Text

Exam Rept 50-295/OL-85-02 on 850617-19.Exam Results:All Five Senior Reactor Operator Candidates Passed Written,Oral & Simulator Portions of Exam
	ML20132F574
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	07/29/1985
From:	Ferrell R, Higgins R, Mcmillen J, Reidinger T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20132F568	List: ML20132F564; ML20132F574;
References
	50-295-OL-85-02, 50-295-OL-85-2, NUDOCS 8508020311
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U.S. NUCLEAR REGULATORY COMMISSION REGION III

, Report No. 50-295/0L-85-02 Docket No. 50-295 License Nos. DPR-39/48 Docket No. 50-304 Licensee: Comonwealth Edison Zion Generating Station Zion, IL Facility Name: Zion, 1 and 2 Examination Administered At: Zion Training Center i Examination Conducted: Five (5) SR0 Examinations kkbt Examiners: Ralpn R. Ferrell 7 79kh Date Hig i 7M 7[FS-

- Date '

T Re dinge M 7!/5' I Date k k-Approved By: J. McMillen 7Mv/F5' Operating Licensing Section Date 4

Examination Summary Examination administered on June 17-19, 1985 (Report No. 50-295/0L-85-02)

Results: All five (5) SRO candidates passed the written, oral, and simu' ator portions of the examination.

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..l REPORT DETAILS 1

1. Examiners

R. Ferrell - Chief Examiner R. Higgins - Examiner T. Reidinger - Examiner P. Doyle - Headquarters Observer 1

,! 2. Examination Review Meeting At the conclusion of the written examination, the examiners met with Mark Carnahan, Ray Landrum, Tim Blake and Haral Logaras of the training

, department. As a result of this review a list of comments was generated and are-included, along with the examiners comments, on a separate

. attachment.

3. Exit Meeting 1

At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the ,

examinations. Those individuals who clearly passed the oral and/or j simulator were identified in this meeting.

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Zion SR0 Examination Comments Attachment 1 Comment 5.01 The answer key has two answers.

Examiner response 5.01 Agreed - will also accept "a" for full credit.

Comment 5.05 Since U-238 contributes 7% of fissions, there is no correct answer.

Examiner response 5.05 Disagree - per the basic nuclear engineering reference manuals consulted, the answer to this question is correct when all answers are considered. The majority of the candidates answered this question correctly.

Comment 5.06 The answer should be B. U-238 Examiner response 5.06 Disagree - per the basic nuclear engineering reference manuals consulted, the answer to this question is correct when all answers are considered.

The majority of the candidates < answered this question correctly.

Comment 5.17 C is T e standard advertised answer. Both C and D are correct.

Examiner respnse 5.17 .

Disagree - C is the most correct answer. With a control rod insertion and an excessively negative MTC, overall power will increase due to the decrease in Tave but not just in the top of the core.

Comment 5.22 The question looks like " Explain how we see the effects of the decay heat" when using the word " mechanism" in the question. Correct answer to this may be expected to read like " Fission Fragments in the Fuel Decay by alpha, beta and gansna decay radiation. The fuel and core internals absorb the' radiation and heat is generated. Tave increases above 547*F.

Stm pressure increases above 1005 and Stm dumps operate to control Tave I at 547*F.

Examiner response 5.22 Agree - the above coninents were added to the answer key.

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Comment 5.23 This is not a simple answer, could be decrease based on Turb efficiency or increase based on Rx efficiency.

Examiner response 5.23 Disagree - The question asked specifically for " unit efficiency" which should have been understood as "overall efficiency." The question was graded by examiner very liberally.

Comment 5.27 Wrong answer to c. It should be, "If pump speed doubles, head quadruples."

Examiner response 5.27 Agreed - The answer key was corrected.

Comment 6.03 Answer F has no question F.

Examiner response 6.03 Agreed - The typo was corrected.

Comment 6.09 Note that the "S" signal only goes to SW0005 and 6 v1vs. Booster pp trip and Fire pp start are subsequent effects.

Examiner response 6.09 Agreed - The candidates answers were graded according to above comment and no credit taken off if subsequent effects not mentioned.

Comment 6.11 Answer to item 1 is not applicable to question.

Examiner response 6.11 Agreed - The additional information was added to key.

Comment 6.17 On section b. We suspect typo in answer. The valve should reclose at 1835 PSIG. If VLV fails open, and it is not due to a single failure, the only way to stop depressurization .s to close the block VLV. This should be an additional correct answer.

Examiner response 6.17 Agreed - The answer key was corrected.

Comment 7.05 On section B. the operator would also use E0P-7, App. A, for verification of natural cire, alcng with the Westinghouse Description. This should be listed as an additional answer.

Examiner response 7.05 Agreed - E0P-7, Appendix A was added as a reference and the question graded accordingly.

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! Comment 7.11 On Section B., the operator could also close the MSIV's in accordance ,

!- with the immediate actions listed in E0P-1, Page 4.

Examiner response 7.11

Agreed - The answer key was corrected.

! Comment 8.02 Section A. Lists the wrong answer. The pump is NOT operable with the j Discharge valve stuck shut.

Examiner response 8.02 j Agreed - The typo was corrected.

f Comment 8.14

! The answer should be 'no Less than 25 instead of No Greater Than.

1 I- Examiner response 8.14

Agreed - The answer key was corrected.

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M U. S. NUCLEAR REGULATORY COMMISSION S IOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: ZION 1&2 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 85/06/17 EXAMINER:

_'R.R.FERRELL APPLICANT: ._________________________

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 exaniination star ts.

% OF CATEGORY % OF APPLICANT'S CATEGORY _

VALUE TOTAL SCORE VALUE CATEGORY 00

_I'S 00_I____ _'SI I__ ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

25 00___I____ _I'_SI__ 00 ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

_I'5 00I____ _I'_5.00 ___ ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 25 ADMINISTRATIVE PROCEDURES,

__ I00___ _I'SI__ 00 ___________ ________ 8.

CONDITIONS, AND LIMITATIONS 100.00 100.00 TOTALS FINAL GRADE _________________%

All work done on this exaniination is niy own. I have neither Sivon nor received aid.

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

EPPL5CEUiI5~555 EiURE

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND s PAGE 2 OUESTION 5.01 ( .50)

Chcose the CORRECT response. The installed neutron source currently used at Zion:

A.is needed to initiate the fission process.

B produces neutrons by the alpha decay of Antimony 123.

C. produces neutrons by the spontaneous fission of Californium 252.

D.is a type of photo-neutron source.

QUESTION 5.02 ( .50)

Choose the correct response concerning Samarium:

A.The change in Samarium concentration following a reactor trip will diniin-ish the shutdown margin.

B.Sanier f uni is produced as a result of the beta decay of promethium.

C.The equilibrium Samarium concentration is directly proportional to reac- -

tot power.

D.Samariuni beta decays to Europioni.

QUESTION 5.03 ( .50)

Which of the following statements about reactivity is CORRECT?

A. Reactivity is the ratio of the neutrons in the present generation divided by the neutrons in the preceding generation.

