ML20234D258
| ML20234D258 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 06/26/1987 |
| From: | Cooley R, Mccrory S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20234D228 | List: |
| References | |
| 50-498-OL-87-02, 50-498-OL-87-2, NUDOCS 8707070146 | |
| Download: ML20234D258 (101) | |
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I SOUTH TEXAS PROJECT FACILITY l
, OPERATOR LICENSE EXAMINATION REPORT l No. 50-498/0L-87-02 l Licensee: Houston Lighting and Power '
P.O. Box 1700 Houston, Texas 77001 l
l Docket: 50-498 )
Operator License Examinations at THE South Texas Project (STP)
Chief Examiner: ! L g w// 7 6 i WepTfen' L. McCrory, Lead Exapfier DatpSigh6 Approved By: ' -
A Mb/
R. A. Cooley, Sec on Chief Dhte Signed
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Summary Writtenandoperatingexaminationswereadministeredtoeleven(11) Senior );
Reactor Operator and three (3) Reactor Operator candidates. One(1) Senior Reactor Operator candidate failed both the written and operating examinations.
All other candidates passed both examinations.
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i 2 l REPORT DETAILS l
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- 1. PERSONS EXAMINED R0 Candidates SR0 Candidates i Total Pass Fail % Total . Pass Fail- % 1 3 3 0' 100 11 10 1 91 l I
'2. EXAMINERS S. L. McCrory(Chief Examiner)
R. Aiello, NRC RII D. Nelson, NRC RII B. Haagensen, Sonalyst i 1
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- 3. EXAMINATION REPORT Perform'ance results for individual candidates are not included in this i
report as it will be placed in the NRC Public Document Room and these results are not subject to public disclosure,
- a. EXAMINATION REVIEW COMMENT RESOLUTION In general, editorial comments or changes made during the examination, the examination review, or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of substantive comments submitted to the NRC after review .,
of the examination by the facility licensee. The changes discussed below are included in the master examination key which is provided elsewhere in this report as are all other changes mentioned above but not discussed herein. The facility licensee examination l
comments, less the supporting documentation, are included in the report immediately following the master examination key. Unless otherwise indicated in this section, the facility comments were incorporated into the answer key.
(1) 1.04 Part b was deleted from the examination due to the fact that under certain conditions any of the three I options could be correct.
l (2) 1.16 Part b was deleted from the examination due to apparent ambiguities.
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3 (3) 3.10 The information in the training material does not agree with the Technical Specifications. The key was q modified to accept only TS parameters.
(4) 4.10 The question was deleted from the examination because 7.07 it was insufficiently clear to solicit the desired response. l I
(5) 4.19 Recommendation rejected. No memorization is required l 7.12 to properly answer the question. The S0P referenced 1 in the question governs operation of the AFW system.
The operator is cautioned-to closely monitor tank :
level when operating the system. The question asked j WHY this is necessary. The TS requirements are I applicable whether the system is being operated or i not and do not require "close" monitoring to ensure l compliance. l l
(6) 8.03 The first set of recommended answers was given ]
partial credit only. j l
(7) 8.07 Recommendation rejected. The question is clearly i stated. It is the candidate's responsibility to read it carefully to ensure he understands what is being asked.
- b. EXIT MEETING
SUMMARY
An exit meeting was held with the facility licensee staff during the second week of examinations. The following personnel attended this meeting:
NRC FACILITY i D. Nelson D. J. Cody B. C. Haagensen J. R. Walker M., Ernstes J. Constantin J. Bartlett M. McBurnett The following areas were observed as generic weaknesses in the candidates during the second week of examinations:
(1) Lack of familiarity with the operation of the RM-11 and ERFDAD systems.
(2) Difficulty properly determining the positions of manually operated valves.
4 (3) Not aware of their designated assembly location for station evacuation when on site but off shift.
- c.
GENERAL COMMENT
S During the first week of operating examinations, some candidates where given casualty scenarios which resulted in a complete loss of normal core cooling while in mode 5. Their approach to handling the problem was unstructured and inconsistent. In no case did the candidates consult the E0Ps to determine if any guidance was provided which might help mitigate the situation. Further, the A0P which was used was inadequate to handle the situation. Similar weaknesses were observed in candidates taking the operating examination in January 1987. This fact was reported in examination report 50-498/0L 87-01.
Tt'ere are numerous reports from several operating plants of loss of core cooling / decay heat removal during plant outages. The susceptibility to this event is particularly high when the reactor coolant system is partially drained. -NRC is concerned about operator training to make operators aware of the dynamics of these types of events and their potential seriousness particularly since boiling in the core region can often occur in a relatively short time. Further, NRC is concerned about the adequacy of abnormal and emergency procedures to provide specific guidance to operators to handle casualties in the shutdown conditions.
The facility licensee should incorporate training in this area into both the initial license and requalification training programs. -
Additionally, the facility abnormal and emergency operating ,
procedures should be reviewed for their adequacy to provide guidance on these types of events and be revised as necessary,
- d. EXAMINATION MASTER COPY Master copies (questions and answers) for the R0 and SR0 license examinations follow this page. Handouts and other examination aids provided to the candidates are not included.
- e. FACILITY LICENSEE EXAMINATION COMMENTS The facility licensee examination review comments follow the examination master copies. Supporting documentation provided with the comments is not included.
_ -___ _ _ A
___,7 U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _SDDIB_IEXeS_1 REACTOR TYPES- _ EWE WECA _ _
DATE ADMINISTERED:_B2ZD5Z19 EXAMINER: _elELLD ._R E CANDIDATE: ____ .;
itdSIEUCIIQtsS_IO_CetJD1DeIEr Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points-for each i question are indicated in parentheses after'the question. The. passing. t grade requires at least 70% in each category and a final grade of at l least 80%. Examination papers will be picked up six (6) hours after the examination. starts.
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1 % OF
! CATEGORY % OF CANDIDATE'S CATEGORY L_UeLDE__IDIeL ___SEDEE___ _UeLUE__ CGIESDRY -
l 24.5D__ _22.02
_ _ _ _ _ _ _ . _ I. PRINCIPLES OF NUCLEAR POWER j PLANT OPERATION, THERMODYNAMICS, l HEAT TRANSFER AND FLUID FLOW
_25 d5__ _23.26 - - - - -
- 2. PLANT. DESIGN INCLUDING-SAFETY ]
AND EMERGENCY SYSTEMS h28.25___26.6Q == ____ 3. INSTRUMENTS AND CONTROLS' i
_28.QQ__ _26.32 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL (106.2G__ _ _ _ _ - - % Tot al s I l
Final Grade l
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All work done on this examination i s my own. I have neither given
.nor received aid.
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l Candidate's' Signature l
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>11__EBluCIELES_DE_UJJCLEGE_EDWER_ELeUI_DPFRATTD$ PAGE 2. )
IEEEt10DYl& BIDS, WFAT IRANSEER_AND_ELijlD_ELDW '
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QUESTION 1.01 (1.00)
Givens Four-reactor cool, ant (RCP) pumps operating in parallel, each with a .,
flow rate "m" an d a c omb i n e d f l ow r a t e "M". Which one of the f oll owi ng best I describes the system response to securing'one RCP? i
- a. The resulting core flow (M) will decrease as individual operating j RCP flows (m) decreases.
- b. The resul ting core flow (M) will increase along with individual operating RCP flows (m).
- c. The resulting core flow (M) will decrease as i nd i v i dual operating I RCP flows (m) increases. i
- d. The resulting core flow (M) will not change due to decrease in RCP back pressure, i
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QUESTION 1.02 (1.00.) i 1
Which one of the f oll owi ng statemen ts best describes' Xenon behavior on a d power decrease, cuer the first hour, follow'ing 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> at 100%
powers l NOTE: [Xe3 denotes xenon concentration l a. Direct CXe3 increases, indirect CXe3 decreases, total [Xe3 decreases.
- b. Direct [Xe3 increases, indirect [Xe3. increases, total [Xe3 l increases. i l
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l c. Direct [Xe3 decreases, indirect CXe3 decreases, total [Xe]
l decreases.
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- d. Direct IXe3 decreases, indirect [Xe3 increases,' total [Xe3 increases.
- e. Direct CXe3 decreases, indirect [Xe3 increases, total [Xe3 i decreases. I l
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' IB EEtdODYNAMICSeBEAI_IEateSEER_etdD_ELU1D_ELOW i
QUESTION 1.03 (1.50)
Indicate whetner each of the following.will make the' moderator temperature coefficient LESS NEGATIVE, MORE NEGATIVE, or have NO EFFECT.
- a. INCREASE' moderator temperature
- b. DECREASE ~ boron concentration
- c. INCREASE core age ,
QUESTION 1.04 (1.00)
State the change (INCREASES , DECREASES or REMAIN THE SAME) in the magnitude of the fuel temperature coefficient'(FTC) for each of the f ol l ow i ng s -
A. An increase in power.
B. (D E L E T E D) 1 C. A' decrease in magnitude of the moderator temperature coefficient 1 (MTC).
QUESTION 1.05 (1.00)
A. cen tr i f ugal pump is-started up with its discharge valve open. How would the following parameters differ (HIGHER, LOWER, THE SAME) if the. pump had d been started with its discharge valve shut?
- a. Motor current
- b. Discharge pressure j
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.lo__EEluCLELES_DE_SUCLEeE_EDWEE_EL6UI_QEEE6IlOUo PAGE 4 {
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1 QUESTION 1.06 (1.50)
Indicate whether the f ol l owi ng wi l l INCREASE, DECREASE, or have NO EFFECT on the available NPSH of a centrifugal pump:
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- a. Throttle shut on the pump discharge valve. . l i
- b. Increase the temperature of the suction side fluid. {
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- c. Increase the pressure of the N2 blanket on the suction side supply tank.
I QUESTION 1.07 '(2.00) i For steam (at 1000 psia) going through a throttling process, indicate whether the following parameters will (INCREASE, DECREASE, or REMAIN THE l SAME.)
.(NOTE: assume ideal conditions)
- a. Enthalpy l
- b. Pressure
- c. Entropy
- d. Temperature 1
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-i QUESTION 1.08 (1.50)
With respect to reactor thermal limits, indicate whether each of the f ol l owi ng statemen ts is TRUE or FALSE:
- a. The average linear power density in the core is expressed in units '
of Rw/ft and is the total thermal power divided by the actiue
. length of all the fuel rods.
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- b. The purpose of limiting the enthalpy rise hot channel factor is: to prevent bulk boiling from taking place during a LOCA.
- c. The purpose of the limit on the heat flux hot channel factor is to-insure that fuel clad temperature does not exceed 2200 deg F during normal operat i ons.
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' QUESTION 1.09 (1.50)
With respect to reactor start up, indicate whether each of the f ol l ow i ng statements are TRUE or FALSE:
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A. The purpose of fully withdrawing the shut down rods is to provide l adequate negative reactivity which may be inserted should a problem occur.
B. Counts doubling indicates that the margin to criticality has been-halved..
- C. If counts have doubled, adding the same amount of reactivity will cause 1
- the reactor to go supercritical.
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QUESTION 1.10. (1.50) l l List 3 reasons why excess reactivity is built into the-core.
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l i I i QUESTION 1.11 (1.00)
List FOUR (4) plant parameters observed to insure that CHF or DNBR limits are not exceeded. ';
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QUESTION 1.12 (1.00) l 1
l List all of the conditions that must be present in order'for natural l
circulation to exist?
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QUESTION 1.13 (1.00)
State TWO (2) reasons why 10 exp -8 amps is chosen as a standard j reference for critical rod height data.
1 L NOTE: " standard reference" is NOT an acceptable answer l
QUESTION 1.14 (1.00)
Explain the principle of operation of the eductor used in the Containment Spray system.
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li__EE1UCLELES_QE_UUCLEAE_EQWEE_ELaNI_DEEE6110No PAGE. 6 IBEEMODYNad1CS,_MEaI_IEeUSEER_AND_ELulD_ELOW
. QUESTION 1.15 (1.50)
A. How does Beff vary over the life of the core? (increase / decrease)-
B. Describe the nuclear characteristics of plutonium ~which causes the variance in Beff as discussed in part "A". j
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C. Describe the affect a-decrease in the delayed neutron fraction has i on power for a given reactivity insertion. (Your response should include. rate and magnitude).
QUESTION 1.16 (1.00) 1 l
A. Define the term " Departure from Nucleate Boiling Ratio" (DNBR).
B. What does DNBR have to be for DNB to occur (theoretically >?
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l QUESTION 1.17 (1.00)
Why do the control rods in the middle of the core (radially) have a greater
, effect on Keff than the control rods ~at the edge of the core (radi al l y)? ,
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QUESTION 1.18 (1.50)
The enthalpy of the reactor cool an t enter ing the steam generator is 650 Btu /lbml its enthalpy leaving is 580 Btu /lbm. .The enthalpy of the'feedwater is 400 Btu /lbm. What is the enthalpy of the steam produced if the reactor l cool an t fl ow is 6 x 10 e x p 7 l bm/h r and the feedwater flow is 6 x 10exp 6 1 Ibm /hr? (SHOW ALL WORK!)
l QUESTION 1.19 (1.00)
Calculate the condensate depression in a condenser operating at 1 psia with-a condensate temperature of 95 deg F. o (SHOW ALL WORK!)
I QUESTION 1.20 (1.00)
Define subcritical multiplication.
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. 2 __ELAUI_DESISbLitELUDitJB_S6EEIY mb EMEREEtCY_SYSIEUS - PAGE 7 1
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QUESTION 2.01 (1.00)
Which one of the following is NOT a source of water to the PRT?
- a. Reactor vessel flange leakoff detection drain b..CUCS. letdown relief 1 I i
- c. CVCS seal return relief-l
- d. HHSI pump discharge relief
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1 QUESTION 2.02 (1.00)
Which statement below regarding the main generator protection system is NOT correct?
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- a. Less than 5% load on the generator for more than'30 minutes will j
' trip the generator circuit breaker on reverse power.
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- b. A turbine trip above the protection interlock <P-7) always results in a reactor trip.
- c. Manuall y tripping tha breaker will NOT cause'a generator trip.
- d. When the 25KV system generator trip relay (86-G1) is energized'due-
, to a fault, the main turbine trips. ,
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I L QUESTION 2.03 (1.00) j With regard to the chemical and volume control system (CVCS), state.what i -
actual position (OPEN, CLOSED, AS IS) the following, valves fail to on a loss of control signal. 4 1
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- a. Letdown orifice isolation valves (XCV'12, 13, 14)
- b. RHR 1etdown control val ves (XRH 66A/B)
- c. Containment isolation vaives
- d. Letdown temperature divert valve (TCV 143) l l
- e. Low pressure letdown control valve (PCV 135).
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j 2 __EL6UI_DESIGU_luCLUDIEG_5GEEIX_6UD_EldEEGEUCY_EYSIEldS PAGE 8 l
l QUESTION 2.04 (2.00)
Indicate whether the f ol l owi ng s t atemen t s regardi ng f i r e protection are TRUE or FALSE.
l a. There are no automatic alarms associated with Wet Standpipe Systems.
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If electrical power is lost to the RCB isolation valve an ESF b.
Bypass /Inop. al arms .
- c. The RCB fire water isolation valve closes on a phase A isolation.
- d. In order to get fire water to the carbon filters inside the RCB, the moter-operated containment isolation valve that supplies the RCB preaction Standpipe System must be opened from CP-002.
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2.__ELGUI_DESIGt2_1tJCLUDitJG_S&EEIY_G61D_EtdEEGEtsCY_SYSIEtdS PAGE 9 f
OUESTION 2.05 (1.75)
Match the following permissive logic functions in column A (1-7) with their respective permissive in column B (a-e).
l COLUMN _A
- 1. Automatically blocks the source range (SR) trip (10exp5 cps).
2.-- - _ _ .
(3-Loop flow permissive) is enablec; below 35% power with 2/4 coincidence in RPS.
- 3. 2/4 Power ranges > 50% inserts turbine trip, reactor trip logic
- 4. _
Al l ow manual block of the intermediate range trip (25% power) and intermediate range rod stop (20% power).
- 5. (At power permissive) 2/4 PR > 10% or 1/2 Turb Imp Press > 10%
inserts 5 reactor trips.
6.__ Al l ow manual block of the power range low set point trip (25%
power)
- 7. (ECP Enabled) when 2/4 power ranges are < 10%.
COLUMN _B
- a. P-10
- b. P-7
- c. P-15
- d. P-9
- e. P-8 QUESTION 2.06 (1.00)
When the 25 KV system trip relay (86-G1) is energized due to a fault condition, a generator trip occurs. Excluding annunciation, LIST the 2 actions that will occur automatically?
QUESTION 2.07 (2.00)
List 8 auto / manual main feedpump (MFP) turbine trips and applicable setpoints. (0.20 for s i gnal ; 0.05 for setpoint)
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i QUESTION 2.08 (2.00)
Excluding manual actuation, list the FOUR (4) Main Steam Isolation au tomat i c Ac tuat i on Si gnal s.
QUESTION 2.091 (1.25)
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List.the FIVE-(5) core bypass flows.
QUESTION 2.10 ( 1. 50 )-
List 6 different plant components cooled by component cooling. water (CCW)~ ,
that operate at a higher pressure than CCW.. H
- QUESTION 2.11 (1.50). l
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l Explain, with respect =to VITAL BUSES, DIESEL GENERATORS (DG),- and EX3 I BREAKER (s) CLOSURE, what happens during an ESF loading sequence:where an SI jI is coincident wi th a si te blackout (mode III). Load sequencernot required.
