ML20206F723

Exam Rept 50-295/OL-87-01 for Exam Administered During Wk of 870323.Exam Results:Four Candidates Passed Exam

ML20206F723
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	04/09/1987
From:	Burdick T, Damon D, Sunderland P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20206F702	List: ML20206F698 ML20206F723
References
50-295-OL-87-01, 50-295-OL-87-1, NUDOCS 8704140346
Download: ML20206F723 (53)

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U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-295/0L-87-01 Docket Nos. 50-295; 50-304 Licenses No. DPR-39; DPR-48 Licensee: Commonwealth Edison Company ATTN: Mr. Cordell Reed Vice President Post Office Box 767 Chicago, IL 60690 Facility Name: Zion, Units 1 and 2 Examination Administered At: Zion Station, Zion Illinois Examination Conducted: Week of March 23, 1987 Examiners: ad . b wek M k 4/B/87 Paul R. Sunderland Dat'e 9ft/f7 Darrel J.) Damon Date Approve.d By: kbi I Thjfmat M/ BurdicV, Chief Date 4 'l-5 7 Operating License Section Examination Summary Examination administered on the week of March 23, 1987 (Report No. 50-295/0L-87-01)

Examinations were administered to four senior operator candidates.

Results: Four candidates passed the examination.

8704140346 870A10 PDR ADOCK 05000295 V PDR

DETAILS

1. Examiners P. R. Sunderland, NRC Region III D. J. Damon, NRC Region III

2. Examination Review Meeting A copy of the examination and answer key was given to facility for review at the conclusion of the written exam. Facility personnel delivered their comments to the Chief Examiner after the exit meeting. The comments and resolution of these comments are Attachment 1 to this report.

3. Exit Meeting On March 26, 1987, at the conclusion of the replacement examinations, the examiners met with members of the plant staff to discuss findings made during the course of the examinations. The following personnel attended the meeting:

E. Fuerst, Facility Superintendent of Production M. Carnahan, Facility Training Supervisor W. Stone, Facility QA Superintendent T. Blake, Facility Training Instructor D. Clark, Facility Training Instructor M. Holzmer, NRC Senior Resident Inspector P. Sunderland, NRC Examiner D. Damon, NRC Examiner The following areas were discussed:

a. Generic weakness exhibited by the candidates included:

• Candidates failed to consistently check Technical SpecificationsinconjunctionwithuseofA0P-9during instrument failures.

b. Generic strength noted included:

• Monitoring and follow-up of the bistable tripping during instrument failures.

ATTACHMENT Zion Exam Report No. 50-295/0L-87-01 Facility Comment:

5.01 c. The correct answer depends on the assumption made regarding the startup procedure.

a. If reactivity addition increments are required to be a specific number of rod steps (ie., 50 steps) followed by a wait period sufficient for count rate to stabilize, the 1/M plot will be unaffected by a change in rod speed.

ANSWER: NO CHANGE.

b. If reactivity addition increments are required to be a given time of rod withdrawal followed by a specified wait time before taking data, the rod speed increase will yield a 1/M plot which over predicts criticality.

ANSWER: 0VER-PREDICT (non-conservative).

Therefore recommend either of the above answer be accepted.

NRC Resolution:

Comment accepted. Answer modified to include "no change."

Facility Comment:

5.11 a. The answer should read " increase slightly',' per the attached pages from

Reference:

W. Thermal-Hydraulic Principles and Applications to the Pressurized Water Reactor II pp 10-47

and 10-48.

NRC Resolution:

Comment accepted. Answer key modified.

Facility Comment:

5.13 The answer key is wrong when converting 1600 psig to absolute pressure. 1600 psig = 1614.7 psia not 1585.3. With the correct conversion the answer works out to be 250 psig.

NRC Resolution:

l Comment accepted. Answer key corrected.

i Facility Comment:

i 5.17 The cited reference established the differential boron worth

, dependency on moderator temperature, but does not develop a mechanism whereby boration at a constant power produces a AI shift in the positive direction. It is recommended that i

answers involving the following concept, which is developed in '

Zion Station approved training materials, be accepted:

a. Boration with no change in power nor rod position will l product the same magnitude reduction in Th, Tavg, and Tc.

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b. The mass density change per *F for Th is greater than for Tc, thus the value of MTC for Th is greater (more negative) than MTC for Tc. (ref. pgs. 3-20 to 3-21)

c. Therefore the temperature reduction will add more positive

reactivity to the upper section of the core than to the j lower section, thus driving AI in the positive direction.

1 NRC Resolution: )

Comment accepted. Answer key expanded to include this acceptable

alternative answer.

4 i Facility Comment:

! 6.04 a. Since the plant is at 100% power, the MFP speed control program j

{ is at a maximum value. Therefore the change in steam flow I signal would have no direct effect on the MFP speed control

circuitry. The answer should read

" Steam flow signal would I

increase causing an immediate SF-FF mismatch which causes the FW Reg valves to open up to match feel flow to steam flow.

Feedwater flow rate increases. Opening the FRVs causes the j differential pressure to decrease which will required an

( increase in MFP speed to compensate.

NRC Resolution:

!' Comment accepted. Answer key expanded to include the effects of the feed reg valves opening.

i Facility Comment:

6.11 The answer key to all parts should allow some tolerance for

the pressures given. In addition, Technical Specification No. 3.8.5.A.1 states that "each accumulator shall be l pressurized to at least 600 psig . . . ."therefore, the answer j to Part 2 should be 600 psig with the above addressed tolerance.

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NRC Resolution:

Comment accepted. Answer key modified to include a range of acceptable

pressures. ,

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Facility Comment:

7.12 The wording of this question leads the candidate to believe he must

send at least one of the operators into the containment. Therefore,

! operator candidate No. 2 would be the correct selection because he j would only be violating an administrative limit.

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NRC Resolution:

Comment not accepted. The question did not state that the four candidates

that data was available for, were the only candidates available to perform the job; therefore, an acceptable alternative is to search for another acceptable candidate. As acknowledged in the facility comment, Candidate No. 2 would be i violating an administrative limit; therefore he is unacceptable. However, Candidate No. 4 is acceptable since he will not be violating the quarterly i whole body limit and the maximum permissible lifetime dose is only limiting j when it is desired to exceed 1.25 Rem /qtr whole body.

} The answer key is changed to read " Candidate No. 4 acceptable since he will not violate the whole body limit of 1.25 Rem /qtr or the administrative limit of 300 mrem / week."

e Facility Comment:

8.02 a. The answer should read Station Manager per Reference EPIP 110-1, j pg. 2 Revision 7.

NRC Facility:

Comment accepted. Answer key modified.

4 Facility Comment:

8.03 c. The answer should be N0 because the information given does not '

include; the tank conUnuously recirculating, or having two channels j ofheattracingoperableontheassociatedinjectionandrecirclines j per Technical Specification 3.8.1.E.2 and 3. l t

i NRC Resolution:

i Comment not accepted. The way the question was worded, a valid assumption on I the part of the candidate would be that if not addressed, all other conditions 4 were acceptable for meeting operability requirements. The answer key remains unchanged. However, credit will be given for an answer of "no" as long as the

! appropriate explanation is also given.

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l Facility Comment:

1 1 8.08 The answer given in the answer key appears to be an answer to a different question. The answer should read:

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! a. 200

! b. 320 1 REFERENCE

! Technical Specifications 3.3.1.C.2, 3.3.2.D  ;

NRC Resolution:

Comment accepted. Answer key modified.

I Facility Comment:

8.16 " Normal" reactor operations should be interpreted as the reactor i

operating (critical) at some power level. Therefore the PORV's  !

or the Reactor trip setpoint of 2385 psig, or

! o)eningat2335psg,iesliftingat2485psigwillpreventtheRCS tie Pressurizer sa et from reaching 2735 psig during normal" reactor operations.

l NRC Resolution: ,

! Comment not accepted. The question clearly asked for the Technical i Specification maximum pressure limit. The intermediate pressure setpoints of PORVs, Safeties or Reactor trip setpoints are not the maximum pressure limit as  ;

stated in Technical Specifications. The use of the word " Normal" should not be j used by the candidate to limit the scope of possible answers. The answer key )

4 remains unchanged.

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$ In addition to the above noted modifications, the following changes were I i made by the examiner on the answer key during the course of grading the j test:

i j 7.09 a. N44 upper normalized current was corrected to 0.528 l 7.10 Step 4, Valve VC 8139 was changed to VC 8439.

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? MASTER COP'y U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION i

l FACILITY: _ZIQU_162________________

REACTOR TYPE: _PWB-BEgg________________

DATE ADMINISTERED: _QZ493429________________

EXAMINER: _QQM961_Q3_______________

CANDIDATE: _________________________

INSIBUGIIQUS_ID_GoN9I90IE1 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 cateSory and a final grade of at least 80%. E>. amination papers will be picked op six (6) hours after the examination starts.

