ML20235V080
| ML20235V080 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/07/1987 |
| From: | Bjorgen J, Burdick T, Mark Daniels, Keeton J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20235V076 | List: |
| References | |
| 50-263-OL-87-02, 50-263-OL-87-2, NUDOCS 8710140557 | |
| Download: ML20235V080 (114) | |
Text
_ _ _ _ _ _ _ _ _ _ -
U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-263/0L-87-02 Docket No. 50-263 License No. DRP-22 Licensee: Northern States Power Company 414 Nicollet Mall i
Minneapolis, MN 55401 Facility Name: Monticello Nuclear Generating Station Examination Administered At: Monticello, Minnesota Examination Conducted:
September 1-3, 1987 Examiners:
J. M. Keeton c #/
/8/7/ 7 Chief Examiner Dat'e
/f
/87 J. Bjorgen M. Daniels c//
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Date Approved By:
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/U 7b2 Operating Licensing Section Date Examination Summary Examinations Administered on September 1 g, 1987 (Report No. 50-263/0L-87-02))
Written, oral, and simulator examinations were administered to five Reactor Operator (RO) and one Senior Reactor Opernor (SRO) candidates.
Results: One SRO and four R0s passed all portions of the examination; one R0 failed the written examination.
8710140557 871000 hDR ADOCK 05000263 PDR
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REPORT DETAILS 1.
Examiners J. M. Keeton, Region III, Chief Examiner J. Bjorgen, Region III M. Daniels, Sonalysts, Inc.
2.
Exit Meeting l
An exit meeting was conducted on September 3, 15'87, with the following persons in attendance:
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Northern States Power L. Eliason, General Manager, Nuclear Plants W. Shamla, Plant Manager, Monticello D. Antony, General Superintendent, Operations G. Earney, Training Superintendent M. Brandt, Operations
'R. McGillic, Operations Traisiing Supervisor USNRC J. M. Keeton, Chief Examiner J. Bjorgen, Examiner M. Daniels, Examiner The following items were discussed during the exit meeting:
a.
A potential weakness exists in the Abnormal Procedures. The immediate actions in the majority of the procedures are, " Verify Automatic Actions and Notify Shift Supervision." However, subsequent actions include actions that must be performed in a very short time span and would appropriately be considered as immediate actions. A specific example is " Loss of RBCCW," which requires tripping the recirculation pumps and scramming the reactor within 60 seconds as subsequent actions. A recommendation was made to facility management that these procedures be reviewed and revised to clarify those operator actions that should realistically be considered inmediate actions.
b.
In the previous Exam Report, No. 50-263/0L-87-01, dated April 23, 1987, the E0Ps were identified as being a potential problem area.
The primary concern was that the E0Ps are not " user-friendly."
Although the same concern exists because no changes have been made, facility management stated that they have contracted an outside organization to upgrade the E0Ps.
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.1 3.
Examination Review Copies of the written examinations and answer keys were given to facility personnel at the conclusion of the written examination. The finalized exam comments were received September 10, 1987.
Facility Comments and NRC Resolutions are included as Attachment 1 of this' report.
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y ATTACHMENT 1 1
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' WRITTEN EXAMINATION COMMENTS AND RESOLUTIONS REACTOR OPERATOR AND SENIOR REACTOR OPERATOR EXAMINATION ADMINISTERED SEPTEMBER 1, 1987
~DocketLNo. 50-263 Comment:
1.02 Answer The answer for Part 2 actua11y'contains three reasons for the power decrease:
1.'
-Recirculation pump 'down shift (run back) adding negative reactivity due to void coefficient.
2.
Reduced feedwater flow adding negative reactivity due to void coefficient.
3.
Decreasing reactor water level adding negative reactivity due to void coefficient.
Any one of these answers should be sufficient for the second reason.
Resolutions Comment partially accepted. Answer key changed to accept the following:
1.
(The decreased feed flow results in) decreased subcooling which adds negative reactivity due to.the moderator coefficient.
2.
The recirculation pump down shift adds negative reactivity due to the void coefficient.
3.
(The reduced feedwater flow results in) decreased subcooling which adds negative reactivity due to the void coefficient.
4.
