ML20247N520

Forwards Answer Key for NRC Requalification Makeup Exam Re Exam Repts 50-266/OL-89-02 & 50-301/OL-89-02

ML20247N520
Person / Time
Site:	Point Beach
Issue date:	05/24/1989
From:	Burdick T, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Fay C WISCONSIN ELECTRIC POWER CO.
References
NUDOCS 8906050381
Download: ML20247N520 (121)

Text

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Q ,4 , *3 j s MAY- 2 41989 s Docket No'.'50-266' Docket No. 50-3011

^

Wisconsin Electric Power Company

. ATTN:' Mr. C.~W. Fay Vic'e President Nuclear Power::

231 West Michigan Street -;P379' Milwaukee, WI 53201 Gentlemen:

Enclosed p. lease. find copy of Examination Report No. 50-266/301-0L-89-02. >

~This was.omitted in error with the letter dated May 22, 1989.

Sincerely, M inal signed by T. M..Burdick / for Geoffrey C. Wright,. Chief' Operations Branch a '

Enclosure:

- As' stated' cc w/ enclosure:.

LJ. J.'Zach, Plant. Manager DCD/DCB'(RIDS)

. Licensing Fee Management Branch Resident Inspector, RIII Virgil _Kanable ) Chief-Boiler Section Charles Thompson, Chairman Wisconsin Public Service'

.Commissi6n R. I. Braund'(SLO)',

WI-Div. of' Emergency Government Lawrence J. McDonnell,. Chief Radiation Protection Section

'WI: Department of Health and Social, Services, Division of Health-R. J. Bruno, Plant Training Manager W. H. Swenson, Project Manager, NRR

'M. R.' Johnson,;EDO- .

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.fmkL co!4 Print Date: 05/16/89 T89-034; NRC REOUAL MAKEUP EXAM (KEY)

Instructions:

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1. Answer all questions enclosed on pages and show all calculations.

2. Do not discuss exam, questions, or answers with anyone.

3. Passing grades are 80% overall,

4. Choose BEST answer. Multiple choice has only one correct answer.

5. Do not write on back of pages. Attach additional sheets if needed.

Section 1 2 3 Points Received Section Point Value 10.4 11.2 N M &"

Percentage Grade Overall SEE APPROVAL COPY COVERSHEET FOR SIGNATURES fATTACHED) 1 i

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l TR-8.6.1 (10-87)

q ., . ;7 c;- 4 fl-' I l

. . .94- .,,

't Print Date: 05/16/89 T89-034: NRC REOUAL MAKEUP EXAM (FOR APPROVAL)

. Instructions:-

1. Answer all questions enclosed on pages and show all calculations.

2. -Do not discuss exam, questions,.or answers with anyone. 4

3. Passing grades are 80% overall

• l

4. Choose BEST answer. Multiple Choice has only one correct answer.  ;

5. Do'not write on back of pages. Attach additional sheets if needed.

Section 1 2 3 i LPoints Received t i

4 Section Point Value 10.4 11.2 20.1 41.7 Percentage Grade'  :

Overall Prepared by N Date i 2 9 Reviewed by TfondoT nW b ^ ^:- Y-- . $Y f /h6 l Technical IIteview /

[ / {V  !

w Cpfriculum' Development bni A Date 5//6/8 C/ .

Approved by IbI #" //A/ Date [ '//'9 d

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

TR-8.6.1

.(10-87) Candidate's Signature l' .

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Exam Ouestion Number -Ouestion Number 1-01 032-03-QO1A.

1-02 052-03-004A 1-03 051-01-020A 1-04 053-03-002AL 1-05 055-01-013A ,

1 031-03-052A 1-07 031-01-003A 1-08 031-03-035A 1-09 053-03-003A 1-10 031-03-034A 1-11 031-03-037A R 1-12 031-03-036A 2-01 051-03-002A 2-02 OG5-02-028A 2-03 031-03-056A' 2-04 031-03-115A 2-05 051-02-034A 2-06 051-05-002A 2-07 055-02-084A 2-08 051-03-007A 2-09 053-01-013A 2-10 031-03-137A 2-11 031-03-057A 2-12 055-02-031A 2-13 055-02-032A ,

2-14 053-02-002A 2-15 053-09-010A.

3-01 053-01-039A 3-02 053-01-040A 3-03 053-01-049A 3-04 053-02-034A 3-05 053-04-028A 3-06 051-02-026A l 3-07 051-02-037A i 3-08 051-03-015A 3-09 051-01-045A l 3-10 052-02-010A I 3-11 055-01-026A

( 3-12 055-02-002A 3-13 055-02-051A 3-14 055-02-054A 3-15 055-02-078A c 3-16 031-03-001A 3-17 031-03-090A 3-18 031-03-096A 3-19 031-03-119A 3-20 043-02-010A 3-21 057-02-019A

. 3-22 053-01-048A 3-23 055-01-027A 3-24 031-01-005A

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Section 1 t

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1 PLANT PROFICIENCY MAKEUP STATIC SCENARIO I i

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l STATIC SIMULATOR SCENARIO SCENARIO 'ST-89-01 Rev. 0

'l Scenario Set-up Time: 30- minutes DESCRIBE CHANGES:

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l Prepared By: 65Bf v

1. 1. !-/ Date: 8~ P N Reviewed By: /- ,, ,

Date: f fY Approved By: /,9 b / M G 4 M Date: -

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Training coordinator I

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'C~ S INSTRUCTOR REFERENCE Scenario - ST-89-01 M INPUT DESCRIPTION / DIRECTIONS / COMMENTS 00:00:00 IC-12 Initialize simulator 100% power MOL SIO3C SI Pumps fail to start NIO4B,25 IR-36 under compensated.

84002-L9,,OFF. NIS Positive rate trip 84006-L9,,OFF 84008-L9,,OFF 84014-L9,,OFF.

47013:0105,,OFF Positive rate annunciator 47012:0202,,0N Pzr low press. Rx trip annunciator 41228-02,,6 IR-35 SUR 00:05:00 RD0515 Drepped rod D-4 00:06:00 Start 20 gallon boration 00:07:00 Start power decrease to 75% at 1%/ min ramp rate.

2 00:12:00 RCO3B,11 Hot Leg Break (11,000 lbs/sec.)

00:14:00 Take both SI pump control switches to the start position.

00:20:00 Reset SI containment Isolation and reset safeguards lockout relay.

00:21:00 Reestablish IA to containment 00:21:30 Establish max. charging (3 pumps) 00:26:00 Silence annunciators Ensure IR <1.5X10 40 amps Freeze simulator Turn Recorder Power Off Static Enference Data l

IR-35 reading 1.0X10 40 amps IR-36 reading 9.0X10 40 amps Containment Pressure 13 psig  !

RWST at 84%

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y STUDENT REFERENCE Scenario - ST-89-01 Plant History Prior to Initiatine Event Forty five' minutes ago, Unit 1 was operating at 100% power, middle of life, steady state with the Gas Turbine out of-service. Xenon was at equilibrium.-Boron was at 444 ppm. All controls were in auto / normal for this plant condition.

Initiatine Event About 30 minutes ago, a rod drop (D-4) and turbine runback from the-dropped rod occurred. During the decrease in power per AOP-6A, a decreasing RCS pressure was observed followed shortly by a RX trip and SI.

Deerator Acticns Taken While the operators were in AOP-6A, rod D-4 was verified dropped by steps 6.1.1 and 6.1.2. Following the runback, boration was started for delta flux correction. Operators

• had reset the steam dumps and were decreasing power to <75%

per step 7.2 when the reactor trip occurred.

Shortly after the trip, cperators entered E0P-0. At step 33 a transition was made to IOP-1. EOP actions have been completed through step 11 of EOP-1.

Procedure and'Stee in Effect Entering step 12 of E0P-1.

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ST 89-01 OTTESTION NUMBER POINTS TOTAL TIME TOTAL 032-03-001A 0.6 0.6 9.45 9.45 052-03-004A- 1.0 1.6 3.6 13.05 051-01-070A 1.0 2.6 4.6 17.65 053-03-002A 1.0 3.6 3.3 20.95 055-01-013A' O.8 4.4 2.1 23.05 031-03-052A 1.2 5.6 2.0 25.05 031-01-003A 1.0 6.6 1.8 26.85 031-03-035A 0.6 7.2 3.7 30.55 053-03-003A 0.6 7.8 1.8 32.35-031-03-034A 0.6 8.4 2.5 34.85 031-03-037A 1.0 9.4 3.8 38.65 031-03-036A 1.0 10.4 3.6 42.*S O

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Question Number: 032-03-001A Point Value: 0.6 kevision Number: 2 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: ROD CONTROL SYSTEM Task Number: C0117 COT Terminal Learnine Obiective:

C0117 COT During all modes of operation and given the Reactor operating Data Book, analyze associated reactor data when core reactivity is changing in accordance with the Reactor Operating Data Book.

Question: Instructor Use Only Following the turbine runback and prior to the reactor trip, how many gallons of boric acid would have been necessary to keep Tavg at 562 0F while

. manually withdrawing Bank D rods from 173 steps to 190 steps? (Assume boron worth is -11.2 pcm/ ppm and the plant was stabilized at 65% power.)

(Show all work.)

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Points Earned

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! . Question No;: 032-03-001A' .Page 2 Answer:- Instructor Use Only

.54s7 Seer M

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Reactivity worth'at 173 steps..on.D: 4999.pcm Reactivity worth at' g535 190 steps on D: 5467 cm

' Reactivity change due to M We control rod movement +66 pcm ( 10 pcm)

(.2 pts.)

Beric acid. change necessary

• • 0 09 7.0

-se nem 4 egg

-11.2 per/ ppm = +6rtppm(i 1 ppm) (.2 pts.)

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Gallons g boric acid

-(N

= Nh4 gal (12 gal) m) (1.75 gal / ppm)

(.2 pts.)

~ Note: N Answer may vary based upon actual rod height

-on the simulator and should be corrected accordingly.

ST-89-01 421 Additional Information:

c g a s s, s a a t o u [Lv 8 *5 K t>

Technical

References:

g. ggp o ufc;7 geo 4 ROD 4, 6.6- o'/[6 /fi Blender' Book ~ g/

Items to be Included with Ouesti2D: None .

Time validation: 9.45 Requal Cvela: N/A K/A

Reference:

. System: 001 ,

Mode: 000 Number: K5.09 Ratinge: RO: 3.5 SRO: 3.7

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. o Question Number: 052-03-004A Point Value: 1.0 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: MAIN TURBINE GENERATOR  !

Task Number: C3121 COT, P3107 COT Termina.? Learnino Obiective:

C3121 COT During conditions of startup, shutdown and normal power.

operation APPLY Technical Specification and procedural requirements associated with operation of the main turbine generator as referenced in OP-1C, " Low Power to Normal Power" and Technical Specifications, Section 15.3.4.

P3107 COT During conditions of normal plant operation MONITOR the turbine generator in accordance with OP-2A, " Normal Power Operation".

