ML20210E201
| ML20210E201 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 09/10/1986 |
| From: | Cooley R, Whittemore J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20210E196 | List: |
| References | |
| 50-498-OL-86-01, 50-498-OL-86-1, NUDOCS 8609220150 | |
| Download: ML20210E201 (47) | |
Text
.
OPERATOR LICENSE EXAMINATION REPORT No. 50-498/0L 86-01 Licensee: Houston Lighting & Power Company P. O. Box 1700 Houston, Texas 77001 Docket: 50-498 Operator License Examinations at South Texas Project (STP)
Chief Examiner:
h 9 9 Id J.
. Whittemore, Operator Licensing Date ection
,6. hiv 7//0/ 2(p f
Approved By:
R. A. Cooley, Chief, erator Licensing Date Section Summary Written examinations were administered to 26 Senior Reactor Operator candidates at the South Texas Project training facility during the week of July 21, 1986.
Twenty-five(25)ofthetwenty-six(26)SeniorReactorOperatorcandidates passed these examinations and will be administered operating examinations at a later date to determine eligibility for Senior Reactor Operator Licenses.
8609220150 860916 PDR ADOCK 05000498 V
2 Report Details 1.
Examination Results Written examinations were administered to 26 Senior Reactor Operator candidates. Twenty-five candidates passed and one of the candidates failed the written examination.
2.
Examiners J. E. Whittemore (Chief Examiner)
J. L. Pellet 3.
Examination Report Performance results for individual candidates are not included in this report as it will be placed in the NRC Public Document Room. This Examination Report is composed of the sections listed below, a.
Examination Review Comment Resolution In general, editorial coments or changes made during the examination or during subsequent grading reviews are not addressed by this resolution section. This section reflects coments and recomended changes to examination answer keys by the licensee. Examination key modifications resulting from these coments and recomendations are included in the master examination keys, which are provided elsewhere in this report. Coments and resolutions are listed by examination section question number.
Coments and Resolutions 5.02 Other correct definitions should be accepted.
For example:
The combination of source neutrons and induced fissions in the subcritical reactor produces a neutron population higher than source neutrons alone.
Resolution:
Coment accepted.
5.03 Other correct explanations should be accepted.
For example:
Use of moderator temperature coefficient (MTC) fonnula and description of effects on buckling and leakage terms.
E
i e
3 0R_
Control rod insertion requires dilution of boron which causes the MTC to become more negative.
Resolution:
The first comment is noted as this concept is reflected in the existing answer key.
The second comment is NOT accepted as the question specifically ask for effect of. rod insertion, NOT baron concentration.
5.04 The correct answer is "No Change" as the delta I function is set to "zero."
Resolution:
Coment accepted.
5.06.a There are more than two significant reasons for total control rod worth. Any of the control rod reactivity requirements that are listed in the STP Rx. Theory Lesson Plan should also be acceptable.
Resolution:
Comment is NOT accepted as referenced documentation does not support coment in reference to TOTAL R0D WORTH.
5.06.c Other correct reasons for multiple rodlets versus one large rod should be acceptable.
For example:
1.
Rodlets are small and uniformly distributed throughout the fuel. Minimizes the number of neutrons absorbed in one region of the fuel assembly.
2.
Minimizes water hole flux peaking.
Resolution:
First comment is noted as this answer is inherent in existing key. Second comment is accepted and will be accepted as a correct alternate answer for full credit.
5.07.c The answer key requires a restatement of " Increasing Power" which was given in the question. The key also requires building to a new equilibrium which is not asked for in the question. A correct explanation of burnout initially exceeding production should be sufficient.
Resolution:
Comment accepted and key modified.
4 5.10.a Another correct answer that should be accepted is that letdown flow is equal to charging flow plus seal leakoff minus seal injection with pressurizer level constant.
Resolution:
Coment will be accepted as an alternate answer for full credit.
5.10.c The grader should consider assumptions assumed by the examinee in explanation of effects.
Resolution:
Coment noted.
~
5.11.a The answer requires a restatement of " pressure decrease" which was given in the question.
Resolution:
Coment accepted and key modified.
5.11.b The answer key is correct if approached strictly as a fluid flow and thermodynamics problem. However, if it approached as an instrument failure analysis, the reference leg break could be perceived as the most severe. The question could also be approached as per accident analysis which does not differentiate in the severity but requires that the operator analyze changes.
Resolution:
The first part of the above coment is accepted and incorporated into the answer key conditional on examinee's stated assumptions. The final sentence is ignored as it does not address the question as asked.
6.01.a An additional trip should be added: Low 011 Pressure (Engine and Turbo).
Resolution:
Accepted and incorporated into key.
6.01.b SI should be acceptable for LOCA and Undervoltage should be acceptable for loss of offsite power.
Resolution:
Accepted and incorporated into key.
6.02.a The word "only" is a key indicator as to the number of responses required by the question and should be highlighted.
Also, either interlock numbers or names should be acceptable.
Resolution:
First coment noted. Second coment accepted and incorporated into key.
5 6.02.c C-1 rod stop can also be bypassed by " Level Trip Bypass" switch on the Intermediate Range power instrument drawer.
Resolution:
Accepted and incorporated into key.
6.05.a 0FF should be acceptable (not required for credit).
" MANUAL" should be acceptable (not required for credit).
Manual only result in blended flow if operator aligns for blended flow.
Resolution:
"0FF" accepted, but not required for credit.
" Manual" NOT accepted as this position is normally used for blended flow.
6.06.a The answer key requires a discussion of the basis for minimum flow. The question does not ask for the basis for minimum flow.
Therefore, "to ensure that minimum flow is maintained" should be acceptable for full credit.
Resolution:
Not accepted as " minimum flow" does not fully explain the reason for the system design feature.
6.06.c The key should be changed to include " Control is transferred to local from outside the control room with the Local Control switch in Stop."
Resolution:
Coment accepted and incorporated into key.
6.07.a The problem is that the top of the RHR heat exchanger tubes are located above the normal water level in the RWST. This means that any leakage or temperature change in the RHR or LHSI system would cause system voiding, not just check valve leakage. The answer should read as follows: ' Leakage from or temperature change within the system causes voiding. A connection from the RCP seal standpipe maintains a positive head on the system.
Resolution:
Comment accepted and incorporated into key.
6.07.b The answer key depicts an acceptable answer for the condition described. However, the conditions described are not viable because in E0P 1P0PS-E0-E010, the low head safety injection pump would have been secured
f o
6 during injection phase when pressure was greater than LHSI Pump shutoff head..Therefore, any response which maintains injection to the RCS and protects the pump from running against a shutoff head should be acceptable.
Resolution:
Comment on question viability is invalid and therefore rejected. The stated conditions are viable if operator action has resulted in leak mitigation or isolation after transfer to the recirc. mode.
- Further, 4
it is not prudent to stop flow to the RCS under accident conditions merely to obtain water from a lower pressure source by stopping High Pressure pumps.
]
Answer key will accept actions that stop LHSI pumps or reduce pressure that pump is operating against that do not result in stopping SI flow.
6.08.a The answer key references the RCP system description and describes an analytical method. The operator may list valves and indications which affect the condition.
Credit should be given for items mentioned which would directly evaluate the correct lineup.
Resolution:
Comment accepted and incorporated into key.
6.08.b.3 There was a design change proposed on the CCW outlet isolation valve from the RCP's. The motor operated valves will be replaced with pressure actuated isolation valves. High temperature and flow will initiate control room alarms and credit should not be lost for this response.
Resolution:
Connent accepted and incorporated into key.
6.08.b.4 The relief valve protects the piping from overpressure in the event of isolation and heat input.
If.the thermal barrier is ruptured, the piping is protected l
from overpressure by the Pressurizer Safety Valves.
The relief, therefore, has no function to mitigate the i
l consequences of a thermal barrier rupture and should l
not be required for credit.
Resolution:
Connent accepted and incorporated into key.
6.09.a The answer key list action resulting from P-14 while the question asks for actions that result from P-15.