QUESTION 2.12 (1.00)
List the FOUR (4) auto / manual si gnal s that will trip the EDG after an emergency start.
QUESTION 2.13 (1.95)
Excluding manual initiation, list.all si gnal s (including set points and coincidences) which are used to initiate an'"SI" signal.
I QUESTION 2.14 (1.00) l l List FOUR (4) automatic initiations that will occur on the AFW system as a l result of an ESF actuation, l'
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-QUESTION 2.15 (1.50) i L.ist'the pressurizer pressure control'(PPC) or protective action for the. l f ol l owi ng' PPC and protec t i on se tpoi n t s. j
- a. 2485 psig.
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.b. 2335 psig c 2260.psig i
- d. 2210 psig
- e. 1950 psig
- f. 1850 psig QUESTION 2.16 (1.00) :
1 A. State the function of the 138KV Site Emergency' Transformer (SET) i B. Where is'the 138KV SET located? !
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- QUESTION 2.17 (1.00)
- a. Describe the effect on a Westinghouse reactor coolant-pump of a loss of seal injection flow from the CVCS.
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- b. Does the pump design allow operation with no seal injection?-
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. QUESTION 2.18 (1.00) l ;
Explain why pressurizer backup heaters come on at +5% level above program?
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I QUESTION 2.19 (1.00)
What is displayed on the main generator field supply breaker. TARGET
! position, should the. breaker trip open? (local . indication) l l A 1-l
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. QUESTION 3.01 (1.00)
With respect to the compensated ion chamber of the intermediate. range nuclear instrument (IRNI), which of.the following statements is NOT correct when the lon chamber -is UNDER COMPENSATED? ,
- a. The IRNI reading shows up a.too high a reading. I
- b. P-6, source range permissive, may never deenergize. .
c . f The gamma s i gnal . f rom the outer volume is greater than the gamma -
signal from the inner volume. '
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- d. Overcompensation is worse than undercompensation..
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- e. Indication drops off quicker when passing through the intermediate !
- l. range. 1 L 1 l l 1 1 QUESTION 3.02 (1.00) l J
With the pressurizer level control selector switch:in-the ch 465 position,.
a failure causes the f ol l owi ng SEQUENTI AL pl an t events.'(assume no. operator I actions taken)
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1 1) Chargi ng fl ow reduced to minimum l 2) Pressurizer level decreases i 1
( 3) Letdown secured and heaters cff 1 l 4) Level increases until high level trip 1
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Which ONE of the following failures occurred?
a) Level channel 465 failed high l I b) Level channel .465 f ail ed low i c) Reference pressurizer level failed to the no' load position 1
d) Auctioneered Tave failed Hi due to a failed RTD I I
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3.__1NSIEUMEUIS_AND_COMIROLS' PAGE 13 QUESTION 3.03 (2.00)
From the selection of DRPI system failures below, classify whether they are
' URGENT or NON URGENT faiiures.
- 1. "A"' data is not equal to o' greater than "B" data (detector failure).
2-. An error has been detected in "A" or "B" data and DRPI is at half accuracy.
l 3. A 12 udc power supply ha: ' ailed.and' disconnected itself.
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4, 1 or 2 pair of timing or data cards.have failed and disconnected themselves.
- 5. The rod devi ation al arm cards dif f er in~ their outputs.
- 6. Any test switch is out of its normal position, l
l 7. The binary sum of "A" data and "B" data exceeds 43 for a standard l rod or 9 for a-shutdown rod. (logic failure control unit).
l 8. A rod deviation alarm condition exist due to. rod misalignment or a dropped rod. ;
QUESTION 3.04 (1.00)
State how (INCREASE, DECREASE, or REMAIN THE SAME) each of the ,following parameter changes will effect the OT Delta T setpoint.
- a. INCREASE in Tave
- b. DECREASE in reactor pressure l l
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3._..LUSIEUMENIS_6MD_CDUIEDLS - PAGE 14 GUESTION 3.05 (2.00)
Wi th regard to the reactor coolant system (RCS) during' plant heatup (H/U),
state whether the f ollowing are TRUE or FALSE.
- a. Overfeeding the S/G may cause excessive cooldown of the RCS.
- b. Pressurizer pressure > 1850 psig will enable excessive cooldown protection.
- i. c. If' reactor startup will be delayed, those reactor coolant pumps not l necessary to maintain temperature may be stopped.
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! d. RCPI D is.the preferred operating pump due'to surge and spray line ,
l connections.
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l l QUESTION 3,06 (2.00) l-Indicate whether the following statements regarding steam generator (S/G) water level control are TRUE or FALSE.
l l a. Lo-Lo S/G reactor trip and AFW startup occurs when 2/4 < or = to l 33% span on i S/G.
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- b. Hi-Hi S/G (P-14) feedpump trip, feedwater isol at ion and turbine trip occurs when 2/4 > or = 87% in 2 S/Gs. ..
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- c. High feedwater flow (>30%) with P-15'and Lo-Lo-Tave~or Lo-flow provide excessive cooldown protection.
- d. Steamline i sol a t i on on high steam rate occurs only when below P-11 and an excessi ve cool down protec t i on si gnal is present.
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-Si ~ fMSIEUMEMIS_eMD_COMIBOLS PAGE 15 QUESTION 3.v7 (2.00)
Indicate whether the following statements regarding pressurizer (PZR) I pressure and level control are TRUE or FALSE.
- a. The si gnal generated by the. pressure control system will con trol heater ,
operation, spray value modulation and safety valve actuation. 2
- b. PZR pressure control ch 455 or 457 supplies the PZR pressure master controller,
- c. The two' spray valves operate together on the same control signal 4 rom the master controller.
- d. The spray valve con trol signal is Proportional Integral Differential.
(PID) compensated so that actual lifting pressure is' solely dependent upon the duration-and rate of change of.the pressure' error signal.
QUESTION 3,08 (2.00)
Indicate whether the following statements rege.rding the bank overlap unit (BOU) are TRUE or FALSE.
- a. The BOU determines which master cycler gets the step up or step.
down orders f rom the sl ave cycler.
- b. By selecting which banks receive the signal the BOU can be used to provide the desired overlap for control. rod movement.
- c. The BOU rece i ves coun ts f rom the slave cyeler, and counts once for i each step of rod movement for both groups in one bank.
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- d. The BOU only functions with the bank selector switch in the ,
automatic or manual positions. When i nd i v i du al banks are selected, '
the BOU i s l ocked out . j OUESTION 3.09 (1,50)
There are 5 Process & Effluent. Radiation Monitors (PERMS) that could l
I possibly assist in helping identify a steam generator tube rupture (SGTR).
One is the main steam line monitors-(RT 8046/47/48/49), another is the b steam generator blowdown (SGBD) monitors (RT 8022/23/24/25). List the other
THREE (3) remaining PERMS. (Instrument numbers not required) i L (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
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- A__INGTRt IMFNIS_eNJ)_C)bIRDLS PAGE'116 y' _
t'i-QUESTION 3.10 (1.00) . ,j - . ,
}
List the FOUR (4) corrections that the OT Delta T setpoint cal cu l at i on- .j includes.
e k i I
f QUESTION 3.1'1 (1.00) r List the FOUR (4) PROTECTION si gnal s that the Tave instrument.prov[ des.
3 . ., ;
, % l S i
(
1
,j GUESTION 3.12 (1.50)
I Four things happen when the two position dotary Level Trip switch on the .i source range drawer is.placed in the BYPASS position. One, it causes'a 4 !
FR/IR bypass alarm on CP-005. Li st* the rsnia i n i ng THREE (3) . A ,
- l. A Ll7 s
n QUESTION 3.13 (1.00)
State the in!tiating conditiois requ' ired for AUTOMATIC swapover of the LHSI pumps to the Rec ircul at i cn Mode followi.ng an St. !
b o1
.h *
' QUESTION 3.14 (1.25) / '
' 3-4 List the purpose (des i gn acc i den t pr otec t i ord ' f M ' the f ol i csvi ng reac tor - Q trips: >
., , . ~
- a. Power range high neutron flux tr i p -(h i gh setpc An t'): '
- b. Power range high neutron flux. trip (Iow setpoint) '
- c. Power range high neutron flux positive rate'. trip ,
- d. Power range high neutron flux negative rate trJp 4, q :. '+
- e. OT Delta T trip -
QUESTION -3.15 (1.00)
List the conditions which will generate an Emergency D.i e se l Gen e r a t'or - ( EDG) auto start signal and the app 1'i cabl e source of auto start'. '
l (**4** CATEGC!RY,03 CONTINUED ON NEXT7PAGE *****>
l L%s ,
3+ -
4- 4 x ., . .;-____ . - -------l-
l
'3.__1NSIRudENIS_AND_COMIEOLS PAGE 17 l
QUESTION 3.16 (2.00) l l .A. List three (3) purposes for rod insertion limits (RILs).
l B. How and why do RILS vary with an increase in reactor power? 'j i
I QUESTION 3.17 (1.00)
List the FOUR.(4) motor driven AFW pump AUTO: start signals. )
1 I
l QUESTION 3.18 (1.00)
-State the condition that will provide a signal to au t omat i chi l y -open the ECCS accumulator discharge valves l
1 QUESTION 3.19 (1.50) l l List the three (3) sources of water available f or the injection and l recirculat. ion phases, 2 for injection and 1 for recirculation respectively, l f ol l owi ng a LOCA.
1 l
l
' QUESTION 3.20 (1.50) 1 List the THREE (3) reasons why hot leg rec ircul at ion 'i s used subsequent to a LOCA.
-l i
l l l 1 ,
1 i
(***** END OF CATEGORY 03 *****)
- J
l Jh1 ' PROCEDUEES ' - NORtieL$_aBUQEtdeL,_EtdEEGEUC1.6UD PAGE 18 j RADIOLOGICAL _COMIROL i
' QUESTION 4.01 (1.00)
State the actions, per 1POPO3-ZG-0004 REACTOR STARTUP, which are required if during a startup, cr i tical conditions are not achieved prior to reaching the (+500) pcm limit?.
QUESTION 4.02 (2.00)-
For each of the following, state whether or not the condition (s) below will place UNIT 1 directly into an LCO. (state YES or NO)
- a. Loss of ONE (1) seismic monitoring instrument.
L b. Loss of ONE (1) meteorological monitoring instrument
.c. Loss of a PRNI channel at > 1% power.
l I d. Loss of BOTH SRN! channels at > 1% power, l
l l
I i L QUESTION 4.03 (1.50) j 1 On a reactor startup, per 00P 1POPO3-ZG-0004 REACTOR STARTUP, cr i t i cal i ty )
is declared when the reactor i s s1 i gh tl y supercritical, whichEis indicated j by what three things? -!
' i QUESTION 4.04 (1.00) i State the OXYGEN and HYDRAZINE limits in the RCS which require the. operator ;
to place the temperature divert valve (TCV-143), to the. automatic position. H I
QUESTION 4.05 (1.00) 'I List FOUR-(4) symptoms of a l ower i ng condenser vacuum, other .than reduction ~ .;
in vacuum, per AOP (1POPO4-CR-0001) LOSS OF VACUUM. !
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
l l
i L___i____-m._ _ _ _ _ _ _ m _
a.__EROCEDUEES - NDEUGL,_eBNDEMeL,_EMERGEMCY_GUD PAGE 19 EeDIOLOGICGL_CONIROL I QUESTION 4.06 (1.50)
. List.the immediate operator actions for a l oss of ONE (1') source range
- nuclear-instrument (SRNI), per AOP (1POPO4-NI-0001) SRNI MALFUNCTION,.
when:
- a. Reactor power > P-6
- b. Reactor power < P-6.
l QUESTION 4.07 (2.00) i List ALL the immediate actions for an anticipated . transient without scram I
(ATWS) per EPPM (LPOP05-EO-FRS1) RESPONSE TO NUCLEAR POWER GENERATION /ATWS.
! l l QUESTION 4.08 ( .50) l l What is the alternate source of water to be used if the AFW storage tank I
level decreases to ( 50%?
l QUESTION 4.09 (1.00)
What is used for stabilizing RCS pressure following an SI, per EOP (1POPO5-EO-ES11) SI TERMINATION, if pressurizer heaters, normal spray, and aux spray are not ava i l abl e ? j l )
I i
-QUESTION 4.10 ( .00) l THIS QUESTION HAS BEEN DELETED FROM THE EXAM j l
1 b
QUESTION 4.11 (2.00)
List ALL the conditions that support or indicate Natural Circulation (NC)
Flow as stated in AOP (1POPO5-EO-ES11) NC VERIFICATION.
l l
l I 1 1 >
l
(***** CATEGORY 04 CONTINUED ON NEXT PAGE.*****)
i
4 ._ EEDCEDUEES - UDEtdeL.,._6BWOEldeL.,._EtdEEGENC'L_eUD PAGE '20 -i rad 1DLOGICAL_COUIRQL i
1
'OUESTION 4.12 (1.50)
List the minimum channels operable and channels to trip for the following reactor trip system instrumentation:
- a. Power range neutron flux high setpoint (mode-1)
.I
- b. Intermediate range neutron flux (mode 1) 1
- c. Source range neutron flux (mode 3)
QUESTION 4.13 (1.25) 1 List the FIVE (5) immediate actions required to emergency borate when. TWO (2) or more control rods are NOT fully inserted after a reactor trip per EOP (1POPO5-EO-ES01) REACTOR TRIP RESPONSE.
QUESTION 4.14 (2.00)
List, in order, the FOUR (4) classes of emergency declarations as sta'ted in i EPIP & AOP (OEPPO7-ZA-0001) EMERGENCY CLASSIFICATIONS. l QUESTION 4.15 (2.50)
List the immediate operator actions for excessiv'e RCS leakage'per AOP-(IPOPO4-RC-0003) EXCESSIVE RCS LEAKAGE.
j QUESTION 4.16 (2.75) l List the immediate actions for a loss of automatic-pressurizer (PZR) pressure control (PPC) per AOP (1POPO4-RP-0001) LOSS OF AUTO PPC.
i i
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) !
- - - ---_--_-____--- = ______-- _ _ _ _ _ _
l sL.__EROCEDURES - MOEtdaL,_ABUOEtdeL _EtdEEGEtJCY_AtdD PAGE 21 EAD10 LOG 1CeL_CQtdIROL l
QUESTION 4.17 (2.00) I
' State the ADMINISTRATIVE personnel exposure limits for the f ol l owi n g radiation workers:
- a. Personnel at STPEGS (quarterly)
- b. Expectant mothers (quarterly)
- c. Skin and extremity (quarterly)
- d. Planned emergency doses QUESTION 4.18 ( .50)
! What is the maximum COOLDOWN rate of the RCS when the'RHR system is in l operation?
l
! QUESTION 4.19 (1.00) l State the importance for closely monitoring AFW storage tank levels per SOP l (1POPO2-AF-0001) GENERAL PRECAUTIONS AND LIMITATIONS.
l QUESTION 4.20 (1.00) 1 l
l Cal cul ate what your dose in MREM would be if you were in a 100 MRAD /hr j gamma f i el d f or 45 minutes.
l l
l l
l 1
t l
l l
l l
l l (***** END OF CATEGORY 04 *****)
l (************* END OF EXAMINATION ***************)
l I -
C__________ --
l l
1.__.EEIUf1ELES_DE_SUCIFAR PDWFP El. ANT.DEEEeIID W PAGE. 22 IBEEMDDYNeMICS._BEeI_IReNSEFR eUD_ELU1D_ELDW
. ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, RF 1
ANSWER 1.01 (1.00) c- (1.0)
REFERENCE SOTX. lesson plan HT & THERMO, sec III, part B, ch 1, . p 322, 323.
191004K114 ...(KA'S)
! e l ANSWER 1.02 (1.00) l d (1.0) l l REFERENCE SOTX l esson pl an , RXTH, FISSION PRODUCT POISON p 5-11 i 192006K106 ...(KA'S) 1 l'
l l
ANSWER 1.03 (1.50)
- a. MORE NEGATIVE (0.5)
- 6. MORE NEGATIVE (0.5) l l c. MORE NEGATIVE (due to depletion of burnable poison rods) (0.5)
REFERENCE l SOTX lesson plan RXTH, MTC & TPD, in objs 6,8,9. I 192004K106 ...(KA'S) i i
l ANSWER 1.04 (1.00)
- a. DECREASES (0.5)
- b. DECREASES (0.5)
- c. DOES NOT CHANGE (0.5)
REFERENCE l SOTX lesson plan RXTH, REACTIVITY and FUEL TEMP EFFECTS,p 15-18, in ob) 15.
192004K107 ...(KA'S) l l
l
L_EBINE1El P4 DE_ULIELFAR EDWER_ELebtT_.DEEEeIIDS PAGE 23
-1BEEtlDDXUht:tLES, HPAT'IEhMSEPR AND ELUlD_ELDW ANSWERS ~--' SOUTH TEXAS 1 -87/05/12-AIELLO, R' F ANSWER 1.05 (1.00)
- a. LOWER: (0.5)
- b. HIGHER (0,5) i REFERENCE i
_.SOTX. lesson plan, HT & THERMO ,- sec III,-part B,.ch 1, p 320, 191004K104 ...(KA'S) l l
i ANSWER 1.b6 .(1.50) l l a.' INCREASE (0.5) l l b. DECREASE (0.5) l
- c. INCREASE (0.5) l REFERENCE SOTX lesson plan, HT & THERMO, sec ~III, part B, ch.1, p 320.
191004K115 ...(KA'S) l' ANSWER 1.07 (2.00)
-a. REMAIN THE SAME (0.5)
- b. DECREASE (0.5)
- c. INCREASE (0,5)
- d. DECREASE (0,5)
REFERENCE-SOTX lesson plan, HT & THERMO, ch 2.5, p 83,~ steam tables.
