Text

Exam Rept 50-029/85-22 on 851029-31.Exam Results:All Candidates Failed Written Exam.One Reactor Operator Candidate Also Failed Oral Operational Exam
	ML20137R600
Person / Time
Site:	Yankee Rowe
Issue date:	01/31/1986
From:	Dante Johnson, Keller R, Kister H; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20137R591	List: IR 05000029/1985022; ML20137R586;
References
	50-029-85-22, 50-29-85-22, NUDOCS 8602130331
	Download: ML20137R600 (4)
	v • d • e

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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT

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EXAMINATION REPORT NO. 50-29/85-22 (OL)

FACILITY D.0CKET-NO. 50-29-FACILITY LICENSE NO. DPR-3 LICENSEE:~ Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts FACI'LITY:'

Yankee Nuclear Power Station EXAMINATION DATES: October 29-31, 1 85 CHIEF EXAMINER

[

(/L/F[

. F. Johnson, Lea Reactor Engineer Date (Examiner)

REVIEWED BY:

/M )

/

//4[#4 Rcbert 'M. Keller, Chief, Projects Section 1C _Date APPROVED BY:

A. t )

N

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Harty B. Kist'eh Chief, 9a'te #

Projects Branch No. 1 SUMMARY: Three Senior Reactor Operations (SRO) an'd four Reactor Operators (RO) were examined. All candidates failed the written examination and one RO candidate also failed the oral operational examination.

'7 B602130331 060131 PDR ADOCK 05000029

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REPORT DETAILS TYPE OF' EXAMS:

Initial'

-EXAM RESULTS:

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I RO l

SRO l

l Pass / Fail i

Pass / Fail

-1 l-I l

I I

I l Written Exam l

0/4'

l 0/3 l

'l i

I l'

I I

I-I l. Oral Exam'

l 3/1 l-3/0 l-

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l-l-

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Overall l

0/4

0/3 l

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-1; CHIEF EXAMINER AT SITE:

D. F. Johnson

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~2.

~UTHER. EXAMINER:

F. Jaggar (EG&G)

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' Sommary of generic deficiencies noted on oral exams:

A.) A majority of the candidates exhibited difficulty in determining,the magnitude,-direction and ti.me frame of changes to' major plant para-meters during transient conditions.

- Bl).

In general, most candidates were weak in their ability to apply known theoretical knowledge in the areas of reactor theory and thermo-

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dynamics'to practical applications, i.e., simple heat balance cal-culations, and transient ~ effects'of reactivity.

2.

Summary of generic deficiencies noted from grading of written exams:

A.

Candidates did not demonstrate an adequate level of knowledge-and.

understanding in the following areas:

(1) operating and emergency procedures (2) plant systems design

..

(3)

instrumentation and~ controls

~

S.

. Greater than 40*J of the candidates were extremely weak in theory of nuclear. power plant operation and thermodynamics associated with plant transients.

3.

Status of Previously Identified Items (Closed) Inspector Follow-up-Item (29/85-03-01) - Training material pro vided was inadequate for preparing R0/SRO examinations.

-The training material provided on July 7,1985.for the upcoming R0/SRO

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examinations scheduled for October 1985 were reviewed by the operator licensi,ng staff and found to be satisfactory.

Procedures and system descriptions were revised accordingly and were adequate for the pre-operation of the written and oral examinations.

(Closed)

Inspector Follow-up Items (29/85-03-02 and 85-03-03)

Procedures OP-3250, OP-3111 and OP-3001 were not revised to reflect current system and plant status.

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The fc? lowing Procedures were reviewed by the Region I staff:

.

A.

OP-3001, "Large Loss of Load Without a Reactor Scram" Rev. 8, May 1985.

B.

OP-3111, " Malfunction of Primary Pressure or Lovel Channels" Rev. 8, December 1984.

C.

OP-3250, " Loss of a 120 Volt' A.C. Vital Bus".Rev.10, June 1985.

OP-3257, " Loss of No. 2 125 Volt DC Battery Bus Power" Rev. 4.

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Review of the above procedures verified that revisions were.made to reflect the correct and current plant status.

4.

' Personnel present at Exit Interview:

NRC Personnel D. F. ' Johnson,; Chief Examiner

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NRC Contractor Personnel F.-Jaggar, EG&G Facility Personnel L. Laffont, Senior Instructor D. Peirce, Instructor 5.

Summary of NRC Comments made at exit interview:

Preliminary results from the oral examinations were discussed with the licensee.

The remaining process of grading the written examinations and turn around time for results were also. discussed.

6.

Examination' Review

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At the conclusion of the written examinations, the-Chief Examiner met with licensee personnel to review the exam and answer keys to identify any' inappropriate questions relative to plant specific design and to ensure that the questions will elicit the answers in the key and that they reflect the most current plant status. The following licensee personnel were present:

L. Laffont D. Peirce Attachments:

1.

R0 Written Examination and Ar.swer Key 2.

SR0 Written Examination and Answer Key 3.. Facility R0 and SRO Examination Comments and Resolutions a

kTrhcHMENT~l

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U.

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HUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATIDH FACIL.ITY:

_ZaWEEE_20WE_____________

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REACTOR TYPE:

_ EWE =WECa________L_______

DATE ADMINISTERED:_83Z1022E____________*___

EXAMINER:

_hEMBIN 4_W.___________'__

APPLICANT:

l

_

_ _. _

INSIEUCIIONS_ID_aEELICANIl UCO sWParatW PaPWP for the ansWWrse Write JusWWrs on one side on1w.

Staple auestion sheet on top of the answei sheets.

Points for each cuestion are indica".ed in Parenthesus after the uusstion. The Pausing stede reauires at least 70% in each categorw and a final grade of.

at least '80%.

Examination PaPWPs Will DW PichWd up Six (6)

houPS after tho examination starts.

% GF CATEGORY

% OF APPLICANT'S CATEGORY

__McLUE_ _IDIAL

___ SCORE ___

_MALUE__ ______________CAIEGOEY_____________

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25.3

_25.00__ _22I00

________ 1.

PRINCIPLES OF NUCLEAR POWER c

___________

PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 2d.0 0 A4. 20

_GSzte__ _E5 set

________ 2.

PLANT DESIGN INCLUDING SAFETY

___________

AND EHERGENCY SYSTEMS W.S

_25.00__ _E5=Ge

________ 3.

INSTRUMENTS AND CONTROLS

___________

Ar.1

_25.00__ _EST*C

________ 4.

PROCEDURES - NORMAL, APHORMAL,

___________

EMERGENCY AND RADIOLOGICAL CONTROL 99.0 0 teer00__ 100.00

________ TOTALS

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___________

FINAL GRADE _________________%

All work done on this examination id mu own. I have neither Eiven nor received aid.

___________________________________

APPLICANT'S EIGNATURE

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1 __ERINCIkLES_DE_MUCLEAR_20WER_ELdWI_DEERtIIDWa PAGE*

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- IMERMODX5cMICSa_WEAI_IEeWSEER AMD ELUID_ELOM

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QUESTION 1.01 (2.00)

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c. If the ~ reactor is operating in the Power rangue how long will

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it take to raise Power from 20%.to 40% with a +0.5 DPH Start-

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uP rateT g

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a QUESTION 1.02-(1.50)

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Compare the calculated Estimated Critical Position (ECP) for a

'otartur 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months arte. 4 trip to the actual Critical Rod Position (ACP) if the followins' e'ents/ conditions occurred.

consider each independent 1w.

Limit vour answer to:

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No. ACP higher than~ECP.

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b. ACP lower than ECP.

c. ACP would not be significant1w different than ECP.

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1. One Reactor Coolant Pump is stopped one minute prior to criticalitw.

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7. The steam dune Pressure controller setroint is increased to a value

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Just below the code safties setroints.

3. The startue is delswed 2 more hours.

QUESTION 1.03 (2.00)

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If the Source Range (SR) instruments indicate 50 ces with Keff ocual to 0.9.

Assuming BOC conditions answer the followins.

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o.

What would the SR. instruments indicate if the rods wuru withdrawn l

(1.0)

to bring Keff eaual to 0.957

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b.

How much reactivitw was added?

(1.0)

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

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1 __2RINCIELES_DE_MUCLEAE_20WER_ELANI_DEEReIIONA PAGE*

3-IMERMODXMAHICS4_WE6I_IRAMSEER_cWD_ELUID_ELOW

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QUE' TION 1.04 1.50)

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Ccncerning the Moderator Temperature Coefficient (MTC), state whether the HTC value would'be MORE NEG., LESS-NEG., or NOT EFFECTED bw each of

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the following'.

' CONSIDER 'EACH SEPERATELY.

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o.

Increase in soluble boron concentration.

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b.

BOC to EOC.'

c.

Fission Product poison buildup.

d.

Burnable Posion rod burnuP.

o.

Insertion of control rods.'

CO.5 each3

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QUESTION 1.05 (1.00)

TRUE OR FALSE 7

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Oc Baron concentration increases:

-a.

Moderator Temperature Coefficient becomes less negative due to increased neutron Iwakage.

(0.5)

b.

Moderator TehPeraturW Coefficient becomes more nWMatiVW due to the increased resonanew absorption factor.

-(0.5)

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

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1.__ERINCIELES_DE_ NUCLEAR _EDWER_ELAWI_DEERAIIDHA PAGE'

4-IWER"0DYHfMICS4_WEAI_IEANSEER_cWD ELUID_ELOW

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QUESTION 1.06 (4.00)

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Ucing the attached Xenon worth curvve Fig. 1.le answer the following.

c.

Power at TO was at 70%.

What was the approximate rower level between T1 and T2?

(1.0)

b.

What was the length of time between T2 and T37 (1.0)

'

c.

What happened at T27 (1.0)

d.

At time T4...

1.

All Xenon Production stopped.

2.

Iodine decaw to Xwnon has stopped.

3.

All Xenon Production rwaains constant, but the burnout inerwases.

4.

Xenon production direct 1w from fission has storPvdp but Xenon Production from decaw of Iodine continues.

(1.0)

..

QUESTION 1.07 (2.00)

secon.darw calorimetric and adjustment of the power rangw inst-After a ruments it is discovered that the Auxiliarv Fwedwater Pumes were crerating.

HOW and WHY would this occurence effect the Power range indication.

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

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1.__ERINCIELES_DE_MUCLEAR_EDWER_ELAHI_QEERAIIDHA PAGE'

5-IMERMODYMAMICSa_WEAI_IRCMSEER_eHD ELUID ELOW

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-QUESTION 1.08 (3.00)

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Use the steam tables and associated McIlier chart to answer the uuvstions bolow, label cuantites with Proper units.

.s.

During cooldown and dvervssurization, wou are rwuuired to remain 50 degrees F subcooled.

As the Pressure decreases through 2085 Psis, what is the maximum'Tave allowed (nearest degree F)?

(1.0)

b.

Steam is leaking from a Pipe flange to atmosphere. A thermocouple placed in the leakage stream reads 400 dudrews F.

What is the (1.0)

degree of suPerheat?

c.

If the thermocou,Ple in,Part b-had read 360 degrees F, and the steam Pressus0 inside the Pipe was 560 Psia, what would wou estimate the steam temperature to be at that Pressure?

(1.0)

QUESTION 1.09 (2.00)

.

It is desired to modifw a closed-loop swstem, such as the CCW sustem, to double the flow. You have three choices to accomplish the modification.

1.

Double the speed of the Present Pump, which is a single stage Pune.

2.

Add another identical Pump to cPerate in Parra11W1 Whith thW eMisting Pump.

3.

Replace the Present Pump with a two stage Pump.

c.

Which of these choices will double the slow and result in the least(0.5)

Pump Power consumption?

b.

EXPLAIN the reason for YOUR choice'and WHY wou evJucted the other

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(1.5)

two choices.

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

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1.__ERINCIELES_DE_ NUCLEAR _EDWER_ELeMI_ DEER $IIDWs PAGE*

6-IWERMODYWeMICSa_WESI_IRLMSEER_AND_ELUID_ELOW QUESTION 1.10 (2.50)

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a.

How would'the delta T during natural circulation compare with the 100% Power delta'T7 (0.5)

b.

Assuming that the Tave is being maintained constant durins natural circulation.

What would happen to the delta T if heat removal was stopped from the stwas generators?

(0.5)

c.

What are three itwas that an operator can check to ensure that natural circulation is satisfactorw?

(1.5)

QUESTIJN 1.11 (1.50)

Critical Heat Flux (CHF) is definad as the heat flux at which

'

DcParture from Nuc1vate Boiling (DNB) occurs. For an INCREASE in each of the Parameters belowr state how the CHF will change.

(Consider each Parameter separate 1w.)

,

' Limit wour answer to Increase, Decreasse or Remains the Same.

e c.

Reactor Coolant Flow Rate.

b.

Reactor Coolant Temperature.

c.

Reactor Coolant Pressure.

(1.5)

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QUESTION 1.12 (1.00)

ExP1Ein'the response of Power AND Tave-if two minutes of i

Ecurgenew Boration is reauired while thw reactor is at I

10 -8 amps and 515 F.

( *. 0 ).

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.24-_*LAMI_DESIGM_IMCLUDING_SSEEI%_aHD_EMERGEUC%_S%SIEM2 PAGE 7 --

. QUESTION 2.01-(3.00)

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o.'

What is the NORMAL water suPP1w to the suctions of the steam driven EBFP and electric driven EBFP7 (1.0)

b.

State two sePerate methods of suPP1 wing steam to the SDEBFP.

c.

State the siternate and/or emergenew source (s) of water available to the steam generators.

(1.0)

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QUESTION 2.02 (2.00)

o.

What is the Purpose of the Auxiliarw Governor in the Main Turbine Control Swsten?

(1.0)

b.

What are the conseauences of pulling the Auxiligrw Ouvernor Test Lever OUT while the reactor is at 100% Power?

(1.0)

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QUESTION 2.03 (2.50)

The following pertain to the Eltetriesl Distribution Swstem at YEnkee Rowe.

c.

