ML20245C469

Exam Rept 50-298/OL 87-02.Exam Results:Four Senior Reactor Operator Candidates Passed All Portions of Exam.Exam Encl

ML20245C469
Person / Time
Site:	Cooper
Issue date:	10/26/1987
From:	Pellet J, Whittemore J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20245C465	List: ML20245C464 ML20245C469 ML20245C684
References
50-298-OL-87-02, 50-298-OL-87-2, NUDOCS 8711030128
Download: ML20245C469 (49)

Text

1 OPERATOR LICENSE EXAMINATION REPORT' N0. 50-298/0L 87-02 Licensee: Nebraska Public Power District P. O. Box 499-Columbus, Nebraska 68601 i

' Facility Docket No: 50-298 Facil,ity License No: DPR-46 Operator License Examinations at Cooper Nuclear Station (CNS)

Chief Examiner: / O Ol 7 dpdE.Whittemore, Operator .

Date Licensing Section, Division of Reactor Safety q l.

Approved By:

I J.4L. Pellet, Chief, Operator

/C 6!h'7 Date ,

Licensing Section, Division of )

Reactor Safety l

Summary:-

Senior Reactor Upgrade examinations were administered to four Senior Reactor Operator (SR0) candidates. All candidates passed all portions of the examinations.and have been issued Senior Reactor Operator Licenses, j l

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8711030128 DR 871028 ADOCK 05000298 PDR

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CNS OPERATOR LICENSE EXAMINATION REPORT Report Details

1. CANDIDATES EXAMINED Pass Fail Total SR0 Candidates 4 0 4 2.- EXAMINER

-J. E. Whittemore (Chief Examiner)

3. EXAMINATION REPORT Performance results for individual candidates are not included in this report as it will be placed in the NRC Public Document Room and these results are not subject to public disclosure.

a. EXAMINATION REVIEW COMMENT AND RESOLUTIONS In general, editorial comments or changes made during the examination or during subsequent grading reviews are not addressed by this resolution section. This section reflects comments and recommended changes to examination answer keys by the licensee. Modifications resulting from these comments and recommendations are included in the

-master examination keys, which are provided elsewhere in this report. ,

Unless otherwise indicated in this section, the facility comments I were incorporated into the answer key, 5.09 Question could also be answered based on the 1 effects.that swelling has on the pellet beside  !

temperature change. Recommend accepting answers based on atomic concentration (N).

Resolution: Not acceptable as the facility provided reference material does not support this contention.

6.09 Two sections of the student text state that hardware failures cause rod blocks. Another section states that a software failure will cause a rod block. This could cause confusion.

Therefore, either True or False should be an acceptable answer.

Resolution: Not acceptable as the answer would be true no matter what type of failure was assumed.

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2-7.03.e- Students are not required to. memorize the E0P

. tables. If an alarm condition arises, they are expected to reference the tables and respond accordingly. The caution section of the E0P states entry conditions for Secondary i Containment Control (E0P-3).as high radiation  ;

max normal. Accept "none" as a correct answer. "

Resolution: Will accept provided that candidate refers to checking radiation level threshold for entry ,

into the E0Ps 7.07.b the Along procedure with also actions tellsstated in the answer the operator key,2 to check N pressure and reduce power to reduce to reduce i pressure. Should accept reference to N2 pressure and power reduction as correct answers.

Resolution: Will allow reducing power as a viable method to close the valve. Checking N2 pressure is a corrective action for mitigating circumstances and is not acceptable, j 7.09.b Procedure 2.1.10, Rev. 13, page 2 indicates that oscillations may be suppressed by inserting control' rods and/or increasing core flow. The preferred method is to reverse the actions that caused the flux oscillations. Therefore the answer should be False.

Resolution: This is not acceptable as the procedure referenced in the comment is for changing power while the question solicits knowledge of action required after-a reactor recirculation pump trip,

b. SITE VISIT

SUMMARY

l (1) At the end of the written examination administration, the l licensee was provided a copy of the examination and answer key for the purpose of commenting on the examination content validity. It was explained to the licensee, that region policy was to have examination results finalized within 30 days, thus a timely response was desired to attain this goal.

(2) At the conclusion of the site visit, the examiner met with licensee representatives to discuss the visit. The following personnel were present:

3 NRC Facility J. E. Whittemore R. Black R. Brunghardt G. Horn G. Reece D. Shallenberger J. Surette ,

l P. Windham Mr. Whittemore opened the meeting by thanking those present for the cooperation received during the site visit. Other items discussed were as follows:

(a) Control room personnel were especially cooperative during the operating exam process.

(b) The licensee was informed that the NRC Requalification Audit Program was being reviewed and the NRC audit scheduled for February,1988 will be affected, if not delayed or cancelled.

One generic weakness noted in the candidates was reported to the licensee. It was noted that this was not considered an action item, but for the licensee's benefit.

(a) Some candidates were confused as to how to supervise the release of radioactive noble gas trapped in the Drywell after leak isolation and plant shutdown. There is no procedure for the scenario posed and candidates were generally unaware of methods to mitigate problem and limitations that are encountered.

c. EXAMINATION MASTER COPIES Master copies of the Senior Reactor Operator license examinations and answer keys are attached. The facility comments which have been accepted are incorporated into the answer key

d. FACILITY EXAMINATION COMMENTS The facility comments regarding the written examination are attached.

Those comments which were not acceptable for incorporation into the examination answer key have been addressed in the resolution section of this report.

U. S. NUCLEAR REGULATORY. COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _QQQEEB__________________

REACTOR TYPE: _QWB-qed _________________

DATE ADMINISTERED: _BZlQB222________________

EXAMINER: _WBIIIEdQBEt_Ji__________

CANDIDATE: _________________________

1NSIBVQIl0NS_IQ CANDIQeIEi Use : separate . paper for the answers. Write answers on one side only.

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

% ' 0F '

CATEGORY. -% OF CANDIDATE'S CATEGORY

__V8LUE_ _IDI8L .___SQQBE___ _V8LUE__ ______________QoIEQQBX_____________ j

_2hAQQ__ _25AQQ ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERIA 0 DYNAMICS

_25tQQ__ _25100 ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND liffTRUMENTATION 25ADQ-_ _25AQQ ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL l

_251Q0__ _25tEQ ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 100x00__ ___________ ________% Totals Final Grade All. work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature '

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l l NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS l

l During the administration of this examination the following rules apply'

l. 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.

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 ggqb section of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a Ogg page, write QDly 2D 202 Sida of the paper, and write "Last Page" on the last answer sheet.

9. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least ibtgg 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 111gtgigtg.

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

14. Show all calculations, methods, or assumptions used to obtain en 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 gEDG1DRE 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.

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18. When you complete.your examination, you shall: l

e. Assemble.your examination as follows:

'C1) Exam questions on top.

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.(2) Exam aids - figures, tables, etc.  !

- (3 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. ,

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c. Turn in all scrap 1 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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l QUESTION 5.01 (1.00)

As a suberitical reactor nears criticality, the length.of time to reach an equilibrium count rate after an insertion of a given fixed amount of positive reactivity...(SELECT THE CORRECT ANSWER)

n. increases primarily because of the increased population of delayed neutrons in the core,

b. increases because of a larger number of neutron life cycles required i to reach equilibrium.