There are no actions that result from P-15 alone, but P-15 in coincidence with other conditions will result in enabling or blocking SI or Feed Water isolation.
Resolution:
Comment accepted and incorporated into key.
l
a 7
6.09.b The key should accept word descriptions of the interlocks.
Resolution:
Coment accepted and incorporated into key.
6.10.a The answer key describes the effect of the steam flow instrument failure on the steam generator level control system and the response of the systems effect feed pump speed control and is correct for the overall effect.
However, the question can be interpreted as asking the initial effect of a steam flow instrument failure high on the feed pump speed control system, and at full power the delta P program may or may not be at maximum value.
Therefore, increase in total steam flow may or may not increase the demand delta P.
This result in no initial effect on feed pump speed if program is already at maximum value. Therefore, either answer should be acceptable.
Resolution:
Coment accepted. Second answer will be accepted conditional on stated assumptions.
7.02.a An alternate name for Pressurizer Level Control Valve (FCV-205) is Charging Flow Control Valve.
Resolution:
Coment accepted and incorporated into key.
7.03.b Components that can be affected by switch should be accepted, but not required for full credit.
Resolution:
Coment accepted and incorporated into key.
7.04 Other responses which would routinely limit the rate of power increase to less than 5%/ min. should be acceptable.
For example:
l Dilution rate capability routinely limits rate for power change to less than 5%/ min.
Resolution:
Coment is not accepted as dilution rate may operationally restrict, but does not procedurally limit rate of power change.
7.07.b.3 The answer key should read:
Blowdown.
(0.25) Process and storage of radioactive waste OR contamination of secondary systems.
(0.25)
Resolution:
Coment accepted and key revised.
7.08.b Key should be revised to:
May form voids in the RCS>
t 4
8 Resolution:
Comment accepted and key revised.
7.11 The answer key describes how water is added to the refueling cavity for credit. This response was not 4
asked for in the question and should not be required for full credit.
Resolution:
Comment accepted and incorporated into key.
8.01.a Since at STP all POP 5 procedures are classified as.
separate and independent emergency operating procedures, the question asking for the three major elements of the Emergency Operating Procedures is confusing. The question can be interpreted as asking the three elements of a single Emergency Operating Procedure or Emergency Operating Procedures as a whole.
Major elements of a single procedure have been that should include symptoms, entry conditions, actions, contingency actions, subsequent actions, cautions, etc... Therefore, major elements of an Emergency Operating Procedure should also be accepted as alternate answers.
Resolution:
Comment is NOT accepted as referenced documentation does not support comment,'but does identify elements that are the same as the answer key.
l.
8.01.b STP E0P's are written such that the ES and EC series are each a separate E0P, and not contained within any other E0P. TP #1 of Introduction to E0P's listed the "EOP's" that STP uses. Due to the wording of the question and the actual organization of the E0P's, no logical single answer to the question can be found.
Therefore, requested that question 8.01.b be deleted and overall point value of the exam be adjusted.
Resolution:
Comment is NOT accepted. Regardless of question wording or format, candidates should know the specific purpose of the ES and ECA series asked for.
8.01.c Alternative correct answers should be acceptable.
For example:
i The E0P's were developed using specific assumptions about plant conditions. Operable equipment and plant conditions in modes 5 and 6 are outside the assumed conditions.
Resolution:
Comment accepted and incorporated into key.
9 l
8.01.d In review of Conditional Infonnation Pages, AFW Flow and SI Initiation /Re-initiation Criteria should be considered comon to all fold out pages.
Resolution:
Coment accepted and incorporated into key.
8.02.b During alert, the Emergency Director is stationed at the E0C instead of the TSC.
Resolution:
Coment accepted and incorporated into key.
8.02.c Radiological Manager should be an alternate acceptable answer.
Resolution:
Coment accepted and incorporated into key.
8.05.a The definitions in the procedure define a Temporary Device Tag to denote a Temporary Condition. The question asked how and Temporary Devices are recognizable and they are recognized by their bright orange color. Therefore, the bright orange color or orange strip should be sufficient for full credit.
Resolution:
This coment is NOT accepted as the proposed answer is incomplete.
Further, the procedure does not state that devices such as blank flanges will be orange, but is does require a tag to be hung adjacent to the temporary condition.
8.05.b The procedure requires that the SS verify the system returned to normal. Therefore, Shift Supervisor should be an acceptable alternate answer.
Resolution:
This coment will NOT be accepted as the procedure intent is for different individuals to sign the
" Temporary Device Removed" blank and the " System Returned to Normal" blank. The key will be modified to allow I credit for answering either SS or Requester.
8.08.a The key references 10 CFR 20 limits and it should state 10 CFR 100 limits.
O_R Accept discussion of cooldown to prevent release of radioactivity through steam generator atmospheric steam relief valves.
10 Resolution:
Changed key to read "10 CFR 100 limits:. The second proposed answer.is NOT acceptable as the question.
solicits the basis Tor the action statement, not the method of conformance.
8.10.a The answer key is correct, however, credit should be given for other correct answers:
Technical Specification Section 3.1.1.3, ACTION A.
indicates that Control Rod Withdrawal Limits should be established. Thus, a discussion on establishing withdrawal limits should be an acceptable answer.
Also, the Action Statement allows for fuel burnup causing boron dilution, making MTC more negative, and should be an acceptable answer.
~
An alternate answer as to how " Rod Insertion Limit" action solves the problem:
Control rod insertion (withdrawal limits) will cause MTC to become more negative due to changes in surface /
volume ratio (buckling) and neutron migration length.
Resolution:
Comments accepted and incorporated into key.
It should be noted that the first coment was inherent in the original answer key.
8.10.c The " modes" should be deleted from the answer key as they were not asked for in the question.
Resolution:
Comment accepted and key changed.
b.
Site Visit Summary At the end of the written examination administration, the licensee i
was provided a copy of the examination and answer key for the purpose of commenting on the examination content validity. The licensee subsequently provided a tour of the Unit 1 facility and the full scope simulator.
It was explained to the licensee, that region policy was to have examination results finalized within 30 days, but due to the large number of examinations to be graded, as well as previously scheduled commitments, this goal may be unattainable.
c.
Examination Master Copy The SR0 master examination and answer follow and constitute the remainder of this report.
Changes resulting from licensee comments are reflected in this key.
[
4 a.
~ U. ~ S.
NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_10MIH_IEM61_1___________
REACTOR TYPE:
_EWB-WEQa________________
DATE ADMINISTERED:_BklGZL22________________
EXAMINER:
_WHIIIEMQBEz_Jz__________
CANDIDATE:
IN11BuGIl0NS_IQ_GeNQ1Q81El
'Uso separate paper.for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question.
The passing grade requires at: least,70% in each category and a. final grade of at logst 80%.
Examination papers willHbe picked up six (6) hours after
+
the examination-starts'.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY
__V6LUE_ _IQI8L
___SQQBE___
_V8LUE__ ______________Q&IEQQBl_____________
________ 5.
THEORY.0F NUCLEAR POWER PLANT
- ._25tDQ__ _25tDQ _ ___________
OPERATION, FLUIDS, AND THERMODYNAMICS
_25z0D__ _25t00
________ 6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 2EzQQ__ _25z00
________ 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
_25tDQ__ _21x00
________ 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS i
100A00__
Totals Final Grade All work done on this examination is my own.
I have neither given nor received sid.
Candidate's Signature d
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.2 IBEBdQQ1NadIQ1 QUESTION 5.01 (1.50) le a primary neutron source necessary to provide sufficient neutrons to start the initial chain reaction in a new core? BRIEFLY EXPLAIN your answer.
(1.5) 4 QUESTION 5.02 (2.50) o.
Define Subcritical Multiplication (M).
(0.75) b.
Briefly explain why M is not used to plot a criticality prediction.
(0.75) c.
If the count' rate is 100 cps at a Keff of 0.95, what will the count rate be at a Keff of 0.99?
