P PRESSURE CONTROL Raisse No.

Om

-

(9/1/84) 9/30/84 t CONDITIONAL STATEMENTS IF EMERGENCY DEPRESSURIZATION THEN Ra.pidly depressurize the is anticipated RPV with the Main Turbine

Bypass Valves IF EMERGENCY DEPRESSURIZATION THEN Enter Procedure EMG-3200.04 or RPV FLOODING is EMERGENCY RPV DEPRESSURIZA-required TION 'AND - less then 3 EMRV's are open - IF RPV FLOODING required THEN Enter Procedure EMG-3200.08 RPV FLOODING , i AND -. at least 3 EMRV's are open , i IF STEAM COOLING is required THEN Enter Procedure EMG-3200.05 I by Procedure EMG-3200.03 STEAM COOLING l LEVEL RESTORATION I, IF TORUS WATER LEVEL THEN Control RPV Pressure to l greater than less than . ' 162 in 800'psig C 163 in 200 psig ! 160 in 100 psi; per Fig A CRUS LOAD I L:MIT C"R*/E IF TORUS WATER TEMPERATURE THEN Control RPV Pressure to . greater :han 125 less than Fig B HEAT CAPACITI TEMPERATJRE LIM!T .' CURVE . '% IF BORON INJECTION is required THEN Open MS Vs (defea:ing l AND isolation in:erlocks.may j~ . MSIVs are closed me required) ' AND AND Main Condenser available Con:rol RPV Pressure vi h AND Main Turbine Bypass Valves i No Gross Fuel Failure ! AND - I No Steam Line Break l _ .. -. _. _ _ _ _. . -. -- - - _ _ _. _ _ _ _ - _ - - -.

' ^ . , . . . . f*~~ ._ . A - .. ' , 5.

THEORY OF NUCLEAR POWER PLAN;T OPERATION, FLUIDS, AND PAGE

p----------------------- -

--_-___ -_-__- ANSWERS -- OYSTER CREEH-86/05/09-LANGE, D.

. ,yf'

ANSWER 5.01 (2.50) After about 10 hours the SDM will increase to approx. 3 % as a result of _ Xenon peaking. After 20 to 30 hours the SDM will be back at 1 % as Xenon its equilibrium value.From this point on the SDM decreases with decays to if no other action the Xenon concentration and the Reactor will go critical(2.50) is taken.

REFERENCE

Oyster Creek, 842.095, RX. Theory handout-Requal. Taught -1985-TCR's.

, ANSWER 5.02 (2.25) , ot. nyn. wks 1 % during transient oper-o.[13 4 Kw/ft-To limit clad plastic strain to ation.

(1.00) 6.

1. Radial position in the core. (0.25) 2. Axial position in the core. (0.25) (any 3 at 0 25 each) e, m les eer. 4 e W M M - 3. Position of the rod in the bundle. (0.25) up Tggf" "#" 4.

Manfacturing tolerances. (0.25) 2200 des.F Limit.

To protect the fuel cladding during a DRY-0UT,LOCA - in the fuel nodes.)

(0.50) c.

(Duetoheatradiationproblems ! REFERENCE Oyster Creek.

Lp. S/D margin and TS requirements.

~ ANSWER 5 03 (3 00) ( a. Adds negative reactivity E0.253 due to the increase in neutron CO.503 leakage - Moderator temperature coefficient.

b. Adds negative reactivity CO.25] due to the increase in neutron CO.503 capture in the fuel - Doppler coefficient.

c. Adds positive reactivity [0.253 due to the decrease in neutron leakage - Mcderator temperature coefficient. C0.503 d. Adds negative reactivity [0.25] due to the increase in neutron leakage - Void coefficient. C0.50 REFERENCE ( 8 12) Plant, Parameter Effects on Oyster Creek LP. Reactor Theory CH. 48 Control Rod Worth and Reactivity Coefficients.

- . 1985-TCR-Lesson Plan, 842.095, pg. 7-9.

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

- . . . . . . . . . 5.