What is the length of and basis for the time delaw in starting the High Pressure Safetw Injection (HPSI) Pumps upon reciept of a Safetw Injection Signal?

(1.0)

b.

What is the voltage above which the diesel generator output breaker will automatica11w.close?

(0.5)

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c.

State the FOUR alarms and trips that are affveted bw the ' RESET *

Position on the emergenew diesel generator local start switch.

(1.0)

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

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".. 2 __ELAMI_DESIGU_ INCLUDING _StEEIX eWD_EMERGENCX_SXSIEWS PAGE'

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QUESTION 2.04 (3 00)

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c.

State the purpose of the SI Accumulator.

(0.5)

b.

At what Pressure is the SI Accumulator inJwcted into the MCS and what volume is injected (cu. ft.)?

(1.0)

c.

State the Purpose and the-normal operating Pressure of each of the three compressed nitrogen swstems associated with the Emergenew Core Cooling Swstem.

(1.5)

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GUESTION 2.05 s3.00)

a.

State the Purpose of'the' Shutdown Coolins Swstem. Include the temperature and pressure below which.the SDC maw bw Placed in

'

operation.

(1.5)

i b.

Describe the Pressure interlock associated with the SDC isolation valves.

Include the Purpose of the interlock.

(1.0)

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c.

If the Shutdown Cooler is inoperabler what other heat exchanger can be used?

(0.5)

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GUESTION 2.06 (3.00)

c.

What is the approximate lift pressure of the fol?.owing Component

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Cooling Swstem relief valves and to where does wach relieve?

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1.

MCP return.

2.

Component Cooling'Surgw Tank.

(1.0).

b.

A source of makeur water to the Component Cooling surge Tank

is the condensate Pump discharge header via'LCV-200.

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1. When is this suurew of water used?

2.

What is a possible consecuence of using this source?

3. What is the other source of makeup to the surge tunk?

(1.5)

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c.

Explain how c erling water can be supplied to the MCPS if both CCW Pumps are inoperable.

(0.5)

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

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'2.__ELANI_DESIGW_IUCLUDING_SAEEI%_eMD_EMECGENCY_SISIEMS PAGE* 9 --

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l QUESTION 2 07 (3.00)

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s.

Boric Acid Mix Tank temperature must be maintained above 155 DEG F

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when adding makeup water to the tank.

How is this accomplished when the makeup water is cold?

(1.0)

b.

Whw are the anion resin bed ion exchangers valved and locked out of service durins normal' operations?

(1.0)

ce Whw must level be maintained greater than 30' in the Low Pressure Surge Tank?

(1.0)

,

QUESTION 2.08 (3.00)

o. Whw does -the -Condensate Recirculation Valve (CV-405) open automatica11w on a reactor scram above 15 MWe?

(0.6)

.

b. List the Condensate Pump automatic tries.

(1.6)

c.-What is the normal discharse Pressure at full load conditions of the!

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1. Main' Condensate Pune?

2.

Boiler Feed Pump 7 (0.8)

QUESTION 2.09 (2.50)

The'foilowing concern Main Coolant Pu2Ps-(HCP)*

o.

How is cavitation Prevented in a HCP and how are net Positive suction head (NPSH) reauirements ensured?

(1.5)

b.

How does the differential Pressure' developed bw a HCP change as coolant temperature increases from 100 DEG F to 510 DEG F7 Explain (1.0)

wour answer.

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

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_INSIRUMENIS C"D_COMIROLS Pf.GE '

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QUESTION 3.01 (1.50)

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a.

During routine shutdown operationse from where does CC-TCV-200 (0.5)

set a signal to open?

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b.

From where does CC-TCV-200 set a signal during normal operations.

(0.5)

c.

At what MCS temperature is control of CC-TCV-200 shifted.

(0,5)

QUESTION 3.02 (3.00)

o.

Describe how a loss of control air Pressure will effect the #1 (1 0)

AND 43 charging Pump.

b.

Describe how each of the three charging Pumps can be used to control Pressurizer level i f control air is not available.

(2.0)

.

QUESTION 3.03 (2.00)

c.

What actuates a rod stop condition during' control rod motion?

(0.5)

b.

Describe the three waws that a " rods in motion * signal can be developed.

(1.5)

GUESTION 3.04 (2.00)

i s.

List the five conditions that will cause 42 HCP to trie.

(1.5)

I b.

What intericek must be satisfied for a loop stop valve to open?

(0.5)

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P (***** CATE00RY 03 CONTINUED ON HEXT PAGE

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QUESTION 3 05 (2.50)

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'c.

What signal (s) will energize the Non-Return Valve (NRV)

automatic trie relaws?

-

(1.0)

b.

When the NRV's recieve an automatic trip signal while the reactor is at full PoWert What other automatic actions saw be initiated as.a result of the.same closure signal?

(1.0)

c.

At what Point durind an MCS CooldoWn is the NRV auto close blocked?

(0.5)

GUESTION 3.06 (3.00)

Dascribe how the indication from the 3 Ivvel detectors on the Pressurizer will. respond if a.

the signal from the linear amplifier fails low.

b.

the reference les flashes to steam.

(3.0)

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QUESTION 3.07.

(2.50)

I o.

From what Part of the MCS does the Low Temperature Overpressure Protection (LTOP) swstem receive its operating signal?

(0.5)

b.

Describe the four functions of the " Kirk Kew Interkock" when it'

'is in the " ARMED' position.-

( 2.0)

QUESTION 3.08 (2.00)

,

I c. The Feedwater Control Swstem maintains s'Iwvel in the steam senerato/s at a set value using both feud forward and feedback he Parameter inputs are used for:

control.9 1. Feed forward?

2. Feedback?

(2.0)

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

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3.__iMSIRU"EMIS_Or,D COMIROLS PAGE.12-.

QUESTION 3.09 (2.00)

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o. What is the automatic trip signal and sutroint that will close the Steam Dump valve MS-PCV-402'? -

(0.5)

'

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b.

If the tr1P Condition has not cleared, how can MS-PCV-401 be.

reopened?.

(0.5)

.

c. After the trie condition h&s clearede in what mode (auto or E

,

manual) should MS-PCV-402.be shifted to recover the valve?

(1'.0)

-

Explain.

.

QUESTION 3.10 (1.50)

c. What four Parameters are Plotted on the generator caPabilitw curve?

(1.0)

b. With generator carrwing a " lagging * load, how can the generator Power Factor be improved?

(0.5)

..

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QUESTION 3.11 (3.00)

,

o.

What radiation monitor (s) would be used to indicatu a sudden fuel failure?

(1.0)

b.

How would an operator distinguish between a fuel failure and a failure of the detector or other circuit malfunction?

(1.0)

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c.

Describe in general terms what action would be taken to minimize the radiological effects of this failure.

(1.0),

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(***** END OF CATEGORY 03

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d a._REOCED URES_=_ NORM ALa_f BNOR M A L2_EMERGEN CY_ A ND PAGE'13'-

RADIOLOGICLL_COMIROL

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QUEST' ION 4 01 (2.00)

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The following concern OP-3054, Natural Circulation.

,

e c.

Now is thd Plant cooled down if the condenser vueuum is* lost due to loss of AC Power?

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(1.0)

b.

Whw muse the water treatment Plant be restarted as soon as practical?

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(1.0)

,

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GUESTION 4.02 (1.50)

,

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State the criterion used to determine which attachment (AeBoorC)

to OP-3000e Emersenew Shutdown from Powere is used.

QUESTION 4.03 (2'.50)

)

.

Rosctor Engineering has determined that containment leakage has exceeded allowable levels and OP-3007e Loss of Vapor Containmente

~

has been initiated.

i l

c.

What must be done to the plant and how much time can vlaspe before this must be accomplished.

(1.0)

b.

If the leakage is not corrected after Part "a*

is establishede what must be done and in what period of time must it be done in?

(1.5)

QUESTION 4.04 (2.00)

.

Ancording to OP-3010e Fire or Forced Evacuation of the Control,Roome thich caseeleIIsorII Qdirects the operator to check the ventilation lineup?

What is the resson for this direction?

,

!

I l

i

!

(*****

CATEGORY 04 CONTINUED OH NEXT PAGE *****)

.

A-""

"-*--*+-~n

-,_._~-,-+,--m,--

-,,,w,-m,-- w,e

--,w,-,-~,--,,r-e-----,.-.,

ey,mmn,m-n--,-ww,,,

,,,-,--c-yen,w-w-,.,-,-------,e-

'.

A.__REOCEDURES_=_MORMOLA_eBWORMOL4_EMERGENCX_dWD PAGE* 14..

.

24210LOOICiL_CONIROL

'

.

~

QUESTION 4.05 (3.00)

-

'

-

c.

Immediate operator action step 6 of OP-3051, Loss of Main Coolant Pressure and/or Safetw Injection Actuatione is ' Accident Diagnostics'. State the three subster diagnostics that comprise this'immediate action. (Para-Phrasing is allowable)

(1.5)

b.

In addition to *a" abover list FIVE other major immediate actions stated in op 3051.

Sub-steps not reeuired.

(1.5)

QUESTION 4.06 (1 00)

,

Por OP-3111e Malfunction of Primarw Pressure or Level Channelse what 2 actions.must be taken if the failed channel is from lour 1 or 2 and SIAS is initiated.

(1 0)

.

..

QUESTION 4.07 (1.50)

OP-3115, Loss of Component CoolinWF directes the stOPPind of the Main Ccolant Pumps (MCP). If bearing water temperature exceeds a sPecified value.after thew are stopped, a sPeelal reuuirement is Placed on anw Pump restarts.

State the temperature limit and the sPecial reuuirement Placed on subseauent restarts.

l QUESTION 4 08 (3.50)

,

List ALL of the eauipment that must be operated wither manuallw or i

locallw during a * Loss of 41 125 Vult D.C.

Bus Power', OP-3257.

i o

QUESTION 4.09 (2.00)

List ALL classifications of enwrdwncies in order of severitwe least to worste per OP-3300, Classification of Emergencies.

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

i

,

-

L

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

- - _ _ - _ _ _

_ _ _.

___

__ _

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

d - EROCEDURES =_NORMALa_6BWORMALa_EMERGENC% AMD PAGE '15-RADIOLO21C*L_C00IROL QUESTION 4.10 (2 00)

'

-

The following concern OP-2151, Boric Acid Addition To The Hain Coolant.

e.

List the two waws boric acid saw be added'to the MCS. Bu specific as to when each can be used.

(1.0)

b.

Above what Pressure'and/or temperature reeuirements must each loops SI MOV be locked open with its motor operator wivetricallw inoperative?

(0.5)

c.

What plant conditions ( t'empe ratu re and/or Pressure) arv reauired in order to add boric acid to a single loop?

(0.5)

'

GUESTION 4.11 (3.00)

The following pertain to 10 CFR 20.

,

s.

Define

-

- Restricted Area.

- Radiation Area

- Occupational Dose.

(1.5)

b.

State the maximum allowable wholvbodw uuartwrlw occupational dose an individual saw receive in a restricted area. What can this limit be increased to and what must be done to increa4w it?

(1.5)

'

QUESTION 4.12 (1.00)

According to OP-2100, Plant Startur From Cold Shutdown, what roauirements must be met when HCS tweperature is between 300 F l-cnd 440 F7

,

(***** END OF CATEGORY 04

- - - - )

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

.

,

...

,

EQUAT!CN SHEET f = ma v = s/:

Cycle afficiency = (, ec wrk

cut}/(Energy in)

,

w = ag s = V,: + 1/2 ar -

.

g = =c-A = A,e'*

A = 1:1

' a = (V. - 1,)/ t xi = 1/2 mv g

PE = agn

. = a /t L = &n2/t;j.g = 0.593/t1/2 y. = y, * at.

g

i/28## * ECC )(**)3 T

-

y,,. p r0 A=

((g p,) * (:$)J

ti = 931 sm

-

.-D:

a = V,,A o

.

,

.

Q = mCoat d = UA A.T I=I,e*

-

I = I,10~* N '

Pw-= W,2 Tit. = 1.3/1 P = P 10,8"#I*I HVL = -0.593/n o 3,*.

-

P=Peo

<

SUR = 25.06/T SG = S/(1 - Kgf)

G = S/(1 - X,g 2)

x gf)) = G (I ~ *en2)

SUR = 25e/1* * (s - s)T G (1 - K

7

'

T = (i=/s ) + (( A - o '/ Ia]

M = 1/(1 - Kgf) = G)/G 3

.

T = 1/(s - 4)

M = (T - Kgf,)/(1 - K,gj)

T = (a - o)/(T.)

ScM = ( -Kdf)/Xef

- * 10 5'c:"45

= (Kef-1)/Xen I = 0.I sec::nds gf (1 + IT)]

a = ((t*/(T K,g}] + (T

/

Ij j'= I d d

7 = (:ar)/(3 x 1010)

I d; 2 =2 2%2

,

2/hr = (0.5 C2)/d (seters)

t = sfi R/hr = 6 C2/d2 (feet)

,

Misesllaneous Conversions Water Par =_ meters I curia = 3.7 x 10 kas I

i gal. = 8.345 lem.

i kg = 2.21 lem 1gja.=3.78litars Ino=2.54x103Stu/nr 1..

= 7.48 gal.

1w = 3.41 x 100 3*w/hr Oensity = 62.4 lbm/ft Density = 1 gs/c::r3 lin = 2.54 c=

Heat of vaccrirstion = 970 Stu/lem

? = 9/5'C + 32 Heat of f 2sion = 144 Stu/itm

'C = 5/9 (?-32)

1 Ats = 14.7 psi = 29.9 in. Hg.

1 STU = 778 ft-lbf I ft. H O = 0.4335 lbf/in.

-

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1.__CRINCIELES_DE_CUCLE!R_EDWER_ELdHI_DEERAIIDMA PAGE*id.

IMEEMODINADICS4_HEAI_IRCMSEER_AND_ELUID_ELOW ANSWERS -- YANKEE ROWE-85/10/29-HEMMING, W.

I l

W l

_

.