D. Reactivity equel to 1 means the reactor is critical.

C. Reactivity can be either added to or removed from the core.

D. Reactivity is the fractional change in neutron population per generation.

(***** CATEGORY 05 CONTINUED ON NEXT PAGE mm**m) l i

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5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3 QUESTION 5.04 ( .50)

Choose the CORRECT response. Assume Zion 1 is soberitical with an initial count rate of 25 counts per second. Rods are withdrawn to add 300 PCM of rocctivity, resulting in a stable count rate of 40 counts per second. Which of the following is closest to the value of Keff after the rod withdrawl (when the count rate is 40 counts per second)?

A. 950 B. 990 C. 995 D. 999 GUESTION 5.05 ( .50)

Which of the following nuclides is NOT a fissile nuclide which contributes ficsions during power operation at Zion?

A. Uranium 235 D. Uranium 238 C. Plutonium 239 D. Plutonium 241 QUESTION 5.06 ( .50)

Choose the CORRECT response. The major contributor to fast fission at Zion ici A. Uranium 235 B. Uranium 238 C. Plutonium 239 D. Plutonium 241 (m**** CATEGORY 05 CONTINUED ON NEXT PAGE manum) i

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S. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4 QUESTION 5.07 ( .50)

Choose the Correct response. The Importance Factor at Zion is _______ than one because delayed neutrons _____________.

A.lessi are less likely to leak from the core.

B.lessi do not cause fast fission of Uranium 238.

C. greater; are less likely to leak from the core.

D. greater; do not cause fast fission.

QUESTION 5.08. ( .50)

Choose the CORRECT response. With a startup rate of .5 decades per minute, roactor power will increase by a factor of 5 approximately every:

A.60 seconds B.72 seconds C.84 seconds D.96 seconds GUESTION 5.09 ( .50)

Choose the CORRECT response. The Isothermal Temperature Coefficient is the

, con of the moderator temperature coefficient and the:

A. fuel temperature coefficient when power is below the PDAH.

I j B. power coefficient when power isy below the point of adding heat.

C. fuel temperature coefficient when power is above the PDAH.

D. power coefficient when power is above the point of adding heat.

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

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5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND , PAGE 5 OUESTION 5.10 ( .50)

Choose the CORRECT response. As fuel temperature increases. control rod worth ________i as the relative thermal neutron flux which the control rod onperiences increases, control rod worth _________.

A. increases; increases B.increasesi decreases C. decreases; increases D.decreasesi decreases GUESTION 5.11 ( .50)

Choose the CORRECT response. Assuming a constant flun profile, control rod worth increases as ___________ increases.

A. boron concentration B. total core flux C. fission product concentration D.aoderator temperature GUESTION 5.12 ( .50)

Choose the CORRECT response. Differential boron worth for a given Tav3 (refer to Figure 5-1) is more negative at lower boron concentrations because:

A.of the thermal flux redistribution at lower boron concentrations.

B. fewer boron atoms are available to compete with each other.

C. fewer fuel atoms are present, reducing the thermal utilization coefficient D.of the harder neutron flux spectrum at lower boron concentrations.

(mmmmm CATEGORY 05 CONTINUED ON NF,XT PAGE mmmmm)

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6 QUEETION 5.13 ( .50)

Choose the CORRECT response. Differential boron worth for a given boron concentration (refer to Figure 5-1) is more negative at 547 de3rees F than it is at 560 degrees F because the:

A.coderator density is less at hisher temperatures.

B. boron absorption cross section decreases at higher temperature.

C. neutron spectrum is harder at higher temperature.

D. neutron leakage is greater at high temperature.

QUESTION 5.14 ( .50)

Choose the CORRECT response. The procedure for the control of Axial Power Distribution are designed to:

A.Dinimize the effects of xenon redistribution during load-follow oaneuvers.

D. serve as backup protection against a dropped rod or siisaligned control rod.

C. ensure adequate control rod reactivity. _

D. limit potential reactivity insertions due to a control rod ejection accident.

QUESTION 5.15 ( .50)

Choose the CORRECT response. What action is required by Technical Specif-icotions 3.2.2.A.4 if Delta I is -9 when reactor power is 95%. Refer to Figure 5-2.

A. return Delta I to the target band within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in hot shutdown withire the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

B. reduce reactor power to less than 50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and reduce the high flux setpoint to less than 55% within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

C. reduce reactor power 1% for each 1% deviation from the target band with-in 15 minutes. ;

D.oither the deviation shall be eliminated or the reactor power shall be immediately to a level no greater than 90%.

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(*rrum CATEGORY 05 CONTINUED ON NEXT PAGE maxxx) l

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

QUESTION 5.16 ( .50)

Choose the CORRECT response. What action is required by Technical Specif-ication 3.2.2.A.6 with Delta I at -10 for the last 61 minutes and reactor power at 70%? Refer to Figure 5-2.

A. return Delta I to the target band within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in hot' shutdown within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

B. reactor power shall be reduced to no greater than 50% power and the hi3h flux setpoint reduced to no greater than 55% of rated values.

C. reduce reactor power 1% for each 1% deviation from the programmed band.

D. return Delta I to the target band within 15 minutes or be in hot shutdown within the next hour.

QUESTION 5.17 ( .50)

Choose the CORRECT response. In which of the following situations will the further insertion of control rods cause Delta I to become more positive?

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A.Duildup of Xenon in the top of the core with rods fully withdrawn.

B. Positive MTC during a reactor startup.

C. Bank D control rods inserted to the core midplane.

D. Excessively negative MTC at EOL.

QUESTION 5.18 ( .50)

Choose the CORRECT response. For a Guadrant Power Tilt Ratio (OPTR) of

>1.09, Tech Specs section 3.2.2.B.3 requires that the operator:

A. reduce reactor power to less than 50%.

B. reduce reactor power to rated power less 2% for every percent that the OPTR exceeds 1.0.

C. bring the reactror to hot shutdown.

D. reduce reactor power to less than 85%.

(rwrum CATEGORY 05 CONTINUED ON NEXT PAGE unman)

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 8 GUESTION 5.19 ( .50)

Choose the CORRECT response. The major source of trition, in the RCS is:

A. diffusion through the clad of tritium produced by ternary fission.

B. reaction of lithium 7 with thermal neutrons.

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C. reaction of lithium 7 with fast 5eutrons.

D. deuterium activation.

GUESTION 5.20 ( .50)

Choose the CORRECT response. In order to siaintain a 200 F subcoolin3 oorgin in the RCS when reducing RCS pressure to 1600 psis, steam generator pressure must be reduced to approximately!

A.845 psis B.645 psis C.445 psis D.245 psig _

GUESTION 5.21 ( .50)

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

A.cbnormally high discharge pressure B.encessive current in the pump motor C. failure of the coupling between the pump shaft and the motor mshaft D.available NPSH less than the required NPSH QUESTION 5.22 (1.25)

Decay heat is a significant source of thermal energy in a shutdown reactor.

Explain the mechanism of decay heat.

(xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx) i 1

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5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 9 GUESTION 5.23 (1.50)

Indicate how the following will affect UNIT efficiency at steady state power level (Consider the affected parameter only and indicate INCREASE, DECREASE, or NO CHANGE.)

o. Condenser hotwell temperature changes from 125 degrees F to 130 degrees F. [.753

b. Steam quality changes from 99.8% to 99.7%. [.753 00ESTION 5.24 (2.25)

Por the Tech Spec bases, the reactor is not to be made critical when the coderator temperature coefficient is positive. Answer tne follc wing questions concerning these bases.

A.Why is this requirement imposed?

B.Under what conditions is this requirement waived?

C. Explain when and why the moderator coefficient may be positive. .

E.75 ea]

OUESTION 5.25 (1.75)

A. Define the term NET POSITIVE SUCTION HEAD as it applies to centrifugal Pumps. [1.03 B.How does the follcwing affect NPSH (INCREASE, DECREASE, or REMAIN THE SAME)?

1. Increase in the tank pressure where the pump is taking suction. [.253

2. Increase in flow rate of the pump. [.253

3. Increase in temperature of the fluid being pumped. E.253 QUESTION 5.26 (1 20)

Using Figures 5-3 thru 5-5, determine the quantity of water required to raise the power from 10% to 50% at BOL with an initial boron concentration of 1000 POW.

UNO (xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx) \

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5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 10 GUESTION 5.27 (2.30)

Answer the following concerning general centrifugal pump characteristics:

A.What happens to the system flow rate if a second centrifugal pump in parallel is started with the first one running? E.403 B.What happens to system flow rate if a second centrifugal pump in series is started with the first one running? E.403 C.What happens to pump head if you double the pump speed? C.403 D.What is pump runout? t.503 E. list 4 indications of pump cavitation. C.63 OUESTION 5.28 ( .50)

Choose the CORRECT response. Assume a critical (Keff=1.000) reactor, power at 20%. If +5 PCM is added by manual withdrawl of rods:

A.Heff will increase, neutron population and core power will continue to increase until the operator inserts -5 PCM by inserting rods or boron.

B.Keff will increase, neutron population and core power will increase by an -

amount equal to .005%.

C.Keff will increase, neutron population and core power will increase, which will add negative reactivity due to Power Defect (Doppler and MTC), can-celling out the + 5 PCM. The core power will level out by itself at a slightly higher power.

D.Keff will increase, neutron population and core power will increase, which will add negative reactivity due to Power Defect (Doppler and MTC), can-celling out the + 5 PCM. The core power will return to the original pow-er level, at a slightly higher Tave GUESTION 5.29 ( .50)

Choose the CORRECT response (s). During plant operation at the beginning of core life, the RCS boron concentration will be decreased (diluted) by the NSO to:

A. Force the control rods further out.

B. Compensate for an increase in Xenon concentration C. Compensate for a power reduction D. Compensate for fuel depletion E. Compensate for a 5 degree F decrease in Tavs (zurr* CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx)

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5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 11 GUESTION 5.30 (1.75)

List 5 ways the NSO at Zion ensures the at:ial power distribution is within limits at all times?

QUESTION 5.31 (1.50)

As an operator observing the intermediate range nuclear instrumentation followins a reactor trip, which would you rather see* undercompensated or overcompensated instruments. Defend your answer.

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

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6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 12 QUESTION 6.01 (1.00)

Briefly describe how the Tech Spec required BIT niinimum level is assured durinS normal plant operation.

QUESTION 6.02 (2.25)

Dezeribe the actions and loading of the vital ESS busses of the Zion station under the following conditions:

A.A station loss of off-site power (blackout) occurs 30 seconds after an ESF actuation has occured. Assume off-site power was available initially.

. E.753 B.An ESF actuation occurs 5 minutes after a station blackout. E.753 C.A blackout occurs after the ESF signal has been ' reset

to allow realign-nent to the recirculation phase after an accident. E.753 QUESTION 6.03 (1.75)

Zion Unit 1 is operating at 85% power equilibrium conditions when a Thot instrussent fails high. Describe how this failure will affect the following.

Assunie all control systems are in automatic and no operator action. Consider each of the below items seperately and independent f ron, the others.

, A. Rod insertion lisiit alarm setpoint B. Positive Displacement pump speed control C. Control Rod Bank Position D.0P-Delta T trip setpoint for the affected loop E.Steas Dump Load Rejection Controller output E.35 ea]

QUESTION 6.04 (1.50)

How will the following CVCS valves fail on a loss of control air ( OPEN, CLOSED, AS-IS, VCT, PRT, or HUT):

A.VC8 ,j A (Letdown Orifice Isolation Valve) l B.VC m_ Containment Letdown Isolation Valve) i C.PCV131 (Low Pressure Letdown Control Valve)

D.TCV129 (Letdown Temperature Divert Valve)

E.VCB167 (Deborating Control Valve) E.3 ea]

(xxxxx CATEGORY 06 CONTINUED ON NEXT PAGE xxxxx) i

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 13 QUESTION 6.05 (2.25)

When the temperature of the RCS is less than 250 degrees F and the head is installed, what 3 means are available to protect the RCS from overpressur-iration due to a pressure transient per Tech Specs?

GUESTION 6.06 (1.00)

The reactor is in hot shutdown with RCS pressure at 1775 psis. The reactor trip breakers have been reset and the shutdown banks are full out. You are the SRO and I & C maintenance wants to perform a calibration on the Turbine Impulse pressure channels. Will you allow him to do this? Defend your answer.

QUESTION 6.07 (1.50)

What 2 design features does the Zion Station have that limits the severity of a cold water accident?

DUESTION 6.08 (1.00)

~

Following an ECCS actuation, the transition from cold les to hot les recirculation is made after 19 hours2.199074e-4 days 0.00528 hours 3.141534e-5 weeks 7.2295e-6 months . Briefly explain WHY 19 hours2.199074e-4 days 0.00528 hours 3.141534e-5 weeks 7.2295e-6 months was selected.

QUESTION 6.09 (1.00)

What 3 action (s) occur in the water supply system for the water Fire Prot-ection on an 'S' signal?

DUESTION 6.10 (1.50)

What are 5 conditions required for ACB 1473 Emergency Feed to bus 147 from Diesel Generator 'O' to automatically close? E.3 ea]

OUESTION 6.11 (1.00)

Briefly describe the DC Control Power ground detection system.

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

l l

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 14 QUESTION 6.12 (1.00)

A. Answer the followin3 TRUE or FALSE.

RHR valve 8700A can only be opened from the MCB provided the following valves are closed:RHOB11A(B)

RH8804A(B)

Both CS0049 and 0050 C.53 B.Briefly explain your reason for choosing your answer. C.53 QUESTION 6.13 (1.50)

I One of the causes of an URGENT FAILURE in a power cabinet of the Rod Control System is a REGULATION FAILURE. Answer the following concerning this failure:

A.What are the 2 causes of this failure? C.753 B.What does it protect against? C.753 QUESTION 6.14 ( .75)

~

What are the 3 causes of the CMPTR ALARM /NIS RAD TILT / ROD DEV/ SED alarm?

l GUESTION 6.15 (1.50)

What do the following trips protect against:

A. Low Pressurizer Pressure B.0ver power Delta T -

'C.High Steam Generator Water Level D.Under Frequency on RCP E.High Pressurizer Level L.3 ea]

GUESTION 6.16 (1.50)

How are the RCP Thermal Barrier Heat Exchangers protected from an RCS leak ;

or rupture? List 5. l l

l

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

I

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 15 QUESTION 6.17 (1.50)

PCV 455C (PORV) control switch is a 3 position switch located on the Main Control Board. Answer the following.