THEORY OF NUCLEAR POWER PLAN;T OPERATION, FLUIDS, AND PAGE

-

p----------------------- --_---_-----_- ANSWERS -- OYSTER CREEK-86/05/09-LANGE, D.

C b 4

ANSWER 5.04 (2.00) A' . At 4% power (0.75) At 4% power, NPSH is higher due to the greater inlet subcooling. At 100% power, the feedwater heaters increase T inlet 9 /** f. # r*W"A h v t=@'i'*" no NPSH is lower.

. war e 4,. /,e w r.

REFERENCE Oyster Creek Fluid Flow CH $7.

Chapter taught, 1985-Requal program.

. , ANSWER 5.05 (1.75) , 1. By increasing Reactor Water Level---> This helps maintain and promote (0 875) natural circulation.

2. Maintaining forced cireviation ---> By using one recirculation pump or (0.875) un-throttled shutdown cooling flow.

REFERENCE Oyster Creek Thermo.& Heat Transfer, CH.4 9, pg.125, Chapter Summary.

Chapter taught-1985, Requal program.

ANSWER 5 06 (1.00) The measured change in pressure across steamlines is proportional to the volumetric flow rate. Volumetric flow rate is compensated with the fluid density to provide mass flow rate.

REFERENCE

GE Thermodynamics Heat Transfer and Fluid Flow pg.7-13 and 7-81

ANSWER 5.07 (1.00) Dissolved oxygen content in the coolant is lower at power operation due to deaeration, hence the effect of C1 ion concentration on stress corrosion cracking of GS is less et power operation.

(1 00) REFERENCE , Item Code 5-4 Oyster Creek Licensed Operator Requal Program . -

e - - - - - - ~ --+ o.

.,., -. - ,n.,m 7,--,, e v- - - -,

. . . . . ~ . 5.

THEORY OF HUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE

gg--------------- , ____ ______________ -86/05/09-LANGE, D.

ANSWERS -- OYSTER CREEK .

ANSWER 5 08 (1.00) The increase in void generation due to the power increase down low (2.0) , in a bundle will result in a negative reactivity feedback throughout the length of the bundle causing an overall bundle power reduc' tion.

REFERENCE Item Code 5-2 Oyster Creek Licensed Operator Requal Program , Lesson Plan-842.095, pg. 11.

, .

. e e

-. . . . . . . . . . 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE

7-------6/05/09-LANGE, D.

-8 ANSWERS -- OYSTER CREEK ANSWER 6.01 (2.00) - isolation caused by induced high flow c. To prevent an'inadvertant sy* stem (0.75) ' through the condensers.

(0.50)' 6. TRUE come off directly at an elevation -), c. The steam lines to the isol.cond.

S' Yarway indication. Operating above this f' corresponding to approx.

water level will cause a potential for damage due to water hammer.(0.75)j- - og g . REFERENCE Oyster Creek LP 4 21, Isol. Cond.

Bas,ic requirements for I/C. Student Learning Objective ( SLO ) 7,10,8.

- System not taught during 1985 requal.

ANSWER 6.02 (2.50) a.

1.

Loss of position indication.

2. Loss of position ind. and reset capability.

3. Loss of position ind. and reset capability.

4.

Loss of control power.

(0.50 for each correct ans.)

5. Loss of control power.

REFERENCE Oyster Creek, 2000-ABN-3200.13. Response to loss of All 125 VDC. pg.

1-0.

LP. # 39, SLO-18.

$' . . , . e e

. . . . . ~ . 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE

7------86/05/09-LANGE, ANSWERS -- OYSTER CREEK

- D.

ANSWER 6.03 (3.00) - c. FW-Flow > Level increases ( O'. 2 0 ), due'to large flow error signal causing FRV to open fully (0.20). Prbbable Turbine Trip on high level.(0.20) b. STH-Flow > Level decrease (0.20), due to large flow error signal causing the FRV to close (0.20). Possible Low level Scram. (0.20) - Rx. Water Level > Level increases (0.20), due to large level error signal causing FRV to open fully (0.20). Probable Turb. Trip on hi-level. (0.20) c.

d. STM-Pressure > Indicated level will decrease (0.20), due to the decrease there will be a resulting overfeeding'and under-in indicated steam flow feeding signal being sent to the FRV (level vs steam flow signal)(0.20).', Depending on the power level,(steam flow), and level being maintained at the time of the incident, actual level may increase or decrease. (0.2 Possible Turbine Trip or Reactor Scram (level inc. or dec),but in either case less significant than a loss of the basic three elements.