% OF CATEGORY  % OF CANDIDATE'S CATEGORY

__2669E_ _19166 ___SG9BE___ _YoLVE__ ______________GoIEG9BI_____________

_EEA99__ _ZEz99 ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

________ 6. PLANT SYSTEMS DESIGN, CONTROL,

_3EA99._ _29199 ___________

AND INSTRUMENTATION

________ 7. PROCEDURES - NORMAL, ABNORMAL,

_2EA99__ .25199 ___________

EMERGENCY AND RADIOLOGICAL CONTROL

_EE499._ _2EA99 ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 199299__ ___________ ________% Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature MASIER CCiPJ

l %$ ' h NRC RULES AND CUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply!

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3. Use black ink or dark pencil 90ly to facilitate legible reproductions.

4. Print your name.in the blank provided on the cover sheet of the examination.

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5. Fill in the date on the cover sheet of the examination (if necessary).

6. Use only the paper provided for answers.

7. Print your name in the upper right-hand corner of the first page of gggb section of the answer sheet. I

8. Consecutively number each answer sheet, write 'End of Category __' as appropriate, start each category on a ogg page, write gely go gDg sidt  ;

1 of the paper, and write 'Last Page" on the last answer sheet.

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9. Number each answer as to category and number, for example, 14, 6.3.

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10. Skip at least tbtgg lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility liittgigtg.

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13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

J 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the gggt1Dgt only.

17. You must sign the statement on the cover sheet that indicates that the

, work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed. l l

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18, When you complete your examination, you shall '

a. Assemble your examination as follows:

(1) Exam questions on top.

(2) Exam sids - figures, tables, etc.

, (3) Answer pages including figures which are part of the answer.

b. Turn in your copy of the examination and all pages used to answer the examination questions.

c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.

d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

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IUEB5001Ne51GE .

QUESTION 5.01 (1.00)

What effect will each of the following have on a 1/M plot? Limit your onswer to UNDER-PREDICT criticality (conservative), DVER-PREDICT criti-i cality (non-conservative), or NO CHANGE. Consider each case separately.

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(.25 ea)

c. time interval between rod pulls on a startup is changed from 1 minute to 30 seconds.

b. intermediate ranse nuclear instrumentation channels are over-compensated.

c. rod speed is changed from 48 steps / min to 72 steps / min

d. source strength immediately prior to the startup changed from 4 cps to 10 cps.

QUESTION 5.02 (2.50)

Compare the CALCULATED Estimated Critical Position (ECP) for a startup to be performed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a trip from 100% power, to the ACTUAL control rod position if the followins events / conditions occurred. Consider each independently. Limit your answer to HIGHER than, LOWER than, or SAME as the CALCULATED ECP.

o. RCS pressure is increased t y 50 psi two minutes prior to l

criticality. (0 5) l

b. The startup is delayed until 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the trip. (0'.5)  !

c. The steam dump pressure setpoint is increased to a value just l below the Steam Generator PORV setpoint. (0 5) 1

d. Condenser vacuum is reduced by 4 inches of Mercury. (0 5)

o. All Steam Generator levels were raised by 5% one minute prior to the l ECP beins reached. (0.5)

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' PAGE 3 Ezl_IBEQBY_QE_HUGLEeB_EQUEB_EleHI_QEEB6IIQUt_ELVIDEt_eHQ IHEE5QQ!NedIGE ..

QUESTION 5.03 (1.50)

o. Does Beta bar effective Increase, Decrease, or Remain the Same, from BOL to EOL? Briefly explain your choice. (1.0)

b. For equivalent positive reactivity additions to a critical reactor, will the SUR be the Same, Larger, or Smaller at EOL as compared to BOL? (no explanation necessary) (0.5)

QUESTION 5.04 ( .50)

At BOL, the components of the power defect in an INCREASING order of significance (reactivity value) aret (choose one)

a. Void, Doppler, MTC l l

b. Void, MTC, Doppler

c. MTC, Void, Doppler l

d. MTC, Doppler, Void l l

00ESTION 5.05 (2.00) i 7'

a. At what axial location in an operating pWR core is the critical heat flux at the MAXIMUM value? (Limit your answer to top, middle, or bottom) (.5)

b. How does the MINIMUM critical heat flux value chanSe (increase, decreas no change) as the following parameters are INCREASED? Consider each separately. (.5 ea)

1. Tave

2. RCS pressure

3. RCS flow l

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QUESTION 5.06 ( .50) )

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

The crit.ical data was taken again at the proper IR level (1E-8 amps).

Assuming RCS temperatures and boron concentrations were the same for each cet of data, is the critical rod height taken at the proper IR level HIGHER THAN, THE SANE AS, or LOWER THAN the rod height taken two decades below?

OLESTION 5 07 (3.00)

Indicate at which time in core life (BOL or EOL) the following accidents will result in a higher final steady-state power level. Briefly explain why, including in your answer any effects due to reactivity coefficients.

a. Main steam line break at 50% reactor power (no reactor trip) (1.0)

b. Total loss of coolant flow at 50% power (no reactor trip) (1 0)

c. Rod withdrawal accident from low in the source range prior to any significant reactor coolant temperature increase. (1.0) 1 OUESTION U.08 ( .50)

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

a. Enthalpy decreases, quality constant.

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b. Enthalpy increases, quality constant.

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c. Enthalpy constant, quality decreases.

d. Enthalpy decaeases, quality decreases.

1 I OUESTION 5.09 (1.50)

The reactor it prodccing 100% rated thermal power at a core delta T i of 42 degrees and a nass flow rate of 100% when a blackout occurs.

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

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PCCE 5 52__IBEQBI_QE_HUGLEeB_EQWEB_EL8HI_QEEBeIIQHt_ELUIDit_eHQ

. IMEBBQQIdedIGE QUESTION 5.10 (2.00) t A dropped control rod (with all other control rods out) is worth cpproximately 200 pcm while a stuck control rod (with all other control rods in) is worth about 1000 pcm, even though the same rod could be considered in both esses. Explain this phenomenon.

i QUESTION 5 11 (1 75)

I Answer the following concerning general centrifugal pump characteristics!

a. What happens to system flow rate (INCREASE, DECREASE or REMAIN CONSTANT) when a second centrifugal pump is started in series with a running pump? State the magnitude of the change, if any. (.5)

b. What happens to pump head (INCREASE, DECREASE, or REMAIN CONSTANT) if  !

pump speed is doubled? State the magnitude of the change, if any.(.25)

c. Define pump runout in terms of pump head and system flowrate. (.5) '

d. List 4 indications of pump cavitation. (.5)

GUESTION 5 12 (1.50)

The plant is in hot shutdown with pressure in one of the steam generators at 805 psis. Use the attached steam tables to answer the following questions.

a. What is the steam temperature in the steam generator? (.5)

b. If an atmospheric relief valve is openeo for 1 minute, what will be the temperature of the discharged steam? (assume discharge pressure is atmospheric) (.5)

c. Will the discharged steam be superheated, saturated, or a mixture of saturated steam and water? (.5) l l

l OUESTION 5.13 (1.75)

To what value must steam generator pressure be adjusted to in order to maintain a 200 degree F subcooling margin in the RCS, when RCS pressure is reduced to 1600 psig? Show all work. Specify answer in units of pSIC.

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QUESTION 5.14 (1.50)

Describe the production and removal mechanisms for Xenon-135 and Samarium-149.

QUESTION 5 15 (1 00)

How will each of the following affect a calorimetric power calculation?

Limit your answer to CALCULATED LOWER THAN ACTUAL, CALCULATED HIGHER THAN ACTUAL, or CALCULATED SAME AS ACTUAL. Consider each case separately.

(.33 ea)

o. measured feedwater temperature is 10 degrees lower than actual feedwater temperature

b. measured steam generator pressure is 30 psig lower than actual steam generator pressure

c. measured feedwater flow is 1E5 lbm/hr higher than actual feedwater flow OUESTION 5.16 (1 50)

State how each of the following will affect shutdown margin. Limit your cnswer to INCREASE, DECREASE, or NO CHANGE. Consider each case separately.