(Provided the candidate states the assumption that the l
recirculation pumps trip on low reactor water level) decreasing' reactor. level adds negative reactivity due to the void coefficient.
]
(Any one of Responses 2, 3, or 4 for 1.0 points.)
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. Attachment 1-2 l;
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, Comment':
.y
'I.05 Answer'
.a.
Candidate may include Pu-241 which also has a lower delayed neutron fraction than U-235.and U-238.
~
Reference:
GE Station Nuclear Engineering Manual March 1982, Page 2-2.
NOTE:
This was covered:in class'and changes are
-being incorporated in the-text and lesson plans.
- Resolution:
Comment noted.
Full credit for Part a will be given provided
.the candidate states Plutonium 239 and 241 or Plutonium 239.
Answer key changed.
Commertt:
1.06' Answer
'b.
Candidate'may also list - to minimize the chance
-of losing pump prime.
Ref'erence:
GE Heat Transfer and Fluid Flow, 6-109 Resolution:
Comment accepted.. Answer key for Part b changed to the following:
1.
. Limit pump starting current [0.125]
2.
Minimize fluid hammer in downstream piping [0,5]
3.
Minimize the possibility of losing _the pump prime [0.125]
Comment:
1.10 Answer l
The Monticello Off Gas System contains no charcoal beds or
-l dryers. The system does contain a preheater which performs the same function as a dryer.
Answer should be to prevent the recombiner catalyst from being wetted to ensure proper operation (or similar wording).
Reference:
B.7.2-0030 Resolution:
Comment partially accepted. Answer key changed to the following:
(
4 The preheaters are installed to remove moisture which would prevent the recombiner catalyst from operating properly.
[1.0]
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4 Commenti
.l.11 Answer-p 4
.a, bL and c Candidate.may.use actual Monticello values 4
s 3
- for Xe reactivity with 100% equilibrium Xe' reactiv'ity
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of approximately. - 2%.
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Reference:
' Nuclear. Engineer Xe Program JResolutioni
-Comment noted. Question, answer, and points deleted from
'y examination. Answer key changed.
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4 Comment:
1.12 Question
~ "
o 10 CFR 55. Part 41,(Page 55 5) states, that "The written h,
.g, examination for :an operator for a ' facility will. include fj a representative sample'from(among the following 14 items,"
.g f g
.etc.
10 CFR 55 Part:43 states that the~ written examination
'Vi' M
for a Senior Operator will ~ include the same items, plus
" Facility ' Operating Limitations in the Technical Specification and their' Bases."-
This has.been interpreted in the past that a R0 candidate does-not have te be as cognizant of the bases as a SR0 candidate;.
therefore, we do not emphasize bases as strongly to the R0 candidates and we doLnot test on bases questions. We feel -
N that this is~an inappropriate question.
Reference:
10 CFR 55 Resolutions Comment accepted. Question, answer and points deleted from the examination. Answer key changed.
,C gment:
1.13 Answer f
S Candidate'could also describe the inverse response to rod movements as contained in C.2 Power Operation.
,n.
Same information, different wording.
/,leference:
C.2-0021 y9 o
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" Resolution: E Comment noted.
Full cred4L will be allowed provided the candidate states the correct concept. Answer key changed to include the statement " alternate wording accepted."
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g Comment:
1.15 Answer i
g Candidate could also list (" Promote even control rod burnup."
k
Reference:
C.2-0017 Resolution:
_ Comment partially accepted. Answer key changed to the folicwing:
1.
Promote even fuel depletion (burnout) [0.5]
2.
Promote even condrol: rod wrrth [U.5]
Comment:
2.02 Answer o
.e b.
Two other acceptable answers are:
1.
Combusti&,e as Control Syst.em.(CGCS)
CoolinghowerPumpsandFans 2.
Reference:
B 9.6-0012
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Resolution:
Comment accepted. ' Ar swer key for Part b changed to include the additional. correct responses.
The. pint value for the question remains at five responses at 0.25 poin',s each.
Comment:
2.05 Answer b.
Per the updated lesson plan and Operai, ions Manual, this answer could be worded:
1.
Not full open of either the irlet isolation valves (M0-2397,M0-2398).
]
2.
Full closure of the return isolation valve (M0-2399).
3.
Pump bearing high cooling water temperature.