(1.0)
QUESTION 5.03 (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)
QUESTION 5.04 (1.50)
'The plant is operating at 50% power with control rods in manual.
How does a HIGH failure of Power. Range channel N-44 LOWER detector offect the following indications?
(Limit your answer to INCREASE, DECREASE, MORE NEGATIVE, LESS NEGATIVE, or NO CHANGE.)
c.
Lower Quadrant Power Tilt Ratio (QPTR)
(0.5) b.
Delta Flux (Axial Flux) indication (Channel 4)
(0.5) c.
Overpower Delta T trip Setpoint (Channel 4)
(0.53
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CATEGORY 05 CONTINUED ON NEXT PAGE *****)
-51__IBEQBl_QE_NUQLE88_EQWEB_EL8NI_QEEB8IIQNt_ELVIQ1t_8ND PAGE 3
-IBEBdQQ1Nad101 QUESTION 5.05 (2.00) c.
Which parameter below will have the MOST effect on the shape of a Differential Rod Worth Curve?
BRIEFLY EXPLAIN your answer.
1)
Core radial flux profile 2)
Core ~ axial flux profile 3)
Core radial temperature profile 4)
Core axial temperature profile (2.0)
QUESTION 5.06 (2.50) c.
Total control rod worth is approximately 8000 PCM.
What are the 2 significant reasons that this value was picked ?
(1.0) b.
Why are the control rods withdrawn or inserted in an overlapping program (0.75) c.
Why is a control rod of several small fingers preferred over one large rod ?
(0.75)
QUESTION 5.07 (3.00)
G.
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 maj or cause for concern about Xenon during reactor operation ?
(0.75) c.
Why will a power increase cause Xenon (or Samarium) to undergo a short term decrease in concentration ?
(0.75)
QUESTION 5.08 (2.00)
How and why is fuel centerline temperature affected by the following?
Consider each independently:
c.
Corrosion and crud buildup on the fuel cladding?
(1.0) b.
Fuel densification?
(1.0)
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5'__IBEQBl_QE_NUGLE88_EQWEB_EL8NI_QEEB8110Nt_ELUIQat_8ND PAGE 4
IBEBdQQ188 DIGS QUESTION 5.09 (2.50)
Indicate on your answer. sheet whether the following statements are true or false:
c.
The temperature difference necessary to transfer heat energy is inversely proportional to the heat flux.
b.
Pump runout is a term used to describe a centrifugal pump operating with a shut discharge valve.
c.
Latent heat of vaporization is another term for latent heat of fusion.
d.
A law applying to centrifugal pumps in closed loop systems states that power required is directly proportional to the square of the pump speed.
o.
For two IDENTICAL centrifugal pumps running at DIFFERENT speeds in IDENTICAL systems, the faster running pump requires a greater NPSH.
QUESTION 5.10 (2.50) e.
During operation, indication for charging flow rate is lost due to a transmitter failure.
Explain how the operator can' accurately evaluate the charging flow rate using other control room indication.
(1.0) b.
Explain how the following' occurrences would affect Net Positive Suction Head available to the Reactor Coolant Pumps.
Assume that no operator action occurs and consider each occurrence independently and separately.
1.
Grid frequency decreases to 59.6 HZ.
2.
Pressurizer temperature increases.
3.
Turbine power increases slightly with rods in manual.
(1.5)
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HI__IBEQBY_QE_NuGLE88_EQWEB_EL6NI_QEEB6IIQNt_ELu1DHi_8ND PAGE 5
-IBEBdQQ1Ned191 QUESTION 5.11 (3.00) c.
During natural circulation cooldcWn,-pressuiizer level increases abnormally' subsequent to the initiation of spray to reduce pressure.
Explain what is occurring.
(1.5) b.
Assume a small LOCA results from the rupture of a pressurizer level
~
transmitter sensing line.
Compare the severity of the accident if the ruptured line is the. upper (refer'ence) or lower (variable) sensing line.
-(1.5) l 4
l
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END OF CATEGORY 05 *****)
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'PAGE 6
QUESTION 6.01 (2.50')
St'te the Emergency Diesel Generator trips that'are operable during G.
a emergency auto-start.
( 1. 0 ).
b.
List the modes of ESF sequencer operation and describe'the1 specific instances for'the occurrence of each mcde.
Further, describe.the action associated with each mode.
(1.5)
QUESTION 6.02 (2.50) e.
List the rod stops'that are only ef f ective 'in the automatic reode of rod withdrawal and explain why they are necessary?
(1.0) b.
What actionicutside the rod control system occurs simultaneously upon receiving a rod stop generated by C-4 and C-57 (0.5) c.
What are 2 methods of defeating'or bypassing rod stops generated by high reading nuclear instruments?
[1.0)
QUESTION 6.03 (2.00)
MATCHING.
Match each of the actions with the appropriate pressurizer pressure control or protection setpoint.
Actions may be used more than once or not at all.
Place an appropriste number after letter on your pcper.
SETPOINT (psig)
ACTION o.-
2485 1.
Normal Pressure b.
233S 2.
Reactor Trip c.
2250 3.
Variable Heaters off d.
2220 4.
Safety valves open o.
1950 5.
PORV Interlock f.
1870 6.
PORV Opens 7.
Safety Inj ection Block 8.
Safety Inj ection Actuation 9.
Variable Heaters Full On e
i
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- h*__ELhBI_SIRIEUS_QE11GNt_CQUIB9Lt_6NQ_INSIBMdENI811QN PAGE 7
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QUESTION 6.04 (2.50) c.
What are the 3 sources of fluid that may be cooled by the Seal Water Heat Exchanger?
C0.75) b.
Where may the cooled fluid from the Seal Water Heat Exchanger be directed?
Indicate which flow path is normal.
(0.75) c.
Describe the interlock between the Letdown Isolation Valve and the Letdown Orifice Isolation valves, and explain the purpose of the interlock.
(1.0)
QUESTION 6.05 (3.00)
P o.
What positions of the " Reactor Coolant Makeup Mode Selector Switch" will NOT result-in the delivery of a BLENDED makeup flow?
(1.0) b.
During boration, what control or instrument serves to control the
-amount of boron added or terminates the process?
(0.5) c.
State how automatic makeup is initiated and explain the automatic action that occurs upon initiation.
No specific setpoints or values are required.
(1.5)
QUESTION 6.06 (2.50) n.
Why does RHR have a temperature control system designed to maintain a constant flow rate?
(0.75) b.
Explain the RHR design feature that allows for continued decay heat removal when a loop must be partially drained for maintenance such as RCP seal replacement.
(0.75) i c.
What are the 4 possible reasons for an operating RHR pump to stop when operating with it's control switch is in normal?
(1.0) i I
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qc a
- 51__EL8hI_AYSIENS_QE11ftNc_GQNIB9L,._660_INSIBQUEUI&Il08 PAGE 8
J 4
- QUESTI0u 6.07 (2.00).
c.
Describe the problem which may'cause AND the design featurs that precludes the potential for water hemmer on.ntartup of the Low Head Injection System.
.(1,0) b.
'What. followup operator action is required when shifting to Cold Leg Recirculation with a sotall break LOCA and RCS pressure et 500 psig?
t' Er. plain why the action is necessary.
(1.0) i QUESTION 6.08 (2,50)-
c.
If'# 1 Saal Water Return flow is loss than minimum receired for starting an RCP, what are 3 things the operator should check initially 4
that may he causing the problem?
_(0.9) b.
Describe 4 AUTOMATIC ACTIONS and/.oc DESIGN FEATURES that act to mitigate the loss of cool.snt should 6 Reactor Coolant Pump Thermal i.
Barrier Heat Exchanger rupture.
(1.6) i i
QUESITON 6.09 (2.00) e.
State the actions that result.from reaching the Permissive P_15 i
setpoint.
(1.0) b.
List the Solid State Protection System Permissive Interlocks that use other Permissive Interlocks as initiation signals AND state the
{
specific initiating Permissives.
(1.0) i.