Assume cycle 9, EOL. (.25 ea)

o. boron concentration is decreased 20 ppm while maintaining constant power and no rod motion

b. bank D rod height is increased from 125 steps to 200 steps while maintaining constant power and baron concentration

c. power level is increased from 30% to 60% with no rod motion and constant boron concentration

d. reactor trip ,

o. while shutdowne the RCS is cooled down by 40 degrees

f. shutdown banks are fully withdrawn during a startup while maintainin3 constant RCS temperature and boron concentration

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PAGE 7 h2_IHEQBl_QE_HWGLE6B_EQUEB.ELeHI_QEEBeIIQHt_ELUIQEt_eHQ IHEBBQQ1He51GE QUESTION 5.17 (1.00) l At EOL after a power transient, xenon is oscillating axially in the core. With the control rods all the way out, the operator can force l a very negative delta-I toward the positive side by borating. Explain '

this phenomenon.

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611'_E L 6 HI_ SIEIE 55_ Q E E IG H1_ G Q UIB Q L t _ e H Q _I N EIB W H E MIeIIQ N PAGE 8 QUESTION 6.01 (1 50)

Describe the response of the 4160V ESF buses of Zion Station under the following conditions:

, c. A station loss of off-site power (blackout) occurs 30 seconds after an ESF actuation has occured. Assume off-site power was available l initially. (.5) l

b. An ESF actuation occurs 5 minutes after a station blackout. (.5)

c. A blackout occurs after the ESF signal has been

• reset

• to allow ,

realignment to the recirculation phase after an accident. (.5)  !

l QUESTION 6.0? (1.50)

What is the setpoint, coincidence, and purpose of each of the following permissives  ;

c. P-8 l

b. P-11

c. P-14 (.5 ea) l l

OUESTION 6.03 (2.25)

The following questions concern the Component Cooling Water System.

1 j o. Name THREE alarms that could indicate an RCS to CCW 1eak. (.75)

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b. Describe three means by which the CCW system is protected against an overpressure condition if an RCS to CCW rupture occurred in the RCP thermal barrier. (1.5) i I

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I QUESTION 6.04 (1.50)

o. If while operating at 100% power, the pressure compensation ,

signal to the SGWLC system fails hight l i

1. Describe the response of the feedwater system

(.75)  !

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l 2. What would be the long term effect on steam generator level?

l Assume no operator action or trip actuation. (.5)

b. What input signal is used as the reference signal for (.25) the feedwater pump speed control system programmed Delta P?

GUESTION 6.05 (2.00)

Indicate which of the Encore Nuclear Instrumentation Ranges (SOURCE, INTERMEDIATE, or POWER), will correctly match with the fo110 win 3 statements. More than one may apply to each.

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

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

c. Utilizes boron in its detectors.

QUESTION 6.06 (1 00)

The following concern the CVCS at Zion.

a. If left in automatic control, what position should PCV-131 be found in two minutes after a safety injection initiation? (.25)

b. Why is letdown flow limited to 120 spm? (.5)

c. With only the PD pump operating at powere which valve (s) is/are utilized to vary RCP seal injection flow from the control board?

(Either noun name(s) or number (s) acceptable) (.25) l l

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62) PL6HI_31EI[Uf_Q[EIGU1_GQUIBQLt_6HQ lH51ByU[HI6119H PAGE 10 h

QUESTION 6.07 (2 25) l What is the INITIAL response of the Rod Control System (RODS IN, RODS OUT or NO CHANGE) and BRIEFLY EXPLAIN why the change will or will not occur for i the following instrument failures. Assume that the plant is at 50% load with all systems controlling in automatic.

o. Loop B(2) Cold Les RTD fails LOW. (.75)

b. Turbine Impulse Pressure (PT-505) fails LOW. (.75)  !

c. Power Range lower detector (NI-44) fails HIGH. (.75)

OUESTION 6.08 ( .50)  :

Protective signals that initiate Reactor Protection and Engineering Safety Features use a 'de-energize to operate' bistable principle.

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

QUESTION 6.09 (1.50)

The reactor is in hot shutdown with RCS pressure at 1775 psis. The reactor i 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. Explain why you would allow /not allow him to do this.

QUESTION 6.10 (2.00)

The following concern target flux difference (delta I target)!

a. What three conditions are required to be satisfied per Technical Specifications prior to determining delta I target? (1 5)

b. If the delta I target is obtained with the reactor at 85% power, how is the 100% target value determined? (.5)

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• 62 'ELeHI_IIIIEHE_DESIGHz_GQUIBQLt eHQ_INEIEWHEMIeIIQH QUESTION 6.11 (2.25)

Following a safety injection actuatione the CVCS aligns to take a cuction from the RWST and discharge from the CCP's via the BIT to the RCS cold legs. What are the other three (3) ECCS flow paths to deliver borated water to the RCS and at what pressure do they begin delivering this water?

QUESTION 6.12 (1 50)

Indicate whether the OT delta T AND OP delta T setpoints will INCREASE, DECREASE, or REMAIN THE SAME if the following parameter changes occur.

Consider each change separately. (No explaination required.)

I a. pressurizer pressure is increased by 100 psis (.5)

b. power range N41 lower detector fails high (.5) i c. Tava is less than full load Tavs with reactor power at 100% (.5) l OUESTION 6.13 (2 00)

I j Concerning the RHR system, describe the interlocks that must be satisfied in order to open the fo110 win 3 valvest ,

a. MOV-RH0700A (RHR pump suction valve train A). (1 0) 4 l b. MOV-RH07000 (RHR pump suction valve train B). (1 0) 1 OUESTION 6.14 (1 75)

Concerning the auxiliary feedwater systemt

a. What three conditions will cause an automatic start of the motor i drivere auxiliary feedwater pumps? (include coincidence) (.75)

b. What four conditions will cause an automatic start of the turbine driven auxiliary feedwater pump? (include coincidence) (1 0)

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hl'EkeNI_EIIIEHE_DESIGHi GQUIBQL1_eHD INEIBWHHI6IIQH

_ PAGE 12 QUESTION 6.15 (1 50) i

o. What condition (s) will activate the second level undervoltage j protection timer associated with an ESF bus? (.5)

I b. What automatic actions occur fo11owin3 activation of the second level j undervolta3' Protection timer? (1 0) 1 I

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Zi)EBQCEQQBEE__HQBdeki_eEHQBuekt_ENEBEEHt1_ANQ BeQIQLQEIGeL_GQUIBQL QUESTION 7 01 (2.50)

o. When is a Type 1 Radiation Work Permit (RWP) required? (.75)

b. What is the maximum time period that a Type 1 RWP is valid? (.5)

c. When is a Type 2 RWP required? (list two) ,

(.75)

d. What is the maximum time period that a Type 2 RWP is valid? (.5) l QUESTION 7.02 (2.00)

A. What are the 4 pump and valve lineups used at Zion to perform an

> Emergency Boration per E0P-Se ' EMERGENCY BORATION'? (1.0)

b. What are the 4 conditions that require emergency boration per E0P-5?

(1.0)

GUESTION 7.03 (2 00)

Answer the following according to COP-2, PLANT STARTUP. (exclude physics testing) l

a. The shutdown banks do not need to be withdrawn prior to dilution if what condition is met? (.75)

b. Which SI signal must be unblocked prior to diluting below the required cold shutdown baron concentration? (.75) l c. Why must the startup of Main Feedwater Pump B or C be delayed until i

ready to go off Auxiliary Feedwater? (.25)

d. Why is it required that the Main Turbine bearing lift pump control l i switch be placed in the AUTO (after-trip) position at the end of the i turbine oil pump interlock checks? (.25) l l

1 i

(summa CATECORY 07 CONTINUED ON NEXT PAGE mamma)

) ,

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

,d ..-

Z.PRQQgQgggg_ _NQSM8(1_AENQBM8(t_EngSQgNQY_gNQ PAGE 14 BeQIQLQGIGeL_GQNISQL QUESTION 7.04 (3.00)

POWER HISTORY (fuel cycle 9) 8/1 -- 0800 hrs. the reactor is at 1% power after a refueling shutdown with oil physics testing complete. Power was raised to 22% maximum at 1800 hrs on 8/1.

8/7 -- 1300 hrs. power ramp commenced to 50% when at 1430 hrs a trip occurred at 32% power from a feed pump failure.

8/11 -- 0030 hrs. the reactor is at POAH and a power ramp is commenced.

At 0830, 50% power is achieved.

8/15 -- 0800 hrs commenced raising power to 90% power, which is obtained  ;

ot 1200 hrs. on 8/16.

8/16 - power is held at 90% until 1735 hrs. on 8/18 when the reactor is )

tripped due to an instrument tech. error. l

o. Describe any fuel conditioning limit violations. (2 0)

b. ASSUME: Control rods for bank D were at 220 steps prior to the trip from 90% power.

The NORMAL power rate of change is 20% per hour unless special limits apply. .

ALL POWER CHANGE IS TO BE CONSIDERED WITH RODS ONLY, NEGLECT BORON CHANGE REQUIREMENTS.