A.What is the purpose of each position? ,

C.753 B.How is an uncontrolled depressurization prevented on a failure of 455C in the full open position? E.753 OUESTION 6.18 (1.50)

What is the purpose of the following perniissives:

A.P-8 B.P-11 C.P-14 ) E.5 ea3 kg g6pytsS k CO@CIdhu (marru END OF CATEGORY 06 mmxxx)

l l

7. PROCEDURES - NORMAL, AE:N O RM AL , EMERGENCY AND PAGE 16

~~~~R56f6E665CEE"66UTR6E"~~~~~~~~~~~~~~~~~~~~~~~

GUESTION 7.01 (1.50)

During a recovery from an inadvertant Safety Injection, under what 3 conditions must the Safety Injection be mar.vally reinitiated?

"~~

OUESTION 7.02 (1.50)

Zion Unit 1 is operatin3 at 85% power and utilizing the Motor Driven Feed-water pump due to a Steam Driven FW pump being out of service. With all plant systems in normal / auto, answer the following questions concerning a MDFW pump / Reactor trip:

A.What are 5 conditions that could cause the MDFW pump to trip. E.753 C.Whrt are 5 items that have to be verified by the NSO per EOP-1, Reactor Trip? E.753 DUESTION 7.03 (2.50)

A.When is a Type 1 Radiation Work Permit required? E.753 _

E: . H o w long is a Type 1 RWP valid? C.503 C.When it a Type 2 Radiation Work Permit required? t.753 D.How long is a Type 2 RWP valid? [.503 (mmmmm CATEGORY 07 CONTINUED ON NEXT PAGE mmmmm)

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 17

~

~~~~R d656L6656dL 66 TR6L'~~~~~~~~~~~~~~~~~~~~~~~

GUESTION 7.04 (1.00)

Answer the followin3 TRUE or FALSE A.RP 1190-1,' PERSONNEL EXPOSURES UNDER EMERGENCY CONDITIONS", recomn. ends that for life saving situations a person shall not exceed 150 rem to the whole body.

B.The 10CFR20 limits for quarterly dose to the skin of the whole body shall not exceed 7.5 REM.

C.At the Zion Station each individual must have supervisory approval before l exceeding a whole body dose equivalent of 50 mrem.

D. Weekly whole body dose equivalents in excess of 300 mrem must be approved by the Radiation-Chemistry Supervisor.

E.25 ea.]

GUESTION 7.05 (2.00)

A.What are 3 conditions the operator should maintain in order to enhance

~

Natural cireplation? [1.03 D.What are 3 indications the operator will use to ensure natural circulat-ion flow ..as been established and is adequate? [1.03 OUESTION 7.06 (1.75)

A. Describe how RCS pressure is maintained when in the solid plant pressure control mode. Be SPECIFIC. E.753 B.What is the major problem to the NSO when operating in this mode? E.25]

C.When is Nitrogen pressure control used instead of solid plant control?

E.503 (zurxx CATEGORY 07 CONTINUED ON NEXT PAGE muzzz)

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 18

~~~~Rd656E66565L'66NTR6L'~~~~~~~~~~~~~~~~~~~~~~~

GUESTION 7.07 (1.50)

Concernin3 a steam break accident, answer the following:

A.What are the indications the operator would see on the secondary side?

List 3. E.753 B.What indications would the operator see on the primary side?

List 3. C.753 QUESTION 7.08 (1.25)

List 2 (two) starting and restarting requirements for the Reactor Coolant Puaps?

DUESTION 7.09 (2.00)

Concerning a reactor startup per GDP-2, fill in the blanks for the follow-ing:

. A.The minimum required overlap between Source Range and Intermediate Range _

channels is ______. [.23 B.Following achieving criticality, you establish a Startup Rate of _____DPM and DO NOT e>:ceed a stable Startup Rate of _____ DPM. [.43 C.The POINT OF ADDING HEAT is identified by the operator when , ,

and _____. [.63 D. Bank D rods will begin to withdraw when Bank C reaches _____ steps. [.23 E.The ROD BOTTOM LIGHT ANNUNCIATOR clears and CONTROL BANK A BOITOM lights are off when rods are above ___ steps. [.23 F. Verify that the Intermediate Range channels begin to respond when the Source Range channels are reading between ____ and _____ CPS. [.43 QUESTION 7.10 (1.50)

Per EDP-0, SAFETY INJECTION, what is/are the criteria for stopping the RCP's in an accident condition?

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

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7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 19

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

~~~~R5656L65565L'EUNTR6L GUESTION 7.11 (2.00)

Per E0P-1, Reactor Trip, answer the following:

A.What actions are required of the operator if 4 rods stick out? E1.03 B.What actions are required if the turbine does not trip? [1.03 QUESTION 7.12 (1.00)

GOP-1 states that 1C RCP on Unit 1 must be started first on a startup. Why in this precaution necessary?

OUESTION 7.13 (2.00)

A.What are 3 indications that a il Reactor Coolant Punip seal has failed open? [1.03 B.What are 3 required actions the NSO must take immediately? [1.03 QUESTION 7.14 (2.00) -

A.What are the 4 ways used at Zion to perform an Emergency Boration? E1.03 B.What are the 4 conditions that require emergency boration? [1.03 OUESTION 7.15 (1.50)

Per E0P-9, LOSS OF REACTOR COOLANT, when can SI be terminated?

(mmmmm END OF CATEGORY 07 mmmmm) l

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0. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 20 GUESTION 8.01 (2.50)

For the following statements from ZAP 10-52-3, ' Shift Manning, Relief, and Turnover", fill in the blanks (may be multiple word answers).

A.Operatin3 Personnel working on safety related equipment should not be permitted to work more than ___ hours in any ___ hour period, nor more than ___ hours in any ___ hour period, nor more than ___ hours in any ___

day period.

D.An operator is not 'at the controls

when ___________ or _________.

C.The oncoming Shift Engineer and Radweste Foreman will obtain awareness of shift activities by use of the __________.

D.The _______ provides a mechanism for the disseminttion of instructions which are general and of continuing applicability to the conduct of operations E.25 ea3 OUESTION 8.02 (2.25)

~

On May 5th a valve lineup was performed on No.1 Centrifv3a1 Charging punp to p1 tee it in service following routine maintenance. An entry is inc?uded in the Standing Orders to minimize usease of the pump. On May 18th an Au::iliary Oper ator reports that the discharge valve is closed and can not be physically opened. Answei the following.