I l
QUESTION 6.10 (2.50) t c.
Explain the initial effect on Feed Pump speed on e HIGH failure of a Steam Generator Level Control system steem flow detector during normal full power operation.
(1,0) i o.
Assuming 100 % power, is automatic protective action more likely to result from a FAILED HIGH or FAILED LOW steam flow detector?
Justify your answer.
(1.5) l l
l
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[QUCGTION~ 6.11 (1.00)
' WP.at ~aretwo reasons thst explain the rationale for NOT using RCS flow 2
1co: one of tha. parereter s f or calculating the 0 tdt trip setpoint when RCS Eflow hes e direct.ralationship to DNB7 11.0)'
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END OF CATEGORY 06 *****)
- 21-EBQQEQVBE1_
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B8019LQE108L_GQNIBQL QUESTION 7.01 (2.50)
Fill in the blanks below dealing with precautions end limitations during cperation of the Reactor. Coolant Pumps, s.
.The. required' minimum pressure differential across the # 1 seal is _____
psi.-
This minimum requirement is expected to be satisfied if RCS pressure is maintained at least ______ psig.
(1.0) b.
If cooling water-flow to the motor bearing oil cooler is lost, pump operation must be terminated before the upper or lower bearing temperature exceeds _____ deg's F.
(0.5) c.
The Reactor Coolant Pump must be stopped within _____ minutes after the No. I seal leekoff is isolated.
(0.5)
.d.
Do not attempt to start a Reactor Coolant Pump if the No. 1 seal flow is less than _____ GPM.
(0.5)
QUESTION 7.02 (2.50) c.
For pressurizer bubble formation, what components are manipulated to initially control:
1.
Charging. flow rate at greater than 35 GPM7 2.
Reactor Coolant pressure between 150 and 250'psig?
(1.0) b..
Which way will the following parameters initially trend to indicate bubble formation? Answer increase, decrease, or stesdy.
]
1.
Reactor Coolant pressure 2.
Letdown, flow 3.
Pressurizer heatup rate (0.75) c.
If it is decided to add Hydrazine to the RCS curing initial heetuo, WHAT CHANGE must be made to the CVCS lineup and WHY?
(0.75)
'~
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
'Z1__ERQ2EQUfA1_z_NQB58L&_atNQBd8L&_EMEB9EN21_6NQ PAe.iE i l BeQIGLG01C8L.CQNIBOL d
-QUESTION 7.03
(: BOD) c.
What are 2 genersi taceptions to the recc?ntennt that all shotdcwn
[
. control rod t>u nks be withdrawn : if posi.tled 'sectiolty.1x be tw3
.sdded.
.(1 D)
I b.
Prior to reactor stuttus., what ac-tionn should re.$uit when the Fv.11 i
Length-Rod Control Etortup Switch is posit.ioned "t.e recet?
(C.5) j c.
What initial action sheent.d be isken in toe fos tsf.ving cases:
}
1.
Criticality in achieved at s rad postt%wn Qreetar then 500 Pc}i below the Eotineteo Cr iticAlsty Pagitiro 1EMP3 (0.El 2.
Criticality to not ic%ie.vod et # don',tt.4 1:32 PC" obove the Estimated CrittcAlity Posit $ ens (0.5) 3.
When power 18 steadted to chlatu 4*ttbyet ante et 10 C(-3) arps there is e LCW ItiSERTIW MFI T A1?t%
(0,Si-i QUESVION 7.04 (1,601 Preceutions in Power Oserstions [s AiP0 Ti OSDT) etC4e that @te re.te of power -A nc re ase s ta li v.6 t e xcoA d ?d /N U;. c r a fGC at.,p chenge.
t(t D1. J.tr e f reasons that rate of torreas4 ts 7 04tkGekt ects t 'ic-l ting than s t ated above?
(1.51 QUESTION 7.05 (2.00) e.
Which of the f oll'swier; soiw.pc ie s t r o w a y)d wit te i nit i al.ly indic3thva.
of a dropped control rod?
1.
" ROD DEVIATION" 2.
" ROD Cof(TROL NON-G7454) ALSA8" 3.
"PR CHANNEL DEV" 4.
"PR FLX. RATE HI RX Thf P A;f RT'-
(1.0) b.
While recovering a drop 4ed r ed.
L.A A9
>4 pyq4ttve Pegotivity compenssted for7 (1.03 i
I
(*****' CATES 0SM 37 CC%TirMGL 6d N!.XT PAGE **stv)
=
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.ll
.CUEti10N 7,06-f3.63) n
- J 1he re. lent is coeratiA6 at AS% cower with all systemn in automatic when one
- M31n'4ta3m isolation palve thuts.
I nd i c.it e how the following parameters n4111 tr$nd (increase, cecrasse, stetdy) after the valve is closed.
d.
Turbine power l
. l ot.p )
b, Yevg. f.affooted e,
Tsvg. tunaffeetta loop) d.
Sites 645.eretor Pressure (affected leop) j' v.
Reactor pouce
{
Steso Goneva?.o preinurc (unaffected loops) t 7
[
QUEST 10f1 7,07 (2.50) n.
A;cor.d(of to the Steam Gener ator Tube Rupture procedure (E030), what
- l i
l are the flow gaths of concern e4 hen the operator is instrycted to "Etop flav FRU4 the ?palted Steam Generator"?
[1.0) n.
List tha tbren distinct niethods of post SGTR cocidown and indicate j
iht disodeactopci of each method.
(1 5) l i
(
,40(S110W 7,04 (2.50) a.
In "dotural Circulation Cooldown with Steam Void in Vessel" (ES03), why is the operater instructed to maintain a LOW pressurizar 16 vel when in it i.a l ly starting the procedure and a HIGH level'for starting,a f
Reactor Coolant Pump?
(1.5) b.
Vny la the ocerator cautioned not to depres6urize the RCS until The entire system ir below 200 deg's F.?
(3.5) o i
c.
Why is there a priority for running specific Reactor Coolant Punps
[
after.they becoca available?
(0 5)
I i
i
(*T*** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
?Z1_iEBQQEQMBE1_:_NQB58Lt_8BNQBd8Lt_EMEBEENQ1_8NQ PAGE 13
~28DIQLQQ108L'_QQNIBQL P
i
. QUESTION 7.09 (2.50)
- 10.,. According to EO-FRS1 (Response to ATWS or Power Generation), what are four (4) viable methods of stopping the Main Turbine, should it fail to trip?
(1.0) b..
Step 6 of the above procedure requires the operator to verify all dilution praths isolated or secured.
What are the two (2) dilution
-paths.of concern?-
(1.0) c.
Vhat action is the operator directed to take if'immediate boration rate i
is slow due-to high RCS pressure and RCP's are stopped?
C0,5)
- ,c QUE'STION. 7.10 (2.00) i t
ci.
Which of the following whole body exposures would cause the greatest amount of biological damage?
1.
1 REM ALPHA 2.-
l' RAD NEUTRON 3.
1 ROENTGEN BETA 4.
1 RAD GAMMA (0.5) b.
What is the most important factor to consider when choosing between a GH TUBE or ION CHAMBER for an area radiation survey?
EXPLAIN.
(1 0) 4.
Provide one reeson why a scintillation counter is superior to a GM Tube.
(0.5)
I i
QVEGTION 7.11 (1,00)
[
Explain how shieloing from irradiated fuel is provided while removing the i
Reactor Vessel head.
(1.0)
(*****
FND OF CATEGORY 07 *****)
e.-,
4
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,n
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--,s s
, m n a,a
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PAGE 14 t
QUESTION 8.01 (3.00) c.
What are the three (3) maj o r elements of the South Texas Proj ect (STP)
Emergency Operating Procedures CEOP's)?
(1.0) b.
What is the purpose of the ES and ECA series contained within a major E0P (Optimal Recovery Guideline)?
(1.0) c.
Why is the operator prohibited from using the E0P's in Operating modes 5 and 6?
C0.5) d.
What information is common to all foldout pages?
