ML20202J788

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Exam Rept 50-382/OL-86-02 on 860317.Exam Results:One Reactor Operator Failed & Six Senior Reactor Operators Passed Exam
ML20202J788
Person / Time
Site: Waterford Entergy icon.png
Issue date: 04/02/1986
From: Cooley R, Whittemore J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20202J785 List:
References
50-382-OL-86-02, 50-382-OL-86-2, NUDOCS 8604160187
Download: ML20202J788 (31)
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OPERATOR LICENSE EXAMINATION REPORT No. 50-382/0L 86-02 i

l Licensee: Louisiana Power & Light Company 142 Delaronde Street .

New Orleans, Louisiana 70174 l l

Docket
50-382 l l Operator License Examinations at Waterford 3 Steam Electric Station (W3SES) l Chief Examiner: & 9!J N phn E. Whittemore Date Approved By: .k- M - kMh b R. A. Cooley g Date~

Summary Singlecategoryoperatorlicenseexaminationswereadministeredtoone(1)

Reactor Operator and six (6) Senior Reactor Operator candidates on March 17, 1986. The Reactor Operator failed the examination while all six Senior

. Reactor Operator candidates passed the examination and have been issued the j appropriate license or certificate.

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4 8604160187 ADOCK 0500 860411~-2 PDR V

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l 4 2 Details

1. Examination Results ,

l 1 Single category written examinations were administered to one Reactor Operator and six Senior Reactor Operator candidates. The six Senior-

, Reactor Operator candidates passed these examinations and the one Reactor -

Operator failed. No operating examinations were administered during this site visit.

2. Examiners J. E. Whittemore (Chief Examiner, did not travel to site)

D. N. Graves

3. Examination Report i Performance results for individual candidates are not included in this report. This examination report is composed of the sections listed below.

A. Examination Review Comment Resolution In general, editorial coments or changes made during the examination or during subsequent grading reviews are not addressed by this report section. This section reflects coments and recomended changes to the examination answer key, made by the licensee. Examination key modifications resulting from these coments and recomendations are included in the master examination and answer keys, which are provided elsewhere in this report. Coments and resolutions are listed by section question number.

3.02.a Also accept "RCS Mass Flow Rate" as COLSS is used to monitor the 12-hour surveillance requirement per NE-4-004.

RESCLUTION: Accept. Key modified i 3.02.b Recomend accepting ." Pressurizer Pressure" and "CEAC Penalty 6.04.b Factors," for items 5 and 7 of answer.  :

1 RESOLUTION: Accept. Key modified.

t 3.03.a Recomend accepting a value of 28-30 GPM as this range is widely used at W3SES.

l RESOLUTION: Accept. Key modified.

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3.03.b Second part of answer should not be required for full credit as this is the reason, not the purpose.

RESOLUTION: Partially accept. Key modified but full credit answer must include concept of system transient behavior, ,

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3.04.c Accept "Startup Feed Reg. Valve" for Bypass valve. Also 1 6.06.c change 5% open to 5% flow demand. Should also accept 3900 RPM or minimum speed.for. feed pump speed program.

a RESOLUTION: Accept. Key modified.'

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3.05.a Also accept " Backup UEL-----Reed Switch" l

. 6.07.a i RESOLUTION: Will accept but not require for full credit. Key modified.

3.05.b Accept: 2/4 CPC generated pretrips in place of individual 6.07.b parameter trips and logic.

RESOLUTION: Accept. Key modified.

3.06.b Delete " Manual" and " Individual Manual" control mode descriptions and accept description of " Modulation" and j " Quick Opening" modes of operation fir same credit.

RESOLUTION: Not accepted. Question specifically -asks for modes of bypass valve CONTROL, not OPERATION.

i 3.08 Delete second sentence. Candidates should not be penalized 6.08 for not stating the trips are not corrected for shadowing.

RESOLUTION: Accept. Key modified to allow credit for stating trips that are corrected. ,

3.09.b Change key to indicate that shearing of RCP shaft is a separate event that is protected against by the trip.

RESOLUTION: Accept. Key modified.

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1 3.10.a Another acceptable should be, "Any calibrate switch out of

" operate."

RESOLUTION: Accept. . Key modified.

3.10.b Another acceptable answer should be, " Warn the operator of increasing count rate when shutdown.

1 i RESOLUTION: Accept. Key modified to accept either answer for full credit.

6.05.a Accept " Cold leg injection valves" to replace header valves.

RESOLUTION: Accept. Key modified.

6.05.b The word " manipulated" should be changed to " closed" as the bypass valve cannot be throttled.

RESOLUTION: Accept. Key modified.

6.09.b Answer for SIAS should reflect modification that allows operator to select one pump that will not start and that letdown is isolated.

RESOLUTION: Accept. ' Key modified.

