ML20211P161
| ML20211P161 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 02/17/1987 |
| From: | Cooley R, Whittemore J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20211P155 | List: |
| References | |
| 50-498-OL-87-01, 50-498-OL-87-1, NUDOCS 8703020307 | |
| Download: ML20211P161 (90) | |
Text
t OPERATOR LICENSE EXAMINATION REPORT No. 50-498/0L 87-01 1
Licensee: Houston Lighting and Power P.O. Box 1700 Houston, Texas 77001 Docket:
50-498 Operator License Examinations at South Texas Project (STP)
Chief Examiner:
G!/3['7 fohnE.Whittemore Date Signed Approved By:
2//7/ h7 R. A. Cooley
{
D&te Signed Sumary Written examinations were passed by 41 of 45 Senior Reactor Operator and 1 (One) of 2 (Two) Reactor Operator applicants that were administered at the South Texas Project training facility during the weeks of July 21 and November 10, 1986. Those candidates passing these examinations were administered operating examinations in January 1987. The results of the operating examinations were 39 of 41 Senior Reactor Operators and one of one Reactor Operator passing the examinations.
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2 STP OPERATOR LICENSE EXAMINATION REPORT Report Details 1.
Examination Results s
SR0 Candidates R0 Candidates Total Pass Fail Total Pass Fail 45 39 2
86.7%
2 1
1 50%
2.
Examiners J. E. Whittemore (Chief Examiner)
B. Haagensen D. N. Graves I. Kingsley S. L. McCrory K. Parkinson J. L. Pellet F. Victor T. Guilfoil G. Weale 4
3.
Examination Report This Examination Report is composed of the sections listed below.
Examination Review Comment Resolution Site Visit Summary Licensee Comments on Written Examination Examination Key (R0 and SR0 Questions and Answers)
Performance results for individual candidates are not included in this 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 or during subsequent grading reviews are not addressed by this resolution section. This section reflects comments and recommended changes to examination answer keys by the licensee. Modifications resulting from these comments and recommendations are included in the master examination keys, which are provided elsewhere in this report.
Unless otherwise indicated in this section, the facility comments were incorporated into the answer key.
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Consents and Resolutions 1.12.a/5.09.a Other correct explanations should be accepted.
For example:
A flow balance between letdown and pressurizer level. Charging flow equals letdown flow plus seal leakoff minus seal injection flow with pressurizer level constant.
Resolution:
Partially accepted and will allow only 1/2 credit for above answer as question solicits theoretical heat transfer and fluid flow conceptual knowledge.
I 2.01.b/6.01.b Voltage regulator should be the only requirement for full credit as the question asks for the alternate power available to the 120VAC instrumentation - not what the power supply to the voltage regulator is.
Resolution:
Not accepted:
" Voltage Regulator" is not specific enough to ascertain applicant's knowledge of power supply.
2.01.c/6.01.c The question asks "What prevents the operator from paralleling AC sources through 120VAC class and non-class busses?" which can also be interpreted as asking how the paralleling of these two busses is prevented. Request that
" Physically and electrically separated" also be allowed as a full credit answer.
Resolution:
Not accepted. Despite separation, which is incorporated into system design for reliability, parallel operation could be obtained if the interlocks were not present.
2.04.b/6.03.b Question does not require the answer to contain the pressure value as does the key.
Resolution:
The coment is invalid as the answer does not require the pressure as indicated by the value being in (parentheses).
2.06.a AFWST using hotwell pump should also be accepted.
Resolution:
Not accepted as the facility could not supply a reference.
4 2.08.b/6.04.b Answers reflecting change of heat loads, operational needs, and seasonal effects should be considered as acceptable, a
Resolution:
These answers will be accepted, but not for credit.
3.01.b/6.06.b Should also accept Computer Room Operator's Console Resolution:
Will accept this answer for no credit as references do not support that this console is available to the operator.
3.03.a/6.07.a Anticipatory / rate of change should also be considered as acceptable.
Resolution:
Noted. Answer already inherent in key.
4.01.b/7.01.b Subsequent step in procedure requires monitoring pressurizer temperature and pressure for saturated conditions. Request answers stating or includimg this be allowed full credit.
Resolution:
Partially accepted. Will accept this answer for 0.25 points as this step does not provide verification that a pressurizer bubble exists, but that conditions are proper for a bubble to exist.
4.03.a/7.03.a Lining up the sample path to the VCT from the pressurizer vapor space is not specifically mentioned in the procedure therefore should not be required for full credit to be obtained.
Resolution:
Licensee withdrew comment.
4.05.a/7.05.a CCW flow should also be accepted as an answer.
Resolution:
Coment not accepted. CCW flow is not a root cause of any changes in RCP motor winding current.
4.05.c/7.05.c Other reasonable indications of seal integrity should be acceptable.
Resolution:
Not accepted.
Indications of integrity will not necessarily disclose an instrumentation problem.
5 4.06.a/7.06.a Procedure also states information on untrippable rods. Request that this be allowed as an additional correct answer. Technical Specifications also provides information to help the operator determine supplementary action.
Resolution:
The first comment is noted and agreed with as this infomation is inherent in the existing answer. The second comment is unacceptable as the operator must know if the rods are trippable in order to choose the correct action statement and simply stating Technical Specifications is not sufficient.
4.07.a/7.07.a No credit should be taken away for not listing RCFC Drains as they have been deleted from Technical Specifications.
Resolution:
Not accepted. Question is about the RCS leak procedure, not Technical Specifications.
4.07.b/7.07.b RM 11 indication is also listed in the procedure as an indication and should be allowed as an acceptable answer.
Resolution:
Not accepted. RM 11 is a microprocessor system that will indicate RCS leakage either inside or outside the containment.
4.10.b/7.10.b Credit should bt allowed for ESF Monitoring Indication as a primary indication.
Resolution:
Not accepted. Procedures do not support this statement.
5.03.b The answer key requires more than the question. The question states " Explain the initial effect on Xenon concentration as power is increased to 100%." The key requires answer to include effects of Iodine. The word " initial" in the question infers that only the effect on Xenon is required for full credit.
Request consideration of this for full credit.
Res~olution:
Not accepted. The word " initial" does not infer ignorance of Iodfre.
Further, any explanation of Xenon behavior requires discussion of Iodine behavior and attributes.
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5.04.a Should accept answer that states less negative due to higher boron concentration.
(i.e., as question infers why the RWST?)
Resolution:
Not accepted. The answer above does not address the theoretical phenomena that the question solicits.
1 S.07.b.
Should also accept maintenance of a negative moderator temperature coefficient as an answer.
Resolution:
Not accepted. The reference is specific that the above is not considered.
i 5.11.a Should also accept answer that states " Stable or decreasing" for steam pressure as used in the STP E0P.
Should also accept i
answer that states that cold leg temperature could decrease with j
time due to losses to ambient for cold leg temperature.
Resolution:
Not accepted. Licensee could not supply specific reference.
5.11.b The STP FSAR gives only one design feature (elevation of heat sink) to enhance natural circulation flow. Request.
l consideration for full credit based on FSAR description.
Resolution:
Partially accepted. Weighted preferred answer more heavily, but i
did not eliminate second answer as theory reference does not support above contention.
i 6.06.c The referenced text does not refer to " modes of display" for the l
RMS Ril.
Request consideration of answers reflecting function i
j keys and system capabilities to be acceptable.
j, Resolution:
Comment is noted. Grader will allow credit for answers reflecting knowledge solicited in question.
6.10.b The words "just below" in the question can be interpreted as requiring only the signals that are enabled by P-11 vice all other protection that is always available. Request consideration of this for full credit answer.
Resolution:
Not accepted. The question is designed to ascertain applicant's knowled e of protection available and any other interpretation is illo ical.
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7 8.02.a Full credit should be given for recognition of LCO non -
compliance on SG gallons per day basis.
Resolution:
Not accepted. Question specifically asks WHY the values are IN or NOT IN compliance.
8.07.d Procedure states SS or STA. Request full credit be given for either response.
Resolution:
Not accepted. Both have responsibility.
8.08 Question is confusing as radiological incidents are addressed in several other procedural areas.
Full credit should be allowed based on student assumptions; i.e., Emergency Plan, Health Physics procedures, etc..
Resloution:
This question is being deleted due to ongoing confusion as to the significance of the referenced terms. The licensee is advised that the referenced procedure should be revised if these terms are to remain insignificant in the administration of the facility's Radiological Protection Program.
h 8
b.
Site Visit Sumary At the end of the written examination administration, the licensee was provided a copy of the examination and answer key for the purpose of comenting on the examination content validity.
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 comitments, this goal may not be attainable.
At the end of the four week period when Operating Examinations were administered, two examiners met with the facility staff to discuss the completion of the examination process for cold licensing, note any generic weaknesses or problems uncovered during the examination process, and answer questions from the facility staff.
The following personnel were present at the meeting.
NRC LICENSEE J. Whittemore (Chief Examiner)
W. Kinsey J. Pellet M. McBurnett J. Walker G. Weldon Mr. Whittemore opened the meeting by expressing appreciation to the licensee staff for the cooperative and enthustic attitude demonstrated during the entire examination process. He also comitted to the finalization of results as soon as possible. The following probleins and generic weaknesses uncovered by the examiners were noted to the licensee.
1.
Candidates generally exhibited limited knowledge in the use and operation of the Radiation Monitoring Microprocessor system (RM-11) and the control room Dose Assessment Computer System.
2.
There is much confusion about how the operator is to order the manipulation of protection trip and interlock bistables subsequent to the failure of nuclear and non-nuclear protection instrumentation.
Procedures need to be develosed to give the operator guidance in exercising control over t1e manipulation of these bistables.
3.
Candidates were unsure how protection channel trip signals were reset.
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4.
Several candidates were confused about the purpose and proper sequence of the gain units that provide signals for automatic control rod positioning.
i 5.
Virtually all candidates had no knowledge about local neutron indication on the Auxiliary Shutdown Panel and several could not discuss the effects of Transfer Switch position on equipment interlocks and protective features. During the examinations there was no procedure available for operating the Remote Panel.
^
6.
A number of candidates had no knowledge of the default protective action recommendation guidelines to implement in case of problems in obtaining a valid dose assessment. A problem in mechanics of 15-minute notification was noted as candidates differed in response as to how many individuals they were talking to during initial notification.
7.
Shift turnover documentation is inadequate at present.
8.
The examiners felt that there is a lack of common philosophical approach by the licensee in providing guidance to operators in tie handling of emergencies that fall outside the bounds of the Emergency Response Guidelines (mode 4 and below).
In conclusion the examiners voiced the opinion that candidate knowledge and use of EPIPs was good.
It was also noted that use and interpretation of Technical Specifications were generally precise and conservative. The licensee asked about the scheduled date of the first NRC administered requalification examinations and were told that no schedule determinations had been made at this time.
c.
LICENSEE COMMENTS The facility staff comments on the Reactor Operator and Senior Reactor Operator written examinations follow. Those coments not addressed in the comment resolution section have been accepted and integrated into the examination answer keys, d.
EXAMINATION MASTER COP _Y The Reactor Operator and Senior Reactor Operator Master Examination and answer keys follow the licensee coments and constitute the remainder of this report. Changes resulting from licensee comments are reflected in these keys.
9 COMMENTS ON THE NRC R0 AND SRO EXAMINATION SECTION 1.0 1.05 a.
Other correct definitions should be accepted.
For example:
The combination of the source neutrons and induced fissions in the subcritical reactor produces a neutron population higher than the source neutrons alone.
1.00 a.
Correct solutions using viable assumptions for the values of beta bar off (whether BOL or EOL) and landa should be accepted for full credit.
Training references use values of.0075 to
.0044 for beta bar eff BOL to EOL respectively and.08 to.1 for landa.
b.
Acceptable range for answer solution should be up to 10% power considering reasonable assumptions.
1.10 c.
The answer key requires a restatement of " Increasing Power [.251" which was given in the question.
The key also requires building to a new equilibrius which was not asked for in the question.
A correct explanation of burnout initially exceeding production on an up power transient should be acceptable.
1.12 a.
Other correct explanations should be accepted.
For example A flow balance between letdown and pressuriser level.
Charging flow equals letdown flow plus seal leakoff einus seal injection with pressurizer level constant.
SECTION 2.0 2.01 b.
Voltage Regulator should be the only response required for full credit as the question asks for the alternate power available to the 120 VAC instrumentation - not what the power supply to the VR is.
c.
The question asks "What prevents the operator from paralleling AC sources through 120 VAC class and non class buses?" which can also be interpreted as asking how the paralleling of these two buses with each other is prevented.
Request that ' Physically and electrically separated" also be allowed as a full credit answer.
2.02 b.
Low oil pressure (engine and turbo) should also be counted as an acceptable answer.
References T/S 4.9.1.1.6C p. 3/4 0.5 Control power in D.C..
2.03 b.
Alternative answer stating that accumulators inject a large values of water for core cooling due to syntes pressure being greater than LHSIP shutoff head should also be an acceptable answer.
2.04 b.
Question does not require the answer to contain the pressure value as does the key.
2.05 b.
The question is aisleading as it asks "... how the SGFWPT vacuum trip can vary during the course of startup or shutdown?" The variance of the trip set point only occurs during startup.
When initially latching the turbine if vacuum is less than 14 inches Hg the trip set point is 3 psig.
When vacuum increases to 20 inches Hg the trip is auto reset to 14 inches Hg.
2.06 a.
AFWST using hotwell dump pump should also be accepted.
b.
" Adequate suction pressure" should also be allowed as an acceptable answer.
References logic drawing 9-Z-40091.
2.07 a.
The answer key requires more than the question.
The question asks for a description of CWP runout protection and does not infer that setpoints for the CW valve limit switches are required for full credit.
Request CW valve set points not be included as a requirement to obtain full credit for this question.
2.00 b.
Answers reflecting change of heat loads, operational needs, and seasonal effects should be considered as acceptable.
c.
Another acceptable answer should be ECW traveling screeens and wash pumps start as they receive a start signal on Safety Injection.
2.09 b.
RHRP relief should be removed from required answer as the RHRPs recieve a trip signal on a SI and are not running.
References logic drawing 9-2-42100.
2.10 c.
There is no CCW surge tank vent per P&lD drawing 9-F-05017. The tank is normally pressurized with nitrogen and inleakage to the system will raise tank level until it lifts the tank relief to the CCW sump.
Request credit for an answer that reflects this type of response.
SECTION 3.0 3.01 a.
Another correct answer is the Condenser Air Removal Systen exhaust process monitor with no automatic actions.
The answer key is in error for the condensate polishing effluent monitor automatic action causing isolation of the polishers.