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c. decreases primarily because of the increased population of delayed neutrons in the core. 1

d. decreases because the source neutrons are becoming less important in relation to total neutron population. (1.0) i 1

-QUESTION 5.02 (1.50) 1 With the reactor critical at 5000 CPS, Rods are used to increase power to  :

10000 CPS, with no change in detector position. State if the final rod position will be FURTHER WITHORAWN, FURTHER INSERTED, OR THE SAME POSITION as when the power level was 5000 CPS and justify your answer. (1.5) i i

QUESTION 5.03 (1.00)

List THREE generic factors that can effect Control Rod worth in a given i reactor. (1.0) l I

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/Qt__IBEQBY_QE_UUQLE68_EQWEB_ELoNI_QEEB61198t_ELVIRSt_6UQ PAGE 3 IBEBdQQ1860103 l QUESTION 5.04 (2.50)

n. Concerning control rod worth during a reactor startup with 100%

l peak Xenon versus a startup with Xenon free conditions, which statement below is correct? JUSTIFY YOUR CHOICE.

1. Peripheral control rod worth will be lower during the 100% 1 peak Xenon startup than during the Xenon free startup.

2. Central control rod worth will be higher during the 100% peak Xenon startup than during the Xenon free startup.

3. Peripheral control rod worth will be higher during the 100%

peak Xenon startup than during the Xenon free startup.

4. Both central and peripheral control rod worth will be the same regardless of core Xenon concentration. (1.5)

b. Answer the following questions as TRUE or FALSE, given that the unit was at rated conditions when a Reactor Scram occurred.

1. If the reactor is started up at the time of peak Xenon conditions, then the neutron thermal flux level will be located HIGHER in the core than if Xenon free conditions existed. (Assume a bottom peaked axial flux distribution.)

2. At the time of peak Xenon conditions, the core is free of Iodine 135. (1.0) f 1

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QUESTION 5.05 (2.00) l Answer the following TRUE or FALSE: {

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a. During equilibrium power conditions, the production rate of indirect Xenon from Iodine is faster than the decay rate of Xenon to Cesium. (0.5)

b. Slowing the rate of a power decrease lowers the height of the resultant Xenon peak. (0,5)

c. The resultant Xenon peak due to a scram from 50% power is larger than one from 100% power. (0.5)

d. During an increase in power from equilibrium Xenon conditions, Xenon concentration initially decreases. (0,5)

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4 - 51__IBEQBl_QE_ NUCLE 68_EQWEB_EL8NI_QEEB6IIQNt_ELu10at_eNQ PAGE. 4 IBEBdQQ1NadICS QUESTION . 5 ~. 0 6 - (2.00)

Explain the long term changes in Shutdown (Reactivity) Margin resulting from fission product-poisons after a reactor scram from full power with equilibrium conditions. The answer should address both the. individual AND collective effects.- (2.0)

QUESTION ~5.07 (1.50)

For each of the following ' events, STATE WHICH coefficient of

. reactivity (Power coefficient, void coefficient, moderator coefficient  ;

or doppler coefficient) would act FIRST to change reactivity.

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a. Control rod drop at power. (0.5)

b. SRV opening at power. , (0.5) l

c. One'recirc. pump trips while at 50% power. (0.5)

QUESTION 5.08 (1.50)

What TWO (2) physical. phenomena, specifically related to the neutron life cycle and fuel characteristics, along with increasing fuel temperature, contribute to a negative doppler coefficient? (1.5)

QUESTION 5.09 (2.00)

Explain how and why the following factors affect the magnitude of the Doppler coefficient over core life.

a. Pu_240 buildup. (1,0)

I b. Fuel swelling. (1.0) 5.10 l

QUESTION (1 50) j What is the reason or basis for the MAPLHGR Thermal Limit? (1.5)

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' QUESTION 5.11 (1.00)

What is the relationship between MAPRAT and MAPLHGR7 (1.0)

QUESTION 5.12 (1.00)

Which ONE of the following operations will have a negative (reducing 1

effect) on available Net Positive Suction Head (NPSH) of an operating centrifugal pump:

a. Throttling open the pump's suction valve.

b.- Throttling open the pump's discharge valve.

c. Decreasing the pump's speed. j

d. Decreasing the temperature of the fluid being pumped. (1.0)

QUESTION 5.13 (1.00)

Consider a closed loop cystem with with two identical centrifugal pumps in parallel, one of which is running at 1800 RPM. The second pump is started -

and run at 1800 RPM. System flow will be...(SELECT THE CORRECT ANSWER)

n. more than double the original flow due to decreased flow resistance.  :

b. slightly less than double the orf.ginal flow due to increased flow resistance. {

c. the same since only the discharge head changes.

d. increased by 3/4 of the second pump rated flow due to increased discharge head. (1.0) l l

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-QUESTION 5.14 (3.00)

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Following a normal reduction in power from 90% to 70% with recirculation flow, HOW will the following change (increase, i decrease, or remain the same) and WHY:-

e.. The pressure difference between the reactor and the turbine steam chest. (1.0) 4 f 'b. Condensate depression at the exit of the condenser. (1.0)

c. Final Feedwater temperature. (1.0) .

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QUESTION 5.15 (1.50)

Match the peaking factors listed below in column "A" with the ratios in column "B" which best describe the peaking factor:

"A" "B" l

a. Local Peaking Factor 1. Ind. Bundle Pwr. / Core avg.~ bundle Pwr.

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b. Axial Peaking Factor 2. Steady state MCPR / Bundle CPR

c. Radial Peaking Factor 3. Nodal pwr. / Avg. Nodal pwr.

4. Highest Pin Pwr. in a node / Average Pin Pwr in a node (1.5)

I QUESTION 5.16 (1.00)

Transient thermal limits have been established to mitigate the release of fission products due to fuel damage. List the 2 mechanisms that cause fuel damage during reactor transients and explain why they occur. (1.0) 1

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QUESTION 6.01 (2.00)'

During refueling, what are 4 methods or aids that may be used to confirm proper fuel orientation? (2.0)  ;

i QUESTION 6.02 (2.50) i The-Reactor Recirculation System interfaces with several other plant s systems. Describe it's interaction with the following systems. (Be f specific as to the point of interface on the Rx. Recirculation system.)

n. Reactor Water Cleanup (RWCU) System.

b. Control Rod Drive (CRD) hydraulic system.

c. Average Power Range Monitoring (APRM) syttem.

d. Residual Heat Removal (RHR) system.

e. Reactor Equipment Cooling (REC) system. (2.5) )

QUESTION 6.03 (3.00)

Concerning the electrical power distribution system

a. What design feature determines if a supply breaker for a 480 VAC Motor Control Center will automatically trip during load shedding? (1.0)

b. Describe two (2) conditions that must be met to close a 4160 VAC bus supply breaker from the control room. (1.0)

c. Explain the reason for the caution plate on Board "C" requiring that  :

4160 VAC breaker 1AF is to be closed before the operator attempts to .

close breaker 1FA. (1.0) i i

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I QUESTION 6.04 (3.00) l For the following RCIC system valves, supply the following information:

1. Specific motive power for operating the valve.

2. Normal position

3. Auto open signals / conditions

4. Auto close signals / conditions

a. Inboard Steam. Isolation Valve (M0-15)

b. Outboard Steam Isolation Valve (MO-16)

c. Steam Supply Blocking Valve MO-131) i

d. Turbine Trip Throttle' Valve (3.0)

(Responses should be numbered a.1, a.2, a.3, etc. AND numbered setpoints j are NOT required for full credit.) 1 1