(0.5)
QUESTION 8.02 (2.50) c.
While serving as Emergency Director, what are four (4) responsibilities that can NOT be delegated?
(1,0) b.
Where are the following individuals located after augmentation during an ALERT:
1.
Emergency 01 rector?
2.
Shift Supervisor?
3.
Plant Operations Manager?
(D.75) c.
With the Initial Response Organization in place, who are the three (3) managers or directors that report directly to the Emergency Director?
(0.75)
QUESTION 8.03 (2.00)
State the guidelines for Einergency Classification using the Barrier Challenge / Failure criteria.
(2.03 QUESTION 8.04 (2.00) o.
How is it normally determined what division has cognizance of system or component operation?
(1.0) b.
How are conflicts resolved in the short and long term?
(1.0)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
e --
~
-A1__eQb1NIBIS$IIXE_EBQCfDWBESt QQNQ1110NS _oHD.L1dII6Il0H1 PAGE 15 i
QUESTION 8.05 (2.50) a.
How are J9mpers and Temporary Devicsc recognizable when installed t6 perform their temporary function?
(;.0)
F b.
Who is responsible for verifying that a tsmporary device or Ju6per has been removed?
(0,5) c.
Who is responsible for ensuring thet a system has been returned to normal after removal of a tempo'rary device AND.what ore two (2) methods that may be used to perform this verification?
(1.0)
QUESTION 8.06' (3.00) c.-
Detail the purpose of Equipment Clearance Books #3 and #4.
(1.0) b.
Is it required for the "Verif ier" to accompany the '*0per6 tor i t.
performing alignment activities for a clearance 7 Explain why or thy not.
(0.E) c.
When reviewing an Equipment. Clearance Order for.nethorizstian,.the Shift Supervisor (issuing authority) is c'eq'at' red to considtr the' list of " Good practices for clearances".
In your o'wn words, giv~a three (3)
.of the " good practices" found on this ligt.
(1.0)
QUESTION 8.07 (3.00)
For each item below indicate YES or NO concerning whether or not the item j'
is the subject of Technical Specification LCO, Action Statement, or Surveillance Requirement.
(Simple mentioning of the item in T.S.
does not meet this requirement.
s.
Turbine EHC System i
b.
Suspended solid content of the ultimate heat sink c.
Fire doors d.
Turbine-Generator steem bypass valves (dump valves)'
e.
Steam Generator (secondary) chemistry f.
Contents (levell of the Auxiliary Feed Storage tank g.
Quadrant Power Distribution l
h.
Wind speed iristrument in the meteorological tower i.
Pressurizer power operated re11ef valve J.
Suspended sclid concentration (ppm) of the RCS (3.0) l I.
l.
l
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
.. ~.
r"~
i Bl._6DMINISIBoIIVE_EBQGEDMBEft_QQNQlIl0N2t_6HQ_LidII6I1QN3 PAGE :16 e
QUESTION 8.08 (2.00) c.
Why do the Tech'nical Specifications require the reactor to be. shutdown and cooled down when RCS activity limits are exceeded for an extended period of time?
(1.0) b.
Why do the Technical Specifications contain transient limits for RCS chemistry that are less restrictive than steady state limits?
[1.0)
QUESTION 8.09 ft,50) s.
Technical Specifications list at least 6 different types of surveillance used to verify operability of Reactor Trip System instrumentation.
List 5 of the surveillance techniques / methods. (1.5) b.
Indicate WHY the following IS or IS NOT allowable or required' 1
At 50% power with one power rance channel inoperable, surveillance is performed on another power ranae channe)..
(0.5) 2.
With power at 1% during startup, an i nt e r ?.ne d i at e range channel fails.
The reactor is shutdowi) for instrument repaire.
(0.5)
QUESTION 8.10 f2.50) c.
During Unit 1 icw power physics testing, it is discovered that the vklue for -the Moderator Tempe#ature Coefficient (MTC) is slightly pusitive in violation of the ' L-l.mitir.g Condit ion f or Operation (LCO).
How does the action st atement specif y that the problem b4 corrected AND how doeq the specified.actioh solve the problem?
(1.0) b.
With reactor power at 10E (-7) amps, RCS temperature is observed to be 558 deg's F.
Explain why the plant is in an LCO and what action is initially required by the action statement.
(1.0) c.
What ere 2 LCO's applicable for a simultaneous loss of all charging pumps with the reactor critical?
(0.5)
L
]
(***r*
END OF CATEGORY 08 *****)
(** swr ******re END OF EXAMINATION ***************)
51__IBIQBY_QE_NVQLE88_EQWEB_EL8HI_QEEB8Il0Nt_ELulD$t_6NQ PAGE 17 IBEBdQQ1N85103 ANSWERS _- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 5.01 (1.50)
NO (0.5) EITHER: Only necessary for source range indication (cr verification of instrument operation) while performing a reactor startup. (1.0)
OR; Many other sources of neutrons available for this purpose (conmic, intrinsic, decay, etc.)
(1.0)
(1.5)-
REFERENCE
'STP Rx Theory, Ch 6, Pu 3,4 ANSWER G.02 C2.50) a.
M:
The ratio of the total number of fission and source neutrons to the total number of neutrons which would exist due to the source only.
(Accept any valid descrip-tion of the multiplyin0 effect on sou.rce neutrons.)
(0.75) b.
As Keft approaches 1, M approaches infinity and cannot be used.to predict critica'lity graphically.
(0.75) 500 eps (1.0) 100(5) c.
CR =-10D(1-0.95 / 1-0.09)
=
=
. REFERENCE STP Rx Theory, Ch.6, Pp.6,8 I'
ANSWER 6.03 (2.001 Ccafficient becomes more negative (0.8) due to changes in coolant i
dOnsity affecting neutron migration length and causing more neutrons
~
to be abscrbed by rods.CO.75)
Albo changes surface / volume ratio and offectively increaces leekage directly affecting MTC. [0.75)
(2.0)
REFERENCE STP Theory, Ch.
8, P.
10 l
l l
k Ll_
5
- ,, b =
l J h> ) j?p 11__In08 QE_NMQLE68_EDWEB_EL6NI_QEEB6IlQNz_E IQ1 6NQ PAGE 18-ItiEBdQQXNad1G1 h- % T n
'd, f
. ANSWERS _- SOUTH TEXAS 1 86/07/23-WHITTEMORE, J.
~
!- I J
- a
. i :- /
lY f
l l
i L'
,. ** ([
,\\'
j Ji/*
ANSWER 5.04 i( 1.pn ) - / " i '
y/
v
. ;~
\\
tr
'y c.
INCREASE
- /' } - (I 'ry
- I.
L ' 1. e s 1
t-f 3
z b.
MORE NEGATIV5 V
f l
,1~
NO CHANdE (0.5 es.Y '
(1.5)j c.
t g
,.s t-l l ?.
REFERENCE STP Rx Theory, Cd. 13, Pp. 13,13 &
.s
-ANSWER 5.05 (2[00) i x-
-(2) Core ' axial flux prcifile. [0.75)
Rod vofth is most affected by the flux seen-at.it's tip (0.75) and the DRW curve depicts unit worth at varying elevations in the core.'[0'.53 (2.0)
-t)
. i, e
',L
- REFERENCE
')
STP-Rx Theory,.Ch.11, P.7 3
4 f-i ANSWER
- 5. 06' (2.50) i 4,
s.
1.
Sufficient to provide rapid shutdown. [0.53 2.
Sufficient.to limit a~oluble boron concentration for MTC considerations.'(0.53 (1.0) b.
Provides for a more uniform reactivity addition rate.
(0.75) c.
There is more control area available for the same mass of poison.
.(providing more uniform flux' suppression)
OR Limit offects of water hole peaking.
(0.75)
REFERENCE STP Rx.' Theory, Ch. 11, Pp. 3,4,9 1
s
,.,-y-yy
<, =
,7
111__IBh0Bl_QE NUCLE 88_EQWEB_EL8HI_QEEB8110Nt_ELVIQat_8NQ PAGE 19 IHEBdQQ1Ned101
-ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER' 5.07 (3.00) e.