,

ANSWER 1.01 (2.00)

sur(t)

P=P 10

.5(t)

40=20X10

.5(t)

-

2=10

.3=.5(t)

to.6 minutes or 36 seconds.

C1.0 for solution and 1.0 for answer 3 (2.0)

REFERENCE SONP, G & A Bank a see 1-11 ROWEe Reactor Training Manualp PP 3-142 - 3-145 ANSWER 1.02 (1 50)

-

1.

e nw -

.

2.

a 4., L.

3. b be.c CO.5 ea.3 REFERENCE SONP, Review of Core Poisons, pp.

4-7 ROWE Reactor Operator Training Manual, pp 3-202 - 3-211 and 3-241 - 3-261

.

e

_

v.

..

1._ ERINCIELES DE NUCLEAR _EQWER_ELau!_DEEROIIONA PAGE ' 17 -

IWEE"0DXWorICSa_HEAI_IEd"SEEE_AND_ELUID_ELOW ANSWERS -- YANKEE ROWE-85/10/29-HEMMING, W.

-

.

_

.

ANSWER 1.03 (2.00)

c.

C (1-K )= C (1-K )

1

2 50 (1

.9)= X (1.95)

5= X(.05)

X=100 counts C.5 solution,

.5 answer 3 (1.0)

b rho = K-1/K K-1/K = K-1/K

1

2

.9-1/.9=.95-1/.95

.1111=.0526

.1111.0526=.058,5 C.5 sole

.5 answer 3 (1.0)

.

REFERENCE SGNP, Suberitical Multiplication lesson, P.

53 Review of Kinetics, P.

KA001/000,KU.49,2.9.

Cook Theorwe PP. I-4.13-15.

.

3-155 - 3-160 ROWE Reactor Operator Trainins Manuale PP

.

ANSWER

'1.04 (2.5.0)

.

Les c.

-MORE NEG.

b.

HORE NEG.

'

c.

HORE NEG.

d.

LESS NEG.

o.

MCRE NEG.

C0.5 each3 REFERENCE ROWE Reactor Operator Training Manuale PP 3-202 - 3-211

.

ANSWER 1.05 (1.00)

s.

False b.

False REFERENCE IP-3 ECI Rx Theorwf Chapter 7, Pugws 21, 22, and 27 DCC Rx Theorw Review Twnt, PP.

1-5.42 -.50 SHNP, RT-LP-1.13, PP.

11-18.

.

_

.,

_-

.

14. ERINCIELES_DE CUCLECE_20WER_RLCHI_DEEROIIDWA P A2E * 18..

IMEC20DXHOCICS2_WESI_ IRA SEER _dND_ELUID_ELOW f.NSWERS -- YANKEE ROWE-85/10/29-HEHMING, W.

.

e.

3-233 ROWE Reactor Operator Training Manuale

_

-

.

ANSWER 1.06 (4.00)

D.

+/- 10%

b.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months c.

Power reduced to 10%

d.

C1 0 each3 REFERENCE SQNPe Review of core poisons lusson, p.

KA004/000,K3 20e3.6.

C:ok Theorve PP. I-5.57-77.

SHNPe RT-HO-1 11.

ROWE Reactor Operator Training Manuale Sve. 3e Pr-241-261 and Fig. 46 ANSWER 1.07 (2.00)

-

NI Power would be adjusted to a lower value than the actual reactor ecuer C1,03.

This is causwd bw the lowering of the average fwedwater tCSPeratu the indicated feedWater teekerature used in the coleulatio{e,ys.

(2.0)

n T1%4J.

k Q.* d el M b i

_ ' - 4 et.ods cre m M 3 m0 07 9 L

REFERENCE ROWE Reactor Operator Training Manuale Sve.

2, PP 17-20, 26-27, 30-31,

.84-85e 100-107

',

ANSWER 1.08 (3.00)

c.

592 - 593 degrees F depending on how round-off is done.

.

b.

188 degrees F of superheat per superheat tables.

500degreesF.q'f6

[1.0 eachl c.

REFERENCE ROWE, Steam Tables and No111er chart

l

=

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

.y__

.-_w

- _ _,

-,_3

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

_

-

__,_m

.

_

._

..

1.__ERINCIELES DE_HUCLEAE_00WER_ELEMI_DEEESIION.

P AGE ' 19 -

IMERMODXM^01CS4_WEAI Ita' SEER _cWD_ELUID ELOW Z

_

CNSWERS -- YANKEE ROWE-85/10/29-HEMMINGe W.

l l

i

-

_-

,

i ANSWER 1.09 (2.00)

c.

Choice 2.

(0.5)

b.

Choice 2 - A second Pump in Parallel Will on1w double Power reauirements while doublins flow (at the same-

'

resistance)

(0.5)

Choice 1 - Doubling the speed of the Present Pump Will double the flow (no change in swstem resistance)e but will increase Power reeuired bw 8 times.

(0.5)

Choice.3 - A 2' stage Pump will increase head, but will not double flow, even if resistance is hvid constant.

(0.5)

d REFERENCE

'

ROWE Reactor Operator Training Manuale Sec. 2e PP 49-51s 90-92

.

<

CNSWER 1.10 (2.50)

o.

Delta T less than full load delta T (42 F)

CO.53 b.

Decrease CO.53 c.-

1.

Swstem above sat. Pressure for the hottest Point of swstem.

2.

Delta T less than 100% Power delta T.

s,Aso a Co.5 each]

(S/Gs operable) W.,iroumah.-4fller*3 3.

Ensure adeouate heat sink

.

Ts.)

c. Tp, u

,g _ r3 pyg,.ru 4.

Z.p % AW.

ggggggggeao.a a w h a co<.= J Tc. 4.T*

.

7,3 ROWE Reactor Operator Training Manuale Sec.

2, PP 54-63 and Problees.

ANSWER 1 11 (1.50)

.

o.

Increase b.

Decrease-c.

Increase CO.5 each3 (1.5)

REFERENCE TP Thermodwnamics and Fluid Flow Topics, P.

196-203.

Pr 149 ROWE Reactor Operator Training Manuale Sec. 2e PP 72-79

.

'.

.

1 __ERINCIELES_DE_ NUCLEAR 20WER_ELANI.0CER4IIQUz PC.GE ' 20.

IHERZODYN2CICSA_HECI_IECNSEER_LUD_ELUID_ELOW ANSWERS -- YANKEE ROWE-85/10/29-HEMHINO, W.

-

,

ANSWER 1.12 (1.00)

TcVe is determined bw the amount of Pune heat and the steam it does not change.

Power decreases dune Pressure setting

-

at a -1/3 DPH rate to source level.

(1.0)

REFERENCE Ycnkee Rowe Reactor Operator Training Manual (ROTM)

Ch8P. 3 PP.

199-2118 144

.

!

.

'

.

,

2.__CLCCI DESISM INCLUDICG SCEEIY CMD EMERGEMCY S%SIEBS PcGE 21 '

CNSWERS -- YANKEE ROWE-85/10/29-HEMMING, W.

'

~

.

ANSWER 2.01 (3.00)

t ank.(7k-l)fDt.39) E. 5 w a 3 c.

Steam-Domin water storage tank.

(1 0)

Electric-Primarw water storage

.

b.

Building heating swstem.

42 and 43 main. steam headers.

C.5 ea3 (1.0)

c.

Charming Pumps discharse header.

Safetw Injection swstem.

C.5 es3 (1.0)

REFERENCE

,Rswe, RSTM, P.

3-93, 3-101.

.

CNSWER 2.02 (2.00)

c..

Causes rapid closure of the control valves when the acev1wration of the turbine is 3% of rated speed Pwr second or drwatwr.

(1.0)

-

D.

A reactor scram and turbine trip will occur.

(1.0)

REFERENCE Roue, RSTM 6-41.

ANSWER 2.03 (2.50)

o.

A 10 second time delaw is used to allow voltage on the

<

emergenew bus to return to normal beforv starting the HPSI (1.0)

Pump.

b.

>/= 460 Volts.

(0.5)

,

c.

Overspeede overcranke high water tenPeraturee and-low oil (1.0)

Pressure.

REFERENCE Rcwer RSTM 19-22e RSTM 9-3-le RSTM 3-1, 3-2.

i

.

24__ELAWI_DESIGi'_ INCLUDING _SOEEIY_CND_ECERGENCY_S%SIEBS POGE' 22.

ANSWERS -- YANKEE ROWE-85/10/29-HEHMINGe W.

l

'

-

_

,

CNSWER 2.04 (3.00)

O.

To inject borated water'into the MCS cold leg in the event of a larse LOCA.

(0.5)

b.

LOCA pressure-473 esis.

(+/- 10)

Water injected-700 cu.f t.

C.5 es3 (1.0)

c.

1294 - 1425 esis....used as injection pressure on SI actuation.

500 psis............used to suPP1w the Pilot actuators on three accumulator relier valves.

100 psis............used to open three trip valves (604eSea)

and to close trip valve 608 on accueulator low level.

C.2 es pressuree 3 ou Purpose 3 (1.5)

,,

'

REFERENCE R wee RSTM 19e PP.

19-49 and 53-56.

.

CNSWER 2.05 (3.00)

,

o.

The SDC is used to cool the MCS from 330 F and 300 esig to 140 F or less du:ing the final stages of plant couldown.

The SDC also removes decaw heat over a long Period of time following the cooldown.

(1.5)

cannot be opened unless Pressurizer (MOV-553 and 554)khe Purpose b.

Valves is<375esidif is to prevent inadvertant Pres.sure overpressurization of the SDC swstee.Co,1p (1.0)

c.

The LPST cooler can be used.

(0.5).

REFERENCE

,

R; wee STM Ch. 21, p.1.

-

.

e t

s

',

.

,

.

2*- ELCOI_DESIGD_ INCLUDING SAEEIX eWD_ EMERGENCY _SYSIEMS PAGE 23 '

CNSWERS -- YANKEE ROWE-85/10/29-HEMMINGe W.

-

'

.

ANSWER 2.06 (3 00)

Co.ts)

'

O.

1. NST,at 150 Psis.G M)

2. VC, Drain Tank on the Brass Box Drain,at 48 Psis Co ts).

(1.0)

Sune Co.ts)

b.

1. When Component Coolins Surse Tank level is low M nerM %

rp ge.

2. Could cause a 3FP trip.

3. Domin wate r 49usT via. LPsv % C.5 ea3 (1.5)

b.-f W c.

A hose connection Permits the use Of fire Water as an emersonew source of water.

(0 5)

REFERENCE Rcwee STM Ch. 20, p.19,21.

CNSWER 2.07 (3 00)

a.

The steam suPP1w temperature regulating valve on the tank heater is bweassed.

(1.0)

-

b.

Thew would remove boric acid from the coolant therebw causing a change in reactivitw (1.0)

c.

To Prov e th volume reauired to suench Pressurizer safetw valve discharme.

(1.0)

REFERENCE o.

STM 17-11 b.

STM 16-12 c.

STM 16-16 CNSWER 2.08 (3.00)

lo.t3 Co.23

c. To provide adeauste flow,thrdush the air ejector,and sland steam condense rs CoJ.3.

(0.6)

b.

1. High Vapor Container Pressure W/ Low main steam Pressure 2.

Overcurrent

3.

Undervoltase 4.

Stuck breaker (1.6)

c.

1.

200 esis +/-20 esis 2.

750 Psis +/-50 esis (0.6)

.

.ym___

_ _ _ _ _ _ _

_ _ _ _,,. _ _ _., _, ___

_,

_

__ _

_,

'

.

-

.

2 __ELC I_DESIGS_ICCLUDINJ_SeEEIY_CMD_EMERGENCZ SYSIEMS Pt.0E ' 24.

ANSWERS -

YANKEE ROWE-85/10/29-HEHMING, W.

REFERENCE

'

STM Chap. 3 PP.

'17,

-

.

CNSWER 2.09 (2.50)

c.

Bw maintaining the Main Coolant Swstem dwnamic and static Pressure head.at the Pump impeller above saturation Pressure. C.753 Minimum

'

(1.5)

M 2.co pseg okees.M.oolant Pune ope]ation is 230 PSIGyco:>.7-'rrT pressure for Main C pnm.ss o%.O 37C b.

The differential Pressure drops (from 99 to 78 PSIG) CO.53 duw to the change in coolant densitw. C0.53 (1.0)

REFERENCE STM 13-10

,

-e e

4

a t

!

-

l l

.

.._---,

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

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

.....

,,_

r.

,_,.r__,-.-7,._m.-., - - _., _ _ _ _ _,

.

'.

.

3.__INSIRUZENIS_ AN1'_CD*jIRDLS Pt.0E * 25 -

ANSWERS -

YANKEE 90WE-85/10/29-HEMMING, W.

-

~

,

_

,

CNSWER 3.01 (1 50)

c.

SDCP suction.

b.

LPST toeperature.

e.

140 F.

C.5 each3 ( 1~. 5)

REFERENCE R wer STM 21-8, 21-g.

ANSWER 3.02 (3.00)

c. Charming flow from the puePs will du to zero andthePuers(dW#,=)

(1.0)

will trie.

b. Charming Pump D2 can be used bw Pulling the F-8 fuses located

-

inside the main control board.

Charmins pumps 1 and 3 can be used bw manuallw contro111ris the Puers speed locallw at the PuSP.

C1.0 each3 (2.0)

REFERENCE Rswer RSTM, p.

15-24, 15-25.

CNSWER 3 03 (2 00)

a.

High SUR of 1.5 DPM on wither I.R. Ch a rine l s.

(0.5)

b.

1. Placing selector switch its 'all in' Position.

2. High Tave with selector switch in ' auto'.

3. Manual switch to 'in' position.

C.5 each3 (1 5)

,

REFERENCE R:we, RSTM'34-13e 34-15.

.

O

- - - - - -

- - - - - - - - - - -. -.

.. -

..

,

i

.

3.__IMSIRUMECIS_eMD_CD IROLS PAGE' 26.

,

ANSWERS -- YANKEE ROWE-85/10/29-HEMMINGe W.

f

'

-

.