6.10.b Accept words to the effect that lower guide tube is tapered instead of requiring the phrase " Dashpot Effect."

RESOLUTION: Accept. Key modified.

8.01.a Delete first sentence in answer as it is not solicited by

the question.

RESOLUTION: Accept. Key modified.

8.05 Add to list of possible answers
Surveillance or maintenance in progress.

RESOLUTION: . Accept. Key modified.

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8.06.a Accept: Flow Wier Monitoring System for no. 2.

RESOLUTION: Accept. Key modified.

8.06.b Delete first statement as it is part of the Action Statement which is specifically not required.

RESOLUTION: Accept. Key modified to require number of systems and specific combinations required.

4 8.09.a Candidates may also mention dose projections based on FSAR accident data.

RESOLUTION: Accept. Not required for full credit.

8.09.b Accept 914 meters for boundary.

RESOLUTION: Accept. Key modified.

B. Exit Meeting Summary An exit meeting with the licensee was not held following administration of the written examinations.

C. EXAMINATION MASTER COPIES The Senior Reactor Operator and Reactor Operator 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: _W6IEBEQBQ_2_____________

REACTOR TYPE: _EWB-QE_______________.___

DATE ADMINISTERED:_QhlD2LlZ________________

EXAMINER: _WulIIEdQBEz_Jz__________

APPLICANT: _________________________

IU118UGIl0N1_IQ_8EELIQaNIl Uce separate paper for the answers. Write answe'rs on one side only.  !

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

% OF CATEGORY  % OF APPLICANT'S CATEGORY

__Y8LUE_ _IQIaL ___1GQBE___ _Y6LUE__ ______________Q81EQQBl_____________

_25tQQ__ 1DQzQQ ___________ ________ 3. INSTRUMENTS AND CONTROLS D

2EzQQ__ 1DQzQQ

___________ ________ TOTALS l FINAL GRADE _________________%

All work done on this examination is my own. I have neither given nor received aid.

APPLICANT'S SIGNATURE l

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

2z__INSIBMMENI1_8NQ_GQNIBQL1 PAGE 2 QUESTION 3.01 (2.00)

e. How will the operator be made aware that an individual CEA timer has failed, and what is the impact of timer failure on normal CEA operation ? (1.0)
b. How will the operator determine the specific CEA(S) affected ?

Where is the indication obtained ? (1.0)

QUESTION 3.02 (2.50)

a. What are the five (5) Limiting Conditions for Operation monitored by COLSS ? (1.0)
b. List six (6) of the parameters which are inputs to the CPC's. (1.5)

QUESTION 3.03 (3.00)

a. What is the range of control of the Letdown Throttle Valve in automatic control and why ? (1.2) l l
b. What is the purpose of the lead / leg unit between the Pressurizer l

Level Controller and Letdown Throttle Valve Controller ? (1.0) c.' Explain how pressurizer pressure can affect pressurizer level indication ? (0.8)

QUESTION 3.04 (2.50)

e. Explain " Compensated Level" signal as it pertains to the Feed Water Control System (FWCS). (1.0) I
b. What are the 3 analog programs generated by the FWCS ? (0.75) l
c. What are the limitations placed on pump speed and valve position during Reactor Trip Override ? (0.75)

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

2A__kN11BMdENlg_8NQ_CQNIBQL1 PAGE 3 QUESTION 3.05 (2.50)

o. List all CEDMCS interlocks that use CEA position as an input, and state the source of the input. (1.6)
b. Describe any other interlock (s) effective in Manual Sequential.

State any applicable circuit logic. (0.9)

QUESTION 3.06 (2.50)

e. Where may Steam Bypass Control " Emergency Off" be initiated from, and what are the effects of initiating " Emergency Off" ? (1.0)
b. Describe the different modes of Bypass Valve control. Address the

" Permissive Switch" position in your description. (1.5)  !

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QUESTION 3.07 (2.50)

a. Where can ALL outputs from In-Core fixed and movable detectors be  ;

routed to ? Be specific for each type of detector and signal. (1.5)

b. What are two specific uses of the movable detector outputs ? (1.0)

QUESTION 3.08 (2.50)

What Reactor Protection System trips can be affected by Temperature and CEA shadowing ? Further, explain all means or methods used to minimize or correct the effects of shadowing on effected trips. (2.5) l l

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

hz__INSIBubENII_AND_QQNIBQL1 PAGE 4 QUESTION 3.09 (2.50)

a. Which of the following input parameters are common to the HI LPD and LO DNBR trips ?
1. Radial peaking factors from CEA position.
2. RCS pressure.
3. Coolant flow rate from RCP speed.
4. Delta T power from coolant temperature, pressure, and flow.
5. Penalty factors from CEAC's for CEA deviation within a subgroup.
6. Core inlet temperature. (1.0)
b. Why is it necessary to have a Steam Generator Low Flow reactor trip AND for what specific events is protection afforded ? (1.5)