NO FUEL CONDITIONING LIMIT VIOLATIONS FOR PREVIOUS HISTORY.

What would be the minimum time required to achieve 100% power with rods at 220 steps, from the time of reaching 1% power on the recovery from 90%7 (1 0) l OUESTION 7.05 (1.50)

Per E-0, REACTOR TRIP OR SAFETY INJECTION, list all the criteria for '

stopping the RCP's. (state any coincidence)

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

• / PAGE 15 Z z _'_E S Q G EQUE E E _:_ H Q B d e k t _ eE H Q B d e k t _E B E B G E N Gl_98 Q BeQIQLQEIGek_GQHIBQL .

~

l QUESTION 7.06 (2.00) j Per E-0, REACTOR TRIP OR SAFETY INJECTION:

e. What TWO conditions constitute ADVERSE CONTAINMENT conditions? (1.0)

b. If ADVERSE CONTAINHENT conditions had been present, list all conditions that must be met in order to again use normal plant parameter indications. (1.0) i

. l l l 00ESTION 7.07 (1.50)

Per GOP-4, PLANT SHUTDOWN AND C00LDOWN:

a. What precaution must be taken with regard to F-essure control before stopping an RHR pump when solid? (.5)

b. What is the minimum allowable RCS pressure when solid with one RCP running? (.5)

c. When Nitrogen pressure control is used instead of solid plant control, I what component provides RCS overpressurization protection?

(.5)

OUESTION 7.08 (2.00)

According to E-0 FOLDOUT PAGE, what are FOUR conditions that indicate that Natural Circulation Flow is occurring? Assume containment conditions are normal.

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

Y *l PAGE 16

. ZA._BBQEEQQBEE_ _UQBd8kl eEdQBd6ki_[d[BGEUGl_6NQ BeQIQkQGIG6L_GQUIBQL

~

l i

QUESTION 7.09 (1.50)

Given the following data concerning the power range nuclear instruments: )

N41 N42 N43 N44 upper actual reading 52 mA 56 mA 58 mA 57 mA vpper 100% current 104 mA 112 mA 112 mA 108 mA l i

lower actual reading 53 mA 55 mA 56 mA 54 mA lower 100% current 106 mA 110 mA 112 mA 108 mA

o. What is the quadrant power tilt ratio (OPTR)? (.75)

b. Assuming that the OPTR is >1.09, what actions are required by Technical  :

Specifications? (include options if any) (.75) l I

l QUESTION 7.10 (2.00) l What are the FOUR immediate actions in FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION /ATWS? Include details of actions to be taken if an expected response is not obtained. (2.0) l QUESTION 7.11 (2.00)

Per RP 1190-1, Zion Radiation Protection Standards:

a. What are the emergency dose limits for the whole body and the extremities for the purposes of saving a life? (1.0)

b. What are the emergency dose limits for the whole body, the extremities, i and the thyroid for less urgent actions? (1.0)

I 1

i

(***** CATEGORY 07 CONTINUED ON NEXT PAGE x*zum) i

'Z_._ESQGEQUBES_:_HQBdekt_8EHQBdekt_EMEEGENGl_eHQ PAGE 17 BBRIQLQEIGBL_GQUIBQL QUESTION 7 12 (3.00)

While functioning as shift supervisor, a condition arises which requires entry into containment while critical at 40% power. The operator entering will receive a whole body dose of 40 mrem. You have the following data available to you Candidate 1 2 3 4 Sex male male female male Age 27 38 24 20 Wk/ exposure 35 mrem 280 mrem 0 arem 30 mrem Otr/ exposure 1230 mrem 970 mrem 460 mrem 1120 mtem Life exposure -

54730 mrem 5200 mrem 9970 stem Remarks history -

4 months -

unavailable pregnant Each candidate is technically competent and physically capable of perform-in3 the task. Emergency limits do not apply and time constraints do not permit obtaining authorization for an exposure limit increase. Give your reasons for acceptins or rejecting each candidate for the job.

(m**** END OF CATEGORY 07 musum)

H 22_ e Q UIMISIB eIIM E _E B Q G E Q U E E H1_Q Q H QIIIQ N $ 1.88 Q _(IMII611Q PAGE 18 NE OUESTION 8.01 (1 00)

On May 5th a valve lineup was performed on No.1 A Centrifugal Charging pump to place it in service following routine maintenance. An entry is included in the Standing Orders to minimize usease of the pump. On May 18th an Auxiliary Operator reports that the discharge valve is closed and can not be physically opened. 1B CCP, both RHR and both SI trains are operable.

Answer the following:

a. Is the pump OPERABLE per Tech Specs? (.25)

b. Has the Tech Spec LCO been violated? (.25)

c. How lon3 can reactor operation continue in this condition? (.5)

GUESTION 8.02 (1.00) a.

Who normally assumes the position of Station Director during a GSEP Emer3ency?

(.25) b.

List the 3 people in order of preference that can acsume the position if the person ir. Part A above is not available. (title only) (.75)

GUESTION 8.03 (1.00)

Per Technical Specifications, are the following components operable based on the below information? (YES/NO only-no explanation required): (.25 ea) a.

SI pump is started manually from the MCB and the' discharge pressure and recirc flow is 15% away from a point on the pump head curve.

b. RWST boron concentration is 1900 PPM. The plant is in mode 2.

c. BIT contains 900 gallons of 11 5 to 13% by weight Boric Acid at a temperature of 150 degrees F. The plant is in mode 1.

d. During a refueling outa3e, a Main Steam Isolation valve is tested and strokes from full open to full closed in 30 seconds.

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

'~

Eti eQUINIEISoIIVE_ESQGEQWBEEz_GQHQIIIQUEt_eHQ_LIBII6IIQUE PAGE 19 QUESTION 8.04 (1.50)

Per ZAP 5-51-4, PROCEDURE CONTROL AND APPROVAL, when would a SPECIAL PROCEDURE CHANGE be used and when would a TEMPORARY PROCEDURE CHANGE be used?

DUESTION 8.05 (1.50)

Indicate whether the following is a primary function of the Shift Engineer OR Shift Foreman (licensed), according to ZAP 1-51-1, STATION ORGANIZATION.

(.25 ea)

a. Authorize Surveillance.

b. Act as Fire Chief.

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

d. Placing equipment in or out of service.

e. Review Unit 1o35+

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

QUESTION B.06 (1.50)

What are THREE conditions that a test or maintenance procedure must meet such that lossing of wires and jumpers is not required according to. ZAP 3-51-4, " Procedure Governing the Use of Temporary Jumper cables, Lifting of Terminated Wires, the Bypassing of Alarms, or the Installation of Mechinal Blocks or Bypasses"?

QUESTION 8.07 (1.50)

Assume that delta flux target is (-1) and turn-on power fraction (Pt) is 100%.

a. What action /s is/are required per Technical Specifications with delta I at (-10) for the last 61 minutes and reactor power at 70%? (.75)

b. What action /s is/are required per Technical Specifications if delta I is (-9) when reactor power is 95%? (.75)

(xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE xxxxx)

l H2_'_6DHIBISIBoIIME_EB9CEQUBEf t_C9HQIIIQNgg_8HQ_(IMII611gNS PAGE 20 m

OUESTION 8.08 (1.00)

Per COP-1, PLANT HEATUP, answer the following: (.5 ea)

a. All three pressurizer safety valves must be operable anytime RCS temperature exceeds ______ degrees.

b. Spray flow into the pressurizer will not be initiated if the temperature difference between the pressurizer and the spray fluid exceeds ______ degrees.

QUESTION 8.09 (1.00)

What four conditions must be met per GDP-1, PLANT HEATUP, in order to open a No. 1 seal bypass valve?

DUESTION 8.10 ( .75)

Paragraph K of 10 CFR 50 54 states 'an operator . . . shall be present at the controls at all times during the operation of the facility.' According to ZAP 10-52-3, ' Shift manning, relief, and turnover", what is meant by

'at the controls'?

GUESTION 8.11 (2.50)

List any 10 of the 14 accident monitoring instruments required to be operable per Technical Specification 3.8.9 in modes 1, 2 or 3. (.25 ea)

GUESTION 8.12 (2.00)

List 4 of the 6 conditions that must be met per Technical Specifications to insure that containment integrity is intact.

GUESTION 8.13 (2.00)

Per Technical Specifications, what 4 conditions must be met so that continuous monitoring of hot channel factors is not required during normal operations?

(xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE xxxxx)

.j .-

011_0Db1HISIBBIIVE_EB9GEQWBgS_ggggIIIgNS_eyg_LIBIIBIIQUE t t PAGE 21 QUESTION 8.14 (2.25)

What three conditions must be met per ZAP 5-51-16, " Reactor Cavity (Incore Shaft) Acess Control", in order to allow access to the incore shaft area? -

GUESTION 8.15 ( .50)

In order to remove a HOLD CARD from a breaker and reclose the breaker, authority must be granted by: (choose one)

a. the shift engineer

b. the operator performing the maintenance

c. the person for whom the HOLD CARD was placed, or in his absence his supervisor

d. the load dispatcher i

e. a and c

f. c and d S. b and d QUESTION 8.16 (1.00)

Per Technical Specifications, what are the minimum and maximum RCS pressure limits during normal reactor operations?

OUESTION 8.17 (1.50)

Per Technical Specifications, how and when is the Quadrant Power Tilt Ratio (OPTR) determined if a nuclear instrument powe'r range excore detector channel is inoperable?

DUESTION 8.18 (1.50)

Per Technical Specifications section 3.21, " Fire Protection', name three (3) circumstances that require that a continuous fire watch be established.

(x**xx END OF CATEGORY 08 xxxxx)

(xxxxxxx*xxxxx END OF EXAMINATION xxxxxxxxxxxxxxx)

. .: 1

'5_ U_IH E Q BI_Q E_H 9 G L E 9 E _ E Q W E B _E L 6 HI_Q E E B eIIQ H t _E L UID E t _ e H Q 22 PAGE 16E859218851G3 l 1

ANSWERS -- ZION 182 -87/03/24-DAMON, D.

ANSWER 5.01 (1.00)

a. over predict (non-conservative )

b. no change

c. over predict (non-conservative) OR no change

d. no change (.25 ea)

REFERENCE W Fundamentals of Nuc Rx Physics, pp 8-20 to 8-47 015000K506 ...(KA'S)

ANSWER 5.02 (2.50)

a. SAME .

b. HIGHER

c. HIGHER

d. SAME

o. LOWER (.5 ea) i REFERENCE l W Reactor Core Control for Large PWRs, pp 7-29 to 7-33, 9-13 to 9-15 192004K103 192006K110 ...(KA*S) i ANSWER 5.03 (1.50)

e. Decreases. (.25) Pu 239 concentration increases (while U 235 concentration decreases) (.5) I bar increases but is not the dominant factor (.25)

b. Larger SUR. (.5)

REFERENCE W Fundamentals of Nuclear Reactor Physics, pp 7-26 to 7-38, 7-51 to 7-58 192003K104 192003K106 ...(KA'S)

1

.' .E _2_IM E Q BI_Q E _H U GLE 6B _EQ W E B _EL9 EI_Q E E B oIIQHPAGE t _ELWID 23 E ISEBBQQIH8HIGE ANSWERS -- ZION 112 -87/03/24-DAMON, D.

9 ANSWER 5.04 ( .50) b (0.5)

REFERENCE W Reactor Core Control for Large PWRs, pp 3-29 to 3-41 192004K108 ...(KA'S)

ANSWER 5.05 (2.00)

a. Bottom of the core. (0.5)

I

b. 1. Decrease j

2. Increase l

3. Increase (0.5 ea)

, REFERENCE j W Thermal-Hydraulic Principles, pp 13-19, 13-24, 13-34 13-19,-24,-34.

193008K106 ...(KA'S)

ANSWER 5.06 ( .50) same (0.5)

REFERENCE W Reactor Core Control for Large PWRs, pp 9-16 to 9-17 192008K105 ...(KA'S)

1 D. TH[QRY_QE_HUGLE68_EQHEB_ PLANT _QP[RATIQN t _E(QIQgt_68Q PAGE 24 IHEBdQQ1HBUIGE ANSWERS -- ZION 182 -87/03/24-DAMON, D. ,

i ANSWER 5.07 (3.00)

a. EOL(.25) - MTC is more negative and thus imparts greater positive reactivity from the drop in coolant temperature.(.75) l (Doppler only Power coefficient (DOPC) is less negative and thus I imparts less reactivity from the power increase.) I

b. BOL(.25) - MTC is less negative and thus imparts less negative l reactivity from the coolant heat-up.(.75)

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

c. EDL(.25) - Beta-eff is less, makins SUR greater.(.75)

(DOPC is less negative and thus imparts less negative reactivity after the fuel temperature begins to increase and rod worth increases.)

REFERENCE W Fundamental of Reactor Physics, Chapter 6 W Reactor Core Control for Large PWRs, Chapters 2 and 3 192003K106 192004K103 ...(KA'S)

ANSWER 5.08 ( .50) '

d (.5)$

REFERENCE W Thermal-Hydraulic Principles, pp 7-45 to 7-53 l 193004K115 ...(KA'S) 1 l

J

,0* **

}." THEORY _QE_NQQ(ggB_PQWEB_PLgNT_QPEBgTIQNg_ELQIQSt_gNQ PAGE 25 IdEBU9 Eld 6DIGE .

ANSWERS -- ZION 182 -87/03/24-DAMON, D.

ANSWER 5.09 (1.50)

To determine flow in NC:

01 = m1 cp deltaT1 => cp = Q1 / ( ml

• deltaT1) 02 = 2 cp deltaT2 => 2 = 02 / ( cp

• deltaT2) (0.5) substituting in for cp in equation 2 =>

m2 = ( 02

• m1

• deltaT1) / ( 01

• deltaT2) 01 = 100, m1 = 100, deltaT1 = 42, 02 = 2, deltaT2 = 28 (0.5)

THEREFORE => m2 = (2 x 100 *42) / (100

• 28) = 3% (0.5)

Eacceptable range 2.9988% to 3.0012%3 REFERENCE W Thermal-Hydraulic Principles, pp 14-15 to 14-29 193008K122 ...(KA'S)

ANSWER 5.10 (2.00)

Rod worth is a function of the ratio of the flux at the tip of the rod to the average flux in the core. (.5) When a rod is stuck out with all I other control rods in, the flux that that rod tip

• sees' is much higher than tfpe rest of the core. This will make the rod worth about 1000 pcm. (.i75) When a rod is dropped with all other rods out, the flux is depressed in that area and the flux that the tip of the rod ' sees' is cuch lower than the rest of the core, making that rod worth only about 200 pcm. (.75)

Esimilar wording will be accepted]

REFERENCE W Fundamentals of Nuclear Reactor Physics, pp 6-26 to 6-32 192005K105 ...(KA'S)

PAGE 26 51__IMEQBI_QE_HWGLEeB_EQUEB_EkoHI_QEEB6IIQHt_ELUIQEt_6HQ IHEBBQQ1HodIGH

-87/03/24-DAMON, D.

ANSWERS -- ZION 182 ANSWER 5.11 (1.75)

(.25)

a. Increases slightly

b. increases (.25) by a factor of 4 (.25)

Head approaches O psi at maximum flow (0.5) c.

d. Any four of the following:

1. Excessive noise

2. Fluctuating discharge pressure

3. Fluctuating motor current

4. Reduction in pump capacity

5. Excessive vibration Esimilar answers acceptable] (.125 ea)

REFERENCE W Thermo-Hydraulic Principles, pp 10-32 to 10-48 191004K109 191004K110 191004K113 191004K114 ...(KA'S)

ANSWER 5.12 (1.50) 521 F (acceptable range 520 to 524) (.5) a.

315 F (+ or - 5) (.5) b.

c. superheated. (0.5)

REFERENCE Steam Tables 035010A102 035010A201 193004K115 ...(KA'S)

ANSWER 5.13 (1.75) 250.7 psis (acceptable range 247 to 253 if work method correct) 1600 psig = 1614.7 psia (.25) sat. temp. for 1614.7 psia = 606.1 F (interpolated) (.5) 200 F subcooling = 406.1 F (.25) sat. press. for 406.1 F = 264.97 psia (interpolated) (.5) 264.97 psia = 250.26 psis (.25) i REFERENCE Steam Tables 000074K101 035010A102 035010K109 193001K101 ...(KA'S)

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

Ez_'_IMEDBl_DE_NUGLEBB_EQWEB_EleNI_QEEB61IQHt_ELQIQEt_6HQ PAGE 27 IHEBdQQ1885 IGE .

ANSWERS -- ZION 182 -87/03/24-DAMON, D.