The correct response is automatic isolation to the neutralization basin.
b.
Should also accept Computer Roon Operators Console.
c.
The referenced text does not refer to " modes of display" for the RMS Ril.
Request consideration of answers reflecting function keys and system capabilities to be acceptable.
3.03 a.
Anticipatory / rate of change should also be considered as acceptable.
3.06 a.
Request other answers stating allowance of control rods to be withdrawn during cooldown/ shutdown with the pressurizer water level greater than 92% (ie. solid operations for rapid refueling, testing, or maintenance) be considered as acceptable.
3.00 a.
The answer key requires more than the question.
The question only requires that the response explain that the signal is processed through a PID circuit / anticipatory rate to answer the question.
Request explanation of PID/ rate circuit also be given credit.
3.09 a.
The charging flow control valve in the STP CVCS receives a signal from actual charging flow to ensure ainlaus flow through the regenative heat exchanger.
The charging flow control valve dcas not supply the RCP seals.
The seals are supplied through a different valve HCV218 which is controlled by the operator.
Request full credit be given for stating minlaus flow to regenative heat exchanger.
SECTION 4.0 4.01 a.
Additional procedures require ainlaua charging flow to cool the regenative heat exchanger.
b.
Subsequent step in procedure requires monitoring pressurizer temperature and pressure for saturated conditions.
Request answers stating or including this be allowed full credit.
4.02 d.
Based on plant conditions procedural allowance is granted for switching items 5 and 2.
Request credit be allowed for this.
4.03 a.
Lining up the sample path to the VCT from the pressurizer vapor soace is not specifically mentioned in the procedure therefore should not be required for full credit to be obtained.
4.04 4.
Procedure states "... evacuate the immediate area
- which would also be an acceptable answer.
Crodit should be given for Containment Ventilation Isolation c.
which is generated from the associated rad monitors.
Containment Ventilation Isolation does all three items listed in the answer key.
4.05 a.
CCW flow should also be accepted as an answer.
b.
Request other reasonable answers be allowed credit such as a leak in the seal standpipe supply line.
Other reasonable indications of seal integrity should be c.
acceptable.
4.06 a.
Procedure also states information on untrippable rods.
that this be allowed as an additional correct answer.
Request Technical specifications also provides information to help the operator determine supplementary action.
4.07 a.
No credit should be taken away for not listing RCFC drains as they have been deleted in Technical Specifications.
b.
RMll indication is also listed in the procedure as an indication and should be allowed as an acceptable answer.
4.08 a.
Alternative answers should be considered based on the extent of contamination ie, whole body / body location.
b.
- 1. Alternative answers should be considered based on student i
assumptions and regulations applied, le 10CFR20.
4.10
- b. Credit should be allowed for ESF Monitoring Indication as a primary indication.
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o SECTION 5.0 5.02 a.
Correct solutions using viable assumptions for the values of beta bar eff (whether BOL cr EOL) and landa should be accepted for full credit.
Training references use values of.0075 to
.0044 for beta bar eff BOL to EOL respectively and.08 to.1 for
- landa, b.
Acceptable range for answer solution should be up to 101 power considering reasonable assumptions.
5.03 a.
Should also accept answers that explain that a slight change in Samarius concentration will occur during the power change but will return to the same value when at the new steady state power level.
b.
The answer key requires more than the question.
The question states " Explain the initial effect on Xenon concentration as power is increased to 100%".
The key requires answer to include effect of lodine.
The word " initial" in the question infers that only the effect on Xenon is required for full credit.
Request consideration of this for full credit.
5.04 a.
Should accept answer that states less negative due to higher baron concentration.
(ie. as question infers why the RWST?)
5.05 Description using a full core discussion vice upper and lower core should be acceptable.
5.07 b.
Should also accept maintenance of a negative moderator temperature coefficient as an answer.
5.09 a.
Other correct explanations should be accepted.
For example:
A flow balance between letdown and pressurizer level.
Charging flow equals letdown flow plus seal leakoff minus seal injection with pressurizer level constant.
5.11 a.
Should also accept answer that states ' Stable or decreasing" for steam pressure as used in the STP E0P.
Should also accept answer that states that cold leg temperature could decrease with time due to losses to ambient for cold leg temperature.
b.
The STP FSAR gives only one design feature (elevation of heat sink) to enhance natural circulation flow.
Request consideration for full credit based on the FSAR description.
5.12 4.
Descriptions of effects on local HCFs should also be considered as acceptable.
b.
A description of increased flow decreasing HCFs based on increasing the DNBR should also be accepted.
6.01 b.
Voltage Regulator should be the only response required for full credit as the question asks for the alternate power available to the 120 VAC instrumentation - not what the power supply to the VR is, c.
The question asks "What prevents the operator from paralleling AC sources through 120 VAC class and non class buses?" which can also be interpreted as asking how the paralleling of these two buses with each other is prevented.
Request that " Physically and electrically separated" also be allowed as a full credit answer.
6.02 b.
Alternative answer stating that accumulators inject a large volume of water for core cooling due to systen pressure being greater than LHSIP shutoff head should also be an acceptable answer.
6.03 b.
Question does not require the answer to contain the pressure value as does the key.
6.04 b.
Answers reflecting change of heat loads, operational needs, and seasonal effects should be considered as acceptable.
c.
Another acceptable answer should be ECW traveling screens and wash pumps start as they receive a start signal on Safety injection.
6.05 a.
Increasing temperature in CCW system or components should also be considered as acceptable as inleakage from other components in addition to RCP thermal barrier could cause this sympton.
6.06 a.
Another correct answer is the Condenser Air Removal System exhaust process monitor with no automatic actions.
The answer key is in error for the condensate polishing effluent monitor automatic action causing isolation of the polishers.
The correct response is automatic isolation to the neutralization basin.
b.
Should also accept Computer Room Operators Console.
c.
The referenced text does not refer to " modes of display" for the RMS Ril.
Request consideration of answers reflecting function keys and systes capabilities to be acceptable.
6.07 a.
Anticipatory / rate of change should also be considered as acceptable.
6.08 a.
Request other answers stating allowance of control rods to be withdrawn during cooldown/ shutdown with the pressurizer water level greater than 921 (ie. solid operations for rapid refueling
, testing, or maintenance) be considered as acceptable.
6.09 a.
The answer key requires more than the question.
The question only requires that the response explain that the signal is processed through a PID circuit / anticipatory rate to answer the question.
Request explanation of PID/ rate circuit also be given credit.
+
6.10 a.
The question asks to " State the action that will result directly from reaching the P-14 setpoint." Request acceptance of FW isolation to mean the same as listing all the valves that isolate as required by the answer key.
No credit should be deducted for the inclusion of additional valves (feed regulating bypass, preheater bypass, and feed isolation bypass) in the answer.
b.
The wurds "Just below" in the question can be interpreted as requiring only the signals that are enabled by P-ll vice all other protection that is always available.
Request consideration of this for full credit.
SECTION 7.0 7.01 a.
Additional procedures require eininua charging flow to cool the regenative heat exchanger.
b.
Subsequent step in procedure requires sonitoring pressurizer temperature and pressure for saturated conditions.
Request answers stating or including this be allowed full credit.
7.02 d.
Based on plant conditions procedural allowance is granted for switching itees 5 and 2.
Request credit be allowed for this.
7.03 a.
Lining up the sample path to the VCT from the pressurizer vapor space is not specifically mentioned in the procedure therefore i
should not be required for full credit to be obtained.
7.04 a.
Procedure states "... evacuate the immediate area' which would also be an acceptable answer.
l c.
Credit should be given for containment ventilation actuation which is generated from the associated rad monitors.
Containment isolation does all three items listed in the answer key.
7.05 a.
CCW flow should also be accepted as an answer.
b.
Request other reasonable answers be allowed credit such as a leak in the seal standpipe supply line.
c.
Other reasonable indications of seal integrity should be acceptable.
7.06 a.
Procedure also states information on untrippable rods.
Request that this be allowyd as an additional correct answer.
Technical specifications also provides information to help the operator determine supplementary action.
I r
l
a e
7.07 a.
No credit should be taken away f or not listing RCFC drains as they have been deleted in Technical Specifirttions.
b.
RM11 indncation is also listed in the procedure as an indication and should be allowed as an acceptable answer.
7.00 a.
Alternative answers should be considered based on the extent of contamination ie, whole body / body location, b.
- 1. Alternative answers should be considered based on student assumptions and regulations applied, le 10CFR20.
7.10 b.
Credit should be allowed for ESF Monitoring Indication as a primary indication.
SECT!DN 8.0 0.01 a.
The question is aisleading as the Technical Specification specifically applies to " Remote Shutdown Monitoring Instrumentation".
Consideration should be given for alternative shutdown monitoring indications.
8.02 a.
- 2. Full credit should be given for recognition of LCO non-compliance on SG gallons per day basis.
0.06 c.
Credit should be given for alternative answers that address other procedural allowances such as from OPGP03-ZA-0010 page 6:
" Exceptions to the INDEPENDENT VERIFICATION requirements above are permitted:
1)
When vertitcation would result in significant personnel
- exposure, 2)
When verification would present a significant personnel safety risk, or 3)
In an emergency condition."
8.07 d.
Request full credit be given for either response.
0.00 Question is confusing as radiological incidents are addressed in several other procedural areas.
Full credit should be allowed based on student assumptions.
te, Energency Plan, Health Physics procedures, etc..
0.09 b.
Full credit should be given for stating that dedicated ring down line is used as preferred method of communication.
U.
S.
NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_$QUIB_IEE61_1___________
REACTOR TYPE:
_EWB-WEQ4________________
DATE ADMINISTERED:_ahll1412________________
EXAMINER:
_WBlIIEdQBEt_Jt__________
CANDIDATE:
INSIBUCIl00S_IQ_Q80Q1QoIEi Vao separate paper for the answers.
Writo answers on one side only.
Stcple question sheet on top of the answer sheets.
Points for each quostion are indicated in parentheses after the question.
The passing grcde requires at least 70% in each category and a final grade of at locst 80%.
Examination papers will be picked up six (6) hours after tho examination starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY
__VoLUE_ _IQI6L
___SQQBE___
_VaLUE__ ______________G8IEQQBl_____________
.25t00__ _2510Q 1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
.25100__ _25i00
________ 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
_25t00__ _25t00
________ 3.
INSTRUMENTS AND CONTROL.S
_25100__.25100
________ 4.
PROCEDURE! - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL LQQt00__
Totals Final Grade All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature
/
li__EBINQ1ELES_QE_NuQLE88_EQWEB_EL8NI_QEEB8I1QNr.
PAGE WD I
IHEBdQQ1Ned1QS&_BE8I_IB8NSEEB_8ND_ELVIQ_ELQW QUESTION 1.01 (2.00) c.
Why does nucleate boiling heat transfer remove more heat than non-boiling heat transfer?
(1.0)_
b.
'Why does film boiling remove less heat'than nucleate boiling?
(1.0)
QUESTION 1.02 (1.00)
Choose the CORRECT response.
In order to maintain a 200 deg. F subcooling morgin in the RCS when reducing RCS pressure to 1600 psig, steam generator pressure must be reduced to approximately:
c.
405 psig.
b.
325 psig.
c.
245 psig.
d.
165 poig.
QUESTION 1.03 (2.00)
A Westinghouse PWR operates at 100 % power with a Tavg. of 587 deg's F and a steam pressure of 980 psig.
What must Tavg. be changed to in order to maintain these conditions with 10 % of the steam generator tubes plugged?
Show all calculations including applicable formulas, equations, and relationships.
(2.0)
QUESTION 1.04 (1.50) to a primary neutron source necessary to provide sufficient neutrons to start the initial chain reaction in a new core? DRIEFLY EXPLAIN your answer.
(1.51
(*****
CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1&__EBINQ1ELEE_QE_NMQLE68_EQWEB_EL6NI_QEEBoIIQNi PAGE 3
IBEBDQQ1N8DIGSt_BE6I_IBaNSEEB_8ND_EL91D_ELQW QUESTION 1.05 (2.25) c.
Define Subcritical Multiplication Factor (M).
(0.75) b.
Provide THREE evolutions for which a 1/M plot is utilized in a Pressurized Water Reactor.
(1.5)
QUESTION 1.06 (2.50)
BRIEFLY EXPLAIN how the following will affect the Moderator Temperature Coefficient:
c.
The charging pump suction inadvertently switches to the Refueling Water Storage Tank.
(1.0) b.
The core ages from BOL to EOL.
(0.5) c.
The RCS is cooled down from 550 F to 450 F.
(1.0)
QUESTION 1.07 (2.75) c.
List or describe 3 of the 4 phenomena that affect the Doppler Power Coefficient and the Doppler only Power Defect.
(1.5) b.
What is the single factor (encompassing at least 2 of the phenomena above) having the most effect on the Coefficient value over cycle lifetime?
(0.75) c.
How will the Doppler Power Defect vary (however insignificant) over the life of the first core ?
(0.5) l i
l l
l i
l l
l
(*****
CATEGORY 01 CONTINUFO ON NEXT PAGE *****)
l L
11__EBINCIELEH_QE_UUCLEeB_EQWEB_EL8NI_QEEBoIIQUt PAGE 4
IBEBdQQ1Ned1GSt_UEel_IB861EEB_800_ELu1D_ELQW QUESTION 1.08 (2.50)
Roactor power is steady at 1000 CPS when sufficient reactivity is added to instantaneously change Keff from 1.0 to 1.001.
c.
Describe when (elapsed time) and how automatic protective action will occur if there is no subsequent operator action.
(1.5) b.
Assuming no operator and no automatic protective action, indicate and explain the final steady state condition of the reactor.
(1.0)
QUESTION 1.09 (2.00)
Hot channel factors are not always directly measurable but-their Technical Specification surveillance frequency requirements are relatively infrequent provided four items are monitored and verified to be within their limits.
Provide these four items (conditions).
(2.0)
QUESTION 1.10 (3.00) c.
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 concern about Xenon during high power reactor operation ?
C0.75) c.
Why will a power change cause Xenon (or Samarium) to undergo a short term decrease in concentration ?
(0.75)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
11__EBING1 ELE 1_QE_NVGLE68_EQWEB_EL8NI_QEEB811QNr PAGE 5
'IBEBdQQ1Nad191t_BE61_IB8NSEEB_6NQ_ELVIQ_ELQW QUESTION 1.11 (1.50)
Indicate on your answer sheet whether the f ollowing stateme its are true or false:
e.
Pump runout is a term used to describe a centrifugal pump operating with a shut discharge valve.
b.
A law applying to centrifugal pumps in closed loop systems states that power required is directly proportional to the square of the pump speed.
c.