I QUESTION 6.05 (1.50) l

a. Why is it imperative that that the Reactor Water Cleanup (RWCU) system never be operated with blow down to the condenser and rad waste simultaneously? (0,5)

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b. State WHEN and explain WHY the RWCU system blowdown flow control valve  :

will trip. (1.0) l l

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l QUESTION 6.06 (2.50) l l

a. List 3 ways that the Rod Block Monitor (RBM) may be bypassed. (1.5) I l

b. Describe how the RBM utilizes the input from en LPRM detector that has failed high or low. Limit discussion to how the faulty input is  ;

treated in the Averaging / Counting circuits. (1.0) l l

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QUESTION 6.07 (2.50) i For the High Pressure Coolant Injection (HPCI) system component failures  !

listed below, state if the HPCI WILL or WILL NOT inj ect upon actuation. j Further provide the REASON.it will not inject or the POTENTIAL ADVERSE 1 AFFECT if it does inject with component. failure. I

a. The HPCI Auxiliary Lube Oil Pump fails to operate. j

b. The Minimum Flow Valve fails to auto open. I

c. The HPCI discharge flow element output signal fails to it's maximum output. (2.5) i 1

QUESTION 6.08 (1.00)

Concerning switches and indication on panel 9-5 for the Reactor Manuel i

" Control System (RMCS), which statement below is correct?

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n. The " Emergency In" position of the " Emergency Notch Override Switch" bypasses all interlocks except Rod Worth Minimizer blocks. .

b. The " Rod Drift Alarm Test Switch" resets the drift alarm when the rod is in an even position.

c. The " Timer Malfunction Select Block Switch" has 3 positions that are  !

labeled Test, Operate, and Reset.

d. The " Rod Settle" amber light indicates that a rod is in the settle mode, and that directional valve 121 should be open. (1.0)

QUESTION 6.09 (1.00) i TRUE or FALSE: l

a. Once the Low Power Alarm Point is exceeded while increasing power, a software failure will still generate a Rod Worth Minimizer rod block. .

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b. The Rod Sequence Control System (RSCS) group notch logic will block an

" Emergency In" signal from the RMCS. (0.5 ea.) (1.0)

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. QUESTION 6.10 -(1.00)

-Concerning the Reactor Protection System (RPS), which statement below is correct?

a. A scram signal is generated if an IRM channel indicates a Hi-Hi condition with it's' companion APRM channel indicating an INOP condition.

b. The Main Steam Line high Radiation Scram signal can be bypassed for instrument testing.

c. An APRM INOP scram signal can be caused by only 2 conditions, d.- The Reactor high Pressure Scram is a backup to the:High Neutron Flux Scram. (1.0)

QUESTION. 6.11 (1.00)

.Which of the following statements most accurate'ly describes the neutron detector used in the Source Range monitors?

a. The detector is a fission chamber,' operating in the ionization voltage region, and pressurized to about 200 psig with Argon gas,

b. The detector'is a fission chamber, operating in the proportional  !

voltage region and pressurized with 18 psig of Nitrogen gas.

c. The detector is a fission chamber, operating in.the ionization voltage ;j region, and and pressurized to 18 psia of Nitrogen gas,

d. The detector is a fission chamber, operating in the proportional voltage region, and pressurized to about 21S psig of Argon gas.-(1.0) i

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QUESTION 6.12 (2.00)

Concerning the Reactor Vessel Level Control system, answer the following TRUE or FALSE.

a. Reactor Feed Pump (RFP) speed can be controlled by the Vessel Master Controller, the Dahl Controller, or the Startup controller.

b. If Control Level "B" is lost while selected foricontrol, switching to Control Level "A" will NOT clear-the RFP lockout'.

c. If Feed Flow "A" instrument is lost while at 50% power, the Dahl enntroller will automatically assume control of RFP speed.

d. In the " Balance" position, the Vessel Level Master Controller deviation meter indicates the difference between the desired level and i the actual level. (0.5 ea.) (2.0)

' QUESTION 6.13 (2.00)

n. State the signals and setpoints which will automatically initiate the Standby Gas Treatment (SGT) system. (0.75)

b. State the specific actions that will result from the initiation of each signal above. Discuss only those actions that occur in the SGT system, and include major post initiation actions that occur. (1.25) l l \

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l =Zr__EBQGEQUBES_:_NQBd8Lt_8BNQBd8Lt_EdEBQENGl_8ND PAGE 12 l 88D10LQQ1G8L_GQNIBQL QUESTION 7.01 (2.00) l During a reactor startup:

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a. What Rod Control System feature must be tested during withdrawal of the first rod? (0.5)

b. What is required to be done when a rod reaches position 48? (0.5)

c. What conditions determine that the reactor is critical? ( 0. 5 ) .

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d.- How can the operator make a quick determination that the Period Meter I is indicating accurately? (0.5)

QUESTION 7.02 (2.00)

Answer the following with regard to the primary containment:

a. During a reactor plant startup, when must the Oxygen concentration be less than 4% ? (0.5)

b. Upon increasing ' temperature of the Suppression Pool, State the temperature at which a Technical Specification Limiting Condition for Operation is FIRST entered. (0.50)

c. The reactor shall be scrammed if suppression pool temperature I reaches ________. (0.50)

d. During reactor isolation conditions, the reactor pressure vessel shall be'depressurized to less than 200 psig at normal cooldown rates if the Suppression Pool temperature reaches ________. (0.50) l i

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.I QUESTION 7.03 (2.50),/

For each of the following plant conditions or events,

1. State the E0P(S) that should be entered by title or procedure number.

(Also state if no specific E0P entry is required.)

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2. Give the specific EOP entry condition met, including any applicable setpoints. (

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n. Suppression Pool Temperature = 105 deg F

, 1 b, Drywell Pressura = 2.25 psig

c. Main Steam Line Rad Monitors read 3.5 times normal f ull 'powe r b ac kg r outid ,

d. Reactor Pressure = 1055 psig

e. South CR0 Equipment area radietion level = 55 mrem /hr. (2.5) 1 QUESTION  ? ,'. 0 4 (1.00)

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i During RPV flooding in accordance with E0P-1, Att. I, the operator is required to terminate all CSCS inj ection prior to depressurization. What is the reason for this requirement?. (1.0) a' o' l

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Pv" l QUESTION 7.05 (2.503.

Procedure 2.4.8.6, " Loss of fuel Pool Cooling", provides instructions for regaining cool'ing due to loss of inventory or component failure.

a. What is the specified backup method of cooling in the event of a Fuel Pool Cooling System component failure? (0.5) y b.- What are three sources of makeup that may be used in the event of loss of inventory? (0.75)'

c. ~In'the-event of a total and sustained loss of cooling capacity (NOT l INVENTORY CONTROL), what'cctions must be taken by the operators-to i miniraiz e radiation exposure and prevent spent-fuel degradation and any- i sig3%q uent radio active release?

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y QUESTION 7.06 (2.50)

s. What are O differeret controls available to the control room operator

..* e" to retard or prevent the automatic operation of ADS Safety / Relief valves? (1.0)

b. What condition (s) should be verified before using any of these i features or controls? (0.5)

c. What can the" control room operator do to DEACTIVATE-automatic 1 operation of the ADS system? (0,5)

d. What conditions will cause automatic lowering of the setpoint of the 2 lowest set relief valves? (0.5)

QUESTION 7.07 (7.50)

The reactor is at '100% power ar# it is suspected that an SRV is stuck open.