Question: Instructor Use only Following the turbine runback and prior to the reactor trip:

2. Explain why the Reference Window on the Generator EHC display was no longer at 100%.

( . 4 ., pts . )

b. Explain whether or not turbine load would have increased if the Setter setting were placed at 100% and the "GO" button depressed.

(.6 pts.)

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... o Question No'.: 052-03-004A. Page 2 Answer: Instructor Use Only a.. The EHC Load Reference was also lowered when the turbine experienced the runback. (.4 pts.)

b. The Valve Position Limit had been lowered so the Governor Valves would not open any further. (.6 pts.)- (also. acceptable is load may increase to the valve position limiter)

ST-89-01 431 Additional Information:

Technical

References:

TRHB 13.11 Items to be Included with'Ouestion: None Time Validation: 3.60 Requal Cvela: N/A K/A

Reference:

. System: 045 Mode : - 000

' Number: K4.12 Ratings: RO: 3.3 SRO: 3.6 l

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, Question Number: '051-01-020A.' Point Value: 1.0 iRevision Number: 5 Approval.Date: 05/17/89

- Question Format: W Question Type: S Subject. Area: STEAM GENERATOR SYSTEM Task Number: P2404 COT Terminal Learnina Obiective:

P2404 COT During'all modes of operation and given operating logs monitor SG operation in accordance with operating logs.

Instructor Use Only Question:

Following the Turbine runback and prior to the reactor trip, assume Dower was lowered to 65%

Der AOP-6A. While the operators are withdrawing j

the dropped rod per procedure, explain why steam l

-generator pressures INCREASE, DECREASE, or REMAIN THE SAME; i

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<uQuestion No.:' 051-01-020A Instructor Use only gg 3. Answer: :

N' SG pressure will DECREASE - ( .2 - pts. ).' because I

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Turbine load is manually increased. (.8 pts.)

1 ST-89-01, 430 h LAdditional.Information:.

E-g Technical

References:

LP-1579.-

.TRHB 11.1 AOP-6A.

' Steam Tables

.. Itama to be' Included with Ouestion: None Time validation: 4.60

- Reaual Cvele: N/A.

K/A'

Reference:

- System:. 001 Mode:: 000 Number: 'A1.03 Ratings:' RO: .3.6 .SRO: 3.7-1

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Question Number:. 053-03-002A Point Value: 1.0

- Revision Number: 1 Approval.Date: 05/17/89 Question Format: W- Question Type: C Subject Area: NUCLEAR INSTRUMENTATION SYSTEM Task Number:. P1304 COT

- Terminal Learnina Obiective:

P1304 COT. During all modes of operation, monitor all three ranges of nuclear instrumentation in order to determine' reactor power level consistent with the accuracy requirements of the NIS.

Instructor Use Only

- Question:

With current conditions, explain whether or not it is possible'to determine reactor power level.

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Points Earned

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t'. 4 h (Question No.: 053-03-002A: Page 2-p p' ..

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Instructor Use.Only-(IntermediateLrange~ channel N-36 is ,

i 'undercompensated which prevents the' source ranges

'from' energizing.) N-35 is availablef(1.0 pts.)'

H andicould:be used:to. determine. reactor power.-

.Also acceptable:'. Reactor power >may not'be-

! . determined since oneLchannel (N-36)Lis-

-undercompensated.theLotherJchannel may.also be-

' unreliable 3and source ranges are not energized,.

or source ranges may be~ energized by_ pressing the'IR Permissive Defeat.

ST-89-01 K/A

Reference:

~ System:- 000

- Mode :: 007

. Number: EK1.05

'L Rating: RO 3.3 SRO 3.8 a Note 2

' 517-p

'-Additional Information:

Technical

References:

TRHB.13.1 Items to be Included with Ouestion: None Time Validation: 3.30-Reaual-cycle: N/A K/A

Reference:

System:- 000

. Mode: 007 Number: EKl.05 Ratings: RO : - 3.3 SRO: 3.8 l-o d.

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Question Number: 055-01-013A Point Value: 0.8 Revision Number: 0 Approval Date: 05/15/89 Question Format: W Question Type: C Subject Area: NUCLEAR INSTRUMENTATION SYSTEM Task Number: P1310 COT Terminal Learnine obiective:

P1310 COT During a normal plant startup or shutdown, verify proper-NIS response to ensure Technical Specifications are not violated.

Question: Instructor Use only Which one of the following statements describes why source range hatruments NI-31 and NI-32 are not indicating?

a. Reactor power level is above the Source Range.

b. 25 minutes have passed since tha reactor trip.

I c. Conditions exist such that the P-6 permissive light is ON.

d. Conditions exist such that the P-10

! permissive light is OFF.

Points Earned l- - - _ _ _ . __ _____ - ____-_______ _ -

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!  : Question No.:: 055-01-013A Page 2 i' Answer: Instructor Use Only

, . c. .(.8 pts.)

ST-89-01 K/A

Reference:

System: 000 Mode: 007 Number: EA1.05 Rating:. RO 4.0 SRO- 4.1 Note 2 524 Additional Information:

Technical

References:

TRHB 13.1-E0P-0.1 l ..

Ita== to be Included with Ouestion: None Time validation: 2.10 Requal Cvela: N/A K/A

Reference:

System: 000 Mode: 007 Number: EA1.01 Ratings: RO: 3.7 SRO: 3.4 t

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Question Number

031-03-052A Point' Value: 1.2 LRevision. Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: C Subject Area: EMERGENCY TASKS Task Number: C7009 COT, C7012 COT Terminal Learnina Obiective:

C7009 COT From any plant condition following a reactor trip or safety 3 injection actuation recognize the critical safety functions j by verifying that all safety related parameters are j satisfied in accordance with the critical safety function status trees.

C7012 COT From operating plant conditions at power following a reactor trip'and safety _' injection' recognize a LOCA by verifying the diagnostic conditions listed in EOP-0,

" Reactor Trip or Safety Injection."

Question: Instructor Use Only NOTE: Choose one answer.

The event in progress is a(n)

a. steam generator tube rupture,

b. break in the feedwater line to "A" steam generator inside containment.

c. charging line break outside containment.

d. stuck-open pressurizer PORV.

e. RCS hot leg break.

f. failed RCP seal.

Points Earned 4

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Q'uestion No.: 031-03-052A Page 2-Answer: Instructor.Use only

e. (1.2. pts.)

'ST-89-01' 724 Additional Information:

-Technical

References:

EOP AOP-1A h to-be Included with Ouestion: None Time Validation: 2.00 Eggggi Cvela: N/A K/A

Reference:

System: 000

..- Mode: 011 Number:- Gil a

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' Question Number: '031-01-003A Point Value: 1.O Revision Number: 0 Approval Date: 05/15/89 Question Format: W . Question Type: C Subject Area: EMERGENCY TASKS  :

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-Task Number:

C7024 COT

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C7024 COT Given a set of Emergency Operating Procedures. apply the l procedural rules of usage to the E0Ps by performing procedural steps in proper sequence making' correct transitions to sequence through the E0Ps to a termination l point.

l Question: Instructor Use only i Assume that switchover to containment' sump i recirculation.is in progress. If "A" RER pump i

' fails to start after its suction is lined up to the containment sump, what action should be taken?- ]

(Choose.one answer.) 1

a. Proceed to ECA-1.1, " Loss of Containment Sump Recirculation."  ;

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b. Wait until PWST-level reaches 64 and secure  !

"B" RHR pump.  ;

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c. Align "B" RHR train for containt ' ump l recirculation.

d. ' Align "A" SI pump for direct suction from the l containment sump. j e.- Cross tie the "A" and "B" RHR pump discharge. .j lines.

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Question'No.:. 031-01-003A Page 2 Answer: Instructor Use.Only

c. '(1.0 pts.)

ST-89-01 K/A

Reference:

System:  ; 000 Mode: 011 Number: G12 Rating: RO 4.O SRO 4.1 Note 3 716 Additional Information:

Technical

References:

EOP-1.3 l'

Items to be Included with ouestion: None Time Validation: 1.80 Recual Cvele: - N/A K/A

Reference:

System: 000 Mode: 011 Number: G12 6

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Question Number: 031-03-035A Point Value: 0.6 Revision Number: 0 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: RESIDUAL HEAT REMOVAL Task Number: CO234 COT, C0514 COT Terminal Learnina Obiective:

CO234 COT During accident conditions of either a secondary fault or a LOCA, the operator must be able to discriminate between overcooling and LOCA indications to effectively diagnose and implement the appropriate EOP.

C0514 COT During an accident . condition the operators must be able to diagnose inadequate suction for the RHR pumps from the RCS hot leg, RWST or containment recirculation sump.

Question: Instructor Use Only Using current conditions, explain whether or not the RHR pump suction should be switched from the RWST to the containment sump for recirculation?

Points Earned

Question No.: 031-03-035A Page 2  ;

Answer: Instructor Use only

! RER suction should not be switched until RWST level is <10% or RHR suction should not be switched because'RWST level is >60% (10%). Also acceptable is current RWST level on the simulator. (.6 pts.)

ST-89-01 I

K/A

Reference:

System: 000 Mode: 011 Number: EK3.15 Rating: RO 4.3 SRO 4.4 Note 2 713 Additional Information:

Technical

References:

EOP-1.3 Its'as to be included with Ouestion: None Time Validation: 3.70 "Aecual Cvela: N/A K/A

Reference:

System: 000 Mode: 011

, Number: EK3.15 Ratings: RO: 4.3 SRO: 4.4

Question Number: 053-03-003A Point Value: 0.6-Revision Number: 1 Approval Date: 05/15/89 1 Question Format: W- .

Question Type: S L Subject Area: ' NUCLEAR INSTRUMENTATION SYSTEM l .-

l- Task Number: C1313 COT Tarminal Learnina Obiective:

C1313 COT During accident.(LOCA) recovery operations recognize the-effect of core voiding on NIS source range indications, without error.

Question: Instructor Use Only-Assuming homogeneous voiding of the downcomer occurs, explain how the response of the source range detectors is affected.

Points Earned

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I Question No.:' 053-03-003A Page 2 Answer: Instructor Use only-

!'When the downeomer develops voids shielding of the

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NIs-is lost, causing the source range count rate to increase.. ( .6 pts.)

=ST-89-01 707 j Additional Information:

Technical

References:

TRHB 13.1 Itama to-be Included with Ouestion: None Time Validation: 1.80 Recual Cvela: N/A K/A

Reference:

System: 191 Mode: 002 Number: K1.17 Ratings: RO: 3.3 SRO: 3.5

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Question Number: 031-03-034A Point Value: 0.6 Revision Number: 1 Approval Date: 05/15/89

' Question Format: W Question Type: S Subject Area: SAFETY INJECTION SYSTEM Task Number: C0608 COT Terminal Learniner obiective:

C0608 COT During a small or large break LOCA assess SI system response by verifying all automatic safeguards components-actuate as required and that system parameters such as flow, temperature and pressure follow expected system characteristics.