ANSWER 3.04 (2.00)

.

o.8 Manual.

t.Undervoltase.

83 *O **k W **

s 0vercurrent.

4*$ Loup bwpass valve closed. g g

dEither Th or Tc stop valve closed.

C.

each3 (1 5)

* y..lfL. *0]$$$ n Y.-- t='e as-% ~:*-P

'***'

d n% 08 REFERENCE Rcwer RSTMe P.

13-16e-17e-18e-20.

CNSWER 3.05 (2.50)

.

a.

Low steam line pressure and high containment Pressure.

(1.0)

b.

Condensate PueP trip and reactor trip.

(1.0)

.

c.

1800 Phis.

(0.5)

REFERENCE Rcwor ROTHe Chapter 9, P.

7-11. Chapter 6, p.6-97e 6-85.

ANSWER 3.06 (3.00)

o.

PR-LT-6 (NR) indicates low level.

PR-LT-8 (WR) indicates low level.

51 2 1

>:1.

C.5 each3 (1.5)

PR-LT-705 (WR) iMi c t s. 41 - y mc s

b.

PR-LT-6 (NR) indicates hisher than actual.

PR-LT-8 (WR) indicates hisher than actual

,

PR-LT-705 (WR) indictes lower than actual. C.5 each3 (1.5)

REFERENCE Rcwer FSAR chapter 201e ROTH 6-43 44.

.

,

.

3.__IESIEUZESIS_AND CD5IROLS P^0E'27-

'

CNSWERS -- YANKEE ROWE-85/10/20-HEMMING, W.

'

-

.

'

ANSWER 3.07 (2.50)

o.

Loor 1 hot los.

(0.5)

Co.t]

CO*'O b.

1. Resets $'LTOP Swstem Misalisne 1 arm on MCB.

he *LTOP Swstem Armed'

2. When MCS is less than)450 ps alarm-will actuate (0 25

"LTOP Swsten Hish,P alarm is unabled 400 psis.

Enables Power oPerateV,fessure*

3. The and motor operated relie alves to 4. actuate at 500 Psin k'E)

C.5 each3 (2.0)

REFERENCE R;wer ROTH 4-54, RSTM 14-20.

ANSWER 3.08 (2.00)

Steam flow (Pressure compensated)

-

Steam senerator level (2.0)

REFERENCE Engineerins Design Change 83-03 CNSWER 3 09 (2 00)

o. Low condenser vacuum ---18 inches (0.5)

b. Must be opened manuallw at the anzzaninv.

(0.5).

c. Should be placed in the manual modw.

If placed in Autu. the valve will return to reeuired setroint at a rate determined,bw the error between actual Pressure and the Controller set Point.

(1.0)

,

REFERENCE Engineering Design Change 83-03

.

+

,

.

3.__IMSIRudEWIO_CCD CDDIt0LS PCIE* 28..

' ANSWERS -- YANKEE ROWE-85/10/29-HEHMING, W.

-

,

ANSWER 3.10 (1.50)

0.' Hesawatts Mesavars Constant Power Factor (1.0)

Hwdrogen, Pressure

SfF generator voltage sheds b.

C.,

field current bw 7 w

inductive load.

(0.5)

REFERENCE ROTM Chap. 9

'PP.

1-68 1-7 ANSWER 3 11 (3.00)

o.

(1)

Bleed Line Process Radiation Monitor.

(2)

Accident Area Radiation Monitor.

CO.5each3 (1.0)

.

b.

Survew Valve Room pipins with Portable radiation instruments to verifw bleedline radiation levs1.

(1 0)

c.

Reduce Power commensurate with swatem donatids C0.53 and maximize purification flow. CO.53 (1.0)

REFERENCE OP 3100, p.

1, 2 a

e e

}

.

' d.__EROCEDURES_e_WDEd La_dBHORCCLs_ EMERGENCY _A"D PAGE*~2F'

R&DIOLOGICOL_CODIEGL CNSWERS -- YANKEE ROWE-85/10/29-HEHMINGe W.

-

.

ANSWER 4.01 (2.00)

o.

Manus 11w use and throttle the omrgenew atmospheroic steam dunes.

(1.0)

b.-

To prevent exceeding the T.S.

reuuirment of 85,000 gallons.

(1 0)

ic$.d W 4mes=5bh A *

d M wM%

REFERENCE Rowee OP-3054.

ANSWER 4.02 (1.50)

ottachment A-No auto isolation of 41 2400 Volt bus (normal trie).

Attachment B-Auto isolation and re-enersization of 41 2400 Volt bus.

Ottachment C-Auto isolation and de-enersization of 41 2400 Volt bus.

-

C.5 eachJ (1.5)

.

REFERENCE Rower OP-30000 p.1.

CNSWER 4.03 (2 50)

o. Must be in Hot Standbv within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(1 0)

^

(. 5 lo Cwithin 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . 0 Must proceed to Cold Shutduwn,)below 300 evid r..

(1 5)

b.

REFERENCE

,

Rower OP-3007, p.1.

.

ANSWER 4.04 (2 00)

The direction is a note located in the svartums section which applies to all cases. f/.83 The direction is there to emure the smoke is not entering the control room from an external source. [/.43 (2.0)

~

.

....

.-.

.

m

-

.

d.__EROCEDURES_=_W2RMEL4_eBM'RM2L4_ECERGECCY_CWD PAGE' 30.

R2DIOLOGICCL_CO2IROL

-

.

ANSWERS -- YANKEE ROWE-85/10/29-HEHMING, W.

'

REFERENCE

-

'

.

R: wee OP-3010e P.1.

ANSWER 4.05 (3 00)

O.

1. If condenser air eJactor radiation and/or steam line radiation is high AND containment Pressure / radiation are normale so to OP-3107, S/G Tube Rupture.

2.

If steamline Pressure is low and decreasing in one or more S/G'se so to OP-3201e Steamline Break.

3.

If VC Pressuree OR VC radiation are high or increasinse so to OP-3106, Loss of Huin Coulant.

C.5 each3 (1.5)

~

b.

-Initiate OP-3000. (Emersonew Shutdown From Power)

If SI is sPuriouse so to attachment A.

-Verifw SI initiation at 1700 psis.

-Verifw containment isolation.

-Insure emersenew Power is'available.

-

-Initiate heat removal via intact S/G's.

-Initiate OP-3300. (Classification of Emersencies)

C anw 5 at.3 each3 (1.5)

REFERENCE Rcwee OP-3051, P.2-3.

CNSWER 4.06 (1.00)

1. Switch inoperable SI channel to manual.

2. Commence realimnment of SI Swstem after inadvwrtant actuation.

(1 0)

..

REFERENCE R; wee OP-3111e Pe 2e ANSWER 4.07 (1 50)

200 F t.53 CCW water must flow at 135 see C.53 for 20 minutes. C.53 (1 5)

.

~

'.

.

,.

A __EROCED'J ES_=_NOR CLa_4B ZEMCLa_ EMERGENCY _cHD PAGE

RODIOLOGICCL_CDUIROL ANSWERS -- YANKEE ROWE-85/10/29-HENHINGr W.

'

~

REFERENCE R;wer OP-3115e P.2.

.

ANSWER 4.08 (3.50)

Coin turbine.

92 Boiler feedpump.

63 Boiler feedeuer.

C ndensate recire m.4/ M OC3 Z-126.

,

OCB Y-177.

G:nerator exciter field breaker.

C.

eachJ (3.5)

0 2, Me d w > & 0 M

REFERENCE R wer OP-3257, p.2.

ANSWER 4.09 (2.00)

-

Unusual Event..

01ert.

Site Area Eeersonew.

0:neral Emersenew.

C.5 each3 (2.0)

REFERENCE Rouer 0P-3300s P.1.

CNSWER 4 10 (2.00)

o.

-Via the noreal charmins liner anw mode.

-Via the Loop Fill Liner <300 psis'or </= 200 F.

C.5 each3 (1.0)

b.

When MCS Pressure is >/= 1000 psis or >330 F.

(0.5)

c.

</= 330 F or < 1000 psis.

(0.5)

REFERENCE Rower'0P-2151, p.1-2.

.

A.__tROCEDURES =_C02:eL4_CBW0treL4_EBERGENCX dWD PAGE.32..

ECDIOLOGICAL_COMIROL ANSWERS -- YANKEE ROWE-85/10/29-HEMMINGe W.

>

.

,

ANSWER 4.11 (3.00)

O. -Anw area access to which is controlled bw the licensee for Purposes of Protection of individuals from exposure to radiation and radioactive materials..

-Anw area, accessible >to Personnel, in which there exists radiation...

at such levels that a major portion of the bodw could receive in one hour a dose in excess of 5 arene or in anw 5 consecutive daws a dose in excess of 100 mrom.

-Exposure to radiation in restricted areas oP in the course of emploweent in which duties involve exposure to radiation. Shall not include exposure for the purposes of medicci diagnosis or theraew.

C.5 each definition 3-(1.5)

b.

1 1/4 rem per auarter t.33 3 rem per auarter not to exceed 5(N-11).C.63 Must have form NRC-4 on file AND Past exposure calculated. C.43 (1.5)

.

REFERENCE

.

R wer 10 CFR 20.3e101eand 202.

ANSWER 4.12 (1.00)

-Maintain a 500 Psin earMin betWeen Plant conditions and the NDT Upper Limit Curve.

-Dedicate an operator to monitor MCS Pressuree P:r. heaters, SI Pueese cnd valve lineup.

C.5 each3 (1.0)

REFERENCE Rcwee OP-2100, P.2.

.

!

.

P g-TTAcMMK R

~

.

U.

S.

NUCLEAR REOULATORY COHHISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

_XASKEE_EDUE_____________

_

-

,

REACTOR TYPE:

EWE-WECd________________

DATE ADMINISTERED _8541022S________________

EXAHINER:

MEd

p,

_________

C_)T/

-

APPLICANT:

q

.j..)

__

____

,

INSIEUCIIQWS.IO_aEELICANIl Uco separate Paper for the answers.

Write answers on one sidW On1W.

Stcele ouestion sheet on top of the answer sheets.

Points fur each curstion are indicated in Parentheses after the ouestion. The passins Crtde reauires at least 70% in each catesurw and a final gradw of at locst 80%.

Examination papers will be Picked up six (4)

hours after tho examination starts.

% OF CATEGORY

% OF APPLICANT'S CATEGORY

__UALUE. _IDIAL

__. SCORE _._

_UALUE__ ______________CAIEGORY_____________

-

A.oo

.25.00__

35e&&A.__________

________ 5.

THEORY OF NUCLEAR ' POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

.25ree _k _-EHSrco s _ _ _ _ _ _ _ _ _ _.

6.

PLANT SYSTEMS DESIGH, CONTROLe

_ ______

AND INSTRUMENTATION 2.L.o o

_2 5. 0 0_ _ _ &&r&& 4 _ _ _ _ _ _ _ _ _ _ _

________ 7.

PROCEDURES - NORMAL, ABNORMAL, ENER0ENCY AND RADIOLOGICAL CONTROL

.1Q. 00 ad.Ob

.2txte_A _2trCDt ___________

________ 8.

ADHINISTRATIVE PROCEDURES:

CONDITICNS, AND LIMITATIONS 9f.co

,

ketr2C_A 100.00

_______. TOTALS

..._____..

FINAL ORADE _________________%

All work done on this exaininution is sw own. I have neither diven nor received aid.

_____.._____________________________

APPLICANT'S SIONATURE

.

m A

'

..

.

5.__IMEORY_DE_WUCLECR_ECWER_ELCOI_DEEE0IIQJa_ELUIDSa_CWD PAGE'

IMERMODXW2OICS QUESTION 5.01 (3.00)

'

-

.

Uce the steam tables and associated Mollier chart to answer the cuestions bolowe label auantites with Proper units.

o.

During cooldown and dvPressurization, wou are reuuired to remain 50 degrees F subcooled.

As the Pressure dvervases through 2085 Pside what is the maximum Tavs allowed (nearest degrew F)?

(1.0)

b.

Steam is leaking from a Pipe flange into a room.

A thermocouPlv (TC)

Placed in the leakase stream reads 400 dvsrevs F.

How manw desroes of suPerheat is this?

(1.0)

c.

If the thermocouple in Part b had read 340 dvsrevs Fe and the steam Pressure inside the Pipe was 540 Psive what would wuu estimate the steam temperature to be at that Pressure?

(1.0)

.

QUESTION 5.02 (1.00)

.

The reactor is Producins 100% rated thermal Power at a core dulta T

.cf 42 degrees and a mass flow rate of 100% when a blackout occurs.

Natural circulation is established and core delta T does to 29 d0srees.

If decaw heat is 2%e what is the core mass flow rate (in %)?

DUESTION 5.03 (2.00)

Acsume one Reactor Coolant Pump trips at 30% Powere without a roactor Protective swstem actuation or a change in turbine load.

Indicate whether the following parameters will INCREASEe DECREASE or REMAIN THE SANE.

c.

Flow in the OPERATING reactor coolant loors.

.

b.

Reactor vessel Delta P c.

Core Delta T d.

An OPERATING LOOP steam generator steam flow (2.0)

(*****

CATEGORY 05 CONTINUED ON NEXT PAGE

- - t*)

.

O

r-

.

..

5.__INEORZ_DE tuCLEAR.EDWER_ELA3I_DEERAIIOW2 ELUIDSz_AWD PCGE 3 --

ICER:0DZMODICS QUESTION'.5.04 (1.50)

'

-

.

What effect does nucleate boiling havw on heat transfer in the core (increase,. decrease or no effect)?

Explain the mechanism (1.5)

of this effect.

' QUESTION 5 05 (1.50)

A variable speed centrifugal pump is operating at 1/4 rated speed in a closed swstem with the following parameters:

Power = 300.Kw Pune delta P = 50 Psid Flow = 880 see What are the new values for these Parameters when the rump speed 10 increased to full rated speed?

(1.5)

.-

.

QUESTICM 5.06 (1.50)

What is the most significant twee of heat transfer (conductione convection, or radiation) taking Place under wach of the followins ccnditions?