Concerning Abnormal Procedure 2.4.2.3.1, " Relief Valve Stuck open":

a. If no position lights are lit, what are 4 control room instrument indications'that could be used to verify a stuck open valve? (1.0)

b. After verifying that a valve is open, what are 3 methods the operator

) can use to attempt closing the valve? {1.5)

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QUESTION 7.08' (3.00)

a. How do the Emergency Operating Procedures CEOP's) provide the operator with guidance for assessing Reactor Pressure Vessel (RPV) LEVEL during elevated temperature conditions.in the Drywell? (1.0)

b. What conditions do the E0P's specify for the operator to ascertain prior to placing in MANUAL or securing.any Core Standby Cooling System (CSCS)?. (0.8) i l

c. What are 2 purposes of " Emergency Depressurization"? (0.6) I

d. What are 2 of the 3 conditions that would require RPV flooding? (0.6) l l

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J QUESTION 7.0g (3.00) l l

Concerning the trip of a Reactor Recirculation (RR) Pump at power, answer the following TRUE or FALSE and explain why:

s. If the operator determinen that the plant is operating in the

" Instability Region", the only option allowed by the procedure for attaining stability is to push rods. (1.0)

b. The operator is allowed to correct flux oscillations only by changes -.

in Control Rod position. (1.0)

I

c. The requirement that IDLE loop temperature must be within 50 deg's, of q core inlet temperature to restart the RR pump is based on thermal 1 shock to RPV RR inlet piping and Rams Heads. (1.0) i 1

QUESTION 7.10 (2500)  !

a.- Define or explain, " Limiting Control Rod Pattern". (0.5) i l

b.' Who is normally responsible for determining and reporting that a

" Limiting Control Rod Pattern" exists? (0.5)

J

c. What are 2 of the 3 "Special Operations" that may cause a limiting pattern? (0.5) l

d. List 2 of the 3 conditions, actions, or limits any one of which the operator may choose to initiate or impose, if forced to operate with a limiting pattern. (0.5) 1

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'?)ESTION 7.11 (2.00)

a. Procedures warn the operator against tripping breakers 1FE & 1GE (EDG feeders to critical busses)1f either the STARTUP or EMERGENCY Transformers are lost. Explain the reason for this particular  :

caution. (1.0)

b. In the event that power is lost to the No-Break Power Panel because power does not transfer to MCC-R, What are 2 actions that can be taken l by the operator to restore power. (1.0) t I

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i at__ odd 181HIBollVE_E800EDUBESt_GQUDIIl00St_eUD_ Lid 116I19BS PAGE 17 i i

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i QUESTION 8.01 (2.50)  ;

I For purposes of Emergency Classification using the modular concept depicted )

in the CNS Emergency Plan, state which MODULE (S) the following SUBMODULES will fall under: ,

n. Primary Coolant Leak i

b. Reactor Protection System failure l i

c. Fire  ;

d. Other limiting conditions f or operations

o. Control room evacuation (2.5) s QUESTION 8.02 (2.00)

According to the CNS Emergency Plan Implementing Procedures (EPIP's);

a. Where are the Technical Support Center (TSC) functions shifted to if the TSC becomes uninhabitable? (0.5) l l

b. What are the 3 means of communication available in each Operations l Support Center (OSC)? (1.0) j

c. Normally, from where do personnel on duty in the OSC receive their j work assignments? (0.5) '

I QUESTION 8.03 (2.00)

It is discovered today, September 22, 1987, at 0800, that a monthly surveillance item which was due Thursday, September 17, during the midnight shift (0000-0800), was NOT performed.

In addition, you learn that the last monthly surveillance for this item was performed four (4) days late. It was performed on time for six months previous to last month.

Have any extended time intervals for this surveillance as given by the CNS Technical Specifications been exceeded? Explain your answer. (2.0) l

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Dt__6001NISIBoIIVE_EBQQEQUBESt_QQUQ11100St_680_ Lid 1I611QUS PAGE 18 l QUESTION 8.04 (2.50)

a. List the 3 reviewers require- to review surveillance tests for completion and acceptability. (1.0)

b. Who are 2 individuals (Titles) that must be notified immediately if failure to complete a surveillance procedure forces a reduction in plant power. (0.5)

c. Who (Title) has the responsibility for insuring that the " Daily Surveillance Log" is completed and all scheduled surveillance has been performed? (0.5)

d. A Shift Supervisor orders the performance of surveillance that he determines is required by an event (eg; heatup, cooldown), and is not time dependent. Who (Title) is responsible for evaluating the adequacy of the documented surveillance? (0,5)

QUESTION 8.05 (1.00)

CNS Technical Specifications state that " Irradiated fuel shall not be handled in or above the reactor prior to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reactor shutdown."

WHICH one of the following most accurately describes the reason?

a. This is the minimum time it takes to set up for fuel handling.

b. Decay heat must be below a specified level.

c. Fuel handling accident analyses are based on 24-hour decay.

d. An accurate Shutdown margin cannot be calculated until Xe is on its decay cycle. (1.0)

QUESTION 8.06 (2.00)

The reactor scrammed from 100% power due to high neutron flux caused by a complete MSIV closure. Explain whether or not a safety limit has been exceeded. (2.0)

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at__8Dd1N1118811VE_EBQQEQUBEft.QQUD1Il0NSt_860_L1011811Q83 PAGE 19 QUESTION 8.07 (2.00)

After any unscheduled scram:

a. Where does the responsibility lie for determining that the plant and j associated safety systems responded as required by the CNS Technical Specifications? (0.5)

b. Who by title will normally be assigned responsibility to identify reactor conditions existing prior to the scram and provide an event description of the scram? (0.5)

c. What is the basis for compliance with Restart Criteria "A" -- THE PLANT IS IN A SAFE CONDITION? (1.0)

QUESTION 8.08 (2.50)

n. What are 2 documents the Shift Supervisor could utilize to determine i if an event required a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification? (1.0) I

b. When making an initial report on the Emergency Notification System (ENS), who and where are you communicating with? (0.75)

c. Indicate by YES or NO answer if the following require "Immediate Notification".

1. An individual receives a 15 Rem whole body dose.

2. The ENS is found to be inoperative.

3. An ESF system is inadvertently actuated. (0.75)

QUESTION 8.09 (3.00)

a. Explain how the CNS Equipment Clearance and Tagging procedure assures ,

that a system is returned to a normal lineup after maintenance or repair is complete. The explanation should include the title of any personnel involved. (1.0)

b. Why may the action required in "a" above not be required for mainten-ance or repair performed during outages in Cold Shutdown? (1.0)

c. Who are 3 individuals that may sign the " Clearance Released By" section of the clearance when the job is complete? (1.0)

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l Az__8001NISIB811VE_EBQQEQuBEf t_GQUQ1Il0 net _8NQ_ Lit l11811QUS PAGE 20 i

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-QUESTION 8.10 (3.00)

A task must be performed in a 150 mrem /hr "High Radiation Area". Consider f the following individuals for the task by determining their allowable

' exposure, approvals that must be obtained, and stating any other {

considerations that'must be made in accordance with CNS administrative l procedures or any other applicable limits or guidelines. State how long each could stay in the area.  :

a. A 22 year'old male contractor has received'400 mrem in the current quarter with a life time exposure of 19.5 Rem. He has a current NRC FORM-4 on file.

b.- A 27 year old male CNS employee with a 35 Rem lifetime exposure has i accumulated 50 mrem during the present week.which is also his 1 quarterly exposure. ]

c. . A 24 year old female, 2 months pregnant, has received prenatal exposure training and has opted to accept the provisions of Regulatory Guide 8.13. Her current second quarter exposure is 20 mrem, which is also her exposure for the year.