(0.20) e. Feedwater Temp.> Level increase (0.20), due to the temp. signal failing in FW-flow and opening the FRV.(0.20) high causing an indicated decrease Probable Turb. Trip on high level. (0.20) REFERENCE Oyster Creek LP. 444, Attachment 42 Loss of Input Signal to FW-Control.

SLO-B.

ANSWER 6.04 (2.25) a.

1. The D/G immediately starts, goes to idle, the automatically shuts down after a time delay of ( 11.5 Min. ) (0.75) an automatic re-2. The persistant undervoltage condition will cause start of the D/G and begin loading in a timed sequence.

'(0.75) l b. The Control Room start /stop switch or the fuel oil cut-off switch in the ! D/G engine compartment.(0.25) NO, The 11.5 min. idle feature allows engine cooldown before shutting q.

down. (0.50) " gg .y % 7 M wk-REFERENCE Requal Program-TCR-828.0.13, BLO, N,L,M.

Dyster Creek Oper. Proed. # 341, pg.1-26.

ANSWER 6.05 (1 00) Must have cleared or-overridden all initiating and auto start signals.. a.

) b. Controlled by (opening losinglthe C/S parallel valves.

l % Yo & </ La serf f6 M d& ~ m

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

- . . . . . i < . . . _ PAGE

6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION ______________ ________________________________7_______86/05/09-LANGE, D.

ANSWERS -- OYSTER CREEK - - REFERENCE Oyster Creek, Oper. Proed. # 348,sec.5.3.5, and LP. # 10, C/S logic.

TCR-828 0.10, BLO-5,10.

. . ANSWER 6.06 (1 50) . Bypass . Setpoint 29 gallons ?*S* Mode switch in refuel or shutdown and 1.

26 7*C ' - derve t. bypass switch in bypass _ Mode switch not in run and <600 psig - 2.

<90 % open

Reactor pressure Auto bypass'20 sec after placing'in 3.

Mode switch in shutdown shutdown 4.

23*Hg Mode switch not in run and <600 psis Reactor pressure 5.

<90 % open Mode switch not in run and <600 psig Reactor pressure or 3 rd stage pressure < 40% power level (each setpoint 0.1 each complete bypass answer 0.2) REFERENCE KR 9 4.

Oyster Creek LP-46 Reactor Protection Gystcar TCR-828 0.37, BLO-7.

ANSWER 6.07 (1.50) (0.25.each) a.

Open f b.

Open c. Close d. Close e.

Lock up as is _

l f. Lock up as is , REFERENCE ~ Oyster Creek Licensed Operator Requal Program. - Iten Code 2-51 j l . TCR-828 0.43e BLO-A.

I - - - _.

- . _ q _------r---- ,, -, _. ,j,y,_,_.__,,__,____..,,,,_,____%, , _ _ _ _ _ _. _,.,., _ _,, _ _ 7.,__,,, _,. _. _ _ _ _ _., _, _, _ _ _ _ _ _ _, _.,..,, _,. -,,., _ _,,,,, _ _. _.., _ _ _ _.,, -

- . . . . .

. s . , 6.

PLANT SYSTEMS DESIGN, CONTR0i., AND INSTRUMENTATION PAGE

________________________________'y_____________________ 86/05/09-LANGE, D.

ANSWERS -- OYSTER CREEK - ANSWER 6.08 (2 00) - 1.

B ~ (1.0) ~ (0.5) - 2.

a. 2 (0.5) b.

(0 51 c.

REFERENCE Oyster Creek Licensed Operator Requal Program,- Item Codes 2-92 & 3-27 . e e . f.