QUESTION 3.10 (2.50)

c. What are 3 of the general conditions that will cause an INOPERABLE annunciator for an Ex-Core Safety Channel ? (1.2)
b. What is the purpose of the " STARTUP CHANNEL _ NEUTRON FLUX HI" annunciator ? (0.7)
c. What are 2 valid reasons for a "STARTUP CHANNEL _ 0FF NORMAL" alarm ? (0.6)

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

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

2x__IN11BudENI1_8HQ_QQNIBQL1 PAGE 5 ANSWERS -- WATERFORD 3 -86/03/17-WHI1TEMORE, J.

ANSWER 3.01 (2.00)

e. A timer failure alarm occurs when the prinary CEA timing circuit fails. (0.5) There is no impact on normal operation as there is a backup timing circuit available. (0.5) (1.0)
b. There are individual red alarm status lights that indicate failure of specific CEA'S (0.5) on the CEA Disable and Timer Failure Lamp Panel. (0.5) (Accept Local CEDMCS Panels on the + 21 ft. elevation in the "B" switchgear room.) (1.0)

REFERENCE j W3SES SD CEDMCS, Pp. 10,11 ANSWER 3.02 (2.50) l

e. 1. Peak linear heat rate I
2. Margin to DNB/DNBR
3. Total core power
4. Azimuthal tilt l S. RCS mass flow rate l
6. Axial Shape Index (Any 5, 0.2 ea.) (1.0) l

-b. 1. Neutron power / flux

2. T cold
3. T hot
4. RCP speed
5. RCS (or PZR) pressure
6. CEA positions j 7. CEA Cor CEAC) penalty factors (any 6, 0.25 ea.) (1.5)

REFERENCE W3SES SD CPC, TAB.1.3 AND COLSS, P.1

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'___INSIBUMENI1_8ND_QQNIBQL1 PAGE 6 ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 3.03 (3.00)

a. (28-30) - 128 GPM. (0.4] Minimum limit for adequate heat transfer across regenerative heat exchanger. (0.4] Maximum limit based on max. charging pump capacity less RCP bleed off flow. (0.4] (1.2) b.

To slow down the speed of the Letdown Throttle Valve stroke (0.53 and minimize system transients. (0.5] (1.0)

c. Changing density in the volume of liquid or steam can affect indicated pressurizer level.

(0.8)

REFERENCE W3SES SD PLCS, Pp.7,9,11 ANSWER 3.04 (2.50)

c. The level signal is dynamically compensated (0.2] for actual level rate of change (0.4] as well as the rate of change of the flow error signal (0.4].

(1.0)

b. Bypass (SU Feed Reg) valve demand Main valve demand Feed pump speed setpoint (0.25 es.] (0.75) c.' Pump speed---------------------5%

(Min. Speed ~ 3900 RPM)

Bypass (SU Feed Reg) valve-----5% Demand (25-30% open)

Main valve---------------------0% (closed) (0.25 es.] (0.75)

REFERENCE W3SES SD FWCS, Pp.2,4,7

bz__kN11BudENISaND_GQNIBQL1 PAGE 7

. ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 3.05 (2.50)

e. UEL-------------Reed switch UCS-----------------Computer LEL-------------Reed switch LCS-----------------Computer UGS-------------Computer Upper Seq. Perm.----Computer LGS-------------Computer Lower Seq. Perm.----Computer Will accept Backup UEL---Reed Switches. Not required for full credit. [0.2 ea.] (1.0)
b. CWP on: 2/4 H'i LPD 2/4 LO DNBR 2/4 Hi Pzr. Pressure [0.3 ea.]

Will acctpt 2/4 CPC generated pretrips in place of LPD and DNBR trips (0.9)

REFERENCE W3SES SD CEDMCS, Pp. 27-29 ANSWER 3.06 (2.50) e.

Initiate from: Turbine Generator control (CP-1) [0.25]

SBCS Cabinet (CP-5) [Q.253 Effects: The signal blocks Perm. and Q.0. solenoids for each

~ valve [0.25] and blocks opening or causes quick closure. [0.25] (1.0) b.

Automatic control: All valves controlled in automatic from Master Controller,with Permissive Switch in Auto.

Manual Control: All valves controlled in manual from master controller with permissive sw. in auto.

Ind. Man. Control: All valves controlled in manual from individual controller with permissive sw. in manual.