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St__8001NISIB611VE_EBQQEQUBEEt_QQUQ1110Nat_oND_L101I8I1QUS PAGE 21 1

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QUESTION 8.11 (2.50) l l a. Complete the following table from EPIP 12, Emergency Exposure Control.

l Emergency Exposure Limits ,

Sampling Corrective Life-Saving Under Or Actions Accident Protective Conditions Actions Whole Body 5 1.____ 2.____

(rem)

Thyroid 15 125 3.____

(rem)

Extremities 75 100 4.____

(rem) (2.0)

b. Who (Title) can authorize the the utilization of the above exposure limits? (0.5) 1 I

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END OF CATEGORY 08

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

• • • • • )

!!RC LICEllSE EXNilMTI0il itNID0tlT EQUATI0ilS, 00:lSTNITS, AliD C0iiVERSI0ftS l

6=m*C*deltaT p 6=U*A*deltaT l

P = Po*10 sur*(t) -

t P = P *e /T SUR = 26/T T = 1 /p + (p-p)/X p T=1/(p-p) T = (@-p)/X p p = (Kerr-1)/Kerr = deltaXerr/Kerr p = 1*/TKerr + perr/(1+ _AT)

A = 1n2/tg = 0.693/tg K = 0.1 seconds-1

~

I = Io*e "*

CR=S/(1-~K err) 2 R/hr = 6*CE/d feet  !

Water Parameters 1 gallon' = 8.345-lbm = 3.87 liters 1 ft3 = 7.48 gallons Density @.STP = 62.4 lbm/ft3 = 1 gm/cm3 Heat of vaporization = 970 Btu /lbm

. Heat of fusion = 144 Btu /lb 1 atmosphere = 14.7 psia = m29.9 inches Hg.

l Miscellaneous Conversions 1 curie = 3.7 x 101U disintegrations per second 1 kilogram ='2.21 lbm d 1 horsepower = 2 54 x 103 Btu /hr :j 1 mw = 3.41 x 10b Btu /hr l 1 inch = 2.54 centimeters -l degrees F = 9/5 degrees C + 32 )

degrees C = 5/9 (degrces F - 32) 'i 1 Btu = 778 ft-lbr i

i-I -Et__IBEQBY_QE_NVQLE88_EQWEB_EL8HI_QEEB8Il0Nt_ELUIDat_8NQ PAGE 22 l IBEBdQQYNedlGS l

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-ANSWE3S -- COOPER' -87/09/22-WHITTEMORE, J.

I l ANSWER 5.01 (1.00)

b. -

l REFERENCE CNS Rx. Theory, P. 3-38 292003K101 ...(KA'S)-

i ANSWER 5.02 (1.50)

The rod position will be the same (0.75) because.the outward motion needed to attain a given period equals the inward motion necessary to kill the period. (0.75) (CONCEPT) (1.5) '

REFERENCE CNS Rx. Theory, P. 7-8 292005K104 ...(KA'S)

ANSWER 5.03 (1.00) i

1. S iz- of the . rod

2. Flue distriebtion (rod location)

3. Moderator temperature

4. Type of absorber material

5. Span

6. Pitch Accept answers eluding to a change in rel. flux (any 3, 0.33 ea) (1.0)

REFERENCE CNS Rx. Theory, Pp. 5-29, 5-30 292005K109 ...(KA'S) l

___._m_ _ _ _ _ _ _ _ _ _ _ _.

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Et__IBEQBl_QE_NVQLE6B_EQWEB_EL6NI_QEE86110Nt_ELUIQ1t_68Q PAGE 23 IBEBdQQ1Ned101 l I

ANSWERS -- COOPER -87/09/22-WHITTEMORE, J. l i

ANSWER 5.04 (2.50)

n. "3" is the correct answer (0.5].-The highest Xenon concentration will be in the center of the core (0.25), which is the high flux region from the previous operating period (0.25). This will increase the flux in the area of the peripheral control rods (0.25] to increase

'their worth (0.25). (1.5)

b. 1. TRUE

2. FALSE [0.5 es.) (1.0) l REFERENCE l CNS Reactor Theory, P. 6-12 292006K108 ...(KA'S)

ANSWER 5.05 (2.00) a.. TRUE i

TRUE

~

b.

c. FALSE  ;

l

d. TRUE [0,5 ea.) (2.0) ]

I I l

REFERENCE CNS Rx. Theory, Pp.6-9 -- 6-11*QNUM 292006K112 292006K111 ...(KA'S).

ANSWER 5.06 (2.00)

Xenon (0.5] will peak and then decay, adding positive reactivity and decreasing SDM. [0.25]

Samarium (0.25] will peak after shutdown and remain at peak until subsequent startup, adding negative reactivity and increasing the SDM. ,

l

[0.25) This reactivity is only a fraction of the reactivity associated with Xenon. [0.25)

The overall effect considering all aspects will significantly decrease SDM over a longterm period. (0.53 (2.0)

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

5t__IBEQBl_QE_NUQLE6B_EQWEB_EL6NI_QEEBeI100t_ELUIQSt_6NQ PAGE 24 IBEBdQQ1 Nod 10S ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

REFERENCE CNS RX. Theory, Pp. 6-12 -- 6-15*QNUM 292006K120 292006K107 ...(KA'S)

ANSWER 5.07 (1.50)

n. Doppler or fuel temperature

b. Void

c. Void [0.5 es.) (1.5)

REFERENCE CNS Rx. Theory, Pp. 4-20 -- 4-42 201003K5L/ 292008K119 292008K120 ...(KA'S)

ANSWEH 5.08 (1.50)

a. Resonance broadening-neutron absorbtion at other than discreet energies. (Doppler Effect) (0.75)

b. Self-Shielding. (0.75)

REFERENCE CNS Reactor Theory, P. 4-37 292004K104 292004K109 ...(KA'S)

ANSWER 5.09 (2.00)

a. Increase (0.5) More resonance peaks absorb neutrcns. [0.53 (1.0)

b. Increase (0.5] Gap decreases, fuel temp decreases, less peak overlap.

So, Doppler increases. [0.53 (1.0)

REFERENCE CNS HT8FF Theory, Pp. 4-41, 4-42 292004K109 292004K108 ...(KA'S)

Et__IBEQBI_QE_SUQLEoB_EQWEB_EL6UI_QEEBoIl0Nt_ELUlQSt_6UQ PAGE 25 IBEBdQDIUedIQS ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

i1 ANSWER 5.10 (1.50)

To prevent fuel cladding disintegration during a DBA LOCA due to excessive peak clad temperature (0.5) by limiting bundle stored energy (0.51 such that any given fuel pin at any given axial / planar point will have a sufficiently low peak clad temperature during a DBA LOCA and subsequent dry-out conditions (0.5). (1.5)

REFERENCE CNS HT&FF Theory, P. 9-17 293009K111 ...(KA'S) l i

ANSWER 5.11 (1.00)

MAPRAT = APLHGR/MAPLHGR Limit REFERENCE CNS HT&FF Theory, P.9.24 293009K114 ...(KA'S)

ANSWER 5.12 (1.00) b.