A.Is the pump OPERACLE per Tech Specs? C.753 B. Hrs the Tech Spec LCO been violated? E.753 C.How long can the pump be left in this condition? E.753 OUESTION B.03 (1.50)

A.What are the requirements for the fire brigade on the back shifts? E.753 B.Under uhat conditions can the minimum shift manning required per Tech Specs be less than required?

E.753

(*warr CATEGORY 08 CONTINUED ON NEXT PAGE mummm) '

B. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 21 QUESTION 8.04 (1.00)

Per the Tech Spec's interpretations,e:: plain what the intent of 'IMMEDIATELY SHUTDOWN

is when it is found in the action statements.

QUESTION 8.05 (2.00)

A.What 7 people / plant positions have to review'a lifted lead-request for a safety related component once the REQUESTER initiates it? Ine10de all signatures up to actual installation. E1.43 B.Which of the above three individuals would not have to sign the request if it were for a non-safety component? [.63 OUESTION 8.06 ( .50)

Choose the CORRECT response. A NON-ROUTINE VALVE LINEUP AUTHORIZATION must be signed by*

A. Center Desk NSO and Operating Engineer B. Shift Foreman and Center Desk NSO

~

C. Shift Engineer and Shift Foreman D. Unit NSO and Shift Foreman GUESTION 8.07 (2.00)

A.When is management verification by a licensed Shift Supervisor necessary when completing an DUT OF SERVICE card? [1.03 B.When shall the ' PARTIAL CLEAR' proc)e ure NOT be used regarding safety tags? [g*g vp C1.03 J

GUESTION 8.08 (2.00)

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

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

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 22 QUESTION 8.09 (1.75)

A.Who assumes the position of Station Director during a CSEP Emergency?

E.753 B. List the 4 people in order of preference that can assume the position if the person in A above is not available. E1.03 OUESTION 8.10 (2.00)

Per Technical Specifications, are the following components operable based on the below information (YES/NO only-no explanation required):

A.SI pump is started manually from the MCB and the discharge pressure and recite flow is within +/- 15% of a point on the pump head curve.

B.RWST boron concentration is 1900 PPM.

C. BIT contains 900 gallons of 11.5 to 13% by weight Boric Acid at a temperature of 145 degrees F.

D.During a refueling outage, the Main Steam Isolation valves are tested and stroke from full open to full closed in 30 seconds.

[.50 ea3 DUESTION B.11 (1.00)

The normal supply breaker to No.1 Safety Injection pump is tagged out by Electrical Maintenance and during an inspection determined to be malfunct-iening. Parts need to be ordered and it will be out of service for 2 weeks.

No other parts exist in the Edison system and no spare breakers are avail-oble. What is your required action as the SRO in reguard to continuing plent operations?

DUESTION 8.12 (2.00)

What is the responsibility of the Shift Engineer in regard to HIGH RADIATION AREA ACCESS CONTROL? List 4.

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

I

B. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 23 I

OUESTION 8.13 (2.00)

What are the conditions that have to be satisfied in order to enter the incore shaft area? List 3.

QUESTION 8.14 (1.00)

Per the Zion Station Fuel Handling Procedures, what is the HIGH FLUX AT SHUTDOWN alarm setting during a refueling?

DUESTION 8.15 (1.50)

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

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

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

- ... w Cycle efficiency = (Networx A f o as .v o s/t out)/(Energy in)

2 l *, ' , og s. s = V ,t + li.' +t E * "C 2

~

A = 1f4 A = A,e

'- U~ -

gg = 1/2 av a=(Vf - Y,)/t Pg = agn w = e/t A = sn2/tijg = 0.693/t1/2 -

yf = V, + at t y ,y,

- 1/2*If*E(*1r')I*533 '

((t1/2)

IIb)) ,

aE = 931 am -I

I=reo a = mCpat ~

(j=UAat. I = I ,e "*

Pwr = Wfah I = I ,10-* N '

TIL = 1.3/u HVL = -0.693/v P = P 10 5UT(t)

P = Poe* ~

l SUR = 25.05/T SCR = 5/(1 - Kdf)

CR, = 5/(1 - Kdfx)

SUR = 25s/1* + (8 - o)T CRg (1 - K,ffj) = Gg (I keff2) -

T = (a=/s) + [(s - e)/[o] M - 1/(1 - K,g) = CR)/G, T = s/(e - s) M = (1 - KdfcIIII ~ "df1)

T = (s - s)/(As) SCM = (1 - Kdf IIE df

- = 10"* seconds .

a = (Kdf*IIIEeM * #E df"df I

T = 0.1 seconds-I e = [(t=/(T Kgf)] + [fdf /(1 + AT)]

d -

Ijj=Id2 ,2gd2 Idjj 22 P = (zeV)/(3 x 10D) 2 I = sN R/hr = (0.5 CE)/d (:neters)

- 'R/hr = 5 CE/d2 (feet) l M'scellaneous Conversions f Water Parameters ;

1 curie = 3.7 x 1010 dps 1 gal. = 8.345 lbm. 1 kg = 2.21 lbm l 1 ga]. = 3.7B liters 1 hp = 2.54 x 103 Btu /hr

! 1f 3 = 7.48 gal. 1 :nw = 3.41 x 100 ?tu/hr Density = 62.4 lbm/f:3 Density = 1 gm/cm3 lin = 2.54 c:n Heat of vaporization = 970 5tu/10m *F = 9/5'C + 32

C = 5/9 (*F-32)

Heat of fusion = 144 3w/ine u 1 At:n = 14.7 psi = g. Hg. 1 BTU = 778 ft-lbf

F EQUATION SHEET

/

~

Q = mah g , ,CRj CRo

~

Q = UAAT A = 0.1 sec I Q = Ec pAT ,

1* = 10 5 ,,e hg = kmV 2 1 = lo e-px Qe A

In 2 DEBR = 0x cl/2 p = Ak/k P = Po10SUR(t)

P = Poet/ T Vtotal = (hin - hout)DT SUR =

T _

,B-o N = Noe -At Ap 1* 6-p 17.58 watts = 1 BTU / min

- p + Ap 1 psi = 6.895 Pe ke rf - 1 1 psi = 2.036 inches lig 6 0*C p=

keff 1 psi = 27.68 inches E20 e 4*C -

Ap =

k2-k3 kk21 CRj

_ 1-keff2 CR2 3-keff) j RR = If eth i

1 S

sCR =

1-keff

uma IfM SIER CO?X :

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 24 ANSWERS -- ZION 182 -85/06/17-R.R.FERRELL ANSWER 5.01 ( .50)

D(A REF.W Fundamentals of Nuclear Rx Physics,p.8-9

-E- g6

-T^ F.:L;- C':* C'an zd ANSWER 5.0: ( .50)

B.

REF.W Fundamentals of Nuc Rv Physics,p.4-30 ANSWER 5.03 ( .50)

~

D. .

REF.H Fundamentals of Nuc Ry Physics.Ch 4 ANSWER 5.04 ( .50)

C.

