Text

Exam Rept 50-458/OL-86-01 During Wk of 860203.Exam Results: Two of Three Reactor Operator Candidates & One of Two Senior Reactor Operator Candidates Passed
	ML20203B195
Person / Time
Site:	River Bend
Issue date:	04/02/1986
From:	Cooley R, Whittemore J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20203B191	List: ML20203B187; ML20203B195;
References
	50-458-OL-86-01, 50-458-OL-86-1, NUDOCS 8604180048
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o OPERATOR LICENSE EXAMINATION REPORT No. 50-458/0L 86-01 Licensee: Gulf State Utilities P. O. Box 2951 Beaumont, Texas 77704 Docket: 50-458 Operator License Examinations at River Bend Station (RBS)

Chief Examiner: Y!J!M Jphn E. Whittemore Date Approved By: . .

R. A. Cooley fh/hb Date Summary Operator license examinations for three (3) Reactor Operator candidates and two (2) Senior Reactor Operator candidates were cdministered at the RBS facility during the week of February 3, 1986. Two(2)ofthethreeReactor '

Operator candidates and one (1) of the two (2) Stnior Reactor Operator candidates passed these examinations and have been issued the appropriate licenses.

i g4180048860412 V ADOCK o3000458 PDR l

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1-2 Details

1. Examination Results Written examinations were administered to two Reactor Operator candidates and a simulator examination was administered to one additional Reactor Operator. Both candidates passed the written examination and the remaining candidate failed the simulator examination.

Two Senior Reactor Operator candidates were administered a written examination, one taking Category 8 only. Both of these candidates were also administered simulator examinations and one was further administered a plant walk-through operating examination. Both candidates passed the written examination. One candidate failed the simulator examination.

2. Examiners i

J. E. Whittemore (Chief Examiner)

D. N. Graves J. L. Pellet

3. Examination Report Ferformance results for individual candidates are not included in this report. This Examination Report is co.nposed of the sections listed below.

A. Examination Review Coment Pesolution ;

In general, editorial coments or changes made during the examination ;

or during subsequent grading reviews are not addressed by this resolution section. This section reflects coments and recomended changes to examination answer keys by the licensee. Examination key ,

modifications resulting from these coments and recommendations are ;

included in the master examination keys, which are provided elsewhere in this report. Coments and resolutions are listed by section question number.

1.03.a Full credit should be given for using correct half-life of 5.02.a 40 seconds and correct equation without requiring redundant ,

statement in second part of answer.

RESOLUTION: Accept. Key modified I

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3 1.03.c Importance factor with explanation should be full credit 5.02.c answer as it is discussed in referenced theory section.

RESOLUTION: Accept. Key modified.

1.04.c Answer should be TRUE, according to referenced material and SR0 examination key answer for Question 5.04.c RESOLUTION: Accept. Key modified.

1.08 The answer key describes the effects of Nucleate Boiling, not transition boiling. The correct answer should be,

" Decrease in heat transfer coefficient due to steam blanketing and re-wetting of the clad surfaces, which results in less efficient heat transfer." See GP Heat Transfer psges 15 and 39.

RESOLUTION: Accept. Key modified.

1.09.a Correct answer is " Increases" critical power. See Simulator 5.08.a Text Volume 4. Heat Transfer Student Handout pages 11-2 and 11-3, and GE Morris Training Center Thermodynamics, Heat Transfer, and Fluid Flow, page 9-87.

RESOLUTION: Accept. Key modified.

1.09.d Correct answer is " increases" Critical Power. See same 5.08.d referenceaspart(a)Page11-3.

RESOLUTION: Accept. Key modified.

2.01.a Correct response should only be Item 3 of the answer key 6.01.a since question asks only for automatic actions in Normal Service Water System.

RESOLUTION: Accept. Key modified.

2.01.b Correct response should not require answer key Item 3 since 6.01.b the question asks only about Service Water System and not (RP)CCW. Item 3 valves are CCW system valves.

RESOLUTION: Accept. Key modified.

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4 2.02.a Additional equally correct systems required for Condenser 6.02.a Air Removal System operation are itemized in 50P-0025, pre requisites for start-up.

RESOLUTION: Accept. Key modified to include listed systems.

2.02.c There are two separators in the system. Another equally 6.02.c correct answer would be to have the separator located after the off-gas condenser. See SD Chapter 41 Pages 41-45.

RESOLUTION: Accept. Key modified.

2.05.c Part(a)discussesRPCCW,andpart(b)discussesTPCCW. Part (c) asks for functions of PCV-111, but doesn't specify which system and is therefore ambiguous. Request this be taken into account when grading and the question be clarified prior to subsequent use.

RESOLUTION: Accept. Question and key modified.

2.06.a "Short-Cycle Cleanup" should also be accepted as a full credit answer. See 50P-0007 Sect. 4.2, Page 5.

RESOLUTION: Accept. Key modified.

2.06.b " Provide adequate NPSH for RFP's" is correct reason. See SD Chapter 31, page 31-15.

RESOLUTION: Accept. Key modified.

2.07.a " Speed Increaser" is synonymous with " Speed Changer."

6.03.a RESOLUTION: Accept. Key modified.

2.10.b Item 4. Correct answer should be, " FALSE." The HPCS Test Return Valve, M0V-F023, closes on high drywell pressure which is an automatic isolation signal. See RBS Tech.

Specs, page 3/4.6.33.

RESOLUTION: Accept. Key modified. ;

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l 3.02.a Full credit response for purpose of valve should be "To l 6.06.a prevent the rods from operating at excessive d/p's, as the i valves are installed to repressurize the the exhaust header after a scram."

RESOLUTION: Accept. Key modified.

3.02.b Per referenced material, the timing and sequence of the 6.06.b DCV's do not determine rod speed. Therefore second part of answer is incorrect and should be deleted.

RESOLUTION: Accept. Key modified.

3.04 Correct setpoints per latest revised Tech. Spec's are:

RV level low: Level 1 or -143" DW pressure high: 1.68 psig RV level low: Level 3 or 9.7" LP ECCS Pump Running ADS Drywell Pressure Bypass Timer: 5 minutes RESOLUTION: Accept. Key modified.

3.05.c " Increasing existing detector voltage," should be acceptable for partial credit if dunking chambers (RBS term for B-10 detector) is not given in candidates response. See SD Chapter 16, page 16-16.

RESOLUTION: Not accepted. Proposed answer is not supported by reference.

3.06.c Correct answer key should be: j o Upscale high trip: In RUN setpoint is 118% and is reduced to 15% when not RUN, i.e., all other mode switch positions. See TS page 3/4.3-2, and SD Chapter 19, page 19-5. l 0 Upscale high alarm trip: In mode switch position other than RUN, provides a 12% fixed signal which is changed to a signal based on flow in RUN. See SD Chapter 19, page 5.

RESOLUTION: Accept. Key modified.

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6 3.08.d Correct answer is " FALSE.". Can only be bypassed with mode switch in SHUTDOWN or REFUEL. See SD Chapter 22, page 13.

RESOLUTION: Accept. Key modified.

3.08.e Correct answer is "TRUE." See Tech. Spec. basis for RPS LSSS for MSIV Closure Scram. TS page B 2-8.

RESOLUTION: Accept. Key modified.

3.10.b "10 seconds" in second part of answer should riot be required for full credit. Question doesq't ask for duration of scram, only why it occurs.

RESOLUTION: Accept. Key modified.

3.11.c Question asks for " Automatic Action" (singular). Key lists 6.10.c three actions. Any one of three should be acceptable for full credit.

RESOLUTION: Not accepted. Answer drawn directly from licensee supplied reference material.

4.02 The answer needs to be revised per the revised copy of A0P-0008. Key answer is completely incorrect.

RESOLUTION: Accept. Key modified to reflect revised procedure.

4.03.c Another valid answer is using reject flow from RWCU to stop 7.03.c level increase. See SD Chapter 9, page 1.

RESOLUTION: Accept. Key modified.

4.03.d Another valid answer is to open bottom head drain to RWCU.

7.03.d See same reference as part (c) above.

RESOLUTION: Accept. Key modified.

4.04.c "To save equipment" should be acceptable for " Emergency 8.08.c Workers."

RESOLUTION: Accept. Key modified.

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l 4.06.c R0's are not required to memorize detailed subsequent action steps of A0P's. Beyond the scope of a license exam for R0 and should be deleted.

RESOLUTION: Not accepted. Full credit does not require detailed subsequent action knowledge. Requires general system and l procedural knowledge.

4.07.b Also, half scram will occur. See A0P-0010, pages 2.3.

RESOLUTION: Accept. Key modified.

4.09.b Installed drywell indication at the plant and on the 7.09.b simulator has a maximum range of 440 deg's. The plant ,

indication was modified well before the plant received it's '

operating license. The simulator modification was completed September 1985. The facility has never operated with the problem. The question as stated does not apply to this facility and therefore should be deleted.

RESOLUTION: Not accepted. Knowledge of design change or instrument modification will count as a full credit answer.

4.09.c Another acceptable answer is due to the difference in the 7.09.c reference leg and variable leg vertical runs in the drywell. '

Candidates were taught that the fuel zone will respond different from the narrow or wide rar.ge due to the fuel zones variable leg negative vertical run in the drywell l compared to positive runs on the other instruments. See attached level instrument piping schematics and instrument analysis summary.

RESOLUTION: Accept. Key modified.

4.10.a The question does not specify Primary or Secondary Containment. Both are different. Question requires clarification prior to subsequent use. A correct answer for either containment daily verification should be acceptable for full credit.

RESOLUTION: Accept. Key modified, l t

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l 8 1 4.10.b An equally correct method of reducing drywell pressure is by l use of SOP-0040, page 10, by use of the H2 mixing system.

RESOLUTION: Accept. Key modified. i 5.09 Pellet Clad Interaction - Intergranular Stress Corrosion Cracking was not included in this groups initial or remedial training programs due to design change in fuel construction, i.e., barrier fuel. Question should be deleted as it does not apply to this facility. See attached GE letter.

RESOLUTION: Accept. Question deleted.

5.11.b To assume that megawatts remain constant for a change in subcooling is not realistic and therefore misleading.

Credit should be given for a thermodynamic discussion of changes to other parameters necessary to maintain a constant megawatt load with a change in subcooling. Since plant i efficiency will vary with subcooling, according to part a, a I change in subcooling will cause a change in megawatt load due to the accompanied change in plant efficiency. Therefore, a reactor power change will be required to maintain a constant megawatt load.

RESOLUTION: Accept. Extraneous correct material is acceptable but not ,

required for full credit.

6.09.a " System is reset by operator," is not required for full credit to describe design feature of FWCS that prevents losing RFP's due to a level transient following a scram, and '

should be deleted from key.

RESOLUTION: Not accepted. Complete description of design feature j includes capability for manual reset.

1 7.04.a Another limitation on heater removal is based on the ability to maintain sufficient feed flow for power level, i.e., if w reactor power is greater than 75% LP heaters cannot be bypassed because bypass line will only provide 25% of rated feed flow.

! 7.04.b Future use of question should specify the heater parameter that is fluctuating.

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9 7.04.c Another reason for caution when shutting down the heater drain pumps is the subsequent decrease in feedwater temperature and resultant increase in reactor power. See Simulator Malfunction 94.

1 RESOLUTION: Connents noted. Extraneous reasons accepted but not required for full credit.

7.07.b Both b. and c. parts require detailed memorization of A0P 7.07.c subsequent action steps. Full credit should be given for a generalized discussion in candidates answer. Licensed operators are not required to have subsequent action steps memorized. See ADM-0022, page 26, section 6.2.1. Both parts b. and c. of this question seem to be inappropriately testing knowledge beyond the scope of a licensing exam procedure category.

RESOLUTION: Not accepted. Required answer reflects general knowledge and understanding of procedures and design, not memorization.

7.08 See above comment and ADM-0022 reference. General discussions should be acceptable in lieu of requiring memorization of tabulated conditions / ranges from an E0P.

Again, material being required for full credit is beyond scope of license exam.

RESOLUTION: Not accepted. Accepted range of key is sufficient so that only general knowledge is rec,uired.

7.10.b "From Control Room Emergency Locker," should not be required for full credit. A general discussion of E0P subsequent should be acceptable for full credit. See ADM-0022, pg. 26.

RESOLUTION: Not accepted, passing credit for this question does not require knowledge of kit location.

8.04.b Answer key requires candidate to have the specifics of long term Tech. Spec. action statement committed to memory.

River Bend requires licensed personnel to commit to memory those action statements containing immediate or less than one hour requirements. They are expected to use the Tech.

Specs, for other action statements and must be able to recognize an LCO. Since every LCO contains an action l I

O 10 statement, it is unreasonable to have all action statementi committed to memory. According to ES-402, the answer required is beyond the scope of knowledge required for the l SR0 exam. An appropriate generalized answer for full credit i j should be, "By complying with the associated action j statement."