193004K115 ...(KA'S) l=
L
2 f.L_ 2BlNCIELES DE_U.UBLEeB_EDUEB_ELeUI_DEEBeILDU, PAGE- 24
'IBEB110DYuetilDS,_BEGI_IRAMREER AND ELUID_ELDW ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, R F. )
l t
I 1
ANSWER 1.08 (1.50) 1 1
a.-TRUE (0,5)
- b. FALSE (0,5) !
- c. FALSE (0.5) ;
REFERENCE
.SOTX lesson' plan, HT'& THERMO, part.B ch 3 , p 193,196, sect II part C,p 271 193009K105 ...(KA'S) l i
ANSWER 1.09 (1.50) '
A. TRUE (0.5)
B. TRUE (0.5)
C. TRUE (0.5)
REFERENCE SOTX lesson plan, RXTH, RX CORE CONTROL FOR LARGE.PWRs. p 6, in obj 4.
192002K114 192005K109 ...(KA'S) !
l l
ANSWER 1.10 (1.50)
)
i (acceptable answers, any ~3 of 4) I
- a. Compensate for fuel burnup. (0.5) 1
- b. Overcome fission product poison buildup. (0,5)-
- c. Overcome effects of power defect. (0.5)
- d. Compensate negative reactivity effects due to plant (moderator) heat up. (0,5)
REFERENCE .
-I SOTX lesson plan RXTH, CONTROL ROD REACTIVITY EFFECTS, In objs 7,8.-
192002K109 ...(KA'S) l l
i j
~
1
11 -- PR T NCIELES_DE_td)DLEGE_EDWER_ ele!:JI_DEEEeIIDS PAGE' 25
- IllEEt:10DYNM i F4 HFAT_IRet2 SEER _et2D_EL.UID_ELDW ANSWERS -- SOUTH. TEXAS 1 -87/05/12-AIELLO, RF
' ANSWER 1.11 (1.00) .
(4 of 8 required) 1
- 1. Rod insertion limits are met. (0.25) 4
- 2. Maintain proper bank overlap (0.25).
- 3. Axial flux difference kept within specification. (0.25) l
- 4. The control rods i n ' a group are aligned within t or - 12 steps. (0.25) l 5.. Reactor power.(0.25)
- 6. Cool an t fl ow rate (0.25) 7 .. RCS average temperature (Tavg) (0.25)
- 8. RCS pressure (0.25) l REFERENCE' l SOTX lesson plan HT & THERMO see II, part B, ch 3, p 205-207. -
l 193008K105 ...(KA'S) l l
)
)
ANSWER 1.12 (1.00)
- 1. Density difference (or DELTA T) created by. heat. addition by the heat source and heat removal by the heat sink. (0.5)
,1 l
- 2. The heat sink must be elevated physically above the heat source.(0.9)
REFERENCE SOTX l esson pl an HT & THERMO sec III, part 8, ch 3, p 355. I 193008K121 . . . ( KA ' S ) -
-1 R.
4
L - EBlGDIELES DE GDCLEAR EDGEE EfANY DEEEATLDU 4 PAGE 26
=IBEEL1DDYNet11CS WFoT IEaNSEEE aND_ELUID riny ANSWERS --' SOUTH TEXAS 1 -87/05/12-AIELLO, RF l- ANSWER 1.13' (1.00) 1 1..It is well above the source range.
g .
OR l Source neutrons are negligible. (0.5) l
- 2. It is below the point of adding heat. (0.5)
OR Doppler' effects are not present (0.25)
-AND l MTC effects are not present (0.25)
REFERENCE SOTX lesson plan. RXTH, RX CORE CONTROL FOR LARGE PWRs,lo ob) 2.
192008K112 ....(KA'S)
ANSWER 1.14 (1.00)
(1 of 2 required)
- 1. The struck molecules are carried along with the high velocity fluid.
(0,5) This process is called entrainment. (0.5)
- 2. As the entrained molecules are carried out of t h e. d i f f-u se r , a low pressure area is created around the mouth of~the nozzle. (0.5) Th i s l ow pressure area will draw more fluid from around the nozzle-Into the throat of the diffuser, where it will be entrained. Thus the process continues.
REFERENCE SOTX lesson plan, HT & THERMO, sect III, p 338..
i.
191004K125 ...(KA'S) o
L__ERINCIELES_DE_UJJELFAR EDWER_EL ANL DEEEaI1Dti;, - PAGE 27 -.
-IEERhiDDYNAMiCS, MFAT IEataSEFR AND EL1J1D_ELOW l I
ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, RF ANSWER 1.15 (1.50) l
'A.-(As the U-235/U-238 isotopes are depleted their fraction of total fissions decreases) thus Beff decreases. (0.5).
B. Plutonium isotopes have smal l er ' del ayed neu tron fractions which j decreases the average delayed neutron fraction over core life. (0.5)
C. As the delayed neutron fraction decreases, one is likely to see a l quicker response to change.in power-(0.25), however, the magnitude of 1 the power change is not affected (0.25).
REFERENCE SOTX lesson plan RXTH, neutron kinetics p 8, in obJs 15,28 j 192003K107 192003K108 . . . < KA ' s >'
l l
l l
l ' ANSWER 1.16 (1.00) l l A. DNBR = heat flux to cause DNB / actual heat flux B. < or = 1.0 (PART "B" WAS DELETED FOR EXAM DATED 87/05/12.
THE QUESTION HAS BEEN SUBSEQUENTLY REWRITTEN TO REFLECT THIS ANSWER.)
REFERENCE SOTX lesson plan, HT & THERMO, sec II, par t C, p 262. 1 193008K110 ...(KA'S)
ANSWER 1.17 (1.00) l
, Neutrons at or near the edge of the core have a higher probability of 1 l
leaking out . than the ones at the center which have a higher probability of a causing fission. (Hence: DRW at center is > .than at' edge). (1.0)
OR They are in an area of higher neutron flux and if inserted, will absorb i more neutrons, i REFERENCE L SOTX lesson plan RXTH, CONTROL ROD REACTIVITY EFFECT,1n objs 4,8.
4 ...(KA'S) l l
l L
l
La PR.LUCLELES DE UDLLEbE EDUEE ELbNI DBERGIlD % PAGE. 28 IMFPMnDYUed1ES,'WFAT IEeMSEpp ann ELUID ELDW -
j i
. ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, RF !
ANSWER- 1.'18 (1.50)
(from formula H/0) l i
m1(hout,1'- hin,1) = -m2(hout,2 --hin,2)
'l ml = reac tor cool an t mass fl ow rate -
m2 ='feedwater mass flow rate l- . . .
(hout,2 - hin,2) - -m1/m2~(hout,1 - hin,1) l hout,2 = -ml/m2 (hout,1 -hin,1) + hin,2 ( O'. 5) i hout,2 = -(6 x 10exp 7 lbm/hr) / (6 x 10exp 6 lbm/hr) .x l
(580 Btu /lbm - 650 Btu /lbm> + 400 Btu /lbm (0,5)'
hout,2 = [(-10) x (-70 Btu /lbm>3 + 400 Btu /lbm i
1 hout,2 = 700 Btu /lbm + 400 Btu /lbm '
hout,2 = 1,100 Btu /lbm (0.5)
Thus, the en th al py of the steam produced is 1,100-Btu /lbm. i REFERENCE SOTX lesson plan, HT & THERMO sect II, part.A, ch 2, p 70, steam tables. J l 193003K119 193003K124 . . . ( KA ' S ) - i l
ANSWER 1.19 (1.00)
[ From the steam tables, l' psia corresponds to a saturation' temperature of 101. 74 de g F.- (0.5) i The difference between the saturation temperature and the' condensate i
L temperature is the condensate depression, thus:
l '101.74 deg F - 95 deg F = 6.74 deg F (0.5)
REFERENCE SOTX lesson plan, HT & THERMO, sect II, part B, ch 2, p 183, steam tables.-
l 193004K111 193008K115 ...(KA'S) 1 i
l l
1
i Lo- 2BINCl2LES DE UUCLEaR BDUEE ELANT DEERaIlDU, PAGE '29
'IBFRMnDYUatilCS,_ BEAT IRaMSEER AND ELUlD ELDW ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, RF l
l l
ANSWER 1.20 (1.00)
The. process or phenomenon of utilizing source neutrons to. sustain the chain reaction for Keff < 1.0. (1.0)
REFERENCE SOTX lesson plan, RXTH, SUBCRITICAL RXTH, in objs 4,5.
192003K101 ...(KA'S) l I
1 l
, 4 l
i I
\
1 l
1
! J 1 -
l c
1' l
l l 'I 1
E_._______________.____
L__ELetiT_DESIDN_lMCLUDIUB_SeEEIY_eND_EM F R GENCY_SYSIEt1S PAGE 30 ANSWERS - SOUTH TEXAS 1 -87/05/12-AIELLO, RF ,
l 1
ANSWER 2.01 (1.00) a (1.0)
REFERENCE SOTX lesson plan, Bk 4, PZR PRESS RELIEF, p 6, in obj 12 007000A301 ...(KA'S)
I ANSWER 2.02 (1.00) i a or b ' '
REFERENCE -
SOTX lesson plan, BK 2, MAIN GEN & EXIT, p 20-25, in obj-5.
1 ...(KA'S) 1
{
l l
l l
ANSWER 2.03 (1.00) l l l
- a. as is/ fail shut (0.2) i
- b. as is (0.2)
- c. as is (0.2) l
- d. divert flow to VCT (0.2) )
- e. open (0.2) ,
f REFERENCE
]
SOTX lesson plan, Bk 5, CVCS, p 10-13, In.obj 3. 1 3 ...(KA'S)
I l
ANSWER 2.04 (2.00) 1 i
- a. FALSE (0.5) )
I
- b. TRUE (0.5) i
! c. TRUE (0.5) -) '
l d. TRUE (0.5) i REFERENCE' SOTX lesson plan, Bk 1,-FPS, p 17, in obJs 3.G, 14.G, 24.
j 086000A302 ...(KA'S) i l
l l 1 l -l l
l 1
- -- _-_O
1 A-2.__ELGUI DESIGU_ INCL 1) DING _SeEFTY AND' mERGEh!CY SYSIEldS PAGE ~ 31
' ANSWERS - . SOUTH TEXAS'1 -87/05/12-AIELLO, R . F.
l
'I ANSWER 12.05 (1.75) d
- 1. a (0.25) 2.: e .(0.25)
- 3. d (0.25)
- 4. a (0.25)
- 5. b (0.25) >
- 6. a (0.25).
- 7. c' (0.25)
REFERENCE SOTX lesson plan, Bk 4, EX CORE NI, p 11.
015000K407 ...(KA'S) {
i I
I. ANSWER 2.06- (1.00)
L I
- a. trips main turbine (0.5) -)
L b. trips permanent magnet generator supply breaker (41M). (0.5) 1
- c. generator output breaker (0.5) 1 (2 of 3 required) . l l
REFERENCE i
SOTX lesson plan, Bk 2, MAIN TURB GEN & EXCITER,.p 20. !
1 ...(KA'S) i l
I ANSWER 2.07 (2.00) 1 (8 of 12 required)
- 1. low bearing oil pressure (0.2) (10 psig) . (.05).
- 2. Iow pressure in the low pressure trip header (0.2) (35 psig) .(0.05). ;
- 3. Iow main condenser vacuum (0.2) ( 14" Hg). (0.05) ,
- 4. high rotor vibration =(0.2) (.005") (0.05) l
- 5. high thrust bearing wear (0.2) (.010"'in either direction.) .(0.05). 1 1.
- 6. .both h i gh pressure and l ow pressure' stop val ves ; cl osed (.25)-
- 7. trip push button from either control panel'is depressed
(.25)
- 18. safety injection.
(.25) ;
- 9. excessive cooldown protection (.25) l 10. Hi Hi S/G 1evel (.2),(90%) (0.05)
L 11. Lo Lo feedwater suction' pressure (.2);(189 psig) .(0.05) l 12. MFW pump turbine' trip on overspeed (0.20), 110% (0.05) l 5
i
c2.a_ELeUI DESIBILlEL1)Dit1G_SeEEIY_AND FMFREEEY SYSIEtiS PAGE 32 J
ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, RF
]
REFERENCE SOTX lesson plan, BK 3, S/G MFP, p 10, in obJ 9.
059000K416' ...(KA'S) i
. ANSWER 2.0S (2.00) l
.. l A) Containment pressure - hl 2 (0.5) l {
i B) Steamline pressure - negative rate (0.5) i C)- " compensated" steamilne pressure - l ol o. (0.5)
D) " compensated" Tc - lol o ;
E) SI (0.5) i I
(4 of 5 required)
REFERENCE i SOTX lesson plan, Bk 3, MAIN STM, p 17, in obj 13.
039000K405 ...(KA's) 1 I
i ANSWER 2.09 (1.25)
- 1. Flow into the upper ~ head (for cooling purposes) (0.25)
- 2. Flow entering into the rod' cluster control guide thimbles (to cool the l l
control rods) (0.25) '
l 3. Leakage flow from the vessel inlet nozzle directly to the vessel outlet l nozzle through the gap between the vessel and the barrel (0.25) l 4. Flow introduced between the baffle and the barrel-(for the purpose of 3 l cooling these-components and.which is not considered avail abl e f or core l cooling) (0.25)
- 5. Flow in the gaps between the fuel assemblies on the core periphery and the adjacent baffle wall (0.25)
REFERENCE l .SOTX lesson plan, BK 4, RX VESSEL & INTERNALS, p 14. !
002000A105 ...(KA'S)
),
l d
1.
I I
1 l
- 2 __ELeNI_DESISbLINELUDINS_SAFFTY eND_EMERSENCY_SYSIEMS PAGE 33 ANSWERS'-- SOUTH TEXAS 1 -87/05/12-AIELLO, RF ANSWER 2.10 (1.50)
(6 of 7 REQUIRED) l
- 1. RHR heat exchanger ( 0. 25). ;
2 -. RCP thermal' barr ier (0.25) 1 3.LLetdown heat exchanger (0.25)
- 4. Excess letdown heat exchanger (0.25)
L 5. Seal water 1 heat exchanger (0.25)
- 6. RCDT heat exchanger (0.25) l - 7. Sample coolers (0.25)
REFERENCE SOTX lesson _ plan, BK 4, CCW, p 41, in obJ 1.
008000K301 ...(KA'S) l ANSWER 2.11 (1.50)
- 1. All equipme.nt operation on vital buses is terminated on loss of power-l j by the load shed signal. (0,5) 3 l 2. Diesel generators start and connect to the vital buses withinL10 seconds subsequently vital power restored. (0.5) l '3. ESF loading sequence commences on DG breaker (s) closure. (0,5)-
l REFERENCE l- SOTX lesson plan, Bk 5, ESF system, p 22, in obJ 10.
013000K407 064000K411 ...(KA'S) l ' ANSWER 2.12 (1.00) 1
- 1. Engine overspeed (660 rpm) (0.25) l- '2. Generator' differential (0.25)
- 3. Loss of 125 VDC control power (0.25) i 4. Local emergency stop pushbuttons (0.25) l 5. Low oil pressure trip (0.25) 1 (4 of 5 required)
REFERENCE ~
SOTX lesson plan, BK 5, ESF D/G, p 4.
.064000K402 ...(KA'S)
E____________._ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _
l L__ELeUI_DESIDU_ INCLUDING _SeEEIY_eND_EMERBENCY_SYSIEMS PAGE 34 )
J ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, RF ANSWER 2.13 (1.95)
- 1. Pressur i zer si gnal (0.15) produced by 2/4 (0.15) low pressurizer-pressure signals ,1850.psig. (0.15)
- 2. High containment pressure ' signal (0.15) produced.by 2/3 (0.15) high containment pressure signals , > or = 3.0 psig. (0.15)
- 3. LoLo ,Tc Si gnal- (0.15) , 532 deg F, (0.15) ' produced by 2/3 (0.15) ..l ol o j Tc signals in one Ll oop coi nci den t wi th e i ther-a neu tron fl ux bel ow 10%. l i
(plus P15) power or.a reactor trip. (0.15) {
q
- 4. Low Steaml ine Pressure Si gnal (0.15) produced by 2/3 (0.15) low I ste am1'i ne. pressure in one line ,735 psig. (0.15) l REFERENCE SOTX lesson plan, BK 5, ECCS, p 4, in obj 5.
]
006030A201 ...(KA'S) l l
l i
ANSWER 2.14 (1.00)
(4 of 6 REQUIRED) l l a. AFW pumps start. (0.25)
- 6. AFW isolation valves open (0.25)
- c. AFW reg valves open (0.25) i d. AFW crossover valve closes (0.25) j i e. AFW turbine steam inlet and trip & throttle valves open. -(0.25) . j
- f. Auto start of aux feedwater pump cubicle ventilation (0.25)
REFERENCE SOTX lesson plan, Bk 6, AFW, p 6, in ob) 1. . ,
013000A401 ...(KA'S) j i
c l
l l
l l
l L_ _ ______ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ __
' 2o_._ELablI_DESISbLib!CL1)DlblG_S6EEIY_eUD_EldERSEblCY_SYSIEldS PAGE 35 ANSWERS'-- SOUTH' TEXAS 1 -87/05/12 ,AIELLO,'R F ANSWER 2.15 (1.50)
- a. Safety valves lift
- b. PORUS open
- c. Spray initiated l d. Backup heaters on 1
1 I e. SI bl oc k/u n bl oc k l
- f. Low pressure safety injection actuation (0.25 ea)
REFERENCE
' SOTX lesson plan, BR 4, PZR PRESS & LEVEL CONT, p 17, 18,1n obj 6.