REF.W Fundsmentals of Nuc R:: Physics ANSWER 5.05 ( .50)

O. ;

REF.W Fundamentals of Nuc R:: Physics,Ch 4 l l

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5. THEORY,0F NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 25 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER H5.06 ( .50)

A.

REF.W Fundamentals of Nuc Rx Physics,Ch 4 ANSWER 5.07 ( .50)

E: .

REF. Fundamentals of Nuc Rx Physics,Ch 6 ANSWER 5.08 ( .50)

C.

REF. Fundamentals of Nuc Rx Physics,Ch 6 AN3WER 5.09 ( .50)

A. -

REF. Fundamentals of Nuc Rx Physics, Ch 3 ANSWER 5.10 ( .50)

A.

REF. Fundamentals of Nuc Rx Physics, Ch 6 ANSWER 5.11 ( .50)

D.

.REF. Fundamentals of Nuc Rx Physics, Ch 6 l

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S. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 26 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL i

ANSWER 5.12 ( .50)

E: .

REF. Fundamentals of Nuc Rx Physics, Ch 5 ANSWER 5.13 ( .50)

A.

REF. Fundamentals ,of Nuc Rx Physics, Ch 5 t ANSWER 5.14 ( .50)

A.

kEF.W.Ls Press Wtr Rx Core Control, Ch 8 ANSWER 5.15 ( .50)

D. -

REF.TS,section 3.2.2.A.5 ANSWER 5.16 ( .50)

D.

REF.TS,section 3.2.2.A.6 ANSWER 5.17 ( .50)

D.

REF.

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5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 27 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 5.18 ( .50)

C.

Y REF.TS,section 3.2.2.B.3 ANSWER 5.19 ( .50)

A.

REF. C-24,p.19 ANSWER 5.20 ('.50)

D.

REF. Steam Tables 4

ANSWER 5.21 ( .50)

A+ -

REF.W Thermo-Hydraulic Principles,Ch 10 ANSWER 5.?2 (1.25)

-Decay heat comes from two principle sources.

a. Fissi.on fragments in the fuel decay by alpha, beta, and samma decay radiation. The fuel and cor e internals absorb the radiation and heat is generated. (.50)

b. ' Source' decay heat.in cores comes from activated isotopes (plutonium, anericium, and curium) that spontaneously fission and create additional fissions cr more likely create more_ fission fragments to decay. (Can be 10-20% of total decay heat). (.50)

REF: W-Fundamentals of Nuc Rx Physics, Ch 2 g ytes (BD ATILN-I y $gicC fRf%,$yi).D to TwE VeEL 1 h O i g ss 6; E L E %

l [. l

=aumeo - M;p;ragnOA%u'o* ** "

gygccTed 6T M-l l

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 28 ANSWERS -- ZION 182 -83/06/17-R.R.FERRELL ANSWER 5.23 (1.50)

a. Increase E.75]

b. Decrease [.753 REFERENCE W Thermo-Hydraulic Principles, Ch 10 a

ANSWER 5.24 (2.25)

A.To prevent an unexpected power excursion during normal operations as a result of either a moderator temperature increase or a decrease of coolant pressure B. Low power physi:s testing C.At coolant teniperatures below the power rangei BOL when Cb is at the greatest C.75 ee]

REF.TS,3.2,p.64

~

ANSWER 5.25 (1.75)

A.HPSH=Pstatic + Pdynamic - Psat B.1. Increase

2. Decrease (due to increase in suction piping H1)

3. Decrease (due to increase in fluid saturation temperature)

F.EF.W Thermo-Hydraulic Principles, Ch 4 1

l

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 29 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 5.26 (1.20)

From Fi3vre 5-3:PD at 50%-PD at 10%

600-X PCM 1200-1000 PPM 653 PCM=--------- X -------------

600-680 PCM 1200-900 PPM From Figure 5-4: Differential Boron Worth = -10.4 PCM/ PPM From Figure U-5: Initial Boron Concentration = 1000 PPM 653 PCM Boron Dilution = ----------- = 63 PPM

-10.4 PCM/ PPM l Dilution Weter in gallons = 4000 gallons OR The equation given from Figure 5-5 may be used to determine the volume. The typical value for the Mass of water in the primary is 504,000 lbs.

504 000 lbs 1000 Vw=----------- In(------ ) = 3937 gallons =Vw 8.30 1000-63 _

REF.Large PWR Core Control, p.5-27-28 ANSWER 5.27 (2.30)

A. Doubles E.40]

B.St.ays the same E.403 C . ee;bl e s QeADRoh.E5 c.40]

D. Head approaches 0 at maximum flow C.53 E.1.Encessive noise and vibration 2.Fivetuating discharge pressure 3.F30ctusting motor current

4. Reduction in pump capacity and efficiency E.15 ea]

REF.W Thermo-Hydtsolic Principles,Ch 10 1

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5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 30 ANcWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 5.28 ( .50)

D.

REF.W R:: Core Control for Large PWR's, Ch 6 ANSWER 5.29 ( .50)

B,D REF.W Rx Core Control for Large PWR's, Ch 6 ANSWER 5.30 (1.75) 1.CR move in a single bank 2.No individual rod more than 15 inches from bank demand

3. Control banks sequenced / overlap 4.RIL maintained

5. Delta I in band E.35 ea]

REF.C--35,p.39 _

ANSWER 5.31 (1.50)

Undercompensated E.53; When overcompensated the operator has no ides what IR level really is while when undercompensated the operator knows'at Icest" (conservative direction) where power is. E1.03 REF.WTC-HO-9.p.16 l d

F

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 31 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 6.01 (1.'00)

BIT is continiously recirculated by the BA transfer pumps.

REF.TS 3.8.1.E ANSWER 6.02 (2.25)

A.Dusses are stripped and ESF loads are sequenced on the bus B.ESF loads not running are sequenced on bus; loads running on bus previous to this are on due to blackout sequence C. Bus strips, blackout loads sequence on REF.B-1-3,p.32-35 ANSWER 6.03 (1.75)

A.Increasei RIL computer sees the increase in Delta T B.Increasei Pressuricer level prostam will indicate a higher level due to Tave increase C. Rods move in to try to decrease the higher Tave the systene sees D. Decrease due to the higher Tave input giving it more penalty signal E M t' _ ,o .v.t ....;c 2 ::'_ R .;. . : : ' ;:.T.vc E. Output will increase but steam dumps will not actuate because they are not armed.

REF.C-33,34 9

0 4

9

f

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 32 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 6.04 (1.50)

A. CLOSED B. CLOSED

_C.0 PEN D.VCT E.VCT [.3 ea]

REF.C-7-1,p.9-13 ANSWER 6.05 (2.25) 1.2 PORV's with a lift setting of 435 psis 2.1 PORV open

3. Pressurizer level less than 25% and pressure less than 100 psis 4.Only 1 charging pump operable REF.TS,3.3.2.6,p.82-83 ANSWER 6.06 (1.00)

NO Placing in test will deenergize the interlock circuit P-7 and unblock the low-pressurizer pressure tr'.p functions and will result in Rx protection actuation.