[0.5 each) (1.5)

REFERENCE W3SES SD SBCS, Pp.21,29,34

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. ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 3.07 (2.50)

n. FIXED MOVABLE Neutron Flux: COLSS Neutron Flux: Computer Computer Core Exit Temp: Computer QSPDS [0.3 for es. correct dest.) (1.5)
b. 1. Flux mapping
2. Detector burnup compensation
3. Ex-Core calibration [any 2, 0.5 each) (1.0)

REFERENCE W3SES SD IN-CORE, Pp. 14,23 ANSWER 3.08 (2.50)

Trips affected include: Lin. Hi Power, Log. Hi Power, DNBR, and LPD.

[0.125 ea.) DNBR and LPT Trips are corrected for CEA and/or Temperature Shadowing. [0.5) An attempt is made to minimize effects by running ARO

[0.25) and periodically updating Ex-Core output during power operation.

- [0.5) Also Strict adherence to PDIL minimizes effects of CEA shadowing.

[0.25) The CPC'S make corrections to DNBR & LPD trips based on axial profile shape and cold leg temperature (0.5% power / deg. F.) [0.5) (2.5)

REFERENCE W3SES SD EX-CORE, Pp.13,14 ANSWER 3.09 (2.50) I

a. 1, 4, 5 [0.33 ea.) (1.0) b.

The CPC's may not see loss of RCP's in MSLB envircnment [0.5) with loss of power supply bus. [0.5) Also provides protection for RCP sheared shaft event. [0.5 (1.5)

REFERENCE W3SES SD RPS, Pp. 28,29,36

iz__iN11BMBENI1_6NQ_QQNIBQL1 PAGE 9 ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 3.10 (2.50)

c. 1. Loss of high voltage
2. Loss of drawer voltage
3. Removal of any ckt. card
4. Test / Cal. switches out of operate [any 3, 0.4 ea.) (1.2)
b. To warn the operator that detector high voltage has not been turned off during SU, OR; count rate is increasing when shutdown. (0.7)
c. 1. Channel relay turned off but voltage still applied.
2. Relay on but voltage off. (0.3 ea) (0.6)

REFERENCE W3SES SD EX-CORE, Pp. 86-88 G

b

U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _W61EBEQBQ_1_____________

REACTOR TYPE: _EWB-GE__________________

DATE ADMINISTERED: _RhlQ141Z________________

EXAMINER:

_WB111EbQBEz_Jz__________

APPLICANT: _________________________

IN11BUQIl0H1_IQ_6EELIQ8HIl Une separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets.

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

% OF CATEGORY  % OF APPLICANT'S CATEGORY

__Y8LUE_ _IQI6L ___1GQBE___ _Y8LUE__ ______________QaIEQQBl_____________

_25zQQ__ 1DQzQQ ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

_lizQQ__ 10010D ___________ ________ TOTALS FINAL GRADE _________________%

All work done on this examination is my own. I have neither givon nor received sic.

EPPL5C Ui75~55GU TUR5"~~~~~~~~~~~~~

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Ei__EL8HI_111IEdi_DE11GNi_QQNIBQLi_8HQ_IN1IBUMENI8IIQN PAGE 2 QUESTION 6.01 (2.00)

e. How will the operator be made aware that en individual CEA timer
has failed, and what is the impact of timer failure on normal CEA operation ? (1.0) 4
b. How will the operator determine the specific CEACS) affected ?

Where is the indication obtained ? (1.0) 1 l

QUESTION 6.02 (3.00)

a. How will individual 6.9 KV motor feeder breakers react to loss of power to a 6.9 KV bus ? WHY ? (0.5)
b. What specific protection is afforded to Reactor Coolant Pump breakers, but not to other 6.9 KV breakers ? C0.5)
c. What are 4 problems or conditions that may exist when the Control Room indication for 6.9 KV bus transformer feeder has both lights extinguished ? (1.0)
d. What conditions must be met to close a tie feeder breaker for the 3 ABS bus  ? (0.5)
e. What alternative conditions must be met to close the auxiliary transformer feeder breaker to bus 2A or 2B ? (0.5)

QUESTION 6.03 (2.50) .

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a. Explain how the Containment Spray System functions to limit offsite i dose or post accident radiation. (1.5)
b. Give two (2) methods of removing or limiting post-accident hydrogen concentration inside the containment. (1.0)

QUESTION 6.04 (2.50)

a. What are the five (5) Limiting Conditions for Operation ~ monitored by COLSS ? (1.0)
b. List six (6) of the parameters which are inputs to the CPC's. (1.5) l

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

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l hz__EL8NI_111IEd1_QE11ENm_QQNIBQLt_8NQ_IN11BudENI&I1QN PAGE 3 l QUESTION 6.05 (2.50)

s. What are (2) reasons for controlling HPSI cold leg flow rate AND how how is this control accomplished ? (1.5)
b. Explai.n the purpose of the HPST neader Flow Orifices and Bypass Valves, and detail how this purpose is accomplished. (1.0)

QUESTION 6.06 (2.50)

o. Explain " Compensated Level" signal as it pertains to the Feed Water Control System (FWCS). (1.0)
b. What are the 3 analog programs generated by the FWCS ? (0.75)
c. What are the limitations placed on pump speed and valve position during Reactor Teip Override ? (0.75)

QUESTION 6.07 (2.50)

a. List all CEDMCS interlocks that use CEA position as an input, and state the source of the input. (1.6)
b. Describe any other interlock (s) effective in Manual Sequential.