For two IDENTICAL centrifugal pumps running at DIFFERENT speeds in IDENTICAL systems, the faster running pump requires a greater NPSH.
QUESTION 1.12 (2.00) c.
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 AND calculational techniques.
(1.0) b.
State 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.
(1.0)
(*****
END OF CATEGORY 01 *****)
r-.
2i__ELaPT._QESIGN_INCLUQ1NE_18EEII_6ND_EMEBGENGl_SISIEd3 PAGE 6
-QUESTION 2.01
- (2. 5 0 )'
O.
What type of power is available to the Class 1E 120 VAC inverters and how is 120 VAC obtained from the NORMAL power supply?
(1.0) b.
What is the alternate power available to the Class'1E 120 VAC bus?
(0.5) c.
What prevents the operator from paralleling AC sources through 120 VAC class and non-class busses?
(1.0)
QUESTION 2.02 (3.00) a.
If it becomes necessary to manually start and load a Stand By Diesel Generator, what is the first load that should be placed on the energized 4160 VAC bus?
Why?
(0.75) b.
What can cause the Stand By Diesel to auto trip if it.has started in the " Emergency Mode"?
(0.75) c.
What will auto start the Stand By Diesel in the " Emergency Mode? (0,5) d.
What are 5 of the 6 controls affected by the Stand By Diesel Generator Mode Selector Switch?
(1.0)
QUESTION 2.03 (2.50) o.
Why is the operator required to stop the Low Head Safety Inj ection Pumps if RCS pressure should increase above 300 psig during cold leg recirculation?
Be specific as to why this action is necessary.
(1.0) b.-
During recovery from a small break LOCA, why will accumulator inj ect ion result in more rapid recovery of core cooling?
(0.75) c.
Explain basically how ECCS pump flow verification tests are accomplished with the unit at power.
(0.75)
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
21__EL8NI_QE11GN_INgLUQ1NG_18EEIY_8NQ_EMEBGENgy_SygIgds PAGE 7-
- QUESTION 2.04 (2.50) c.
Containmen't Spray system design requirements dictate a minimum and maximum.pH limit during system operation and accident recovery.
What' are the reasons for these limits?
(1.0) b.
What is the atmosphere above the liquid in the spray additive tank and why is _ it necessary?
(0.5) c.
What are two (2) functions accomplished by the spray system to enhance-public health and safety subsequent to an accident?
(1.0) 1 QUESTION 2.05 (2.50) a.
.What interlocks would prevent the Steam Generator Feed Pump turning gear from auto starting after coast down to 2 RPM?
(0.75) b.
Describe how the Feed Pump Low Condenser Vacuum trip can very during the course of startup or shutdown.
(0.75) c.
Aside from condenser vacuum and manual trips, what are four (4) conditions not related to feed pump problems that may initiate a feed pump trip?
(1.0)
QUESTION 2.06 (2.50)
^ c.
Where can excess water in the Main Condenser hotwell be diverted to?
(0.75)
=b.
Aside from the power supply, what should be checked when a condensate pump will not start when the switch is placed in start?
(0.75)
.c.
Describe the automatic feature of the condensate polishing demineralizer bypass valve.
(0.5) d.
Under what plant conditions is main steam the predominate steam source to the deserator?
(0.5) a
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
21__ELeNIiDESIGN_INGLVQ1NG_SeEEII_6NQ_EUEBGENGl_SYSIEd3 PAGE 8
QUESTION 2.07 (2.00)
.o.
Describe the " Runout" protection afforded the Circulating Water pumps for starting and stopping.
(1.5) b.-
What will cause auto starting of the Open and Closed Loop Auxiliary Cooling Water pumps?
(0.5)
QUESTION 2.08 (2.50) a.
What heat loads will normally be supplied by an operating Essential Cooling Water (ECW) train?
(0.75) b.
What is the normal ECW train configuration for the unit at steady state power and how does it change for startup or shutdown?
(0.75) c.
What are four (4) additional actions-that will occur automatically on an ECW Pump start due to train actuation?
(1.0) t -
QUESTION 2.09 (1.50) e.
What~are the possibilities for the source of RCS leakage with increasing PRT level during normal operation at power?
(1.0)-
b.
What-are additional possibilities if PRT level increases while Safety-Inj ect ion is ongoing?
(0.5)
QUESTION 2.10
(?,50) a.
list six (6) specific components whose failure will result in radio-active leakage into the CCW system.
(0.9)
.b.
What happens to CCW system excess inventory due to in-leakage?
(0.6) c.
Describe all CCW system automatic action that may result from CCW IN-LEAKAGE and OUT-LEAKAGE.
(1.0) i l
(*****
CATEGORY 02 CONTINUED ON NEXT PAGE *****)
' c21__EL8HI_QE110N_INGLWQ1NQ118EEII_8ND_EMEBGENQ1_111IEd3 PAGE 9
-QUESTION 2.'11' (1.'00)
~. si.
Fill'in the blanks-for the'VCT level setpoints for-Level Transmitter L-ll3:
DIVERT-HI ALARM LO ALARM START EMER. MAKE UP LO LO ALARM.
(0.5)
_ What are two (2) alternateLhigh boron concentration flow paths in the b.
event-the Immediate Boration valve fails-to-open?
-(0,5) r 1
i 1
i t
i i
t 4
(*****
END OF CATEGORY 02 *****)
b c
F li__INSIBudENIS_8NQ_CQNIBQLS PAGE 1 01 LQUESTION-3.01:
(2.50) s.
List 2fot the 3. Process and Effluent Radiation' Monitors that are associatedLwith the steam (secondary) plant and state the automatic-
' action' associated with each monitor.-
(1.0)
.b.
What are the locations of the operating consoles fo'r the Radiation
~
Monitoring' System (RMS)~RM-11 microcomputers?
(0.75)
.c.
'What-are three (3) modes of display on the RMS CRT's?
(0.75)
QUESTION 3.02 (2.00)
.a.
Explain how the sequenced operation of the Control Rod Drive Mechanism (CRDM) acts to prevent excessive wear on the movable gripper.
(1.0) b.
Describe how the CRDM operates to lock out a withdrawn' rod for rapid refueling.
(1.0)
--QUESTION 3.03 (3.00)
. Answer the following about the " Power Mismatch Channel" portion of the rod control system:
a.
What is the purpose?
(0.75) b.
What are the-inputs?
(0.5)
-c.
Describe how' failure of an input will affect the control rods and explain the effect considering signal failure only to the Power Mismatch channel.
(1.0) d.
Explain how and why the channel output is affected,-depending on the
. size of a load change.
(0.75) f
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
2t__INSIBUdEN11_ANQ_QQNIBQLS PAGE 11 QUESTION 3.04 (2.50) e.
List the inputs to the Feedwater Bypass Control Valve system and explain why the inputs.are used compared.to the inputs used for controlling the Feedwater Control Valve.
'C1.0) b.
Assuming 100% power, is automatic protective action more likely to result from a FAILED HIGH or FAILED LOW Steam Generator Level Control System Steam Pressure Detector.
Justify your answer.
(1.5)
QUESTION 3.05 (2.50) c.
Why is it desirable to cause's reactor trip if the turbine trips at ca power level greater than 50%?
(0.75) b.-
How does the Solid State. Protection System (SSPS) sense.that a turbine trip has~ occurred?
(1.0) c.
In the event that the. trip (in a.
above) does not function when required, what prevents reactor safety limits from being reached or exceeded?
(0.75)
QUESTION 3.06 (2.50) c.
The High Pressurizer Level reactor trip is automatically blocked during shutdown.
Why is it necessary to be able to block this trip when the reactor is shutdown?
C0.75) b.
Describe the logic and coincidence necessary to automatically block the trip during-shutdown.
[0.75) c.
What other trips are blocked or unblocked simultaneously?
(1.0)
QUESTION-3.07 (2.00)
Describe HOW and explain WHY the RCP Undervoltage and the RCP Underfrequency trips function differently.
(2.0) l
(*****
CATEGORY 03 CONTINUED ON NEXT PAGE *****)
2t__INSIEudENI1_6ND_QQNIBQL1 PAGE 12 QUESTION 3.08 (2.50) c.
Explain why the pressurizer spray valves do not always' automatically open at the same pressure even though the setpoint.is not changed.
Be-specific in_ answering.
(1.5) b.
Explain how inadvertent RCS depressurization is prevented if-the pressure signal controlling a Power Operated Relief Valve (PORV) should fail high.
(1.0)
I QUESTION 3.09 (3.00) c.
Explain why the Charging Flow Control Valve receives an input signal from actual charging flow.
(1.0) b.
Describe the effect that a low pressurizer level signal'has on'the letdown system.
(1.0) c.
What effect can'high and low failure of a loop Tavg. have on pressurizer level in automatic control?
(1.0)
QUESTION 3.10 (2.50) c.
Name.the Reactor Protection System Permissive Circuits that receive any inputs from summed power.
(1.0)
I b.
Name and describe the operation of the nuclear instrument comparato)r circuits that monitor core power distribution.
(1.5)
I t
i
(*****
END OF CATEGORY 03 *****)
at__EBQCgDUBgS_:_UgBdett_agNQBuatt_gugBGENGX_oNQ PAGE 13 86019LQQ10eL_GQUIBQL QUESTION 4.01 (3.50)
According to the Heat up procedure, 1 POP 03-ZG-0001:
c.
What major valves (excluding valves associated with RCP seals), are manipulated to form a bubble in the pressurizer AND how are they manipulated to commence bubble formation?
ALSO state applicaole modes of valve control.
(1.5) b.
What are 2 indications of bubble formation stated in the procedure?
(1,0) c.
Before commencing RCS heatup, the operator is cautioned that RCP's should be started at a pressure between 325 and 450 psig.
What are the possible consequences of starting RCP's outside of this recommended pressure band?
(1.0)
QUESTION 4.02 (3.00)
During a reactor startup or startup preparation:
a.
What are the 3 items of information that are transferred from the Estimated Critical Position Calculation to the Neutron Doubling Curve Plot?
(0.75) b.
Explain how and what Nuclear Instruments (NI) are selected to the NR -
45 recorder, prior to control rod withdrawal?
(0.5) c.
What is the NI operability check performed between criticality and power leveling for data recording?
(0.75) d.
For the following events that occur during a normal startup, place them in the order they occur:
1.
Commence power increase to 10 (E-8) amps.
2.
Withdraw Shutdown Bank Control rods.
3.
Commence withdrawing Bank "A"
4.
Obtain baseline data for Neutron Doubling Curve Plot.
5.
Adj ust RCS boron concentration.
6.
Neutron counts double.
(1.0)
(*****
CATEGORY 04 CONTINUED ON NEXT PAGE *****)
Jer__EBQQEQUBEl_:_NQBd8kt_8HNQBd8Lt_EdEBGENQ1_8ND PAGE 14 88Q19LQQ1Q8L_GQNIBQL QUESTION 4.03 (2.00) e.
Prior -to cool down of the RCS, the operator is instructed to " Degas the Primary System".
BRIEFLY state how this is accomplished.
(1.0) b.
How can the operator affect the time necessary to accomplish degassing of the RCS?
C0.5) c.
During the initial cooldown, what conditions will cause excess cooldown protection'to be initiated?
.(0.5)
QUESTION 4.04 (2.50) a.
What are the immediate. action requirements if a new fuel assembly is dropped in the Fuel handling Building (FHB)?
(0.8) b.
What are 2 methods that can be used to initially ascertain whether or not the new fuel clad has been breached?
(0.7) c.
What 3 automatic actions COULD result from dropping a spent fuel assembly in the containment?
(1.0)
QUESTION. 4.05 (2.50) a.
What are the major factors that may influence RCP motor winding temperature to INCREASE as well as DECREASE during heat up of the RCS?
(1.0) b.
What are 3 abnormalities or problems indicated by required frequent filling of RCP # 3 seal standpipes?
C0.75) c.
With a RCP seal temperature indication going off scale, what other indication should be checked to ascertain whether a seal or instrumentation problem exists?
(0.75) s t
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
Esz__EBQQEQUBES_:_NQBd6Lt_8ENQBdekt_EUEBGENQ1_6NQ PAGE IS
'B6010LQQ198L_GQNIBQL QUESTION 4.06 (2.00) e.
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)
QUESTION 4.07~
(2.00)
During the performance of " Excessive RCS Leakage" (IPOPO4-RC-0003):
e.
What leakage detection systems would be indicative of a leak within the containment?
(1.0) b.
If the leak was not inside the containment (according to the above indication) or outside containment by thorough visual inspection, what other indication should be checked to indicate:the source of leakage out of the RCS?
(1.0) d 8
4
(*****
CATEGORY 04 CONTINUED ON NEXT PAGE *****)
-4 __EBQQEQUBE1_=_NQBd8Lt_8BNQBd8Lt_EMEBQENQ1_8ND PAGE. 16 t
88DIQLQQ198L_QQNIBQL QUESTION 4.08 (3.00) c.
Place the following list in the correct order of use for removing stubborn radioactive contamination on the skin of an individual with no open wounds.
1.
Titanium 0xide 2.
Soap and water 3.
Vacuum 4.
Potassium permanganate 5.
Pressure sensitive tape (1.0) b.
A 25 year old male technician is required to work in an area where the whole body dose rate is 0.150 REM /Hr.
His lifetime exposure is 1.535
. REM and his current quarterly and yearly exposure is 0.1 REM.
1.
-State how long may he work in the area during the current quarter and list the exposure levels reached and the approvals needed to receive the maximum exposure.
(1.0) 2.
How much time may he work in the area during the following quarter of the same year in accordance with STP administrative procedures.
Explain.
(1.0)
QUESTION 4.09 (2.00) c.
According to " Reactor Trip Response" (EO-ES01), what specific immediate actions are required of the operator if 2 control rods are not fully ir serted af ter a trip?
(1.2) b.
After a reactor trip with stable conditions attained, what are 2 conditions that would cause the operator to actuate safety inj ect ion?
State how parameters would trend, not actual value that would precipitate operator action.
(0.8) 4 4
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
dz__EBQQEQUBES_:_NQBd8Lt_6CNQBd8Lt_EMEBQENQ1_eND PAGE 17 bod 10LQQ10aL_QQNIBQL QUESTION 4.10 (2.50) 2.
Immediate action in " Reactor Trip or Safety Inj ect ion" (EO-E000) requires the operator to verify feedwater isolation.
State the valves that must be checked to confirm proper isolation.
(0.9) b.
What are the primary and alternate methods of verifying Phase "A" containment isolation?
(0.6) c.
When the operator is instructed to " Check for faulted S/G", what indication is observed?
(0.5) d.
With a valid safety inj ection, what should the condition of the Reactor Containment Fan coolers be according to EO-E000?