! RESOLUTION: Accept. Key modified to require only general knowledge j for full credit. G I

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! 8.05.c Another equally correct answer is, "If the LCO specifies i that TS 3.0.4 is not applicable." See TS 3.0.4 RESOLUTION: Accepted. Key modified.

l 8.05.d " Failure to comply with an action statement when required,"

should be acceptable for full credit. To be in a situation i requiring the use of an action statement implies the LCO l j cannot be met.

i RESOLUTION: Accept. Question graded accordingly.

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i 8.11 "All relief sheets have two sections" should not have to be l stated in candidates answer for full credit if he discusses i

both of the sections.

RESOLUTION: Accept. Key modified. ,

i j B. February 5, 1986 Exit Meeting Summary j Near the conclusion of the site visit, the examiners met with licensee i representatives to discuss the results of the examinations. The j following personnel were present for the exit meeting.

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NRC LICENSEE j D. Graves D. Gipson J. Pellet E. Brohl D. Andrews i

D. Ashley i i

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11 One of the three candidates was reported to have clearly passed the simulator portion of the operating examination. The other two

, candidates had not clearly passed the simulator portion of the operating examination. It was also reported that the one candidate affected had clearly passed a plant walk-through examination. It was explained to those present that written examination results would not i be immediately available and that operating examination evaluations did not necessarily reflect written examination results.

j C. GENERIC COMMENTS

! The following apparent problems or areas of weakness were observed by the examiners and noted to the licensee.

1. Candidates exhibited poor ability to use procedures during both !

abnormal and emergency transient conditions. Particular noteworthy, was failure to complete and verify complete, immediate actions.

2. Failure to recognize loss of instrumentation during degraded conditions. The event that precipitated this comment by the examiners was later determined to have been caused by a problem '

with simulater modeling.

D. EXAMINATION MASTER COPIES The SRO and R0 master examination and answer keys follow. Changes resulting from licensee comments are reflected in these keys.

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U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _BlMER_RENQ_1____________

r REACTOR TYPE: _RWB-REh_________________

DATE ADMINISTERED:_th4024Qi________________ '

EXAMINER: _WBlIIEdQBEt_Ja__________ ,

APPLICANT: __,,_____________________

INRIBUGIl0N1_IQ_6EELIQ8HIl Uno separate paper for the answers. Write answers on one side only.

Stcple 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 categdry and a final grade of at lotst 80%. Examination papers will be picked up six (6) hours after tho examination starts.

% OF CATEGORY % OF APPLICANT'S CATEGORY -

__V6LUE _IQI6L ___1GQBE___ _V6LUE__ ______________Q&IEGQBI_____________ t

_25tDQ__ _21100 ___________ ________ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

_25tDQ__ 25t0Q ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND ElERGENCY SYSTEMS

.21x00__ _25100 ___________ ________ 3. INSTRUMENTS AND CONTROLS 25tDQ._ _25100 ___________ ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENC) AND RADIOLOGICAL CONTROL 100100__ 100AQ0 ___________ ________ TOTALS FINAL GRADE _________________% I All cork done on thir, examination is my own. I have neither givon nor received aid. I APPLICANT'S SIGNATURE i

11__EBINCIELER_QE_ NUCLE 88_EQWEB_EL8NI_QEEB8IIQNt PAGE 2 IBEBdQQ1Ned1 Git _BE61_IBAN1EEB_aND_ELu1D_ELQW QUESTION 1.01 (2.00)

Your reactor has j ust scrammed f rom extended f ull power operation. )

Ton (10) hours later cooldown is complete, and the reactor is measured ct that time to be shutdown by 1% dk/k. Describe the changes, if any, to the reactivity by which the reactor is shutdown over the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

Include any adverse conditions that may occur as a result. (2.0)

QUESTION 1.02 (3.00) l A reactor startup is in progress. You have been given the cotimated critical rod position for the conditions at 0800.

You start to pull control rods at 0800 for the approach to critical. HOW WOULO EACH OF THE FOLLOWING conditions or events l AFFECT the ACTUAL CRITICAL ROD POSITION (more rod withdrawal, less rod withdrawal, or no significant effect)?

o. One reactor recirculation pump is stopped (Hypothetical '

situation only). (0.5)

b. Xenon is changing due to extended power operation, terminated 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months previously. (0.5)

c. Shutdown cooling is stopped (significant decay heat). (0.5)

d. Reactor head vent is inadvertently closed. (0.5)

o. Moderator temperature is gradually decreasing. (0.5)

f. Reactor Water Cleanup System isolates (significant decay heat). (0.5) 1 1

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(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

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11__EBINQIELER_QE_NUQLE88_EQWEB_EL8NI_QEEB8IIQNm PAGE 3 IBEBBQQ1NedIQ1t_HE41_IB8NSEEB_88Q_ELUIQ_ELQW QUESTION 1.03 (3.00)

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A new experimental reactor uses a new fuel that has 5 delayed precursor groups. The longest has a half life of 40 sec's. and the average is 8.5 occ's.

a. For this reactor, what is the stable period Crate of power decrease) after shutdown from the power range ? Explain and show any calculations necessary.

(1.25)

b. What specific information is needed to determine a beta fraction for this reactor ?

c.

HOW and WHY will the EFFECTIVE beta fraction differ from the ACTUAL beta fraction ?

QUESTION 1.04 (2.50) 1 True or False

c. Void coefficient is directly proportional to core size.

b. At 15% power, the major contributor to Power Coef ficient is Fuel Temperature Coefficient.

c. The larger the core, the lower the relative neutron leakage.

d.

The 2 isotopes that make the largest contribution to the Doppler effect are U-235 and P-240.

o. The Overall Temperature Coefficient becomes a meaningless term below the power range.

QUESTION 1.05 (2.00)

c. Explain the positive effect that occurs to the Moderator Temperature Coefficient when moderator temperature is increased. (1.0)

b. Explain the effect on Fuel Temperature Coefficient due to changing moderator temperature and void fraction. (1.0)

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

Iz__EBINCIELER_QE_NWGLE8B_EQWEB_EL8HI_QEEB8IlQNA PAGE 4 IBEBBQQIN8BIQit_HE8I IB8HIEEB_8NQ_ELW1Q_ELQW QUESTION 1.06 (1.50)

Explain WHY core orificing is necessary and HOW orificing accomplishes this purpose.

(1.5)

QUESTION 1.07 (2.00)

Match one of the following numbered items with each of the four lettered otstements. A letter-number sequence is sufficient. (2.0)

1. MAPRAT 5. PCIOMR

2. APLHGR 6. GEXL

3. CPR 7. TOTAL PF $

4. FLPD 8. LHGR

o. Parameter by which plastic strain and deformation are limited to less then 14.

b. Ratio of bundle power required to produce onset of transition

c. boiling somewhere in the bundle to actual bundle power.

Parameter by which peak clad temperature is maintained less

d. then 2200 degrees F during postulated design basis accident.

Contains guidelines restricting power ramp rates above the threshold power.

QUESTION 1.08 (1.00)

When boiling transition occurs in the boiling transition region of a fuel channel, how and why does the film heat transfer coefficient change ?

(1.0)

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Iz__EBINGIELE1_QE_HUGLE8B_EQWEB_EL8HI_DEEB8IIQNt PAGE 5 IBEBdQQ188 digit _HE8I_IB8NSEEB_8NQ_ELu1D_ELQW QUESTION 1.09 (2.00)

For each of the following conditions, state whether it will cause an increase, decrease ,

or have no effect on critical power. Assume all other persmeters are constant.

i s. Decrease in reactor pressure.

(0.5)

, b. Increase in inlet subcooling.

(0.5)

c. Increase in core flow. (0.5)

d. Location of axial power peak moves up in the core. (0.5)

QUESTION 1.10 (1.00)

Explain pump.

the difference between cavitation and gas binding in a centrifugal (1.0)

QUESTION 1.11 (2.50)

Explain why the reactor vessel level indication errors below occur:

a. If variable leg temperature (and pressure) are above calib' ration conditions, level.

indicated water level will generally be lower than actual (1.253 b.

If variable leg temperature (and pressure) increase when water level is zero or very low, an instrument which is not density compensated will indicate a level which is higher than actual. (1.25) 1

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

Iz__EBINQIELER_QE_ NUCLE 88_EQWEB_EleNI_QEEBeIIQNm PAGE 6 IBEB5001N8510ft_BE81_IB8NSEEB_8ND_ELUID_ELQW QUESTION 1.12 (2.50)

e. Explain how the validity of a 1/M plot during fuel loading is affected by'

1. Proximity vf source to the detector.

(1.0)

2. Direction of fuel load in relation to detector. (0.75)

b. How would the CHANGE in neutron count rate vary between a Koff change occurring prior to the midpoint of fuel load and en equal Keff change occurring near the end of fuel load ?

(0.75) i l

(***** END OF CATEGORY 01 *****)

2z__EL8NI_DE1198_ INCLUDING _18EEI1_8HD_EMEBGENGl_111IEd1 PAGE 7 QUESTION 2.01 (2.50)

e. What automatic actions will occur to the Normal Service Water System as a result of any Standby Service Water auto initiation signal ? (1.0)

b. What will additionally occur if initiation results from loss of RPCCW header pressure ? (1.0)

c. Describe how an emergency water supply can be made available to the RHR system. (0.5)

QUESTION 2.02 (3.00)

a. Name 5 systems that must be operating to support the operation of the Condenser Air Removal system. (1.0)

b. What are the inlets (suctions) and discharges of the specific stages of a Steam Jet Air Ejector unit ? (1.0) 1

c. Place the follow'ng Off Ges System components in the correct order of I actual flowpath:

1. Cooler Condenser.

2. Prefilter. I

3. Dessicant Dryer.

4. Off Gas Condenser. I

5. Moisture Separator.

6. H2 Detector. (1.0)

QUESTION 2.03 (2.00)

e. Describe a typical 120 VAC Uninterruptible Power Supply. Include power sources (i.e. 120 VAC, not switchgear or MCC number), how they are arranged to ensure power is r.untinuously supplied to its connected loads, and any automatic t'.ansfers. (1.5)

b. What provides the NORMAL power supply to the EHC System (except for the EHC pumps)? (0.5) i l

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2t__EL6NI_DE11GN_INGLUDING_18EEIl_8ND_EMEBGENCY_111IEMS PAGE 8 QUESTION 2.04 (2.50)

e. What permissives must be met ?or an auto transfer to occur between power supplies for a 4.16 KV normal service bus ? (1.0)

b. What determines whether a fast or slow auto transfer occurs ? (0.5)

c. From where is it possible to parallel the SPLIT 4.16 KV non-safety (normal service) buses ? Be specific for all buses. (1.0)

QUESTION 2.05 (2.50)

a. What RPCCW heat loads will be. Laolated due to a LOCA isolation signal ? (1.0)

b. Why must the TPCCW System he maintained in a specific pressure band during operation ? (1.0)

c. Aside from system pressure control, what function does the TPCCW System Pressure Control Valve (PCV-111) serve ? C0.5)

QUESTION 2.06 (2.50)

a. What is the purpose of the recirculation line from the outlet of condensate demineralizers to the main condenser ? (1.5)

b. Describe the automatic operation of the condensate demineralizer bypass 1 valve. Explain the reason for the automatic operation. (1.0) I I

l QUESTION 2.07 (2.00)

a. List the Lube Oil pumps associated with a Reactor Feed Pump. (1.0)

b. Describe in correct order the Feed and Condensate system long cycle cleanup flow path. (1.0) l

(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

21__EL6HI_DE11EN_INCLUDINE_18EEI1_6ND_EMEBRENC1_111IEMS PAGE 9 QUESTION 2.08 (2.50)

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c. Describe two methods for detecting and/or locating a leaking fuel bundle or assembly during the refueling procedure. (1.75)

b. What is the purpose of the refueling seal assembly ? (0.75)

QUESTION 2.09 (2.50)

e. What function is served by the Main Steam Shutoff Valves ? (0.75)

b. List the three separate drain top locations common to each steam line. Further, describe how the system is constructed to provide for adequate and effective drainage during startup and normal power operation. (1.75)

QUESTION 2.10 (3.00)

s. Describe how shutdown cooling could be attained if a normal suction valve (from recirculation system) could not be opened. (1.0)

b. Answer the following TRUE or FALSE:

1. The reason for RCIC automatic isolation due to low steam pressure is that low pressure is indicative of of a pipe break.