- State any applicable circuit logic. (0.9)

QUESTION 6.08 (2.50)

What Reactor Protection System trips can be affected by Temperature and CEA shadowing ? Further, explain all means or methods used to minimize or correct the effects of shadowing on effected trips. (2.5)

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

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6t__kL8HI_111IEdi_DE11GNt_QQNIBQLt_8NQ_INSIBudENIAIIQN PAGE 4 1

QUESTION 6.09 (2.50)

e. Is the ability to borate for cold shutdown, prior to cooldown, 1 compromised by loss of letdown capability ? Explain your answer. (1.0)
b. Describe the initial effect on the CVCS due to:
1. SIAS
2. CIAS (1.5)

QUESTION 6.10 (2.50)

e. What is the dual purpose of the CEA shrouds ? (0.8)
b. Describe the different methods of limiting or minimizing bottoming impact of full length CEA's after a reactor trip. (0.8)
c. Describe the specific material used in the part length CEA's from top to bottom. Specific numbers or elevations not required. (0.9) 1 l

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

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

ht__EL6NI_11LIEMS_P.E11GNt_QQNIBQLt_8NQ_IN118UMENI8IIQN PAGE 5 ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 6.01 (2.00)

c. A timer failure alarm occurs when the primary CEA timing circuit fails. [0.53 There is no impact on normal operation as there is a backup timing circuit available. [ 0.-5 3 (1.0)
b. There are individual red alarm status lights that indicate failure of specific CEA'S [0.5] on the CEA Disable and Timer Failure Lamp Panel. [0.53 (Accept Local CEDMCS Panels on the + 21 ft. elevation in the "B" switchgear room.) (1.0)

REFERENCE W3SES SD CEDMCS, Pp. 10,11 ANSWER 6.02 (3.00)

a. All breakers open on undervoltage. (0.5)
b. Phase differential current (or Differential Protection) (0.5)
c. 1. Lamp burned out
2. Breaker racked out
3. Control power de-energized
4. Trip circuit fuse blown [0.25 en.] (1.0) d.- 1. Other tie breaker open
2. 480 VAC feeder to 31 ABS open [0.25 ea) (0.5)
o. 1. Bus de-energized or,
2. Generator on line, bus and transformer synched. [0.25 ea.] (0.5)

REFERENCE W3SES SD 56b, Pp 4,6 & SD 56c, Pp. 11,13 ANSWER 6.03 (2.50)

e. Spray reduces containment pressure which reduces out leakage [0.751

~

and scavenges atmospheric iodine. [0.75] '

(1.5)

b. 1. Hydrogen recombiners
1. Containment atmosphere release system. [0.5 es.] (1.0)

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Et__ELANI_111IEdi_DE11ENt_GQNIBQLt_8ND_INSIBudENI6IIQN PAGE 6

, ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

l REFERENCE i W3SES SD 15c, P.1 AND SD 19 P.2 ANSWER 6.04 (2.50) j

o. 1. Peak linear heat rate
2. Margin to DNB/DNBR I
3. Total core power l
4. Azimuthal tilt l
5. RCS mass flow rate l
6. Axial Shape Index (Any 5, 0.2 ea.] (1.0)
b. 1. Neutron power / flux
2. T cold I
3. T hot  !
4. RCP speed
5. RCS (or PZR) pressure
6. CEA positions
7. CEA Cor CEAC) penalty factors [any 6, 0.25 es.] )

(1.5)  :

l REFERENCE W3SES SD CPC, TAB.1.3 AND COLSS, P.1 4 1

' ANSWER 6.05 (2.50) o . ' 1. Prevent total flow from exceeding runout conditions. [0.53

2. Prevent all SI flow from spilling out of a break. [0.53
3. Upon a SIAS, all CLI header valves open to a predetermined throttled position. [0.5] (1.5)
b. 1. To equalize flow between hot and cold leg injection paths. [0.51
2. Bypass valve is open for cold leg injection and closed to equalize flow between paths. [0.5] (1.0) i REFERENCE W3SES SD Saf ety Inj ection, P.13

i 6t__EL6NI_SIRIEdi_DESIGNt_QQNIBQLt 8ND_INSIBudENI811QN PAGE 7 ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 6.06 (2.50) .

e. The level signal is dynamically compensated (0.2) for actual level rate of change (0.4) as well as the rate of change of the flow error signalCO.4). (1.0)
b. Bypass valve CSU Feed Reg) demand Main valve demand Feed pump speed setpoint (0.25 ea.) (0.75) i 1
c. Pump speed---------------------5% (Min. Speed ~ 3900 RPM)

Bypass (SU Feed Reg) valve-----5% Demand (25-30% open) s Main valve---------------------0% (closed) (0.25 ea.) (0.75)

REFERENCE .