REF.C-34, Logic diagrams 5653D30 sh.4,6,8,16 ANSWER 6.07 (1.50) 1.RCS loop isolation valve interlock and the 25% trip on PR NI's (SU of an idle loop is supposed to be done < 10% power)

2. Flow restrictors in MS lines, heavy pipe restraints and auto protective features ( closure of MSIV's and start of ECCS)

REF.C-9,p.11 i I

L I

4

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 33 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 6.08 (1.00)

Analysis of the solubility of boron within the upper regions of the core.

Specifically at 211 degrees F the solubility of boric acid is 27.5 w/%. The concern is thet should the solubility limit be reached, the boric acid

would crystallice out and possibly restrict flow in the top of the core.

REF.C-11B,p.19 ANSWER 6.09 (1.00) f Chuts valves to Seryjee. Water Booster Pumps (SWOOO6/5), Booster Pumps trip, fire header pressure drops, fire pumps srart PEF.NPT-221, Chapter 6,p.5 ANSWER 6.10 (1.50) 5/7 et .3 er 1.Mr.it. Feed ACB1471 over current d.: 1p relay reset

2. Reserve Feed breeter ACB1472 os er- current trip relay reset

3. Diesel Generator differential current relay reset -

l 4 Main Feed breaker ACB 1471 open 4

5. Reserve Feed breaker ACB 1472 open

! 6. Diesel 'O' override relay energi:ed 7.DC 'O' supply breaker to bus 247,ACB2473 open REF.D-1-3,p.20 ANSWER 6.11 (1.00) 1.E 1i!--t1y 3 r : md i+3--the-+eut r+1-e r-coon. ore--conreec t i on -o f P ahs e w i nd i ng s 2.If a second atound should occur a sample current f3cw will be passed throv3h the citcuits *t 5 y ea, T t GRtx tD ; uEt., AtWE Tc ( th e B c c. Ocs m . c le @,) i REF.B-1-4,p.6 4

h

- ~ ,- -, ~ , , - ,,

( - 1 l

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 34 ANSWERS -- ZION 1E2 -85/06/17-R.R.FERRELL ANSWER 6.12 (1.00)

A.TRUE B. Interlocks provided to insure the system is operated as designed. Only time you want to use RHR is to supply suction to Charging /SI/ Containment spray and during this time the RWST would be empty and th'>s the Recirc sump would be the source of water for cooling the r::. These interlocks prevent inadvertantly draining the RWST to the Recire sump.

REF.C-10,p.5-6 ANSWER 6.13 (1.50)

A.1. Coil current does not match the current order within a preset time 2.Fu11 current is on too lon3 [+753 D. Protects agaist dropping a rod or overheating the coils E.753 REF.C-33,p.26 ANSWER 6.14 ( .75) -

1.4/- 12 steps between 2 rods in a bank 2.+/- 12 steps between rods and bank demand signal 3.SD banks less thsn 220 steps C.25 ea]

FEF.C-13,p.50 At'SWER 6.15 (1.50)

A. Steam void formation and degradation of DNBR B.0verheating fuel cladding C. Carryover D.0verheating E.Packup to high pressure trip /overstress piping REF.C-34rp.9-11

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'6 . PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 35 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER- 6.16 (1.50)

1. Inlet-Check valve to prevent backleakage 2.A11 piping can-withstand'RCS pressure

3. Flow. indicator 4.FCV 685 closes on high flow

5. Relief valve set at 2485 to protect piping E.3 ea3 REF.C-5,p.17 ANSWER 6.17 (1.50)

A.0 PEN-opens valve AUTO-set to open at 2335 psis f.UTO-LOW-set at 435 by PT 403 when RCS is < 250 degrees F

-D. Interlocked with. channel 458 to close at 1835 psis eku WCW V A wii.

REF.C-6,p.9 ANSWER 6.18 (1.50)

A.P-8 > 60% single loop low flow Rv trip is auto unblockedi2/4 PRNI E.53 B.P-11: 2/3 pressurizer pressure channels < 1915 psis operator can bloci the low pressure SI E.53 C.P-14: 2/3_ narrow ranse instruments in 1/4 SG's at > 70%, the Feed Reg end bypasses close, MFP's trip, and Main Turbine trips E.53 REF.C-34,p.17-18

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _ . _ _ _ _ _ . . _ _ _ _ _ _ . _ . _ . _ . . ________ __m_.__..__..____.__ _. . . _ . __ . _ . _ _ .___.__.________.____m_ __._____.

7. PROCEDURES.- NORMAL, ADNORMAL, EMERGENCY AND PAGE 36

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

~~~~ Rd656L6G5C5L 6UNTRUL ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANS9ER 7.01 s1.50)

1. Pressurizer pressure decreases below 1815 psis 2.Pressuriner level decreases below 10%

3.RCS subcooling drops below 35 degrees F [.50 ea3 REF.EOP-0, appendix B,p.10 ANSWER 7.02 (1.50)

A.1. Loss of all condensate / condensate booster pumps 2.Hi-Hi S/G 1evel or SI 3.Lo Lube Oil pressure at 4 psis ~

4.4KV bus under voltage

5. electrical overload

6. System Aux Transformer 142 trips

7. Generator 86-G1 (G2) or 86-G1B(G28) relay trip [5/7 at .15 ea.]

B.1. Verify reactor trip 2 Verify turbine trip

^

3.Ver ify AFW flow 4.Verift 'ssuricer pressure / level begin to recover

5. Veri, ierator trip 50 seconds later

6. Anno- reactor trip over the page 05/6 at .15 ea3 ANSWER 7.03 (2.50)

A.All roetine access or wor k in radiologically controlled areas where 4

personnel are NOT expected to exceed a whole body dose equivalent of 50 J

mrem / day E.753 B. Man of'1 year from January 1. [.50]

, C.All access work in radiologically controlled areas where personnel ar e oxpected to exceed a whole body dose equivaler.t of 50 mrem /dayijobs invt.1ving significant contsmination and/or airborne radioactivity may require one. [.753 D. Length of the job. E.503 F.RP 1190-1,p.12-15 4

I

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 37

~~~~RA5i5E55fEEE E5NTRUL'~~~~~~~~~~~~~~~~~~~~~~~

ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 7.04 (1.00)

A. FALSE B.TRUE C.TRUE D.TRUE REF.RP 1190-1 p.30 ANSWER 7.05 (2.00)

A.1.Pressuri er level >/= 50%

2.Pressuri er pressure > 2000 psia 3.SG 1evel in NR in at least 1 SG (feed / steaming that SG) E.33 ea]

B.1.RCS Delta T </= 1.2 x full load Delta T 2.RCS or core exit thermocouple temperatures constant or decreasing 3.SG pressure constant or decreasing at a rate

rate of decrease of RCS while maintaining SG 1evel with continuous AFW E.33 ea]

REF.NPD-229,Ch.6,p.32 "

EtC 7 ,Aiv m + 4 ANSWER 7.06 (1.75)

A. Balance between charging and letdown-HCV128 full open, PCV131 in auto or manuali Charging:FCV121 or PDP speed control E.753 B. Lifting of relief valves E.25]

C. Nitrogen-lona duration shutdown or access to RCS Solid-< 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months shutdown or does not require breaching RCS integrity E.503 REF.NPS 229

f

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 38

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~~~IRd656L6656dL'66 TR6L ANSWERS -- ZION 182 -85/06/17-R.R.FERRELL ANSWER 7.07 (1.50)

A. Low stessi pressure High steam flow rate Initial high steam senerator levels-swell E.25 ee]

B. Falling Tave Low pressurizer pressure Low pressuri er level E.25 ea3 REF.C-9,p.11 ANSWER 7.08 (1.25)

1. Restart should not be attempted until motor has been allowed to cool by standing idle for a period of not less than 30 minutes.