011000K103 ...(KA'S) l l ANSWER 2.16 (1.00)
A. Provides backup power to ESF busses (via motor operated disconnect switches and busses). (0.5)
- b. Eastside of switchyard inside fenced perimeter. ( 0 . 5) '
REFERENCE SOTX lesson plan, Bk 1, OFFSITE ELECT DIST, p 9, in obj 3e.
062000G004 ...(KA'S) l 1
l ANSWER 2.17 (1.00)
I a. Loss of seal water will cause a l oss of cool filtered water to the lower l radial bearing and the Mi seal. (0.25) Leakage from the RCS up the I shaft, past the thermal barrier heat exchanger will provide unfiltered I ceol water to the bearing. (0.25) The lack of f il tration coul d cause higher wear on the bearing, and shorter life for the #1 seal. (0.25)
- b. YES (0.25) (Pump operation with th i s casual ty will be within design j limits)
REFERENCE =
SOTX lesson plan, BK 4, RCPs, p 13, In1obj 7.
003000A201 ...(KA'S) l
i l
l' 24__EL6MI_DESISN_ INCL 1JDIUS_SeEEIY_eND_ FM F R GENCY_SYSIEldS PAGE 36 ANSWERS'~- SOUTH TEXAS 1 -87/05/12-AIELLO, RF I l
l ANSWER 2.18 (1.00)
Upon receiving a rapid insurge of water, the average water temperature of. .j the pressurizer is < saturation temperature for 2235.psig. (0.5) So in anticipation of an ensuing outsurge, possibly resulting in excessive pressure transient, B/U heaters come on when level is 5% above programmed..
level to. help bring pressurizer water temperature back to saturation temperature for-2235 psig. (0.5)
REFERENCE j
SOTX lesson plan, BR 4 .PZR PRESS & LEVEL CONT., p 14, in obj 15.
3 011000K103 ...(KA'S) l l
l ANSWER 2.19 (1.00) 1 A cl osed RED " TARGET" flag would be displayed. l l
REFERENCE SOTX lesson plan, Bk 2, MAIN GEN & EXIT, p 12, in obj 3.
062000A401 ...(KA'S)
I l
l l
i l
l l l
l l
l l
l l
l 1
I i
1 __lb1SIEUMFUTS_eUD_fDUIEDLS- PAGE. 37 1
ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, . R F.
ANSWER 3.01 (1.00) e
- REFERENCE
- SOTX? lesson plan, Bk 4, EXCORE NI, p 1,2,13,.In obJ 2.
015000K502 ...(KA'S)
ANSWER 3.02 (1.00) a REFERENCE SOTX lesson plan, Bk 4, PZR PRESS AND LVL CONT,-p 26.
l 011000A210 ...(K4'S) .
l l
ANSWER 3.03 (2.00)-
1 l U - urgent 1 N - non urgent
- 1. U
^
- 5. N
- 2. N- 6. N
- 3. N 7. U
- 4. N 8. U '
(0.25 each) l REFERENCE SOTX lesson plan,.Bk 6, DRPI, p 2, in ob) 3.G.
001000K403 001050A201 ...(KA'S) -
ANSWER 3.04 (1.00)
- a. DECREASE (0,5) :
- b. DECREASE (0.5) I REFERENCE '
SOTX lesson plan, BR 4, TEMP MON, p 12, in obj 3.
i 012000A101- ...(KA'S)
&' iblSIE1)L1EhlIS_eblD_fDUIRDLS PAGE '38
. ANSWERS'- . SOUTH. TEXAS 1 -87/05/12-AIELLO,1R F ANSWER 3.05 (2.00)
- a. TRUE. (0.5)
- b. FALSE (0.5) i
- c. TRUE (0.5) I
- d. TRUE (0.5)
REFERENCE
.SOTX 3esson plan', GOP & ENG PROC, PLANT H/U, p 13, 15,.16.
002020A301 ...(KA's)
,l ANSWER- 3.06 (2.00) l 1
- a. TRUE (0.5) g b. FALSE ( 0. 5)'
j c. FALSE- (0.5) l l' d. FALSE (0.5) t REFERENCE SOTX lesson plan, Bk-6, SGWLC P 9-12, in obj 6,7,12.
0 350 0 0 GO,0 4 ' ...(KA'S)
ANSWER 3.07 (2.00)
I a. FALSE (0.5) l .b. TRUE (0.5)
- c. TRUE ( 0,5)-
- d. FALSE (0.5)
REFERENCE
.SOTX lesson plan, BR 4, PZR PRESS & LUL CONT SYS P 7-9,.in obj ~ 7,1 O' .
010000K602 ...(KA'S)
LANSWER' 3.08 (2.00)
- a. FALSE'(0.5) b..TRUE (0.5) i
- c. FALSE ~(0,5) l i
-d. TRUE' (0.5)
REFERENCE SOTX lesson plan, BK 6, ROD CONT P 29, in obJ 11,,12,13.-
001000K403 ...(KA'S) l
=____________--__ _-_ ._ _ _ _ _ _ _ - _ _. . _ .
3.__.lNSIRIIMFNYR AND_EDbiT9nt R .PAGE 39 ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO,.R F ANSWER 3.09 (1.50)
(RT 8043) (0.5) 1
L 4. discharge of TGB sump 1. sump, pumps (RT 8041) (0,5) l L (3 of 4 required) ,
1 REFERENCE '!
SOTX lesson plan, Bk 7, RAD' MON SYS,'part II, p 51,In obj 2.
073000K101 ...(KA'S) l l
ANSWER 3.10 (1 00) l
- a. Cool an t temperature (0.25) l b. Pressure (0.25) i l c. Power (0.25)
- d. Axial power distribution (0.25) i REFERENCE i SOTX lesson plan, BR 4, TEMP MON, p'10, in obj 7.
012000K611 ...(KA'S)
I l l i ANSWER 3.11 (1.00)
! a. OT Delta T (0.25)
I b. OP Delta T (0.25) i
- c. Low Tave (0 25)
- d. Low-Low Tave (0.25) l REFERENCE SOTX lesson. plan, Bk 4, TEMP MON, p 9, In obj 2. !
015000K601 ...(KA'S) ,
1 t
f
_ . ~ _ _ _ _ - - - . _ - - _ -
I
~ 3s__INSIBUMEUIS_AND_EDNIEDLS PAGE 40-ANSWERS --' SOUTH TEXAS 1 -87/05/12-AIELLO,-R F ANSWER. 3.12 (1.50)
- 1. The l e v el trip' bypass lamp. lights (0.5) 2.;The operation selector switch is enabled (0.5)
- 3. A 118 UAC signal is provided to prevent a reactor trip condition during.
test operations. (0.5)
REFERENCE
'SOTX lesson plan, Bk 4, EXCORE NI, p 5, in obJ 9,10..
015000K406 ...(KA's) 1 ANSWER 3.13 (1.00)
Receipt.of RWST Low-Low level alarm (0.5) coincident with an SI signal (0.5)
NOTE 'No credit shall be lost if the candidate states "at least one of the two miniflow isolation valves for each pump must be closed before the associated sump i sol at i on val ve can open" .
REFERENCE SOTX lesson plan, Bk 5, ECCS p 2, in obj 14.
005000K411 ...(KA'S)
L 1
l l
l
__ _ - _ - _ _ - _ _ _ _ --- - - - - _ _ _ - -_ - - - - _ _ _ _ - ____O
- 3 __INSIEUMENIS_eND_CDNIBDLS PAGE 41
-ANSWERS -- SOUTH. TEXAS 1 -87/05/12-AIELLO, R F ANSWER 3.14 (1.25) a.' Protects against excessive heat flux leading to DNB due.to reactivity excursions (0.25) ]
- b. . Protects.against reactivity excursions which are too rapid to be protected by temp & press protective circuitry (0.25)
- c. Protect against rod ejection accident (0.25)
I d. Protect against mul t i pl e rod drop (0.25) l l~ e. Protect from DNB (0.25) i
! (alternate answers for "a" and "b")
l
- a. Provides protection during power-operations to mitigate the-consequences of a reactivity excursion from all power levels.
- b. Provides protection during subcritical and low power operations to i mitigate the consequences of a power excursion beginning from low power.
1 1
REFERENCE SOTX lesson plan, BK 6,.SSPS p 6, in obj 2.
012000G004 ...(KA'S) l l
l l ' ANSWER 3.15 (1.00) I I !
i l 1. Safety Injection (0.25), from respective " Train (A,B, or C) Actuation" l 1rgic. (0.25) l 2. Under Vol tage (0.25), from respective train " Load Sequencer". (0.25).
l l REFERENCE SOTX lesson plan, Bk 5, ESF DG, P 3.
i 064000A301 ...(KA'S)
L l
l l
l 1
A__lblSIB1JtdENIS AND EDhlIRDLS PAGE- 4 2 '.
ANSWERS - -SOUTH TEXAS 1 -87/05/12-AIELLO, RF l
l AN9 DER 3.16 (2.00)
A. 1. Maintain adequate shutdown margin (0.5) .
- 2. Maintain nuclear peaking factors within limits (0,5) ,
3L Minimize the effects of an ejected rod (0.5) l
~
1 B.-RIL increase with increasing reactor power because the power defect I increases with increasing reactor. power (0.5). l I REFERENCE SOTX lesson plan, Bk 6, ROD CONT -In ob) 28c, P 4' 3 001000K504 ...(KA'S) !
')
,)
ANSWER 3.17 (1.00). j
- a. S/G Lo-Lo level (0.25) a
- b. Safety Injection (mode 1) (0.25)
I c. LOOPL(mode 2) (0.25)
I
l REFERENCE SOTX lesson plan, Bk 6, AFW P 2, in obj 4.
061000K402 ...(KA'S)
-1 ANSWER 3.18 (1.00) l
- 1. "SI" si gn al (0.5)
- 2. The auto open signal generated bp increasing. pressure.above the'P-11 setpoint. (0.5)
REFERENCE-SOTX lesson plan, Bk 5, ECCS P 3, in obj 4.
006000A301 ...(KA'S) j l
L e
'h
f J"
- .t__1MSIB1JtdEMIS_eUD_CDNTpnl A PAGE -43 ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, RF ANSWER- 3.19 (1.50)
- 1. Injection phase source of water:
- a. RWST-(via HHSI/LHSI pumps) (0.5)
- 6. Accumulators (0.5)
- 2. Recirculation phase source of waters
- a. containment sumps (0.5)
REFERENCE SOTX lesson plan, Bk 5, ESF SYS P-16, ECCS SYS'in obj-14.-
ANSWER 3.20 (1.50)
- 1. Terminate boiling in the reactor vessel . (0,5)
- 2. Establ i sh subcool ed fl ow through the core (0.5)
- 3. Recover boron that has pl ated out on_the fuel- and upper internals (0.5)
REFERENCE
'SOTX lesson plan, BK 5, ECCS P 5, in obj 14,18.
000011K313 ...(KA'S)
}
H.
y o
.4o__EBDCEDDEES_ UDEtttL,_eBNDEMAL.,_EldEnrwNN suD '
y- ,%AO(; g 44 l EeDlDLDSICAL DDtATEDL .
~
n;. ' # ;
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ANSWERS -- SOUTH' TEXAS 1 -87/05/12-AIELLO, R.F 1 4
c AN%ER 4.01 (1.00)
Hal t further rod withdrawal (0,5) and notify the' shift supervisor.*(0.5)' ,
- k. s
, OR y
+ 1
.)\ .h.
' Insert nods to the jl 500" pcm 1imit (0.5) and notify ,the shift s}per)isee.[. .
(0.5) i 't j r- ,: .y .-
REFERENCZ 1 ., Nk ,
SOTX. lesson plan, RXTH, S/D REACTIVITY CONSIDERATIONS P 6,.LN OBJ,J,g ( '
-y .a p.
REACTOR STARTUP (1POPO3-ZG-0004). % \N t U 192008K103 ...(KA'S) ,
.E .\t '
, ,^
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, * % L [- 3 r( k \g It
,a
-ANSWER 4.02 .(2.00) * '3 '
L-
- j 8-. J 5 > El J
y .
- q t ..
- a. YES (0,5) "
2 + L..
- b. YES' (0,5) 4 'd 4 ,
c . YES ' (0.5)
- d. NO (0.5) 1 y> ;l 4 b f
REFERE' .:: ,g ,
bOTX T . S . , LCO 3.3.1, 3.3.5,3, 3.3.3,4.
(' '
015000 "Si . . . WW S ) Y .
{
A i
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. i l d . %-. . .
A l D 3
,4 ,
l i
ANSWZR 4 03 (1.50) '
5 S
g N
- i
'1o -
Start up.rrth a is esitive (0.25) and constant (0.25 , rea'cta power k t si N increating-00.5), and there is no positive reactid )ty being aided,q't [ >j>n," ' "
c on t reA, rod motion L(0.5).
3 -y .e 4 t . s ) ; i. - ,
i
, ?
n Jz s < , s; REFERENCEi h) , y s ][ '
i SOTX 'l e sson,. p 1 an , RATy , YRX CORE CONTROL FOR LARGE PWRs,1 %ob.,.1i 'k "
RE$CTOP STARTUP (1POPD'3-ZG-0004) %
- 192008k111 ...(Ln'5)' v h 7a ly
+ .m t w',. 3l' y
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,. ( I
% 4 % 1- , .
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@ AA__ERDCED1JRES - Nnntlet, asunRMAI_; FMFRSEhlC.Y_eND PAGE 45 y, RaDIDLDSirel rnuvent
, 1 ANSWERS -- SOUTH TEXAS 1 -87/05/12-AIELLO, R F' J- I 4.04 (1.00) s.' ANSWER l[ !
l
- h OXYGEN < 0.1 ppm (0.5) !
l + .I t pe -
0jHYDRA21NE <0.5 ppm (0.5F 1 ,
l )2? REFERENCE . .
l SOTX lessonLp'lan, GOP & ENG PROC, PLANT H/U, p'9, 10. J Li--004000K401 ...(KA'S) H
{}
1
. ANSWER 4.05 (1.00) j
- 1. Unexplained decrease in turbine load (0.25)
L 2. Increase in turbine exhaust hood temperature-(0.25) j I
- 3, fa-ceeSed condensate. temperature (0.25) {
L .I
^
Inu en,e in circulating water inist.to outlet di f f eren t i al _ temperature - j sG 2d> '
l-
. s_ .. _ a. wei- v ac u um low alarm (0.25) l' (4 of 5 requinad)
)
REFERENCE SOTX AOP, (1PQPN' "P="^':
L 000051G011 ...(KA'S)
,)
. ANSWER 4.06 (1.50) n at No immediate operator actions are required (0,5)-
I L -bl . Suspend al l operations involving core' alterations or positive reactivity. j changes. (Refer to T.S.- 3.9.2 and 3.3.1'.) (0.5) 2.If reactor trip has occurred, then' refer to-EO-DOOO.(reactor trip or Safety Injection). (0.5)
PEFERENCE I
, .SOTX AOP,- (1POPO4-NI-0001) ;
015000A201 ...(KA'S) :
1 I
1 L
l l
l
\
l L :
L :
".4.i_ EEDCED1JEES - NnPMe M eBUDEMAL_EMEEEEb!E.Y_GUD PAGE. 46 EADIDLDGlteL_LDb!IEDL ANSWERS ---SOUTH TEXAS 1 -87/05/12-AIELLO, RF
.t 1 ANSWER 4.07 (2.00)
I
- 1. Verify reactor trip, if reactor trip bkrs will not open then open 480v j LC FDR BKRS 1K1 and 1L1 (0.5) .i 1
- 2. Verify turbine trip, if turbine will not trip then trip EHC oil pumps (0.5) i
- 3. Start AFW pumps (0.5) )
- 4. Verify all rods inserted, if 2 or more rods failed to insert, then emergency-borate (0.5) i REFERENCE SOTX EPPM, BK 7, (LPOPO5-EO-FRS1).
000029G010 ...(KA'S) {;
1 ANSWER 4.08 ( .50) l Hotwell (0.5)
REFERENCE a l SOTX EOP, BK 2, (1POPO5-EO-E010).
061000K107 ...(KA'S)
ANSWER 4.09 (1.00)
Use ONE (1) pressurizer PORV. (1.0) l REFERENCE 1 SOTX EOP, Bk 3A (1POPO5-EO-ES11) P 27. )
010000A201 010000A202 ...(KA'S) j l
l i I
4.10 ( .00)
L ANSWER j THIS QUESTION HAS BEEN DELETED FROM THE EXAM l REFERENCE SOTX EOP, Bk 3A, (1POPO5-EO-ES11), RCP START CRIT, P 1,.SYS BK 4.'RCPs.In obJ 12.
l 003000K614 ...(KA'S) l I
I I j
1 A__ERDCED1)RES - UDEUA ARNnpMAt ,_EMEEEEUCY_6UD PAGE '47
-EADIDLDGICAt nDUIEDL -
ANSWERS - -SOUTH TEXAS 1 -87/05/12-AIELLO, R F'
)
l l
l
. ANSWER 4.11 (2.00) 1.. RCS Subcool ing - ) 31F (0,5)
'2. Core Exit. temperatures stable or decreasing (0.5)
- 3. S/G. Pressures stable or decreasing (0.5) l 4. RCS (loop > Hot Leg Temperatures are stable or decreasing. (0.25) RCS l (loop) Cold Leg Temperatures are near saturation temperature for S/G I l
Pressure. (0.25) I
)
REFERENCE l SOTX EOP, Bk 3A, (1POPO5-EO-ES11), NC, P 1. l l 193008K122 ...(KA'S)
I L
ANSWER 4.12 (1.50) 1
-t I a. 3,2
- 6. 2,1
- c. 2,1 (0.25 pts each) l I REFERENCE l SOTX T.S., TABLE 3.3-1, P 3/4 3-2.