W3SES SD FWCS, Pp.2,4,7 ANSWER 6.07 (2.50)

a. UEL-------------Reed switch UCS-----------------Computer LEL-------------Reed switch LCS-----------------Computer UGS-------------Computer Upper Seq. Perm.----Computer LGS-------------Computer Lower Seq. Perm.----Computer Will sccept Backup UEL---Reed switches. Not required for full credit. (0.2 es.) (1.0)
b. CWP on: 2/4 Hi LPD 2/4 LO DNBR 2/4 Hi Pzr. Pressure (0.3 ea.)

Will accept 2/4 CPC generated pretrips in place of LPD and

, DNBR trips. (0.9)

AEFERENCE W3SES SD CEDMCS, Pp. 27-29 l

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

ht__EL6NI_SYSIEdS_DESIGNt_QQNIBQLt_6NQ_INSIBudENI6IIQN PAGE 8 ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 6.08 (2.50)

Trips affected include: Lin. Hi Power, Log. Hi Power, DNBR, and LPD.

[0.125 es.] DNBR and LPD Trips are corrected for CEA and/or Temperature Shadowing. [0.5] An attempt is made to minimize effects by running ARO

[0.25] and periodically updating Ex-Core output during power operation.

[0.5] Also Strict adherence to PDIL minimizes effects of CEA shadowing.

[0.25] The CPC'S make corrections to DNBR & LPD trips based on axial profile shape and cold leg temperature (0.5% power / deg. F.) [0.53 (2.5) l REFERENCE W3SES SD EX-CORE, Pp.13,14 ANSWER 6.09 (2.50) -

e. No. [0.53 BAMT is sufficiently concentrated to attain necessary RCS concentration by allowing pressurizer level to increase above normal level. [0.53 (1.0) )
b. 1. Starts 2 charging pumps, [0.25] and positions valves to inj ect from BAMT to RCS. [0.25] Isolates Letdown. [0.25] (0.7G)
2. Isolates [0.25] Letdown [0.253 and controlled bleed off from RCP seals. [0.25] (0.75)

REFERENCE WSSES SD CVCS, Pp. 45-47 ANSWER 6.10 (2.50)  !

a. 1. Shield withdrawn CEA's from RCS cross flow.
2. Transfer upward loads from fuel alignment plate to support plate. [0.4 es.] (0.8)
b. Center finger contacts guide port and is connected to shock absorber on spider. [0.4] A dashpot effect is also provided by the CEA guide tubes. [0.41 (Accept tapered guide tube for dashpot effect.)

(0.8)

c. TOP---- (16")--- B4c MIDDLE--(58")----Hollow water filled tube BOTTOM--(75")----Solid Inconel [0.3 es.) (0.9) 6

. - - . - . - - - - - _. . , _ - . , _w _ _ , . - - _ . , . . ~ . . _ , . - . . , . . , . _ , . , - - - - . , . - .-e--

62__EL8NI_111IEd1_DE11ENt_GQUIBQLt_8NQ_INSIBVdENIeIlQN PAGE 9 ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

REFERENCE W3SES SD RV & INTERNALS, Pp.10,11,16 1

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o

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j

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,,vn-..,--,,- ,- - v_,, + - . -,- . , , , ,w,.mp-.-.-m,-, , ,--nmg.,..y.,v,,n m.-.,,-

U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _W61EBEQBQ_2_____________

REACTOR TYPE: _EWB-GE__________________

DATE ADMINISTERED: _RhlQ241Z________________

EXAMINER: _WBlIIEdQBEz_Jz__________

APPLICANT: _________________________

INSIBMGIl0N1_IQ_aEELIGeNIl Use separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at loast 804. Examination paptrs will be picked up six (6)~ hours after -

the examination starts.