REFERENCE ,

CNS HT&FF Theory, P.6-76 )

291004K114 ...(KA'S) i ANSWER 5.13 (1.00)

(b)

REFERENCE CNS HT&FF Theory, Pp. 6-100, 6-101 293006K113 ...(KA'S)

L__________-___ _

5___'IHEQBl_QE_NUQLE88_EQWEB_EL8HI_QEEB8Il0Ni ELu1QSt_8NQ PAGE 26

.IBEBdQQ1N86101 ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

ANSWER 5.14 -(3.00)

n. Decreases (0.5]. There is less steam flow, therefore, less pressure drop through-the main steam lines (0.5]. -(1.0) b .- Increases (0.5). With the same amount of cooling water through the condenser and less of a heat load [0.5). (1.0)

c. Decreases ( 0. 5 ] . - Less extraction steam from the turbine to heat the feedwater (0.5]. (1.0)

REFERENCE

.CNS HT&FF Theory, Pp. 7-45 -- 7-52 f '

293007K109 293006K127 293007K106 ...(KA'S)

ANSWER 5.15 -(1.50)

a. -- 4.

l

b. -- 3.

c. --

1.

REFERENCE- -

CNS HT&FF Theory, Pp. 9-5 -- 9-8 293009K101 293009K102 293009K103 ...(KA'S) .

i l '

ANSWER 5.16 (1.00)

a. Severe overheating of fuel cladding due to inadequate cooling. (0,5)

I

b. Fuel cladding fracture caused by relative expansion of the fuel j pellets inside the cladding. (0,5) )

REFERENCE CNS.HT&FF Theory, P.9-41 293009K105 ...(KA'S) I 1

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l ht__EL6NI_SISIEUS_DESIGNt_QQUIBQLt_800_INSIBudENI6I198 PAGE 27 i

ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

ANSWER 6.01 (2.00)

1. Channel fastener assemblies will meet in the center of the cell.

2. The lifting handle boss, or protrusion, faces the control rod in the cell.

3. The serial number on the fuel channel and/or lifting handle can be read from the center of the cell.

4. The channel spacer buttons are adj acent to the control rod blades.

5. There is cell to cell symmetry. (any 4, 0.5 ea.] (2.0)

REFERENCE OSTM BK. I, CH. 2, P . 1 '7 l

234000K101 ...(KA'S)

ANSWER 6.02 (2.50)

a. The RWCU takes suction from the "A" recirculation loop. (0.5)

b. The CRD hydraulic system supplies the purge flow to the recirculation pump mechanical seals. (0.5)

c. Recire. Loop Flow elements provide input signals to the APRM flow converters. (0.5)

d. The recire. loops provide suction and return paths for RHR in the shutdown mode. OR, Accept LCPI Inj ection f or full credit. (0,5)

e. The REC system provides the necessary cooling water to the recire.

pump motors and mechanical seals and cooling water for the MG set oil system. (MG Cooling Water not req'd for full credit) (0.5)

REFERENCE OSTM BK. 2, CH. 2, P.41 202001KK11 202001K107 202001K110 202001K121 202001K123

...(KA'S)

1 1

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ht__EL8NI_SYSIEUS_QESIGNt_QQUIBQLt_oNQ_INSIBudENIoIl0N PAGE 28 l l

ANSWERS -- COOPER -87/09/22-WHITTEMORE, J. l l

ANSWER 6.03 (3.00)

{

a. Breakers whose control circuitry do not have UNDERVOLTAGE COILS will remain closed upon loss of power. (0.5)

]

b. 1. All protective relays must be reset. (0.5) f

2. The Sync. Switch for the selected breaker must be taken to the "0N" position. (0,5)

3. Control power available

4. De-energized bus .  ;

5. Breaker racked in (any 2, 0.5 es.]

c. An interlock between the breakers prevents backfeeding the non-critical bus from the critical bus. [0.5) The interlock is an undervoltage coil on the bus between the breakers that must be energized or breaker 1FA will trip. [0.5] (1,0)

REFERENCE OSTM BK. I, CH. 9, Pp. 14, 31, & Table 5 262001K404 262001K401 262001A102 ...(KA'S)

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ht__EL6HI_H1HIEUS_ DES 1Q6t_CQUIB9Lt_6ND_INSIBudENIeI1QN PAGE 29 ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

]

I l

i ANSWER 6.04 (3.00) {

a.1 AC a.2 Open a.3 Rx. vessel low-low level j o.4 Gp. V isolation 1 d

b.1 DC l I

b.2 Open b.3 Rx. vessel low-low level k b.4 Gp. V isolation c.1 DC c.2 Closed c.3 Rx. vessel low-low level c.4 Rx. vessel level high d.1 AC/ Spring (accept " Spring" only) d.2 Open d.3 none (Accept closure of MOV-131) (0.15 ea.] (2.25) .

d.4 Loss of lube oil pressure, Low pump suction pressure, High turbine exhaust pressure, Overspeed, Gp.V isolation. (0.15 ea.] (0.75)

REFERENCE OSTM BK. IV, CH. 7 Pp. 8-12 217000K201 217000K102 217000K402 ...(KA'S)

ANSWER 5.05 (1.50)

a. Operating the drain paths cross connected will decrease condenser vacuum possibly causing Turbine trip. (0.5)

b. 1. Low pressure (5 psig) upstream of flow control valve will trip the valve to prevent drawing a vacuum on the RWCU. (0.5)

2. High pressure (140 psig) upstream of valve will trip the valve to preclude overpressurizing downstream piping. (0.5) l REFERENCE OSTM BK. IV, CH. 12, Pp. 9, 10 l 204000K106 204000K107 204000K402 204000K602 ...(KA'S) 4

ht__ELaNI_S1HIEdS_ DES 10Nt_GQUIBQLt_6NQ_INSIBudENIollQU PAGE 30 ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

ANSWER 6.06 (2.50)

a. 1. Manual operation of the RBM BYPASS switch. (0,5)

2. Reference APRM input level < 30%. (0.5)

3. Edge rod selected. (0.5)

b. 1. A failed low LPRM detector is removed from the averaging and counting circuits. (0,5)

2. A failed high detector is averaged and processed as if it were a valid input. (0.5)

REFERENCE OSTM BK. I, CH. 9, Pp. 8, 17 .

215002K401 215002K604 ...(KA'S)

ANSWER 6.07 (2.50)

a. Will not inj ect. (0.5) Steam admission valves will not open. [0.25]

l b. Will inj ect . [0.5) Pump overheating or seal damage may occur during i low or no flow conditions. (0.5)

c. Will not inject. [0.51 as signal will cause turbine speed to remain at minimum. (0.25] (2.5)

REFERENCE OSTM BK.IV, CH. 9, Pp. 9, 10, 15 206000K411 206000K414 206000K418 ...(KA'S) l l

! ANSWER 6.08 (1.00) '

b.