Reference:
B.2.2-0006, M8107-030, Revision 3, Page 10 Resolution:
Comment partially accepted. Answer key for Part b changed to the following:
1.
Pump bearing cooling water high temperature [0,5)
I 2.
Full closure of the return isolation valve (MO-2399)
[0.25] or either of the inlet isolation valves (MO-2397
)
i or 2398) not full open [0.25]
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b l
l Comment:
2.06 Answer Candidate could also phrase the answer, "to prevent thermal and mechanical stresses to the motor windings."
Reference:
B.I.4-0050 Resolutian:
Comment partially cccepted. Will accept the following alternate answer:
"To prevent thermal and mechanical stresses to the motor windings from starting current heat."
.omment:
2.08 Question and Answer This question is susceptible to multiple interpretation and does not elicit the answer given.
The main condenser /
off gas system also includes the recombiner system; the six recombiner trips should also be acceptable answers.
Recombiner trips:
1.
High off gas flow 2.
Low dilution steam flow 3.
High eductor discharge pressure 4.
High off gas radiation levels 5.
High outlet hydrogen concentration 6.
Two of three analyzers disabled in the operating train
Reference:
B.7.2-0011 Resolution:
Comment accepted.
Answer key changed to include the additional correct responses.
Point value for the question remains at six responses at 0.4 points each.
Comment:
2.10 Answer The question does not elicit the answer given, in that it asks why both heater hand switches are never placed in the on position while operating SBGT in manual, it does not ask for what resulting damage will occur. The answer supplied in the answer key was taken from the SBGT lesson plan and used in class as amplifying information. We teach the candidates to answer question whenever possible per the Monticello Operations Mar.ual.
The General Precautions section of B.4.2 (SBGT) contains information on not placing heater switches in "on" while running in manual.
The candidates have been informed as part of their
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watch standing' 0JT that these heaters will not trip on high temperature while in manual and therefore should not be-used, this should also be a correct answer.
Reference:
B.4.2-0035, 0036 Resolution:
Comment accepted. Answer key changed to accept the following alternat. answer:
The heater should not be used while in manual operation because the heaters will not trip on high temperature.
Comment:'
3.01 Question and Answer a.
Que> tion is "open-ended" in that it does not specify the number of responses required for full credit nor does it separate tne point totals between Parts a and b which the candidate could use for guidance.
NUREG-1021, Revision 4 ES-202, Page 5 states that "open-ended" questions should be avoided.
If a specific number of responses are required, the question should clearly state that expectation so the candidate will know when the answer is complete.
Full credit should be given for the four components / systems listed in the Operations Manual.
1.
LPRM trip units 2.
Associated APRM r.hannel 3.
Plant Process Computer 4.
Rod Block Moniter
Reference:
B..".1. 2-0006 Resolution:
Comment partially accepted. Answer key for Part a changed to ti.e recommended correct answers, point value for the question was changed to [4 at 0.25 each], 0.5 points were deleted from the question and examination.
Comment:
3.02 Answer b.
The change in core flow from a switch from the EPR to the MPR (approximately 918 psig to 923 psig) would be so small it would not be noticed by an operator using available indication. An acceptable answer could also be "no change" due to the slight pressure change.
Resolution:
Comment partially accepted. Answer key for Part b changed to the following:
i
i Attachment i 7
1 Increase [0.25] the-increased press.a.e reduces the void content of the two phase mixture in the core.
Less two phase flow, less restriction to core flow [0.5] - or - No indicated flow change [0.25] due to the small change in pressure, no change in flow wou'Id 'oe indicated [0.5].
Comment:
3.03 Answer.
The. question is open-ended and does not specify the number of resporises required.
b.
Candidates could also answer the question per the Operations Manual for full credit.
1.
Scram has occurred and 2.
Reactor pressure above setpoint l
and 3.
Control switch in auto
Reference:
B.3.3-0013 Resolution:
Comment accepted. Answer key for Part b changed to the following:
1.
Scram [0.25]
2, Reactor Pressure increases to setpoint [0.25]
3.
Control switch in auto [0.25]
Comment:
3.06 Question and Answer IW-98-1 and 2 may also be referred to as the reactor injection shutoff valves located in the drywell.
Reference:
B.6.5-0009 Resolution:
Comment accepted.