.

e v

' . . - - , . . I ~ . I - -

a--

---=m- - + -,, - - - - - ,.-mew m., w,,g- -- - - - .------.v-.-----r--*e e.m& mm,-- - - + - - - - -. - yw y-e e7-----rw--*gg --v-----

_ -. . . . . . . - . _ ' 7.

PROCEDURES - NORMAL, ABHORMAL, ENERGENCY AND PAGE

~~~~E 65UEU556dL CUOiRUL~~~~~~~~I~'~~~~~'~~~~~~~~ ~ ____________________ -86/05/09-LANGE, D.

ANSWERS - OYSTER CREEK .

ANSWER 7.01 (2.00) , 1. If a reactor limiting safety system setpoint has/has notebeen exceeded.

~ fuel intes'rity is 2. If reactor vessel pressure boundary integrity or (1.00) threatened.

_ , REFERENCE '. , Rev. Or pg.4&10.

Oyster Creek Proed. ABN-3200.13 ' . - ANSWER 7.02 (2.50) 1. Classification of the event.

2. Approving and directing official notification to off-site agencies.

information releases to the media.

3. Approving and conveying protective action recommendation to the N.J.

4.

office of Emergency Mgnt.

lower level to non-assigned 5. Directing on-site evacuation at the Alert or personnel.

6. Authorizing emergency workers to exceed 10 CFR 20 Rad. exposure limits.

(any 5 at 0 50 each) REFERENCE Oyster Creek EPIP-2, pet 3 ANSWER 7 03 (2.75) . ,C e elev.23' in the reactor bids.*by. Using the Control Rod Drive System confirming both CRD pumps are running and throttleing the by-pass valve.

a.

(0.75) b. 1. Scram the Reactor - 2. Verify all rods in.

3. Trip all Recire. pumps.

, 4. Trip the Main Turbine.

' 5. Close the MSIV's 4. Trip all FW pumps .7.

Trip all condensate pumps.

8. Initiate both isolation condensers.

. . , ' eight correct answers at 0.25 each ) ~ - l - ( t s nsus A/d.

- . .a e n ~ ' ~ S - e =+w?-------'w-m---u---< - --4 - rr--e yme - -

e==r

- "-wr =-7

- ---+----w-- -w 7T-----'-' - - ' -

-~; . . , . . .

. . . , . . 7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE

--- sE5i5c55iEsc E6aisac--------r-

'--------

____________________ ANSWERS -- OYSTER CREEK-86/05/09-LANGE, D.

. REFERENCE Oyster Creek, ABN 3200.30 (ConprolRoomEvacuation) . ANSWER 7.04 (1.00)- Prevents unstable steam condensation by depressurizing the A.

reactor while the torus has sufficient heat capacity. ( br0 ) _ toprevent{yelicfatiqufdamagetothetoruswalls.

B.

In order -- r - - - ' s5-

(0.5) . . . - REFERENCE Osyter Creek Procedure EMG-3200.02 Osyter Creek Handout 1202.06 Torus water temperature control pg. 14-16 ANSWER 7.05 (1.50) At drywell temperatures greater than 212 degrees F, steam can replace the non-condensibles being evacuated and maintain a high containment pressure.(1.5) REFERENCE Oyster Creek Procedure EMG 3200.02 Primary Containment Control Handout 1202.08 Primary Containment Pressure Control pg.5

ANSWER 7.06 (1 00) If the reactor is not shutdown, cooling down the reactor will add positive reactivity to the core complicating the~ power control ' {,

problem. Reactivity changes are minimized by minimizing the change . (1.00) in temperature.

REFERENCE 0.C. Proc. EMG-3200.01, Item Code 64-1 l - . . e

. -~ . m t _,,, _ _.. _.. _ -. _ _. _ _ _ _ _. _ _ _ _ _ _. _ _. _. _ _. _ _ _ _. _ _ _ _. _ _ ._ _ _ _ _ _ _ _ -. .. . _

. . . . . . . . - . . PAGE

7.

PROCEDURES - NORMAL, ABHORMAL, EMERGENCY AND --- RE5i5E55iEEE E5siE5E------- F--------------- ____________________ -86/05/09-LANGE, D.

ANSWERS -- OYSTER CREEK .