REFERENCE OSTM BK. IV, CH.2, Pp. 7-10 l

, 201002A202 201002K406 201002K407 ...(KA'S) ]

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1 ht__EL681_11SIEba_DEH10Nt_QQNIBQLt_oNQ_INSIBUBENIoIIQN PAGE 31 ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

ANSWER 6.09 (1.00)

a. TRUE

b. FALSE REFERENCE OSTM BK. IV, CH. 3. P. 13 201004K406 201006A207 ...(KA'S) li ANSWER 6.10 (1.00)

d. (1.0)

REFERENCE OSTM BK. IV, CH. 5, Pp. 14-18 2120000004 ...(KA'S)

ANSWER 6.11 (1.00)

a. (1.0)

REFERENCE OSTM DK. I, CH. 4 P.12 291002K119 ...(KA'S)

ANSWER 6.12 (2.00)

n. False

b. True 1

c. False

d. False REFERENCE OSTM BK. III, CH. 6, Pp.9, 10, 18 216000K113 259001K607 291003K108 ...(KA'S)

- - _ _ _ _ - _ - _ _ _ _ _ i

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ht__EL6NI_SISIEdS_DE1106t_QQNIBQLt_eND_INSIBudENIol1QN PAGE 32 ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

l 1 l J ANSWER 6.13 (2.00) l '

o. High DW pressure----------------2 psig Low Rx. Vessel------------------12.5" High Rad. in the exh. plenum----100 mr/hr. (Accept 10 mr/hr)

(0.15 for es, signal and 0.1 for ea. setpoint) (0.75)

b. For Rx. level & DW pressure:

l Fans start, Train inlet / outlet valves open, d/p control valves operate to maintain 0.25' H20, Electric heaters maintain humidity < 70%, and fan vortex operates to maintain flow and limit maximum d/p across L filter train. (0.15 ea.) (0.75)

For high radiation:

All of the above plus: The exhaust valve from primary containment vent line to the RB exhaust plenum shuts, (0.25] and the valve from primary containment to the SGT. (0.25] (0.5) i REFERENCE OSTM BK. III, CH. 3 Pp. 20, 21 261000K401 ...(KA'S) l l

I 1

l Zi__EBQQEQUBES_:_UQBdokt_oBUQBdol.t_EdEBQEUQ1_oNQ PAGE 33 f BoDIQLQQ1GoL_QQUIBQL ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

/

ANSWER 7.01 (2.00) ,

a. Emergency In Notch Override. (0.5)

b. Make a coupling check.

l

c. Flux increasing on a stable period with no rod motion. (0.5) I

d. Multiply time (in seconds) it takes power to double by 1.443.  ;

OR, Check against other indication. (0,5) .

1 REFERENCE Proc. 2.1.3, P. 3 201002K406 201003A202 201003K406 201003K507 ...(KA'S)

ANSWER 7.02 (2.00)

I

a. Within 24 hours of going to "RUN"

b. 95 deg F (0.50)

c. 110 deg F (0.50)

d. 120 deg F (0.50)

REFERENCE CNS PROC 2.1.1, P.12,a TECH SPEC 3.7.A.1 223001G011 223001G015 223001K513 ...(KA'S)

ANSWER 7.03 (2.50)

a. Primary Containment Control, E0P Sup Pool Temp > 95 deg F )

b. RPV Control and PC Control, E0P 1&2 - DW pressure > 2.0 psig l None (Also accept E0P-1) l

d. RPV Control, E0P >1045 psig j

e. Secondary Containment Control,EOP Area > 50 mrem /hr (Accept  !

"None" with explanation) l REFERENCE I CNS PROC. 5.8, Pp.1-4 & E0P 3, TAB. 3.2 )

272000K101 295024K011 295025K011 295026K011 ..,(KA'S) l l

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Zt__EBQQEQUBEE_:_NQBdoLt_8BNQBdelt_EUEBQEUQY_600 PAGE 34 86010LQQ1GoL-QQUIBQL ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

ANSWER 7.04 (1.00)

Prevent washing boron out of the core. (1.0)

REFERENCE E0P-1, ATT. 1, P. 4 295031K302 ...(KA'S)

ANSWER 7.05 (2.50)

a. Cross-tie to the RHR system. (0.5)

b. 1. Condensate makeup to skimmer surge tank. (normal)

2. Fire hoses

3. Hoses connected to the service box condensate and demin. water hose connections.

4. From Condensate via RHR

5. From SW via RHR [any 3, 0.25 ea.] (0.75)

c. 1. Evacuate RB

2. Isolate secondary containment

3. Initiate SGT

4. Provide makeup as above.

5. Allow pool to boil (0.25 ea, action) (1.25)

REFERENCE Proc, 2.4.8.6, Pp. 1, 2 233000K107 233000K302 233000K306 ...(KA'S) l ANSWER 7.06 (2.50) l a. ADS inhibit, ADS Timer reset, LLS Logic reset, or stop all LP CSCS l pumps. (Any 3, 0.33 es.) (1.0)

b. Ensure level is increasing due to injection. (0.5) i l c. Place " ADS INHIBIT SWITCHES" to " INHIBIT". (0.5)

d. Any Safety / Relief valve has opened (0.2) AND [0.11 a HP Reactor Scram signal is present. [0.2] (0.5) l l

1 l

l 1 - - . _ _ _ _ - _ - _ _ _ - _ _ _ _ _ - _ _ _ _ _ -

Zz__EBQQEQUBES_:_NQBdoLt_6BUQBd6Lt_EdEBQENG1_600 PAGE 35 B6010LQQ196L_GQUIBQL ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

REFERENCE Proc. 2.2.1, Pp. 8-11 2180000010 218000K402 218000G002 ...(KA'S)

ANSWER 7.07 (2.50)

e. Change in DEH control, Change in Feedwater, Supression Pool Level, Supression Pool Temperature, Computer, SPDS valve position, Tail Pipe Temperature, 30 psig tail pipe pressure, gen. load change, stm flow /

feed flow mismatch. (Any 4, 0.25 ea.) (1.0)

b. 1. Cycle Switch Between Auto and Manual l

2. Turn ADS inhibit Switches to " INHIBIT" position.

3. Remove fuses in the Auxiliary Relay Room panel.

4. Reduce reactor power. [any 3, 0.5 ea.] (0.5)

REFERENCE Proc. 2.4.2.3.1, Pp. 2, 3 .

239002A401 ...(KA'S) 2 ANSWER 7.08 (3.00)

a. There is a table in the CAUTIONS section that specifies instrument accuracy level ranges at various DW temperatures. (1.0)

b. The operator must determine the the system was auto initiated inadvertently, (0.4) OR adequate core cooling exists. [0.41 (0.8)

c. To maintain adequate core cooling (by promoting inj ect ion) . (0.3)

To maintain Primary Containment Integrity (by minimizing release potential). (0.3)

d. 1. RPV Level cannot be determined.

2. DW Temp. reaches RPV sat. temp.

3. OW pressure cannot be maintained below the Primary Containment design pressure. (any 2, 0.3 ea. (0.6)

REFERENCE E0P-1, Pp. 6, 03, ATT.I & E0P-2, P. 3 ,

259002K001 ...(KA'S) )

\

\

I

Zt__EBQQEQUBES_ _NQBd6Lt_8BNQBd8Lt_EMEBQENQY_68Q PAGE 36 f 88Q10LQQ108L_GQUIBQL l ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

ANSWER 7.09 (3.00)

a. False. [0.5) Procedure also allows-for increasing flow using the unaffected pump. [0.53 (1.0)

b. True. [0.5) As this would counter effect.the attempt to attain j stability. [0.51 (1.0)  ;

l

c. False. [0.5) Based on possible RR pump damage. [0.51 (1.0)

' REFERENCE Proc. 2.2.68, Pp. 13,14, & Proc. 2.4.2.1.1, Pp. 2, 3 .

202001A203 202001A221. ...(KA'S)  ;

I ANSWER 7.10 (2.00)

a. A pattern which contains a rod which, if completely withdrawn, could result in a MCPR < 1.07. OR, A pattern-that results in operating beyond a thermal limit. (0,5)

b. Reactor Engineer (0,5)

c. 1. Interchange of normal patterns (due to burnup).  ;

2. Establishing special patterns in order to locate failed fuel. 1

3. Establishing special patterns due to CR0 system malfunction. {'

[any 2, 0.25 ea.] (0.5)

d. 1. Both RBM channels in service.