(0.5)
(*****
END OF CATEGORY 04 *****)
(*************
END OF EXAMINATION ***************)
it__EBINQ1 ELE 1_QE_NVQLE88 EQWEB_EL6HI_QEEB8I1QNi PAGE 18 IBEBdQQINed10ft_BE8I_IB8NSEEB_8ND_ELMID_ELQW ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 1.01 (2.00) c.
Nucleate boiling creates turbulent flow which promotes more mixing.
[0.5)
The coolant picks up latent heat of vapcrization and carries it to cooler' parts of the channel. [0.5)
(1.0) 4 b.
In film boiling, a film of steam coats the clad surface and forms an insulating layer (0.5) which greatly reduces the heat transfer coefficient. [0.5)
(1.0)
REFERENCE GP HT & FF, Pp. 123,124
. ANSWER 1.02 (1.00) c.
(245 psig.)
(1.0) i REFERENCE Steam Tables ANSWER 1.03 (2.00) 1 S/G heat transfer = Q = UACTavg - Tstm)
(0.25)
Q, U,
Tstm remain constant;
[0.25)
A1(Tavg1 - Tstm) = A2(Tavg2 - Tstm)
[0.5)
Given A2 = 0.9 x Al
.From Stm tables: Tsat for 995 psia = 544 F.
(0.5)
A1(587 - 544) 0.9A1(Tavg2 - 544)
=
Tevg2 = 591.8 (Accept 591 - 592.5)
[0,5)
(2.0)
lt_iEBINQ1 ELE 1_QE_NVQLE88_EQWEB_EL8NI_QEEB8I1QNi PAGE 19 IBEBdQQ1N8510ft_HE81_IB8NSEEB_8NQ_ELVIQ_ELQW
-ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 1.04 (1.50)
NO [0.5) EITHER: Only necessary for-source range indication (or verification of instrument operation) while performing a reactor startup. (1.0)
Many othe* sources of neutrons available for this purpose (cosmic, intrinsic, decay, etc.)
[1.0)
(1.5)
REFERENCE STP Rx Theory, Ch 6, Pp 3,4 ANSWER 1.05 (2.25) 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.
CONCEPT (0.75) b.
1)
Fuel loading / Refueling 2)
Rod Withdrawal Startup 3)
Boron Dilutions (Startup) 4)
ECP Discrepancy (0.5 each, three required]
(1.5)
(Accept " initial startup" in lieu of #2 or 3)
REFERENCE STP Rx Theory, Chapter 6, Pp 6 l
9 h
ANSWER 1.06 (2.50) a.
LESS NEGATIVE [0.25] More boron to leave core area per degree temperature change. (Or equivalent answer)
(1.0) b.
MORE NEGATIVE [0.25] Less boron, opposite result as above.[0.25] (0.5) c.
LESS NEGATIVE [0.25] Water density changes are less as temperature is reduced.
(1.0) t l
REFERENCE STP Reactor Theory, Chapter 8, Pp 6,8 l
l l
L-
. =
_li__EBINQ1 ELE 1_QE_NUQLE88_EQWEB_ELANI_QEEB6I1QNi PAGE 20 IBEBdQQ1Ned101t_BE81_IB8NSEEB_6NQ_ELUIQ_ELQW
. ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 1.07 (2.75) o, 1.
Changes due to depletion and buildup of U-238 and Pu-240.
2.
Changes due to increased fuel temperature caused by fission gas pollutants reducing gap thermal conductivity.
3.
Changes due to fuel densification.
4.
changes due to clad creep.
(Any 3, 0.5 ea.]
(1.5) b.
Decrease in the rate of effective fuel temperature change with power.
(0.75) c.
(Very slight) decrease.
(0.5)
REFERENCE STP Theory, Ch. 7, Pp.17,18 ANSWER 1.08 (2.50) e.
Power is to low to meet requirements of P-6, therefore the source range scram is in effect and will occur at 10 (ES) CPS. [0.5) 1.
Reactivity ~ change in keff or 1-Keff/Keff
.001/1.001 = 0.001
=
2.
Period =.007 -.001/0.1(0.001) = 60 seconds 3.
Ln P/Po = t/T
= Ln 100 =t/60 5
4.
Time before trip occurs ~ 276 seconds (Accept any answer between 3 1/2 and 6 minutes if viable correct concept is used to evaluate answer.
[1.0)
(1.5) b.
Reactor power will continue increasing until POAH where the increase in fuel (and moderator temperature) will add negative reactivity to stop power increase. (0.5)
Final power will be near PA0H. (0.5]
(1.0)
REFERENCE STP Theory, Ch. 5 Pp.5-17 STP SD RPS, P.16
-it__EBINQIELER_QE_NuQLE88_EQWEB_EL8NI_QEEB8I19Nt
~P' AGE 21 IBEBdQQ1NedIQ1t_BE81_IB8NSEEB_8NQ_ELVIQ_ELQW
-ANSWERS -- SOUTH _ TEXAS'1
-86/11/13-WHITTEMORE, J.
ANSWER 1.09 (2.00) e.
Rod groups sequenced and overlapped.
b.
Rod insertion limits adhered to.
c.
Axial flux difference limits adhered to.
i-d.
Rod group alignment maintained. [0.5 each)
(2.0)
REFERENCE STP TS, B 3/4 2-3 ANSWER 1.10 (3'.00)'
}
a.
1.
1-135 varies linearly with power level (0.5] as subject to removal l
only-by radioactive decay. [0.25]
2.
Xe-135 does not vary linearly (0.25] as it is subj ect 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) 4 c.
Increasing power can cause increased burnout prior to building to a new equilibrium level. CONCEPT.
(0.75) i i
REFERENCE STP Rx. Theory, Ch.
9, PP.6-8 l
ANSWER 1.11 (1.50) a.
False b.
. False c.
True (0.5 en.]
(1.5)
REFERENCE STP HT&FF, Pp.322,323 m
. _ ~
it__EBINQIELE1_QE_NVQLE88_EQWEB_EL8HI_QEEB8110N2 PAGE 22
~IBEBdQQIN8dIQ1t_BE81_IB8NSEEB_8NQ_ELVIQ_ELQW
' ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
i ANSWER 1.12 (2.00) e.
Perform a heat 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. (Allow 1/2 credit for:
-Chg. flow = L/D flow + Seal L/0 - Seal inj. flow with Pzr. level constant.
(1.0) b.
1.
Increase 2.
Increase 3.. Increase (0.33 ea.]
(1.0)
Accept other answer if supported by viable assumption.
. REFERENCE i
GP Theory, Pp. 243, 319-334 4
i i
i t
I i
1 i
- -~
-.,,-,--,,,,,,.,.,-,---,,,-----.~.-.,.--.-n,.,_
,,...-.,.e.--...,,..
21__EL6HI_ DESIGN _INCLUDINQ_18EEII_8NQ_EUEBGENQ1_SX1IEd3 PAGE 23 ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 2.01 (2.50) o.
Normal 480 VAC is rectified to DC and then-inverted to produce 120 VAC. [0.5]
(1.0) b.
A voltage regulator-supplied from a different 480 V MCC than the one supplying the inverter..
(0.5) c.
Class: A manually operated bar interlock permits energizing from either source if the other source is open.
(0.5)
Non-class: The auto transfer switch will select only one source at a time.
(0.5)
REFERENCE SD Class 120VAC, P5 & Non-class 120VAC, PS,6 ANSWER 2.02 (3.00) a.
ECW pump (0.5] as it supplies cooling water to the SBG. [0.25]
(0.75) b.
1.
Overspeed 2.
Gen. Differential 3.
Loss of 125 VDC control power.
p 4.
Low lube oil pressure (0.25 ea.)
(1.0) c.
1.
SIS 2.
Undervoltage on respective bus (0.25 en.]
(0.5) d.
1.
Start /Stop i
2.
Volt. reg. Auto / man.
3.
Volt. Reg. adj ust 4.
Governor speed control
-5.
Governor Mode 6.
Gen. Output Bkr.
(Any 5, 0.15 ea.]
(0.75)
REFERENCE SD, SBG, P.4 & SBD, Pp. 27,49,50,52,53 l
l E
Zi__EL6NI_ DESIGN _INGLUDING 18EEII_eNQ_EMEBQENC1_111IEd$
PAGE 24-ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 2.03 (2.50) a.
The RWST level signal - that auto initiates cold leg recirculation also closes LHSI pump mini-flow recirc. valves to RWST.
(0.53 Continued operation of-the pumps will result in damage. [0.53 (1.0) b.-
Accumulator injection causes increased RCS depressurization and results in increased ECCS pump inj ection rates.
OR; Inj ects a large amount of water when LHIS is not available.
c.
ECCS pumps are run individually with flow returning-to the RWST through the Mini-Flow recire. lines.
(0.75)
REFERENCE
'SD, ECCS, Pp. 5,7 ANSWER 2.04 (2.50) a.
Minimum:
Maintain Iodine in solution.
(0.5)
Maximum:
Prevent caustic attack on RCS and Sump metals.
(0.5) b.
(~
3psig) N2 (0.25] to prevent NaOH degradation. (0.25]
(0.5) c.
Reduces containment pressure to reduce leakage and minimize leakage to offsite.
-(0,5)
Entraps fission products in solution and prevents their escape to the atmosphere.
(0,5)
2t__EL6HI_ DESIGN _INGLUDING_18EEII_eND_EMEBGENC1_SYSIEd3 PAGE 25 ANSWERS --- SOUTH TEXAS -1
-86/11/13-WHITTEMORE, J.
. ANSWER 2.05 (2.50) c.
1.
HP stop valves closed.
2.
LP stop valves closed.
.3.
Bearing oil pressure low (<15 psig) 4.
Motor overload condition.
(Any 3, 0.25 ea.]
(0.75) b.
Normal setpoint is 14".
(0.3753 but if vacuum is less than 20",
the trip is auto reset to 3 psig until vacuum is > 20" and trip resets to 14".
(0.375)
(0.75) c..
1.
S.I.
~2.
. Excessive cooldown 3.
Hi-Hi'S/G level 4.
Lo-Lo feed suction pressure
-(0.25 ea)
(1.0)
REFERENCE SD, S/G FEED PUMP, Pp.8,10
}
1 ANSWER 2.06 (2.50)
J c.
1.
Secondary make up tank 2.~
Auxiliary boiler deaerator
~
3.
Other unit (Cond. system or secondary M.U.
tank)
(0.25 ea)
(0.75) b.
1.
Recirc. valve shut 2.
Suction valve open 3.
Discharge valve. shut (0.25 ea)
(0.75) c.
Auto opens on high polisher D/P (0.5)
~
d.
During low power _(0.25) or large load rej ect ion. (0.25]
(0.5)
REFERENCE SD, COND, Pp. 5,8,9 FEED SYS. P.5 i
2t__EL8NI_QE11GN_INCLUQ1NQ_18EEII_8NQ_EdEBGENQ1_H11IEd3 PAGE -26 ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER-2.07 (2.00) e.
When the first pump is started, it's discharge valve will open to the (40%0 position. [0.25] When the second pump is started it's discharge valve.will open to (35%)
[0.25] allowing both valves to open fully.
[0.253 There is no restrictions or auto action for starting the third and fourth pumps.
(0.?5]
When the second to last pump is stopped, the remaining pump will trip unless it's. discharge is less than (41%)
open. [0.5]
- ( 1. 5 ) -
b.
1.
Low system pressure 2.
Trip of operating pump (0.25 ea)
(0.5)
& OL-ACW, P.8 ANSWER 2.08 (2.50)
'e.
1.
Essential EAB HVAC chillers 3.
CCW-Pump supplementary (room) cooler (0.25 ea)
EDG accepted but not required.-
(0.75) b.
Normalt 1 train operating, 1 train in standby, 1 train off.
(0.5) l Startup or shutdown:
Switch to 2 trains operating, 1 in standby.(0.25) c.
1.
Start ECW discharge strainer.
2.
Open ECW blowdown.
3.
Open pump discharge valve.
4.
Provides signal to Sodium Hypochlorinator.
5.
Starts ECW room vent fans.
6.
Traveling screen starts.
7.
Screen wash pump starts.
[any 4, 0.25 ea.]
(1.0)
REFERENCE SD, ECW, Pp.5,6 4
1 l
s.
..-,..-4,.--c
.,_.--,.y,,-
y
~.. -.,, - -,. -
-,r,-..w-
'2t__EL8HI_DE11GN_INGLUDING_18EEIX 8NQ_EdEBQENCY_111IEd$.
PAGE 27 ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 2.09 (1.50) e.
Pzr safety valves Pzr1 relief valves CVCS Sea 11 return relief CVCS letdown relief (0.25 ea)
(1.0) b.
ECCS pump reliefs (0.5)
REFERENCE SD, PZR, Pp. 5,6 ANSWER 2.10 (2.50) c.
RHR HX, RCP Thermal Barrier, LO HX, Excess LD HX, Seal Water HX, RCOT HX, Sample Coolers.
(Any 6, 0.15 ea)
(0.9) b.
Systen relief discharges to the CC J sump which is subsequently proces2ed by liquid waste system.
(0.6) i c.
OUT-LEM(AGE:
1.
Auc> make up 2.
Au :-) isolation of non-ESF train 3.
Auto isolation of RCP thermal barriers 4.
CCP cross-connect shuts IN-LEAKAGE:
1.
Surge tank relief opens (0.2 for ea. action)
(1.0)
REFERENCE SD, CCW, Pp. 40-42 4
l L
1 l-f2t__EL8HI_QE11GN_ INCLUDING _18EEll_8ND_EME8GENGl_111IEd3
. PAGE.28
. ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 2'.11 '
(1.00) e s.
, Divert 95%
Hi Alarm 95%
~Lo Alarm 15%
Start Emer. Make up 1%
~ LO LO Alarm
~1%
[0.1 eal (0.5) b.
RWST via parallel MOV's to Chg. pump-suct.
[0.25]
i' BAT via BA filter and normally shut manual valve.
[0.25]
C0.5) i REFERENCE 1
STP EXAM BANK, Pp. 24,25
)
j-e h-L i
i i
t
.l i
1 i
i
]
[
1 I
i i
i 4-m---
y-
--.m
-y-,..---
y.
, =..
,%.m-%,,,,,,y,mm,,%-,y,..,,-.,,.,,.,
,.g,%,,,_-_,,m
-_,_.,p%.
,,_-,,,.,m.____,..,.,_,,_.,.,_,,_.,y,.
li__INSIBUBENIS_860_GQNIBQLS PAGE-29 ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 3.01 (2.50) c.
1.
Turbine bldg. sump and drain system.