2. The RCIC turbine exhaust vacuum breakers will shut on High Drywell Pressure OR Low Turbine Steam Supply Pressure.

3. Shutdown cooling flow can be partially diverted to the RCIC Spray Line for thermal shock prevention.

4. Signals to automatically isolate the containment do not operate any High Pressure Core Spray valves. (2.0) l

(***** END OF CATEGORY 02 *****)

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21__IN11BudENI1_88Q_GQNIBQL1 PAGE 10 QUESTION 3.01 (3.00)

e. Aside from indication, what are two of the three uses (or reasons for measuring) pressure above the Core Plate ? (1.0)

b. Why is a thermocouple mounted on the vessel head vent line ? (0.5)

c. Briefly explain the function of the LOGIC NETWORK portion of the Core Flow Summing Network. (0.75)

d. What general problem (s) may result during maintenance or surveillance on a level indicating system sharing a common 0/P sensing line ?(0.75)

QUESTION 3.02 (2.50)

a. What is the purpose of the equalizing valves between the exhaust and cooling water headers in the CRD hydraulic system ? (1.0)

b. Assuming normal system conditions, what determines the speed at which an individual control moves. (1.0)

c. How is excessive control rod speed prevented in the event that the flow or pressure control station fails in a manner to increase drive header pressure. (0.5)

QUESTION 3.03 (2.50)

a. What are two reasons for the interlock requiring the flow control valve to be at minimum position before a recirculation pump can be started ? (1.0)

b. Describe three interlocks of the recirculation control system that are designed to preclude excessive thermal stress. (1.5)

QUESTION 3.04 (1.50)

List the signals and their setpoints that must be present to initiate the Automatic Depressurization System. (1.5)

(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

2t__IN11BWMENI1_6ND_QQNIBQL1 PAGE 11 QUESTION 3.05 (2.50)

o. For a Source Range Monitor channel, what are the trip units that use a common input ? (1.0)

b. What are the inputs to en SRM INOP trip unit ? (0.75)

c. How can the SRM system be made more sensitive to Keff change during fuel manipulation and why does greater sensitivity result ? (0.75)

QUESTION 3.06 (3.00)

a. While observing the full core display, what indication would you see as a result of:

1. An LPRM detector failing high ?

2. An LPRM detector failing low ?

3. An LPRM detector being selected for display ? (1.0)

b. What is the basis of the setpoint for en LPRM Upscale trip ? (0.5)

c. Explain how the reactor mode switch can affect reference inputs to the APRM Upscale trip units. Be specific for all different units affected. (1.5)

QUESTION 3.07 (2.00)

Describe two different procedures the operator can use to continuously insert a control rod AND explain why one method is preferred over the other. (2.0)

. 1 i

(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

2t__IN11BudENI1_8ND_GQNIBQL1 PAGE 12 QUESTION 3.08 (3.00)

TRUE or FALSE:

a. Energizing one of the back up scram valve solenoids will have no effect on the control rods,

b. A half scram signal will not affect the Scram Discharge Volume vent valve.

c. The IRM INOP scram is bypassed in "RUN".

d. It is possible to bypass the Scram Discharge Volume High Level scram anytime.

e. The purpose of the MSIV closure scram is to inhibit the release of fission products.

f. For the Turbine Control Valve Fast Closure scram, the valve position is sensed directly. (3.0)

I QUESTION 3.09 (2.00)

e. There are 106 Reed switches within a position indicator probe and 98 are used for digital position indication. What are the remaining eight (8) switches used for specifically. (1.0)

b. What are two separate occurrences within the indicating system that will cause a ROD DRIFT ALARM ? Do NOT state malfunctions such as high cooling or drive water. State what actually causes the alarm to annunciate. (1.0)

QUESTION 3.10 (1.50)

c. Explain why it is possible to perform a dead bus transfer to alternate power on an RPS bus without tripping the reactor. (0.5)

b. What are two reasons for the direct occurrence of a scram when moving the MODE Switch from "RUN" to " SHUTDOWN" with the reactor at full power ? Consider only protection circuitry and not secondary effects.

(1.0) l i

(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

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

2t__IN11BWHENI1_6ND_QCBIEGLi PAGE 13 QUESTION 3.11 (1.50)

o. Which Area or Process Radiation Monitors are NOT part of the Digital Radiation Manitoring System ? (0.5)

b. Which of the Main Steam Line Radiation Monitor trip units or bistable units will cause a channel trip ? (0.5)

c. What automatic action will result if two Main Steam Line monitors (channels) trip in a one out of two twice logic ? C0.5) l l

l 4

l

(***** END OF CATEGORY 03 *****)

i

O 4t__PBQQEQMBEl_:_NQBd6Lt_6HNQBd6Lt_EdEBGENQ1_6NQ PAGE 14 B6DIQLQQ1Q6L_GQUIBQL QUESTION 4.01 (3.00)

< Match the following events (a-f) with the approximate pressure at which they should be performed per GOP-0001, Plant Startup to Low Power Alarm Point. The pressures may be used more than once or not at all. (3.0)

a. Place steam seals in service 1. 20 psig

b. Startup the Offgas System 2. 100 psig

c. Warm up the RCIC piping 3. 150 psig

d. Startup the first reactor feed pump 4. 250 psig

e. Start turbine shell warming 5. 400 psig

f. Startup the SJAE 6. 450 psig

7. 600 psig

8. 850 psig QUESTION 4.02 (2.50)

Instrument Air header pressure is decreasing. All systems are re-sponding properly to the decreasing air pressure. Besides keepinq j the Shift Supervisor informed of plant conditions, what actions should l be taken by the control room operator (s) and at what point (if appli-cable) per AOP - 0008, Loss of Instrument Air? (2.5)

QUESTION 4.03 (2.50)

During reactor shutdown /cooldown:

a. Describe and explain the possible effect(s) of taking the turbine off line at 15% thermal power. (1.0)

b. Why should the operator avoid supplying steam seals with the auxiliary boiler whenever possible ? (0.5)

c. How can the operator stop increasing level in the pressure vessel with a feed pump operating and the feedwater control valves already fully shut ? (0.5)

d. What can the operator do to limit or minimize bottom head cooldown ? C0.5)

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

at__EBQQEQVBES_=_NQBd8Lt_8ENQBd8Lt_EMEBGENQ1_8NQ PAGE 15 B8010LQQ1Q8L_GQNIBQL QUESTION 4.04 (2.50)

c. In addition to utilization of Time, Distance and Shielding, a concept called Source Reduction can be utilized to lower personnel exposure.

List three examples or methods that can be utilized for reducing SOURCE STRENGTH. (1.0)

b. What are normal and maximum non-emergency weekly exposure limits at River Bend ? (0.5)

c. What are the limits for emergency exposure at River Band ? (1.0)

QUESTION 4.05 (2.50)

o. Assume N0 operator action and predict plant response for a. failed open Turbine Bypass valve with the following conditions * (Assume that bypass valves are fully shut when failure occurs).

1. Turbine generator on line at 15% power. (0.5)

2. Reactor power at 8% and Mode Switch in RUN. (0.5)

3. Reactor power at 4% and Mode Switch in STARTUP. (0.5)

b. What immediate actions SHOULD be performed by the operator ? (1.0)

QUESTION 4.06 (2.50)

c. List the steps that operators must perform prior to evacuating the Control Room due to fire or smoke. (1.0) {

i

b. How do operators obtain guidance for required action upon leaving the control room ? (0.75)

c. When cooling down from outside the Control Room, how can coolant temperature be determined below 212 deg's. without installed operable indication ? (0.75) l

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

- -~ - -- - -

ft__PBQQEQMBE1_=_NQBd&Lt_8ENQBd8Lt_EdEBQENGl_8NQ PAGE 16 B8DIQLQQIQ6L_QQNIBQL QUESTION 4.07 (2.00)

c. What is the immediate action required of the operator for a loss of power to a Reactor Protection System bus at power ? (1.0)

b. Aside from isolation, what other automatic action will occur upon loss of the bus ? (1.0)

QUESTION 4.08 (2.50)

o. How does the operator verify that all rods are inserted after a scram ? Assume the computer is out of service and be specific.

b. What happens te the Recirculation Pumos on a reactor scram ? List all signals that may cause this action to occur. (1.0)

c. What are two causes of a turbine trip after a reactor scram. (0.5)

QUESTION 4.09 (2.50)

c. What are the two basic choices of action if during the performance of E0P-0002 the operator finds himself in the UNACCEPTABLE region of the Heat Capacity Temperature Limit graph ? (1.0)

b. Emergency procedures require specific action to be taken at a Drywell temperature of 330 deg's F. Installed indication has a maximum range of 200 deg's. Explain how to resolve this problem.(1.0)

c. Why will high Drywell temperature affect Fuel Zone level indication differently than Wide or Narrow range indication ? (0.5)

QUESTION 4.10 (2.50)

c. How is it verified daily that containment integrity is satisfactory ?

Specific values or numbers are not required. (1.0)

b. During operation in Mode I, how can high Drywell pressure be reduced ? Be specific as to flow path options. (1.0)

c. During a maintenance outage, how would Drywell cooling be accomplished '

upon a loss of Service Water ?

(0.53

(***** END OF CATEGORY 04 *****)

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

-- .. .- . - - - - - - - -- - - - - - - - - - - - - - - - - ~ ~ ' ---

i it__EBINGIELE1_QE_NMGLE88_EQWEB_EL8HI_QEEB8IIQNm PAGE 17 IHEBdQQ1NedIQ1t_HE81_IB8NIEEB_8NQ_ELulD_ELQW ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J. ;

4

) ANSWER 1.01 (2.00)

If the reactor was shut down by 1% dk/k as measured at the time of I i posk xenon, then SDM will decrease as xenon decays. Since xenon 4

(peak) is greater than the 1% dk/k, an inadvertent criticality could ecsult. (2.0)

REFERENCE !

6. P. BWR Reactor Theory Handout, pg 83,89

)

l ANSWER 1.02 (3.00)

o. No significant effect

b. Less rod withdrawal -

! c. More rod withdrawal

d. No significant effect

o. Less rod withdrawal s

f. More rod withdrawal (0.5 EA.) (0.5) l REFERENCE i

G. P. BWR Reactor Theory Handout, Section F., Reactivity Coefficients and Defects 1

7 ANSWER 1.03 (3.00) i

o. T= t1/2 /In2, = 40/.693, =57.7 sec's. (accept 56.7-58.7)

Maximum power change rate is dependent on longest lived delayed neutron precursor group.

(1.25) l

b. Specific yield of each precursor group.

(0.75)

c. The effective fraction will be smaller than actual fraction (0.5) as delayed neutrons are less likely to cause fast fission (0.5).(Less j likelyhood of leakage tends to increase effective fraction but is less important.) Accept

Importance Factor (1.0)

! REFERENCE j Roactor Theory Handout, Pp. 23a-2,23b-2 !

1 i

li__EBINGIELE1_QE_NuGLE88_EQWEB_EL8HI_QEEB811QNt PAGE 18 IMEBdQQ1NedICit_HE8I_IB8NSEEB_8ND_ELu1D_ELQW ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

l ANSWER 1.04 (2.50)

e. False

b. True ,

, l

c. True

d. False ,

o. False (0.5 ea.) (2.5) ;

l REFERENCE G.P. Theory, Pp. 13-27 I

l

) ANSWER 1.05 (2.00) l

o. The positive effect occurs because moderator is expanded out of the core (0.5) and less neutrons are absorbed in the moderator at higher temperature.(0,5) (1.0) i b. As temperature or voids increase, slowing down time and length become longer. (0.5) Any change in resonance peaks will become more significant as neutrons spend more time in resonant energy spectrum. (0.53 (1.0)

REFERENCE 1 G.P Reactor Theory P. 17 l

a ANSWER 1.06 [1.50)

A3 the boiling rate increases, two-phase flow resistance increases. This would tend to divert coolant flow from the higher powered center fuel bundles where it is needed the most (concept 0.75). Orificing has the offect of providing a large resistance to flow so that any additional resistance caused by two-phase flow is acceptably small (concept 0.75).