1.
I-135 varies linearly with power level [0.51 as subject to removal only by radioactive decay. [0.25]
2.
Xe-135 does not very linearly-[0.25] as it is subject to removal by decay [0.25] and burnout. [0.25]
(1.5) b.
Xenon instability can result in high local heat generation and possible fuel failure.
(0.75) c.
Increasing power can cause-increased burnout prior to building to a new equilibrium level.
(0.75)
=
REFERENCE STP_Rx. Theory, Ch. 9, PP.6-8 ANSWER 5.08 (2.00) c.
FCT-increase: [0.5].
Corrosion and crud buildup will increase the overall resistance to heat transfer [0.5].
(1.0) b.
FCT Increases (0.5].
Densification results in fuel shrinkage and an increase in the gap between the fuel pellet and the clad, OR; Migration of fission gasses from pellets to the gap. [0.53 (2.0)
REFERENCE GP HT & FF, P 237-239 ANSWER H5.09 (2.50) c.
False b.-
False c.
False d.
False e.
True
[0.5 ea.]
(2.5)
REFERENCE STP HT&FF, Pp.322,323
. ~.
iii__IB'EQBl_QE_NMGLE88_EQWEB_EL8HI_QEEB8IIQNi_ELWIQ1t_6NQ PAGE' 20 IBEB5001N85191
> ANSWERS -- SOUTH TEXASL1
-86/07/23-WHITTEMORE, J.
' ANSWER; 5.10 (2.50)-
a.
Perform a-host balance calculation across'the regenerative heat exchanger by using delta.T across both side of HX'and letdown flow rate to determine charging' flow rate.
OR Chg.EFlow = L/D Flow i
+' Seal Leskof f - Seal Inj ection, with Tavg. and Pzr. level c onst. ant..
~(1.0) b._
l.
Increase'[0.25] as/the slower pump spee'd will decrease flow friction losses. [0.25]
(0.5) 2.
Increase [0.25] as RCS pressure-has increased.-[0.25]
(0.5) 3.
Increase [0.25] as pump inlet temp. has decreased. [0.25]
(0.5)
( Accept other viable answers if correct assumptions are stated to yield the answer.)
LREFERENCE GP Theory, Pp. 243, 319-334 i
ANSWER 5.11 (3.00) e.
Due-to the-decrease in pressurizer temperature / pressure the system is voiding _elsewhere [0.75] and forcing-coolant into~the -
- pressurizer. [0.75]
(1.5) b.
The lower line rupture is more severe (0.75] as the~ mass loss of water to greater than thermass loss of steam. [0.75]
.OR Upper may be more severe considering f alse indicating;1evel [0.75]
accounting for improper or inadequate operator or auto action,-
' depending on stated assumptions. [0.75]
(1.5) 4 REFERENCE.
GP Theory, Pp. 355-358 h
i
l 61__EL'6NI_111IEdi_DE11GNt_QQNIBQLt_6NQ_INSIBudENI6I1QN PAGE' '21 ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 6.01 (2.50) c.-
- 1. - Overspeed 2.
Generator differential 3.
Loss of'125 DC control. power.
4.
Low Oil Pressure Trip
[0.25 ea.]
(1.0)-
b.
Mode 1 --
Occurs for SI/LOCA [0.25]
D/G starts (does not close in on bus or-pick up any load)
[0.25]
(0.5)
(0.5)
Mode 2 --
Occurs for UV/ loss of off site power. [0.25]
D/G starts, loads are shed, D/G breaker. shuts, loads sequenced on bus. [0.25)(0.5)
Mode 3 --- Occurs for UV/ loss of offsite power and SI/LOCA [0.25]
same action as above but with different order of load sequencing
[0.25]
(0.5)
REFERENCE LP, D/G, Pp.3,4 ESF Pp.20,21 ANSWER 6.02 (2.50) a.
Low power interlock (C-5). [0.25]
Auto control is erratic at lower power levels.
[0.25]
(0.5)
Bank "D" withdrawal limit (C-11).
[0.25]
Prevents misalignment of group demand counters.
[0.25]
(0.5) b.
Turbine runback (0.5) c.
C-1 (Intermediate Range) rod stop can be manually blocked when_P-10 above setpoint.
C-1 can be defeated by IR Level Trip Bypass switch.
C-2 (Power Range) can be blocked or defeated by use of the " Rod Stop Bypass Switch" on NI panel.
[Any 2 of 3,
0.5 ea.]
(1.0)
REFERENCE SD, ROD CNTRL, Pp. 25,26 l
l
hi__EL'8NI_111IEMS_QE11GNt_QQNIBQLt_8NQ_INSIBUMENI6IIQN PAGE 22 ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 6.03 (2.00)
~4.
o.
b.
6.
3.
c.
d.
9.
o.
7.
2.
[6 answers e 0.33 es.]
(2.0) f.-
REFERENCE LP, PZR, SECT 1.3.1 P.17 7
ANSWER 6.04-(2.50) e.
1.
- 1 Seal Water leakoff.
2.
Excess Letdown.
3.
CCP miniflow recire. line.
[0.25 ea)
(0.75) b.
Normal
[0.25]
is to Charging Pump suction
[0.25]
Alternate is to VCT.
[0.25]
(0.75) c.
Orifice Isolation Valves cannot be opened unless Letdown Isolation Valves are open, OR; Letdown Isolation Valvos may be closed if all Orifice Isolation Valves are closed or close permissive activated.[0.5]
The interlock is to ensure RCS pressure is kept on the regenerative heat exchanger to prevent flashing-and HX damage.
[0.53 (1.0)
61__EL'6NI_111IEd1_DE11GNt_GQNIBQLt_6ND_INSIBudENIeIIQN PAGE 23 ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
-ANSWER 6.05 (3.00) e.
BORATE, DILUTE, and ALTERNATE DILUTE. (0.33 ea)
-(Accept "0FF" for no credit)
(1.0) b.
' Boric Acid Batch controller.
(0.5) c.
1.
Initiated by VCT low level.
(0.25) 2.
Auto Action:
o RMVP starts o-BAT pumps start o
Valve to chg. pump suct. hdr. (FCV 1108) opens.
o B.A.
flow control valve CFCV 110A) throttles to deliver preset flow.
o P.W.
flow control valve (FCV lilA) throttles to deliver preset flow.
(0.25 es. action]
(1.25)
REFERENCE LP, RMUS, Pp.17-19, 24 ANSWER 6.06 (2.50) e.
To ensure that a minimum flow is maintained (0.5) to eliminate boron and temperature stratification. (0.25)
(0.75) j b.
The RHR inlet headers are tapped off the RCS hot legs below centerline to allow operation with loops partially drained.
(0.75) c.
1.
SI Signal 2.
Undervoltage (accept loss of power) 3.
Phase overcurrent 4.
Low discharge flow 5.
Control transferred to local with local switch'in "Stop".
(Any 4, 0.25 es.)
(1.0)
l
6'__EL'6NI_SISIEd1_DESIGNt_GQNIBQLt_6NQ_IN11BudENI611QN
'PAGE 24 ANSWERS --' SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 6.07 (2.00) c.
During normal operation the LHIS may leak or temperature may change partially voiding the system. (0.5)
A positive head is maintained on the system by the RCP #3 seal standpipe.
[0.5)
(1.0)
'b.
The. low head pumps must be stopped.-OR Reduce RCS pressure. [0.5)
When system auto shifts to cold leg recirculation, the miniflow recirc valves on the pumps shut (0.25) and there is no flow through the pumps due to high system pressure.
(0.25)
(1.0)
REFERENCE LP, ECCS, Pp. 3,5 ANSWER 6.08 (2.50) e.
1.
Correct lineup 4.
Seal return flow 2.
VCT pressure 5.
Seal inj ect. flow 3.
Water return filter d/p 6.
Seal d/p (Any 3, 0.33 ea.)
(1.0) b.
1.