015000K101 015000K301 ...(KA'S)
I i ANSWER 4.13 (1.25) l l l l 1. Verify running or START one (1) CCP. (0.25)
I l
! 2. START one BA pump (0.25) l
- 3. OPEN emergency borat i on fl ow con trol valve (0.25)
- 4. OPEN chargi ng fl ow con trol valve (0.25)
- 5. Verify ) 30 gpm flowrate. (0.25) l 1
l l
l l
1
l i
do__EEDCED11PFA - UDBideL_6BUDELieb_Eb!EEEENfN AhfD PAGE' 48
-B&DlDLDBlL6L_EDUIRDL .
i
)
~ ANSWERS'-- SOUTH TEXAS 1 -87/05/12-AIELLO, RF i i
REFERENCE SOTX EOP, Bk 3, (1POPO5-EO-ES01) P 15.
000005A203- ...(KA'S) l J
ANSWER .4.14 (2.00) J
- a. Notification of unusual event (0.5).
- b. Alert .
l (0.5) {
i 3
- c. Site. area emergency (0,5)
- d. General emergency (0.5)
REFERENCE l SOTX EPIP & AOP, (DEPPO1-ZA-0001) P 4.
194001A116 ...(KA'S) 1 f
ANSWER 4.15 (2.50)
.1. Verify automatic actions, IF required. (0.5)
- 2. Verify pressurizer level is being maintained between 25% and 60% j PRESSURIZER LEVEL. (0,5) l 3. Start additional charging pumps as necessary. (0.5) ;
- 4. If unable to maintain pressurizer level, then: !
- a. Trip reactor (0.5)
- b. Initiate Safety Injection (0.5) J REFERENCE I l SOTX AOP, (1POPO4-RC-0003), P 2.
~
000009G010 ...(KA'S)
J ,
l J l
o ;
i l
l :
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1 l 1 I
1
_ _ _ _ - - - _ _ _ _ _ 1
A _ EEDEED1JEES_=_UDEdeL_eBNDEdeL FMFRAFNC.Y_aND PAGE. 49 EaDIDLDDICAL_EDNIEDL ANSWERS'-- SOUTH TEXAS 1 -87/05/12-AIELLO, RF
-l 1
l ANSWER 4.16 (2.75)
- 1. Check if any PZR pressure channel has failed high or low. If yes, perf orm the f ollowing :(0,5)
- a. Select a position on the PZR PRESS CONT SEL switch that removes the failed channe'l from control. (0.25) R
.2. Check PZR spray valves closed if < 2235 psig. (0.5)
- a. Pl ace spray valve controllers in manual (0.25)
- b. Close the spray valves (0.25)
- 3. Check PORVs closed if < 2235 psig. (0.5)
- a. Close PORVs (0.25)
(0.25) !
' REFERENCE i SOTX AOP, (1POPO4-RP-0001), P 3. !
010000G014 ...(KA'S) 1 i
l ANSWER 4.17 (2.00) l l
- a. 1000 mrem /qtr (0.5) l l l 1
- b. 100 mrem /qtr (0.5) l c. 6 Rem /qtr (skin) (0.25)
I 15 Rem /qtr (extremities) (0.25) 1
- d. 25 Rem whole body for emergency operations. (0.25) l 75 Rem whole body for life saving operations. (0.25).
REFERENCE SOTX ADMIN PROC, (OPGP03-ZR-0026).
194001K103 ...(KA'S)
, ANSWER 4.18 ( .50) 100 deg F/hr (0.5) 1 L . .
f 5 __ERDCED1)EFI - NnRtdeLo_eBNnpMM-,_EMFRAEbC'_etJD PAGE 50 BADlDLDDICAL CDtGPJ3L
. ANSWERS - SOUTH TEXAS 1 -87/05/12-AIELLO, RF REFERENCE SOTX SOP (1POPO2-RH-0001), P 6.
005000A101 ...(KA'S)
ANSWER ~4.19 (1.00)
AFW pumps have no loss of suction trip protection on AFWST low level.
l l REFERENCE l SOTX SOP, (1POPO2-AF-0001), p 2.
061000A104 061000G010 ...(KA'S) 1 ANSWER 4.20 (1.00) 100 MRAD /hr = 100 MREM /hr ( OF = 1 for gamma)
I j 100 MREM /hr (0.75 hrs) = 75 MREM I
REFERENCE' 10CFR20 194001K103 ...(KA'S) l l
i, l
l l \
l l
l l
l l
l L________._________.__ __
i T ;
l '
i U. S. NUCLEAR REGULATORY. COMMISSION .
SENIOR REACTOR' OPERATOR LICENSE EXAMINATION FACILITY: _SDUIB_IEXe5 1 . _ _ __
REACTOR TYPE: _ EWE WECd____ _
DATE ADMINISTERED _B2ZD5Z19 ______ !
EXAMINER: _UCCEDEX._S._ _ -
CANDIDATE: _
iINSIEUCILDUS_IQ_CeUQlDAIE.:.
Use separate paper for the' answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each.
question are indicated in parentheses after the question. The passing grade requires at leact 70% in each category and a final. grade of at least 80%. Examination papers will be picked up six (6) ' hours after the examination starts.
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% OF iCATEGORY % OF CANDIDATE'S CATEGORY .f L_U6LUE_ _IDI6L ___SCDEE _UALDE__ ________L6IEBDEX___ _
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_25.0D__ _25.38 - 5. THEORY OF NUCLEAR POWER PLANT.
OPERATION, FLUIDS, AND THERMODYNAMICS ;
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_25.QQ__ _25.38 '
- 6. PLANT' SYSTEMS DESIGN, CONTROL, j
AND INSTRUMENTATION
,_23.50__ _23.84 __ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND. RADIOLOGICAL l CONTROL 1
L25.QQ__ _25.28 - _____ 8. ADMINISTRATIVE PROCEDURES, ,
CONDITIONS, AND LIMITATIONS l
.28.50__ *;
Tot al s ?
Final Grade All. work done on this exami< nation i s my own. I have neither given nor received aid. -] 4 I
Candidate's Signature I I i l >
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'l i L __IBEDEY_ DE_flUCLEeE_EDWEE_EL6tJIiDEEEeIIDth_EL1J1DS._ /" JD PAGE 2 IBEEUDDXt%Lil.CS I l QUESTION 5.01 (3.00)
Explain how RCS boron dilution may cause an undesirable variance in axial core power. Include a detailed discussion of what occurs to axial power l
L distribution with time. Assume full' power, steady state equilibrium
-conditions, and systems in automatic. (3.0) :
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l QUESTION 5.02 ( .50) l t
l Givent Four reactor coolant (RCP) pumps operating in parallel, each with a flow rate "m" an d a c omb i n e d f l ow r a t e "M". Which one of the following best l
describes the system response to securing one RCP? 'i
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- a. The resulting core f l ow (M) will decrease as i n d i v i du al operating RCP flows (m) decreases.
- b. The resul t i ng core fl ow (M) will increase along with individual operating RCP flows (m). )
- c. The resul t i ng core fl ow (M) will decrease as individual operating RCP
, flows (m) increases.
l l d. The resulting core flow (M) will not change due to decrease in RCP 3 back pressure.
1, QUESTION 5.03 (1.00)
List the FOUR (4) plant parameters observed to insure that CHF or DNBR limits are not exceeded. j 1
1 j GUESTION 5.04 (1.00) i l List all of the conditions that must be present i n order f or natural circulation to exist?
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i QUESTION 5.05 (1.00) l State TWO (2) reasons why 10 exp -8 amps is chosen as a standard reference l for critical rod height data. NOTE: " standard reference" is NOT.an l acceptable answer.
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L QUESTION 5.06 (1.00) i A centrifugal pump is started up with its discharge valve open. How would l
the f oll owi ng parame ters di f f er(HIGHER, LOWER, THE SAME) if the pump had been started with its discharge valve shut? i l
l a. Motor current'
- b. Discharge pressure QUESTION 5.07 (1.50)
Indicate whether the f ol l owi ng wi l l INCREASE, DECREASE, or have NO EFFECT )
on the available NPSH of a centrifugal pump:
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- a. Throttle shut on the pump discharge valve i I l
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- b. Increase the temperature of the suction side fluid' j i
- c. Increase the pressure of the N2 bl anket on the suction side supply !
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QUESTION 5.08 (1.50) l With respect to reactor start up, indicate whether each'of the f ol l ow i ng j statements are TRUE or FALSE:
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- a. The purpose of pulling the shut down rods is to provide adequate l negative reactivity which may be inser ted shoul d a problem occur.
l l b. Counts doubling indicates that the margin to criticality has been
) halved.
I c. If counts have doubled, adding the same amount of reactivity will l_ cause the reactor to go supercritical.
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.So__IBEDRY_DE_UUCLEeR_EDWER_ELeUI_DEEEellGN._ELulDS._eUQ PAGE 4 ~l IBERdQDYUedlCS QUESTION 5.09 (2.00)
For steam (at 1000 psia) ' going through a throttling process, indicate whether the f oll owi ng par ame ters wi ll (INCREASE, . DECREASE, or REMAIN THE ,
SAME.)- (NOTE: assume ideal conditions) )
- a. Enthalpy -
i 6. Pressure J c. Entropy 1
- d. Temperature )
1 QUESTION 5.10 (2.00)'
The enthalpy of ti,e reactor coolant entering the steam generator is 650 q Btu /lbm; its enthalpy leaving is 580 Btu /lbm. The enthalpy of'the feedwater-is-400 Btu /lbm. What is the enthalpy of the steam produced if the reactor )
cool an t flow is 6 x 10E7 lbm/hr and the feedwater flow is 6 x 10E6 lbm/hr?'
(SHOW ALL WORK!)
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QUESTION 5.11 (1.00)
Calculate the condensate depression in a condenser operating at i psia wi.th I a condensate temperature of 95 deg F. (SHOW ALL WORK!)
QUESTION 5.12 (1.50)
The plant i s operati ng at 50'. / power wi th con trol rods in manual. How does- !
a HIGH failure of Power Range channel N-44 LOWER detector affect the 1 following indications? (Limit your answer to INCREASE, DECREASE, MORE I NEGATIVE, LESS NEGATIVE, or NO CHANGE.)
- a. Lower Quadrant Power Tilt Ratio (OPTR) (0.5)
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- b. Del ta Flux (Axial Fl ux ) indication (Channel 4) (0.5) 1
- c. Overpower Del ta T trip Setpoint (Channel 4) (0.5) !
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L__IBEDEX_DE_b!1JDLEeB_EDWEE_ELeblI_DEEEGI1Dti._EL1J1DS _6UD PAGE 5
.IHFPMnDYU6d1DS QUESTION- 5.13 (2.00)
State the effect on the Moderator Temperature Coefficient (MTC) of control rod insertion into the core and provide 2 reasons for the occurrence of-this effect. (2.0) i QUESTION 5.14 (3.00)
- a. Explain the linearity or non-linearity of I-135 and Xe-135 concentration with reactor power level. .(1.5)
! b. What is the operator's major cause for concern about Xenon during l reactor operation ? (0.75)
- c. Why will-a power increase cause Xenon (or Samarium) to undergo a short l term decrease in concentration ? (0.75)
I QUESTION 5.15 (3.00) l l The plant is operating at 45% power with all systems in automatic when one l Mai n Steam Isol ati on Val ve shuts. Indicate how the following parameters I
will trend (increase, decrease, steady) after the valve is closed,
- a. Turbine power l
- b. Tavg. (af f ec ted loop) l l c. Tavg. (unaffected loop)
- d. Steam Generator Pressure (affected loop)
- e. Reactor power
- f. Steam Generator pressure (unaf f ec ted l oops)
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.A _EL6UI_ MSIEMS_DESIBL_DDUIEDLo_6ND_INSIEUMEUIeIIDN- PAGE 6 .i QUESTION 6.01 (1.50)
MatchLthe f ol l owi'ng permi ssi ve logic functions in column A (1-7) with-their l respective permissive ~ in column G-(a-e).
COLUMN A COLUMN B
- 1. Automatically blocks the' source range (SR) a. P-10
- trip (10e~xp5 cps). b. P-7 l
- c. P-15 J
- 2. (3-Loop flow permissive) is enabled below 35%. 'd.-P-9 power with 2/4 coincidence in RPS. e. P-8
- 3. 2/4 Power ranges > 50% inserts turbine trip, reactor trip; logic
- 4. (At power permissive) 2/4 PR > 10% or 1/2 TurbLImp.
Press > 10% inserts 5 reactor trips.
- 5. Al l ow manu al block of the power range low set point trip (25% power)
- 6. (ECP Enabled) when 2/4 power ranges are <-10%.
QUESTION 6.02 (1.00)
With regard-to the chemical anc volume control system (CVCS), state _what position (OPEN, CLOSED, AS IS) the f ol l ow i ng' val ves' f ai l ' too on a l oss ' of control signal
- a. Letdown orifice isolation valves ('XCV 12, 13, 14 ) -
- b. RHR letdown control val ve s (XRH 66A/B) ,
- c. Containment isolr+ ion valves )
- d. Letdown temperature divert valve (TCV 143) !
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- e. Low pressure letdown. control valve (?CV 135) l QUESTION 6.03 (1.50)
Explain, with respect to VITAL BUSES, DIE 3EL. GENERATORS (DG), and DG BREAKER (s) CLOSURE, what happens during an ESF loading sequence where:an SI -
is' coincident with a site bl ackou t (mode-III). ;
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so__RLGUI_SYSIEUS_DESIEU._CDWIEDL,_eUD_1MSIEUMENIeIIDN )
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'l L H QUESTION 6.04 (1.50)
List the pressurizer pressure control (PPC) or protective action for'the ,
following PPC and protection setpoints.
- a. 2485 psig 1
l b. 2335 psig c 2260 psig i
- d. 2210 psig '
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- e. 1950 psig l
- f. 1850 psig-l l QUESTION 6.05 (2.00) l l
Indicate whether the following statements'regarding fire protection are TRUE or FALSE.
I Wet Standpipe Systems are manually operated and there are no automatic
, k. l l alarms with these systems. l
- b. If electrical power is lost to the RCB isolation valve an ESF ;
Bypass /Inop. alarms. '
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- c. The RCB fire water isolation valve closes on a phase A isolation, l
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In order to get fire water to the carbon filters inside the RCB, the motor-operated containment isolation valve that supplies the RCB preaction Standpipe System must be opened from CP-002, l
l-l- QUESTION 6.06 (1.50)
- a. Why is the operator required to stop the Low-Head Safety Injection Pumps if RCS pressure should increase -above 300 psig during cold leg recirculation? Be specific as to why this action is necessary. (0.75) l
- 6. During recovery from a small break LOCA, why will accumulator injection result in more rapid recovery of core cooling? (0.75) l l
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L4o__EL6NI_SYSIEMS_DESIEN 4 _EDNIEDL 4 _eUD_INSIEUMENIeIIDU PAGE 8 OUESTION '6.07 (2.50) {
l a.. Conta'inment Spray system design' requirements dictate a minimum and l maximum pH limit during system operation and accident recovery. What are the reasons for these limits? ( 1. 0 ) -
l- 6. .What is the atmosphere above the liquid in the spray. additive tank and L -why is it necessary? (0.5) i
- c. What are two (2) functions accomplished by the spray system to' enhance public health and safety subsequent to an accident? (1.0) l QUESTION' 6.08' (2.50) 'j 1
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- a. List 2 Process and Effluent Radiation Monitors that~aro associated !
with the steam (secondary) plant and state the automati: action j l associated with each monitor. (1.0) '
- b. What are the locations of the operating consoles-for the Radiation l Monitoring System (RMS) RM-11 microcomputers? (0.75)
QUESTION 6.09 (1.00)
- With the pressurizer level control selector switch in the ch 465 position.
l a f ailure causes the f ollowing plant events. (assume no operator actions 1 taken) l l 1. Charging flow reduced to minimum l
- 2. Actual Pressurizer level decreases '
1 1 3. Letdown secured and heaters off l
- 4. Actual level increases until high level trip Which one of the following failures occurred?
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- a. Level channel 465 failed high l b. Level channel 465 failed low l
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- c. Reference pressurizer level stuck in the no load posi t ion
- d. Auctioneered Tave failed Hi due to a failed RTD
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lo__ELeUI_SYSIEBS_DESlDU._fDUIEDL,_sMD_luSIEDUEMIeIIDS PAGE 9 QUESTION 6.10 (1.00)
State the conditions required for AUTOMATIC swapover of the LHSI pumps'to the Recirculation Mode f ol l owi ng an SI.
- QUESTION- 6.11 (1.50)
List'the purpose (protection) for the f ol l owi ng reac tor trips:
- a. Power' range high neutron flux trip (high setpoint)
L b. Power range high neutron flux trip (low setpoint)
- c. Power range high neutron flux positive' rate trip l
- d. Power range high neutron flux negatice rate trip l l e. OT Delta T trip 1
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l QUESTION 6.12 .( 2. 0 0 )
l Indicate whether the f ol l owi ng statemen ts regardi ng the bank overl ap' un i t (BOU) are TRUE or FALSE.
I a, 'The BOU determines which master cycler gets the step up or step down orders from the slave cycler.