Consider each condition separate 1w.

c.

Nucleate boiling.

b.

Accident condition in which coolant is boiled and converted to steam in the reactor vessel.

c.

Heat from fission thru the fuv1 rod.

d..Decaw heat removal bw natural circulation of coolant.

o.

Decaw heat of fission Products to clad surface.

CO.3 each3

,

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

- - - - )

..

~'e

,,--,,ya,n

,

.,

3.__IMEDRY_OE_CUCLECR_EDWER_ELCCI 0EERAIION4_ELUIDS4_AWD PCOE ' 4 IWER20DY 4dICS

QUESTION 5.07 (2.50)

-

.

o.

How AND whw does the Doppler Defect change as reactor Power is increased?

(1.0)

i b.

How does each of the followins affect the Fuvi Tumewrature Coefficient (Hore negativer Ivss negativer or nu vffect)?

1.

Accumulation of Xenon and KrwPton sases in the fuel to clad map.

2.

Increase in the amount of fuel to clad contact.

3.

Buildup of PU239 over core life.

(15)

.

QUESTION 5.08 (1 50)

o.

Provide TWO reasons for Xenon contributins more nwsative reactivitw at full Power than Samarium.

(1.0)

-

i b.

Explain whw wou agrew or disagree with the followins statement:

'Eauilibrium Samarium concentration at 50% PuWer is approximate 1w half its concentration at 100% Power.'

(0.5)

QUESTION 5.09 (1.00)

For a reactor operatins at a constant Power and temperature, the thermal neutron flux near EOL will be (GREATER THANE SHALLER THAHe or THE SAME AS) the flux near BOL7 EXPLAIN.

(1 0)

.

(*****

CATEGORY 03 CONTINUED OH NEXT PAGE

- - - - )

-

-. -

.

-

..

-

- *

s

..

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!51__IHEDRY_DE_WUCLEct 20WER ELfMI_DEERAIIDNa ELUIDSz_AWD PAGE 5-

'IWERMODYWOCICS

.

QUESTION 5.10'

(3.00)

'

-

.

o.

Define the ters * Shutdown Marsin*.

(0.5)

I b.

The reactor is at 70% Power with rod control in automatie. Power

' level is increased to 80%.

(Assume buron is constant throushout and sufficient rod worth to accomodate the change.)

EXPLAIN each answer.

'

1.

What happens to Shutdown Marsin immediatelv following the Power change?

( 0. 5 ) -

2.

Five hours after the transient?

(0.5)

3.

Thirtw hours after the transient?

(0.5)

'

c.

Would wour answer to Part

b.1*

be anw different if the operator had adjusted baron concentration for the Power change?

EXPLAIN.

(1.0)

.

A-GUESTION 5.11 (2.50)

CenPare the CALCULATED Estimated Critical Puvition (ECP) for a otartuP to be Performed 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a trip from 100% Powere to the ACTUAL control rod Position if the following events / conditions occurred.'

Consider each independent 1w.

Limit wour answer to HIGHER thane LOWER thane or SAME as the ECP.

o.

The FOURTH coolant Pune is started two minutes Prior to criticalitw.

(0.5)

b.

The startue is delaved until 0 hours0 days 0 hours 0 weeks 0 months after the trip.

(0.5)

c.

The steam dump Pressure sWtPoint is increased tu a value Just

below the Steam Generator PORV setPoint.

(0.5)

'

!

d.

Condenser vacuum is reduced bw 4 inches of Hercurw.

(0.5)

o.

All Steam Generator invels are being raised bw 5% as the ECP is reached.

(0.5)

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

- - - - )

'

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-.-, _ __ _,_,. _ _-._____ _ _ - _. _ _ _..,._. _.___-_ _ _.

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

-

,

.. _ ~

-

.

-

..

__.

.

- -

-..

-

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-3.__ICEDRY_DE_MUCLEit_20MER_ELCOI_DEERCIIOUa_ELUIDSa_AWD PAGE'

6.

..

.

~IMERMDBZW2MICS

'

.

,

QUESTION 5.12 (1.50)

~

'

-

.

!

Compare the responce of the followins at BOL and EOL to a dropped rod at full power. (Assume all rods out, the dropped rod has the same corth at BOL and EOL, and.the reactor does not trie, no operator cction.)

o. Initial power drop. (Greater or Less) Explain.

(0.5)

'

b. Rate of power recoverw. (Faster or Slower) Explain.

(0.5)

c.

Final steadw state Tave. (Higher or Lower) Explain.

(0.5)

GUESTION 5.13 (2.50)

'

o.

What two coefficients of reactivitw are used tu calculate the Isothermal Temperature Coefficient?

(1.0)

,

b.

HOW and WHY is the magnitude of the Isothermal.Tvererature Coefficient effected bw an decrease of buron concentration from 500 rpm to 100 Pen at EOL conditions?

(1.5)

,

G

(***** END OF CATEGORY 03

- - - - )

-

+

.

a*._RLCOI_SYSIENS_DESIGMa_CD"IROLa_AND.IUSIEUZEMIAIION PAGE* 7

.

_

QUESTION 6.01 (2.00)

'

.

,

c.

What is the purpose of the Auxiliarw Governor in the Main Turbine Control Swstem?

'(1.0)

b.-

What are the conseauences of Pulling the Auxiliarw Govvenor Test Lever OUT while the reactor is at 100% power?

(1.0)

QUESTION 4.02 (2.50)

The followins pertain to the Electrical Distribution Swstem at Ycnkee Rowe.

o.

What is the length of and basis-for the time delaw in startins the High Pressure Safetw Injection (HPSI) Pumps upon recient of a Safetw Injection Signal?

(1.0)

b.

What is the voltase above which the diesel generator output breaker will automatica11w close?

(0.5)

..

c.

State the FOUR alarms and tries that are affected bw the ' RESET *

Position' on the emergenew diesel senerator local start switch.

(1.0)

.

M. 00 QUESTION 6.03 (4,44)

o.

Boric Acid Mix Tank toneerature must be mainteined above 133 DEO F when adding makeup water to the tank.

How is this accomplished when the makeue water is cold?

(1.0)

b.

Whw are the anion resin bed ion exchangers valved and locked out of service during normal operations?

(1.0)

-

Whw ust ve a

t

,

.

deh[ hrk 'd.".

(***** CATEGORY 06 CONTIHUED OH NEXT PAGE *****)

.

_..

_'ELAWI_SYSIEMS_DESIG"a_COMIEDLa_AND_INSIEUMENICIIDW PCCE*

8.

'

QUESTION 6.04 (2.50)

'

_

-

.

The following concern Main Coolant Punes (MCP):

o.

How is cavitation prevented in a MCP and how are net Positive suction head (NPSH) reauirements ensured?

(1.5)

5.

How does the differential Pressure developed bw a HCP change as coolant temperature increases from 100-DEO F to 510 DEG FT Explain (1 0)

wour answer.

QUESTION 6.05 (3.00)

'

o. ~ Describe how a loss of control air Pressure will effect the 61 (1 0)

AND 43 charming Pump.

d b.

Describe how each of the three charming Pumps can be used to control Pressurizer level if cont *rol air is not available.

(2.0)

..

QUESTION 6.06 (2.00)

o.

List the five conditions that will cause 42 MCP to trip.

(2 5)

b.

What interlock must be sat,fied for a loop stor valve to open?

(0.5)

i

.

QUESTION 6.07 (2.50)

-

c.

What signal (s) will energize the Non-Return Valve (NRV)

automatic trip relaws?

(1.0)

r b.

When the NRV's receive an automatic trip signal while the reactor is at full Powert what other automatic actions saw be initiated as a result of the same closure signal?

(1.0)

c.

At what point during an MCS couldown is the NRV auto close blocked?

(0.5)

.

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

.

y,.,,.,__..m

._-._,.._.r_--,.

-_,.~.~-.._--.,,~7

- -, _ _ _. -

-.,,,

,,. -... -. - -.

.

-. - -

-

,m

'

-

.

6.__2LeMI_S%SIEMS DESIGWs_CODIE0L2 AWD_INSIEUMEWIAIT.DW PCGE 9-

.

QUESTION 6.08 (2.50)

'

.

,

c.

From what part of the HCS does the Low Temperature Overpressure Protection (LTOP) swstem receive its overating signal?

(0.5)

b.

Describe the four functions of the ' Kirk Kew Interkock' when it is in the * ARMED * Position.

(2.0)

GUESTION 4.09 (2.00)

n. What is the automatic trie signal and setpoint that will close the Steam Dump valve MS-PCV-4027 (0,5)

b.

If the trip condition has not clearede how can MS-PCV-402 be reopened?

(0.5)

c. After the trip condition has cleared, in what mudo (auto or manual) should MS-PCV-402 be shifted to recover the valve?

(1.0)

Explain.

.

GUESTION 6.10 (3.00)

a.

What radiation monitor (s) would be used to indicate a sudden fuel failure?

(1.0)

b.

How would an operator distinsuish between a fuvi failure and a failure of the detector or other circuit malfunction?

(1.0)-

c.

Describe in general terms what action would be taken to minimize the radiological effects of this failure.

(1.0)

.

(***** END OF CATEGORY 06

- - - - )

..

.

,

_ _ - - _ - _ _ _.

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_ _. _

_ _ _ -. - - - -.-

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-2 __RROCEDURES.=.MORH2La_ABNDEMOLa_EMERGENCX.iWD PAGE' 10.

,

RADIOLOGICOL CDMISOL

-

'

GUESTION 7.01 (2.00)

-

For each of the listed responsibilities or authoritiest indicate

chether it corresponds to the Shift Supervisor (SS) Positione l

SuPervisorw Control Room OPeratur (SCRO) Positione or BOTH.

(Use a separate answer Pase)

1. To know what rec o rds,- rePortsp surveillance Procedurest and loss are reeuired to be maintained and direct their completion.

2.

To determine anw plant activitw which could Jeopardian Personnel safetw or Plant WGu1Psente 3.

To grant Permission to other departments to perform their Procedures, such as operational or surveillance Procedures when reuuired bw that

' Procedure.

4. To obtain assistance from other Plant Personnel When conditions warrant.

5. To scant Permission to Personnel to enter vital areas.

...

6. To shutdown the reactor when it is determined that the safetw of the Plant is in JeoPardw or when oPeratins parameters exceed reactor

,

Protection setroints.

7.

To be explictlw aware of when a safetw reinted swstem is removed

from or returned to service and to ensure'the information is

'

transmitted to all appropriate Personnel.

,

8.

To maintain the skills of the operating shift bw Passins on infor-nation sained from LERs, standing orderse and changus to swstems

,

and Procedures.

QUESTION 7.02 (3.00)

.

s.

Procedure OP-4708, Determination of Shutdown Marsine Provides a

-

method of calculating shutdown marsin (SDM) for three conditions.

.

Beins specifica list the three conditions and include MPP11 Cable modes.

(1.5).

'

b.

When must a SDH be calculated?: Include anw applicable modese time limitse or other conditions.

(1.5).

>

(*****

CATEGORY 07 CONTINUED ON NEXT PAGE

- - - - )

-

.

w-

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-,-rw-

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_-

.

-

.

-.

.

-

2.__EEDCEDURES =_ NORMAL 4_ABWORMela_EMERGENCX AND P AGE ' 11 -

RADIOLOGICAL _CONIROL QUESTION 7.03 (3.00)

'

-

.

The following concern OP-2156, Operation of the Component Cooling Swstem.

a.

What Precaution must be taken when starting a CCW PunP?

Whw?

(1.0)

b.

'If CCW M ressure drops to 50 psis with both Pumps runninst what must be done?

(1.0)

c.

State the minimum flow reoufred through the CCW Pump. What can be done to achieve this minimum 7 Whw is the minimum reauired?

(1.0)

GUESTION

'7.04 (2.00)

The followins concern OP-2151r Borie Acid Addition To The Main Coolant.

o.

List the two waws boric acid saw be added to the MCS. Bw specific as to when each can be used.

(1 0)

..

b.

When must each loop's SI MOV be locked open with it's motor operator electricallw inoperative?

(0.5)

c.

What Plant conditions are reauired in order to add boric acid to a single loop 7 (0.5)

QUESTION 7.05 (1.50)

Por OP-2101, Plant Startur 'F r o m Hot Standbwe when must'the entire SI owstem be in the Automatic Operational Lineup 7 State anw associated ocdes.

(1.5)

.

QUESTION 7.06 (2.00)

A List the immediate operator actions reuu' ired bw OP-3004, Plant Action In the Event of a Bomb Threat, Situation II, Bomb Threat Phone Call With Breach of Plant Protected Area.

(2.0)

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

e

,

.-.

_. _ -.. _.

_,

.,

.

, _. -

-.

-

'

.Z.__RR0CEDURES_=_WORZeL4_AB30RMBLa EMERGENCY _dND PAGE'12-

.

R&DICLOGICAL_COWIROL

'

QUESTION 7.07 (1.00)

-

'

-

According to OP-2100, Plant Startup From Cold Shutdown, what rceuirements must be met when MCS temperature is between 300 F cnd 440 F7 i

QUESTION 7.08 (1.00)

If the Control Room must be evacuated immediatelse what items must bo taken with the evacuating personnel?

.

QUESTION 7.09 (2.50)

According to OP-3010, Fire or Forced Evacuation of thw Control Room, what can be used to substitute fore or regain control of, the followins if thew should be lost during the casualtw. Be specific as to what is used and/or where it is located.

__

- MCS-Pressure.

C.53

- Pressurizer level.

C.53

~

- Charging pumps.

C.753

- Core temperature.

C.753 QUESTION 7.10 (1.00)

State the automatic actions that occur evr OP-3234, Total Loss of AC l

with the integritw of MC Swstem not established.

,

l QUESTION 7.11 (3.00)

.

l The followins pertain to 10 CFR 20.

l 0.

Define:

- Restricted Area.

- Radiation Area

-.0ccupational Dose.

(1.5)

b.