Question: Instructor Use Only What, if any , safeguards equipment is not running which should have sequenced on?

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Q'uestion~No.: 031-03-034A Page 2 3.,

Answer: Instructor Use Only

'The SI pumps are not running. (.6 pts.)

l ST-89-01

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Technical

References:

Static Simulator TRHB 13.4 Itama to be Included with Ouestion: None Time validation: 2.50.

Reaual Cvele: N/A' K/A

Reference:

System: 006 Mode: 000 Number: K4.05 Ratings: RO: 4.3 SRO: 4.4

Question Number: 031-03-037A Point Value: 1.0

, Revision Number: 1 Approval'Date: 05/15/89 Question Format: W Question Type: S Subject Area: REACTOR COOIANT SYSTEM Task Number: C0219 COT Terminal Learnina Obiective:

CO219 COT During emergency conditions, analyze the effect of a LOCA on the containment. Satisfactory understanding should include the containment design limits and sump capacity.

Question: Instructor Use only Assuming containment spray actuated explain whether or not the containment design criteria would be-exceeded if two of the four reactor containment accident fans fail to start.

Points Earned l

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itrestion No ': '031-03-037A Page 2

Answer: Instructor Use only 4 Th's containment design would not be' exceeded'since ^

b two.of thefour containment accident fans are I adequate.provided one containment spray pump is.in operation.-(1.0 pts.)

p ST-89-01 702 Additional Information:

Technical

References:

TRHB 10.1.and 10.'16 TS 15.3.3 Iteam'to be Included with Ouestion: None Time Validation: 3.80 Requal cycle: N/A K/A

Reference:

System: '002 Mode: 020

. Number: K3.02 Ratings: RO: 4.2 SRO: 4.6 t

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Question Number: 031-03-036A Point Value: 1.0-Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: EMERGENCY TASKS i Task Number: C7009 COT Terminal Learnine obiective:

I C7009 COT From any plant condition following a reactor trip or safety injection actuation recognize the critical safety functions by verifying that all safety related parameters are satisfied in accordance with the critical safety function status trees.

Question: Instructor Use only Perform an evaluation of the critical safety function status trees with the current plant ,

I conditions. Assume: Core exit thermocouple are reading 690 0F, reactor vessel narrow range level is 40 ft.; reactor vessel wide range level is 93 i ft.; containment sump "B" level is 65 in.; and all l containment high range radiation monitors are reading 1.3 R/HR.

Which one of the following status trees have the highest priority?

a. ST-1 "Subcriticality"

b. ST-2 " Core Cooling"

c. ST-3 " Heat Sink"

d. ST-5 " Containment"

e. ST-6 " Inventory" I

i Points Earned

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- Question ~.No.: 031-03-036A: Page 2

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I(1.0l pts.)'

G ^ ST-89-01

.715

' Additional'Information:

, Technical'

References:

=ST-2 CSP-C.2

' Items to be Included with Ouestion: None

. Time validation: 3.60 Requal Cycle: N/A K/A

Reference:

System: 000 Mode: 011 Number:- Gil s

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PLANT PROFICIENCY MAKEUP STATIC SCENARIO II l'

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~ STATIC SIMUIATOR SCENARIO SCENARIO - ST-48-09 Rev. 2 Scenario Set-up Time: 10 ' minutes DESCRIBE CHANGES:

Added overrides for clarification.

j. g i,~/2./ /7 Prepared By: -

Date: .

Reviewed By: N/# Date:

Approved By: ' Data: I'2' Training Coordinator l

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INSTRUCTOR REFERENCE Scenario 'ST-88-09

,1 M I,52.,ill DESCRIPTION / DIRECTIONS / COMMENTS 00:00:00 IC-12 Initialize simulator 100% power MOL l 47012:0202,,0N Pzr-Press. Rx Trip first out-

'47009:0104,,OFF TD AFW Trip 47001:0205,,OFF RCP Fire Annunciators 47001:0305,,OFF 44901-0101,,OFF 44901-0201,,OFF 46537-G,,0N Cavity Cooling Tan 46537-R,,OFF 46319-G,,0N Pzr.Htr's 1C, 1D, and 1E 46319-R,,OFF

'46320-G,,0N 46320-R,,OFF 46321-G,,0N r

46321-R,,OFF 00:05:00 RC05,18 Pressurizer Stern Space. Leak 00:07:00 Silence annunciators (Ensure 5C loads sequenced on)

Freeze simulator Turn Recorder Power Off Static Reference Data PZR press. 1410 psig and level 30%

Tave - 546*?

Containment Pressure / Humidity - 2.0 psig/100%

SG 1evels 0% and press. 960 psig

STUDENT REFERENCE Scenario - ST-88-09 Plant Historv Prior to Initiatine Event Approximately 15 minutes ago,. Unit I was operating at.100%.

pcwer, middle of life, steady state with the Gas Turbine out of service. Xenon was at equilibrium. Boron was at 444 ppm.

All: controls. vere in auto / normal for this plant condition.

Initiatine Event Within'the-past several minutes, operaters observed a charging pump in auto Hi/Lo annunciator and the RCS pressure decreasing. A runback to 954 occurred followed shortly by a reactor-trip and then an auto SI.

Oeerator Actions Taken No operator actions have been taken.

Precedure and Stee in Affect ~

' Entering EOP-0 step 1.

S l-i L ___ _ _ _ . - - _ _ __ _ - - - - - - - - - - - - - -

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1 ST 88-09 OUESTION POINTS TOTAL _ TIME TOTAL

- 051-03-002A 0.6 0.6 2.9 2.9 055-02-028A 0.5 1.1 1.4 '4.3 'I 031-03-056A 1.0 2.1 2.2 6.5 1 031-03-115A 0.5 2.6 0.9 7.4 051-02-034A 0.5 3.1 2.0 9.4 051-05-002A 0.7 3.8- 4.2 13.6 055-02-084A 0.9 4.7 2.4 16.0 051-03-007A 1.0 5.7 6.4 22.4 053-01-013A 1.0 6.7 4.0 26.4 i 031-03-137A 0.6 7.3 6.0 13 2 . 4 -

031-03-057A .0.8 8.1 2.7 35.1 055-02-031A. 1.0 9.1 1.4 36.5 055-02-032A- 0.6 9.7 1.5 38.0 053-02-002A 0.5 10.2~ 3.8 41.8 053-09-010A 1.0 11.2 3.2 45.0 f.

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Qusstion Number: 051-03-002A Point Value: 0.6 Revision Number:- 4 Approval Date: 05/17/89 Question Format: W Question Type: S Subject Area: CONTAINMENT SPRAY SYSTEM Task Number: C1908 COT Terminal Learnina Obiective:

C1908 COT During emergency operations recognize the radiological hazards in containment if the NaOH tank fails to inject on a LOCA to preclude a radiological release to the enviro". lent.

Instructor Use Only Question:

Assume that the system fault worsens. Containment pressure increases to 26 psig. Explain what, if  ;

any, effect NOT' adding sodium hydroxide to the cpray will have on containment. (Comment specifically on pressure, temperature and airborne activity.)

Points Earned

o .1, ,

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e =Quoction'No.21 051-03-002A :Paga 2

[ Answer: Instructor..Use only

'No effectL on' pressure'or temperature._(.2 pts.)

~ Airborne activity.will~ increase. NaOH's function iis to1 increase iodine's solubility..in.the containment sump' water which will1 remove iodine

, from the containment atmosphere. (.4 pts.)

ST-88'09' 546 Additional Information:.

Technical

References:

"TRHB 10.1' TRHB'10.2 TRHBc10.12 Technical Specifications Itama to be Included with'Ouestion: None

-Time Val'idation: 2.90

-Reaual Cycle: N/A K/A

Reference:

- System: -026

! ' Mode: 000 Number: A2.05 Ratings:f RO: 3.7 SRO: 4.1 4

Oc00 tion Numb 0r: 055-02-028A Point Value: 0.5 Revision Number: 1 Approval Date: 05/15/89

' Question Format: W Question Type: S Subject Area: REACTOR COOLANT PUMP Task Number: C0313 COT, C0902 COT Terminal Learnina Obiective:

CO313 COT During all modes.of operation, and given a copy of OI-1 diagnose conditions requiring RCP tripping in accordance with OI-1, " Reactor Coolant Pump Operation Guide".

C0902 COT 'During all modes of operation, diagnose malfunctions of the  !

pressurizer pressure control system prior to causing'a '

reactor trip.

Question: Instructor Use Only With current conditions, explain whether or not the ,

RCPs should be tripped.  !

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I Points Earned I

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fQu'estion No.: ~055-02-028A Page 2 Answer: Instructor Use only

The RCP's'should.not be tripped.. (.2 pts.) EC1 subcoolinais areater than 302Z (no adverse

', containment) (.3 pts.)

!(Also acceptable.is current subcooling meter

' indication)

ST-88 e 1

558

Additional Information:

Technical

References:

AOP-1B-EOP-0

'EOP-1 Items to be Included with'ouestion: None Time Validation: 1.40 Ragnal__ Cycle: N/A '

K/A

Reference:

System: 000 Mode: 009 Number: EK3.13 Ratings: RO: 3.4 SRO: 3.7 4

-_w-_:_____. . _ .. _ . _ . - . - . _ - _ . _ - - - - _ _ - - . , . _ _ _ _ _ _ _ - _ _ _ _ - _ - - - _ . _ _ _ _ _ - _ - _ - _ . _ _ - - - -

ca- o Qusction Numbars 031-03-056A ' Point Value:' 1.0

. Revision Number:l 2 Approval Date: 05/17/89

. Question Format:. W . Question Type: S' Subject Area:- REACTOR COOLANT SYSTEM Task Number: CO226 COT Terminal Learnina Obiective: ,

CO226 COT Considering all available control board indications, recognize the need to monitor incore TCs and wide range RTDs while on natural circulation considering the conditions that make TCs and RTDs more accurate than other related-indications.

Instructor Use Only.

Question:

Assume the reactor coolant pumps are tripped and the subcooling meter is out-of-service. What parameters would you use to calculate subcooling?

(No calculations required.)

Points Earned

N

-'$', .-~..$-

yl Page 2

?Questi$n'No.:' ~031-03-056AL .

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Answer: Instructor Use only ,

Incore. thermocouple.or RCS temperature. (.5 pts.) -

'RCS pressure (.5 pts.)

.ST-88 530 k

l Additional Information:

' ' Technical'

References:

TRHB 10.2 EOP-0.2

.. Items'to be-Included with Ouestion: None

' Recual h e Validation:'

Cycle:'..N/A 2.20 K / A R e f e rf,,n g,g :- System: 002 Mode: 000

, Number: K5.17 L

Ratings: RO: 3.8 SRO: 4.1 l

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Question Number: 031-03-115A Point Value: 0.5 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: SAFETY INJECTION SYSTEM Task Number: C0604 COT, C0615 COT Terminal Learnina Obiective:

C0604 COT During emergency or accident conditions, the operator must be able to diagnose malfunctions of the SI system that inhibit any function of the SI system.