Answer key changed to accept alternate i
wording to Response 5.
Comment:
3.07 Answer a.
The control system will shift to the master controller and will increase the recirculation pump speed to whatever the master is set at which may or may not be the minimum speed of 45%.
Reference:
B.S.8-0002
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' Attachment l' 8
m.
L Resolution:.
Comment accepted. Answer key for Part a changed to the following:
The control system will generate-a step increase to the setting of the master. controller and the recirculation pump speed will increase to the' master controller setting [0.5].
The rate limiter will-control the speed increase at 2% per.
second1[0.25].
Comment:
.3.09 Answer b.
The' polarity or current' type (AC or DC) is not required knowledge for an operator. An. acceptable answer is.RCIC turbine speed is controlled by comparing actual turbine-speed with.the required speed and generate an electrical signal to adjust speed accordingly or similar explanation.
Reference:
M8107-003 Revision 3, Page 7 Resolution:
Comment partially accepted. Answer key for Part b changed
.to the'following:
The'RCIC turbine speed is controlled by comparing actual
' turbine speed-with the required turbine' speed,-' generated-l by the ramp generator / flow controller, [0.25] which generates
~
an electrical signal to adjust'the' turbine. steam flow.
[0.25]
Comment:
3.12 Answer Another possible answer is pump suction valve closing.
Reference:
B.3.4-0015 4
Resolution:
Comment accepted. Answer key changed to add recommended answer as Response No. 5.
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' Comment:
4.03 Answer c.
Candidate may answer per Technical Specifications k
that specifies that a second independent operator or engineer be used.
Either answer should be accepted.
Reference:
Technical Specification 3.3.B.I.b Page 80 and B.S.2-0002 i
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f 4.
" Attachment 1
.9 Resolution:
Comment accepted., Answer. key'for Part c changed to include.the following' alternate answer.:
- A second independent operator or engineer be:used to verify correct rod movement.
Comment:
4.09 Answer b.
Answer could be false if the operator felt he should tell. his immediate-supervisor (Shift Supervisor) and let the SS inform the General Superintendent Operations, or if-he was not medically qualified due to taking medication.
Reference:
4ACD-4.7 Page 17 Paragraph F
- Resolution:
Comment not. accepted. Monticello Administrative Control Document 4 ACD-4.7 states the following:
'4'ACD-4.7, Page 5, Paragraph 5.6.1 states "Ros and SR0s-shall be responsible for informing the General Superintendent
' Operations-(GS0) upon. determining they do' not meet the medical
. qualification delineated in 10 CFR 55."
Attachment:
1 4 ACD-4.7,.Page 17, Paragraph g states "R0s and SR0s.shall immediately inform the General Superintendent Operations (GS0) upon determining they do not meet the medical qualifications delineated in 10 CFR 55."
4 ACD-4.7, Page 17, Paragraph f states " Operators shall immediately inform the Shift Supervisor if taking medication that may impair their ability to operate the plant. The Shift Supervisor shall determine if a relief is warranted."
The Monticello Administrative Controls clearly state the requirement that the operator is responsible for notifying the GS0 if not meeting the medical qualifications.
The Shift Supervisor is only responsible to determine if a' relief is required for the operator.
Comment:
4.10 and 4.12 1
-The Abnormal Procedures C.4 contain immediate operator actions l-which state, " verify automatic actions;" there is also a section which states, "The possible automatic actions which may occur."
l 4 ACD-4.2 (Integrated Operating Procedures) concerning automatic actions states "The Automatic Actions that will probably occur as a result of the event should be identified."
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10 4 AWI-4.2.1 draft copy'(Abnormal Operating Procedures (C.4)
Writer's Guide) concerning automatic actions states, "The Automatic Actions section shall list the pertinent najor system automatic actions that the operator could exp1ct to see following the casualty."
The intent of the imm:diate operation action to " verify automatic actions" is for the operator to identify the event which is occurring and verify that auto _matic actions which should have v. curred did in fact occur.
It is not expected that all automatic actions listed will occur every time an event occurs, the automatic actions that occur depend on the initiating cause of the event.
The intent of the automatic action list in the procedure is not to list all the expected actions which would or could occur. The intent is to ensure the operator verifies automatic actions which will occur for that particular situation and if 1
the proper initiating signals are present.