'[0.25]
High rad. level stops the sump. [0.25]
2.
Condensate polishing system.
(0.25]
High rad. stops flow to naturalization basin.
(0.25]
3.
S/G blowdown.
(0.25] High rad. stops flow to naturalization basin.
[0.25]
4.
Cond. Air Removal sys. (0.25]
No automatic action. (0.25]
[Any 2.
0.5 each)
(1.0) b.
(0.25 ea.]
(0.75) c.
1.
Grid display 2.
Trend display 3.
Group display (0.25 ea.]
(0.75)
REFERENCE LP RMS II, Pp.13,14,15,17 ANSWER 3.02 (2.00) c.
The sequence always starts by increasing current to the stationary gripper coil and-initially lifting the rod (0.5) before the movable gripper engages or withdraws.(0.5]
(1.0) b.
The hold out coil raises the locking mechanism into position behind the stationary gripper arms. (0.33]
The stationary gripper is deenergized to allow it's arms to engage the locking mechanism. (0.33]
The holdout coil is deenergized and the system self locks. (0.33)
(1.0)
REFERENCE LP, R00 CONTROL, Pp16-18
2t__INSIBudENIS_8ND_GQNIBQL3 PAGE 30
' ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 3.03 (3.00) o.
To provide fast control rod response and stability. CONCEPT (0.75) b.
Turb Inpulse Pressure & Auct.'Hi Nuc. power (0.5).
c.
Will cause an insert or withdraw signal only while failure is occurring (0.5] as mismatch is a rate error signal and static mismatch will not result in auto rod motion.[0.5]
(1.0) d.
A non-linear gain unit will cause a larger mismatch for a larger load change as a larger change requires a larger reactivity change.
(0.75)
REFERENCE LP, ROD CONTROL, Pp. 21,22 ANSWER 3.04 (2.50) e.
Level error (0.25] and auctioneered high nuclear power. [0.25]
Nuclear power used to anticipate changes in heat f. lux into the Steam Generator.
[0.25]
System does not use flow error due to inherent inaccuracies at low flow conditions. [0.25)
(1.0) b.
Low failure failure is more likely to result in protective action.
[0.5]
The pressure detector directly affects the flow transmitter output and the highest output of the flow transmitter is (133%) [0.25]
and a flow error of (33%) is correctable by level error before a trip point is reached. (0.25]
A low failure on the other hand will result in a 100% error which is not correctable by level error before a trip setpoint is reached. (0.5]
(1.5)
REFERENCE LP, SGLWC, Pp. 24,27
2t__INSIBudENI1_6ND_QQNIBQL1 PAGE 31 AN S W E R S --- SOUTH TEXAS l'
-86/11/13-WHITTEMORE, J.
ANSWER 3.05 (2.50) c.
To prevent undesirable thermal transients not mitigated by the control rods and steam dumps. (CONCEPT)
(0.75) b.
1.
2/3 Low Auto Stop Oil Pressure 2.
2/4 Turbine stop valves shut.
[0.5 ea.]
(1.0) c.
Backup is provided by OTdT or Hi Pressurizer Pressure trip.
(Mention of one backup trip is worth 0.5 pts. AND accept High Pressurizer Level trip for no credit.)
(0.75)
REFERENCE LP,SSPS, Pp11,12 ANSWER 3.06 (2.50) o.
Allows control rod testing or withdrawal at low temperature.
(0.75) b.
3/4 Power range channels less than 10%-[0.25] AND [0.25] 2/2 Turbine impulse power less than 10%. [0.25]
C0.75) c.
1.
Low Pressurizer Pressure.
2.
RCP undervoltage 3.
RCP underfrequency 4.
Low flow REFERENCE LP, SSPS, Pp.'10.17 ANSWER 3.07 (2.00)
A Low voltage trip will trip the reactor (0.5) where a Underfrequency trip will trip the reactor and the RCP breakers. [0.5)
Breakers are tripped on underfrequency to prevent the slowing of pumps and reducing flow coastdown time. (1.0)
(2.0)
REFERENCE LP, SSPS, Pp. 10,11 L.
.2i__INSIBudENI1_8NQ_GQUIBQL1 PAGE 32-
. ANSWER'S -- SOUTH TEXAS 1
--86/11/13-WHITTEMORE, J.
ANSWER 3.08 (2.50) e.
The control signal is from the Pressurizer Master Controller and the. actual. operating setpoint is modified by duration (0.75] as.well as rate of change. [0.75]
(Accept an explanation of a PID controller for full credit (1.5) b.
An interlock signal prevents autematic operation below (2185) psig.
[0.51 The interlock signal.is.provided'by another channel. [0.5](1.0)
REFERENCE LP, PRESS. CONTROL, Pp. 9,12 ANSWER 3.09 (3.00) o.
Ensure adequate cooling to regen. HX.
(1.0) b.
Immediately closes all orifice isolation valves-[0.53 and letdown isolation valves close 10 seconds later. [0.51 (1.0) c.
Low failure will have no ef f ect as the control signal is auctioneered high loop Tavg. [0.5]
High failure will cause the level to control at a max. level of 60%. [0.5]
(1.0)
REFERENCE LP,PZR LEVEL CONT, Pp.27-29
E2x__INSIBudENI1_8NQ_GQNIBQLS PAGE 33 ANSWERS -- SOUTH TEXAS-1
-86/11/13-WHITTEMORE, J.
ANSWER.
3.10 (2.50) c.
P-7 P-8 P-9 P-10 P-15 (0.2 es.]
(1.0) b.
Power Range Detector Current Comparator. [0.25]
Compares 1the 4 upper or lower detector outputs with the average upper or lower output to generate a signal proportional to deviation. (0.51 (0.75)
Power Range Channel Current Comparator. (0.25]
Compares the output of all 4 channels to the_ low suctioneered channel output and generates a signal proportional to the deviation.
(0.5]
(0.75)
REFERENCE LP, EX-CORE NI'S, Pp. 11,19,20
/
f
y, g
~#{
k, b
fi__EBQQEQUBE1_:_NQBd8L1_aBNQBdeLZ EMEBGENQ1_6NQ PAGE 34 88DIQLQQIQaL_GQNIBQL i
- ANSWERS -- SOUTH TEXAS (1
-86/11/13-WHITTEMORE, J.
^~
C'%?
n
/k t
.V %
ANSWER 4.01.
I-( 3. 5 0 )'
.o.
The Charging Flow Control valve (1*CV-FCV-02'053-[0.5) is closed-in the manual mode. [0.25]
r Thu Letdown Pressure Control valve (1*CV-dCV-135) [0.5] is placed'in j
auto and set t'o maintain (150 -250 psig) it r e,s s u r e. - [ 0. 2 5 ]
(1.5) g b.
Increasing letdown flow rate (0.53 and a (N'a r ed decrease in pressurizer heatup' rate. [ 0.~ 5 ] Allow 0.25 for " Verify saturated conditions" (1.0)
?
q.
c.
Less than 325 psig may cause damage to RCP seals,.(0.'5] while being.
greater-than 450 psig may cause failure of the)RHR system. [0.5] (1.0)
N:
)
$ f P.EFERENCE 1 POP 03-ZG-0001, Pp. 5 -
1 I
s p
O L
AMSWER 4.02 ) \\
(3.00)
- 3 y
l' i.
fo. - ECP, ECP +'500 PCM,'ECP - 500 PCM
[0.25 es.]
(0.75) b.
Highest reeding SR, [0.25] and Highest reading IR. 10.25]
(0.5)
G
- c.. Ensure) fat-loast i decade) overlap between SR and IR.
(0.75) d.'
5,\\ 2, 4,
6, 1
(Subtract 0.25 points'for each perturbation or; 2,5,4,3,6,1 necessary to achieve proper order.)
(1.0)
REFERENCE i
1 POP 03-ZG-0004, Pp. 3-7
- x ANSWER 4.03 (2.00)
\\
- c.
A nitrogen cover blanket is established in the VCT [0.5] and the pressurizer vapor space is vented
[0.5]
(1.0) b.
By-controlling letdown flow (# of orifices onsline).,
(0,5)
-c.
Less than 532 F.
while greater than 1950 ps ig RCS pressure.
(0.5)
REFERENCE s
.tPOP03-ZG-0007, pp4,5 r
Aww u
st__EBQQEDMBES_=_NQBdekt_6BNQBd8Lt_EdEBQENQ1_6NQ PAGE 35
.88Q19LQE198L_RQNIBQL ANSWERS --: SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 4.04
_(2.50) c.
Immediately evacuate the FHB [0.43 and notify the control room. [0.4]
(0.8) b.
Health and Safety obtain samples (0.35 3 and perform a visual inspection _[0.35]
(0.7) c.
.1.
Trip and isolation of containment purge.
2.
Trip and isolation of supplementary containment purge.
3..
-Isolation of containment atmosphere monitor. [0.33 ea.)
OR; Containment Ventilation Isolation Accept. mention of various alarms for no credit.
(1.0)
REFERENCE 1POPO4-FH-0001, P.1 1POPO4-FH-0003, Pp. 1,2 ANSWER 4.05 (2.50) c.
May decrease as the fluid being pumped becomes less dense and less winding current is required. [0.53 May increase due to increased atmosphere temperature. [0.5]
(1.0) b.
1.
Damaged seal 2.
Worn seal 3.
Seal not fully seated 4.
Leak in RHR
[Any 3, 0.25 ea.]
(0.75) c.
1.
Inj. temp.
2.
Inj. flow 3.
Leakoff flow 4.
Other RTD.
(Any 3, o.25 ea.]
(0.75)
REFERENCE 1POPO4-RC-0002, Pp. 11-13
-3t__BBQQEQUEEl_:_NQBd8Lt_8BNQBd8Lt_EdEBQENQY_8NQ PAGE 36 88QIQLQQ1Q8L_QQNIBQL-
-ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER' 4.06-(2.00) e..
Whether the failure is in the control system (0.5] or'due to friction
/ mechanical interference. [0.5]
(1.0) b.
Go to manual, [0.5) and trip reactor if motion continues. [0.5]
(1,0).
REFERENCE-1 POP 04-RS-0002, Pp.1,2 4
. ANSWER
-4.07 (2.00) s..
1.
Containment atmosphere monitoring system.
2.
Sump. level and flow monitoring system.
3.
RCFC drain flow monitoring system.
[0.33 ea.]
(1.0)
.b.
1.
RCDT (level, temp.)
2.
-PRT (level, temp.)
3.
S/G (activity, feed /stm flow, level)
[0.33 ea.]
(1.0)
REFERENCE 1POPO4-RC-0003,Pp.2,3 ANSWER 4.08 (3.00) e.
3, 5,
2, 1,
4 [ subtract 0.25 for each perturbation necessary to achieve correct order)
(1.0) b.
- 1.
May receive a dose of 2.75 - 0.1 =2.65 this qtr.
May stay in the area for: 2.65/.15 = 17.66 hrs. (accept 17.35 - 18.0) (0.5]
Needs approval to exceed 1.0 REM by Radiation Protection Supervisor
[0.25] and 2.0 REM by the Plant Manager. [0.25]
(1.0 2.
STP administrative limit is 5.0 REM /Yr. [0,5)
Allowable dose is:
5.00 - 2.75 = 2.25/0.15 = 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />. [0.5 (1.0) i REFERENCE OPR08-ZC-0002, Pp. 4,7,8 OPG03-ZR-0006, Pp.3,4
Lax __EBQQEQUBER_=_NQBdekt_6BNQBdelt_EMEBGENQ1_8NQ PAGE 37 88DIQLQQ198L_QQNIBQL ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE,- J.
l ANSWER 4.09
.(2.00) e.
o Start boric acid-pump.-
o Open boric acid flow control valve.
o-Verify > 30.GPM flow.
[0.4 ea.)
(1.2) b.
Decreased subcooling.
Decreased pzr. level.
[0.4.ea.)
(0.8)
REFERENCE 1 POP 05-EO-ES01 ANSWER 4.10 (2.50) n.
o.
Flow control valves o
_ Flow control valve bypass valves o
FW isolation valves o
FW isolation 8/P valves o
S/G blowdown isolation o
Sample isolation (0.15 es.)
(0.9) b.
Primary:'
ERFDADS Alternate: MCB Indication (0.3 es.)
(0.6) c.
S/G pressure (0.5) d.
Running, cooled by CCW.
(0.5)
REFERENCE 1 POP 05-EO-E000, Pp,9,11,23
U.
S.
NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_SQQIB_IEX61_1___________
REACTOR TYPE:
_PWB-WEQa________________
DATE ADMINISTERED: _gh/11212________________
EXAMINER:
_WBlIIEMQBEt_Jz__________
CANDIDATE:
INSIBUCIlQN1_IQ_QaNQ1QalEl Uco separate paper for the answers.
Write answers on one side only.
Stcple question sheet on top of the answer sheets.
Points for each quGstion are indicated in parentheses after the question.
The passing 9rede requires at least 70% in each category and a final grade of at locst 80%.
Examination papers will be picked up six (6) hours after tho examination starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY
__ VALVE _ _IQIAL
___SQQEE___
_VaLUE__ ______________CaIEQ981_____________
25tDQ__ _25t3B
________ S.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS
_2E100__ _25t2B
________ 6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
_25t00__ _25t28
________ 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
_32150__ _22tQk
________ 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS
_RatEQ__
Totals Final Grade All work done on this e.caminction is my own.
I have neither given nor received aid.
Candidate's Signature i
51__IBEQBl_QE_NVQLEaB_EQWEB_ELaNI_QEEBoIl0Ut_EL91Q1t_aNQ PAGE 2
IBEBdQQ1Nad1CS QUESTION 5.01 (1.00)
During a reactor startup, an initial reactivity addition causes count rate to increase from 20 CPS to 40 CPS.
A second reactivity addition causes the count rate to increase from 40 CPS to 80 CPS.
Which of the following ctatements is correct?
c.
The first reactivity addition was smaller.
b.
The second reactivity addition was smaller.
c.
The first and second reactivity additions were equal.
d.
There is insufficient data given to determine relationship of reactivity values.
QUESTION 5.02 (2.50)
Roactor power is steady at 1000 CPS when sufficient reactivity is added to instantaneously change Keff from 1.0 to 1.001.
c.
Describe when (elapsed time) and how automatic protective action will occur if there is no subsequent operator action.
(1.5) b.
Assuming no operator and no automatic protective action, indicate and explain the final steady state condition of the reactor.
(1.0)
QUESTION 5.03 (2.00)
After a reactor startup reactor power is maintained at 50 %.
a.
What will happen to Samarium if power is increased to 100 % after 2 months?
(0.5) b.
Explain the initial effect on Xenon concentration as power is increased to 100 %?