% OF CATEGORY  % OF APPLICANT'S CATEGORY

__Y8LUE_ _IQIeL ___1GQBE___ _Y8LUE__ ______________G8IEQQBl_____________

_25tQQ__ 1QQtDQ ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS l _2E100__ 1QQiQQ ___________ ________ TOTALS FINAL GRASE _________________%

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

l APPLICANT'S SIGNATURE

Az__6051N11IB8IIVE_EBQQEQUBEli_QQNQIIIQNit_6NQ_L151I8I1QN1 PAGE 2 QUESTION 8.01 (3.00)

For each of the following situations indicate what REQUIREMENT, if any, applies and what ACTION, if any, should be taken. Consider ooch situation separately.

s. Diesel generator A's operability load test, which is required every 31 days, is scheduled for today. The last three tests were completed 36, 68, and 102 days ago respectively. The plant is at 100% power. (1.0)
b. The plant is at 295 F and heating up at 1 F per minute, when an HPSI pump is found inoperable. (1.0)
c. The plant is at 100% power and the discharge valve for one of the emergency feedwater pumps has been frozen shut for four (4) days and cannot be re-opened. (1.0)

QUESTION 8.02 (3.00)

For each of the following events explain briefly why the NRC SHOULD or SHOULD NOT be notified within 1 hr.

s. During instrument testing while at power, three pressurizer pressure safety channels are momentarily place in bypass.
b. While at power, Tave momentarily dips to 510 F and then

- returns to normal.

c. Refueling water tank level falls below 400,000 gallons and cannot be restored.

4

d. During surveillance testing an expected actuation of LPIS train A occurs. (3.0)

QUESTION 8.03 (2.00)

What actions, if any, should the Shift Supervisor take if the plant is in Mode 6, fuel loading is in progress, and the Refueling Senio'r Reactor Operator reports, "We have j ust lost the audio count rate out here in the containment, but I'm in position to load this fuel bundle, so I'll lower it down to prevent leaving a suspended load over the core." Justify your answer. (2.0)

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

Az 8Dd1N11IB8IIVE_EBQGEQUBEft_GQNQ1Il0Nat_8NQ_LIMII8Il0NS PAGE 3 QUESTION 8.04 (2.50)

e. What are the two different types (administrative) of maintenance performed at Waterford 3 ? (0.5)
b. Describe what happens to a CONDITION IDENTIFICATION and WORK AUTHORIZATION (CIWA) Tag if it is hung on a component and the component is subsequently removed to a shop for repair. (1.0)
c. Explain what should be done if it is discovered that CIWA work instructions for a safety related component deviate from the requirements of the component vendor manual. (1.0)

QUESTION 8.05 (2.00)

During shift turnover, the oncoming and offgoing shifts should walkdown the control panels together. Describe 5 topics that should be included in the turnover discussion that occurs during this walkdown in accordance with OP-100-007. (2.0)

QUESTION 8.06 (2.50)
o. List the Leak Detection Systems addressed in the Waterford Three

. Technical Specifications. (1.2)

b. What are the operability requirements to meet the Limiting Condition for Operation for Leak Detection Systems in Mode 1 ? (Do NOT discuss the action statement.) (1.3)

QUESTION 8.07 (2.50) i

s. What action is necessary if continued operation in mode 1 is desired with inoperable Steam Line Safety Valves ? Explain the reason (s) for this action. (1.5)
b. Explain why the Main Turbine or related equipment is addressed in the Technical Specifications when the turbine is not considered to be Safety Related equipment. -

(1.0)

I j

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

~

'Az__'8DMINISIB8IIVE_EBQQEQUBEft_QQNDIIIQN1t_8ND_LIMII8IIQN1 PAGE 4 QUESTION 8.08 (2.50)

o. Complete the following table:

The guidelines for emergency exposure are:

ORGAN CORRECTIVE ACTION LIFE SAVING Whole Body 25 Rems ----------

Extremities ----------- ----------

Thyroid ----------- ----------

b. What are 4 of the 5 guidelines recommended by the Emergency Plan that should be used to select personnel to receive exposures to the limits listed above ? (2.5)

QUESTION 8.09 (2.50)

o. Provide a basic description of the method used to manually calculate off-site dose rate from the control room during an emergency. Include parameter values needed to make the projection. (2.0)

,b. Where (location or distance from release) will the proj ected dose rate occur ? (0.5)

QUESTION 8.10 (2.50)

c. List four means or procedures used to prove or determine operability of an individual Reactor Protection System channel. (1.0)
b. During mode 1 operation the operator reports that one Pressurizer Pressure Safety channel is reading 90 psi lower than the lowest of the other channels, which all agree within 20 psi. Describe the problem if any #ND action necessary to continue operation in mode 1. (1.5)

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

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

It__hDd1811186IIVE EBQCEQMBEft_GQNQ1I19Nat_aNQ_LIMII8IlQN1 PAGE 5 ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 8.01 (3.00)

o. (Esch test must be within 25% of required time) and each three consecutive tests must be within 3.25 of required time. [0.3]

Declare DG A inoperable. [0.3] Prove operability of DG B within 1 hr. [0.2] Conduct load test on DG A. [0.23 (1.0) l

b. Only one HPSI pump required operable until 350 deg's. [0.5] Ensure third pump aligned to provide second train of ECCS before exceeding 350 deg's. [0.51 (1.0)
c. Unable to comply with LCO or Action Ststement. (T. S. 303) [0.4]