CCW piping to and from RCP's-is designed for high pressure.
2.
Check valve on inlet prevents prevents back leakage into CCW system.
3.
Motor operated valve on outlet auto shuts on high temperature or flow.
[0.5 each)
(1.5)
Accept for no credit:
Relief valve protects isolated piping from overpressure due to heating.
REFERENCE LP, RCP, Pp.10,17 ANSWER 6.09 (2.00) c..
(P-15 in coincidence with other conditions can result in blocking or enabling:
1.
FW isolation (0.5) 2.
Safety Injection 0.5) b.
1.
P-7 uses P-10 & P-13 (0.5) 2.
P-15 uses P-4 (0.25) 3.
P-16 uses P-4 (Interlock names acceptable)
(0.25)
6L__EL'8HI_111IEd1_QE11GNt_QQNIBQLt_8NQ_IN11BudENI8110N' PAGE 25 ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.-
REFERENCE LP,'SSPS, P.
19 4
ANSWER 6.10 (2.50) a.
Speed increases (0.53 because the FRV will open causing feed header pressure to decrease, increasing dp between steam and feed headers, i
(0.25] and Total steam flow signal also increases. [0.25]
Also
- accept for full credit:
-There may be little or imperceptible change if max. d/p already exists.
(1.0) b.
Low failure will more likely result in protective action. [0.5]
The maximum flow rate that can be seen by the system is (133%).so a net feed flow error of (33%) will be seen-and is correctable by level error
- signal. (0.5]
A low failure.results infan error of (100%) and will not' be corrected by level error deviation before a protection setpoint has been exceeded. (0.5]
(1.5) i REFERENCE LP, SGLCS, Pp.30,31 ANSWER 6.11 (1.00)
(The flow is assumed to.be' constant) and several trips exist to provide i
protection for loss of flow. [0.5)
Changes in. flow cause changes in tamperature, which is an input. [0.5]
(1.0)
)
,-w-,
-g-,.
- y-..r-,,,,.,,w, ww,.y,#.
,.pgm,m%
,., ween
.eww_wp w,y,.9_,,,,y,
+ww
.,--,9
_g
-w,y g
9 9
7
Z1__Ef0GEQuBE1_:_NQBd8Li_8ENQBd8L&_EMEBQENQ1_8NQ PAGE~ 26 88DIQLQQIQ8L_QQNIBQL LANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 7.01
-(2.50)
-e.
2004, 3504 (1.0) b.
200 dog's (0.5) c.-
30 minutes (0.5).
'd.
0.2 GPM C0.5)
REFERENCE LP, RCP, P.13 ANSWER 7.02 (1.50) c.
1.
Charging-flow (Pzr Level) control valve (1* FCV- 0 2 0 5 )
2.
Letdown pressure control. valve (1*PCV-135)
(0.5 ea)
(1.03-b.
1.
Increase
'2.
Increase 3.
Decrease (0.25 es.)
(0.75) c.
Divert' letdown flow from demineralizer (0.5] as demineralizer may release undesirable ions and resin may deplete.
[0.25]
C0.75)
REFERENCE 1-POP 3-ZG-01, Pp4,5,8, i,
I i
Z1-_ESQQEQWBES_:_NQBdekt_6BNQBd6L&_EMEBGENQ1_8NQ PAGE 27 88010LQE1Q8L_GQNIBQL ANSWERS -- SOUTH TEXAS 1-
-86/07/23-WHITTEMORE, J.
ANSWER 7.03 (3.00) e.
- 1. '
If_the Reactor Coolant temperature and boron concentration are being maintained at the hot shutdown, Xenon-free condition.
(0.5) 2.
If the Reactor Coolant has been borated to the cold shutdown, Xenon free concentration.
(0.5) b.
1.
Alarms (urgent and non-urgent failure) reset.
2.
Step counters reset.
(0.25 ea.)
Accept mention of other components that may be affected by switch for no credit.
These include: Master cycler, Slave cycler, P/A converter, Bank overlap unit.
(0,5) c.
1.
Continue startup 2.
Insert rods to a position 500 PCM below ECP.
3.
Borate to clear annunciator.
(0.5 es.)
(1.5)
REFERENCE 1-POP 3-ZG-04, Pp. 2,4,7,8 ANSWER 7.04 (1.50) e.
Fuel conditioning limits.
(0.75) b.
Turbine Generator loading limits.
(0.75)
~ REFERENCE 1 POP 03-ZG-0008, Pp.2.16 ANSWER 7.05 (2.00) e.
2 b.
Adj ust turbine load (0.5) AND/OR bore., concentration.(0.5]
(1.0)
REFERENCE 1-POP 4-RS-01, Pp 1,2
Zi__EBuQEQUBZ1_=_NQBueLt_6BNQBd6Lt_EMERGENQX_8NQ PAGE 28 88010LQQ108L_QQNIBQL ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 7.06 (3.00) c.
Steady b.
Increase c.
Decrease d.
Increase
-o.
Steady (or increase if S/G relief assumed open) f.
Decrease
[0.5 ea.]
[3.0)
REFERENCE STP QUESTION BANK, P.98 ANSWER 7.07 (2.50) s.
[0.25 es.)
(1.0) e.
1.
Steam Dump. [0.25]
Possible release of radioactivity. [0.25]
2.
Backfill.
[0.25]
Adverse-RCS chemistry and dilution of boron.[0.25]
3.
Blowdown.
[0.25]
Process and storage of radioactive waste.
OR Contamination of secondary systems.
[0.25]
(1.5)
REFERENCE STP QUESTION BANK & E030, Pp.2,3 i
1
,,--,,,....y, y..
Zi__EdQGEQWBE1_=_NQBd8Lt_8BNQBd8Lt_EMEBGENGl_8NQ PAGE 29 88Q10LQQIG8L_GQNIBQL
-ANSWERS-- ~ SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 7.08 (2.50) 4 o.
Low level to accommodate void growth.
(0.75)
High level to prevent pressurizer from emptying.
(0.75)
-b.
May form voids in loops OR RCS (0.5) c.
Provide normal pressurizer spray.
-(0.5)
REFERENCE iPOP05-E0-ES03, Pp3,4 l
ANSWER 7.09 (2.50) c.
1.
Manually trip from MCP i
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 (0.5)
REFERENCE 1 POP 05-E0-FRS1, Pp4,6,9 ANSWER 7.10 (2.00) e.
- 2 **
(0.5) b.
Relative dose rate. [0.5) GM Tubes are more sensitive to lower dose rates (or equivalent answer). [0.5)
(1.0) c.
ACCEPT EITHER:
Faster counting, OR Energy sensitive (0.5)
REFERENCE HP MAN., Pp. VI-2.10 & VI-6.8,9
'l
.r.
m,.
.7,
_.,w-_.m-.,--,--
.r,-.,
v-
..m,..
s-.-
I LZi_iEHQQEQuBER_=_NQBM8Li_8BNQBM8Lt_EMEBEENQ1_8NQ
'PAGE 30 B8010LQQIQ8L_QQNIBQL ANSWERS -- SOUTH. TEXAS 1
-86/07/23-WHITTEMORE, J.
i ANSWER
- 7.11' (1.00)
A3 water level in the refueling cavity is raised, the vessel head is reised j ust above the water level until there is sufficient level to provide shielding.
(1.0)
REFERENCE LP, REFUEL. SYS., P.64~
l 4
i l
2
m Ri_'BDMINIRIB8IIVE EBQQEQWBEft_QQNDIIIDNit_8NQ_LIMII6IIQNA' PAGE.
31 ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 8.01
-(3.00) o.
1.
ORG's 2.
FRG's-3.
CSFST's (0.33 es.)
(1.0 b.
ES--Supplements E series by providing alternate recovery action. (0. 5).
ECA-Supplements E and ES series by providing guidance for low probability or unique event scenarios.
(0.5) c.
Can overpressure RCS. OR Modes 5 & 6 are outside conditions assumed by procedures.
(0.5)
L d.