(1.0) c.
If shutdown from 100 % power results in the insertion of approximately 500 PCM of negative reactivity due to the buildup of Samarium, how much reactivity would be inserted from shutdown or trip at 50 % power?
Assume equilibrium Samarium conditions for both cases.
(0.5)
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
Sz__IBEQBl_QE_NVQLEoB_EQWEB_ELeNI_QEE86IIQNt_ELU10St_eND PAGE 3
IBEBdQQ1 Nod 193 QUESTION 5.04 (2.50)
BRIEFLY EXPLAIN how the following will affect the Moderator Tcmperature Coefficient:
c.
The charging pump suction inadvertently switches to the Refueling Water Storage Tank.
(1.0) b.
The core ages from BOL to EOL.
(0.5) c.
The RCS is cooled down from 550 F to 450 F.
(1.0)
QUESTION 5.05 (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 distribution with time.
Assume full power, steady state equilibrium conditions, and systems in automatic.
(3.0)
QUESTION 5.06 (2.00)
Explain why the critical boron concentration will not very in a linear otraight-line manner when graphed in comparison to burnup of the initially loaded core.
OR, explain the shape of the graph.
(2.0)
QUESTION 5.07 (2.00) c.
Why are burnable poison rods used in the INITIAL core?
(1.0) b.
Why may they be used in a SUBSEQUENT core?
(1.0)
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
-St__IEEQBI_QE_NMQLE88_EQWEB_EL6NI_QEEB6Il0Ni ELVIQ3t_8NQ PAGE 4
IBEBUQQINedlG3 QUESTION 5.08 (1.06)
Choose the CORRECT response.
In order to maintain a 200 deg. F subcooling acrgin in the RCS when reducing RCS pressure to 1600 psig, steam generator pressure must be reduced to approximately:
a.
'405 psig.
b.
325 psig.
c.
'245 psig.
d.
165 psig.
- QUESTION 5.09 (2.00) a.
10uring 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 a calculational technique. (1.0) b.
State howLthe 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.
Also assume steady high power operation.
1.
Grid frequency decreases to 59.6 HZ.
2.
Pressurizer temperature increases.
- 3. Turbine power increases slightly with rods in manual.
(1.0)
QUESTION 5.10 (2.00)
A Westinghouse PWR operates at 100 % power with a Tavg. of 587 deg's F and e steam pressure of 980 psig.
What must Tavg. be changed to in order to maintain these conditions with 10 % of the steam generator tubes plugged?
i Show all calculations including applicable formulas, equations, and t
relationships.
(2.0)
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
n =,-
.51__IdEQBl_QE_NWQLE88_EQWEB_EL8NI_QEEB8IIQNi_ELW1Q1t_8NQ' PAGE
'S LIBEBdQQ1Ned191 QUESTION 5.11-(2.50) a.
The following parameters'will provide indication of natural circulation flow:
o Core exit temperature o
Cold leg temperature o
Steam pressure Describe how these parameters will. trend or indicate if natural circulation flow is lost.
(1.5) b.
What are 2 design features of the Reactor Coolant System that' enhance natural circulation flow?
(1.0)
QUESTION 5.12 (2.50)
Describe and explain how a " Hot Channel Factor" would be affected if:
a.
A reflector were installed around the core.
(0.75) b.
RCS design flow rate was increased.
(1.0) c.
Boron poison rods were axially zoned'to be more heavily concentrated in the upper portion of the core.
(0.75)
Assume full power, BOL, ARO for all situations
(*****
END OF CATEGORY 05 *****)
ht__EL8BI_111IEd1_QE11GNt_QQNIBQLt_6NQ_1811BudENI6I196 PAGE 6
-QUESTION 6.01 (2.50) e.
What type of. power is available to the. Class 1E 120 VAC inverters and
.how is 120 VAC obtained from the NORMAL power supply?
(1.0) b.-
What is the alternate power available to the Class 1E 120 VAC bus?
(0.5) c.
What prevents the operator from paralleling AC sources through 120 VAC class and non-class busses?.
(1.0)
QUESTION 6.02 (1.50)
G.
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) b.
During recovery from a small break LOCA, why will accumulator injection result in more rapid recovery of core cooling?
(0.75)
QUESTION 6.03 (2.50) e.
Containment Spray system design requirements dictate a minimum and maximum pH limit during system operation and accident recovery.
What are the reasons for these limits?
(1.0) b.
What is the atmosphere above the liquid in the spray additive tank and why is it necessary?
(0.5) c.
What are two (2) functions accomplished by the spray system to enhance public health and safety subsequent to an accident?
(1.0)
(*****
CATEGORY 06 CONTINUED ON NEXT PAGE *****)
~ _
A 4t__EL6NI_li1IEUS_QESIGNt_QQNIBQLi_eNQ_INRIBudENI6I19N PAGE 7
i QUESTION 6.04 (2.50)
[
c.
What heat loads will normally be supplied by an operating Essential
' Cooling Water (ECW) train?
(0.75)
' b.
What is the normal ECW train configuration for the unit-at steady state power and how-does it change for startup or shutdown?
(0.75)
- c.
. What are four (4) additional actions that will occur automatically on an ECW Pump start due to train actuation?
(1.0)
QUESTION 6.05 (3.00) i O.
What are 3 symptoms of radioactive leakage into the CCW system?
(1.0) b.
What 4 conditions will cause an auto start of a CCW pump?
(1.0) c.
- State 6 possible sources of radioactive leakage into the CCW system during operation.
(1.0)
QUESTION 6.06 (2.50) s.
List 2 of the 3 Process and Effluent Radiation Monitors that are associated with the steam (secondary) plant and state the automatic action 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) c.
What are three (3) modes of display on the RMS CRT's?
(0.75) l l
4 i
a i
(*****
CATEGORY 06 CONTINUED ON NEXT PAGE *****)
4 e-a
- v. e,r e-emme.--enm--,---m--,
-e--,-,-+,-y-<,+
.-,n,,.,,,w.--g.,e--,,y=,---
,-ee-,
,,wo,
,w-mwe,e,,ev,,,gw,,,ew,,,ge,ymg, w w,y mwmup----e-,-
ht__EL8HI_111IE51_QE110Nt_QQUIBQLt_aNQ_IN11BudENI6IIQN PAGE 8
QUESTION 6.07 (3.00)
Answer the following about the " Power Mismatch Channel" portion of the rod control system:
o.
What is the purpose?
(0.75) b.
What are the inputs?
(0.51 c.-
Describe how failure of an input will affect the control rods and explain the effect considering signal failure only to the Power Mismatch channel.
(1.0)-
d.
Explain how and why the channel output is affected, depending on the size of.a load change.
(0.75)
QUESTION 6.08 (2.50) a.
The High Pressurizer Level reactor trip is automatically blocked during.
shutdown.
Why is it necessary to be able to block this trip when the reactor is shutdown?
(0.75) b.
Describe the logic and coincidence necessary to automatically block the trip during shutdown.
(0.75) c.
What other trips are blocked or unblocked simultaneously?
(1.0)
QUESTION 6.09 (2.50) e.
Explain why the pressurizer spray valves do not always automatically open at the same pressure even though the setpoint is not changed.
Be specific in answering.
(1.5) b.
Explain how inadvertent RCS depressurization is prevented if the pressure signal controlling a Power Operated Relief Valve (PORV) should fail high.
(1.0) 1 I
i
(*****
CATEGORY 06 CONTINUED ON NEXT PAGE *****)
hi__EL8HI_SI1IEd1_DE11DNi_GQNIBQLt_8NQ_IN11BudENI8IIQN PAGE 9
QUESTION 6.10 (2.50) c.
State the action that will result directly from reaching the P-14
. Pe rmiss ive' setpo int..
(1.0) b.
Describe the protection that is available for a steam line break during cooldown just below the P-11 setpoint.
Description should include
-specific initiating signals and resultant basic protective action that occurs.
(1.5)
(*****
END OF CATEGORY 06 *****)
Zi__EBQQEQuBE1_:_NQBdeLt_aBNQBdakt_EdEBQEUQ1_aNQ PAGE 10 BaQIQLQQ1 gal _QQNIBQL QUESTION 7.01 (3.50)
According to the Heat up procedure, IPOP03-2G-0001:
a.
What major valves (excluding valves associa ad with RCP seals), are manipulated to form a bubble in the pressurizer AND how are they manipulated to commence bubble formation?
ALSO state applicable modes of valve control.
(1.5) b.
What are 2 indications of bubble formation stated in the procedure?
(1.0) c.
Before commencing RCS heatup, the operator is cautioned that RCP's should be started at a pressure between 325 and 450 psig.
What are the possible consequences of starting RCP's outside of this recommended pressure band?
(1.0)
QUESTION 7.02 (3.00)
During a reactor startup or startup preparation:
o.
What are the 3 items of information that are transferred from the Estimated Critical Position Calculation to the Neutron Doubling Curve Plot?
(0.75) b.
What Nuclear Instruments (NI's) will the operator select to the NR -
45 recorder, prior to control rod withdrawal?
(0.5) c.
What is the NI operability check performed between criticality and power leveling for data recording?
(0.75) d.
For the following events that occur during a normal startup, place them in the order they occur:
1.
Commence power increase to 10 (E-8) amps.
2.
Withdraw Shutdown Bank Control rods.
3.
Commence withdrawing Bank "A" Control Rods.
4.
Obtain baseline data for Neutron Doubling Curve Plot.
5.
Adj ust RCS boron concentration.
6.
Neutron counts double.
(1.0)
(*****
CATEGORY 07 CONTINUED ON NEXT PAGE *****)
Zi__EBQQEQWBES_=_NQBd8L&_8BNQBd8Lt_EdEBGENGI_8NQ PAGE 11 88DIQLQQ108L_GQNIBQL QUESTION 7.03 (2.00) a.
Prior'to cool down of the RCS, the operator is instructed to "Deges the Primary System".
BRIEFLY state how this is accomplished.
(1.0) t b.
How can the operator affect the time necessary to accomplish degassing of the RCS?
(0.5) c.
During the initial cooldown, what conditions will cause excess cooldown protection to be initiated in the form of Safety Inj ect ion?
(0.5)
QUESTION 7.04 (2.50) o.
What er the immediate action requirements if a new fuel assembly is dropped in the Fuel handling Building (FHB)?
(0.8) b.
What are 2 methods that can be used to initially ascertain whether or not the new fuel clad has been breached?
C0.7) c.
What.3 automatic actions COULO result from dropping a spent fuel assembly in the containment?
(1.0)
QUESTION 7.05 (2.50) c.
What are the major factors that may influence RCP motor winding i
temperature to INCREASE as well as DECREASE during heat up of the RCS?
(1.0) b.
What are 3 abnormalities or problems indicated by required frequent filling of RCP # 3 seal standpipes?
(0.75) c.
With a RCP seal temperature indication going off scale, what other indication should be checked to ascertain whether a seal or instrumentation problem exists?
(0.75) l 4
l
(*****
CATEGORY 07 CONTINUED ON NEXT PAGE *****)
4
Zt__EBQQEQUBES_:_NQBd8Lt_6BNQBd8Lt_EUEBGENQ1_oNQ PAGE 12 86DIQLQQIQ8L_QQUIBQL QUESTION 7.06 (2.00) c.
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)
QUESTION 7.07 (2.00)
During the performance of " Excessive RCS Leakage" (IPOPO4-RC-0003):
o.
What leakage detection systems would be indicative of a leak within the containment?
(1.0) b.
If the leak was not inside the containment (according to the above indication) or outside containment by thorough visual inspection, what other indication should be checked to indicate the source of leakage out of the RCS?
(1.0)
(*'***
CATEGORY 07 CONTINUED ON NEXT PAGE *****)
Zi__EBQQEQuBES_ _NQBd8Li 8BUQBd6Li_EMEBGEUQ1.86Q PAGE 13 B6010LQQ1Q8L_CQUIBQL QUESTION 7.08 (3.00) c.
Place the following list in the correct order of use for removing stubborn radioactive contamination on the skin of an individual with no open wounds.
1.
Titanium Oxide 2.
Soap and water 3.
Vacuum 4.
Potassium permanganate 5.
Pressure sensitive tape (1.0) b.
A 25 year old male technician is required to work in en area where the whole body dose rate is 0.150 REM /Hr.
His lifetime exposure is 1.535 REM and his current quarterly and yearly exposure is 0.1 REM.
1.
State how long may he work in the area during the current quarter and list the exposure levels reached and the approvals needed to receive the maximum exposure.
(1.0) 2.
How much time may he work in the area during the following quarter of the same year in accordance with STP administrative procedures.
Explain.
(1.0)
QUESTION 7.09 (2.00) o.
According to " Reactor Trip Response" (E0-ES01), what specific immediate actions are required of the operator if 2 control rods are not fully inserted after a trip?
(1.2) b.
After a reactor trip with stable conditions attained, what are 2 conditions that would cause the operator to actuate safety inj ect ion?
State how parameters would trend, not actual value that would precipitate operator action.
(0.8)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
Zi__EBQQEQUBE1_:_UQBdeLt_eHUQBdekt_EdEBGENQ1_68Q PAGE 14 88010LQQ106L_QQUIBQL QUESTION 7.10 (2.50) o.
Immediate action in " Reactor Trip or Safety Inj ec t ion" (E0-E000) requires the operator to verify feedwater isolation.
State the valves that must be checked to confirm proper isolation.
(0.9) b.
What are the primary and alternate methods of verifying Phase "A"
containment isolation?
(0.6) c.
When the operator is instructed to " Check for faulted S/G", what indication is observed?
(0.5) d.
With a valid safety inj ect ion, what should the condition of the Reactor Containment Fan coolers be according to E0-E0007 (0.5)
(*****
END OF CATEGORY 07 *****)
~.
A&__oDUINISIB6IIVE_EBQGEQUBEnt_GQ60111001t_60D_L1011611063 PAGE 15 QUESTION 8.01 (2.50) c.
Technical Specification LCO's specify where Shutdown Monitoring Instrumentation may be observed or read.
What are three different sources listed for obtaining " Shutdown Monitoring Instrumentation" values or readings?
(0.75) b.
What containment parameters can be monitored by " Accident Monitoring Instrumentation"?
(1.0) c.
What instrument surveillance methods as defined in Technical Specifications encompass adj ustment of alarm, interlock, or trip setpoints?
(0.75)
QUESTION 8.02 (3.00) o.
Explain why the following leakages are IN or OUT of compliance with the Limiting Condition for Operation.
Consider each individually and independent of the others.
1.