C0615 COT During emergency or accident conditions the operator must be able to recognize conditions for terminating or resetting SI as identified in the Emergency Operating Procedures.

Question: Instructor Use Only Explain whether or not SI should be terainated.

l Points Earned

r.  :.,

- Question No.: 031-03-115A -Page 2'-

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Answer: Instructor Use Only.

1SI should not be terminated. (.3 pts.) RCS .

- pressure is'not > 1600 psig (or is'not stable or increasing). - (.2 pts.) (also' acceptable is current simulator pressure)

U ST-88-09 535 g

Additional Information:

f Technical

References:

EOP-1 Itamm to be Included with Ouestion:l None Time Validation: 0 .90 t Requal Cvela: N/A K/A

Reference:

System: 000 Mode: 009 Number: EK3.24 -

Ratings: RO:-'4.1 SRO:- 4.6 4

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Questio'n Number: 051-02-034A Point Value: . 0.5 Revision Number: 2 Approval Date: 05/17/89 I Question Format: W Question Type:- S ,

Subject Area: CHEMICAL & VOLUME CONTROL SYSTEM Task Number: C0403 COT, C0404 COT Terminal Learnina Obiective:

C0403 COT During all modes of operation, assess the affect of a safeguard actuation signal on CVCS without error.

C0404 COT During all modes of operation diagnose the affect on CVCS that a loss of component cooling would have prior to actuation of the temperature control valve.

Question: Instructor Use Only-(This question does not apply to current simulator conditions.)

The RCS leak is identified and isolated. RCS pressure is stable at 1700 psig. SI is reset and safeguards equipment secured. Charging and letdown are re-established. PZR level is 30%. The control operator then notices that RCS pressure is slowly decreasing. Explain whether or not initiating a manual safety injection will cause letdown to isolate?

Points Earned

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,1 Question No.: 051-02-034A' Paga 2 Answer: Instructor Use Only

A manual SI signal does not produce a containment isolation which would isolate letdown. (.5 pts.)

ST-88-09 543 Additional Information:

Technical

References:

Iogic Sht. 7 Items to be Included with Ouestion: None Time Validation: 2.00 Recual Cycle: N/A

- K/A

Reference:

System: .013 Mode: 000 Number: K1.01 Ratings: RO: 4.2 SRO: 4.4 4

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4" Question Number: 051-05-002A- ' Point Value:. 0.7

. Revision' Number: 1 Approval Date: 05/15/89

. Question Format: W- Question Type: S Sub' ect Area: j CONTAINMENT VENTILATION Task Number: C1802 COT,.P2303 COT Terminal Learnine obiective:

C1802 COT During emergency operations and given a copy of EOP-0 assess the response of the containment ventilation system to a safeguards. actuation signal in accordance with EOP-0,

" Reactor Trip or Safety Injection".

P2303 COT During refueling operations and given a copy of RP-1C operate the refueling manipulator in accordance with RP-1C,

" Refueling".

Question: Instructor Use Only Explain whether or not the cavity cooling fans (lW4A and B) should be in operation at this time.

(Prior to the event the cavity cooling fans (1W4A and B) were running.)

Points Earned

~

Question No.: 051-05-002A Page 2

. Answer: Instructor.Use only They'should-not be operating..(.2 pts.)'The cavity '

coolina fans are powered from B31 which is strioned via the B03/B04-lockout device during an SI. (.5 pts.)

ST-88-09 547 Additional Information:

a- nn --

Technical Referenegg:

Electrical Master Data Book Logic Sht. 9 Items to be Included with Ouestion: None Time VaEidation: 4.20 Recual cvele: N/A K/A

Reference:

System: 013 Mode: 000 Number: K4.11 Ratings: RO: 3.2 SRO: 3.8 l

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Question-Number: 055-02-084A Point Value:

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0.9 Revision Number: -2 Approval Date: 05/15/89 Question Format: W QucwHn.7 Type: S Subject Area: REACTOR COOLANT SYSTEM

' Task' Number: CO215 COT Terminal Learnine obiective:

CO215 COT During all modes of operation and given a copy of AOP-1A,-

diagnose leakage from the RCS in accordance with AOP-1A,

" Reactor Coolant Leak".

Question: Instructor Use Only.

Analyze plant indications.using the appropriate procedures and determine if a steam generator tube

' rupture has occurred.

a. What specific plant indications / parameters will you reference during your analysis?

(.3 pts.)

b. What is the conclusion of your analysis?

(.6 pts.)

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l-Points Earned

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l (Question No.: 055-02-084A Page 2.-

Answer: Instructor Use'Only

a. Condenser air eiector radiation alarms l- (RE-215, 225) (.1 pts.)

l S/G blowdown radiation alarms

-(RE-219, 222) =(.1 pts.)

Main steam line radiation alarms 1,

(RE-231, 232) (.1 pts.)

l b. Eg S/G leak or rupture.- (.6 pts.)

ST-88-09 557 ,

Additional Information:

Technical

References:

AOP-1A EOP-0 EOP-3 .

-AOP-3A Items to be Included with Ouestion: None Time Validation: 2.40 Recual Cycle: N/A K/A

Reference:

System: 000 Mode: 009 Number: EA2.02 Ratings: RO: 3.5 SRO: 3.8 s

___u.__ _ _ . _ _____.-_____m_______________._-_ _

y l- G '- 6 Question Number: __051-03-007A Point Value: ,1.0 F Revision Number: 2- Approval-Date: 05/15/89 Question Format: W Question Type: C Subject Area: SAFETY INJECTION SYSTEM

' Task Number: P0610 COT Terminal Learnina obiective:

P0610 COT During an~ accident. situation operate SI system (HPSI) in the recirculation mode prior to expiration of the RWST level.

Question: Instructor Use Only-Assume the RCS fault worsens and the SI system must be realigned to the containment sump. To do this transfer, the operator transitions from EOP-1

(" Loss of_ Reactor or Secondary Coolant") to EOP-1.3

(" Transfer to Containment Sump Recirculation") and completes the realignment to the containment sump.

Given: RWST level is 8%;

Containment pressure is 9 psig; containment sump level is 50 inches; and RCS. pressure is 210 psig.

. Ten hours after the accident, what is the proper line up for tha low head (RHR) and high head (SI)

. systems? (Choose one answer.)

a. RHR pumps suction from containment sump; SI pumps suction from.RWST; and injection flow through core deluge and cold legs.

b. RHR pumps suction from containment sump; SI pumps suction from RHR discharge; and injection flow through cold legs only.

c. RHR' pumps suction from containment sump; SI pumps suction from RHR discharge; and injection flow through core deluge only.

. d. RHR pumps ruction from containment sump; SI pumps suction from RHR crossconnected to SI system; and injection flow through ccre deluge.

a. RHR pumps suction from containment sump; SI pumps suction from RHR discharge; and i

injection' flow through core deluge and cold L legs. ,

Points Earned l;

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n Question No.: ' 051-03-007A Page 2 Answer:- Instructor Use Only

e. (1.0' pts.)

ST-88-09 545 Additional Information:

Technical

References:

EOP-1 EOP-1.3

- Items'to be Included with Ouestion: None Time Validation: 6.40.

Requal Cycle: N/A K/A

Reference:

- System: 060 Mode: 020 Number: A4.02 d

4 Question Number: 053-01-013A Point Value: 1.0

- Revision Number: 2 Approval Date: 05/15/89 Question Format: W Question Type: C Subject Area: ROD CONTROL SYSTEM Task Number: C0105 COT Terminal Learnina Obiective:

C0105 COT During normal power operations with the rod control system in automatic assess the response of the rod control system to change plant conditions. Assessment of expected rod speed and direction as the Tref - Tavg error exceeds 1.5 Dag F in either polarity is required, without error.

Question: Instructor Use only Prior to the start of this event, control rods were positioned with bank D at 213 steps and Tavg matched Tref. Core burnup is approximately 4500 MWD /MTU. Considering only the effects due to the turbine runback, assuming the plant is stable at 95% turbine power, what would be the final rod position?

a. 228 steps

b. 190 steps

c. 175 steps

d. 160 steps

e. 145 steps Points Earned

u o .

.'Quacticn No :

. 053-01-013A Page 3

- Answer: Instructor Use only'

' b.- '(1.O pts.)

. ST-88-09 549

' Additional Information:

Technical

References:

6 ROD Book' TRHB 13.8 Items to be Included with Ouestion: None Time Validation: 4.00

' Reaual cvela: N/A K/A

Reference:

System: 001 Mode: 000 Number: K5.29 Ratings:- RO: 3.7- SRO: 3.9 e

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Question Number: 031-03-137A Point Value: 0.6 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: SAFETY INJECTION SYSTEM Task Kumber: C0615 COT Terminal Learnina obiective:

C0615 COT During emergency or accident conditions the operator must be able to recognize conditions for terminating or resetting SI as identified in the Emergency Operating-Procedures.

Question: Instructor Use only Assume that RCS pressure is stable at 1650 psig and you have transitioned to EOP-1.1, "SI Termination." SI has been reset and the safecruards eauiement has been secured, RCS pressure starts to decrease rapidly.

Explain whether or not a manual initiation of safety injection will cause the RHR pumps to resequence on (restart)?

i

-1 Points Earned

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' Question No.: 031-03-137A Page 2 Answer: Instructor Use Only i

The RHR pumps will restart. (.4 pts.) 'A manual SI will resequence all safeguards equipment once the SI signal is reset. (.2 pts.)

F ST-88-09 536 Additional' Information:

Technical'

References:

1 Logic Sht. 7 Items to be included with Ouestion: None Time Validation: 6.00 Reaual cycle: N/A K/A

Reference:

System: 006 .

Mode: 050 Number: A4.01 b

I r: - _ _ - _ _ _ - - _ - _ _ _ _ _ _ - - _ _ - _

Question Number: 031-03-057A Point Value: 0.8 i Revision Number: 1. . Approval Date: 05/15/89.

Question-Format:' W Question Type: C Subject' Area: AC ELECTRICAL DISTRIBUTION SYSTEM' Task Number: C4 4 COT Terminal Learnina Obiective:

.C4304 COT During an emergency or accident condition assess the response of the diesel generators to an undervoltage condition on a safeguards bus in that.the DG aust function to provide electrical power to its associated safeguards loads.

Question: Instructor Use only Assume that under the present plant conditions, a loss of AC occurs and busses A05 and A06 de-energize. How will the emergency diesels and safeguards equipment respond to this event?

(Choose one answer.)

a. SI pumps will strip on undervoltage.

I 480 volt equipment will strip on undervoltage.

Emergency diesels will re-energize A05 and l A06. SI pumps will resequence on.

l 480 volt equipment will resequence on.

b., SI pumps will not trip and ride the bus.

480 volt equipment will strip on undervoltage.

Emergency diesels will re-energize AOS and A06. SI pumps will continue to ride'the bus when A05 and A06 bus voltage is restored.