Red Path Summary, AFW Flow, SI Init./Reinit. criteria (Any 2, 0.25 ea.)
(0.5)
REFERENCE LP, INTRO. TO E0P'S, Pp.5,6 ANSWER 8.02 (2.50) e.
_l.
Decisions concerning offsite notification.
2.
Approval for disseminate information for public release.
3.
Approval for exceeding 10CFR 20 exposure limits..
4.
Approval for entry into evacuated areas.
5.
Approval for offsite protective action recommendations.
(Any 4, 0.25 ea.)
'C1.0) b.
1.
Emergency Director------------------------
EOC 2.
Shift Supervisor--------------------------
MCR 3.
Plant. Operations Manager------------------
MCR C0.23 ea.)
(0.75) c.
1.
TSC Manager i
2.
Plant Operations Manager 3.
General Services Director 4.
Radiological Manager (Any 3, 0.25 ea.)
(0.75)
REFERENCE STP EP, P.C-9 & FIG. C.3 I
_-._m.
__ _-,.~.-_-_.. _. _, - -.. -.. -
Ri_'BQMIN11188IIVEiEBQQEQUBEli_QQNQIIIQNS&_8NQ_ lid 1I8I1Q'N1 PAGE 32
' ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 8.03 (2.00)
BARRIER STATUS CLASSIFICATION No barrier lost or challenged NOTICE OF UNUSUAL EVENT 1 Barrier lost or challenged ALERT 2 Barriers lost or challenged SITE AREA EMERGENCY 3 Barriers lost or challenged GENERAL EMERGENCY
[0.5 EACH]
(2.0)
REFERENCE STP EP, TABLE D-1, P.2 ANSWER 8.04 (2.00)-
c.
There are Interface Agreements in effect detailing who operates specific systems or component parts of systems.
(1.0) lb.
Conflicts are initially resolved by the Shift Supervisor. [0.5)
Division Managers are required to follow up and institute a final policy. (0.5]
(1.0)
REFERENCE OPGP03-20-0004, P.10 1
ANSWER 8.05 (2.50) c.
Electrical or mechanical j umpers are bright orange wire or orange striped tubing or pipe. [0.5]
Temporary Devices or conditions are accompanied by a bright orange tag. [0.51 (1.0) t b.
The designated verifier. (Allow 1/2 credit for SS or requestor)
(0.5) c.
The Shift Sup9rvisor verifies (0.5] and he may verify by visual inspection (0.25] or functional check. (0.25]
(1.0)
1 Ai_'_BQUIN11188I1YE_EBQQEQWBEli_GQNDIIIGNat_8NQ_LIMII8IIQNS PAGE 33 ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
-REFERENCE OPGP03-ZO-0003, Pp.3,7 ANSWER 8.06 (3.00) c.
Clearance Book No. 3 is for clearances on equipment under the cognizance of the Chemistry Operations.and Analysis Superintendent.
[0.5]
Book No. 4 is for equipment under control of the Maintenance Superintendent. (0.53 (1.0) b.
No. (0.25]
Verification is intended to be a separate, independent, and redundant activity.
(0.25]
(0.5) c.
1.
Vent and/or drain piping runs which are to be isolated by the clearance.
2.
Disable prime movers (motors, turbines, etc.) prior to isolating 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 5.
Tag all active operating mechanisms (valve operators, MOV breakers, etc.).
6.
When restorir
'luid systems, avoid any condition that may cause water hammer.
(Any 3, 0.5 es.]
(1.5)-
REFERENCE OPG3-ZO-1, Pp. 3,8,18 ANSWER 8.07 (3.00)
Yes (3.7.1.3) o.
No b.
No q.
Yes (3.2.41 c.
Yes (3.7.11) h.
Yes (3.3.3.)
d.
No 1.
Yes (3.4..',
o.
No j.
No (0.3 ea.)
(3.0)
REFERENCE STP T.S.
as indicated above.
.G.
J
r fi_*_BQd1UISIBBIIVE_EBQQEDVBEtt_GQUD11100S _aND_L101I611QUE PAGE 34 t
ANSWERS -- SOUTH TEXAS 1
-86/07/23-WHITTEMORE, J.
ANSWER 8.08 (2.00) c.
Based on not exceedinD 10CFR20 exposure limits [0.5) at the site boundary following ran STGR. [0.51 (1.0) b.
Chemistry is contrclied to minimize corrosion. [0.33]
Corrosion is time dependent. [0.33]
Higher limits allow time for restoring steady state limits. [0.33]
(1.0)
REFERENCE STP QUESTION BANK, Pp.80.01 ANSWER 8.09 (2.50) c.
1.
Actuation logic test 2.
Analog channel operational test 3.
Channel calibration 4.
Channel check 5.
Reeponse time check G.
Trip actuating device operational test
[Any 5, 0.3 ea.]
(1.5) b.
1.
Allowable (0.25] as an inoperable channel may be bypassed to allow performance of surveillance on another channel. [0.25)
(0.5) 2.
Allowable but not reouired [0.25] as power may be increased to P-10 before channel is restored. [0.25]
(0.5)
REFERENCE STP T.S.,
TABLES 3.3.1 & 4.3.1
y Hi_*_B0 DIN 11IB6IIVE_EBQQEQUBEft_QQNQ1I19N1t_6NQ_ lid 1I6119N1 PAGE 35 ANSWERS -- SOUTH TEXAS'1
-86/07/23-WHITTEMORE, J.
ANSWER 8.10 (2.50) c.
Insert rods (0.5) as rod insertion will require boron concentration be diluted OR, increase neutron leakage which will make MTC more negative. [0.51 (1.0) b.
The plant is in an unanalyzed condition (less than the minimum. temp.
for criticality).[0.5)
Must be at 561 deg's within 15 minutes or in hot standby within the next 15 minutes. [0.5]
(1.0) c.
1.
Require 2 charging pumps (in modes 1,2,and 3). [0.25]
2.
' Require 2 boron flow paths (in modes 1,2, and 3).
(0.25)
(0.5)
REFERENCE STP TS.3.1.1.3, 3.1.1.4, 3.1.1.2, 3.1.2.4 i
I
TEST CROSS REFERENCE PAGE 1
QUESTION VALUE REFERENCE 05.01 1.50 WJE0000539 05.02 2.50 WJE0000542 05.03 2.00 WJE0000546 05.04 1.50 WJE0000540 05.05 2.00 WJE0000543 05.06 2.50 WJE0000547 05.07 3.00 WJE0000550 05.08 2.00 WJE0000535 05.09 2.50 WJE0000553 05.10 2.50 WJE0000557 05.11 3.00 WJE0000554 25.00 06.01 2.50 WJE0000669 06.02 2.50 WJE0000670 06.03 2.00 WJE0000671 06.04 2.50 WJE0000672 06.05 3.00 WJE0000673 06.06 2.50 WJE0000674 06.07 2.00 WJE0000675 06.08 2.50 WJE0000676 06.09 2.00 WJE0000677 06.10 2.50 WJE0000678 06.11 1.00 WJE0000679 25.00 07.01 2.50 WJE0000680 07.02 2.50 WJE0000681 07.03 3.00 WJE0000682 07.04 1.50 WJE00C0683 07.05 2.00 WJE0000684 07.06 3.00 WJE0000685 07.07 2.50 WJE0000686 07.08 2.50 WJE0000687 07.09 2.50 WJE0000688 07.10 2.00 WJE0000689 07.11 1.00 WJE0000690 25.00 08.01 3.00 WJE0000691 08.02 2.50 WJE0000692 08.03 2.00 WJE0000693 08.04 2.00 WJE0000694 08.05 2.50 WJE0000695 08.06 3.00 WJE0000656 08.07 3.00 WJE0000697 08.08 2.00 WJE0000698
- 0 TEST CROSS REFERENCE PAGE 2
QUESTION VALUE REFERENCE 08.09 2.50 WJEG000699 08.10 2.50 W5E0000700 25.00 Gi._ _ _ _ _
100.00 I