Unidentified:----------------------------------------
0.55 GPM 2.
S/G leakage;
- 1---------------------------------------------------
0.35 GPM
- 2---------------------------------------------------
0.1 GPM
- 3---------------------------------------------------
0.1 GPM
- 4---------------------------------------------------
0.2 GPM 3.
Leakage through various RCS manual vent and drain valve seats and packing glands.----------------------------
4.6 GPM 4.
Cold Leg # 3 Accumulator downstream check valve from leak check on previous shift.------------------------
3.5 GPM (2.5) b.
Considering the above leakages simultaneously, what is the identified leakage as defined by Tech. Spec's.?
(0.5) P
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
t 4
Hz__8DdIN111BoIIVE_EBQQEQUBESt_QQNQ1IIQNSt_8NQ_ lid 11oI1QUS PAGE 16 QUESTION 8.03 (2.50)
Explain why the SRO SHOULD or SHOULD NOT allow the following evolutions to cccur.
Assume the unit is at full power and state ALL considerations.
o.
A craftsman wants to check the fit of a newly designed gagging device 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 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) 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 leakage detection systems.
(1.0)
QUESTION 8.04 (1.50)
Ocscribe the site review process for a Technical Specification inter-pretation request.
(1.5)
QUESTION 8.05 (3.00) c.
What are 3 types of activities toat are considered to be preventative maintenance?
(0.75) b.
Is a Maintenance Work Request t.1W R ) normally required to perform preventative maintenance?
(0.4) c.
Who is responsible for providing work instructions in emergency situations?
(0.6) d.
What are 3 additional permits that may be required to properly process an MWR7 (0.75) o.
What is the administrative tool for providing safe system alignment for maintenance?
(0.5)
(*****
CATEGORY 08 CONTINUED ON NEXT PAGE *****)
r At__6Dd1N111BoIIVE_EBQQEQUBEft-QQUDIIIQUSt_6NQ_LIMII6IIQU3 PAGE 17 QUESTION 8.06 (2.50) c.
Who are the issuing authorities for clearances?
(0.75) b.
How are clearances issued in cases where interface boundaries are crossed?
(0.5) c.
Is a clearance verifier normally allowed to rely on local / remote indication for verification?
Explain.
(0.5) d.
What restrictions, if any, apply to adding tags to an active clearance?
(0.75)
QUESTION 8.07 (3.00) c.
What computer printouts should be collected for use in the post - trip review?
(1.0) o.
For category 2 and 3 reactor trips, who has authority to allow restart and who's recommendations are solicited in making the decision to restart?
(1.0) c.
What is the major responsibility of on shift operations personnel while a post - trip review is ongoing?
C0.5) d.
Who has responsibility for conducting interviews with plant personnel involved with the trip?
(0.5)
QUESTION 8.08 (3.00) c.
For the organizations listed below, assume a Site Area Emergency has been declared and state ; time allowed to make initial notification, normal method of notification, and alternate (backup) method of notification.
1.
Texas Dep't of Public Safety 2.
INPO 3.
Matagorda County Sheriff 4.
NRC (2.0) b.
When should followup notification to state and county officials begin and what is the preferred method of transmission?
(1.0)
(*****
CATEGORY 08 CONTINUED ON NEXT PAGE *****)
Ax__6DdIN11186IIVE_EBQQEQUBE1x_GQNQlIl0 Nit _6NQ_ lid 1I8IIQN3 PAGE 18
' QUESTION' 8.09 (2.50) i o.
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.
i i
i.
i
(***** END OF CATEGORY 08 *****)
(*************
END OF EXAMINATION ***************)
It__IHEQBI_QE_NWGLE88 EQWEB_ELeNI_QEEB81196t_ELWIQ1t_6NQ PAGE 19 IBEB5001N651G1 ANSWERS -- SOUTH-TEXAS 1
-86/11/13-WHITTEMORE, J.
[
I ANSWER.
5.01 (1.00)
'b.
(The second' reactivity addition was smaller)
REFERENCE LP.RXT.09, p.
5 ANSWER 5.02 (2.50) c.
Power is too low to meet requirements of P-6, therefore the source range scram is in effect and will occur at 10 (E5) CPS. (0.5)
.001/1.001 = 0.001
- 1. Reactivity ~ change in keff or 1-Keff/Keff
=
2.
Period =.007 -.001/0.1(0.001) = 60 seconds 3.
Ln P/Po = t/T
= Ln 100 at/60
- 4.. Time before trip occurs " 276 seconds (Accept any answer between 3 1/2 and 6 minutes if viable correct concept is used to evaluate answer.)
(1.0)
(1.5) b.
Reactor power will continue increasing until POAH where the increase in fuel (and moderator) temperature will add negative reactivity to stop power-increase. (0.5)
Final power will be near POAH. (0.5]
(1.0)
Accept power level between PA0H and 10%.
REFERENCE STP Theory, Ch. 5 Pp.5-17 STP SD RPS, P.16 ANSWER 5.03 (2.00) c.
Nothing (0.5) b.
Xenon concentration initially dips (0.5] as increased flux results in increased burnout, (0.25] but iodino does not immediately increase to the new level. (0.25]
(1.0) c.
Approximately 250 pcm. Accept 240 -260 pcm.
(0.5)
li__IBEQBl_QE_NWCLE88 EQWEB_EL8NI_QEEB8110Nt_ELu1Dit_8bD PAGE 20 IBEBdQQ1Ned1GS ANSWERS -
SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
REFERENCE STP QUESTION BANK, Pp. 88,89 l
l ANSWER 5.04 (2.50) c.
LESS NEGATIVE [0.25] More boron to leave core area per degree temperature change. (Or equivalent answer)
(1.0) b.
MORE NEGATIVE [0.25] Less boron, opposite result as above.(0.25] (0.5) c.
LESS NEGATIVE (0.25] Water density changes are less as temperature is reduced.
(1.0)
REFERENCE STP Reactor Theory, Chapter 8, Pp 6,8 i
ANSWER 5.05 (3.00)
Ao dilution occurs, Control rods move in, [0.2) power in upper core goes down, (0.2) power in lower core goes up. (0.2]
i UPPER CORE:
Initially, lower power reduces burnout, causing Xenon to increase, causing further power reduction. (0.6) Later Xe will decrease as decay from iodine decreases. (0.3)
This allows power to increase reducing Xe due to increased burnout. (0.3)
LOWER CORE:
Initially, power increase causes increased Xe burnup, causing power to increase further. (0.6]
Later as iodine concentration increases, increased Xe forces power down, causing more Xe buildup. (0.3)
Xe will decrease after iodine inventory starts to decay and cycle will repeat. (0.31 (3.0)
CONCEPT l
REFERENCE l
STP QUESTION BANK, P. 01 l
I ANSWER 5.06 (2.00)
Initial drop due to buildup of fission product poisons, (0.5) followed by a lovel region caused by burnout of burnable poison rods adding positive roactivity as fuel is depleted. (1.0)
Concentration drops gradually as l
fuel depletes over remaining core life. (0.51 (2.0)
L
It _IHEQBl_QE_NWGLE88 EQWEB_EL8NI_QEEB8Il0Nt_ELW1QEt_8NQ PAGF 21 IBEBdQQ1NedIGE l'
l ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
l L
REFERENCE t
LP.RXT 10, P.
9-ANSWER 5.07 (2.00) o.
Supplement dissolved boron and provide (~ 4.65 %)
-k.
to balance l
I reactivity due to fuel burnup. OR accept positive MTC conceptual explanation.
(1.0) l I
b.
May be added for flux shaping.
(1.0)
REFERENCE LP.RXT.10, P. 9 ANSWER 5.08 (1.00) c.
(245 psig.)
(1.0)
REFERENCE Steam Tables t
ANSWER 5.09 (2.00) c.
. Perform a heat balance calculation across the regenerative HX (0.51
(
by using delta T across both side of HX (0.25) and letdown flow rate r
(0.25] to determine charging flow rate.
(Allow 1/2 credit for Chg. flow = L/D flow + Seal L/0 - Seal inj. flow with Pzr. level constant.)
(1.0) r b.
- 1. Increase 2.
Increase i
3.
Increase (0.33 es.)
(1.0)
Accept other answer if supported by viable assumption.
REFERENCE STP HT & FF, Pp. 243, 319-334 f
i I
11..IHEQBl_QE_NUGLE68_EQWEB_ELeNI_QEE86Il0Nt ELU10St_8NQ PAGE 22 IHEBbQQ1N8bl0S ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
I i
ANSWER 5.10 (2.00)
S/G heat transfer = Q = UACTavg - Tatm)
(0.25)
Q, U, Tatm remain constant;
-[0. 2 5 ]'
A1(Tavg1 - Tatm) = A2(Tavg2 - Tstm)
[0.5)
Given: A2 = 0.9 x Al From Stm tables: Tsat for 995 psia = 544 F.
[0.5) i A1(587 - 544) 0.9A1(Tavg2 544)
=
q Tovg2 = 591.8 (Accept 591 - 592.5)
(0.5]
(2.0) l REFERENCE l
I ANSWER 5.11 (2.50) c.
Core exit temperaturet Rise as core temperature rises.
(0.5)
Cold leg temperaturet.
Remain relatively constant.
(0.5)
I Steam pressuret Decrease (as boil off occurs)
(0,5)
J b.
1.
Restrictions to flow (from valves, bends, elbows, and other restrictions) are minimized.
(0.25) i' j
2.
Maximum elevational difference between center of heat generation j
and center of heat removal.
(0.75) t i
REFERENCE STP HT & FF, Pp. 355-357 l
l t
V k
j
'i
Ei__IBEQBl_QE_UUQLE88_EQWEB_EL8HI_9EEB8Il08t ELU10St_eUD PAGE 23 IBEBdQQ1U8dIQ2 ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEt10SE;* J.
ANSWER 5.12 (2.50) c.
The HCF would decrease (0.25] as a reflector woulactend to flatten the neutron flux and make the peak / average ratio closer'to 1.0, (0.75)jf/
t b.
The HCF would decrease (0.5] as the higher -flow rete'wos1d decrease I
core delta - T, (0.5) and flux would be less skewed toward nottom of.
core, putting the ratio closer to 1.0. OR, ONBR increases f (1.0) c.
The HCF would increase (0.25] as flux would be more heavily skewed toward the bottom portion of the core, (0.5)
~ (0.75)
REFERENCE STP HT & FF,Pp. 190-195 i
'(
/
t t:
h s
/
t 1
s x
l o
m
r * ' '
+
, q ht. EL8HIlh11IEdi_DE11GNi_QQNIBQLi_8NQ_IN11BudENI8IIQN PAGE 24 ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
/ :/
L y.
1 AN'SWER 6.01 (2.50)-
r R.
! $d,
c.
125 OC and 480 AC. (0.5)
Normal 480 VAC is rectified.to DC and then E '. "
inverted to'broduce 120 VAC. [0.5)
(1.0) i b.
A voltage regulator supplied from a different 480 V MCC than the one supplying the inverter.
(0.5) c.
Class: A manually operated bar interlock permits energizing from either source if the other source is open.
(0.5) 1 Non-ci'Jss: The auto transfer switch will select only one source at a time.
(0.5)
' ~
e.
REFERENCE
.SO~ Class 120VAC, PS & Non-class 120VAC, PS,6 go ANSWER 6.02 (1.50) o.
The RWST level signal that auto initiates cold leg recirculation also closest (HS1 pump mini-flow recire. valves to RWST.
[0.5)
Continued loperati'on of the pumps will result in damage.CO.25)
(0.75) b.!,heiumblator inj ection causes' increased RCS depressurization and results in increased ECCS pump injection rates.
OR; Injects a large volume of water when LHIS is not available.
(0.75)
,1-
'l 9 0
$j ' '14 w
_A F
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\\v A
\\) ANSWERS L ' SOUTH TEXAS L)
-86/11/13-WHITTEMORE, J.
\\'
\\
ANSWER 6.03 (2.50) c.
Minimum:
Maintain Iodine in solution.
(0.5)
Maximum:
Prevent caustic attack on RCS and Sump metals; (0.5) 3 b.
(~ 3psig) N2 [0.25] to prevent NaOH degradatioW. [0.25]
C0.5)_
Reduces containment press 0re t'o reduce leakage and minimize leakage to c.
offsite.
5 V
.(0.5)
I Entraps fission products in so1Ution and prevents their escape to the atmosphere.
(0.5)
- ~
f REFERENCE 4
'g ANSWER ~
6.04
- (2. 50)
N L 7
')
1 a.
.1.
\\-
2.
Essential EAB HVAC ghillers
'-y 3.
CCW Pump supplementary (room) cooler (0.25 ea)
EDG secepted buthnot required.
(0.75)
\\;
4 b.
Normal:
1 train operat;ing.
l' train in standby, 1 train off.
(0.5)
Startup or shutdownI Switch to 2 trains. operating, 1 in standby.(0.25) c.
1.
Start ECW disct arge strainer.
2.
Open ECW blowdown.
3.
Open pump discharge valve.
(
4.
Provides signal to Sodium Hypochlorinator.
yy.
i Starts ECW room vent fans.
^6.
- Starts tr4yeling screens.
7.
Starts screen wash pumps.
(Any 4, 0.25 ea.]
(1.0) 1
'T I
REFERENCE SD, ECW,-Pp35,6 I'
s T
k N_;
.m-
e ht__EL8NI_11SIEda_DE11ENt_QQNIBQLt_eNQ_INSIBudENIol1QN.
PAGE 26 ANSWERS ~-- SOUTH TEXAS l'
-86/11/13-WHITTEMORE, J.
. ANSWER 6.05
[3.00) o.
Increasing radiation level, increasing surge tank level, and an increase in temperature or flow downstream of the Reactor Coolant Pump
' thermal barrier.
[0.33 ea.]
[1.0) b.
LOOP, SI, Low pressure in CCW, Low pressure in ECW [0.25 ea.]
[1.0) c.
- RHR HX, RCP Thermal Barrier, Letdown HX, Excess Letdown HX, Seal Water HX, RCDT HX.
[0.167 ea)
[1.0)
REFERENCE STP QUESTION-BANK
' ANSWER 6.06
[2.50) e.
1.
Turbine bldg. sump and drain system.
[0.25]
High rad. level stops the sump. [0.25]
2.
Condensate polishing system.
[0.25]
High rad. stops flow to the naturalization basin.
[0.25]
3.
S/G blowdown.
[0.25] High rad. stops flow to naturalization basin.
[0.25]
[ANY 2, 0.5 EA.]
4.
Cond. air removal sys. [0.25]
No automatic action.
[0.25]
[Any 2, 0.5 ea.]
[1.0) b.
HP Office, TSC, MCR. [0.25 ea.] Accept computer rm.,
no credit (0.75) c..
1.
Grid display 2.
Trend display 3.