(i.e., Group 1-5 i
isolition, diesel generator start, ECCS Initiation, etc.)
Depending on the event there are automatic actions which can and do occur which are not listed in the Abnormal Procedures.
A good example is the Reactor Scram procedure C.4-a; not listed in the Procedure Automatic Action List are items'which normally occur af ter a high power scran, such as SBGT start, secondary containment isolation, group 2 isolation, group 3 isolation, etc.
If the scram were to occur from low-low water level events such as Group 1 isolation, Recirculation pump trip, HPCI start, etc.
.j would occur.
The lists of Automatic Actions in the Abnormal Procedures are not all inclusive, other automatic actions should and will occur.
Reasonable answers, other than those listed in the scram procedure should be counted as correct.
1
Reference:
4ACD-4.2 Page 7 4AWI-4.2.1 Page 3-4 (draft only)
Resolution:
Comment not accepted. 4 AWI-4.2.1 (d'ait copy), Page 4,
[
Paragraph 6.2.3.5, "Immediate Operato, Actions" states, "Immediate operator actions are those actions that operators should take immediately, when there are indications of an off normal situation. When applicable, the actions shall be generic steps common to all abnormal procedures. With the exception of C.4-A, Reactor Scram, they should include the following:
1.
Verify automatic actions or manually initiate if they have not occurred.
T-t,
-11
-2.
Monitor the blant for entry conditions to the Emergency Operating Procedures, Operations Manual Section C.S.:
3.:
Notify shift supervisor of the' plant condition.. These actions are normally performed without having to refer to-a' procedure.
' 4 ACD-4.2, Page 4, Paragraph _6.2.6 states, "During. abnormal conditions, applicable Abnormal Procedures in Section C.4 of the Operations Manual should be referred to after the immediate actions have,been taken and the situation is under control."
TheLexamination questions stated to list-the automatic' actions in'accordance with the procedures. The'Monticello administrative documents state that the operator should refer to the procedure after the immediate actions have been completed._ If the operators do not know the automatic actions for the procedure
~
then the operator. will. not know what immediate actions are required.
Comment:
-Question 6.02 Panel C259 is in the Control Room.
The candidate may not give panel number. Also, the stack monitor no longer alarms at the MPCA.
See attached memo.
Resolution:
Comment accepted.
This question was deleted from the-examinat un because of system and setpoint changes.
-Comment:-
Question.7.05
. Operations Manual C.2 Page 32 states "take action as required by technical Specification 3.1.B.," Technical Specification
' 3.1.B. states " satisfy the minimum requirements by placing appropriate devices, channel, or trip system'in the tripped condition, or place and maintain the plant under the specified required condition using normal operating procedures."
The candidate may answer take action required by Technical Specifications, place RPS channel in trip condition or commence reactor shutdown until APRM's are readjusted.
Resolution:
Comment accepted.
The answer key was changed to accept "take actions in accordance with Technical Specifications."
Comment:
Question 7.08 The answer key lists a reference of C.5-1101 and C.5-1101.
There are no immediate actions in the E0Ps. The question would lead the candidate to answer referring to the abnormal 1'
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12 procedure. The automatic ' actions listed in the abnormal procedure are only some of the auto functions that may occur during that particular event, given that the scram occurred due to high drywell pressure, Group I isolation, and RCIC initiation, should not be verified because their logic does not receive a drywell pressure input.
Some of the events to verify for high pressure are:
Group 2, 3 isolation Diesel generator starts ECCS actuation ie., HPCI, CS, LPCI Reactor Scram Resolution:
Comment noted. The comment was taken into consideration during grading. Tha answer key is unchanged.
Comment:
Question 7.11 The abnormal procedure assumes the reactor is at power. The question could be answered to trip the CRD pump if the candidate assumes the reactor is shutdown or in refuel mode when loss of RBCCW occurs.
R,esolution:
Comment not accepted. This comment should be directed to Question 7.10.
The question specifically addresses the abnormal procedure. Any answer not identified in that procedure is not acceptable. The answer key is unchanged.
Comment:
Question 7.12 Both Diesel Generators would start. Monticello Operations Manual B.9.8. Page 2.