REFERENCE G. P. Heat Transfer and Thermal Limits, pg 28 4

It__EBINCIELER_QE_NUGLE88_EQWEB_EL8NI_QEEB&I1QNA PAGE 19 IBEBdQQ1NedIGit_BE6I_IB8NSEEB_8NQ_ELulD_ELQW ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 1.07 (2.00) )

o. 8

b. 3

c. 2

d. 5 (0.5 each)

REFERENCE i G. P. Heat Transfer and Thermal Limits, pg 47,53,58-59,65 ANSWER 1.08 (1.00) l Docreases,(0.5) due to steam blanketing and rewetting of the clad ourfaces. [0.53 (1.0)

REFERENCC GP HT Theory, P.18 ANSWER 1.09 (2.00)

O. Increase. b. Increase.

c. Increase d. Decreases (0.5ea.) (2.0)

REFERENCE GP HT Theory, Pp 37 - 44 l i

ANSWER 1.10 (1.00)

Covitation occurs when water flashes to steam in the pump eye.(0.5) Gas binding means that the pump is filled with a non-condensable gas.(0.53 (1.0)

REFERENCE GP HT Theory, P. 4-4 l

It__EBINQ1 ELE 1_QE_NUQLEaB_EQWEB_ELeNI_QEE86IIQNt PAGE 20 IBEBdQQ1Ned101&_BE61_IBaNSEEB_aND_ELUID_ELQW ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 1.11 (2.50)

o. The temperature increase causes a density decrease (0.53 so that the precsure felt at the tap will be lower than under calibration conditions [0.5] which will indicate a water level that is lower than actual level [0.25] (1.25)

b. The temperature has the same effect on water in the variable leg but at very low levels, the effects of steam density dominate the effects due to water density. [0.5] Steam density increases with increased temperature [0.25] which increases pressure felt at the tap, [0.25]

decreasing differential pressure and increases indicated level. [0.25]

(1.25)

REFERENCE GP HT Theory, transient analysis, Pp.8,9 ANSWER 1.12 (2.50)

o. 1. If detector is too close to the source, count rate is too high and detector may be insensitive to core changes.[0.5) If detector is too far from source, initial count rate may be low and any change will make ICRR small. [0.53 (1.0) 4

2. Loading towards the detector means that less neutrons will be absorbed before detection as core becomes larger. Thus detectors become more sensitive to core as core moves closer. (0.75)

b. A larger change in neutron count rate will occur at the end of loading ;

as a larger change results when Keff approaches unity. (0.75)

REFERENCE 1 Rx Theory Handout, P. 22.4 1

1

2t__EL8HI_DE11EN_INGLUDINE_18EEII_8ND_EdEBEENGl_111IEd1 PAGE 21 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

4 ANSWER 2.01 (2.50)

c. Normal service supply and return valves (MOV-57A,B & g6A,B shut.(1.0)

b. 1. Normal supply and return valves to CCW HX'S (MOV-501A,B & 511A,B) ,

shut. (0.5) 1 j 2. Standby supply'and return valves to CCW system (504A,B & 510A,B) I i open. (0.5] (1.0) j 1

l c. A connection is provided from Standby Service Water for flooding the containment or drywell. (0.5) j' REFERENCE RBGS SD, Ch.46, Pp.3,4 & Ch. 47,P.3 ANSWER 2.02 (3.00)

O. Main Steam, TPCCW, Condensate, 120 and 480 VAC Electrical Distri-bution, Instrument Air, Make up water, TPHVAC, TP Drains, TP

, Equipment Drains, Sealing Steam, Offgaa, Hoggers, Service I Water. (Any 5, 0.2 each) (1.0)

I b. 1st__Stg.

1 Inlet: From main condenser. Outlet: To SJAE condenser.

2nd Stg.

I Inlet: From SJAE condenser. Outlet: To Off Gas system.

! (0.25 each) (1.0)

c. Off Gas Condenser, (Moisture Separator) H2 Detector, Cooler l Condenser, (Moisture Separator), Profilter, Dessicant Dryer.

1 (Moisture Separator may appear in either or both spaces shown.

Subtract 0.2 for each arrangement shift necessary to establish correct order.) (1,0)

REFERENCE i RBGS SD Pp. 40-37, 41-5

, - . - , - - . - - . _ - - - . - - - - , - . , . - . - ~ , , _ - - . . , -, , . ~ . . . , , , ...-..n., _ - _ - , _ . . - - . , - - - , , - .,...,.,-,e.,- ,--..e

Zi__EL&NI_ DESIGN _INCLUDINQ_SeEEII_8NQ_EMEBGENC1_111IEd1 PAGE 22 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 2.03 (2.00)

c. An uninterruptible power supply inverter (0.25) receives power from rectified 480 VAC (0.25), which is the normal source.

A second source of power to the inverter is 125 VDC (0.25) from j the station battery. This supply will feed the inverter without interruption should the normal supply fail (0.25). Malfunction of both DC sources or the inverter will cause a static switch (0.25) to automatically transfer the power source to a 120 VAC regulating l transformer (0.25). (1.5)

b. Permanent magnet generator on the turbine front standard. (0.5) t REFERENCE River Bend Simulator Text, Chapter 36, EHC, pg 36-52 River Bend Simulator Text, Chapter 44, AC Electrical Distribution, pg 44-10 ANSWER 2.04 (2.50)

I

o. 1. The normal breaker trip was not manual or due to overcurrent or ground fault trip signal. (0.5)

2. Preferred source has normal voltage. (0.5] (1.0)

b. A fast transfer will occur if voltage remains > 70% of normal. (0.5)

c. 2A,8 and 3A,8 may be paralleled from the control room or switchgear.

(0.5) 4A,8 may be paralleled from switchgear only. (0.53 (1.0)

I REFERENCE RBGS SD 44, Pp.4-7 ANSWER 2.05 (2.50)

o. RWCU NRHX, Containment sample coolers, Recirc. pumps, and Drywell Equipment Drain Sump Cooler. (0.25 es.) (1.0)

b. Pressure must be > than Redwaste HX's and < Normal service water system to preclude leakage of radioactivity to the environment. (1.0)

c. Provide a pump minimum flow recirculation path. (0.5)

Zi__EL8HI_DE11GN_ INCLUDING 18EEII_8ND_EMEBGENQ1_111IEMS PAGE 23 ANSWERS -- RIVER BEND 1 -86/32/04-WHITTEMORE, J.

REFERENCE RBGS SD 48, P.6 & 49, P. 23 ANSWER 2.06 (2.50]

o. To maintain a minimum flow [0.5] through the cond. oumps, air ejector condensers, gland steam condensers, off gas condenser, and condensate l domineralizers. [0.2/ component] OR; Short cycle clean up.[1.03 (1.01

b. The valve will auto open upon a turbine trip with generator loaded greater than 70% and reclose one minute later. [0.5] To provide ,

adequate NPSH for Reactor Feed Pump [0.53 (1.0) l REFERENCE '

RBGS SD 31, Pp. 5,34 ANSWER 2.07 (2.00)

c. RFP main oil pump, RFP AC motor driven pump, RFP DC motor driven pump, Speed changer main oil pump, Speed changer motor driven pump. [4/5 req'd 0 0.25 es.] (1.0)

b. Condensate pump to RFP bypass valve,[0.15] level control valves,

[0.15] first pt. htrs., [0.15] startup recirc valve, [0.15]

condenser. [0.15] [0.25 for correct order] (1.0)

REFERENCE RBGS SD 32, Pp.2,6,7, I

l ANSWER 2.08 (2.50)

o. Within the vessel, a fuel sampler can isolate and sample a four bundle assembly.[0.5) The sampler stops circulation and allows ,

leaking fission product buildup until detection is possible. [0.5] '

The f uel pool has e f uel assembly sipper. [0.5] The sipper circulates water in an isolated assembly to detect fission product buildup.

[0.25] (1.75)

b. To provide a seal between the reactor vessel and the Drywell to form and allow flooding of the refueling cavity to the level of the upper pool. (0.75]

1

l

- l 2t__ELaNI_DE11EN_INGLWQING_laEEIX_8NQ_EMEBGENC1_ElSIEd1 PAGE 24 l

ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J. 1 REFERENCE RBGS SD 57, Pp. 19,22 l

l ANSWER 2.09 (2.50) l

o. They are shut in a peut accident situation to ensure that the MSIV-PLCS can function effectively. (0.75)

b. Upstream inboard MSIV's, Upstream of outboard MSIV's, and Down- i stream of MSSV's. [0.33 es.) All drains are routed to main con- l denser. [0.25] Drainage is routed through a restricting orifice i which can be bypassed during startup. [0.5] (1.75) !

REFERENCE j

RBGS SD 34, P.10 1 ANSWER 2.10 (3.00) ,

c. Water is pumped from the suppression pool to the vessel via the RHR heat exchangers. [0.5) The vessel is allowed to fill and overflow into the main steem lines and discharge back to the suppression pool via ADS discharge lines. [0.5] (1.0)

I

b. 1. FALSE

2. FALSE

3. FALSE

4. FALSE l

REFERENCE l RBGS SD'S 10 Pp.11,12 *** 11 Pp. 16,17 ***12 p. 2 f

]

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

. - . . . . , _ _ _ ,,5..--~,, , - . . _ -

2i__INSIBudENI1_8NQ_GQNIBQL1 PAGE 25 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 3.01 (3.00)

c. o Set control rod drive hyd. pressure.

o Set CRDM cooling water pressure.

o Leak detection system. (HPCS pipe break) (any 2, 0.5 es.) (1.0)

b. Avoid exceeding temperature limits on Drywell Equipment Drain Sump during venting. (0.5)

c. The circuit determines whether loop flows are added or subtracted (depending on pump configuration) to determine total flow. (0.75)

d. Other indicating systems may be adversely affected by the equalizing valve on the instrument. (0.75)

REFERENCE RBGS SD 3- 5,16,17,18 4

q ANSWER 3.02 (2.50) i

c. (After a scram, exhaust header pressure decreases through the directional control to the scram discharge header.) To prevent the rods from operating at excessive d/p's, (0.5) the valves are installed to repressurize the exhaust header. (0.5) (1.0)

b. Flow is controlled through the directional control valves by pre-

determined throttling. (1.0)

c. A relief in the drive water line limit drive water pressure to (510 psi) above reactor pressure. (0.5) j

! REFERENCE

{ RBGS SD 6, Pp. 11,14,15 1

1 J l i

i

at__INSIBudENI1_8ND_CQNIBQL1 PAGE 26 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 3.03 (2.50) l

c. o Prevents valve cycling as pump speed changes.

o Prevents excessive temperature stress as a result of flow changes.

o Provides for reduced pump starting current. (any 2, 0.5 ea.] (1.0)

b. o Conditions in a. above are met o Vessel bottom head and steam dome delta T < 100 deg. F.

o Recire loop and steam dome delta T < 50 deg. F o Recirc loop suction line < 50 deg. F. between loops.

(any 3, 0.5 es. ] (1.5)

REFERENCE RBGS SD 8, Pp. 7-9 '

! ANSWER 3.04 (1.50) o RV water level low;_ -Level 1, 143" o DW pressure high;_1.68 psig o RV water level low;_ Level 3, 9.7 psig.

o LP ECCS Pump running o ADS Drywell Pressure Bypass Timer: 5 minutes (1.5)

REFERENCE 4 RBGS TS, P. 3/4 3-36 i

ANSWER 3.05 (2.50)

c. Downscale, Retract permit, Upacale--High (alarm), Upscale--

high-high (scram). (0.25 ea.] (1.0)

b. Voltage, Mode Sw. position, Module status. (0.25 es.) (0.75)

c. By replacing the normal fission chamber with a B-10 detector (0.25) which uses a higher detector voltage (0.25] and has a different gas mixture.(0.25) (0.75)

REFERENCE RBGS SD 16,Pp. 20,25 I

l

2i__IN1IBudENI1_8ND_GQNIBQL1 PAGE 27 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

t ANSWER 3.06 (3.00)

O. 1. Red light

2. Green light

3. Yellow light (0.33 es.) (1.0)

b. Trips before LHGR Limit is reached. (0.5)

c. Upscale high trip: A 15% signal is raised to 118% in run.[0.5)

Upscale thermal power trip: In "RUN" a signal is inserted based on flow. [0.5)

Upscale high alarm trip: A 12% reference signal is changed to a signal baseo on flow in "RUN".[0.53 (1.5)

I REFERENCE I RBGS SD 18,P.11 & SD 19,P.5 ANSWER 3.07 (2.00)

o. Hold the INSERT BUTTON depressed OR; Hold the IN-TIMER SKIP button depressed. (0.5)

b. Use of the IN-TIMER SKIP button is NOT preferred as this method i bypasses the timer [0.53 and eliminates the settle function. [0.5)

This prevents equalization of piston differential pressure except

through the seals and reduceu seal life.[0.53 (1.5) a REFERENCE

! RBGS SD 21,P.7 i

ANSWER 3.08 (3.00)

O. Falso

b. True

c. True

d. False

o. True

f. False

_= . . - . . __. -_

11__INSIBudENI1_8NQ_QQNIBQL3 PAGE 28 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

REFERENCE RBGS SD 22, Pp. 12,13,15,20,22 ANSWER 3.09 (2.00)

o. There are two switches each for: (0.2) Full out, Overtravel full out, Full in, and Overtravel full in. (0.2 each use) (1.0)

b. 1. When a rod NOT SELECTED leaves an even notched position and passes an odd notched position. (0.5)

2. A SELECTED ROD passes an odd position with no motion command.

4 (0.53 (1.0) 1 1

REFERENCE RBGS SD 5 Pp.19,20

't ANSWER 3.10 (1.50)

c. This causes two trips on a single bus, but two bus trips are required to ceuse a scram. (0.5)

b. 1. Going through "Startup" causes trip setpoint changes to lower values (ie; APRM trip unit reference values decrease) (0,5) 2e RPS trip systems are energized (for 10 seconds) when Mode l Switch is placed in shutdown. (0.5)