Group display
[0.25 es.]
[0.75)
REFERENCE LP RMS II, Pp.13,14,15,17
ht__EL8HI_SYSIEUS_DESIDNt_QQUIBQLt_6NQ_INSIB9dENI61100 PAGE 27 ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 6.07 (3.00) c.
To provide fast control rod response (and stability)
(0.75) b.
Turb Inpulse Pressure & Auct. Hi Nuc. power (0.5) c.
Will cause an insert or withdraw signal only while failure is occurring-
[0.53 as mismatch is a rate error signal and static mismatch will not result in auto rod motion.[0.53 (1.0) d.
A non-linear gain unit will cause a larger mismatch for a larger load change as a larger change requires a larger reactivity change.
(0.75)
REFERENCE LP, R0D CONTROL, Pp. 21,22 ANSWER 6.08 (2.50) c.
Allows control rod testing or withdrawel at low temperature.
(0.75) b.
3/4 Power range chmnoels less than 10% [0.25] AND [0.25) 2/2 Turbine impulse power les, thsn 10%. [0.25]
(0.75) c.
1.
Low Pressurizer Pressure.
2.
RCP undervoltage 3.
RCP underfrequency 4.
Low flow
[0.25 ea.]
(1.0)
REFERENCE LP, SSPS, Pp. 10.17 ANSWER 6.09 (2.50) a.
The control signal is from the Pressurizer Master Controller and the actual operating setpoint is modified by duration [0.75) as well as rate of change. [0.75)
Accept explanation of PID controller for full credit.
(1.5) b.
An interlock signal prevents automatic operation below (2185) psig.
[0.5)
The interlock signal is provided by another channel. [0.5][1.0)
REFERENCE LP, PRESS. CONTROL, Pp. 9,12
A t-J61__EL8HI_1111 EMS _DESIGNi_QQNIBQLt_8NQ_IN11BVMENI8IIQN.
PAGE 28-ANSWERS - ' SOUTH TEXAS 1
.-86/11/13-WHITTEMORE, J.
' ANSWER-
- 6.10 (2.50) la.-
1.
T u'r b ine - t r ip.
2.-
Feedwater' pumps trip 3.
FW, isolation valves close
- 4.
FW reg. valves close
( 0.'2 5 e s.' ).
(1.0)
Accept "Feedwater Isolation" in lieu of # 3 & 4.
b.-
_ Cont.-press. I (5.0 psig) [0.5) initiates SI [0.25]
(0.75).
H1' press. stm rate. [0.5) causes main stm. isolation [0.25]
C0.75)
REFERENCE SSPS,.Pp. 15-18 J.
l f
r I
e-
-9
-w-,.-
,-,w-y,,-,.
,,,,...., ~,,
..e%-..,.--.-+,
,ymw.-_4
.., g
,,, - +,
-,, - - -. - - - - -. ~,,
E
]
Zt__EBQQEDVBE1_:_NQBd6Lt_6BNQBd8kt_EdEBGENQ1_6ND PAGE 29-B8DIQLQQ198L_QQNIBQL
-ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
LANSWER 7.01 (3.50) s.
The Charging Flow Control valve (1*CV-FCV-0205) [0.5] is closed in the manual mode. [0.25]
The Letdown Pressure Control valve (1*CV-PCV-135) [0.5] is placed in auto and set to maintain (150 -250 psig) pressure. [0.25]
(1.5) b'.
Increasing letdown flow rate [0.53 and a marked decrease in pressurizer heatup rate. [0.5]
(0.25 for " Verify Pzr. sat. conditions).
(1.0) c.
Less than 325 psig may~cause damage to RCP seals, [0.5] while being greater than 450 psig may cause failure of the RHR system.~ [0.5] (1.0)
REFERENCE 1 POP 03-ZG-0001, Pp. 5-7
' ANSWER 7.02 (3.00) e.
ECP, ECP + 500 PCM, ECP - 500 PCM
[0.25 es.]
C0.75)
E b.
Highest reading SR, [0.25] and Highest reading IR. ]0.25]
C0.5) c.-
Ensure Cat least 1 decade) overlap between SR and IR.
(0.75) d.
5, 2,
4, 3,
6, 1
[Sub' tract 0.25 points for each perturbation 0R; 2,
5, 4,
3, 6,
1 necessary to achieve proper order.]
(1.0)
REFERENCE 1 POP 03-ZG-0004, Pp. 3-7 ANSWER 7.03 (2.00) c.
A nitrogen cover blanket is established in the VCT [0.5] and the pressurizer vapor space is vented.
[0.53 (1.0) b.
By-controlling letdown flow (# of orifices on line).
(0.5) e
- c.. Less than 532 F.
while greater than 1950 psig RCS pressure.
(0.5)
.Zi__EBQQEQVBER_ _NQBd8Li_8HNQBd8Lt_EdEBQEUQ1_8NQ PAGE 30 88Q1QLQQIQ8L_QQUIBQL-JANSWERS'--' SOUTH TEXAS l'
-86/11/13-WHITTEMORE, J.
REFERENCE 1 POP 03-ZG-0007, Pp4,5 ANSWER 7.04 (2.50) e.
Immediately-evacuate the FHB [0.43 and notify the control room. [0.43 (0.8)
.b.
Health and Safety,obtain samples (0.35 ) and perform a visual inspection [0.35]
.(0.7) c.
1.
Trip and isolation of containment purge.
2.-
Trip and isolation of supplementary containment purge.
3.
Isolation of containment atmosphere monitor (1-HF-RA-8011)
[0.33 ea.]
OR; 'Contaiment Ventilation Isolation (1.0)
REFERENCE 1POPO4-FH-0001, P.1 1POPO4-FH-0003, Pp. 1,2 ANSWER 7.05 (2.50)
-a.
May decrease as the fluid being pumped becomes less dense and less winding current is required. [0.5)
May increase due to increased atmosphere temperature.'[0.53 (1.0) b.
1.
Damaged seal
-2.
Worn seal 3.
Seal not fully seated 4.
Leak in RHR 5.
Stand pipe leak
[Any 3, 0.25 ea.]
(0.75) c.
1.
Inj. temp.
2.
Inj. flow 3.
Leskoff flow 4.-
Other RTD.
[Any 3, 0.25 ea.]
(0.75)
REFERENCE 1POPO4-RC-0002, Pp. 11-13
'Zz__EBQQEQVBE1_ _NQBd6Lt_8ENQBd8Lt_EDEBQEUQ1_6ND.
PAGE 31 88DIQLQQ108L_QQNIBQL.
ANSWERS -- SOUTH YEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 7.06 (2.00) e.
~Whether the failure is in the control system (0.5] or due to friction
/ mechanical interference. [0.53 (1.0) b.
Go to manual, [0.53 and trip reactor if motion continues. [0.53 (1.0)
REFERENCE 1POPO4-RS-0002, Pp.1,2
' ANSWER 7.07 (2.00) a.
1.
Containment atmosphere monitoring system.
2.
-Sump. level and flow monitoring system.
3.
RCFC drain flow monitoring system.
[0.33 ea.]
(1.0) b.
'i.
RCDT Clevel,. temp.)-
2.
PRT (level, temp.)
3.
S/G (activity, feed /stm flow, level)
[0.33 ea.]
(1.0)
REFERENCE 1POPO4-RC-0003,Pp.2,3 ANSWER
'7.08 (3.00) a.
3, 5,
2, - 1, 4 (subtract 0.25 for'each perturbation necessary to achieve correct order)
(1.0) b.
1.
May receive a dose of 2.75 - 0.1 =2.65 this qtr.
May stay in the area for: 2.65/.15 = 17.66 hrs. (accept 17.35 - 18.0) [0.53 Needs approval to exceed 1.0 REM by Radiation Protection Supervisor
[0.25) and 2.0 REM by the Plant Manager. [0.25]
(1.0 (Also accept DM/DS) 2.
STP administrative limit is 5.0 REM /Yr. [0.5)
Allowable dose is:
5.00 - 2.75 = 2.25/0.15 = 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />. [0.5 (1.0)
REFERENCE OPR08-ZC-0002, Pp. 4,7,8 i
OPG03-ZR-0006, Pp.3,4
Zia_EBQQEQUBEl_=_NDBd6Lt_6ENQBd6Lt_EMEBQENQ1_6NQ
'PAGE. 32' 88Q10LQQ198L_QQNIBQL-86/11/13-WHITTEMORE, J.
ANSWERS ~--: SOUTH TEXAS 1 TANT.WER 7.09 (2.00) c.-
' o' Start' boric acid pump.
o Open boric acid flow control valve.
o Verify > 30.GPM flow.-
(0.4 ea.)
(1.2) b.
Decreased subcooling.
Decreased pzr. level.
(0.4 ea.)
(0.8)
REFERENCE 1 POP 05-E0-ES01 ANSWER
_7.10
-(2.50) s.~
oc : Flow control valves
~
o Flow control valve bypass valves o
FW-isolation valves o
FW isolation B/.P valves o
- S/G blowdown isolation
- o Sample isolation
- (0.15 ea.)
-(0.9).
-b.
Primary:.
ERFDADS Alternate: MC8 Indication (0.3 ea.)
(0.6)'
c.
S/G pressure (0.5)
'd.
Running, cooled by CCW.
(0.5)
REFERENCE-1 POP 05-E0-E000, Pp,9,11,23 t
I t
y
-~
ru, y
e
+,,,r,,
---.-wy w.y,,-
,wp.m.
y g
+
w m,
-r-
--.a,-
s
,-ea
,~
Az__8DMIN11IB8IIVE_EBQQEQUBEst_GQNkII1QNSt_8NQ_ lid 1I8I1QNH PAGE 33~
~
ANSWERS -- SOUTH TEXAS 1-
-86/11/13-WHITTEMORE, J.
' ANSWER 8.01' (2.50) s,-
Local indication ASP indication.
QPDS indication MCR indication (Any 3, 0.25 ea.]
(0.75) b.
Pressure Radiation Sump level Hydrogen concentration (0.25 es.]
(1.0) c.
Calibration Analog channel op. test Digital channel op. test (0.25 ea.]
(0.75)
REFERENCE STP TS Pp. 3-59, 3-64, & DEF'S ANSWER 8.02 (3.00) a.
1.
In compliance as the limit is 1 GPM.
(0.25) 2.-
In-compliance on total leakage limit of 1 GPM, (0.5] but not in compliance on daily leak rate limit of-500 GPD on # 1 Steam Generator. (0.5]
(1.0) 3..
OK, allowed 10 GPM identified leakage.
(0.5) 4.
In compliance (0.5] as pressure isolation valves are allowed 0.5 GPM' leakage per inch of nominal valve size. (12") (0.25] (0.75) b.
8.85 GPM (0,5)
REFERENCE STP TS, P.
3/4 4-20
fat __6DMIN11188IIVE_EBQGEQVBESt_QQNQII1QNSt_6NQ_LIMII611QNH PAGE 34 YANSWERS -- SOUTH TEXAS 1-
-86/11/13-WHITTEMORE, J.
ANSWER 8.03 (2.50) e.
Should not allow
[0.25) as action must be taken to reduce power if Safety is inoperable for 15 minutes. [0.25)
(0.5) b.
May be-allowed [0.5) if block valve can be shut. [0.25)
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.] [0.25)
(1.0) c.
Msy continue to operate (for 1 month) [0.5) if daily containment grab samples are taken. [0.5)
(1.0)
REFERENCE STP TS, Pp. 3/4 4-9, 11, 14 ANSWER 8.04 (1.50)
From requestor to:
Applicable DM/DS Toch. Support Superintendent PORC Plant Mgr.
[0.3 for es. step a 0.3 for correct order.)
(1.5)
REFERENCE PGP3-ZO-18, P.
4 ANSWER 8.05 (3.00) n.
Lubrication, calibration, routine maintenance, inspection.
[Any 3,-0.25 ea.)
(0.75) b.
NO.
(0.4) c.
Shift Supervisor (0.6) d' Confined space entry permit, Painting permit, Flame permit, RWP
[any 3, 0.25 es.)
(0.75) o.
Equipment Clearance (0.5)
REFERENCE STP QUESTION BANK
e fi__6Dd1811186IIVE_EBQQEQMBEft_QQNDIIl0N1t_660_LidII6110NS PAGE' 35 ANSWERS -- SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 8.06 (2.50) c.-
Shift Supervisor, Chem. Ops. Foreman, Maint.Sup's.
(0.25 ea.]
(0.75) b.
'A single clearance is issued (0.253 by the issuing authority who has requested the equipment be cleared. (0.25]
(0.5) c.
May rely on indication only if manual verification impractical.
(0.5)
-(Accept-any example of impracticality) d.
Tags may be added only if they are requ' ired for the original scope of the work.
(0.75)
REFERENCE OPGP3-ZO-0001, Pp.6,8,12
' ANSWER 8.07 (3.00) c.
Pre trip / Post trip log (ERFDADS & PROTEUS), Transient log, Control room alarm printout, and SOE printout.
(0.25 ea.]
(1.0 b.
The Plant Mgr. allows restart (0.33 based on recommendations from SS for CAT. 2 trips (0.35] and PORC for CAT. 3 trips. (0.35)
(1.0) c.
-To maintain the plant-in a safe condition.
(0.5) d.
(0.5)
REFERENCE OPGP03-ZO-0022, Pp.4,5 1
n fat __6DMIN11186IIVE_EBQQEQMBEft_QQUQ1110NS _eug_ lid 1I6110NS PAGE~ 36 t
ANSWERS -
SOUTH TEXAS 1
-86/11/13-WHITTEMORE, J.
ANSWER 8.08 (3.'00) e.
TIME METHOD ALTERNATE 1.
15 Min.
Designated line Comm. telephone 2.
no limit Comm. Telephone Comm. telephone 3.
15 Min.
Designated line Comm. telephone
-4.
1 Hr.
EtlS Comm. telephone
[0'2 es.]
[0.2 ea.]
[0.1 ea.]
(2.0 b.
As.soon as the initial notification are completed [0.5] via telecopier,(also accept d e d ic at e d line")
'[ 0. 5 ].
(1.0)
REFERENCE.
OEPP01-ZA-0003, Pp.3,4,5,14 ANSWER 8.09 (2.50) c.
1.
Onshift response organization 2.
Initial response organization 3.
Emergency response organization
[0.25-ea.]
(0.75) b.
1.
Brief successor 2.
Notify offsite response organizations 3.
Document the turnover
[0.25 es.]
(0.75) c.
Personnel.are required to' report to an assembly area where a.
coordinator. accounts for all personnel and reports to the Security Manager.
(1.0)
REFERENCE.
C, Pp. 2,3 SECT F, P.2
_