State the maximum allowable wholebodw ouarterlu occurational dose an individual saw rwceive in a restricted area. Whct can this limit be increased to and what must be done to increase it?

.( 1. 5 )

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

..

- - -

_

.

,

.22 _EEDCEDUEES.= NDEM2L4_ABNDEMAL2_EMERGENCX_AND PAGE '13--

RADIDLOGICAL_COMIEGL QUESTION 7.12 (3.00)

'

i

-

.

c.

-Immediate operator action st9P d of OP-3051, Loss of Main Coolant Pressure and/or Safetw Injection Actuatione is " Accident Diagnostics'. State the three subster diagnostics that comprise this immediate action. (Para-Phrasing is allowable)

(1.5)

b.

In addition to

'a'

abover list FIVE other major immediate actions stated in cn= 3051.

Sub-steps not reauired.

(1.5)

-

$

(***** END OF CATEGORY 07

- - - - )

-

_

,__

- - _.

'8 __'ADMINISIR&IIME_EROCEDURES2_CDHDIIIDWSz_AND_LIMIIAIIONS PAGE'14

-

QUESTION 8.01 (3.00)

-

.

Discuss how each of the following Prevent release of radioactivitw to the enviorment.

-

a.

Limiting Condition for Operation.

b.

Limiting Safetw Swstem Settings.

c.

Safetw Limits.

QUESTION 8.02 (1.50)

The following concern the tagging of Plant euuipment:

a.

Who (bw Job title) is the Local Control Authoritw for tagging a Diesel Generator out of service?

(.75)

b.

Who saw Perform locallw Controlled Plant tagging?

(.75)

..

G (W d

i de at

%

er n

er-r o

h i

.

a t

ti e

anw mu be ak dt.NO

* ^ -

QUESTION 8.04 (2.00)

a.

For each Technical Specification freauenew notation shown belows state the Technical Specification.freousnew (include time units). (1.0).

Me Qe She Re P

,

b.

As stated in Technical Specificationse Section 3e what is the allowable time interval for surveillance reuuirements?

(1.0)

'

i QUESTION 8.05 (2.50)

In August of 1982, Yankee Rowe was exempted bw the NRC from hav.ing to

,

!

ocet the * fixed fire suppression P&Ouirements of 10 CFR 50, ePPundix Re j

for the Control Room area.

List 5 of the 7 Justificatione that allowed l

this exemption to be granted.

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

_

, - -

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,,, - - -,, -

--,e,,,

- ' '

..

._

.-

_

_ _ _. _

.S.__ADMINISIRAIIME_EROCEDURESz_CDNDIIIONSz_eWD_LIMIIAIIDMS Pt.GE *15-

.

QUESTION S.06 (2.00)

'

-

.

a.

How manw members are reauired on the fire brigade Per Technical (0.5)

SPecificationse Section 67

-

b.-

Who saw NOT be included as members of the brigadeT (1.0)

c.-

Who is responsible-to function as the fire brigade IvaderT (0.5)

GUESTION 8.07 (3.00)

a.

As directed bw OP-3321, De-escalation and Recoverwe who has the final authoritw to de-escalate an emersonewT (0.5)

b.

Who has the Primarw responsibilitw to reco,mmend de-escalating an emersenew to the individual in Part

'a*?

(0.5)

c.

What group of Personnel confer to determine the aPPruPriate time and classification for de-escalatins.

(1.0)

_

d.

What Plant conditions should exist before de-escalation (1.0)

can be consideredt QUESTION 8.08 (2.00)

When a medical on-site emersenew exists in a radiation areae what are the guidelinese Per OP-3305, Onsite Medical emergenciese for:

-entering an area where there-is an injured Person.

!

-radiation exposure.

-moving of an injured person from the area.

.

,

l

\\

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

- - - - )

l

-

l

.

--

-

..

.

-.

. -

_ _ _ _

_

_ _ _ _ __

_

___

.

,

B.__ADMINISIR&IIME_EROCEDURES2_CONDIIIDWSz_AND_LIMIIAIIDMS PAGE *16..

QUESTION 8.09 (2.50)

~

-

.

a.

In accordance with OP-3300 Classification of Emersoncies, define:

.

-Emersonew Action Level.

-Event.

(1.0)

b.

What is the time limit established to notifw offsite authorities when needed.

When does this time period start?

(1.5)

QUESTION 8.10 (3.50)

The-followins concern Technical Specifications 3.4.1, Main Coolant Loops.

a. List the reauirements for the main coolant loops in Modes 1-5.

(1.5)

b. When in Mode 5, what can be used in Place of main coolant loops 1-4 to satisfw the oPerabilitw reauirements?

(1.0)

c. When in Modes 3, 4e and 5, the reuuired coolins Pumps saw be de-enersized Providing What two conditions are maintained?

(1.0)

~

GUESTION 8.11 (2.00)

The followins concern Shutdown Marsin (SDM).

a.

The Plant has Just entered Mode 3 from Mode 4.

(MCS temperature at 500 F). A SDM indicates'the SDM is 5.'5".

' Describe anw actions to be taken.

(1.0)

b.

List 4 of 6 factors that are considered when eciculating SDMT (1.0)

.

i (***** END OF CATEGORY 08

- - - - )

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

,,

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...

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...

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,,

_

EQUATION SHEET

.-

f = sa v = 5/

Cycle afficiency = (~.1er M -

cut)/(Energy in)

,

.

w = ag s = '/,: * 1/2 - st -

-

.

= OC" KE = 1/2 mv a = ('If

'l )/t A=M A=Ae3 a

PE = mgn

= e/t t = m2/t;fg = 0.593/tifg vp = V, + at

2 aff * C(tu -)(t )1-y,y g r0 7/g

. CltT/z) *l'1 - A*

d = 931 mi - ~~" a = V,,Ao I=If . . G = mCart 6 = UA A.7 I = I e# - n I = I,10-* #Il - Pw = W eb f Tit. = 1.3/u ' ' P = P 10,sur(t) gyg,,g,gg37, a g'- P=Pe ~ o SUR = 26.06/T SG = 5/(1 - Kgf) G = 5/(1 -- Kgfx) x SUR = 25a/ t* * (s - a)T G;(1 - K,ff7) = G II ~ "eff2) Z T = ( t*/s ) + ((a - o V is] M = 1/(1 - Kgf) = G)/G, . ' M = (1 - KdfcIIII ~ #eff1) T = s/(s - a) T = (s - s)/(T ) scM = ( -Kgf)/Kef t' = to seconds a = (Kgf-1)/Kgf-3 I = 0.1 sec:nds gf (1 + I7)]

=((t*/(TKgf)] + (I

/ I d) = I d P = (r.aV)/(3 x 1010) I d; I =2 2 l ~ Ld22

2/hr = (0.5 CE)/d (meters) t = en R/hr = 6 CE/d2 (f,,g) , Miscallaneous Conversiens Watse Parsneters . I curia = 3.7 x 1010 ens I sal. = 8.345 tem.

1 gal. = 3.78 litars 1 kg = 2.21 tem 1 np = 2.54 x 103 Stu/hr 1 ff = 7.48 gal.

1 mw = 3.41 x 100 5tu/hr

Oensity = 62.4 lbs/ft 11n = 2.54 cm Oensity = 1 gm/cd

F = 9/5'C + 32 Heat of vacort:stion = 970 Stu/lem Heat of fusion = 1..4 3w/lem

'C = 5/9 (*F-32) 1 Aca = 14.7 ssi = 29.9 in. Hg.

1 BTU = 778 ft-1bf 1 ft. H O = 0.4335 Inf/in.

. O y - -m7- ---. - - -.,,, ., -.,,. -., ,e.----e,,.m-~.,..,,.,,,.gm,.,,-..~,,,,,--- ,, , -... - -,., - -,, - ~ ~ ~

. .-. .... ' 1..

, n 5.__IHEORY_DE_WUCLEdR_ ROWER _ELADI_QEER$IIDWA_ELUIDS2_AWD PAGE 17 - IBERH0 DYNAMICS ANSWERS -- YANKEE ROWE-85/10/29-HEMMING, W.

\\

' - h# 15 % bk Nd ANSWER 5.01 (3.00) a.

592 - 593 desrees-F. depending on how round-off is done.

b.

188 desrees F of superheat per superheat tables.

c.

500 dasrees F.

C1.0 each3 , REFERENCE ROWE, Steam Tables and Nollier chart ANSWER 5.02 (1 00) -Flow is Prop. to cube root of power.

2% 1/3 Power = 1.259% flow REFERENCE _ General Phwsicse NT I FF, Section 3.2 ROWE Reactor Operator Training Manuale Sec.'2e er 54-43 . ANSWER-5.03 (2.00)

c.

Increase b.

Decrease c.

Increase d.

. Increase CO.5 ecch3 (2.0) i ! REFERENCE Summer Plant Swstems Descriptions, Auxiliarv Building Swutense Charter AB-4, P 1dI Summer Neat Transfer Thermudwnamics and Fluid l Flow Books PP 180, 211e 322, 328 GLJ 175 ! ROWE Reactor Operator Training Manuale Sec. 2e er 40-44 i l l

l ! I ^ I ! ! . - - _

- . _ ' . . . 5.__IMEDRY_DE_WUCLEdR_EDWER_ELdWI_DEEReIIDWa_ELUIDSa_dWD PAGE 18.

IMERHODYW6MICS - ANSWERS -- YANKEE ROWE-85/10/29-HEHHING, W.

- - _ , ANSWER 5.04 (1.50) Increases heat transfer CO.53.

Bubble formation /removel breaks up the laminar laver allowins cooler fluid to set to the cladding C0.53.

Also, the bubbles carrw awaw latent heat of vaporization which is released in the bulk coolant when the bubbles collaP%e CO.53.

REFERENCE Farlew Thermodwnamics Manuale Chapter 4, P 9e Chapter 5, P 10 1 Fis V-1 GLJ 137 , 'ROWE Reactor Operator Training Manuale Sec. 2r PP 72-63 ANSWER 5.05 (1.50)

= 19.2 Mw (0.5) Power (2) = Power (1)(N2/N1) cubed = 300x(4)

2 800 Psid (0.5) - 50x(4) = Delta P(1) (N2/N1) Delta P(2) = = 3520 wpm (0.5) Flow (2) = F1bw(1) (N2/N1) = 800x(4) = , REFERENCE-GPNT Vol. IIIs Ch. 2s Sect. He P.

2-234.

PT

ROWE Reactor Operator Training Manual, Sec.

2, PP 49-50 ANSWER 5.06 (1.50) c.

Convection b.

Radiation / convection (large Delta T) c.

Conduction i d.

Convection (natural) , ' . o.

Conduction CO.3 each3 REFERENCE WTHP Chapter 13 PT

ROWE Reactor Operator Training Manuale Sec. 2r PP 64-69 l l t -- r*'-7 -- - - . .

._.

.. _.. . _. '.. ....... c..._ . _. -- ., ., . 5 __IMEDEY CE_tuCLECE_EDWEE ELdWI_DEEEoIIDH4_ELUIDS4_AND PAGE 19-IHERMODYNAMICS ANSWERS -- YANKEE ROWE '-85/10/29-HEHHING, W.

' - . CNSWER 5.07 (2.50) c.

As power increasest fuel temperature increases, the Doreler Defect becomes more nesative (1.0) b.

1.

More negative.

2.

Less nesative.

3.

Jknwr negative.

CO.5 each3 (1.5) Le ss REFERENCE CPSL Reactor Theorw Chap. 14 pr. 14-7 thru 14-11 ROWE Reactor Operator Training Manual, Sec.

3, er 189-202 ANSWER 5.08 (1.50) o.

1.

Hisher fission wield.

2. Larser (thermal) absorbtion cross section (1.0) .. b.

Disagree C0.13 Eoullibrium Se concentration is not Power (0.5) dependen.t.EO.43 REFERENCE GPNT, Vol. II, Ch.

4, Sect D, p.

4-144'to 4-150.

PT

ROWE Reactor Operator Training Manual, Sec.

3, er ~243-244, 261A-267 ANSWER 5.09 (1.00) Greater Than to.537 RR = Macroscopic absore. in fuel * Thermal Flux , cince amount of fuel decreases the thermal flux must increase to (1.0) caintain a constant RR CO.53 REFERENCE H. B.

Robinson RO Lesson Plan, RxTh-LP-9 RxTh-LP-47 ROWE Reactor Operator Training Manual, Sec. 3, er 97-99 . - - -. _ s-% - ,._, _ _ - _, , -. _

. . .. . . 5.__IHEDEX DE_ NUCLEAR _EDWE2_ELAWI_DEERoIIDW4_ELUIDSa_OND PAGE 20.

IHESHDDXHABICS ANSWERS -- YANKEE ROWE-85/10/29-HEHHING, W.

_

, ANSWER 5.10 (3.00) c.

Shutdown Margin is the instantaneous amount of reactivits the reactor is or would be suberitical from its present condition assumins all full lensth rods are fullw inserted except the rod of highest worth is assumed to be fullw withdrawn.

(0.5) b.

1.

Immediate1w following the transiente the movement of the control rods exact 1w compenates for the change in Power defect.

Therefore no change in shutdown margin.

(0.L) 2.

Five hours later Xenon is at a lower value su rods must be inserted to compensate.

Therefore shutdown margin decreases since Power defect is the same (80% value).

(0.5) 3.

Thirtw hours later Xenon has increased close to the 80% ' value.

Rods have withdrawn tO ComPentate.

Therefore shutdown marsin has increased.

(0.5) c.

Yes CO.53, if boron concentration was reduced to compensate for - Power defect and control rods were at the original position the shutdown marsin has decreased to.53.

(1.0) , REFERENCE CP1L Reactor Theorv Chap. 151 OP 1009.3 ROWE Reactor Operator Training Manuale Sec.

3, PP 220-241 Sec. 4e OP-4708 Technical Specifications, p.

1-3 ANSWER 5.11 (2.50) 6.

SAME b.

HIGHER , c.

HIGHER d.

SAME , , o.

LOWER [0.5 each3 (2.5) REFERENCE McGuire Reactor Theorv Lesson Plansi Reactivitw Balancese P.