2. Tag out Rod movement control switch.  ;

3. Limit reactor power so that error will not result in MCPR going  !

below 1.07. Cany 2, 0.25 ea.) (0.5)

I i

REFERENCE I Proc. 2.4.1.4, Pp. 1, 2 l

-2010020001 201002K015 ...(KA'S) );

i, 21__EBQQEQUBEH_:_NQBd6Lt_8BNQBdoLt_EdEBGEUQ1_6NQ PAGE 37 86010LQQ1GoL_QQUIBQL ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.  ;

l

)

1 ANSWER 7.11 (2.00)

a. These breakers have an anti-pump circuit which does not permit reclosing if the closing signal is still present. (1.0)

b. 1. Place the Bypass Transformer / Inverter Selector switch on Bd-C in the Bypass Transformer position.

2. Operate the Static Switch 18 Transfer Test switch to the " FORCE TO AC LINE" Position.

3. Place the CLOSE TO STARTUP SYSTEM switch on the inverter accessory module cabinet in the closed position.

4. Operate switch S3 inside static switch cabinet to the "LINE" position. [any 2, 0.5 es.) (1.0)

REFERENCE Proc's. 2.4.6.2, 2.4.6.3, & 2.4.6.7 262001K406 262002K401 ...(KA's) l l

i l

l r

at__6Dd1NISIB6IIVE_EBQQEQUBEHt_QQUQ1110NSt_6ND_L16116IIONS PAGE 38  !

ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

-ANSWER' 8.01 (2.50)

n. Radiological b' . Operational

c. Fire-Natural-Security

d. Operational and Radiological

e. Operational (0.5 ea.) (2.5)

REFERENCE Proc.-5.7.1, Att. A-294001A116 ...(KA'S)

ANSWER 8.02 (2.00)

a. Control Room (0.5)

b. 1. Telephone

2. Gaitronics

3. Bonephone (0.33 wa.) (1.0)

c. TSC l i

REFERENCE Proc.5.7.7, Pp. 3 & Proc. 5.7.8, Pp. 1, 6 294001A112 ...(KA'S) l l -'

ANSWER 8.03 (2.00)

The extended surveillance time may not exceed 25% of the surveillance

. interval, or 30/4 = 7.5 days. At this time, the surveillance is only I l

five days late. (1.0) l However, the total time for the last three consecutive surveillance may l not exceed 3.25 times the. surveillance interval. For the last three i l intervals,' time = 31 + 35 + 36 = 102, and 3.25

• 31 = 100.75 days. So this i l allowable interval has been exceeded. (1.0) l REFERENCE l CNS TS P. Sa & Proc. 0.26, P.8 201001G011 ...(KA'S) l 1

( . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ A

St__6Dd1NISIB6I1YE_EBQQEQUBESt_CQUQ1110NSt_6ND_L10116I19NS PAGE 39 ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

ANSWER 8.04 (2.50)

a. Individual performing test, Shift Supervisor, Responsible engineer or test coordinator. (0.33 ea.) (1.0)

b. Ops. Supervisor and DMNO (0.25 ea.) (0.5)

c. Swing shift Shift Supervisor (0.5)

d. Operation's Supervisor (0.5)

REFERENCE Proc. 0.26, Pp. 7-9 201001G001 ...(KA'S)

ANSWER 8.05 (1.00) c.

REFERENCE ,

CNS TS, P.209a 234000G006 ...(KA'S)

ANSWER 8.06 (2.00)

Yes (0.5) the scram was produced by a high flux instead of by the MSIV closure (0.75). If this happens, a safety limit is assumed to have been exceeded (0.75). (2.0) s REFERENCE CNS TS 1.1.c.

212000G005 ...(KA'S) l I

.l <

l ! '",

]

I 1 at__80dlNISIB6IIVE_EBQQEPJJBEft_CQUQ1Il0NSt_680_LIdlI6IIQUS PAGE 40' ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

4 a

ANSWER 8.07 (2.00)

F

n. SORC (0.5)

b. STA ,/ (0.5) >

c. No safety limits were exceeded ~(0.53 and the plant is in a safe and ,'

stable mode of operation. (0.5) (1.0) ,-

REFERENCE , t 7, Proc. 2.0.6, Pp. 1, 2, 6 ,

294001A111 294001A112 ...(KA'S) -

r.

ANSWER 8.08 (2.50) >

n. Title 10 Code of Federal Regulations (19 CFR 50.72), or CNS proceoure 2.0.5, Shift Communicator Responsibility. (1.0)

b. NRC Operations Center (Op's Officer), NRC Headquarters, Bethesda, Maryland. (0.75)

c. 1. NO 2 YES

3. NO (0.25 es.) (0.75)

/

REFERENCE <

Proc. 2.0.5, Pp. 1-4 3 j 294001A116 ...(KA'S)

/ -

l~ ,.

i

,o , ,

1 i

i

i' e

'At__6DdINISIB6IIVE_EBQQEQNSEnt_QQUQIIl982t_aND_LidII611QUS PAGE 41 ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

i ANSWER 8.09 (3.00)

a. The " Normal Position" section of the clearance will be filled out (0.51 by the Shift Supervisor (0.25] or the Control Room Operator,

[0.25] detailing the. position of valves, switches, etc. (1.0)

b. For ^this condition the lineup will be returned to normal by the system valve lineup prior to startup. (1.0)

c. Person" responsible for the job, Person signing the " Clearance Issued" e section, Supervisor of the person signing the " Clearance Issued" section,3.or person completing the repair. (any 3, 0.33 es.] (1.0) he REFERENCE, Proc. 0.9, P. 5 ,

204001K102 ...(KA'S)

ANSWER 8.10 (3.00)

a. ConO/ actor personnel are administrative 1y limited to 1000 mr /qtr. and there sare ne daily or weekly limits. [0.53 That assumption alone f.

1. would allow the worker 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to complete the j ob. A consideration to be addressed is exceeding the value for 5(N-18). This would be lawful as long as he did not exceed the federal quarterly limit of

-t 1.25 Rem /qtr. [0.51 (Allow full credit for conservative action to stay below 5(N-18).) (1.0)

b. Station personnel are administrative 1y limited to 1000 mrem /qtr.[0.25]

However the must have approval to exceed 150 mrem / day and 300 mrem /wk. [0.25] Thus with approval this individual could remain in the area.for 950/150, or 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. [0.51 (Allow full credit for allow-ing full 3 rem /qtr. exposure.) (1.0)

c. An individual who accepts the provisions of the Reg Guide is limited

. to an exposure of 500 mrem for the entire gestation. [0.51 Thus, this

~{ person.could work in the area for 480/150, or 3.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. There would l- be NG further exposure during the pregnancy. [0.51 (1,0)

REFERENCE Proc. 9.1.2.1. Pp. 5-7 294001K103 ...(KA'S)

/

l 1 i at__eDd1NISIBoIIVE_EBQQEDUBESt_QDUQlIl0NSt_6UQ_ Lid 1I6I198S PAGE 42 l

ANSWERS -- COOPER -87/09/22-WHITTEMORE, J.

ANSWER 8.11 (2.50)

a. 1. 25

2. 75

3. No limit

4. 200 (0.5 en.] (2.0)

b. The Emergency Director (0.5)

REFERENCE EPIP 12 ATT. A 294001A116 ...(KA'S)

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