REFERE.NCE RBGS SD 22, P.5 ANSWER 3.11 (1.50) i

c. Main Stm. Line monitor and Off Gas Sys. monitor.(0.25 ea.) (0.5)

b. High-High or INOP. (0.25 es.) (0.5)

c. Reactor scram, MSIV closure, or Mechanical vacuum pump trip and isolation. (0.167 es.) (0.5)

REFERENCE RBGS SD 53a Pp. 3,4 & 53c, P. 1 i

i

. - - . - _ . - __ - _ . - - , - - , _ , _ ,_-c, , . _ - _ _ , _ __ .- ,,, , ,_, . , , _ , , , . , . _ , _ , _ . , . . _ _ - -

i i

di__EBQGEDVBER_:_NQBd8L&_8tNQBd8L&_EdEBGENGY_8NQ PAGE 29 88QIQLQGIG8L_GQNIBQL ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

r ANSWER +.01 (3.00)

c. 3 or 150 psig

b. 4 or 250 psig

c. 2 or 100 psig j d. 5 or 400 psig i o. 6 or 450 psig or 2 or 100 psig

f. 4 or 250 psig

} REFERENCE GOP-0001, pg 18-20 SOP-0080, pg 5 i

ANSWER 4.02 (2.50) ,

! When air pressure decreases to 100 psig, [0.623) decrease Rx. power to

! 80% using recirc flow . [0.625) When pressure decreases to 65 psig or ;

it is determined that pressure cannot be restored, [0.625) manually I i ocram the reactor. [0.625) (2.5)

I i

REFERENCE

, River Bend AOP - 0008, pg 3 l l

ANSWER 4.03 (2.50)

c. Bypass valves are rated at 10% steem flow. [0.25) Dropping over 10% i j load will cause a pressure increase (0.25) which will result in a reactor screm. [0.5] (1.0)

I b. Increases total liquid weste inventory. (0.5)

c. Close motor operated upstream isolation valves OR; reject flow from RWCU. (Accept either answer) (0,5)

d. Reduce CRD. cooling flow OR; open bottom head drains. ( Accept 1

either answer) (0.5) ,

I l REFERENCE

! GOP-003, Pp.4-6 I ,

} l l

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st__EBQQEQUBE1_=_NQBd8Lt_8BNQBd8Lt_EdEBEENQX_8NQ PAGE 30 B8Q10LQ9108L_QQNIBQL ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 4.04 (2.50)

I

a. 1. Decontamination. 2. Draining & Purging of equipment. )

3. Storing for decay. 4. Reducing reactor power level. I Cany 3, 0.33 es.1 (1.0) l

b. Normal: 100 mrem /wk. Max.: 300 mrem /wk (0.5) !

c. Emergency workers: 25 Rem ( To save equipment) (0.25)

Life Saving: 75 Rem (0.25)

If adequate planning time is available, reduce limits to 12 Rem (0.5)

REFERENCE HP & Practical Applications, Pp.28,41 l

l ANSWER 4.05 (2.50)

e. 1. Turbine load decreases about 5%. (0.5)

2. Reactor pressure will decrease to 849 psi causing MSIV closure and subsequent scram. (0.5)

3. Cooldown and depressurization occurs with no automatic action to stop the transient. (0.5) i b. 1. 7.hift to alternate regulator (and adj ust).

,; 2. Select bypass valve opening jack and cycle.

3. Attempt to cycle valve using test button. (0.33 ea) (1.0)

REFERENCE AOP-0041, Pp.2,3 I

l I

1 I

dz__EBQQEQMBEl_:_NQBd8Lt_6RNQBd6Lt_EMEBQENQ1_6NQ PAGE 31 E8Q19LQfl08L_QQNIBQL ANSWERS -- RIVER BEND 1 _86/02/04-WHITTEMORE, J.

ANSWER 4.06 (2.50)

o. 1. Arm and depress all four manual scram buttons. i I

2. Mode Switch to SHUTDOWN. l

3. Verify control rods fully inserted.

4. Initiate HPCS, LPCS, and RCIC.

5. Trip main turbine. (0.2 each) (1.0)

b. The COF distributes appropiate procedural attachments to selected j operating personnel.

(0.5) c.

Use a touch pyrometer or equivalent on the RHR suction piping. (0.5)

REFERENCE AOP-0031, Pp.5,6,15 I

ANSWER 4.07 (2.00)

c. 1. Re-energize from alternate power.

2. Reset isolation.

3. Open isolation valves. (0.33 ea.) (1.0)

b. 1. Standby Gas Treatment starts.

2. Accident recorders shift to fast speed. (0.5 es.)

Accept that half scram occurs but not required for full credit. (1.0)

REFERENCE AOP-0010, Pp.3,4 4

4 1__EBQQEQUBES_=_NQBd8Lt_8BNQBd8Lt_EMEBGENQ1_8NQ PAGE 32 88Q10LQQ108L_QQNIBQL ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 4.08 (2.50) c.

Depress RAW DATA & ALL RODS pushbuttons. (0.5) The core display for all rods should be blank and a full-in green light will be displayed.CO.5)

(1.0)

b. Pumps shift to slow speed due to' C0.2)

1. FW flow < 30%.

2. RV level < LEVEL 3.

3. MSL to recirc. pump suction dt < 8 deg's. F.

4. Turbine trip. (0.2 each) (1.0)

c. Manual or Reverse Power. (0.5)

ANSWER 4.09 (2.50)

o. Must lower supression pool temperature (0.5) and/or RPV press. (1.0)

b. Installed instrumentation has been changed to resolve problem.

Accept change.

any reasonable answer that reflects knowledge of design (1.0) c.

Calibrated for different conditions OR; elevational differences in instrument piping runs.

(0.5)

REFERENCE E0P-0002, Pp. 7,8,12 AND RBGS SD 3, P.12

st__EBQGEQWBE1_=_NQBueLa_8BNQBd6Lt_EMEBEENGl_8HD PAGE 33 B&Q19LQElG6L_GQNIBQL ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 4.10 (2.50)

o. SECONDARY CONTAINMENT:

Verify Shield Bldg. annulus [0.251, Aux. Bldg. [0.25], and Fuel Bldg. [0.25), Pressure. [0.25]

PRIMARY CONTAINMENT:

Daily verification is not required except during refueling by checking required closure on penetrations.

ACCEPT EITHER ANSWER FOR FULL CREDIT. (1.0)

b. May be purged to plant stack [0.33] or SBGTS. [0.33] or reduced via the H2 mixing system.

(1.0) c.

Ventilation chill water can be aligned to Drywell unit coolers. (0.5)

REFERENCE T.S 3.6.5.1 & SOP-005g, P.8 & SOP-0060, P. 4 l

I

. 1 1

TEST CROSS REFERENCE PAGE 'l l

QUESTION VALUE REFERENCE 01.01 2.00 WJE0000417 01.02 3.00 WJE0000418 01.03 3.00 WJE0000422 01.04 2.50 WJE0000425 WJE0000427 01.05 2.00 )

01.06 1.50 WJE0000429 01.07 2.00 WJE0000430 4

01.08 1.00 WJE0000436 01.09 2.00 WJE0100438 01.10 1.00 WJE0100440 01.11 2.50 WJEC000442 01.12 2.50 'WJE0000444 25.00 02.01 2.50 WJE0000432 02.02 3.00 WJE0000434 i 02.03 2.00 WJE0000445 j 02.04 2.50 WJE0000446

, 02.05 2.50 WJE0000447 02.06 2.50 WJE0000448 l 02.07 2.00 WJE0000449

02.08 2.50 WJE0000451

) 02.09 2.50 WJE0000452 j 02.10 3.00 WJE0000454 1

25.00 03.01 3.00 WJE0000455 03.02 2.50 WJE0000457 03.03 2.50 WJE0000459 03.04 1.50 WJE0000460 03.05 2.50 WJE0000461 03.06 3.00 WJE0000462 03.07 2.00 WJE0000463 03.08 3.00 WJE0000465 03.09 2.00 WJE0000466 03.10 1.50 WJE0000468 03.11 1.50 WJE0000470 25.00 -

1 04.01 3.00 WJE000G474 04.02 2.50 WJE0000475 1 04.03 2.50 WJE0000478 04.04 2.50 WJE0000480 04.05 2.50 WJE0000482 04.06 2.50 WJE0000484 04.07 2.00 WJE0000486 '

, 04.08 2.50 WJE0000487 f

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TEST CROSS REFERENCE PAGE 2 QUESTION VALUE REFERENCE 04.09 2.50 WJE0000490 04.10 ?.50 WJE0000492 25.00 100.00 1

A a

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

U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _BlVEB_RENQ_1____________

REACTOR TYPE: _RWB-EEh_________________

DATE ADMINISTERED: _ShlD24Qi________________

EXAMINER: _WBIIIEdQBEz_Jz__________

APPLICANT: _________________________

IN11BVQIIQNS_IQ_8 EEL 108 nil Uno separate paper for the answers. Write answers on one side only.

d Stcple question sheet on top of the answer sheets. Points for each

question are indicatec in parentheses after the question. The passing j grade requires at least 70% in each category and a final grade of at l

logst 80%. Examination papers will be picked up six (6) hours after tho examination starts.

% OF CATEGORY % OF APPLICANT'S CATEGORY

__V8LVE_ _IQIaL ___SQQBE___ _Y8LUE__ ______________QaIESQBl_____________

_22150__ _221QR ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

_25tDQ__ _25thi ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMEdTATION

_251DQ__ _25thi ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

_25tDQ__ _25thi ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS

_RZziQ__ 1QQzQQ ___________ ________ TOTALS FINAL GRADE _________________%

All work done on this examination $s my own. I have neither givon nor received aid.

-~~~~~~~~~~~~~

PPLiC UT I5 55G5ATURE

St__IBEQBl_QE_NUGLE68_EQWEB_EL8NI_QEEB8110Nt_ELVIQat_8NQ PAGE 2 IBEBdQQ1NedlG1 QUESTION 5.01 (2.50)

e. Explain how the validity of a 1/M plot during fuel loading is affected by:

1. Proximity of source to the detector. (1.0)

2. Direction of fuel load in relation to detector. (0.75)

b. How would the CHANGE in neutron count rate vary between a Keff change occurring prior to the midpoint of fuel load and an equal Keff change occurring near the end of fuel load ? (0.75)

QUESTION 5.02 (3.00)

A new experimental reactor uses a new fuel that has 5 delayed precursor groups. The longest has a half life of 40 sec's. and the average is 8.5 OOC's.

a. For this reactor, what is the stable period (rate of power decrease) after shutdown from the power range ? Explain and show any calculations necessary. (1.25)

b. What specific information is needed to determine a beta fraction for this reactor ?

c. HOW and WHY will the EFFECTIVE beta fraction differ from the ACTUAL beta fraction ?

QUESTION 5.03 (2.50)

Draw a typical graph of K excess Vs. Core life and explain the reasons for major changes in curve slope or direction.

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

It__IBED81_QE_NVQLEaB_EQWEB_EL8NI_QEEB8IIQNt_ELUlQ1t_8ND PAGE 3 18E850D188d101 QUESTION 5.04 (2.50)

True or False

o. Void coefficient is directly proportional to core size.

b. At 15% power, the major contributor to Power Coefficient is Fuel Temperature Coefficient.

c. The larger the core, the lower the relative neutron leakage.

d. The 2 isotopes that make the largest contribution to the Doppler effect are U-235 and P-240.

o. The Overall Temperature Coefficient becomes a meaningless term below the power range. (2.5)

QUESTION 5.05 (2.00)

c. Explain the positive effect that occurs to the Moderator Temperature Coefficient when moderator temperature is increased. (1.0)

b. Explain the effect on Fuel Temperature Coefficient due to changing moderator temperature and void fraction. (1.0)

QUESTION 5.06 (2.50)

During refueling the reactor is subcritical with a stable count rate of 50 CPS and Keff = 0.96.

a. A new assembly is added to the core and after 5 minutes the new count rate is 58 CPS. What is the new Keff ? (1.5)

b. What will core condition (Keff) be after adding TWICE the amount of reactivity that was added in part a (in addition to what was added in part a ) ?