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- 6. By selecting which banks receive the signal the BOU can be used to provide the desired overlap for control rod movement.
- c. The BOU receives counts from the slave cycler, and counts'once for l each step of rod movement for both groups in one bank.
l l d. The BOU only functions with the bank selector switch in the automatic or manual positions. When i n d i v i du a'l banks are selected, the BOU is locked out.
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QUESTION 6.13 (2.00) l
! With the reactor at full power, equilibrium conditions, the NI signal to l
the Rod Control System is lost. If the Rod Con trol System is in automatic, L HOW and WHY will it respond to the loss of NI signal? (2.0) l l
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1 QUESTION 6.14 (2.00) l l
i During plant startup, with rod group C approximate 1y'50% withdrawn, power I
'is lost to channel B of the Digital Rod Position Indication (DRPI) system.
- a. What will be the attendant alarm (s) on the main control room annunciators? (0.5) 1
- b. What is the MAXIMUM deviatio, that could exist between two individual rods'in the same group without generating a deviation alarm?. -(0.5)
- c. Administratively, what permits.or prohibits continuation of the startup? (1.0) l l
4 QUESTION 6.15 (1.50)
El ec tr i cal bus E1D11, 125VDC' (channel II) is-de-energized. . What is the impact on the Auxiliary Feedwater system if AFW is. actuated? (1.5) j i
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2-_EROCEDURES_=_NOEdeL,_eEblOEdeL _EMEEGEMC'f_eMD # PAGE. 11- .]
EAD1DLOGICeL_CDMIEOL'
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-QUESTION 7.01 (1.00)
List the immediate operator actions for a loss of ONE (1) source. range q
' nuclear instrument (SRNI), per AOP (1POPO4-NI-0001) SRNI MALFUNCTION, when: '
- a. Reactor power > P-6
- b. Reactor power < P-6 I i
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QUESTION 7.02 -(2.00) l
- a. If the control rods will not move in either mode or direction, what other information must the operator have to determine the supplementary action required? -(1.0)
- b. What immediate and followup steps should the operator take'if the control rods are moving in the automatic mode without a demand signal, and the immediate action has no effect? (1.0) 1 I
l-l QUESTION 7.03 (3.00)
- a. Immediate action in " Reactor Trip or Safety Injection" (EO-E000)-
l requires the operator to verify feedwater isolation. State the valves L that must be checked to confirm proper isolation. (1.0) i
- b. What are the primary and alternate methods of verifying Phase "A" containment i sol a t i on? (1.0)
- c. When the operator is instructed to " Check for faulted S/G", what l
indication is observed?- (0.5) i I
- d. With a val id saf e ty injection, what should the condition of the Reactor 1 Containment Fan coolers be according to EO-E000? (0,5) i 1
QUESTION 7.04 (2.50) -
l a. According to the Steam Generator Tube Rupture procedure (E030), what u are the flow paths of concern when the. operator is instructed to "Stop flow FROM the faulted Steam Generator"? (1.0) l b. List the three distinct methods of post SGTR cool down and indicate the disadvantages of each method. (1.5)
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l QUESTION' 7.05 (2.50)
- l. -a. According to EO-FRS1 (Response to ATWS.or Power Generation), what are j l four (4) viable methods of stopping the Main Turbine, should it fail 1 to trip automatically? (1.0). j l
1 L b. Step 6 of the above procedure requires the operator to verify all i L dilution paths isol ated or secured. What are the two (2) dilution I l paths of concern? (1.0) l
-c. What action is the operator directed to take if immediate boration rate ,
i s sl ow due to high RCS pressure and RCP's are stopped? (0.5) I l
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- QUESTION 7,06 (1'.00) 1 l State the' actions which are required if during a startup, critical l conditions are not achieved prior to reaching the (+500) pcm 1imit?
i l l l QUESTION 7.07 ( .00) l State the reactor coolant pump (RCP) start / restart criteria per AOP l (1 POP 03-EO-ES11 7CP START CRITERIA.
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1 QUESTION 7.08 (2.00) l l
l List ALL the conditions that support or indicate Natural Circulation (NC) l Flow as stated in AOP (1POPO5-EO-ES11) NC VERIFICATION.
QUESTION 7.09 (1.00) l l Calculate what your dose in MREM would be if you were in a-100 MRAD /hr l gamma field for 45 minutes.
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2 _ EEOCEDUEES_=_UDEtael,_eBUDEt.1eL,_Et!EEGEUCY_eUD PAGE 13 EAD1DLOGICAL_CQtdIEOL
'l QUESTI ON 7.10 (2.00)
You have J ust compl e ted a ref uel i ng ou tage . The trip breakers are shut and 1 you are starting up the reactor. The reactor is critical below the IR l neutron flux interlock setpoint (P-6). I&C is currently conducti.ng STPs on l all PRN!s. A report comes'in stating that N-41 is not responding properly. !
i I&C request to place N-41 in the trip condition and continue STPs on all l l remaining PRNIs. Using the attached T.S., decide whether or not I&C.should j
- continue the surveillance test as requested. (FULLY SUPPORT YOUR ANSWER!) j I
QUESTION 7.11 (2.50) l l State.the ADMINISTRATIVE personnel exposure limits for the following:
- a. Personnel at STPEGS
- b. Expectant mothers
- c. Skin and extremity I j
- d. Pl anned emergency doses 1
QUESTION 7.12 (1.00) l State the importance for closely monitoring AFW storage tank levels per SOP (1POPO2-AF-0001) GENERAL PRECAUTIONS AND LIMITATIONS. i 1
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- .PAGE 14 EAD10 LOGICAL _CDUIEOL I
QUESTION 7.13 (3.00)
'Given each of the events described below .along with Table D-1, Emergency ,
Action Levels, classify each event separately to the correct EAL. Note j that some events may not fall into any EAL. State any assumptions used in '
making a classification,
- a. While operating at 100% power, steady state, a bomb threat is received stating that an explosive device has been placed in the con trol room. j Upon conducting a search of the control room, what appears to be such a device is discovered. Examination of the device indicates that it
.may be triggered by radio control or movement. (0.75)
- b. While moving fuel in the core, during refueling outage, all offsite ,
power is lost due to line damage from high winds. Investigation i l reveals that offsite power will be restored in 20~24 hours. Onsite l power systems operate according to design, with adequate fuel oil for
! at least 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> of operation. (0.75)
- c. While operating at 100% power, steady state, a double ended rupture of one RCS cold leg occurs. (0.75) l d. While operating at 100% power, steady state, a main steam line break l occurs downstream of containment but upstream of the main steam l
isolation valve. Subsequently, calculated steam generator tube i leakage increases from 0.2 gpm at steady state to 40 gpm with no indication of secondary activity in the intact loop. . (0.75) l l
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1 B.__eDMINISIRGI1UE_ERDCEDURESo_CDUD1I1DNS _eUD_LIU1IeIIDUS 15 I 4 .PAGE QUESTION'-8.01 (2.50) j
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- Explain why the SRO SHOULD or SHOULD NOT allow the following evolutions to occur. Assume the unit is at full power and state ALL considerations.
- a. A craftsman wants to check the fit of a newly designed gagging device I for a Pressurizer Code Safety. The test will take about 45 minutes to complete. (0.5)
- b. A modification must be made to a PORV block valve operator and will y take about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to complete.- (1.0)-
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- c. A Technician needs 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to repair 1 of the 3 required RCS l eakage detection systems. (1.0) J
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l GUESTION' 8.02 (3.00)
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I a. What are 3 types of activit'ies that are considered to be preventative maintenance? (O'.75)
- b. Is a Maintenance Work Request (MWR) normal l y required to perform preventative maintenance? (0.4)
- c. Who is responsible for providing work instructions in em~ergency situations? (0.6)
- d. What are 3 additional PERMITS that may be required-to properly process l an MWR? (0.75) 1' l e. What is the administrative tool for providing safe system al ignment i for maintenance? (0,5) l L QUESTION 8.03 (2.50)
- a. What are the 3 separate groups that make up the Station Emergency Response Organization? (0.75)
- b. What 3 conditions must be satisfied to formally transfer the responsibility of the Emergency Director? (0.75)
- c. Briefly describe how on site personnel are accounted for during an emergency. (1.0)-
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8.__eDU1U1SIEeI1UE_EROCEDURES+_COND1IlONSo_eUD_LidllellOUS PAGE 16:
QUESTION 8.04 (2.50)
- a. While serving as Emergency Director, what are four (4)'
responsibilities that can NOT be delegated? (1.0)
- 6. Where ar e .the f ol l owi ng individuals located after augmentation during l
an ALERT:
-1 . Emergency Director?
l l 2. Shift Supervisor?
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- 3. Plant Operations Manager? '(0.75)
- c. With the Initial Response Organization in place, who are the three (3) j managers or-directors that report directly to the Emergency Director?
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l QUESTION 8.05 (2.50)
- a. How are Jumpers and Temporary' Devices recogn'izable whenEinstalled to perform their temporary function? (1.0)
- 6. Who is responsible for verifying-that a temporary device or jumper has been removed? (0.5)
- c. Who is responsible for ensuring that a system has been returned to normal after removal of a temporary cevice AND what are'two (2) methods that may be used to perform this verification?
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'I B _eDtd1NISTEGI1!JE_EEDCEDjJEESo_EDUD1IIDNS _eUD_ Lit 11IGIIDUS .PAGE 17 1 1
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' QUESTION 8.06 (3.00) I
- a. Who (by title) has cognizance for.the equipment covered by Equipment Clearance-Books (1.0) 1 (1) #3 (2) M4
- 6. Is it required for'the " Verifier" to accompany the " Operator" in performing alignment activities for a clearance? Explain why or why not. (0.5)
- c. When rev i ewi ng an . Equ i pmen t ' Cl earance Order f or au thor i zat i on , the i Shift Supervisor (issuing authority) is required to consider the' list of " Good practices for clearances". _ In your own words, give.three (3) of the " good practices" found on this list. (1.0) l l
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l QUESTION 8.07 (2.00) j 1
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- a. Why do the Technical Specifications require the reactor to be shutdown j and cool ed down when RCS ac t iv i ty limits are exceeded for-an extended j l
period of time? (1.0). l l
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- b. Why do the Technical Specifications contain transient limits for-RCS chemistry that are less restrictive than steady state limits?' (1.0) l l
l QUESTION 8.08 (1.50) l a. The shift supervisor is the " issuing authority" for clearances affecting the plant. What duties and/or responsibilities, pertaining to clearances, may the issuing authority delegate.to an alternate.
OPERATOR? (1.0) l
- b. How should the shift supervisor assure himself that a clearance requestor is qualified to process a clearance if the shift supervisor has doubts? (0,5) i QUESTION 8.09 (1.50)
What are three generic principles, found.in the definition of ALARA, which .
i form the programmatic basis for determining whether.or not to implement !
I actions to reduce radiation exposure? (1.5) l I
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QUESTION 8.10 (2.00)
I
- a. For. purposes of clearance processing, what constitutes a high pressure l system which requires ext 9 protection? (1.0) I l
l b.- When preparing a clearance for a high pressure system, what~ extra l measure (s) is(are) taken to protect personnel working on that system?
l (0.5) 1 l
- c. When verifying that a high pressure system i s properly i sol ated and is !
safe to commence work, what one check provides the most positive j l assurance that the. system is' safe to open? (0,5) l l
l :
I QUESTION 8.11 (2.00)
For each item below indicate YES or'NO as to whether the Technical l 1 Specification Limiting Condition for Operation (LCO) is satisfied concerning DC power sources: (Tech Specs are provided) (2.0) e a. The total battery vol tage for the battery supplying bus E1811'is 125 l VDC on float charge while in mode 3.
l
- b. The battery charger servicing bus E1D11 has a faulty output breaker while in mode 5.
- c. No surveillance has been performed on the battery on bus E1A11 for ten days while in mode 4.
- d. One of the two battery chargers servicing bus E1C11 is temporarily removed from service for maintenance while in mode 1.
1 1
1 l
l l
L
(***** END OF CATEGORY 08 *****)
(************* END OF EXAMINATION ***************) =
l l : Si_,_IHFnav DE, uuCLEeE_EgyER_ELeNI_DEEEeIIDtbEL1J1DS4_eND PAGE 19 IHFRMnDYNAMICS
' ANSWERS'-- SOUTH TEXAS l' -87/05/12-MCCRORY, S.
l l
l l
ANSWER 5.01 (3.00)
As dilution occurs, Con tr ol rods move 'in, [0.23 power in upper core goes down, [0.23 power in lower core goes up. [0.23 UPPER CORE: Initially,.1ower power reduces burnout,. causing Xenon to increase, causing further power reduction, [0.63 Later'Xe will L decrease as decay.from iodine decreases. [0.33 This allows power to increase reducing Xe due to increased burnout. [0.33 I
LOWER CORE: Initially, power increase'causes increased Xe burnup, causing power to increase further. [0.63 Later as iodine concentration increases, increased Xe-forces power down,.
i causing more Xe buildup. [0.33 Xe will decrease after iodine I
inventory starts to decay and cycle will repeat. [0.33 (3.0) i CONCEPT l
l REFERENCE l STP QUESTION BANK, P. 91 l
1 ANSWER 5.02 ( .50) c (0.5) l REFERENCE 4 l SOTX lesson plan HT & THERMO, sec III, part B, ch 1, p 522, 323 !
l 191004K114 ...(KA'S) l l
l l
l ANSWER 5.03 (1.00) l l 1. reactor power 5. CEA w/i +- 12 steps of group
- 2. coolant flow rate 6. CEA insertion ilmits
- 3. RCS average temperature (Tave) 7. Bank overlap 4 RCS pressure. 8. Axial flux difference (any 4 at 0.25 ea).
1 l-REFERENCE SOTX lesson plan HT & THERMO see II, part B, ch 3, p 205-207.
193008K105 ...(KA'S)
L__IBEDEY_DE_UUCLEeE_EDWEE_ELeNI_DEEEeIIDN# _ELUIDS,_GUD PAGE 20 IMFPMnhyMGMICS ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
ANSWER 5.04 (1.00)
- 1. Density difference (or DELTA T)' created by heat addition by' the heat .j source and heat removal by the heat sink. (0.5)
- 2. The heat sink must be elevated physically above the heat source.- (0.5)
REFERENCE SOTX lesson plan HT & THERMO sec III, part B, ch 3, p 355.
193008K191 ...(KA'S) l ANSWER 5.05 (1.00) 1 i
'(2 of 5 REQUIRED, however answer #3 not valid i f 'used wi th answer #4 or #5) l- 1. It is well above the source range. (0.5) l l 2. Source neutrons are negligible. (0.5) l'
- 3. It is below the point of adding heat. (0.5) l
- 4. Doppler eff ects are not present (0.5)
( 5. MTC effects are not present (0,5)
REFERENCE l SOTX lesson plan, RXTH, RX CORE CONTROL FOR LARGE PWRs Io obj 2.
I 192008K112 ...(KA'S) l l
l ANSWER 5.06 (1.00) y a. Lower (0,5) l l l b. Higher (0.5)
REFERENCE SOTX lesson plan, HT & THERMO, sec III, part B, ch 1, pL320.
1 191004K104 ...(KA'S) l l
l l
l
L_IBEDEY DE UDLLEaE EDUEE EL6NT DEEEATlDth ELUIDSo bMD -PAGE 21 IBEEMDDYNAMICS ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
' ANSWER 5.07 (1.50)
- a. Increase (0.5)
- b. De'c r e a s e . -(0,5)
L c. .I nc,* e ase (0.5)
REFERENCE SOTX lesson plan, HT & THERMO, sec III, part B, ch 1, p 320 191004K115 ...(KA'S) l ANSWER 5.08 (1.50) l t A. true (0.5)
- 8. true (0.5)
C. true (0,5)
REFERENCE l 'SOTX lesson plan, RXTH, RX CORE CONTROL FOR LARGE PWRs. p 6,.in obj 4.
l 192002K114 192005K109 ...(KA'S) l ANSWER 5.09 (2.00)
I
- a. REMAIN THE SAME (0.5) l b. DECREASE (0,5) l c. INCREASE (0.5)
L d. DECREASE (0.5) l l ' REFERENCE SOTX lesson plan, HT & THERMO, ch 2.5, p 83, steam tables.
l 193004K115 ...(KA'S) i 1
. 'l 1
l 1
E , 3 1 y
% .1i ,6
- j l
i yL _IHEORY DE_NDff.EGR_EDWER_ELaNI_DEERGIIDth_ELDIDS 4_oND } -
' PAGE 22-
- IHFct ODXNAMI CE,' *~
- s. A ANSb3ERS -- SOUTH TEXAS 1 -8 h/05 /12-MdCRORY , Se 1
A o
ANSWER 5.10 (2.00) i 4
'm1(hout,1 - hin,1) = -m2(hout,2 - hin,2) (
.0.5) f .:
mi = reactor cool an t mass f l ow rate m2 = feedwater mass flow rate
-ml/m2'(hout,1 - hin,1)
(hout,2 - hin,2) =
s hout,2 = -m1/m2 (hout,1 -hin,1) + hin,2 (0.5) hout,2 = -(6 x 10exp 7 lbm/hr) / (6 x 10exp 6 lbm/hr) x .
j (580. Btu /lbm - 650 Btu /lbm) + 400 Btu /lbm ( 0 . 5)' '
hout,2 = [(-10) x (-70 Btu /lbm>3 + 400 Btu /lbm ,
a hout,2 = 700 Btu /lbm + ~400 Btu /16m '
i hout,2 = 1,100 Btu /lbm (0.5) )
.J Thus, the-enthalpy of the steam produced is 1,100 Btu /lbm. ~!
ii
)
REFERENCE SOTX lesson plan, HT & THERMO sect I I', part A, ch 2, p 70, steam tables.2. ,
193003K119 193003K124 ...(KA'S)
ANSWER 5.11 (1.00) i From the steam tables, 1 psia corresponds to a saturation temperature of .