480 volt equipment will resequence on.

c. SI pumps will strip on undervoltage.

480 volt equipment will strip on undervoltage.

Emergency diesels will re-energize A05 and A06. SI pumps will resequence on.

480 volt equipment will be locked out and not resequence on.

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d. SI pumps will not trip and ride the bus.

l 480 volt equipment will not trip and ride the bus. Emergency diesels will re-energize A05 and A06 picking up the loaded bus. .

1 Points Earned l

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l huestionNo.: 031-03-057A Page 2 ,

Answer: Instructor Use Only

b. (.8 pts.)

ST-88-09 538~

Additional Information:

Technical

References:

Logic Sh. 6, 7, 8 TRHB 10.6 Items to be Included with Ouestion: None Tina validation: 2.70 Recual cycle: N/A K/A

Reference:

~ Systam: 062 Mode: 000 Number: K3.02

, Ratings: RO: 4.1 SRO: 4.4 e

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Question Number: ' 055-02-031A Point Value: 1.0 Revision Number: 2- Approval,Date: 05/15/89

--Question Format:' W-Question Type: C Subject Area: . STEAM DUMP.. CONTROL SYSTEM 2 Task Number: C2806 COT Terminal Learnina obiective: )

i- C2806 COT During normal power operations, diagnose malfunctions of' the' condenser steam dump system prior to causing a reactivity addition to the RCS. )

i j

Question: Instructor Use Only i

., ' Assume that after receiving the reactor trip, the fast bus transfer did not occur. Given that no-operator action was taken, what is the response of the condenser steam dump system'and its effect on the'RCS? '(Choose one answer.)

a.- The condenser steam dump system will operate as designed.and control RCS temperature at 547*F.

b. The condenser steam dump system will operate as designed and_ control RCS temperature at 551*F.

c. The condenser steam dump system will modulate-closed prematurely, and: remain closed, resulting in a RCS heatup to > 547'F.

-d. The condenser' steam dump system will operate and remain open, cooling the RCS down to

< 547'F until the operator switches to steam pressure control.

a. The condenser steam dump system will not '

operate'at all, and the RCS Tave will increase

} to'552 0 F and lift the steam generator l atmospheric steam dump valves.

s Points Earned

[ sc Question'.No.: '055-02-031A Page 2 Answer: Instructor Use Only e.- (1.0 pts.)

ST-88-09 559 Additional Information:

Technical

References:

I EOP-0.2 Logic Sht. 17 TRHB 13.9 Items to be Included with Ouestion: _None Time Validation: 1.40 Reaual evele: N/A K/A

Reference:

System: 041 Mode: 020 Number: K3.02 Ratings: RO: 3.8 SRO: 3.9

b. _ - - - . _ _ _ _ - _ _ . - _ _ _ - _ _ _ _ _ _ _ _ - _ _

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)

l Question Number:~'055-02-032A Point value: 0.6 l '

' Revision Number: 1 ' Approval Date: 05/15/89 Question Format: W .

Question Type:- S AUXILIARY FEEDWATER SYSTEM.

.. Subject Area:

Task Number: C4207 COT q i

{

. Terminal Learnine Obiective:- ]

C4207 COT During abnormal operating conditions, diagnose conditions .

I n requiring AFW automatic actuation without error.

Question: Instructor Use Only Assume that events in this scenario occurred with the exception that RCS pressure had never decreased below 1780 psig. What auxiliary feedwater pump (s) should be running in this situation? (Assume Unit  ;

1.) l l

Points Earned

.1. ._ . _ . _ . . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _

)

P Question No.: 055-02-032A Page 2 i

Answer: Instructor Use only l Unit 1 turbine driven AFW pump (1P29). (.2 pts.)

"A" mo?.or driven AFW pump-[P38A]. (.2 pts.)

"B" motor driven AFW pump (P38B]. (.2 pts.)

ST-88-09 561 I l

Additional Information:

' Technical

References:

Logic Sht. 20 TRHB 11.4 Items to be Tncluded with Ouestion: None Time Validation: 1.50 Recual Cycle: N/A K/A

Reference:

System: 013 Mode: 000 Number: K4.04 Ratings: RO: 4.3 SRO: 4.5 I

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j Question Number: 052-02-002A ' Point Value: 0.5 l

Revision Number: 1 Approval Date: 05/15/89 Question Format: W- Question Type: S Subject Area: REACTOR PROTECTION SYSTEM 1

Task Number: C1102 COT I

Terminal Learnino Obiective:

C1102 COT During all plant operating conditions involving closed 1 reactor trip breakers, recognize conditions requiring reactor protection actuation. Recognition of all plant parameters that will cause a reactor trip as well as their corresponding setpoints are required, without error.

Question: Instructor Use only What signal caused the turbine runback?

l Points Earned i

I L

p' 4 .

Question No.: 053-02-002A Page 2 l

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Answer: Instructor Use only l

OT Delta T (,5 pts.)

ST-88-09 l

552 Additional Information:

Technical

References:

TS 15.2.3-Logic Sht. 16 STPT'4.2 Items to be' Included with Ouestion: None Time Va'11dation: 3.80 Recual Cvela: N/A K/A

Reference:

System: 045 Mode:' 000 Number: K4.12 Ratings:= RO: 3.3 SRO: 3.6 l

. , )

Question Number: 053-09-010A Point Value: 1.0 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: STEAM. DUMP CONTROL SYSTEM-Task Number: C2810 COT Terminal Learnina Obiective:

C2810 COT During power operations, with the mode selector switch in automatic, assess the response of the condenser steam dump system to a load rejection. Assessment of the control system's ability to maintain Taverage at or near the Treference value is required without error.

Question: Instructor Use only All controls were in auto / normal prior to the start of this event.

a. After the turbine runback to 95%, explain whether or not the condenser steam dump system operated (i. e., dump steam) prior to the reactor trip and safety injection? (.5 pts.)

b. Explain how the condenser steam dump system would have responded had the rod control system been in manual. (.5 pts.)

Points Earned J

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s Qu'estion No.: 053-09-010A~ Page 2 Answert Instructor Use Only

a. The S/D system didn't arm for enerate).

(.5 pts.) There must be a -10% load decrease in 120'sec. to arm the steam dumps; the turbine runback was only 5%.

b. The S/D system would not arm. (.5 pts.)

due to the turbine runback of only 5% vice the needed 10% in 120 sec. The fact that a larger Temperature error would be generated will not affect operation of the steam dumps since they're not armed.

ST-88-09 555 Additional Information:

Technical

References:

Logic Sht. 17 TRHB 13.9 STPT 5.2 Items to be Included with Ouestion: None Time validation: 3.20 Regual Cycle: N/A -

K/A

Reference:

System: 041 Mode: 020 Number: A3.02 Ratings: RO: 3.3 SRO: 3.4 1

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Section 3 s

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l LIMITS AND CONTROLS KMGUp 9

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LIMITS AND CONTROLS i

OUESTION NITMBER POINTS TOTAL TIME TOTAL 053-01-039A 0.5 0.5 1.0 1.0 053-01-040A 0.8 1.3 5.3 6.3 053-01-049A- 1.0 2.3 4.8 11.1

,053-02-034A 1.0 3.3 5.1 16.2 053-04-028A 0.6 3.9 2.5 18.7 051-02-026A 0.5 4.4 2.4 21.1 051-02-037A 0.5 4.9 4.0 25.1 051-03-015A 0.8 5.7 3.4 28.5 051-01-045A 1.0 6.7 3.6 32.1 052-02-010A 0.8 7.5 1.1 33.2 055-01-026A 1.0 8.5 3.7. 36.9 055-02-002A 0.7 9.2 5.5 42.4 055-02-051A 0.8 10.0 2.5 44.9 055-02-054A 0.8 10.8 1.8 46.7 055-02-078A 1.1 11.9 3.6 50.3 031-03-001A 0.8 12.7 3.2 53.5 031-03-090A 0.7 13.4 6.1 59.6 031-03-096A 0.8 14.2 4.2 63.8 031-03-119A 1.0 15.2 2.7 66.5 043-02-010A 1.2 16.4 4.2 70.7 057-02-019A 1.0 17.4 3.0 73.7-053-01-048A 1.0 18.4 5.0 78.7 055-01-027A 1.0 19.4 5.5 84.2 031-01-005A 0.7 20.1 3.5 87.7 l

Question Number: '053-01-039A Point Value: 0.5 g Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: ROD CONTROL SYSTEM Task Number: C0102 COT Terminal Learnina obiective:

C0102 COT While operating with rod motion possible from either manual l

or automatic means, assess causes of interlocks, permissives and automatic functions associated with the rod control system without error.

Quution: Instructor Use only When selected, which position (s) of the rod control l bank selector switch is the bank overlap program in effect?

Points Earned

h d. .

)

e., a j

l

. Questi on No.: 053-01-039A Page 2 Answer: Instructor Use only Automatic and manual (.25 pts. each)

Additional Information:

iwthnical

References:

AOP-6B step 7.5.A LP1547 Rod control System l

c Items to be Included with Ouestion: None l

L Time Validation: 1.00 Requal Cvele: N/A K/A

Reference:

System: 001 l Mode: 000 L Number: K4.02

Ratings

RO: 3.8 SRO: 3.8 l

Question Number: 053-01-040A Point Value: 0.8 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: ROD CONTROL SYSTEM Task Number: C0105 COT, P0106 COT Terminal Learnina Obiective:

C0105 COT During normal power operations with the rod control system in automatic assess the respanse of the rod control system to change plant conditions. Assessment of expected rod speed and direction as the Tref - Tavg error exceeds 1.5 Deg F in either polarity is required, without error.

P0106 COT During normal plant operations with the rod control system in either the manual or automatic mode, monitor the rod control system to determine if rods move in the correct direction and at the proper speed in response to power and temperature, without error.

Question: Instructor Use only

1. At what speed would you expect rods to be moving with an indicated temperature of +2*F on the Tave - Tref deviation meter? (.6 pts.) -

2. In what direction would the rods be moving?

(.2 pts.)

Points Earned

4

. Question No.:- 053-01-040A- Page 2 9

Answer: Instructor Use only 9

l'. 8 steps per-min. (.6 pts.)

2. In~ (.2 pts.)

- Additional-Information:

Technical

References:

Setpoint Document.section 5.1~

-7J 1547 Rod Control System

' Items-to be Inclu'ded with'Ouestion: None f . Time Validation: 5.30 Recrual Cycle: . N/A q.

K/A

Reference:

System: 001-Mode: 000 Number:

GO7 9

e e

t

-js1&, J Point Value: t;t" 8 Question Number: 053-01-049A Revision Number: 2 Approval Date: 05/17/89 Question Format: W Question Type: M Subject Area: ROD CONTROL SYSTEM' Task Number: C0102 COT, C0105 COT Terminal Learnina Obiective:

C0102 COT While operating with rod motion possible from either manual or automatic means, assess causes of interlocks, permissives and automatic functions associated with the rod control system without error.