(1.0) [

t

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

Ez__IBEQBl_QE_NVQLEeB_EQWEB_EL&NI_QEEB8IIQNt_ELVIDat_8NQ PAGE 4 IBEBdQQ1NedICS QUESTION 5.07 (1.50)

Answer True or False for each of the statements below. Provide a reason for cny statement that is false.

o. The BTU is defined as tSat amount of work required to raise the temperature of one ga'.lon of water by one degree Farenheit.

b. The value for the enthalpy of liquid water at the triple point is "ZER0" BTU /Lbm- oF.

c. The phase diagram for water which shows temperature and specific entropy is called a T-s diagram. (1.5) l QUESTION 5.08 (2.00)

For each of the following conditions, state whether it will cause an increase, decrease , or have no effect on critical power. Assume all other parameters are constant.

e. Decrease in reactor pressure. (0.5)

b. Increase in inlet subcooling. (0.5)

c. Increase in core flow. (0.5)

d. Location of exial power peak moves up in the core. (0.5)

QUESTION 5.09 (2.50) 1 1

Explain why the reactor vessel level indication errors below occur

o. If variable leg temperature (and pressure) are above calibration conditions, indicated water level will generally be lower than actual level. (1.25)

b. If variable leg temperature (and pressure) increase when water level is zero or very low, an instrument which is not density compensated will indicate a level which is higher than actual ? (1.25)

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

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

Ez__IHEQBX_QE_NUQLE88_EQWEB_EL8NI_QEEB8IIQNt_ELU101t_8NQ PAGE 5 IHEBdQQ1Nad101 QUESTION 5.10 (1.50)

T-s diagrams of real plant cycles show a small amount of subcooling in the host sink (condenser).

o. How will cycle efficiency be affected if subcooling is decreased ?

Why ? (0.75)

b. How can the operator change the amount of subcooling for a constant Megawatt load ? (0.75) i i

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

Ez__EL8HI_1111Edi_DE11GNt_.40NIBQLi_6ND_IN11BudENI6IIQN PAGE 6 QUESTION 6.01 (2.50)

o. What automatic actions will occur to the Normal Sorvice Water System as

! a result of any Standby Service Water auto initiation signal ? (1.0)

b. What will additionally occur if initiation results from loss of RPCCW header pressure ? (1.0)

c. Describe how an emergency water supply can be made available to the RHR system. (0.5) 4 QUESTION 6.02 (3.00)

c. Name 5 systems that must be operating to support the operation of the Condenser Air Removal system. (1.0)

b. What are the inlets (suctions) and discharges of the specific stages of a Steam Jet Air Ejector unit ? (1.0)

c. Place the following Off Gas System components in the correct order of l actual flowpath:

4 l 1. Cooler Condenser.

l 2. Profilter.

J 3. Dessicant Dryer.

4. Off Gas Condenser. ,

t

5. Moisture Separator. '

l 6. H2 Detector. (1.0) 1 QUESTION 6.03 (2.00) l

o. List the Lube Oil pumps associated with a Reactor Feed Pump. (1.0) l

, b. Describe in correct order the Feed and Condensate tiystem long cycle

! cleanup flow path. (1.0) l

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

Ez__EL8NI_1111Ed1_QE119Nt_CQNIBQLt_8ND_INSIBudENI8IIQN PAGE 7 QUESTION 6.04 (2.50)

o. What function is served by the Main Steam Shutoff Valves ? (0.75)

b. List the three separate drain top locations common to each steam line. Further, describe how the system is constructed to provide for adequate and effective drainage during startup and normal power operation. (1.75)

QUESTION 6.05 (3.00)

o. Aside from indication, what are two of the three uses (or reasons for measuring) pressure above the Core Plate ? (1.0)

b. Why is a thermocouple mounted on vessel head vent line ? (0.5)

c. Briefly explain the function of the LOGIC NETWORK portion of the Core Flow Summing Network. (0.75)

d. What general problem (s) may result during maintenance or surveillance on a level indicating system sharing a common D/P sensing line 7(0.75)

QUESTION 6.06 (2.50)

c. What is the purpose of the equalizing valves between the exhaust and cooling water headers in the CRD hydraulic system ? (1.0)

b. Assuming normal system conditions, what determines the speed at which an individual control moves. (1.0)

c. How is excessive control rod speed prevented in the event that the flow or pressure control station fails in a manner to increase drive header pressure. (0.5)

QUESTION 6.07 (2.00)

S Dcscribe two different procedures the operator can use to continuously insert a control rod AND explain why one method is preferred over the other. (2.0)

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

ht__EL8NI_111IEdS_QE11ENt_QQNIBQLt_6NQ_INSIBudENI8I1QN PAGE 8 QUESTION 6.08 (2.00)

c. There are 106 Reed switches within a position indicator probe and

98 are used for digital position indication. What are the remaining i eight (8) switches used for specifically. (1.0) i

b. What are two separate occurrences within the indicating system that will cause a ROD DRIFT ALARM ? Do NOT state malfunctions such as high cooling or drive water. State what actually causes the alarm to annunciate. (1.0) l QUESTION 6.09 (1.50) 4

c. Describe the design feature of the Feedwater Control System that prevants losing feed pumps due to a level transient following i a reactor scram. (0.75)

I b. Explain the effects of and the operator action required for a temporary (1 minute) loss of signal to a feed water control valve while in automatic at full power. (0.75) i

) QUESTION 6.10 (1.50)

I

o. Which Area or Process Radiation Monitors are NOT part of the Digital Radiation Monitoring System ? (0.5) 4

b. Which of the Main Steam Line Radiation Monitor trip circuits will

! cause a channel trip ? (0.5)

c. What automatic action will result if two Main Steam Line .nonitors (channels) trip in a one out of two twice logic ? (0.5)

QUESTION 6.11 (2.50)

c. Describe how system design minimizes packing gland stem leakage from the motor operated gate valves in the Recirculation system.(1.0) 1

b. How would excess stem leakage be detected AND corrected during normal operation at power ? (1.0)

c. Why is Recirculation Pump seal injection flow necessary when procedures will allow operation without continuous flow ? (0.5)

(***** END OF CATEGORY 06 *****)

Zt__EBQQEQUBER_:_NQBd6Lt_eRNQBd6Lt_EMEBQENGl_8NQ PAGE 9 88Q1QLQQ198L_GQNIBQL QUESTION 7.01 (3.00)

Match the following events (a-f) with the approximate pressure at which they should be performed per GOP0001, Plant Startup to Low Power Alarm Point. The pressures may be used more than once or not at all. (3.0)

c. Place steam seals in service 1. 20 psig

b. Startup the Offges System 2. 100 psig

c. Warm up the RCIC piping 3. 150 psig

d. Startup the first reactor feed pump 4. 250 psig

o. Start turbine shell warming 5. 400 poig

f. Startup the SJAE 6. 450 psig

7. 600 psig

8. 850 psig 1

QUESTION 7.02 (2.50) j

e. During a reactor startup/heatup, the maximum hestup rate limit is inadvertently exceeded. Where will you obtain guidance as to the required subsequent action ? C0.5)

b. During startup, how can the absence of condenser vacuum affect the occurrence of Inter-Granular stress corrosion ? WHY ? (1.0)

c. What is the Shift Supervisor's responsibility in the event it is decided to start up with incomplete items on the Master Start Up Check Off List ? (1.0) 1 QUESTION 7.03 (2.50)

During reactor shutdown /cooldown:

e. Describe and explain the possible effect(s) of taking the turbine off line at 15% thermal power. (1.0)

b. Why should the operator avoid supplying steam seals with the auxiliary boiler whenever possible ? (0.5)

c. How can the operator stop increasing level in the pressure vessel with a feed pump operating and the feedwater control valves already fully shut ? (0.5)

d. What can the operator do to limit or minimize bottom head cooldown ? (0.5)

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

i Zi__EBQGEQWBEl_=_NQBd8Lt_8BNQBd66t_EMEBGENGl_8NQ PAGE 10 B&Q10LQGIG8L_GQNIBQL 4

i i

f QUESTION 7.04 (2.50)

! o. What general limitations or limiting plant parameters may restrict i j or inhibit removal of feed water heaters from service ? (0.5) j b. Explain how a reactivity transient may result from fluctuating ,

I j Sth or 6th point heaters. (1.0) i

c. Why must the operator exercise caution when shutting down the l

Heater Drain Pumps ? (1.0) t l

1 QUESTION 7.05 (2.50)

! o. Assume NO operator action and predict plant response for a failed open Turbine Bypass valve with the following conditions: (Assume that bypass valves are fully shut when failure occurs).

1. Turbine generator on line et 15% power. (0.5) l 2. Reactor power at 8% and Mode Switch in RUN. (0.5)

I I 3. Reactor power at 4% and Mode Switch in STARTUP. (0.5)

b. What immediate actions SHOULD be performed by the operator ? (1.0)

]

i j QUESTION 7.06 (2.50)

c. List the steps that operators must perform prior to evacuating l the Control Room due to fire or smoke. (1.0)

I l

b. How do operators obtain guidance for required action upon leaving j the control room ? (0.75)

c. When cooling down from outside the Control Room, how can coolant temperature be determined below 212 deg's. without installed operable indication ? (0.75) 1 l

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

Zi__EBQQEQUBE1_:_NQBd6Lt_eHNQBd8Lt_EMEBGENQ1_68Q PAGE 11 88Q10LQQIQaL_QQNIBQL 1

QUESTION 7.07 (2.50)

O. Aside from rod blocks, what are two basic reasons that the operator must correct misaligned control rods ? (1.2)

b. If motion is inhibited due to rod blocks, what options are available to the operator to clear the block ? C0.8)

c. If misaligned rods are being repositioned, what plant computer programs does the procedure recommend utilizing to indicate out of limit conditions ? (0.5) l QUESTION 7.08 (2.00)

For purposes of Level Restoration (EOP0004), action must be taken dopending on Reactor Pressure Vessel pressure. Define the three specific pressure conditions, list the specific ranges, and note any special oignificance of the setpoints. (2.5)

QUESTION 7.09 (2.50)

o. What are the two basic choices of action if during the performance of E0P-0002 the operator finds himself in the UNACCEPTABLE region

, of the Heat Capacity Temperature Limit graph ? (1.0)

b. Emergency procedures require specific action to be taken at a Drywell temperature of 330 deg's F. Installed indication has a maximum range of 200 deg's. Explain how to resolve this problem.(1.0)

c. Why will high Drywell temperature effect Fuel Zone level indication differently than Wide or Narrow range indication ? (0.5) 1 l

1

)

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

Zi__EBQQEQUBEl_ _NQBdeLi_6tNQBd8Li_EMEBGENQ1_6NQ PAGE 12 88DIQLQEIQ8L_QQNIBQL QUESTION 7.10 (2.50)

c. According to E0P-0001 (RPV Control), what are the four conditions that require RPV flooding ? Setpoints or numbers not required. (1.0)

b. What must be done if the main condenser is required to used as a heat sink and the MSIV' S are closed due to low RPV level ? Indicate the general method used. (1.0)

c. If the SLC system has been initiated, why is the operator directed j to maintain a lower than maximum RPV level ? (0.5)

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(***** END OF CATEGORY 07 *****)

Ri__8DMINI1186IIVE_EBQGEQUBEli_GQNDIIIQNii_8NQ_LIMII8Il0N1 PAGE 13 QUESTION 8.01 (2.00) i With respect to operability surveillance of ECCS pumps and valves, oxplain the following terms.

I

c. Reference value.

b. Alert range.

c. Conditionally acceptable,

d. Test ratio. (2.0)

QUESTION 8.02 (1.00) i List five (5) agencies that must be notified within 15 minutes after o General Emergency is declared at River Bend. (1.0)

{

1 QUESTION 8.03 (3.00)

Fill in the blanks regarding the River Bend Safety Limits: (3.0)

THERMAL POWER shall not exceed ___(a)___ of RATED THERMAL POWER with the reactor vessel steam dome pressure less than ___(b)___ or core flow less than ___(c)___ of rated flow.

The Minimum Critical Power Ratio (MCPR) shall not be less than ___(d)___

1 uith the reactor vessel steam dome pressure greater than or equal to

___(b)___ and core flow greater than or equal to ___(c)___ of rated flow.

The reactor coolant system pressure, as measured in the reactor vossel steam dome, shall not exceed ___Cel___.

The reactor vessel water level shall be above ___(f)___.

QUESTION 8.04 (2.00)

c. What are the Reactor Coolant Leakage Detection Systems addressed in the River Bend Technical Specifications ? (1.0)

b. What is/are the provision (s) that allow (s) extended power operation with only two operable Leakage Detection Systems ? (1.0)

I

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

Ri__8DdIN11188IIVE_EBQQEQUBEft_QQNDIIl0 Nit _6NQ_LidlI6110N1 PAGE 14 QUESTION 8.05 (3.00)

o. Where would the operator find the interpretation on a Technical Specification requirement that had required previous interpretation ?

(0.75)

b. What is the operator's responsibility when the Limiting Condition for Operation (LCO) cannot be met ? (0.75)

c. When is the operator allowed to enter an operating condition where en LCO cannot be met without relying on provisions of an action statement ? (0.75)

d. What is Non-Compliance with a Technical Specification ? (0.75) l QUESTION 8.06 (2.50)

c. When may " Independent Verification" be waived for placement or removal of a Temporary Alteration ? (0.5)

b. What is the time limit for duration of a Temporary Alteration and what should be done if the time limit is reached ? (1.0)

c. When may a temporary electrical jumper be installed without meeting the administrative requirements of the Temporary Alteration procedure (ADM 0031) ? (1.0) l i

l QUESTION 8.07 (2.50) I i

) o. What is the mechanism of " Tagging Adj ustment" that allows f or '

testing of tagged out equipment ? (1.0) l

b. What is the use or purpose of the " Supplemental Clearance" in the tagging system ? (1.0)

c. What is the " SEQUENCE" block used for on a tagging order ? C0.5) I i

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

Az__8DdlN11IB8IIVE_EBQQEQUBEft_QQNQlIIQNSt_8ND_ lid 1I8I1QNS PAGE 15 QUESTION 8.08 (2.50)

o. In addition to utilization of Time, Distance, and Shielding, a concept called Source Reduction can be utilized to lower personnel exposure.