101.74 deg F. (0.5) 4.
The difference between the saturation temperature and the condensate .
temperature is the condensate depression, thus: '
101.74.deg F - 95 deg F = 6.74 deg F (0.5) f. '
.. t REFERENCE . ,
SOTX lesson plan, HT & THERMO, sect II, part B, ch~2, p 183 7 steam f'abims. ,
. c:
193004K111 193008K115 ...(KA'S) ,
i.
s e ,
5 i P
1 e J'
t t
- y
-.-._-~N-
- L__IkiEDRY_DE. fillDLEGR_EDWER_ELANI_DEEEeI1DNo_EL1J1DS,_GND PAGE 23
.IHFRMnDYNad1CS i
ANSWERS -- SOUTH TEXAS 1 '
-87/05/12-MCCRORY, S.
. ANSWER 5.12- ( 1. 50 )'
1
- a. INCREASE I
- b. MORE NEGATIVE j i
- c. 'NO CHANGE (0.5 ea.) '(1.5) i REFERENCE STP Rx Theory, Ch. 13,, Pp. 13,15 & SD RPS, P.8 ANSWER' .5.13 (2.00)
Coefficient becomes more negative-[0.5) due. to changes in coolant density affecting neutron migration length and causing more neutrons to be absorbed
'by rods.[0.753 Also changes surface / volume ratio and effectively increases j leakage directly affecting MTC. [0.751 i REFERENCE STP Theory, Ch. 8, P. 10 ,
ANSWER 5.14 (3.00)
- a. 1. 1-135 var i es l inearl y wi th power level [0.53'as subject to removal only by radioactive decay. [0.251- ;
-1
- 2. Xe-135 does not vary linearly [0.253 as it is subject to removal by decay [0,253 and burnout. [0.25]
- b. Xenon instability can result in hie' local hcet generation and possible 'I fuel: failure. (0.75)-
- c. Increasing power can cause increased burnout prior to bui1 ding to-a new equilibrium lavel. (0.75)
REFERENCE STP Rx. Theory, Ch. 9,-.PP.6-8 l L
L i
l L
L _- -- _ ___
1%_IBEDRY_DE_UJJDLEAR pnbJFR ELeNI_DEEEGIIDik_ELUIDS,_eh!D PAGE 24
- INFPMnDYUetHES ANSWERS--- SOUTH TEXAS 1 -87/05/12-MCCRORY, S. 1 l
I 1 l
.j ANSWER 5.15 (3.00) 1
- a. Steady j b, Steady I
- c. Decrease .
0
- d. Increase 1
! e. Steady (' or increase if S/G relief assumed open)
- f. Decrease (0.5 ea.) (3.0)-
REFERENCE STP QUESTION BANK, P.98 l
l 1
I l l l l l
f i
i x_ _-___.______.___.__m._. _ _ _ . _ _
7 l
L __ELeNI_SXSIEdS_DESIBN# _fDNIEDL,_eND_INSIElJdENIellDN PAGE 25 ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
.1 ANSWER: 6.01 (1.50) j
- 1. a. (0.25)
- 2. e' (0.25) , j
- 3. d (0.25) '
- 4. b (0.25) '
- 5. a (0.25)
E6. .c (0.25) l REFERENCE SOTX lesson plan, BR 4, EX CORE NI, p 11.
015000K407 ...(KA'S) 1
. ANSWER 6.02 (1.00) 1
- a. as is OR fail-close-(0.2) I
- b. as is (0,2)
- c. as is (0.2)
- d. divert flow to VCT (0.2) l-
- e. open (0.2) l REFERENCE l SOTX lesson plan, BK 5, CVCS, p 10-13, i n ob.i 3.
1 004000A203 ...(KA'S) 1 l
l ANSWER 6.03 (1.50) 1 1 1. All equipment operation on vital buses is terminated-on loss of power '
l by the load shed signal. (0.5) l l 2. Diesel generators start and connect.to the vital buses within 10 ~
seconds subsequently vital' power restored. (0,5) l
SOTX lesson plan, Bk 5, ESF system, p 22, in obJ 10.
013000K407 .064000K411 ...(KA'S)
I l
l
_______________.___.__2._ _ _ _ _ _ . _ _ _ _
L__ELeUI_SYSIEMS_DESISL_EDUIEDL AND_INSIB1)LiENIGIIDN PAGE- 26 ANSWERS:-- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
ANSWER 6.04 (1.50)
- a. Safety' valves lift ,
- b. PORVs open
- c. Spray. initiated
- d. Backup heaters.on
- e. SI' block / unblock
- f. Low pressure safety injection actuation (0.25 ea)
REFERENCE SOTX lesson plan, BK 4, PZR PRESS & LEVEL CONT, p 17, 18, In'ob5 6.
! 011000K103 ...(KA'S) 1 l
l ANSWER 6.05 (2.00)
I a. FALSE -(0.5)
I
- b. TRUE (0.5) l c. TRUE (0,5)
- d. TRUE (0.5)
REFERENCE SOTX lesson plan, BK 1, FPS, p 17, iniobjs 3.G, 14.G,.24.
086000A302 ...(KA'S) l' l
1 .
(l ANSWER 6.06 (1.50)
~
a.' The RWST level signal that auto ini t ia res col d l egf re circulation al so L
cl oses LHSI pump mi n i-fl ow rec i rc . val ves to RWST. .CO.53 Continued-operation of the pumps will result in damage.f0.253 (0.75)
- b. Accumulator injection causes increased'RCS depressurization and results.
In_ increased ECCS pump injection 1 rates. OR; Injects a l arge .vol ume of water when LHSI is not available. '(0.75) l L.
A PLeNI_SYSIEMA DESISS_DDtiTEDL_eND_INSIE1Jt!ENIeIIDN. PAGE 27 ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
ANSWER 6.07 (2.50)
- a. Minimumt. Maintain Iodine in solution. (0.5)
Maximum: Prevent caust i c 'at tack on RCS ~ and Sump me tal s. (0.5)
- 6. (~ Spsig) N2 [0.253 to prevent NaOH degradation.-[0.253 (0.5) i c. . Reduces containment pressure to reduce leakage and minimize leakage to offsite. (0,5) l l Entraps fission products i n sol u t i on and preven ts the i r1 escape to the atmosphere. (0.5)
REFERENCE SD, CS, Pp. 1,2,3 l ANSWER 6.08. (2.50)
- a. 1. Turbine bldg. sump and drain system. [0.253 High rad.. level stops
( the sump. [0.253
- 2. Condensate polishing system. [0.253 High rad. stops flow to the natural i zation basin. [0.253
- 3. S/G bl owdown . [0.253 High rad, stops flow to naturalization basin. [0.253
- 4. Cond, air removal sys. IO.253 No automatic action. [0.253
[Any 2, 0.5 ea.] (1.0) 1 l b. HP Office, TSC, MCR. [0.25 ea.) Accept computer rm., no credit (0.75).
l l Lc. 1. Grid display 1 2. Trend display
- 3. Group display [0.25 ea.3 (0.75)
REFERENCE l
A _ ELeNI_SYSIEMA D E S.lStL_EDNIRDLo_eND_INSIBijtdENIGIIDM PAGE 28 ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
' ANSWER 6.09 (1.00) a REFERENCE SOTX~ lesson plan, BK 4, PZR PRESS AND'LVL CONT, p 26.
011000A210 ..,(KA's)
ANSWER 6 10 (1.00)
Receipt of RWST Low-Low level alarm (0.5) coincident with an SI signal (0.5)
REFERENCE SOTX lesson plan, BK 5, ECCS p 2, in obj 14.
005000K411 ...(KA's)
ANSWER 6.11 (1.50)
'b. Protects against reactivity excursions (which are too rapid to be.
protected by temp & press protective circuitry) '(0.3)
- c. Protect against rod ejection accident (0.3)
- d. Protect against multiple rod drop (0.3)
- e. Protect from DNB (0.3)
REFERENCE SOTX. lesson plan, Bk 6, SSPS p 6, I n ob) 2.
012000G004 ...(KA's)
ANSWER 6.12 (2.00)
- a. FALSE (0.5)
- 6. TRUE (0,5)
- c. FALSE (0,5)
- d. TRUE (0,5)
L 1
i L __ELeNI_SYSIEMS_DESISS _CONIBDLo_eND_INSIB1)MEliTeI1 Dbl PAGE 29 1
' ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
- REFERENCE SOTX lesson plan, BK 6, ROD CONT P 29, in obJ 11,,12,13.
l 1
001000K403 ...(KA'S)
I 1
1
\
ANSWER 6.13 (2.00) l The'RCS will attempt to move rods out.-(0.75) This is'because the loss of l NI signal 1is seen as an instantaneous large change in power with a'large'
- l. power mismatch. (0.5) The rate.of power change signal wi l l r ap i dl y . dec ay, 1 l to zero since the signal represented a. step change. (0.25) When the rate l signal goes away the RCS ignores the~ constant power mismatch and will be l driven by any Tref - Tave mismatch that may have developed'as a result of ,
I rod motion. (0.5) 1 l REFERENCE STP LP.DM.01, & WESTINGHOUSE COURSE TRAINING MATERIALS K/A 001-000-K1.05 1.R. 4.4 001000K105 ...(KA'S) ,
l !
l l
ANSWER 6.14 (2.00) l l a. Non-Urgent f ailure alarm (DPRI trouble) (0.5) j
- b. 14 steps (+10, -4 for channel A> accuracy (0,5) H
- c. T.S. permit operation to continue since t h e' l'imit.is +,- 12 steps (0.5) and the reduced accuracy with only one channel is within this limit (0.5).
REFERENCE STP O.LIC.HO.RPI.01, O.LIC.LP.DM.01, 1 POP 03-ZG-000'4 ,'T.S. 3.1.3.2 I o K/A 014-000-K4.06 I.R. 3.7 j
- l. 014000K406 ...(KA'S) l l
o i
l l' ANSWER 6.15 (1.50)
Aux. feed will be blocked to S/G D (FV 7526 & AF 0019) (0.75). Steam will l'
l be blocked to the turbine dirven aux feed pump'(MS 0143 & MS 0514) (0.75).
REFERENCE l STP O'.LIC.HO.AFW.01, P&ID 9-F-00024, ELEC SLD 9-E-DJAB-01 y
l K/A 061-000-A2.03 1.R. 3.4 l 061000A203 ...(KA'S) o
. . . - . ---___u-----_.-_- w
l 1 2u_EEDCEDLIEFA - NDRMAI >_eBNDRMAt.', FMFRGENCY_eND PAGE' 30 B6D1DLDBlDAL_DDLLCBDL ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
1
-)
ANSWER. 7.01 (1.00) l l
'a. No immediate operator actions are required'(0.5) ]
- b. Suspend all operat i ons .invol v ing core al terat i ons or nosi t ive reactivity changes. (Refer to T.S.- 3.9.2~and 3.3.1.) (0.5)
NOTE: Credit 0.15'pt forl"If reactor trips refer to'EOP" if it substituted for the. answer in parts a or b, l 1
REFERENCE SOTX AOP, (1POPO4-NI-0001) l'
, 015000A201 ...(KA'S) 'l i
)
)
ANSWER 7.02 (2.00)
- a. Whether the failure is in the control system (0.53 or due to friction
/ mechanical interference. [0.53 -( 1. 0 )
1
- b. Go to manual, [0.53 and trip reactor if motion continues. [0.53- - ( 1. 0 ) .
REFERENCE 1 POPO 4-RS- 0 0 02, Pp.1,2 ANSWER 7.03 (3.00)
- a. o Fl ow con trol valves I o Fl ow con trol valve bypass valves ;
o FW isolation valves !
o FW isolation 8/P valves _;
o S/G blowdown i sol a t i on '
o Sample isolation (0.167.ea.3 :( 1. 0 ) .
-b. Primary: ERFDADS (ESF status monitor l i gh t s)' l Alternate: MCB Indication [0.5 ea.] '(1.0) c.- S/G pressure ( 0.53 -
- d. Running, cooled by CCW. '(0.5)
_m-~_____ _ . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _ _ _ . . _ _ _ _ . _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _
-7 EEDCEDUEES - NDEdel,_aBUQEdeL, FMEEGENCY_6UD PAGE 31 EaD10 LOGICAL _CQUIEOL ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
REFERENCE 1 POP 05-EO-E000, Pp,9,11,23 I
-ANSWER 7.04 (2.50)
- a. PORV, .MSIV and bypass, Steam supply to AFW Pump, and Blowdown Isol at ion Val ves. [0.25 ea.] (1.0)
- 6. 1. Steam Dump, [0.253 Possible release of. radioactive.ty.'[0.253
'h
- 3. Blowdown. [0.253 Process and storage of rad'ioactive waste.-
OR Contamination.of secondary systems. [0.25] (1.5)
REFERENCE STP QUESTION BANK & E030, Pp.2,3
)
ANSWER 7.05 (2.50)
- a. 1. Manu al l y trip from MCP
- 2. Stop.EH control pumps
- 3. Trip from front standard
- 4. Shut MSIV's [0.25 ea.] -(1.0)
- b. 1. Letdown demineralizers
- 2. Reactor makeup water (pumps) [0.5 ea.] (1.0)
- c. .Open pzr PORV's ( O '. 5)
REFERENCE 1 POP 05-EO-FRS1, Pp4,6,9
' ANSWER 7.06 (1.00)
Insert rods to;the (-500) pcm limit (0.5) and notify the shift supervisor. ,
(0.5)
REFERENCE SOTX lesson plan, RXTH, S/D REACTIVITY CONSIDERATIONS P 6, LN OBJ 7.
192008K103 ...(MA'S)
L _ _ E E D E E DjJ R F A - UDRMAl>_eBNDEMeL4 _EMEEGENCY_eND PAGE 32 EbDlDLDGlEAL_EDUIEDL
' ANSWERS -- SOUTH TEXAS 1 --87/05/12-MCCRORY, S. )
i J
ANSWER 7.07 ( .00) l QUESTION ~ DELETED FROM EXAMINATION DURING THE GRADING OF THE EXAMINATION I REFERENCE i SOTX EOP, BK 3A, (1 POP 05-EO-ES11), RCP START CRIT, P. 1.
003000K614 ...(KA'S) ]
ANSWER. 7.09 (2.00)
- 1. RCS Subcooling - >.31F (0.5)
- 2. Core. Exit temperatures stable or decreasing (0.5)
- 3. S/G Pressures stable or decreasing (0,5)
- 4. RCS (loop) Hot Leg Temperatures are' stable or decreasing. (0.25)
RCS (l oop) Cold Leg Temperatures are near saturation temperature for S/G Pressure. (0.25)
REFERENCE SOTX EOP, Bk 3A, (1 POP 05-EO-ES11), NC, P 1.
193008K122 ...(KA'S) {
l l
ANSWER 7.09 (1.00) ,
100 MRAD /hr = 100 MREM /hr 40F = 1 for gamma) l 100 MREM /hr (0.75 hrs) = 75 MREM l
REFERENCE 10CFR20 l 194001K103 ...(KA'S) )
I i
)
1 I
l .j l
l' _ _ _ _ - _ _ __ --
'24.._EEDCEDURES - UDEdeL _6BUDBdeL _EMEEEEUCY_GUD 4 PAGE 33 BADIDLDSIEci rnNTnot ANSWERS - . SOUTH TEXAS'1 -87/05/12-MCCRORY, S.
ANSWER 7.10 (2.00)
LCO 3.3-1 table 3.3-1 action 2 allows the continuance of the surveillance test prov i ded the mi n imum channel s operabl e requirement is met. (1.0) The inoperable channel must be bypassed for surveillance ~ testing of the.other channels to preclude opening of the reactor-trip-breakers. (1.0)
REFERENCE
'SOTX1T.S., LCO 3.3-1, TABLE-3.3-1, ACTION 6,.P'3/4 3-7.
015000K301 ...(KA'S) l l
ANSWER 7.11 (2.50)
, a. 1000 mrem /qtr (0.6) l b.'100 mrem /qtr (0.6)
- c. 6 Rem /qtr (skin) (0.30)-
15 Rem /qtr (extremities) (0.30) g i
- d. 25 Rem whol e body for emergency operations. (0.35) 75 Rem whole body for life saving operations. (0.35)
( REFERENCE #
l SOTX ADMIN PROC, (OPGP03-ZR-0026).
194001K103 ...(KA'S) l l
l ANSWER 7.12 (1.00) a AFW pumps have no loss of suction tr i p p rot e c t i on on AFWST l ow l ev e l .
1 REFERENCE l
SOTX SOP, (1 POP 02-AF-0001), p 2.
061000A104 061000G010 ...(KA'S)
]
l l
l o
I l
l l
l l l
l
- Z.__EBOCEDUEES - NDEMel._eBNGEdeLo_EMEEGENC'f_eND PAGE' 34 red 10LOGICeL_CONIEOL ANSWERS.- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
.t
. ANSWER. 7.13 (3.00) i
.I
- a. Alert (CR evacuation must be anticipated) (0.75): 1 I
- b. NOUE (Loss.of offsite pwr w/no loss of diesels) (0.75) J
-l
- d. AlertL(Primary / Secondary leakage >10-gpm (50 gpm w/ steam line break)
(0.75)
REFERENCE STP-EMERGENCY PLAN TABLE D-1.