C0105 COT During normal power operations with the rod control system in automatic assess the response of the rod control system to change plant conditions. Assessment of expected rod speed and direction as the Tref - Tavg error exceeds 1.5 Deg F in either polarity is required, without error.

Question: Instructor Use Only When going from low power to normal power, the operator places the rod control system in automatic at 11% power. At this power level, which one of the following statements is FALSE?

a. The system will respond to all automatic insertion signals.

b. The system will respond to all automatic withdrawal signals.

c. The sy.? tem will respond to all automatic withdrawal signals if power level is increased to greater than 15% power.

d. The system should remain in manual at 11%

power.

1 Points Earned

.s: .

Page 2 l Question.No.: .053-01-049A  :

i y

/

Instructor Use Only Answer:

c.P,

b. ( 1'. 0 . pts . )

Additional Information:.

Technical

References:

-Logic drawing section 5.1 LP-1547 Rod Control. System Items to be Included with Ouestion: None Time ValidatioD: 4.80 P.aggal evele:. N/A K/A

Reference:

System: 001 Mode: 000 Number: K4.03 Ratings: RO: 3.5 SRO: 3.8 l

t I

6 . la Question Number: 053-02-034A Point Value: 1.0 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: REACTOR PROTECTION SYSTEM Task Number: C1104 COT, C1107 COT Terminal Learnine obiective:

C1104 COT During all modes of opcration with the reactor trip breakers closed, identify all causes on interlocks, permissives and automatic functions associated with operation of the reactor protection system, without error.

C1107 COT When operating in the source or intermediate range of nuclear instrumentation, assess the effect of bypassing a trip condition in the reactor protection system, with regard to the trips which may be bypassed and the protection that remains after the bypass has been made, without error.

Question: Instructor Use Only During Unit i reactor startup, the operator notices that' intermediate range channel N-35 has failed to start indicating. N-36 has been tracking properly with.both source range instruments. The Duty Shift Superintendent directs the operator to place the

" Level Trip" switch on N-35 in the " BYPASS" position.

a. What two functions does the "Laval Trip" switch serve when it is placed in " BYPASS"?

(.5 pts.)

b. Explain whether or not the startup is allowed

! to continue. (.5 pts.)

l l

l l

Points Earned

l l' Qilestion No. : 053-02-034A Page 2 l

Answer: Instructor Use only

a. The Intermediate High Flux Trip (.25 pts.)

and the Intermediate Range Rod Stop (.25 pts.)

is bypassed for that channel,

b. The startup may continue per criticality checklist / Tech. Specs./OP-1B (only require 1 operable intermediate range channel) (only one reference is required) (.5 pts.)

302 Additional Information:

Technical

References:

TRHB 13.3 T.S. 15.3.5 Items to be Included with Ouestion: None Time Validation: 5.10 Recual cvele: N/A K/A

Reference:

System: 012 Mode: 000 Number: K6.04

' Question Number: 053-04-02BA Point Value: 0.6 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S 4

Subject Area: ' REACTOR COOLANT SYSTEM Task Number: C0919 COT Terminal Learnina Obiective:

C0919 COT During normal power operations with the control range of the pressurizer level control system, identify 80% of the causes of interlocks, permissives, and automatic functions associated with pressurizer pressure control system.

Question: Instructor Use Only Unit 1 is operating at 30% power with'all controls functioning normally. 1P2A charging pump is in manual at 20 gpm, 1P2B charging pump is in auto and one 40 gpm letdown orifice is in use. For the situations below, indicate what initial effect (increase, decrease, no change) each failure will have on actual pressurizer level:

a. One RTD bypass manifold Tcold channel fails high. (.2 pts.)

b. Pressurizer level channel LI-433 fails high.

(.2 pts.)

c .- Loss of control air to charging pump 1P2B.

(.2 pts.)

Points Earned

n. -

q

ik -

1 Question No.: '053-04-028A Page 2 -j

-i

' Answer: ' Instructor Use only' -

a. Increase -(.2 pts.) l

b. No change (.2 pts.)

.c. Decrease (.2 pts.) ;j 093-Additional-Information:

Technical

References:

TRHB_13.6 pg. 3-5 Logic 883D195 Sht._18.

Items to be Included with Ouestion: None Time Validation:: 2.50 Regnal Cycle:. N/A-K/A

Reference:

. System: 011 Mode: 000 Number: K1.02 Ratings: RO: 3.7 SRO: ' 3.8 I

. Question Number: 051-02-026A Point Value: 0.5.

Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: CHEMICAL & VOLUME CONTROL SYSTEM Task Number: C0421 COT Terminal Learniner Obiective:

C0421 COT During all modes of operation assess the affect on the RCS due to changing letdown domineralizer configuration without error.

Question: Instructor Use Only on April 1 Chemistry requests the standby mixed bed domineralizar be placed in service. It was last in service-on February 15. What (if any) actions are required prior to placing the standby mixed bed domineralizar in service?

l Points Earned

T:.

-Question No.:

051-02-026A Page 2~

Answer: Instructor Use'only The standby mixed bed domineralizar must be-flushed and samoled prior.to placing it in service. (.25 pts. for flushed and. 25 pts. for sampled)

Alternate answer: It must be boron equilibrated.

(full credit for this answer) 193 Additional Information:

Technical

References:

OP-5D Itama to be Included with ouestion: None Time Validation: 2.40 Recual Cycle: N/A K/A

Reference:

System: 004 -

Mode: 020 Number: A2.13 Ratings: RO: 3.4 SRO: 3.9

p-

• e

-Question Number: 051-02-037A Point Value: 0.5 Revision Number: 1: Approval Date: 05/15/89 Question Format: -W Question Type: S Subject Area: CHEMICAL & VOLUME CONTROL SYSTEM Task Number: C0403 COT,1C0423 COT Terminal Learnina obiective:

C0403 COT During all modes of operation, assess the affect of a safeguard actuation signal on CVCS without error.

C0423 COT During all modes of operation identify causes of the.

interlocks, permissives, and automatic functions associated with CVCS prior to operation.

Question: Instructor Use Only

a. Following.a containment isolation signal, explain how the letdown orifice isolation valves (AOV 200 A, B, & C) recieve an automatic shut signal. (.25 pts.)

b. With a pressurizer level of lit, explain how the letdown orifice isolation valves (AOV 200 A, B, & C) recieve an automatic shut signal.

(.25 pts.)

Points Earned

duestionNo.: 051-02-037A Page 2 q

Answer: Instructor Use Only i i

a. A containment isolation signal closes Letdown containment Isolation valves (cv 371A and 3 CV 371) either sands a signal (via limit '

switch) to close the orifice valves.

(.25 pts.)

b. A low pressurizer level closes Letdown Isolation valve (LCV-427) which sends a signal (via limit switch) to close the orifice valves. (.25 pts.) '-

236 Additional Information:

Technical

References:

Logic 883D195 Sht. 18 Sht. 21 "tems to be Included with Ouestion:

None Time validation: 4.00 Reaual Cvela: N/A K/A References System: 004 Mode: 000 Number: K4.04 Ratings: RO: 3.2 SRO: 3.1 1

O

____m__________--__-______-___---------------

! e,

- Question Number: 051-03-015A Point Value:'~0.8 Revision Number: 1 Question Format:- W Approval Question Type: Date: . S05/15/89 Subject Area: ' RESIDUAL HEAT REMOVAL SYSTEM Task Number:: C0509 COT-Terminal Learnina Obiective:

C0509 COT During all modes of operation identify causes of

. interlocks, permissives, automatic functions associated-with the RER system without error.

Question: Instructor Use Only A-large break IOCA has occurred. RWST level has

' dropped below 60%. .The'RHR and SI systems are

- being prepared for containment sump recirculation according to EOP-1.3, " Transfer to Containment Sump Recirculation." Prior to opening valves SI-850A and SI-850B (containment sump B hydraulic isolation

- valves) in Step 5 of EOP-1.3,.the DSS directs valves SI-851A and SI-851B (containment sump isolation valves) be cycled. Explain whether or not SI-851A and SI-851B will cycle.

l Points Earned

duestionNo.: 051-03-015A Page 2  ;

Answer: Instructor Use Only

)

1 l

851A and B can not be opened unless 897's (A or B) is shut. (.8 pts.)

304 Additional Information:

Technical

References:

EOP 1.3 TRHB 10.8 Items to be Included with Ouestion: None Time Validation: 3.40 Recual cvele: N/A K/A

Reference:

System: 006

. Mode: 000 Number: K4.11 w _ _ _ __ _ _ _

c. .

++

J

'QQastion Number: 051-01-045A Point Value: -1.0 Revision Number: 1- Approval Date: 05/15/89 Question Format: -W Question Type: C j

Subject Area: REACTOR COOIANT SYSTEM j i

' Task Number: CO211 COT Terminal Learnina Obiective:

CO211 COT '

During all modes of operation' analyze the affect of a-LOCA on the RCS to determine severity and location.

Question: Instructor Use only ]

In comparison to a water space leak of the same

~

size, which one of the following describes the effect of a vapor steam leak on pressurizer pressure'and/or level?

In a vapor space'1eak

a. pressurizer pressure'will decrease faster than in a water space leak.

b. pressurizer level will decrease faster than in water space leak.

c. pressurizer pressure will decrease the same as in a water space leak.

d. pressurizer level will decrease the same as in a water space leak.

e. - both pressurizer pressure and level will decrease the same as in a water space leak.

Points Earned

n;;pOC ;,:

l 1

Qu2Gtien No.:

1 051-01-045A- Page 2 Answer:- Instructor Use Only-

a. (1.0 pts.)

293 Additional Information:

Technical

References:

LP-1539.

Items to be Included with Oue'stion: None

-Time Validation

• 3.60-Recual Cvele: N/A K/A

Reference:

System: 002 Mode: 000 Number: K1.08

' Ratings:

RO : . 4.5 SRO: 4.6

. Question Number: 052-02-010A Point Value: 0.8 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: C Subject Area: STEAM GENERATOR BLOWDOWN SYSTEM Task Number: C2401 COT, C2603 COT i

Terminal Learnina Obiective: I C2401 COT During power operation ASSESS lineups to verify proper operation of the steam generator in accordance with proper-operating parameters identified on operating logs.

C2603 COT Concerning the automatic operation of the steam generator blowdown system, IDENTIFY causes of interlocks, permissives and automatic functions associated with the steam generator blowdown system as identified in LP0037.

Question: Instructor Use Only Which one of the following conditions would HQI result in closure of steam generator blowdown valves (CV-2042 and CV-2045)?

a. Placing control switches for steam generator blowdown valves (CV-2042 and CV-2045) to shut.

b. A high flow condition (>30 kilopounds) in the blowdown lines detected by flow elements FE-5940 or FE-5941.

c. A loss of instrument air to the steam generator blowdown valves (CV-2042 and CV-2045).

d. A high pressure condition (>50 psig) in the blowdown tank detected by pressure switch l PS-5955.

l l

Points Earned l

Q'estion u No.: 052-02-010A Page 2 Answer: Instructor Use only

b. (.8 pts.)