List three examples or methods that can be utilized for reducing 4

SOURCE STRENGTH. (1.0)

b. What are normal and maximum non-emergency weekly exposure limits at River Bend ? (0.5)

c. What are the limits for emergency exposure at River Bend ? (1.0)

QUESTION 8.09 (2.50)

c. Track a completed Procedure Sign Off List after it is filled out by the operator. (0.75)

b. List the sequence of events required to complete a Safety Related System Checklist and track through the system as above. (1.0)

c. What is meant by " Independent Verification" ? (0.75)

I t

QUESTION 8.10 (2.00)

, G. What are the two basic functions provided by the manned Technical Support Center ? (1.5)

b. What is the purpose of the Operations Support Center ? (0.5) l OUESTION 8.11 (2.00) 00 scribe how Shift Relief Check Sheets are used in the shift relief procedure AND explain how the Control Operating Foreman and At The Controls Operator check sheets differ from the others. (2.0)

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

(*************

END OF EXAMINATION

- - - - )

i .

! Ei__IHEQBl_QE_NUGLE8B_EQWEB_EL8HI_QEEB8Il0Ni_ELUIQ1t_6NQ PAGE 16 IHEBBQQ18851GS ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

i J

i ANSWER 5.01 (2.50)

c. 1. If detector is too close to the source, count rate is too high and detector may be insensitive to core changes.[0.5) If detector is too far from source, initial count rate may be low and any change will

]

make ICRR small. [0.53 (1.0) i r l 2. Loading towards the detector means that less neutrons will be absorbed before detection as core becomes larger. Thus detectors i become more sensitive to core as core moves closer. (0.75)

b. A larger change in neutrcn count rate will occur et the end of loading es a larger change results when Keff approaches unity. (0.75)

! REFERENCE ,

Rx Theory Handout, P. 22.4 l

} I j ANSWER 5.02 (3.00)

o. T= t1/2 /In2, = 40/.693, =57.7 sec's. (accept 56.7-58.7)

Maximum power change rate is dependent on longest lived delayed neutron 1 precursor group. (1.25) j b. Specific yield of each precursor group. (0.75)

! c. The effective fraction will be smaller then actual fraction (0.53 as j deleyed neutrons are less likely to cause fast fission (0.5).(Less j likelyhood of leakage tends to increase effective fraction but is

! less important.) Accept

Importance Factor (1.0)

REFERENCE Roactor Theory Handout, Pp. 23e-2,23b-2 l

e I

h f

i I

i

Iz__IBEQBl_QE_NVGLE88_EQWEB_ELANI_QEEB8IIQNt_ELUIDS&_8NQ PAGE 17 IHEBdQQ1N8d1G1 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 5.03 (2.50)

I C 1

I I

IA s---------------------------------------------------------

I

! l I *B Kcff=1 l______________________________________________________* __

I D I

I I

I l_________________________________________________________ (1.0)

CYCLE (GWDT) >>

A.-B. Samarium buildup.

B.-C. Poison burnout faster than fuel depletion.

! C.-D. Fuel depletion. (0.5 es.) (1.5)

REFERENCE G.P. Theory p. 13 ANSWER 5.04 (2.50)

o. Felse l b. True l

c. True

d. Felse

o. False (0.5 es.) (2.5)

REFERENCE G.P. Theory, Pp. 13-27

Et__IBEQBl_QE_NuGLE88_EQWEB_EL8HI_QEEB8119Nt_ELU101t_eNQ PAGE 18 IHEBdQQ1Nadlui ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 5.05 (2.00)

o. The positive effect occurs because moderator is expanded out of the core (0.53 and less neutrons are absorbed in the moderator at higher temperature.[0.53 (1.0)

b. As temperature or voids increase, slowing down time and length become longer. [0.5) Any change in resonance peaks will become more significant i as neutrons spend more time in resonant energy spectrum. [0.53 (1.0)

REFERENCE G.P Reactor Theory P. 17 f

ANSWER 5.06 (2.50)

c. Crl/Cr0 = 1-Keff0/1-Keffi 58/50 = .04/1-K1,

, Keffi = 1.12/1.16 = 0.9655 (1.5)

b. Reactivity change = (K1-1/K1) -

(Ko-1/Ko

= (0.9655-1/0.9655) -

(0.96-1/0.96)

= - 0.006 2 X Reactivity = - 0.012 Kaff(fins 1) = 1/1-dk/k, 1/1-C-0.012) = 1/1.12

=0.988 (1.0)

REFERENCE Rosctor Theory Handout, P. 22.2 ANSWER 5.07 (1.50)

o. False (0.3) Energy not work a pound not ge11on.[0.33 (0.6)

b. False (0.3) BTU /Lbm not BTU /Lbm-oF [0.33 (0.6)

c. True. (0.3) l REFERENCE G.P. Theory, Pp. 6,23,41

Ez__IBEQBl_QE_NUQLE8B_EQWEB_EL8NI_QEEB8Il0Nt_ELUIQ1t_8NQ PAGE 19 IHEBdQQ1NedIQ1 ANSWERS _- RIVER BEND 1 _86/02/04-WHITTEMORE, J.

ANSWER 5.08 (2.0T

o. Increase. b. Increase.

c. Increase d. Decreases (0.5es.] (2.0)

REFERENCE GP HT Theory, Pp 37 - 44 d

ANSWER 5.09 (2.50)

c. The temperature increase causes a density decrease (0.5) so that the pressure felt at the tap will be lower than under calibration conditions (0.5] which will indicate a water level that is lower than actus1 level (0.25] (1.25) l b. The temperature has the same effect on water in the variable leg but at very low levels, the effects of steam density dominate the effects due to water density. [0.5] Steam density increases with increased temperature (0.25] which increases pressure felt at the tap, (0.25]

decreasing differential pressure and increases indicated level. [0.25]

(1.25) ,

i

! REFERENCE GP HT Theory, transient analysis, Pp.8,9 ANSWER 5.10 (1.50) 1

c. Increase (0.25] as less heat is rejected to the condenser and does not

have to be supplied by the source (reactor). [0.5] (0.75)

b. By changing the temperature and/or flow of the Circ. Water. (0.75)

(Accept additional discussion of plant response -- not required for full credit) l REFERENCE GP HT Theory, Pp. 49-51 l

Ez__EL8HI_111IEdi_DE11GNt_QQNIBQLt_8NQ_INSIBWdENI6Il08 PAGE 20 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 6.01 (2.50)

c. Normal service supply and return valves (MOV-57A,9 & g6A,8 shut.(1.0)

b. 1. Normal supply and return valves to CCW HX'S (MOV-501A,8 1 511A,B) shut. [0.5)

2. Standby supply and return valves to CCW system (504A,9 & 510A,B) open. [0.5] (1.0)

3. Normal system supply & return valves to CCW system (MOV-16A,B and

c. A connection is provided from Standby Service Water for flooding the containment or drywell. (0.5)

, REFERENCE RBGS SD, Ch.46, Pp.3,4 & Ch. 47,P.3 ANSWER 6.02 (3.00)

o. Main Steam, TPCCW, Condensate, 120 and 480 VAC Electrical Distri-

bution, Instrument Air, Make up water, TPHVAC, TP Drains, TP l Equipment Drains, Sealing Steam, Offges, Hoggers, Service Water.

[Any 5, 0.2 es.) (1.0)

, b. 1st__Stg.

Inlet: From main condenser. Outlet: To SJAE condenser.

2nd Stg.

Inlett From SJAE condenser. Outlet: To Off Gas system.

[0.25 each) (1.0)

c. Off Gas Condenser, (Moisture Separator), H2 Detector, Cooler Condenser, (Moisture Separator), Profilter, Dessicant Dryer.

(Moisture Separator can be in either or both locations shown.

Subtract 0.2 for each arrangment shift necessary to establish correct order. (1.0) 4 REFERENCE RBGS SD Pp. 40-37, 41-5 4

l

. l ht__EL8NI_111IEdi_DE11GNt-QQNIBQLa_880_IN11BudENI8IIQN PAGE 21 l ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

i j ANSWER 6.03 (2.00)

O. RFP main oil pump, RFP AC motor driven pump, RFP DC motor driven pump, Speed changer main oil pump, Speed changer motor driven pump. [4/5 req'd 0 0.25 ea.] (1.0) 4

b. Condensate pump to RFP bypass valve,[0.15] level control valves,

, [0.15] first pt. htra., [0.15] startup recirc valve, [0.15]

condenser. [0.15] [0.25 for correct order] (1.0)

REFERENCE J RBGS SD 32, Pp.2,6,7, t

l ANSWER 6.04 (2.50)

I ,

c. They are shut in a post accident situation to ensure that the MSIV-PLCS can function effectively. (0.75)

b. Upstream inboard MSIV's, Upstream of outboard MSIV's, and Down- i stream of MSSV's. [0.33 en.] All drains are routed to main con-i denser. [0.25] Drainage is routed through a restricting orifice which can be bypassed during startup. [0.5] (1.75)

. REFERENCE R8GS SD 34, P.10 ANSWER 6.05 (3.00)

o. o Set control rod drive hyd. pressure. l o Set CRDM cooling water pressure.

o Leak detection system. (HPCS pipe break) (any 2, 0.5 es.) (1.0)

b. Avoid exceeding temperature limits on Drywell Equipment Drain Sump during venting. (0.5)

! c. The circuit determines whether loop flows are added or subtracted (depending on pump configuration) to determine total flow. (0.75)

d. Other indicating systems may be adversely affected by the equalizing j valve on the instrument. (0.75)

I I

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

_ _ _ _ _ . _m - _ . __ , - _ _ . . _ _ , _ _ _ _ _ _ _ . . . ,

6t__EL8NI_111IEdi_DE11GNt GQNIBQLt_8NQ_IN11BudENI8IIQN PAGE 22 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

REFERENCE 98GS SD 3- 5,16,17,18 i ANSWER 6.06 (2.50)

c. (After a screm, exhaust header pressure decreases through the directional control to the scram discharge header.) To prevent the rods from operating at excessive d/p's, (0.5) the valves are instelled to repressurize the exhaust header. [0.53 (1.0)

b. Flow is controlled through the directional control valves by pre-determined throttling. (1.0) i c. A relief in the drive water line limit drive water pressure to

, (510 psi) above reactor pressure. (0.5)

REFERENCE j RBGS SO 6, Pp. 11,14,15 l ANSWER 6.07 (2.00) j o. Hold the INSERT BUTTON depressed OR; Hold the IN-TIMER SKIP button depressed. (0.5)

b. Use of the IN-TIMER SKIP button is NOT preferred as this method bypasses the timer (0.53 and eliminates the settle function. [0.5)

This prevents equalization of piston differential pressure except through the seals and reduces seal life.[0.53 (1.5)

J REFERENCE RBGS SO 21,P.7 l

ANSWER 6.08 (2.00) i

c. There are two switches each for: (0.2) Full out, Overtravel full out, Full in, and Overtravel full in. (0.2 each use) (1.0)

I b. 1. When a rod NOT SELECTED leaves an even notched position and passes en odd notched position. [0.5)

2. A SELECTED R00 passes en odd position with no motion command.

[0.51 (1.0)

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

! 6t__EL8HI_111IEdi_QE11ENt_CQNIBQLt_8NQ_INSIBWHENI8IION PAGE 23 l

{ ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

I REFERENCE R86S SD 5 Pp.1g,20

! ANSWER 6.0g (1.50)

c. At 10" RV level a higher then normal setpoint is inserted for 10 seconds (0.25 ) and then setpoint is reduced below normal until i water level is above 10" (0.25) and system is reset by operator.

j [0.25] (0.75)

b. Velve will lock at last controlled position (0.51 and the operator must reset the circuit efter the signal is regained. [0.25] (0.75) i

! REFERENCE

. RBGS SD Pp. 8-10 ANSWER 6.10 (1.50)

o. Main Stm. Lino monitor and off Gas Sys. monitor.[0.25 es.) (0.5) i b. High-High or INOP. [0.25 es.) (0.5) j o. Reactor scree, MSIV closure, or Mechanical vacuum pump trip and j isolation. [0.167 es.] (0,5)

REFERENCE l RBGS SD 53e Pp. 3,4 & 53c, P. 1 l l 4

i ANSWER 6.11 (2.50)

c. The velves have dual stem packing glands .[0.5) There is a leek off path between glands directing leakage back to the Dry Well Equipment Drain Sump. [0.51 (1.0)

! b. The leek off lines contain temperature and flow detectors. [0.51

The line can be isolated by a solenoid valve, placing the second

gland in service.[0.53 (1.0) l c. The "Cloen" water supply prolongs seal life. (0.5)

(

)I

/ /

L.__EL8dI_111IEdi_QE11GNt_GQNIBQL4_8NQ_IN118UMENI8IIQN PAGE 24 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

- I REFERENCE RBGS SD 7, Pp. 4,4,14

Zt__EBQCEDUBES_=_NQBd8Lt_8BNQBd8Lt_EMEBRENGl_8NQ PAGE 25 B8DIQLQEIG8L_GQNIBQL ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 7.01 (3.00)

o. 3 or 150 psig

b. 4 or 250 psig

o. 2 or 100 psig

d. 5 or 400 peig

o. 6 or 450 psig or 2 or 100 psig

f. 4 or 250 psig REFERENCE 60P-0001, pg 18-20 SOP 0080, pg 5 ANSWER 7.02 (2.50)

c. Technical Specificatior.s (0.5) b.