Start shutdown within one hour. [0.2] 9et standby within next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. [0.2] Hot Shutdown within following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. [0.23 (1.0)

REFERENCE T.S., pp. 3/4 0-1, 3/4 0-2, 3/4 5-8, 3/4 7-4, 3/4 8-11 ANSWER 8.02 (3.00)

e. Should report [0.5] plant is operated outside d$ sign basis [0.25]
b. No report [0.5] needed when an action statement for LCO is

, , entered [0.25]  ;

c. Should report [0.5] shutdown due to inability to meet LCO action statement requirement [0.25]

)

d. No report [0.5] for ESF actuation during surveillance testing [0.25] (3.0) l REFERENCE 10 CFR 50.72 ANSWER 8.03 (2.00]

l Order Refueling SRO to move fuel to a safe and conservative position. l

[1.0] Suspension of fuel loading is required by loss of audio count rote. [1.0] (2.0) 1

lt__'8DMIN11188IIVE_EBQQEQMBEft_QQNDIIIQNit_8ND_LIMII8Il0N1 PAGE 6 l .

! ANSWERS _- WATERFORD 3 -86/03/17-WHITTEMORE, J.

1 s REFERENCE l T. S. 9.2 ANSWEP 8.04 (2.50) 1

c. Controlled and Uncontrolled (0.25 ea.) (0.5)
b. Half of the two part tag should accompany the component, (0.5) l and the other half should be hung near the location where the

! component was installed. (0.53 (1.0)

c. Work should be stopped until a technical review and resolution are accomplished. (1.0)

REFERENCE UNT-5-002, Pp. 4,14,22 ANSWER 8.05 (2.00)

1. Status of Safety related systems.
2. Operating equipment and systems alignment.
3. Inoperable equipment, Tech. Spec. actions and/or surveillance requirements.
4. Reason for panel or computer alarms.
5. Outstanding clearances.

I 6. Unusual events in past 24 hrs.

7. Surveillance or maintenance in progress. (any 5, 0.4 ea.) (2.0)

REFERENCE OP-100-007, P. 5

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w ..-.-a ,

"Az__'6DMIN11IBaI12E_EBQQEQWBEf t_GQNDII1981t_8ND_LIMII611QN1 PAGE 7 ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 8.06 (2.50)

o. 1. Containment atmosphere particulate monitoring system.
2. Containment sump level and flow monitoring system.
3. Containment cooler flow monitoring switches.
4. Containment. atmosphere gaseous monitoring system. [0.3 es) (1.2)
b. Must have three systems operable. [0.5) Must always have #1 and
  1. 2 with #3 or #4. [0.8) (1.3)

REFERENCE T. S. 3/4.4.5 ANSWER 8.07 (2.50)

J e. RPS setpoints must be reduced to limit core thermal power. [0.75)

This is necessary so the core will not produce steam flow in excess of the capacity of the operable safety valves. [0.75) (1.5)

b. The turbine overspeed system is addressed, as inoperability of the trip could result in the turbine becoming a missile hazard which could affect safety related eculpment. (1.0)

REFERENCE 3

,T.S. 3/4.3.4 & 3/4.7.1.1

ANSWER 8.08 (2.50)
o. Whole Body 25 Rems 100 Rems Extremities 100 Rems 300 Rems Thyroid 125 Rems No Limit (0.2 for each correct answer) (1.0) i
b. 1. Individual is a volunteer.
2. Individual is familiar with consequences of exposure.
3. Should not use fertile females.

j 4. Should not have received previous emergency exposure.

5. Sclect older individuals. (any 4, 0.375 es.-) (1.5) 1 REFERENCE l

EP-2 030, P. 3 e

1

Az__8DMIN11IB811ME_EBQQEQMBEft_CQNDIIl0 Nit _8NQ_L16118I10NA PAGE 8 ANSWERS -- WATERFORD 3 -86/03/17-WHITTEMORE, J.

ANSWER 8.09 (2.50)

o. Release rate and dispersion factor [0.5] are converted to dose rate using a nomograph in the control room.[0.53 Parameters needed are release flow rate, uC/cc or mR/hr. monitor readings, wind speed and temperature differences from met. tower at 10M and 60M. [1.03 (2.0)
b. Exclusion area boundary. (Accept 914 meters) (0.5)

REFERENCE EP-2-050, ATT. 7 ANSWER 8.10 (2.50)

c. 1. Channel check.
2. Channel calibration.
3. Channel functional test.
4. Response time check. [0.25 ea.] (1.0)
b. Problem is that protection system design logic is compromised.[0.53 Declare low reading channel inoperable. [0.5] Place affected channel in trip or bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. [0.5] (1.5)

REFERENCE T. S. 4.3.1.1, 4.3.1.3, and '

3.3.1 Action stmt.2 l

1 I

1 i

l i

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