Reactivitw Coefficients, er 14e-22 Operating Procedures; ReacLivitw Balance Calculation OP/0/A/6100/06 l .

^- -- - - - . ....... -......... .._. - -. . . .-

- + . . , 5.__IMEORX_DE_CUCLEA3_EDWEE_ELLNI_2EERSIIDM2_ELUIDS2_aWD PCGE 21 - IMESMODXNAMICS ANSWERS -- YANKEE ROWE-85/10/29-HEHHIHO, W.

ROWE Reactor Operator Training Manual, Swe. 3e pp 202-218, 235-241 - - , . ANSWER 5.12 (1.50) a. The initial power drop will be greater at EOL. Thw smaller B, the greater the prompt drop for a siven reactivitw addition.

(0.5) b.

The reactor responds faster at EOL. The smaller Be the higher the SUR for a siven reactivitw insertion.

(0.5) c. Tave will be lower at BOL. The smaller HTC reuuires a larser temperature drop to to balance the nesative reactivitw inserted bw the rod.

(0.5) REFERENCE HO-RTR Sec. 8.2 ROWE Reactor Operator Training Manuale Swc. 3, pp 135-136, 140-142, 202-211 ._ CN3WER 5.13 (2.50) . o.

HTC FTC CO.5 ea3 (1.0) b.

Becomes more negative CO.53.

Because as the coolant is heated or cooled the amount of boron that is effective 1w changed in the core is reduced thus HTC has a greater effect C1.03.

(1.5) REFERENCE VCS.. Curve Booke fis. II-15, Reactor Theorw p.

1-5.22, Westinshouse Theorw, p.

3-34.

ROWE Reactor Operator Training Manuale Sve. 3e pp 211, 218-220 . -o m.

.n-

n m

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

, . - . . . . 4.__2L82I_SYSIEMS_DESIGWa_CONIROLa_eWD IWSIEUMENIAIIDW PAGE 2 2.. ANSWERS -- YANKEE ROWE-85/10/29-HEHHING, W.

' - - . ANSWER 6.01 (2.00) . c.

Causes rapid closure of the control valves when the acerleration of the turbine is 3% of rated sreed per second or greatur.

(1 0) D.

A reactor scram and turbine trip will occur.

(1.0) REFERENCE Rower RSTM 6-41.

ANSWER 6.02 (2.50) c.

A 10 second time delaw is used to allow voltage on the emersonew bus 'to returri to normal before starting thw HPSI

(1.0) pune.

b.

>/= 460 Volts.

(0.5) . c.

Overspeede overcranks high water temperature, and low oil (1.0) pressure.

REFERENCE Rowe, RSTM 19-22, RSTM 9-3-1, RSTM 3-1, 3-2.

3.00 ANSWER 6.03 (3,44) a.

The steam surels temperaturv regulating valve on the tank hwater is bweassed.

(1.0) b.

Thew would remove boric acid from the coolant therebw ccusins a (1.0) change in reactivitw . REFERENCE o.

STM 17-11 b.

STM 16-12 c.

STM 16-16 . - - g.

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

_.. .... . . i* ' . . . 4.__ELCNI_SISIEMS_ DESIGN 4_CONIEDL4_AND_IWSIEUMEWIAIIDW PAGE 23 - ANSWERS -- YANKEE ROWE-85/10/29-HEMHING, W.

' ' - . ANSWER 6.04 (2.50) c.

Bw maintaining the Main Coolant Swstem dwnamic and static Pressure head at the pump impeller above saturation Pre %sure. C.753 Hinimum pressure for Main Coolant Pump operation is 250 PSIG. C.753 (1.5) b.

The differential Pressure drors(from 99 to 78 PSIG) [0.53 due to the change in coolant densitw. CO.53 (1.0) REFERENCE STM 13-10

f.NSWER 6.05 (3.00) . o. Charming flow from the Pumps will so to zero and the Pump will trie.

(1.0) b. Chargins pump 42 can be used bw Pullins the F-8 fuses located ._ inside the main control board.

Charming Pumps 1 and 3 can be used bw manuallw controlling the Puses speed locallw at the Puer.

C1.0 each3 (2.0) REFERENCE Rower RSTMe P.

15-24, 15-25.

ANSWER 6.06 (2.00) c.

Manual.

Undervoltase.

4O Overcurrent.

Loor bweass valve closedy dLd ,3T* . Either Th or Tc stoe valve closed.

[pe each3 (1.5) b.

Th-Te </= 20 F.

(0.5) ? ' ' REFERENCE Rowee RSTM, p.

13-16e-17e-18e-20.

.. < ,

'

% / /4

.

- - - ... - . . , l 6.__ELCWI_S%SIENS_DESIG22_CONIROLa_AND_INSIEUNENI6IIDW PAGE 24. < . CNSWERS -- YANKEE ROWE-85/10/29-HEMMING, W.

d . - . .. . ANSWER 6.07 (2.50) c.

Low steam line Pressure and high containment Pressure.

(1.0) b.

Condensate Pune trip and reactor trip.

(1.0) c.

1800 psis.

(0.5) REFERENCE Rowe, ROTHe Chapter 9, P.

7-11. Chapter 6, P.6-97e 4-85.

CNSWER 6.08 (2.50)' o.

Loop i hot les.

(0.5) b.

1. Resets "LTOP Sustem Misalisned* alarm on MCB.

, 2. When MCS is less than 450 psise the *LTOP Sustom Armed * alarm will actuate.

.. 3. The "LTOP Swsten High Pressure * alarm is enabled at 400 psis.

4.

Enables Power operated and motor operated relier valves to actuate at 500 psis.

C.5 each3 (2.0) REFERENCE Rowee ROTM 6-54, RSTM 14-20.

ANSWER 6.09 (2.00) c. Low condenser vacuum ---18 inches (0.5) b.

Must be opened manuallw at the mezzanine.

(0.5) ,

c. Should be placed in the manual mode.

If Placed in Auto. the valve will return to reouired setroint at a rate determined bw the error between actual Pressure and the controller cet Point.

(1.0) REFERENCE Ensineerine Design Chanse 83-03 , l . --

- -. -. -.. - -.. -... .. ... .... . -. . - - .. -. . , , . 6.__ELCNI_SYSI233_DESIG32_CONIEDL4_CND_INSIEUMENIAIION PAGE 25 - ANSWERS '--- YANKEE ROWE-85/10/29-HEHHING, W.

. _ , CNSWER 6.10 (3.00) . o.

(1) Bleed Line Process Radiation Honitor.

(2). Accident Area Radiation Honitor.

CO.5esch3 (1.0) b.

Survew Valve Room Pipins with Portable radiation instruments to verifw bleedline radiation Invel.

(1.0) ' c.

Reduce Power Commensurate With swstem demands to.:13 and maximize purifiestion flow. CO.53 (1.0) REFERENCE OP 3100, P.

1,

_ d

i , .. _ __ - _ _. _ -. .. _ _. _,. . -. . -, _ - -,.. , - .__.. - _ - -. - -.

.,

. . , 2.__ RR OC E D U R ES _= _N C R MIL a _ e B " D R M OL a _ E M E R G E N CY _d W D PAGE 24--. RADIOLOGICAL _CDWIROL ANSWERS -- YANKEE ROWE-85/10/29-HEHHING, W.

' - . ANSWER 7.01 (2.00) - 1.

Both 2..SCRO 3.'SS 4.

SS 5. SS 6. Both 7. Both 8. Both C.25 each3 (2.0) REFERENCE , Rower AP-2001, PP.2-7.

ANSWER 7.02 (3.00) c.

Reactor critical in modes 1-2 with 1 or more stuck rods.

Reactor suberitical in modes 3-5 without stuck rods.

._ Reactor suberitical in 3-5 with 1 or more, stuck ruds. C.5 each3 (1.5) b.

Modes 1-Se calculate within 1 hour after detection of an inoperable rod and at least everv 12 hours thereafter.

Modes 3-5 at least once everw 24 hours.

Prior to anw mode change.

C.5 each3 (;.5) REFERENCE Rower OP-4708, p.1.

ANSWER 7.03 (3.00) o.

The discharse valve must be closed Prior to starting. C.53.This prevents reverse accelleration of the Pune from backflow and minimizes disruptions to Plant operations. C.53 (1.0) b.

Reduce coolins demand if Possible or increase survice water suPP1w to the component coulers.

(1.0) c.

1500 sPs.t.53 Establish flow through the idle heat wxchange ecuiPnent.C.253 To prevent overheating of the Pump.C.253 (1.0) . _. _ _. _,

... ......: ..t:: - - - - ---- - . -- - - - - . '*-. . . , 2*__EROCEDUEES_= NOR21L4_CBWORCAL4_EMERDENCX_cWD PAGE 27' RADIOLOGICAL CONIROL ANSWERS -- YANKEE ROWE-85/10/29-HEHHING, W.

REFERENCE ' ' ~ Rower OP-2156: P.3.

. CNSWER 7.04 ~(2.00) , , -c.

-Via the normal charmins linee anw mode.

-Via the Loop Fill Linee <300 Psis or </= 200 F.

C.5 each3 (1.0) b.

When MCS Pressure is >/= 1000 Psis or >330 F.

(0.5) c.

</= 330 F oP < 1000 Psis.

(0.5) REFERENCE Rowe, OP-2151, p.1-2.

, S ANSWER 7.05 (1.50) < . . Modes 1-2'at MCS Pressure >/=,1800 Psis.

Mode 3 at MCS Pressure >/= 1800 Psis or at MCS tesPerature of'>/r 490 F.

s C.25 es moder.25 ea setPoint3 (1.5) REFERENCE ' Rouse OP-2101, p.2.

, i ANSWER 7.06 (2.00) - i-Notifw Shift Supervisor.

- ' -Initiate Plant Shutdown.

-Notifw hisher Plant manadeent.

, , -Initiate Bomb Search Proceduret.253 and Operator VC HuusekeePins -

1-Inspection if VC integritw is not established.C.253

-Classifw the emersonew (OP-3300).

-Evacuate all non-shift Personnel.

-At detonation sinus 15 minutwse sound the Plant emersunew alare.

$ld , C.25 each responsw3 k2TI) . REFERENCE i Rouer OP-300A.

i e - . , f l- ._.

.

' J.

~ ~~ - ~~ , _ -... - . . . , 2.__ERDCEDUS.ES_ MD' MtL2_ ABWORMOLa_EMERGECCY_cWD.

PAGE 2 8...

RADIOLOGICAL _CONIRDL " ANSWERS -- YANKEE ROWE.

-85/10/29-HEHHING.

W.

-

- , ANSWER 7.07 (1.00) -Maintain a 500 Psis earsin between Plant conditions and the NDT upper Limit Curve.

-Dedicate an operator to monitor MCS Pressuree Pzr. heaters, SI Punese

. and. valve-lineur.- C.5 each3 (1.0) REFERENCE Rowee OP-2100, p.2.

ANSWER 7.08 (1.00) -Electrical Kews.

-Station Los Book.

-OP-3000.

-Plant Personnel Telephone Directorw.

C.25 each3 (1.0) .. ' REFERENCE Rowe, OP-3010e 7.3.

, < ANSWER 7.09 (2.50) . -MCS Pressure using the Niese Gause in the PAB.C.53-P r. level saw be approximated using the 10w Pressure suPMe tank li.21hb# I 1avel.C.53-Chargins Pumps can be operated loca11W Dw oVerridied their contPQ11ers and Jumping the CCP breaker control circuits.C.53 Instructions and Jumpers are inside the breaker cabinets.t.253-Core temperature bw usins a rortable Poteratiameter C.53 and ' (2.5) monitoring the ICI T/C's at the 41 VC blister.C.253 - REFERENCE Rowe, OP-3010e P.4.

, e ---w-r- -e- ,, -,.. -, - _ _,,,. _...,, --=,,,,, ,.-,w.

,_,__,_,w w--y__ . -. -,,. -,,. -,,,.,,, _, -. - - - - -, -.. y_--w, -,. y y.* _c

.... . . - - . - - - , .-. ' ' . . . 2 _ RECCEDURES_=_ NORM 5La_ABWORMAL2_EHERGEUCY_cND PAGE 29-l RBDIOLOGICAL COWIROL ANSWERS -- YANKEE ROWE-85/10/29-HEHHING, M.

' ' - . ANSWER 7.10 (1.00) -Auto opening of emergenew bus tiv BT1A and BT1B, 2A and 2B, 3A and 3B.

-Auto start of all available emersenew D/G's and auto closure of'their respective ACB's.

E.5 each3 (1.0) REFERENCE Rowee OP-3254.

. ANSWER 7.11 (3.00) a. -Anw area access to which is controlled bw the licensee for Purposes ' of erstection of individuals from exposure to radiation and radioactive materials.

-Anw area, recessible to personnele-in which there exists radiation... at such levels that a maJoe portion of the bodw could receive in ..; one hour a dose in excess of 5 aren, or in anw 5 consecutive daws a dose in excess of 100 area.

. -Exposure to. radiation in restricted areas or in the course of . emploweent in which duties involve exposure to radiation. Shall not include exposure for the purposes of medical diesnosis or theraPw.

C.5 each durinition3 (1.5) b.

1 1/4 rem Per auarter.C.33 3 rem per ouarter not to exceed 5(N-18).C.63 Must have form NRC-4 on file AND Past exrosure calculated. C.43 (1.5) REFERENCE Rower 10 CFR 20.3,101,and 202.

. b e o "w

. - .

..

.: . - i - - . . , 2.__EROCEDURES =_M022CLa_eBNOR21L2_EMERGEWCX_AND PAGE 30. RADIDLDGICAL_COWISOL . ANSWERS -- YANKEE ROWE-85/10/29-HEHHING.

W.

'

- . , ANSWER 7.12-(3.00) - c.

1, If condenser air wJector radiation and/or steam line - radiation is high AND containment Pressure / radiation are normale'so to OP-3107e-S/G Tube Rueture.

2.

If steamline pressure is low and decreasing in one or more S/G'se so to OP-3201, Steamline Break.