The absence of vacuum means that less feedwater de-aeration will occur. [0.5) Increased 02 in feedwater increases the probability that corrosion will occur. [0.5) (1.0)

c. Submit or recommend operating limitations based on incomplete portions of check-off list.

(1.0)

REFERENCE 80P-0001, Pp.2,3 ANSWER 7.03 (2.50)

o. Bypass valves are rated at 10% steam flow. [0.25) Dropping over 10%

load will cause a pressure increase (0.25) which will result in a reactor screm. [0.51 (1.0)

b. Increases total liquid weste inventory. (0.5)

c. Close motor operated upstream isolation valves OR; reject flow from RWCU. (accept either answer) (0.5)

d. Reduce CRD cooling flow OR; open bottom head drain. (Accept either answer) (0.5)

Zi__EBQQEQUBE1_=_NQBd8Lt_8BNQBd8L&_EMEBGENQX_8NQ PAGE 26 88DIQLQG108L_QQNIBQL ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

REFERENCE GOP-003, Pp.4-6 ANSWER 7.04 (2.50)

c. MCPR or Turbine limits (0.5)

b. Extreme high levels in the heaters will auto bypass the condensate stream around the heaters (0.5) causing feed water temperature to decrease and change reactor power. (0.5) (1.0)

c. Flow through the domineralizers must increase as pumped forward flow is reduced. (0.5) Subsequent pressure oscillations may cause feed pump trip. (0.5) (1.0)

REFERENCE GOP-0002, Pp. 1,2

?

1

! ANSWER 7.05 (2.50)

n. 1. Turbine load decreases about 5%. (0.5)

2. Reactor pressure will decrease to 849 psi causing MSIV closure and subsequent scram.

(0.5)

3. Cooldown and depressurization occurs with no automatic action to stop the transient. (0,5)

b. 1. Shift to alternate regulator (and adj ust).

2. Select bypass valve opening jack and cycle.

3. Attempt to cycle valve using test button. (0.33 ea) (1.0)

REFERENCE AOP0041, Pp.2,3

Zi__EBQGEQUBE1_=_NQBd8Lt_8BNQBd8Lt_EdEBGENGl_8NQ PAGE 27 88Q10LQG198L_CQNIBQL ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 7.06 (2.50)

o. 1. Arm and depress all four manual scram buttons.

2. Mode Switch to SHUTDOWN.

3. Verify control rods fully inserted.

4. Initiate HPCS, LPCS, and RCIC.

5. Trip main turbine. (0.2 each) (1.0)

b. The COF distributes appropiate procedural attachments to selected operating personnel. (0.5)

c. Use a touch pyrometer or equivalent on the RHR suction piping. (0.5)

REFERENCE AOP-0031, Pp.5,6,15 ANSWER 7.07 (2.50)

a. 1. Excessive rod worth.

2. Thermal hydraulic problems. (0.6 ea.) (1.2)

b. 1. Scram.

2. Change power with recirc flow. (0.4 ea.) (0.8)

c. OD1 AND OD-7 REFERENCE AOP-0026, Pp.2,5 l

ANSWER 7.08 (2.00)

HIGH PRESSURE........>485 PSIG ...... Shutoff head of LPCI (0.75) l l

INTERMEDIATE PRESSURE.... 60- 485 PSIG [0.5)

LOW PRESSURE.........<60 PSIG........RCIC LP ISOLATION (0.75)

REFERENCE E0P-0004, P.4

Zt__EBQCEDUBES_:_NQBd8Lt_8BNQBd8Lt_EdEBQENGl_8ND PAGE 28 B8210LQQ1G8L_GQUIBQL ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 7.09 (2.50)

c. Must lower supression pool temperature (0.5) and/or RPV press. (1.0)

b. Installed instrumentation has been changed to resolve problem.

Accept any reasonable answer that reflects knowledge 6f design change. (1.0)

c. Calibrated for different conditions OR; elevational differences in instrument piping runs. (0.5)

REFERENCE E0P-0002, Pp. 7,8,12 AND RBGS SD 3, P.12 ANSWER 7.10 (2.50)

n. 1. DW or containment temperature exceeds RPV saturation temperature.

2. Indeterminate RPV level.

3. Excess D/P between Drywell and containment OR between containment and annulus.

4. Excessive Drywell temperature. (0.25 each) (1.0)

b. A jumper kit obtained from the control room emergency locker (0.5) is used to bypass the interlock relay. (0.53 (1.0)

c. To prevent excessive dilution and reactivity addition. (0.5)

REFERENCE E0P-0001, Pp. 14,24,28 i

l i

1

. 1 l

i At__8DMIN11188I1YE_EBQQEQUBEft_QQNQ1IIQNit_8ND_LIMII6110H1 PAGE 29 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 8.01 (2.00)

e. Value previously recorded when component was known to be operating properly.

b. A value that is outside of acceptance value but within minimum or maximum value,

c. A component that has one or more values in the ALERT range and all other values in the acceptable range.

d. Test value divided by reference value. [0.5 ea.) (2.0)

REFERENCE STP205-301, P.4 ANSWER 8.02 (1.00)

- Louisiana Nuclear Energy Division Louisiana Office of Emergency Preparedness East Feliciana Parish West Feliciana Parish Pointe Coupee Parish East Baton Rouge Parish West Baton Rouge Parish Mississippi Highway Safety Patrol (5 required at 0.2 each)

REFERENCE EIP 005, General Emergency, Rev 0, pg 5 ANSWER 8.03 (3.00) i

s. 25% ~ !

b. 785 psig i

c. 10%

d. 1.06

o. 1325 psig

f. the top of the active irradiated fuel (6 at 0.5 each)

REFERENCE River Bend Technical Specifications, Safety Limits

1 ft__aQUIN111BaIIVE_EBQQEQUBElt_QQNDIIIQNSt_8ND_L15118IIONS PAGE 30 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 8.04 (2.00)

e. 1. Drywell particulate monitoring system.

2. Pedestal floor sump drain flow monitoring system.

3. Air cooler condensate flow monitoring system.

4. Drywell gaseous monitoring system. (0.25 ea.) (1.0)

b. Taking and analyzing daily grab samples from the drywell allows operation (for 30 days) with two operable systems. (Concept of sampling required for full credit.) (1.0)

REFERENCE T.S. 3.4.3.1 ANSWER 8.05 (3.00)

c. There are interpretation letters included in the Tech. Spec's. (0.75)

b. To comply with the ACTION STATEMENT. (0.75)

c. When it is required to change modes to meet an action statement, or TS 3.04 is specified as N/A. (0.75)

d. LCO's not met and action statements not complied with when re-quired or within the specified time interval. (0.75)

REFERENCE T.S. Sect. 3 and Interpretation letters. ,

l ANSWER 8.06 (2.50)

a. To prevent significant radiation exposure. (0.5)

b. 90 days, (0.25) then submit a DCR. (0.75) (1.0)

c. When installation and removal are steps in an approved procedure. (1.0)

REFERENCE ADM-0031, Pp.2,4,7 t

I

At__8DMIN11IB811YE_EBQQEDUBEft_QQNDIIIQNSt_880_LIMII811QN1 PAGE 31 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 8.07 (2.50)

o. Tags can be removed for testing by executing a Partial Clearance l

Release. (1.0)

b. Allows person performing a separate task to use an existing clearance tagout. (1.0) l

c. To indicate a preferred sequence of tag removal. (0.5) l REFERENCE ADM-0027, Pp. 10,16,21 ANSWER 8.08 (2.50)

e. 1. Decontamination. 2. Draining & Purging of equipment.

3. Storing for decay. 4. Reducing reactor power level.

Cany 3, 0.33 ea.)

(1.0) l

b. Normal: 100 mrem /wk. {

Max.: 300 mrem /wk (0.5)

c. Emergency workers: 25 Rem (To save equipment) (0.25)

Life Saving: 75 Rem (0.25)

If adequate planning time is available, reduce limits to 12 Rem (0.5)

REFERENCE HP 8 Practical Applications, Pp.28,41

l At__8DdlN11188IIVE_EBQQEQUBEft_QQNQ1110 Nit _8NQ_LIMII8Il0N1 PAGE 32 ANSWERS -- RIVER BEND 1 -86/02/04-WHITTEMORE, J.

ANSWER 8.09 (2.50)

e. Reviewed by SS [0.25), placed in control room status file [0.25),

and forwarded to Ops. Sup. when replaced by next completed

procedure. [0.25] (0.75)

b. 1. First operator lines up.

2. Second operator verifies.

3. SS reviews both completed lists.

4. Placed in CR status file

5. Forwarded to OS when replaced by next checklist. [0.2 ea.] (1.0)

c. A second person does an independent check without visual or audible contact with the first checker. (0.75)

REFERENCE ADM-0022,Pp.26,27 ANSWER 8.10 (2.00)

a. 1. Provide engineering,[0.253 technical,[0.25] and management support [0.25] to mitigate an accident. [0.25] (1.0)

2. To coordinate onsite emergency response. (0.5)

b. To serve as a staging area f or site personnel during emergency response and recovery operations. (0.5)

REFERENCE EMER. PLAN, Pp. 13.3--61-62 ANSWER 8.11 (2.00)

C.All relief sheets have two parts.) Part I is filled out by off-going personnel [0.5] and reviewed by on-coming personnel prior to assuming the shift. [0.5) Part II is completed as early in the shift so possible by on duty personnel. [0.5] The COF and ATC sheets have a Part III that is to be completed by the end of shift. [0.53 (2.0)

REFERENCE OSP0002, P. 4

e TEST CROSS REFERENCE PAGE 1 QUESTION VALUE REFERENCE 05.01 2.50 WJE0000419 05.02 3.00 WJE0000421 05.03 2.50 WJE0000423 05.04 2.50 WJE0000424 05.05 2.00 WJE0000426 05.06 2.50 WJE0000428 05.07 1.50 WJE0000435 05.08 2.00 WJE0000437 05.09 2.50 WJE0000441 05.10 1.50 WJE0000443 22.50 06.01 2.50 WJE0000431 06.02 3.00 WJE0000433 06.03 2.00 WJE0000450 06.04 2.50 WJE0000453 06.05 3.00 WJE0000456 06.06 2.50 WJE0000458 06.07 2.00 WJE0000464 06.08 2.00 WJE0000467 06.09 1.50 WJE0000469 06.10 1.50 WJE0000471 06.11 2.50 WJE0000472 25.00 07.01 3.00 WJE0000473 07.02 2.50 WJE0000476 07.03 2.50 WJE0000477 ;

07.04 2.50 WJE0000479 l 07.05 2.50 WJE0000481 1 WJE0000483 07.06 2.50 07.07 2.50 WJE0000485 07.08 2.00 WJE0000488 07.09 2.50 WJE0000489 07.10 2.50 WJE0000491 siEs 1 08.01 2.00 WJE0000493 08.02 1.00 WJE0000494 08.03 3.00 WJE0000495 l 08.04 2.00 WJE0000496 08.05 3.00 WJE0000497 08.06 2.50 WJE0000498 08.07 2.50 WJE0000499 08.08 2.50 WJE0000500 08.09 2.50 WJE0000501 08.10 2.00 WJE0000502 1 1 j

1 .- - . --

.1 e

TEST CROSS REFERENCE PAGE 2 QUESTION VALUE REFERENCE 08.11 2.00 WJE0000503 25.00 97.50 f

a l

l l

1 t

..-o, , .______,.,_7.--. , . , , _ , , _ , , , _ , , . , . , , _ , . _ . _ _ . _ . . . , , . . ,. _ , , ~ , , _ . , _ , , , _ , - . _ , . r . . . _ . . , , . . ,,7_ .

ML20203B195

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