194001A116- ...(KA's) l i
Bo__eDt!1 bust R ATIVE_EEDEED1JEES+_CDUD1IIDUS,_eUD_ Lit!1IGIIDUS PAGE 35 ANSWERS'-- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
ANSWER 8.01 (2.50)
- a. Should not allow [0.253 as ac t i on must be taken to reduce power if Safety is inoperable for 15 minutes. [0.253 (0.5)
- 6. May be al l owed C0.53 if block valve can be shut. [0.253 PORV ' may be out of service for more than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. (72 Hrs.') [0.253 (1.0)
- c. May continue to operate (for 1 month) [0.53 if daily containment. grab samples are taken. [0.53 (1.0).
REFERENCE STP TS, Pp. 3/4 4-9, 11, 14 ANSWER 8.02 (3.00)
- a. Lubrication, calibration, routine maintenance, inspection.
surveillance IAny 3, 0.25 ea.] (0.75)
- b. NO. (0.4)
- c. Shift Supervisor (0.6)
- d. Confined space entry permit, Equipment clearance, Fl ame permi t , RWP Fire hazard permit, security clearance, charcoal filter clearance (any three at 0.25 ea) (0.75)-
- e. Equipment Clearance (0.5)
REFERENCE STP QUESTION BANK
l
-fL__eDdlulSIReIIVE_EEDCED1)RES._EDND1IIDNS 4 _eND ITMIIGI1DNS .PAGE 36-ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
ANSWER- 8.03 (2.50)
- a. 1. Onshift response organization l
- 2. , Emergency response orgainzation l 3., Initial response organization (optional) (0.75) ,
OR ;
- 1. TSC l
- 2. OSC
- 3. EOC
- b. 1. Brief successor L
2.- Notify offsite response' organizations _
j 1 3. Document the turnover (sign emerg. dir checklist) [0.25 ea.] (0.75) 1 l
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- c. Personnel are required to report to an assembly area where a coordinator accounts.for all personnel and reports to the Security- 4 Manager. (1.0) l REFERENCE STP EP SECT. C, Pp. 2,3 SECT F, P.2 ANSWER 8.04 (2.50) i
- a. 1. Decisions concerning offsite notification.
- 2. {
Approval for dissemination of information for-public release. !
- 3. Approval for exceeding 10CFR 20 exposure limits, i
- 4. Approval for entry into evacuated areas. '
- 5. Approval for offsite protective action recommendations. l
[Any 4, 0.25 ea.] (1.0)-
- b. 1. Emergency Director------------------------ EOC
- 2. Shift Supervisor-------------------------- MCR
- 3. Plant Operations Manager------------------ MCR [0.25 ea.] (0.75)-
- c. 1. TSC Manager
- 2. Plant Operations Manager
- 3. General Services Director
- 4. Rad i ol ogi c al Director (Any 3, 0.25 ea.] (0.75)
REFERENCE STP EP, P.C-9 & FIG. C.3 1
L__aDMINISIEaIlVE_EEDDED1JEEL_DDb!DlIIDbL%_aND_LidlIeIlONS PAGE '37 ANSWERS.-- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
ANSWER 8.05 (2.50) ,
- a. Electrical or mechanical Jumpers are'clearlyu tagged,.1abeled or
' identified (brightly colored tags mar be used). -(1.0) b.. The Shift-Supervisor or. designated verifier. (0.5). y
- c. The Shift Supervisor verifles [0.53 and he . may ver i f y by v i sual
. inspection IO.25] or functional check ~. [0.253 l
(1.0)
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REFERENCE:
I OPGP03-ZO-0003, Pp.3,7 j l
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.So__eDUINISIEeI1UE_EEDCEDUEES 4 _CDNDlIIDNS,_eND_LIMIIeIIDNS PAGE 38 ANSWERS --1 SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
ANSWER 8.06 (3.00)
- a. Clearance Book No. 3 is for clearances on equipment under the l cognizance of the Chemistry Operat i ons and Anal ysi s Super i n tenden t , j I
[0.53 Book No. 4 is for equipment under control of the Maintenance l
Superintendent. [0.53 (1.0)
OR ;
The original books 3 ano 4 no_ longer exist. Book 3 is.for equipment ]
and systems under tahe cognizance of the Facility Services Manager. 1 3
l b. No. [0.253 Verification - is intended to be a separate,. Independent, and l
redundant. activity. [0.253 (0.5) I
- c. 1. Vent and/or drain piping runs which' are to be i sol ated by the I clearance.
- 2. Di sabl e pr ime movers (motors, turbines, etc.) prior to isolating l pumps.
- 3. When required to remove trip circuit fuses, first remove closing circuit fuses and rack out the breaker.
)
- 4. Use the two man rule in the switchyard i i
- 5. Tag all active operating mechanisms (valve operators, MOV breakers, )
etc.). I i
l l 6. When restoring fluid systems, avoid any. condition that may cause l water h anme r .
1 [Any 3, 0.5 ea.3 (1.5) l Accept any good engineering practice concept since this list has been
} deleted from the procedure. Administrative matters are'not considered engineering practices.
REFERENCE j OPG3-ZO-1, Pp. 3,8,18 ;
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l ANSWER 8.07 (2.00)
- a. Based on not exceeding 10CFR20 exposure limits [0.53 at.the site boundary following an'STGR. [0.53 (1.0) l l
- b. Corrosion is time dependent. (0.5) Higher l imi tes all ow t ime f or restoring steady state limits. (0.5) (1.0).
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Bo ADtd1MISIReIluE_EROCEDURES COND1IlOMS,_.eMD_.Litd11ellOWS PAGE 39 ANSWERS , -- SOUTH TEXAS 'l -87/05/12-MCCRORY, S.
REFERENCE STP QUESTION BANK, Pp.80.81 ANSWER' 8.08 (1.50) a.- The ss may delegate the paperwork part of a clearance (filing out the tags;and forms and reviewing P& ids). (1.0) 6.- The ss should review the current' listing.of.. station personnel who have-
,been trained'in clearance procedures. (0.5)
REFERENCE STP-OPGP05-20-0001_pgs 5 & 6 K/A 194001-K1.02 I.R. 4.0 194001K102 ...(KA'S) l' 1
- ANSWER 8.09 (1.50) l 1
(ANY 3 AT 0.5 EA) 1.. Current technology - existance of mater i al s and knowl edge to make the desired action possible l
- j. 2.
i Economics - cost or affordability -)
! 3. Social f ac tors - soc i al acceptability of con templ ated : ac t i on , l egal-
! liabilities l 4. Expected benefit - exposure reduction per unit expenditure,.
l significant reduction of health risk l:
1 (Verbatim response not required, concepts only)
L REFERENCE
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STP OPGP03-2R-0002, pg 3 1
.K/A 194001-K1.04, I.R. 3.7 I I 194001K104 ...(KA'S)
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Bo__eDMINISIEGI1UE_EEDEEDURES 4 _CDND1IIDNS 4 _eUD_LIU1IGIIDNS- PAGE 40 ANSWERS -- SOUTH TEXAS 1 -87/05/12-MCCRORY, S.
4 ANSWER 8.10 (2.00)
- a. A system which operates at >150 psig (0.4), >200 deg.F (0.4) and which has a maximum potential opening > 1/2 inch (0.2).
- b. .. > o u b l e valve protection (where possible) -(0.5)
- c. Observe pressure reading (0.36): on a local '(0.07)1 pressure instrument l l whose scale accuracy is sufficient to assure that a zero gauage l readingLis at'or near atmospheric pressure (0.07). ,
l OR Observe no. drainage through'an open vent path. (0.5)
REFERENCE !
a.&b. STP OPGP03-ZO-0001 pg. 7
- c. Ge eric prudent engineering practice t K/A 154001-K1.09 I.R. 3.3 )
K/A 194001-K1.02 1.R. 4.0
'K/A 194001-K1.01 1.R. 4.0 194001K101 194001K102 194001K109 ...<KA'S) i ANSWER 8.11 (2.00) ]
! (0.5 EA) 1
- a. no ,
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- b. yes !
- c. no !
- d. no REFERENCE.
STP TS 3.8.2 l K/A 063-000-SG8 I.R. 4.1 063000SG8 ...(KA'S)
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COMMENTS ON NRC R0 AND SRO EXAMINATIONS 05-12-87 SOUTH TEXAS PROJECT Questions Comment l 1.04 B. Change the answer to " Increases."
The-fuel temperature coefficient becomes more negative due to Pu-240 buildup and clad creep causing a decrease in effective fuel temperature.
Ref: SOTX lesson plan RXTH, Reactivity and Fuel Temperature !
Effects, pp 17-18, Attachment I 1.11/5.03 Credit should be given if the Technical Specification I parameters were listed.
- 1. Control rods in a group aligned within + 12 steps
- 2. Insertion limits
- 3. Proper bank overlap
- 4. Axial flux dif ference Ref
- Tech. Spec. Basis 3/4 2.2 and 3/4 2.3 pp 3/4 2-2 and 3/4 2-4, Attachment 2 1.16 B. The question should be reworded to ask (wha; does DNBR have to be for DNB to occur?) instead of "for boiling to occur"?
The answer key should accept either < or = 1.0 f rom a theoretical concept or < or = 1.3 from an operational concept.
Ref: SOTX lesson plan, Heat Transfer and Thermodynamics, 1 Section II, Part C, p 262 and SOTX Technical Specifications Bases 2.1.1 p B 2-1 1.17 An alternate answer should be: They are in an area of higher neutron flux and if inser ted will absorb uore neutrons.
Ref: SOTX lesson plan RXTH, Control Rod Reactivity Effects, p 7, Attachment 4 2.02 Either a or b should be an acceptable answer since question asks for a single incorrect statement and P9 enables turbine -
trip / reactor trip.
Ref: SOTX Technical Specifics. cions Bases: Limiting. Safety '
System Settingo, p B 2-7, Attachment 5 2.03/6.02 Credit should be allowed for those that recognized that the 100 and 150 gpm orifice Isolation Valves have been changed to air-operated valves and now fail closed.
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Question Comment 2.06 Generator (Output) circuit breaker should be added as an alternate answer. 1 i
Ref: SOTX lesson plan, Main Turbine Generator and Exciter, l pp 20 and121, section 2.1.3, Attachment 6 i 2.07 Main feedwater pump turbine trip on overspeed should be included as an acceptable answer.
Ref: SOTX lesson plan, Book 3, S/G MFP, p 4, Attachment 7 1
2.08 Answer key should be revised as per the Technical !
Specifications:
- 1. Containment pressure - High 2
- 2. Steamline pressure - negative rate
- 3. (Compensated) steam line pressure - LO LO '
- 4. (Compensated,) T -
0 LO cold Ref: Technical Specifications Table 3.3-4, p 3/4 3-30, Attachment 8 2.12 Answer key should include low oil pressure trip.
i The diesels trips with low bearing oil coincident with low turbo oil pressure. I Ref: Technical Specifications 3/4.8.1, p 3/4 8-5, Surveillance 4.8.1.1.2.3.6C, Attachment 9 2.13 Revise the high containment pressure setpoint to 3 psig as per Technical Specifications and (P-10) in the 3rd answer should be revised to P-15). '
Ref: Technical Specifications Table 3.3-4, p 3/4 3-28, s
Attachment 10 2.1A Revise answer key to include automatic start of aux feedwater pump cubicle ventilation.
Ref: SOTX Ingic drawing 5V-14-9-Z-41634,' Rev. 2 3.07 Revise 3.07 D to False. The word solely does not take into account the propgttional part of the controller.
3.09 Credit should be given for listing the Turbine Generator Building sump radiation monitor.
Ref: Abnormal Operating Procedure IPOP04-RA-0002, Attachment 10 l
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l Question Comment l
l 3.10 Credit should be given for Technical Specification 1 parameters for which the setpoint is varied: I
- 1. Coolant Temperature
- 2. Pressure 1
- 3. Power
- 4. Axial Power Distribution j 1
Ref: Technical Specification Bases for 2.2.1, p B 2-5,
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Attachment 11 1 3.13/6.10 Credit should not be lost for including the pump mini-flow recirc valve closed.
Ref: SOTX lesson plan, Book 5, ECCS p 5, Attachment 12 3.14/6.11 Full credit should be given for reactivity excursion in parts A and B as per Technical Specification Bases for these trips. ;
Ref: Technical Specification Bases for limiting safety system settings 2.2.1, p B 2-4 '
3.18 Full credit should be given for listing the automatic open I signal generated by increasing pressure above the P-ll setpoint.
Ref: SOTX logic drawing 5N-12-9Z-42028 4.05 Credit should be given for Condenser Vacuum low alarm.
Ref: SOTX A0P IPOP4-CR-0001 (2.6), Attachment 14 4.06/7.01 Credit should be given for including "If Reactor Trip go to E0000".
Ref: SOTX AOP (1 POP 4-NI-0001), 4.2, Attachment 15
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l Question Comment 4.10/7.07 The answer key should be revised to include all the Start / Restart Criteria.
- 1. Restart Duty Criteria
- 2. RCP Oil
- 3. Seal Water Injection
- 4. Seal Leakoff Flow
- 5. Standpipe Level
- 6. No. 1 Seal DP
- 7. Thermal Barrier and Motor Bearing Cooling Water
- 8. Oil Lift Pump Running and Oil Lift Pressure l
.1875 points each l
Ref: SOTX Procedure IPOPS-E0-ES112, Attachment 16 4.19/7.12 Operators should not memorize specific precautions but should know the reasons for monitoring a parameter. The i question should be revised to:
State the importance for closely monitoring AFW storage tank level.
The key should be revised to:
- 1. AFW pumps have no loss of suction trip protection AFWST low level. (.5)
- 2. To Ensure that the minimum level is maintained as per technical specifications (.5) i 6.14 a. Change answer to Non-Urgent failure alarm or DPRI trouble l
Ref: 0-LIC-H0.RPI.01, p 3, Section C.1) a), Attachment 17 7.03 b ESF status monitoring lights should be accepted as the
" Primary" method of verifying phase "A" containment isolation because these lights are driven by ERF/ DADS Key ERFDADS (ESF status lights) 8.01 a & b Credit should be given for concerns regarding Personnel Hazards and Radiation 8.02 a Other words which describe types of preventative maintenance should be acceptable and since this procedure can currently be used to perform surveillance, types of surveillance should be acceptable.
Ref: OPGP03-ZM-0002, p 3, Section 1.5, Attachment 18
Question Comment I 8.02 d Delete pint permit f rom the answer key. The current j
procedure discusses clearances /eprmits. Therefore, full ;
credit should be given for any three clearances / permits !
listed in section IV of the MWR Form.
Ref : SOTX Procedure OPGP03-ZM-0003, Attachment 19 8.03 a The question references " Groups" and the current Emergency Plan does . not use this term. In addition, the plan now has I only two response organizations.
Full credit should be allowed for any of the following groups within the emergency organization:
- 1. Fire Brigade
- 2. First Aid
- 3. Emergency Medical l or
- 1. Onshift Response Organization
- 2. Emergency Response Organization {
l Ref: Attachment 20, p 1 of 22 or
- 2. Emergency Operations Center
- 3. Operations Support Center Ref : Attachment 20, p 11 of 22 l 8.03 b Signing the Emergency Director's Checklist should be acceptable for documentation.
Ref: 0EPP01-ZA-0002, p 11 of 15 8.04 e Radiological Manager should be changed to Radiological Director Ref: OEFP01-ZA-0010, Attachment 20 8.05 a All references to a specific color have.been. removed from the procedure. Full credit should also be given for stating the jumper will be " Tagged" or " Labeled". ~
Ref : SOTX OPGP03-ZO-0003, p 2 of 16, Attachment 22 8.05 Full credit should be given for " Shift Supervisor".
Ref : SOTX Procedure OPGP03-ZO-0003 p 7.of 16, Attachment.22 U__-_-_-__.___.--.-_-__.___--_._.---_-_-.__-_-----.
l Ques tion Comment 8.06 a Per the equipment clearance procedure we now have only 3 l
BOOKS.
Ref: SOTX Procedure OPGP03-ZO-0001, Attachment 23 8.06 c The reference to " Good Practices for Clearances" no longer exists in the equipment clearance procedure. Therefore, the l question should be deleted or graded for good engineering I practice concepts.
i Ref: SOTX Procedure OPGP03-ZO-0001, Attachment 24 l
8.07 a Key should be revised. The limits are_per 10CFR100.
Ref: Technical Specification Bases p B 3/4 4-5, Attachment
.~. 24 8.07'b Parts a and b on this question should be separated to i different questions.
This is the second part of a two part question. The first !
part of the question asks for information on the basis of the RCS activity limits.
l The second part of the question asks for information about the bases for transient limits that are less restrictive than steady-state limits. But, this part is about chemistry and not activity. Both specifications have steady-state and transient limits. The response from the examinee is keyed
>n him recognizing that the second part is about chemistry i and not activity. There is a good probability that on a I
timed exam the second part of this question could be misread. Therefore, an acceptable alternative response should be.
The transient limit accommodates possible iodine i spiking phenomenon which may occur following changes in thermal power.
1 Ref: Tech. Bases B 3/4 4-5, Attachment 24 8.10 a A "High Pressure" system is not defined in the current procedure. Grading should be in accordance with paragraph 4.5 of the current equipment clearance procedure.
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Ref: OPGP03-ZO-0001, Rev. 3, p 7, Attachment 25 l
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8.10 e When verifying that a high pressure system is properly isolated and is safe to commence work, visual inspection of vents and drains should be given full credit.
Ref: OPGP03-ZO-001, Rev. 3, p 23, Section 5.14, Attachment 26 i
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