2.Within any 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period, number of starts should be limited to max of 3 with a minimum wait of 30 minutes; 4th start should not be a t t e nip t e d until motor has been allowed to cool for at least I hour. E.625 eal REF.C-5,p.16 ANSWER 7.09 (2.00)

A.1 decade B. 75,1.0 C.Decreasin3 SUR, Increasing RCS temperature. Increasing pressurizer press-vre (Increasing pressuri=er level)

D.179 E.20 F.1000, 10,000 REF.GOP-2,p.12-14

)

I 1

f

7. PROCEDURES - NORMAL, ABNORMAL, EMERL"_NCY AND PAGE 39

- ~ ' ~ " ' " ' ' " ' " " ~ ' ' '

~~~~RA616L65iEAL 56sTRUL ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 7.10 (1.50)

After verification of at least 1 CCP or SI pumps in service AND when the wide ranSe RCS pressure drops below 1200 PSIG (1520 for adverse contain..ent where containment pressure is 5 psis or greater).

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

REF.EOP-0,p.7 ANSWER 7.11 (2.00' A. Borate 400 PPM and determine required boron concentration C1.03 B.Reinitiate turbine trip or attempt to close valves manually. E1.03 c - uty.c >tw.

REF.EOP-1,p.5 Ebp -l ; pi ANSWER 7.12 (1.00)

May trip aSainst backflow when other pumps are in operation REF.GOP-1,p.23 ANSWER 7.13 (2.00)

A.1.No.1 seal flow high > 6 spm 2.RCP seal wtr outlet temp high efter verifying adequate CC flow 3.No.1 seal delta P <250 PSID t.33 ea]

B.I.Close leak off valve within 5 min

2. Initiate unit shutdown and be in hot standby within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 3.Stop pump when at hot shutdown [.33 ea]

REF.AOP-2 s

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7o PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 40

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~~~~R5656L665C5L C6NTR6L ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 7.14 (2.00)

A. BAT >BATP) Charging Pump Suction via:1. Emergency Boration Viv MOV8104

2. Manual Emergency Boration Viv VC8439 3.VC FC0110A and FCV0110B CCP> BIT > Cold Les Discharge V1vs [.25 ea]

B.1. Control Rod Height less than bank limit Lo-Lo point with the reactor critical

2. Failure of 2 or more RCCA to fully insert on a trio or shutdown

3. Unexplained / uncontrolled reactivity increase

4. Failure of RCMS to e:: tent that bypass is necessary E.25 ea]

REF.EOP-5 ANSWER 7.15 (1.50)

RCS pressure > 2000 PSIG AND Indicated pressurizer level > 50% of span AND

~

RCS subcooling > 50 degrees F AND Water level in at le.st 1 SG in narrow range OR Water level in 1 SG stable and AFW flow > 420 GPM REF.EOP-9 o'

f 1 8.. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 41 ANSWERS ---ZION 182 -85/06/17-R.R.FERRELL ANSWER 8.01 (2.50)

A.16,24,24,48,72,7 B.behind the panels,out of the control room C. Turnover checklist D. Standing order book REF. ZAP 10-52-3 ANSWER 8 02 (2.25)

A .4&4 N D B.Me '1tD C.7 days REF.TS,3.8,p.165 ANSWER 8.03 (1.50)

A.5 members at all times and shall not include the minimum shift crew nec- ~

essary for safe shutdown of the plant or personnel f equired for other essent' functions during a fire emergency. E.75]

B.Shi ,rtage caused by sudden sickness or home emergency. C.753 REF.TS,6.0,p.300 TS,6.0,TBL 6.1.2,p.331 ANSWER 8.04 (1.00)

Hot Shutdown within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months REF.TS Interpretations 79-1

80 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 42 ANSWERS -- ZION 182 -85/06/17-R.R.FERRELL ANSWER 8.05 (2.00)

AoShift Foreman B. Tech Staff Tech Staff Operating Engineer Operating Engineer Station Superintendent Station Superintendent SCRE Shift Engineer REF. ZAP 3-51-4 ANSWER 8.06 ( .50)

Co REF.2AP 3-51-4B ANSWER 8.07 (2.00)

A.When safety related systems are involved C1.03 Bol.To modify the boundaries of an existing out-of-sorsice job to accon.id-ate additional work or system hydros. -

2.To permit long term operation of equipment that can't be cleared for service due to outstanding Work Request or Modification related req-uirements. C.5 ea3 REF. ZAP 14-51-2 ANSWER 8.08 (2.00) loSevere weather conditions threaten safe transport.

2.A signficiant radiological hazard would be encountered.

30There is a security threat occuring which would have an adverse inipact on the personnel while leaving the site.

4. Conditions similar to these in magnitude which in the opinion of the Station Director : would adverrsely aff ect the site personnel.

REF.EPIP 360-1

i

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 43 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 8.09 (1.75)

A. Station Superintendent or alternate E.75]

B. Shift Engineer

-Shift foreman Ghift Control Room Engineer Senior Experienced NSO E1.03 REF.EPIP110-1,p.2 ANSWER 8.10 (2.00)

A.NO B.NO C.YES D.NO REF. Tech Specs ANSWER 8.11 (1.00)

TS 3.05 applies-nothing required if the corresponding emergency source is available and all r edundant systems are oper able , 7 Dtws nmt omariO4 REF. Tech Specs ANSWER 8.12 (2.00)

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

2. Maintenance of a los book / clipboard for each "R' key 3.Accountin3 for each 'R* key at end of shift 4.Forwardins filled out los sheets to the Office Supervisor E.5 ea3 REF. ZAP 5-51-15 ,

l

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8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 44 ANSWERS -- ZION 1&2 -85/06/17-R.R.FERRELL ANSWER 8.13 (2.00) 1.Incore thimbles are in the reactor vessel 2.Incore detectors are taken out of service 3.Incore detectors are in the storage position or are inserted in the reactor vessel _C.66 ea]

REF. ZAP 5-51-16, p.2 ANSWER 8.14 (1.00)

</= 5X steady sourcs range counts but no-_h4;"er than 25 REF.FHI-00, p.3-ANSWER 8.15 (1.50)

Temporary Procedur e change-intent of existing procedure SHALL not be changed Special-SHOULD be used when an intent change is necessary REF.7AP 5-51-4 W.___.________._.____________.._.________.-____ -

ML20132F574

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