, 3.

If VC Pressuree OR VC radiation are high or increasinge do to OP-3106, Loss of Main Coolant.

C.5 each3 (1.5) b.

-Initiate OP-3000. (Emergenew Shutdown From Power) If SI is spuriouse so to attachment A.

-Verifw SI initiation at 1700 esis.

-Verifw containment isolation.

-Insure emersonew power is available.

-Initiate heat removal via intact S/G's.

-Initiate OP-3300. (Classification of Emergencies) C anw 5 at.3 each3 (1.5) . REFERENCE Rower OP-3051, p.2-3.

. f i . % - w...-. ,,,, - - - -, _.

- - _ ,. .

....... . . .j _ . -. . _ . _, , . . . 8.__CD'2INISIRAIIME EEOCEDURES2_CONDIIIDMS4_cHD_LIMIISIIDWS PACE

ANSWERS -- YANKEE ROWE-85/10/29-HEHMING, W.

_

- , ANSWER 8.01 (3.00) e.

LCOs indicate the lowest functional caPabilitw or performance lovel of eauiPnent required for safe operation Of the facilitv.

01.03 b.

As lons as automatic Protection occurs prior to exceeding a LSSS, then the~ abnormal condition will be corrected prior to exeveding a Safetw Limit. ti.03 c.

The integritw of the Phwsical barriers which guard against the uncontrolled release of radioactivitw is Protected as lons as a Safetw Limit is not violated. C1.03 (3.0) REFERENCE 10CFR50.34 CNSWER 8.02 '(1.50) -- c.

Shift Supervisor (.75) 'b.

Oniv.those Persons authorized on the Local Control Tassin's List (.75) REFERENCE Rowe, AP 0017e P.1 f.% l - ced~ W-*

. . . .

-. > __.

s -; - . , - - 8.__ADOINISIE&IluE_2ROCEDURESa_CONDIIIONSx_AWD_LIMIIAIIONS PAGE 32.. . ANSWERS -- YANKEE ROWE-85/10/29-HEHHING, W.

. ' - ' . ANSWER 8.04 ( 2. 0 0 )- - . a.

W-At least once everv 7 daws.

92 daws.

Q '

SA ' 184 daws.

R '

18 months.

.70 P- -Prior to each release.

t 26'each3 (1.0) p b.

Maximum extension not to exceed 25% of the ruuuirement. C.53 A maximum combined interval time for anw 3 consecutive intervals not to exceed 3.25 times the reeuired interval. C.53 (1.0) REFERENCE Rower-Tech. Spec.-Section 3.

ANSWER 8.05 (2.50) - Control Room is continuous 1w manned.

. - Fire detection eouipment is installed in areas not visibiw to operators.

- Electrical Penetrations are sealed.

- Fire dampers are installed in all vent lines.

- Portable fire extinauishers'are readilw available.

- Inadvertant operation of a fixed sustem could cause euuiPaent damade or ' Control Room evacuation.

- Flammable material inventorw is low and controlled.

C.5 vach for anw 53 REFERENCE Rower T.S.

exeertion letter dated August, 1982 (in front of T.S.). ANSWER 8.06 (2.00) , c.

5.

(0.5) b.

Brigade shall not include the minimum shift crew reuuired for safe shutdown of the plante 2 licensed operaturse or anw Personnel reeuired for essential functions during the fire.

(1 0) c.

Supervisorw Control Room Operator.

(0.5) .

.. ..--....;. ..: ... . .. . . . . - - -

'

. . , S.__cDMINISIRfIIME_ESDCEDURESa_CDHDIIIONSa_AND_LIMIIAIIONS PAGE 33 - . ANSWERS -- YANKEE ROWE-85/10/29-HEMMING, W.

. REFERENCE Rowe, T.S. Section de P.6-2 and A'P-200r, P.5.

. ANSWER 8.07 (3.00) c.

Recoverv Manager.

(0.5) b.

TSC coordinator.

(0.5) c.

Recoverw Manaser.

TSC Coordinator.

Plant Emersonew Director.

Emersonew Coordinator.

Ensineering Support-Center.

C.20 each,3 (1.0) .d.

Stable Plant conditions with some certaintw that the severitw of the emersonew is not likelv to worsen.' (1.0) REFERENCE

Rower OP-3321e P.1.

. ANSWER' 8.0'8 (2.00) -Enter if the whole bodw exposure will be 100 run or less AND the victim saw be alive.

-Choose the oldest Person for the resue as the 100 rem is onCW Per lifetime.

-Move the victim on1w if the radiation exposure will kill him.

-Do not move the victio i f the exposure dose is 50 erve or less and moving could cause more inJurw.

C.5 vach3 (2.0)

. I !

, . -- ,,-- - - - - - - - - -.. a --e-., - - - - - -, -.----- - - - --,,..., - -. _. - - - .n.. ,- - - - - - - - - -

<-- - - - - , - , S.__fD]IMISIEaIIME_ERDCEDURESA_CONDIIIDMSa_iND_LIMIIAIIOMS PAGE 34. ANSWERS -- YANKEE ROWE-85/10/29-HEMMING, W.

- - , ANSWER 8.09 (2.50) 8.

-Enersenew Action Level...A specific abnormal Plant instrument readins OR plant condition which reouires plant staff to declare one of the four emersonew classifications.

(0.5) -Event....................A catamorw of EAL's scoured accordins to plant swstems or conditions.

(0.5) b.

15 minutes.C.53The time is begins from the time at which operators recognize that an EAL has been reached and that the event warrants classification. E1.03 (1.5) REFERENCE-Rower-CP-3300, p.2.

ANSWER 8.10 (3.50) c.

Modes 1 and 2...all main coolant loops (MCL) in operation.

._ Mode 3..........at least one MCL in operation with all operable.

Mode 4..........at least one MCL or shutdown coolins sustem in operation with all MCLs operable.

Mode 5..........at least one MCL or shutdown coolins swstem in operation with at least 2 MCLs or shutdown coolins swstems operable.

E,p5'each mode 3 (1.5)

b.

Shutdown Cooling Swstem with the shutdown coolins euse.

~ Shutdown Cooling Swstem with the low pressure surge tank coolins pump and cooler.

E.5 each3 (1.0) ~ c.

No operations that will dilute the MCS and core outlet temperature must remain 10 F below saturatiuon.

(1.0) REFERENCE Rowe, T.S. 3.4.1.

, ! .

_.

.. ..u.

.... . o.

, .. -. - ..., - .- . , , . 8.__AD"INISICOIIME_EBOCEDURES2_CONDIIIDMSa_eHD LIMIIAIIDMS PAGE 35 - ANSWERS -- YANKEE ROWE-85/10/29-HEMMING, W.

- ' . ANSWER 8.11 (2.00)

a.

Initiate and continue to esersancv borate at greater than 26 GPM of 2200 PPM boric acid until SDM is restored.

(1.0) b.

(1) MCS Baron Concentration (2) Control Rod Position (3) Xenon Concentration (4) Samarius Concentration (5) Fuel Burnup (6) MCS T AVE.

Canw 4 at.25 eachJ (1 0) REFERENCE-Cower TS 3/4.1 1 and OP 4708, p.3.

< e

e l \\ ~ .- . -.... . .-. -- - -... - ... --

_- . ., ., ,, _ - - - -.. . _ ' '

.

. . TEST CROSS REFERENCE PAGE

' QUESTION VALUE-REFERENCE ________ ______ __________ 05.01 3.00 WCH0000255 05 02-1.00 WCH0000256 , 05.03 2.00 WCH0000257 - , - 05.04 1.50 WCH0000258 05.05 1.50 WCH0000259 - 05 06 1.50 WCH0000260 05.07 2.50 WCH0000261 05.08 1.50-WCH0000262 .05.09 1.00 WCH0000263-05.10 3'.00 WCH0000264 05.11 2.50 WCH0000265 05.12 1.50 WCH0000266 05.13 2.50-WCH0000267 ______ 25 00 04 01 2.00 WCH0000299' I 06.02 2.50 WCH0000300 06.03' 3.00 WCH0000301 06.04 2.50 WCH0000302 06.05 3.00 WCH0000303 06.06 2.00 WCH0000304 06.07 2.50 WCH0000305 06.08 2.50 WCH0000306 .. 06.09 2.00 WCH0000307 06 10 3.00 WCH0000308 ______ 25.00 07.01 2.00 WCH0000268 07.02 3.00 WCH0000269 07.03 3.00 WCH0000270 ! 07.04 2.00 WCH0000271 l.

07.05 1.50 WCH0000272 07.06 2.00 WCH0000273 07.07 1.00 WCH0000274 07.08 1 00 WCH0000275 07.09 2.50 WCH0000276 07.10 1.00 WCH0000278 07.11 3.00 WCH0000279 - 07.12 '3.00 WCH0000311 ______ 25.00 08.01 ~ 3.00 WCH0000280 08.02 1.50 WCH0000281 08.03 1.00 WCH0000282 08.04 2.00 WCH0000283 08.05 2.50 WCH0000284 08.06 2.00 WCH0000285 . ' ___ _ _ _ _ _ _ _ _ _ _ _ _ _

--...a.....-. . -- ..... .- --.. ......... . ... f 7 .. .... ... -.. f*' . .

,. TEST CROSS REFERENCE - PAGE 2- . QUESTION' VALUE REFERENCE ________ ._____ ..________ 08.07.

3.00 WCH0000286 08.08 2.00 WCH0000287 08.09 2.50 WCH0000288 . ,

08.10 3.50 WCH0000289 - - 08.11 2.00 WCH0000290 . ______ 25.00 ______ ______ .100.00 i .- a b O .. W . N

- g QfffltYNT h - -- m YANKEE R0WE R0 AND SR0 EXAMINATION C009 TENTS AND RESOLUTIONS R0' Exam-Cement: 1.04....A.

Incorrect answer Makes the MTC less negative or even positive (Reference: R0 Training Manual, RE.Section, Page 3-208, Paragraph e) NRC Resolution: Answer changed to "less negative".

Coment:

1.10....May get emergency procedure answers for c (Reference: OP-3054,' Natural Circulation, Step 3 of Subsequent Actions) NRC Resolution: Answer altered to accept both answer key and procedure referenced above.

- SECTION II Coment: 2.01....A.

TK-1 DWST, TK-39 PWST DWST. TK-1 or PWST TK-39 Safety Injection Tank (Reference: OP-3203, Loss of Feedwater) NRC Resolution: : Coment not accepted. Question clearly states normal lineup and does not ask for alternate supplies.

Coment: 2.07....Part C.

This is no longer true Pressurizer Safety Va'lves discharge to Vapor Container through Rupture Disc (Ref: Systems Training Manual, Page 14-26) (Ref: Systems Training Manual, Page 16-17) NRC Resolution: Question deleted.

i

y , - - . SECTION III Coment: 3.06....Part A.

PR-LT-6 (NR indicates high) PR-LT-8 (WR indicates high) PR-LT-705 (WR indicates low) (Ref: R0 Training Manual, Page 6-44, paragraph 3) Part B.

This will-react the same as the other two channels when the reference flashes. Answer should read higher than actual.

(Ref: R0 Training Manual, I&C Section, Page 6-43, last paragraph) NRC Resolution: Coment not accepted. Training material indicates that the-linear amp processes a positive output for PR-LT-6 and 8 which would make the answer key correct if power-is lost. PR-LT-705 answer was -- altered to be " fails as is" as linear amplifier is not in its ~ circuitry. In part B, the answer key remains unchanged.. Training material indicates that PR-LT-705 responses opposite of.the other two channels where the reference leg is lost.

SECTION I7 Comment: 4.08.... Answer should read condensate recirculation valve (Ref: OP-3257, Loss of #1, 125 volt D.C. Bus) NRC Resolution: Coment accepted, answer key altered.

SRO EXAM SECTION V - Coment: 5.07....B.

Part 2: How does fuel to. clad contact effect the FTC.? Answer key said Less Negative.

As clad to pellet contact increases,.the heat transfer fuel to clad improves, this lowers the fuel temperature for any power level.

c , . . , . If the fuel temperature'becomes less negative with increase in fuel temperature, then the opposite must be true. The FTC becomes more negative as fuel tenperature is decreased.

(Ref: R0 Training Manua, RE Section Page 3-199, first paragraph also page 3-202, first. paragraph) NRC Resolution: Comment not accepted. Answer key is supported by the above references and figure 13.

Comment: 5.07....B.

Part 3: How does the buildup of PU-239 core life effect FTC? Answer key said, more negative Should be less negative (Ref: R0 Training Manual, Pg. 3-192, second paragraph) ' - NRC Resolution: Comment accepted, answer key altered to be "less negative".

SECTION VI Comment: 6.03....Part C.

This is no longer true,. Pressurizer Safety Valves discharge to Vapor Container.

(Ref: Systems Training Manual, pg. 14-26) -(Ref: Systems Training Manual, pg. 16-17) NRC Resolution: Question deleted.

SECTION VII Comment: 8.03....While in Mode 1 at 10% power, an operator reports IR chat:ael 1 has failed low. What action, if any, must be taken? There-is no.IR channel #1, it's 3 & 4.

The question was not clear; was it talking about intermediate or intermediate power range?

L

y, .- - _,.. . -- ,

Answer Key indicated'the question was talking about IR Channels 3 & 4 but the answer is wrong.

If the plant is at 10% power .it would be at 18 MWe.

b. of Action 3 states above 15 MWe operation may continue.

(Ref: Yankee's Technical Specification, pg. 3/4 3-2 and .3/4 3-5) NRC. Resolution: : Question deleted.

. O t 4 }}

v t e Inspection Report - Yankee Rowe - 1985022
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
1985 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 7(0) 8(0) 9(0) 10(0) 11(0) 12(0) 13(0) 14(0) 15(0) 16(0) 17(0) 18(0) 19(0) 20(0) 21(0) 22(0) 23(0) 24(0) 25(0) 98(0) 99(0) Security Operator Exams Emergency Planning Other

IR 05000029/1985022

Text

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