ANSWER 5.14 (1.50)

Xenon production: directly from fission (.25) and from beta decay of Iodine-135 (.25)

Xenon removal: beta decay to Cs-135 (.25) and burnout by neutron absorbtion to Xe-136 (.25)

Samarium production: beta decay of Pm-149 (.25)

Samarium removal burnout by neutron absorbtion to Sm-150 (.25)

REFERENCE ,

W Reactor Core Control for Large PWRs, pp 4-11, 4-12, 4-30 j 192006K103 192006K104 192006K116 192006K117 ...(KA'S) -

l l

ANSWER 5.15 (1.00)  !

a. calculated higher than actual

b. calculated higher than actual

c. calculated higher than actual (.33 ea) .

l l

REFERENCE 1 W Thermal-Hydraulic Principles, chapters 4 and 5 002020K501 193007K106 193007K108 ...(KA'S) I ANSWER 5.16 (1.50)

a. decrease

b. no change

c. no change

d. no change

e. decrease

f. no change (.25 ea)

REFERENCE W Reactor Core Control for Large PWRs, pp 7-13 to 7-23 Technical Specification 1.42 001000K508 004000K519 192002K110 192002K113 192002K114

...(KA'S)

? .

E. THEQSI_QE_HQQLE68_EQWEB_EL8NT_QPEBAIIQN t _E(QIQEt_6NQ PAGE 28 ISEBb991HedIGE ANSWERS -- ZION 112 -87/03/24-DAMON, D.

ANSWER 5 17 (1.00)

Temperature will be lowest in the lower part of the core, thereby making boron worth highest in this section of the core. More negative reactivity will be added to the lower section.of the cover forcing the flux peak higher in the cover thus driving delta-I Loward the positive side of the band.

Alternate acceptable answer Boration with no change in power or rod position will produce the same magnitude reduction in The Tava and Tc. The mass density change per degree for Th is greater than for Tei thus the value of MTC for Th is greater (more negative) than for Tc. Therefore the temperature reduction will add more positive reactivity to the upper section of the core than to the lower section, thus pulling delta-I in the positive direction.

REFERENCE W Reactor Core Control for Large PWRs, pp 5-13 to 5-14 pp 3-20 to 3-21 001050K502 192004K110 ...(KA's) i

6___EL8HI_gISIEdg_QEHIGHg_GQUISQLt_9NQ_INSISQd[HIBIIQN PAGE 29 ANSWERS -- ZION 182 -87/03/24-DAMON, D.

ANSWER 6.01 (1.50)

c. ESF busses are stripped and ESF loads are sequenced on the bus

b. ESF loads not running are sequenced on busi loads running on bus previous to this are on due to blackout sequence

c. ESF Bus strips, blackout loads sequence on (.5 ea)

REFERENCE Zion System Description pp 1-86 to 1-87 000056K208 000056K301 ...(KA'S)

ANSWER 6.02 (1.50)

a. P-8: 2/4 PRNI >60%, single loop low flow Rx trip is auto unblocked (.5)

b. P-11: 2/3 pressuri=er pressure channels < 1915 psis Coperator can block the low pressure SI] to allow further cooldown and depressurization(.5) l i

l c. P-14: 2/3 narrow ranse instruments in 1/4 SG's at > 70%, Ethe Feed Re3  !

and bypasses close, MFP's trip, and Main Turbine trips 3 to protect main  !

turbine from water damage (.5) note: answer in E3 not required for full credit l l

l REFERENCE '

Zion logic diagram 5653D30 sheets 2,4,5,6,7,8,13,14 010000K102 010000K603 015000K101 035010K112 ...(KA'S) l l

l e

, . - =.- - . . . . . - - _ - . . - - . __. . . - -

41__EL6HI_E!SIEHE_DESIGHt_GQUIEQLt_eHQ_INIIEUNEUI6IIQH PAGE 30 ANSWERS -- ZION 1A2 -87/03/24-DAMON, D.

ANSWER 6.03 (2 25)

I s. any three required: (.25 ea) i 1. CCW surge tank high level.

2. CCW RMS alarm.

3. RCP Thermal Barrier outlet low flow alarm

4. RCP Thermal Barrier Return Cooling Water Flow High

5. Aux building area rad alarm (other alarms will be considered for credit on a case basis)

b. 1. High flow of 190 spa throttles return isolation valve FCV-685 shut.

l i 2. Check valve (CC-9495) isolates on reverse flow.

3. Relief valve ("E500 psis) protects from overpressure. (.5 ea)

REFERENCE 1 ZION System Description pp 15-10 to 15-12

, ZION P&ID M-67

! 008000A104 000000A301 008000K103 008000K104 . . . (KA'S) l l

I ANSWER 6.04 (1.50)

J

a. 1. Steam flow signal would increase (0.25) causing an immediate-SF-FF mismatch which causes the FW res valves to open to match feed flow to steam flow. The FW res valves opening causes differential pressure to decrease which will require an increase in MFP speed to compensate.(.25) Feed flow increases (.25)

2. The steam senerator level would level out at a higher than I normal level. (0.5) i

b. Total steam flow. (.25) i REFERENCE ZION System Descriptions, pp 25b-2 to 25b-5, 21a-33 '

035010K112 059000K104 ...(KA'S) i 4

m__yy . _ . _ _ , _ _ _ _ _ _ w._ .--_,. ., - . , . - _ , - m,_-_,_ .., _ . _ , _

,,-,___-.-,-_,m,._~ . . - - , . . - . . _ _ _ . _ _ , _ , .

4_ _'_ Ele BI_ EISIE B E _ Q E SIG H r _G Q UIB Q L t _ e H Q _IN EIE W H E MIeIIQ U PAGE 31 ANSWERS -- ZION 182 -87/03/24-DAMON, D.

ANSWER 6.05 (2.00)

o. INTERMEDIATE and POWER (.25 each)  ;

b. SOURCE, INTERMEDIATE and POWER (.25 ea)

c. INTERMEDIATE, POWER, and SOURCE (.25 ea)

REFERENCE ZION System D'scriptions, e pp 6a-11, 6b-8, 6b-9, 6b-13, 6b-15, 6b-17, 6c-22, 6c-23 015000K501 ...(KA'S)

ANSWER 6.06 (1.00)

a. SHUT (.25)

b. Prevent (resin channeling due to) excess flow through demin resin. (0.5) l l c. HCV-182 (Charging flow control valve, Back pressure regulator or RCP Labyrinth delta P control Valve). (.25)

REFERENCE ZION System Descriptions, pp5a-4, Sa-6, Sa-34, Sa-35 COP-4, pg 37 004000K104 004000K404 004000K525 004000K603 ...(KA'S)

ANSWER 6.07 (2.25)

a. NO CHANCEi(.25) Results in a low loop Tavs, Rod Control utilizes a Auctioneered High Tavs. (.5)

b. RODS INi(.25) Pimp will generate a minimum Tref, a large temperature error will cause rods to insert. Power rate mismatch will also cause rods to insert. (.5)

c. RODS INi(.25) Nuclear power > turbine power (mismatch), rods in to compensate for anticipated high Tava.(.5)

REFERENCE ZION System Description, pp 8a-11 to Ba-13 OC1000K403 ...(KA'S) 1

.. _= .

iz2_P(gMI_SIgI[53_Q[gIQWr_QQUISQLg_gNQ_lHEIBQd[HIGIIQN PAGE 32

- ANSWERS -- ZION 182 -87/03/24-DANON, D.

l ANSWER 6.08 ( .50)

High-high containment pressure,(.25) to prevent inadvertant initiation of containment spray if power is lost. (.25)

REFERENCE ZION System Descriptions, pp 9-13, 12b-3 026000K101 ...(KA'S)

• ANSWER 6.09 (1.50)

Will not allow the test.(0.5) Placing in test will deenergize the interlock circuit P-13 which feeds P-7. This will unblock the low j pressurizer pressure trip function which will result in a rcactor j protection actuation. Shutdown rods will drop. (1.0)

REFERENCE Logic dia3 ram 5653D30, sh. 4,6,8,16 j 012000K401 ...(KA'S)

I ANSWER 6.10 (2 00)

a. Equilibrive. xenon (.5), full length rod banks more than 190 steps withdrawn (.5), as high a power as practicable (.5)

b. Multiply the 85% value by the ratio 100/85. (alternate acceptable on a graph, draw a straight line from 0 at 0% power through the 85% value. 3 The line will intersect the 100% target value.) (.5) l l

REFERENCE l Technical Specification 3.2.2.A.3 l 015020A201 ...(KA'S) i ANSWER 6.11 (2.25)

1. RWST to SI pumps to RCS cold less (.5) at 1500 to 1550 psis (.25)

2. Accumulators to RCS cold less (.5) at 600 to 650 psis (.25)

3. RWST to RHR pumps to RCS cold less (.5) at 150 to 200 psig (.25) j REFERENCE

ZION System Description, pp 12a-7 to 12a-11 006000G004 006000K103 006020K104 ...(KA'S)

i 612_PL6HI_SIEI[HE_QERIGNt_GQNIBQLt_6HQ_INEIEWHEMI611gH PAGE 33 ANSWERS -- ZION 182 -87/03/24-DAMON, D.