ANSWER 7.07 (2.00) flow through one ENRV sufficient The minimum RPV pressure producing steam to limit peak clad temp to 2200 deg. F has been determined to be 700 psis.

The surge of steam flow resulting from rapid depressurization"will osain lower fuel temperatures, providing additional time for reestablishing (2.00) o source of coolant injection.

. REFERENCE FJC 300 O.C. procedure ENG 3200.05 handout 1202 12 pg. 6 , ANSWER 7 08 (1.50) c. A plant shutdown is required (1.0) because plant operation with less than four recire loops in service is prohibited (1.0).

(1.0) b. Power operations may be resumed.

REFERENCE Oyster Creek Licensed Operator Requal Program, - Item Code 4-21 ANSWER 7.09 (1 50) (0.5 each) a. 100 des F/hr b. 50 des F c. 50 psid - 7~. #. C. . d. 195 des F C e.

5% f. 200 des F REFERENCE - Item Code 4-30 Oyster Creek Licensed Operator Requal Program, . w e I ! I i

- , . . . . s e 8.

ADMINISTRATIVE PROCEDURES, CDHDITIONS, AND LIMITATIONS PAGE

'

-86/05/09-LANGE, D.

ANSWERS -- OYSTER CREEN . ANSWER 8.01 (2.00) . 1. Its Corresponding NORMAL or: EMERGENCY power source is operable. (1.00).

2. All of its redundent system (s), subsystem (s), train (s), component (s) and device (s) are operable.

(1.00) - . REFERENCE Oyster Creek, TS.Sec. 30, Operability Requirements. Specification 8.

.

. ANSWER 8.02 (3.00) I o. This assures that an adaquate flow pat,h and communication e,xist from the.

(0.50) This is needed annular space and the core shroud to core region.

to be assured that reactor water level instrument readings are indicat-ive of water level in the core region. (0.50) b.

1. 4 f t, 8' above the TAF.(0 50), Water level can presently be monitored (0.50) - / fp fyy p e p t.

g,the TAF.

s M 4 ft, 8' (0.50 c. The SRM nearest the core alteration must be operable.

Two SRM's must be operablei one in the core quadrant and one in the(0.50) adjacent quadrant.

REFERENCE sec.2 1, Safety Limits and Fuel Oyster Creek, Tech. Spec. bases and spec.

Clad Integrity.

ANSWER 8 03 (2 00) /**

[,f independent samples of tank taken/pr.ior to discharge 7(1.0)

a. Two (2) I and one near completion.

s _ b. Two (2) station personnel independently check valving prior to ( 1 0 ).; discharge.

REFERENCE - Item Code 8-7 Oyster Creek Licensed Operator Requal Program, - , l -

!* ',? , Qg: n'$ ',:%!> ~ *! . . 'h ' '. ., _.

,g

/

.e r,.4 f , \\ ~ .f, ' t ., s . +- .-----------------,,yo, ,., %---.-,y-- ,, -. -., - -, -, - -_,--.---,,.-.-.-.,,,.7,-,-y .-_-- - ,,,,. _,. - - _ _ - - -,. - - _ - - _

. > i . . . . m . 8.

ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE

_________________ ________________________________7_______,_6/05/09-LANGE, -8 D.

CNSWERS -- OYSTER CREEK ANSWER 8.04 (2.00) . 64,6'+ o. 1. Place the plant in a safe condition.

2. Supervisor should resolve'the question or change the procedure (0.5) in accordance with 107.

b. Cognizant supervisor-technical validity and does not chang'e the (0.5)' intent.

GSS-operatic.ial and safety concerns with regard to Tech Specs . (0.5) ~(0.5).

c. Working copy-the green copy being used to document the actual

execution of procedural steps which include sign-offs, recorded , - . data, QC hold points, etc.