130 Additional Information:

Technical References

• TRHB 11.1 M-201 Sh 3 Items to be Included with Ouestion: None Time Validation: 1.10 Recual Cvele: N/A K/A

Reference:

System: 035 Mode: 010 Number: K4.03 1

Question Number: 055-01-026A Point Value: 1.0 Revision Number: 2 Approval Date: 05/15/89 Question Format: W Question Type: E Subject Area: PRESSURIZER PRESSURE CONTROL SYSTEM Task Number: C0906 COT Terminal Learnine Obiective:

C0906 COT During a normal plant heatup/cooldown analyze the effect on the pressurizer pressure control system caused by a temperature change during solid plant operations to avert a pressure transient on the RCS.

Question: Instructor Use Only The plant is solid on RHR at 200*F and 325 psig.

PCV-135 will not control properly in automatic and has been placed in manual. Explain how a reduction (2,30% ) in service water flow to the CCW heat exchangers affect the primary system temperature and pressure? (Include how the CCW and RHR systems are affected.)

l Points Earned i i

-Question No.: 055-01-026A Page-2 Answer: Instructor Use Only A' reduction in SW flow will increase CCW temperature (.25 pts.) which in turn increases RHR temperature (.25 pts.) which increases primary system temperature (.25 pts.) and pressure (.25 pts.) (Also acceptable: lift relief valve or PORV or bring in the " low temperature overpressure" alarm)

Additional Information:

Technical

References:

LP 1618 TRHB 10.7, 10.9 Items to be Included with Ouestion: None Time Validation: 3.70 Recual Cycle: N/A K/A

Reference:

System: 010 Mode: 000 Number: A1.04 Ratings: RO: 3.6 S.RO: 3.8 i

l

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

Question Number: 055-02-002A Point Value: 0.7 1 Revision Number: 1 Approval Date: 05/15/89 Question Format: W . Question Type: S ,

Subject Area: RESIDUAL HEAT REMOVAL SYSTEM

]

Task Number: P0515 COT Terminal Learnine obiective:

P0515 COT During all modes of operation and given a copy of Technical Specifications, respond to loss of RHR-during normal operations in accordance with Technical Specifications 15.3.3, " Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and containment spray". j I

Question: Instructor Use Only Unit 1 is at 100% power. At 0300 on December 12, "A" RHR pump is declared inoperable and repairs initiated. At 1200 on December 13, Maintenar.ca reports the "A" RHR pump repairs cannot be completed before 1200 on December 15. What actions, if any, should be taken regarding Unit 1 operations?

1 Points Earned

Quocticn No.:: 055-02-002A Page 2 Answer:- Instructor Use Only If the "A" RER pump is not restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of being declared inoperable the unit must be placed in hot shutdown. Since the pump will not be restored before 1200 on December 15,_this is greater than the additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> allowed by Tech. Specs so the reactor shall'be maintained in a ,

condition with the reactor coolant temperatures .i between 500 and 350DF. (Also acceptable are I words to the effect as stated in TS 15.3.3.A.3)

~

(.7 pts.)

773

-Additional Information:

Technical

References:

T.S. 15.3.3.A.1 T.S. 15.3.3.A.3 Items to be Included with Ouestion: None Time validation: 5.50 Reaual Cvele: N/A K/A

Reference:

System: 005 Mode: 000 Number: K3.01 Ratings: RO: 3.9 SRO: 4.0 l

i l

Que.stion Number: 055-02-051A Foint Value: 0.8 Re'ision Number: 2 Approval Date: 05/15/89 Question Format: W Question Type: C Subject Area: EMERGENCY TASKS

. Task Number:- C7017 COT Terminal Learnina Obiective:

C7017 COT During all modes of operation and given a copy of AOP-10A, diagnose control room inaccessibility in accordance with AOP-10A, " Control Room Inaccessibility".

Question: Instructor Use Only Both units are at 100% power. A fire in the Unit 1 side of the Control Room has required Control Room evacuation.

Which one of the following statements is trum?

a. RCP's should be stopped on Unit 1 and left running on Unit 2.

b. Safety Injection is to be manually initiated on Unit 1, then unnecessary equipment will be locally secured.

c. All technical specifications are to be followed just as they would be under normal operating conditions.

d. Unit 1 and Unit 2 containments shall be isolated via containment isolation.

Points Earned

Quc0 tion No. : 055-02-051A Page 2 1

- Answer: Instructor Use Only

d. (.8 pts.) )

054 Additional Information:

Technical

References:

AOP-10A Items to be included with Ouestion: None Time Validation: 2.50 Reaual cvele: N/A K/A

Reference:

System: 000 Mode: 067 Number: EA2.13 Ratings: RO: 3.3 SRO: 3.4 C- _ _ _ _ . _ _ _ _ _ - - _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

. o-

m. 4 Question Number:. 055-02-054A Point Value: 0.8 Revision Number: 1 Approval Date: 05/15/89' -

Question Format: W Question Type: C -

Subject Area: ROD CONTROL SYSTEM Task Number: C0108 COT Terminal Learnincr obiective:

C0108 COT During all modes of operation, assess the response of the I rod control system to a malfunction of the turbine impulse pressure detector without exceeding rod insertion limits or Technical Specification limits.

Question: Instructor Use Only Unit 1 is operating at 100% power. Control bank D is at 213 steps with a previously failed high turbine first stage pressure transmitter (PT-485).

Which one of the following statements is 1DLt?

a. The control rods can be stepped in, but not out, in the manual mode.

b. The control rods can be stepped in and out in the manual mode.

c. The control rods have an auto rod stop in effect, prohibiting in and out movement in the auto mode.

d. The control rods can only be stepped in bank select.

Points Earned

• e Question No.: 055-02-054A Page 2 Answer: Instructor Use only

b. (0.8 pts.)

134 Additional Information:

Technical

References:

TRHB 13.8, Logic Print Sht. 16 Items to be Included with Ouestion: None Time Validation: 1.80 Recual Cvele: N/A K/A

Reference:

System: 001 Mode: 050 Number: K5.01 Ratings: RO: 3.3 SRO: 3.6 e

Qizestion Number: 055-02-078A Point Value: 1.1 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: CHEMICAL & VOLUME CONTROL SYSTEM Task Number: C0407 COT Terminal Learnine Obiective:

C0407 COT During cold shutdown conditions, assess the effect on letdown caused by a loss of RHR during rolid plant operation prior to losing letdown.

Question: Instructor Use only Unit 1 is operating in a solid condition with 1A RHR pump operating and supplying letdown via RH-715C (RHR to letdown cross-connect) and CV-369A (RHR letdown). Valve RH-700 (RHR hot leg suction valve) is inadvertently closed. Explain any effect this would have on RCS pressure; include the initial response, if any, of PCV-135.

l l

l Points Earned

e' O Question No.: 055-02-078A Page 2 Answer: Instructor Use only RCS uressure would increase (.5 pts.) due to a decrease in letdown flow (.2 pts.) and charcina flow beine maintained by the charging pump.

operating in manual. (.2 pts.) The decrease in letdown flow is due to the suction of the RHR numes beins isolated and PCV-135 closina down to maintain pressure. (.2 pts.)

312 Additional Information:

Technical

References:

OP-3C TRHB 10.6 TRHB 10.7 Items to be IncJuded with Ouestion: None Time Validation: 3.60 '

Recual Cvele: N/A K/A

Reference:

System: 004 Mode: 010 Number: K1.01 Ratings: RO: 3.4 SRO: 3.9 l-f.

L - __ - _ - -- - _

..< s Question Number: 031-03-001A Point Value: 0.8 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: EMERGENCY TASKS Task Number: C7028 COT Terminal Learnina Obiective:

C7028 COT During an accident or emergency condition involving a steam generator recognize multiple casualties so they may be identified and their priorities established according to EOP, Emergency Contingency Actions.

Question: Instructor Use Only With Unit 2 at 75 power, a safety injection and reactor trip occurs, and the immediate actions of E0P-0 " Reactor Trip or Safety Injection", are completed. The following statements summarize key indications:

1. The RCS is losing inventory, > 200 gpm.

2. One steam generator is depressurizirag uncontrollably.

3. Air ejector radiation alarms (2RE215) indicate a steam generator tube rupture.

w

4. DTA notifies you the critical safety functions status trees indicate a transition to H-5

" Response to Steam Generator Low Level,"

(yellow condition).

Which one' statement indicates the condition that must be given first priority?

Points Earned

-Question No.: 031-03-001A Page 2 Answer: Instructor Use only Statement 2 (0.8 pts.)

078 Additional Information:

Technical

References:

EOP-0, Reactor Trip or SI EOP-2 " Symptoms or Entry Conditions" Items to be Included with Ouestion: None Time validation: 3.20 Recual Cvele: N/A K/A

Reference:

System: 000 Mode: 040 Number: Gil a

Question Number: 031-03-090A Point Value: 0.7 I Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: EMERGENCY TASKS Task Number: C7009 COT Terminal Learnine Obiective:

C7009 COT From any plant condition following a reactor trip or safety injection actuation recognize the critical safety functions by verifying that all safety related parameters are satisfied in accordance with the critical safety function status trees.

Question: Instructor Use Only Following a reactor trip from 98% power, the operator notes the following information:

RCS Secondarv A B PZR Level 10% SG Level % 10 8.5 PZR Pressure 1885 psig SG Pressure psig 1010 1010 THWR 588 0 F AFW gpm 95 110 TCWR 548 0 F RCP's off Rx Core' Containment Thernoccuples 590 CF CTMT Pressure 1.0 psig Subcooling 36 0F Sump "A" Level 80%

Power 1.0E-9 Amps RE-126/127/128 2.0E-1R/HR Explain whether or not critical safety functions are satisfied.

Points Earned

Question No.: 031-03-090A Page 2 Answer: Instructor Use only critical safety functions are not satisfied (.5 pts.) because pressurizer level is low (<12%).

(.2 pts.)

Also acceptable: Inventory (I) is not satisfied or

a. yellow path exists or a transition to CSP I.2 is

. required (any of the above is acceptable)

(.5 pts.) because crassurizer level is low

(<12%). (.2 pts.)

060 Additional Information:

Technical

References:

ST's 1-6 Items to be Included with Ouestion: None Time validation: 6.10 Recual Cvele: N/A KML.Re_ference: System: 000 Mode: 056 Number: EA2.48 Ratings: RO: 4.3 SRO: 4.4 e

Question Number: 031-03-096A Point Value: 0.8 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: C Subject Area: AC ELECTRICAL DISTRIBUTION SYSTEM Task Number: C4306 COT Terminal Learniner oblective:

C4306 COT During an emergency or accident condition assess the effect of electrical system malfunctioning on as a result of a loss of power to various electrical components.