i j ANSWER 6.12 (1.50)

OT delta T OP delta T

c. increase remain the same

b. decrease decrease

c. increase remain the same (.25 ea)

I REFERENCE i j Technical Specifications 2.1.1.B.4, 2 1.1.B.5 010000K101 012000G009 015000K101 ...(KA'S) i ANSWER 6.13 (2.00) 4 c. To open MOV-RHB700A, the following valves must be shut:

! MOV-CS0049 (containment spray supply valve train A) j MOV-CS0050 (containment spray supply valve train B)

MOV-SI8811A (containment recirc sump suction valve train A)

MOV-RH8804A (charging pump suction valve) (.25 ea)

b. To open MOV-RH8700B, the following valves must be shut:

MOV-CS0050 (containment spray supply valve train B)

MOV-CS0049 (containment spray supply valve train A)

MOV-SIB 8118 (containment recire sump suction valve train B)

MOV-RH8804B (safety injection pump suction valve) (.25 ea) l t

l REFERENCE ZION System Description, pg 10-24 i 005000K407 ...(KA'S) i i

J ANSWER 6.14 (1.75)

a. 2/3 low-low level in any one steam generator any SI signal blackout signal (.25 ea)

! b. 2/3 low-low level in 2/4 steam generators j 2/4 reactor coolant pump bus voltages low any SI signal j blackout signal (.25 ea) i i

1 1

1

. i f _ _*_P L 6HI_fIfl[b f _Q E SIG M t _G Q UIEQ L t_6NQ _INSIBQ U EHI611g N PAGE 34 ANSWERS -- ZION 182 -87/03/24-DAMON, D.

REFERENCE 2 ION System Description pp 12c-1 to 12c-2 061000K202 061000K402 ...(KA'S)

ANSWER 6.15 (1.50)

a. Less than 3850 volts on the associated ESF bus (.25) for greater than 8 seconds. (.25)

b. After 5 minutest (.25) l The associated diesel senerator starts (.25)

The bus strips and DG closes in on the bus (.25)

Blackout sequencer for that bus is activated (.25)

REFERENCE Annunciator Response Manual, Section 15, pp 48, 6D, 6E AOP-21, ps 3 .

j 062000K104 062000K302 062000K404 ...(KA's) l l

7. PRQQgQQRES_ _NQBM6(g_6ENQBM6(g_[MgSQ[NQ1,6NQ PAGE 35 S6DIQLQEIGeL_GQUIBQL ANSWERS -- ZION 182 -87/03/24-DAMON, D.

ANSWER 7.01 (2.50)

a. All routine access or work in radiologically controlled areas where personnel are NOT expected to exceed a whole body dose equivalent of 50 mrem / day (.75) ,

I

b. Max of 1 year from January 1. (.50)

c. All access work in radiologically controlled areas where personnel are expected to exceed a whole body dose equivalent of 50 mrem /dayi(.5)

! Jobs involving significant contamination and/or airborne radioactivity l may require one.(.25)

d. Length of the job. (.50)

REFERENCE RP 1190-1, pp 12-15 194001K103 ...(KA'S)

ANSWER 7.02 (2.00) ,

1

a. BAT to BATP to Charging Pump Suction via: j

1. Emergency Boration Viv MOV8104

2. Manual Emergency Boration Viv VC8439 i

3. VC FCV0110A and FCV0110B 1

4. CCP to BIT to Cold Le3 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 trip or shutdown

3. Unexplained / uncontrolled reactivity increase

4. Failure of RCMS to extent that bypass is necessary (.25 ea)

REFERENCE EDP-5, pp 2 to 3 000024G010 000024K201 000024K204 ...(KA'S)

Z _2_E B Q G E Q UE Ef _:_H Q BdeL1_e E H Q Bd eL1_E M E BG EN Gl_e MQ PAGE 36 BBQIQLQGIGeL_GQHISQL ANSWERS -- ZION 182 -87/03/24-DAMON, D.

I ANSWER 7.03 (2.00)

a. S/D margin is not violated. (.75)

b. HI STEAM FLOW. (0.75)-

c. Prolonged idling may damage the turbine due to high moisture (.25) content in the steam when steam demand is minimum.

d. To allow auto stop of the pump as turbine speed is increased above approximately 600 RPM (.25)

REFERENCE GDP-2, pp 9, 10, 23, 29 OO1000G005 006000G007 059000G007 191003K108 ...(KA'S)

ANSWER 7.04 (3.00) ,

a

a. power increase to 32% power exceeded the 3%/hr rate on 8/7 (.75)

Did not hold at 25% power for i hr on 8/7 (.75) and exceeded 3%/hr on ramp to 50% on 8/11 (.5)

b. 19.1 hrs (+/- 0.5 hrs) (1.0)

REFERENCE GDP-3, p. 6 001000C007 ...(KA'S)

ANSWER 7.05 (1.50)

At least 1 CCP or SI pump running (.5) AND wide range RCS pressure drops below 1250 PSIG (1550 for adverse containment) (0.5)

OR Within 5 minutes after losing CCW to RCP's. (0.5)

REFERENCE E-0 Foldout page, E-0 step 14 000007G007 000007G010 000007G011 ...(KA'S)

' Z

1.EB9GE99BES_:_NQSd6Lt_6ENQSd8(1_EMEEGEHQ1_8NQ PAGE 37 B691969EIGeL_G9 BIB 96 ANSWERS -- ZION 182 -87/03/24-DAMON, D.

ANSWER 7.06 (2.00)

a. containment pressure greater than or equal to 5 psisi or containment radiation greater than or equal to 10E5 R/hr (0.5 ea)

b. When pressure decreases below 5 psisi or when rad levels are less than 10E5 R/hr and evaluation of total integrated dose is completed by TSC (0.5 ea)

REFERENCE E-0, pg 2 note 000007G007 000007G010 ...(KA*S)

ANSWER 7.07 (1.50)

a. Place PCV131 in manual BEFORE stopping the pump.

b. High enough to maintain greater than or equal to 200 psid across the il seal or approximately 400 psis in the RCS

c. PRT rupture disc. (.5 ea)

REFERENCE GOP-4 pp 38 & 42 003000K103 005000K104 007000A102 ...(KA'S)

ANSWER 7.08 (2.00) l 4 of 5 required.

1. Core exit TCs (.25) - stable or decreasing (.25)

2. RCS Subcooling (.25) greater than 30 F (.25)

3. SG pressure (.25) -

stable or decreasing (.25)

4. RCS hot les temperature (.25) -

stable or decreasing (.25)

5. RCS cold les temperature (.25) - at approx. saturation temp for SG pressure (.25)

REFERENCE E-0 FOLDOUT PAGE 000007G002 193008K122 ...(KA'S)

l

! Z,.__BBQGE9yBgS_:_N9Bde61_0BN9BdB61_EMEEGENQY_98D PAGE 38

B001069G1G06_G9 NIB 96

ANSWERS -- ZION 1L2 -87/03/24-DAMON, D.

i

)

1 l

i ANSWER 7.09 (1.50) .

c. normalized currents N41 N42 N43 N44 avg upper O.5 0.5 0.518 0.528 0.511 .

1 lower O.5 0.5 0.5 0.5 0.5 1

man upper / avg upper =1.03 max lower / avg lower =1.0 QPTR=1.03 (.75) l

b. The reactor shall be put in the hot shutdown condition; however, cperation below 50% of rated power, for purposes of correcting the tilt, shall be permitted. (.75) ,

! l REFERENCE ,

I Technical Specifications 1.37, 3.2.2.B.3 )

W Reactor Core Control for Large PWRs, pp 8-30 to B-31

015000A104 015000 GOO 7 0,15000GOOB ...(KA*S) i l

ANSWER 7.10 (2.00) l I

action response not obtained l

1. verify reactor trip manually insert control rods and locally l

trip rod drive MG's and Rx trip and bypass l 1 breakers

2. verify turbine trip manually trip. If it will.not trip, shut 4 MSIV's and MSIV bypasses j

3. check AFL) pumps running start pumps

4. emergency borate by emergency borate in following prefered order j injecting BIT MOV-VC8104, FCV-0110A & B, VC8439

(.25 for each action, . 25 f or each response not obtained)

REFERENCE FR-S.1, steps 1-4

OOOO29G011 ...(KA'S) o f

I l

t i

4

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

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

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

7. PRQQ[QQB[3_ _NQBd8(t_6ENQBM8(g_[bESQEHQ1_6NQ PAGE 39 BeQIQLQGIGeL_GQNIBQL 3 ANSWERS -- ZION 182 -87/03/24-DAMON, D.

i ANSWER 7.11 (2.00)

o. dose equivalent to the whole body shall not exceed 75 rems; and (.5) additional dose to the extremities shall not exceed 200 rens. (.5)