(0.5) Field copy-the copies of the procedure being used in the field by the persons actually performing the work to provide procedural guidance or reference, but NOT being used fue documentation or sign offs.

REFERENCE - Codes 8-4, 8-21, 8-51 Oyster Creek Licensed Operator Requal Program, ANSWER 8.05 (2.00) STANDING ORDER ( 4 21 ), Allowable bypass configuration for LPRM's and APRM's system.

(0.50) i To determine bypass allowance.

Accomplished by reviewing the following --#. 1. APRM bypass information sheet. (0.50) f,gaf rq A 2. LPRM status information sheet. (0.50) jyg ..f.

q 3. LPRM bypass information sheet. (0.50) d%. ' _ REFERENCE STANDING ORDER 4 21-(Use and reason for) rev.4 11.

' f ANSWER 8.06 (2 00) assures that an adaquate flow Specification 2 1.e of Tech. Spec's, path exists from the annular space between the pressure vessel wall' i to the core region. This provides for good com-I and the core shroud, thus assuring that reactor level munication between these areas , instrument readings are indicative of water level in the core region.

- (2.00) . O l ~~ e , __ l _.

l _ t

. . .. ____ ____. - _ _ _ _ _ _ _ _ _ _ _ _ . . 's . e s , 8.

ADMINISTRATIVE PROCEDURES, C9NDITIONS, AND LIMITATIONS PAGE

#

' -86/05/09-LANGE, D.

ANSWERS -- OYSTER CREEH . REFERENCE . T.S. 2.1.e, ABN 3200.02-Caution 4 Lesson Plan 4 47, SLO-4 20.

. ANSWER 8 07 (2.00) ' YES, (0.50).

- ' The containment spray function is only required to be operable'when Table 3 1.1 (E), and primary containment is required to be operable.

_ note-(u) on pg. 3.1.13.

Primary containment is not required, < 212 des., RX. not critical., . -T.S-3.5.A, pg 3 5 1 (a).

or if repair is, complete

A startup can continue until P/C is required, . prior to criticality.

CAF for required administrative controls.

REFERENCE Oyster Creek T.S. requirements for P.C, and C.S.

$ _ e . ~ e w-m e M

_ _ _ _ _ _. _ _

- __ . s , . e . . ' _ ' PAGE

TEST CNOSS REFERENCE QUESTION VALUE REFERENCE i ' __________ ________ ______ 05.01 2.50 BAN 0000243

05.02 2.25 BAN 0000244

05 03 3 00 BAN 0000245 03.04 2.00 BAN 0000246 .

03.05 1.75 BAN 0000253

05.06 1.00 BAN 0000261 - 05.07 1.00 BAN 0000264 05.08 1.00 BAN 0000265 ______ . 14.50 .

, 06.01 2 00 BAN 0000247 . 06.02 2.50 BAN 0000248 "

06 03 3 00 BAN 0000250 06 04 2.25 BAN 0000252 06.05 1 00 BAN 0000257 06.06 1.50 BAN 0000250 06 07 1 50 BAN 0000266 06.00 2 00 BAN 0000267 ______ 15.75

07 01 2.00 BAN 0000249 07.02 2.50 BAN 0000255 07.03 2.75 BAN 0000256 , , 07.04 1 00 BAN 0000259 07 05 1.50 BAN 0000260 07.06 1 00 BAN 0000262 07.07 2 00 BAN 0000263 ,, 07.08 1.50 BAN 0000268 f 07.09 1.50 BAN 0000269 - ______ , 15.75 08.01 2 00 BAN 0000251 08.02 3.00 BAN 0000254 08.03 2.00 BAN 0000270 08.04 2.00 BAN 0000271 08 05 2.00 BAN 0000272 08.06 2.00 BAN 0000273 08.07 2.00 BAN 0000274

______ ~. 15.00 ______

~ . }}

v t e Inspection Report - Oyster Creek - 1986010
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \| 26 \|
1986 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 7(0) 8(0) 9(0) 10(0) 11(0) 12(0) 13(0) 14(0) 15(0) 16(0) 17(0) 18(0) 19(0) 21(0) 22(0) 24(0) 25(0) 26(0) 27(0) 28(0) 29(0) 30(0) 31(0) 33(0) 34(0) 35(0) 36(0) 37(0) 38(0) 39(0) 40(0) 41(0) 99(0) Security Operator Exams Emergency Planning Other

IR 05000219/1986010

Text

REGION I

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