Question: Instructor Use Only Both units are operating at 100% power with 13.8 kV cross-tie breaker H52-21 (old H52-02) out-of-service, and 345 kV line 111 (to Granville) is out-of-service. A fault condition isolates switchyard bus BS-2. The emergency diesel generators (G01 and G02) will automatically start, (Choose one answer.)

a. supply their respective buses, and trip on overload.

b. but'only G01 will supply its respective 4160V bus, 1A05; G02 will run unloaded.

c. and supply their respective Unit 1 4160V busses, 1A05 and 1A06.

d. and supply their respective 4160V busses for both units, lA05, lA06, 2A05 and 2A06.

Points Earned

. Question No.: 031-03-096A Page 2 .

Answer: Instructor Use only

c. (.8 pts.)

103 Additional Information:

Technical

References:

TRHB 12.3 TRHB 12.4 TRHB 12.8 Items'to be Included with Ouestion: None Time Validation: 4.20 Recual Cvele: N/A K/A

Reference:

System: 062 Mode: 000 Number: K1.02 Ratings: RO: 4.1 SRO: 4.4

4 e

' Question Number: 031-03-119A Point Value: 1.0 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: C Subject Area: SAFETY INJECTION SYSTEM Task Number: C0604 COT, C7009 COT Terminal Learnine Obiective:

C0604 COT During emergency or accident conditions, the operator must be able to diagnose malfunctions of the SI. system that inhibit any function of the SI system.

C7009 COT From any plant condition following a reactor trip or safety injection actuation recognize the critical safety functions by verifying that all safety related parameters are satisfied in accordance with the critical safety function status trees.

Question: Instructor Use only During an SI actuation due to a LOCA, and with normal system lineup, which one of the following situations would indicate an SI system misalignment / malfunction? (Consider each separately.)

a. Accumulator pressure of 725 psig with RCS pressure 800 of psig.

b. BAST level of 35% and RWST outlet valves (825 A & B) open.

c. SI pump outlet cross connect valves (SI 829 A

& B) closed.

d. Pressurizer pressure channels indicating 1730 psig (PC-429), 1732 psig (PC-430),1738 psig, (PC-431).

e. SI pump 15A discharge valve 1-MOV-866A open.

Points Earned

I Question No.: 031-03-119A Page 2 Answer: Instructor Use only

b. (1.0 pt.) '

171 Additional Information:

Technical

References:

'TRHB 10.8

'P&ED 110E017 sh. 2 of 3 Items to be Included with Ouestion: None Time Validation: 2.70 Recrual Cvela: N/A K/A

Reference:

System: 000 Mode: 011

, Number: EA1.13 Ratings: RO: 4.1 SRO: 4.2

7

. a Question Number: 043-02-010A Point Value: 1.2 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: REACTOR COOLANT SYSTEM Task Number: CO232 COT, PO435 COT Terminal Learnine Obiective:

CO232 COT During steady state or transient power operation PREDICT-the consequences of exceeding pressure / temperature limits  !

by identifying the results of overpressure at low temperature and of high temperature at low pressure.

PO435 COT During conditions of normal full power operation respond to a reactivity transient at high power in terms of its effect on power level and RCS parameters such as pressure and temperature, without error.

Question: Instructor Use Only With Unit i reactor in cold shutdown (RHR Train A is operating) at 250 psig and 200*F in the RCS, IEC requests SI accumulator levels be increased from 17% to 40%. After starting "A" safety injection pump (P-15A), RCS pressure increases rapidly.

1. RCS' protection is provided in this case by (select one of the following) (.8 pts.)

a. PZR safety valves.

b. PZR PORV's.

c. auto closure on 1MOV700 and IMOV701 (RCS supply to RHR).

d. operator action only.

2. What is the potential consequence to the RCS if no protection were available? (.4 pts.)

Points Earned

es e 4

Question No.: 043-02-010A Page 2 Answer: Instructor Use Only

1. b. (.8 pts.)

2. Potential Brittle fracture - (IOCA of the reactor vessel). (.4 pts.)

274 Additional Information:

Technical

References:

l T.S. 15.3.1.B and 15.3.15 Items to be Included with Ouestion: None Time Validation: 4.20 Recual Cycle: N/A K/A

Reference:

System: 002 Mode: 000 Number: K4.10 Ratings: RO: 4.2 SRO: 4.4 4

-_-.__m_--___. _ _ _ _ . _ _ _ _ . . _ . - . _ _ _

o a e

Question Number: 057-02-019A Point Value: 1.0 Revision Number: 1 Approval Date: 05/15/89, Question Format: W Question Type: E Subject Area: TECHNICAL SPECIFICATIONS Task Number: C6501 COT, P6511 COT l

Terminal Learnina Obiective:

C6501 COT During all modes of operation assess TS and procedural requirements to equipment necessary for safe operation of the plant in accordance with all procedural and Technical Specification requirements without error.

P6511 COT During any mode of plant operation, apply Technical Specification requirements in accordance with all action statements associated with the applicable Technical Specification.

Question: Instructor Use only Unit 1 is at 100% power. Assume all systems are operating normally.

1. At 1500, the PPCS computer alarm, " Flux Difference (Top-Bottom) N-41," is received.

What, if any, action is required to be taken by the operator? (.2 pts.)

2. At 1530, the PPCS computer alarms, " Flux Difference (Top-Bottom) N-44" and " Flux Diff Pos Band Limit" are recieved. At 1535, the PPCS computer alarm, " Delta Flux - Minutes out of Band" is recieved. Assume that N-41 remained outside of the band since 1500.

Explain what, if any, operator action is required for this alarm. (.8 pts.)

Points Earned

e C Question No.: 057-02-019A Page 2 Answer: Instructor Use Only

1. No action required. (.2 pts.)

2. Reduce power until the AFD is within the operating envelope or power is reduced <50%.

(.8 pts.)

Additional Information:

Technical

References:

Tech Specs section 15.3.10.B.2 LP 618 Limiting Conditions for Operation Items to be Included with Ouestion: None Time validation: 3.00 Recual Cvele: N/A K/A

Reference:

System: 015 Mode: 000 Number: GOS Ratings: RO: 3.3 SRO: 3.8

i'

. o Question Number: 053-01-048A Point Value: 1.0 Revision Number: 2 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: ROD CONTROL SYSTEM Task Number: C0105 COT, C0120 COT Terminal Learnina Obiective:

C0105 COT During normal power operations with the rod control system in automatic assess the response of the rod control system l

to change plant conditions. Assessment of expected rod speed and direction as the Tref - Tavg error exceeds 1.5 Dag F in either polarity is required, without error.

C0120 COT With the rod control system in the automatic mode and the plant operating at an initial power level of 100% FP, assess the response of the rod control system to a turbine runback in terms of correct direction and speed, without error.

Question: Instructor Use only For the following plant conditions, state if rod motion will be in, out, or no motion. Assume 90%

power with bank D rods at 180 steps for the start of all transients with the rod control system in automatic. '(Consider each condition separately)

a. The rod position indication (IRPI) syst m is in runback defeat for testing when a turbine runback occurs due to the power range instrument (N-41) failure. (.5 pts.)

IN OUT NO MOTION

b. A (>5%) negative spike (<1 second) sensed by power range instrument (N-41) . (.5 pts.)

IN OUT NO MOTION Points Earned l

R q Quoction No.: 053-01-048A Page 2 i

Answer: Instructor Use only

a. IN (.5 pts.) '

b. IN (.5 pts.)

Additional Information:

Technical

References:

Logic drawing 883D195 sh. 16 LP1547 Rod control System Items to be Included with ouestion: None Time Validation: 5.00 Recual Cvela: N/A K/A

Reference:

System: 001 Mode: 000 Number: K4.03 l ,

Ratings: RO: 3.5 SRO: 3.8 i

l l

l

Question Number: 055-01-027A Point Value: 1.0 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: CHEMICAL AND VOLUME CONTROL SYSTEM Task Number: C0426 COT

. Terminal Learnina Obiective:

C0426 COT During a normal plant startup and given a copy of OP-1A assess charging, letdown and pressurizer pressure when drawing a bubble in the pressurizer in accordance with OP-1A, " Cold Shutdown to Low Power Operation".

Question: Instructor Use Only The RCS pressure is 385 psig; both RCP's are in operation; all pressurizer heaters are on; and RCS temperature is 370*F. The operator slowly decreases charging pump speed to draw a pressurizer bubble. Explain how RCS pressure will responsed if:

a. pressurizer temperature is 445'F. (.5 pts.)

b. pressurizer temperature is 405'F. (.5 pts.)

1 Points Earned

Qu'z tion No. : 055-01-027A Prg3 2 Answer: Instructor Use only

a. RCS pressure will remain constant saturation pressure is 401 psia or 386 psig.

(+/- 5 psi) ( . 5 pts. )

b. RCS pressure will drop Saturation pressure is 261 psia or 246 psig. (+/- 5 psi) ( . 5 pts. )

Additional Information:

Technical

References:

OP-1A, Steam Tables Items to be Included with Ouestion: None Time Validation: 5.50 Recual Cycle: N/A K/A

Reference:

System: 002 Mode: 000 Number: K5.09 Ratings: RO: 3.7 SRO: 4.2

- _ _ _ _ _ _ _ _ _ - _ _ _ _ _ A

. r Question Number: 031-01-005A Point Value: 0.7 Revision Number: 1 Approval Date: 05/15/89 Question Format: W Question Type: S Subject Area: EMERGENCY TASKS Task Number: C7024 COT, C7025 COT Terminal Learnina Obiective:

C7024 COT Given a set of Emergency Operating Procedures apply the procedural rules of usage to the EOPs by performing procedural steps in proper sequence making correct transitions to sequence through the EOPs to a termination point.

C7025 COT Given a set of Emergency Operating Procedures analyze the format and organization of the EOPs by identifying the various transition paths between procedures and the established priorities of various groups of procedures.

Question: Instructor Use Only A total loss of all AC power from 100% power has occurred. Indicated SG wide range level for the "A" SG is 190" and for the "B" SG is 195". The turbine-driven AFW can only feed each SG at 75 gpm.

The DSS decides to make a transition from ECA 0.0

" Total Loss of AC," to CSP H-1, " Response to Loss of Secondary Heat Sink." Explain whether you AGREE / DISAGREE with this decision.

I l

Points Earned

)

l t_-______---_-_----- i

L~ , "A  ;

1 QuOction No.: 031-01-005A Paga 2

)

Answer: Instructor Use only. I

.t Disagree (0.2 pts.) Daring a loss of all AC, ST's f

are to be monitored for information only; CSP's are not to be performed. (.5 pts.)

Alternate answer: Should be in ECA O.0, " Loss of All AC" 080 Additional Information:

i Technical

References:

ECA-0, cautions I- Items to be Included with Ouestion:

Added alternate answer to cover the procedure where the note is listed based o,n comments from a practica exam.

Time Validation: 3.50 Recual cvele: N/A l K/A

Reference:

System: 000 l' Mode: 055 Number: G12 l

I l

l l