I b. planned whole body dose equivalent shall not exceed 25 rems; and (.33) planned dose equivalent to the extremities shall not exceed 100 rems (including the whole body component); and (.34) planned dose equivalent to the thyroid shall not exceed 125 rems. (.33)

REFERENCE l RP 1190-1, pg 32 1

194001K103 ...(KA'S)

ANSWER 7.12 (3.00)

! candidate 41 rejected (.25) since he has no history on file and will l exceed 1 25 REM /GTR whole body exposure (.5) candidate 42 rejected (.25) since he will exceed the weekly limit of l 300 mrem whole body without Red-Chem approval (.5) candidate 43 rejected (.25) since she will exceed 500 mrem whole body

! during the term of her pregnancy (.5) candidate 44 accepted (.25) since he will not exceed the admin limit of 300  !

mrem /wk (.25) or the whole body limit of 1.25 REM /DTR (.25)

REFERENCE RP 1190-1, pg 30 USNRC Regulatory Guide 8.13 l 10 CFR 20.101 194001K103 194001K104 ...(KA'S) l

'Ez__6DMINIIIBeIIME_EBQGEQWBEft GQUQIIIQHit_eWQ_LIMIIeIIQUE PAGE 40

' CNSWERS -- ZION 112 -87/03/24-DAMON, D.

ANSWER 8.01 (1.00)

o. No (.25)

b. No (.25)

c. 7 days (.5)

REFERENCE Technical Specification 1.27, 3.8 1.C 004000G005 006000G005 ...(KA'S) t ANSWER 8.02 (1.00)

c. Station Manager (or his alternate) (.25)

b. in the following order l

) shift engineer shift foreman

• shift control room engineer (.1 eae .15 ea for correct order) 1 l REFERENCE EPIP 110-1, pg 2

068000G002 ...(KA'S)

CNSWER 8.03 (1.00)

8. NO

b. NO ,

c. YES

d. NO (.25 ea)

REFERENCE Technical Specifications 4.8.2.A.1, 3 8 1.F 3 8.1.E.1, 4 9.4.A.2 004000G005 0060000005 039000G005 ...(KA'S)

ANSWER 8.04 (1.50)

Temporary Procedure change-used when intent of existing procedure is not to be changed (.75)

Special-should be used when an intent chan3e is necessary (.75) l

'H _'_eQUINISIBeIIME_ESQGEQUEEft_GQHQIIIQHit_eHQ LIMIIGIIQWE PAGE 41

' ANSWERS -- ZION 182 -87/03/24-DAMON, D.

REFERENCE ZAP 5-51-4, ps 4 194001A102 ...(KA'S)

ANSWER 8.05 (1 50)

o. Shift Engineer

b. Shif t Foreman -

c. Shift Foreman

d. Shift Engineer

o. Shift Foreman

f. Shift Engineer (.25 ea)

REFERENCE 1 ZAP 1-51-1, pp 4 to 6 I 194001K102 194001K116 ...(KA'S)

ANSWER 8.06 (1.50)

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

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

3. Test or maint. procedure is reviewed for completeness prior to returning system to an operable condition. (.5 ea)

REFERENCE ZAP 3-51-4, ps 4 194001K102 ...(KA'S)

ANSWER 8.07 (1.50)

c. Reactor power must be reduced to no greater than 50% power (.5) and the high neutron flux trip setpoint must be reduced to no greater than 55% of rated values. (.25)

b. The deviation shall be eliminated or reactor power shall immediately be reduced to a level no greater than 90%. (.5) Then accumulate penalty time if appropriate. (.25)

REFERENCE Technical Specifications 3.2 2.A.6, 3.2.2.A.5 015000G007 015000G008 ...(KA'S)

~<, .-

'81_'ieQUINISIB6IIV[_PEQQ[QUEEH1_GQUQIIIQHft_6HQ_(INIIGIIQUE PAGE 42

' ANSWERS -- 21DN 182 -87/03/24-DAMON, D.

ANSWER 8.08 (1 00)

o. 200 F (.5)

b. 320 F (.5) t REFERENCE Technical Specification 3.3 1.C.2, 3.3.2.D 010000K403 010000K603 022000K301 035010K602 ...(KA'S) l ANSWER 8.09 (1.00)

1. RCS pressure (.125) greater than 100 psis and less than 1000 psig (.125)

2. No. 1 seal leakoff valve (.1'25) open (.125)

3. No. 1 seal leakoff flowrate (.125) less than 1 spm (.125)

4. Seal injection flowrate to each pump (.125) greater than 6spm (.125) i REFERENCE j GOP-1, precaution I-I 003000K602

...(KA'S)

I ANSWER 8.10 ( .75)

, l l l An operator shall be considered to be at the reactor controls if he (she) has visual contact with the unit annunciator panels and is in a position to respond if required. (.75) l REFERENCE ZAP 10-52-3, pg 5 194001K105 ...(KA'S) 4 4

4 4 4

at__0DUIN1EIB011VE_E8QgEQUBESi _QQMQlligNQ3_8NQ_610lI811QNS PAGE 43 ANSWERS -- Z ION 18<2 -87/03/24-DAMON, D.

I .

i.

ANSWER 8.11 (2.50)

Any 10 of the following: (.25 ea) l 1. Containment pressure (narrow range)

2. RC outlet temp - Thot (wide range)

3. RC inlet temp - Tcold (wide range)

4. RC pressure (wide range)

5. Steam line pressure

6. Pressurizer water l evel

7. SG water level (narrow range)

8. SG water l evel (wide range)

9. RWST level

10. AFW flow

11. RCS subcooling margin

12. PORV position indication

13. PORV block valve position indication

14. Safety valve position indication i

REFERENCE lechnicel Specification 3.8.9 and table 3.8.9-1 016000 GOO 5 ...(KA'S)

ANSWER 8.12 (2.00)

Any 4 of the following (.5 ea)

All penetrations required to be closed during accident conditions .are either:

1. capable of being closed by an operable automatic containraent isolation valve system, or

2. closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions

3. equipment hatch is closed

4. at least 1 door in each air lock is closed and sealed

5. containment leakage satisfies specification 2.10

6. penetration pressurization systems are in service i REFERENCE Technical Specification 1.11 OO7000 GOO 5 ...(KA'S)

,.m - p-.v --

~ _ __ y- s-,. .-: y_

"; , :l

'.,92_*_eQUIMIEIB6IIVE_EBQGEQWBEf t GQBQIIIQHf t_eHQ_LIMIIBIIQUE PAGE 44 o ANSWERS -- ZION 182 -87/03/24-DAMON, D.

ANSWER 8.13 (2.00)

1. Control rods in a single bank move together with no individual rod insertion differing by more than 15 inches from the bank demand position.

2. Control rod banks are sequenced with overlapping banks.

3. ihe full length control bank insertion limits are not violated.

4. A>:ial power distribution control procedures are observed. (.5 ea)

REFERENCE Technical Specification bases, page 68 193009K107 ...(KA'S)

ANSWER 8.14 (2 25)

1. the incore thimbles are in the reactor vessel J

2. the incore detectors are taken out of service

3. the incore detectors are in the storage position or are inserted into the reactor vessel (.75 ea)

REFERENCE ZAP 5-51-16, pg 2 l 194001K103 194001K104 194001K105 ...(KA'S) l l

ANSWER 8.15 ( .50) f (.50)

REFERENCE ZAP 14-15-2' P3 22 194001K102 ...(KA'S)

. tr T't Ez'__eQUINISIB8IIVE_EBQGEQUBEf t_GQUQIIIQWEt_6HQ PAGE 45

• ANSWERS -- ZION 182 -87/03/24-DAMON, D.

ANSWER 8 16 (1.00) max pressure 2735 psig min pressure 2220 psia (2205 psig) (.5 ea)

REFERENCE Technical Specifications 1.2.1.A, 3.2.4.A.2 010000G005 ...(KA'S)

• ANSWER 8.17 (1.50)

OpTR shall be determined by monitoring at least 4 thermocouples per quadrant (.5) once an hour (.5)'and after any load change greater than 10% at any power level above 50% (.5)

REFERENCE Technical Specification 4.2.2.C.2 015000G005 015000G007 015000G008 015000K301 015020K504

...(KA'S)

ANSWER 8.18 (1.50)

1. when the sprinkler system for a zone is inoperable

2. When the CO2 system for a zone is inoperable

3. when one or more required fire penetrations are not intact -(.5 ea)

REFERENCE Technical Specifications 3.21.3.B, 3.21.4.B, 3.21.6.B 194001K116 ...(KA'S) u .