Resolution:
Comment noted.
l Comment:
Question 7.15 l
Answer Key is missing answer for question (f).
Correct answer would be 1100 and 1200 Series.
The answer for (h) should be none.
The setpoint for the plenum monitor has been set up.
See attachment Volume F Memo.
Resolution:
Comment noted.
The answer key was corrected.
Comment:
Question 8.04 - Part c l
4 ACD-3.1 Section 6.3.5 allows the plant manager or his designee I
to review, approve, and document overtime work restrictions on behalf of the plant manager.
For operations, this would include the Site Superintendent.
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! Resolution:
Comment accepted. The answer k'ey was changed to also accept
" designee, i.e.,1 Site Superintendent or Operations ;
Superintendent."
Comment:
-Question 8.08 - Part d-The LPE and R0 is required to log the availability of;the fire brigade' members.
The Shif t Supervisor is. responsible' for. shift manning and reviewing the LPE and R0 logs to insure manning.
Resolution:-
' Comment noted. The answer key was changed..
Comment:
Question 8.12
'The question asks for two safety. limits. Only one safety limit is required to be adjusted during single loop operations.
L
-The MCPR safety limit must be adjusted by.01 as required by L
Technica1' Specification 2.1.A.
The operating limit'MCPR and-MAPLHGR limits.are not safety limits.
Resolution:
Comment noted.
- Comment:
-Question 8.14L-Part a Unable to justify General Emergency; appears to be NUE.
.,'l Resolution:
Comment not accepted. The information given in the question would-indicate a large LOCA with failure of ECCS. Guideline 28 of A.2-101.under Example BWR Sequences would require this to be classed as a General Emergency if no other =information is immediately available. The answer key is unchanged.
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S.-NUCLEAR REGULATORY COMMISSION i.
SENIOR REACTOR OPERATOR LICENSE EXAMINATION L
FACILITY:
_MgNIlggLLg______________
REACTOR TYPE:
_BWB-GU_3_____ ___________
DATE ADMINISTERED: 87/09/01--
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EXAMINER:
_LCggTON _J.
7 2
CANDIDATE:
INSIB99119BS_I9_C8BDID61El Use ceparate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses af ter the question.
The passing grade requires at least 70% in each category and a final grade of at least 80%.
Examination papers will be picked up six (6) hours after the e:-tamination starts.
i i
% OF CATEGORY
% OF CANDIDATE'S CATEGORY
__Y8LUE_ _I0186
___@CQBE___
_M86UE__ ______________C61EQQBY_____________,
26t25__ _2ErdZ
___________.________ 5.
THEORY OF NUCLEAR POWER PLANT
~
OPERATION, FLUIDS, AND THERMODYNAMICS er 6.
PLANT SYSTEMS DESIGN, CONTROL,
-"~~ ""~4.75
~~~~~~~~~~~
~~~~~~~~
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~~"
AND INST:,UMENTATION
_2535E__ _23322
________ 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
_EEz25__ _23122
________ 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS i
193192__
Totals Final Grade 1
All worL done on this examination is my c,wn.
I have neither given nor received aid.
)
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Candidate's Signature l
1 l
l MASTER COPY
-u-___-______
_._m_
C NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS o
.DU ing the administration of this examination the following rules appl y:
)
1.
Cheating on the examination means an automatic denial of your application i
and could result in more severe penalties.
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2.
Restroom trips are to be. limited and only one candidate ataa time may I
leave.
You must avoid all contacts with anyone outside the examination
]
room to avoid even the appearance or possibility of cheating.
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I 3.
Use black ink or dark pencil gely to facilitate legible reprodu:tions.
4.
Print your name in the blank provided on the cover sheet of the examination.
l 5.
Fil) in the date on the cover sheet of the examination (if necessary).
6.
Use only the paper provided for answers.
7.
Print your name in the upper right-hand corner of the first page of egch section of the answer sheet.
8.
Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category or a og'w page, write gnly 90 gag sidg of the paper, and write "Last Page" on the last answer sheet.
9.
Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least ihrep lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if thev are commonly used in facility litgtatute.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all cal cul ati ons, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE DUESTION AND DO NOT LEAVE ANY ANSWER BLANP.
- 16. If parts of the examinattar are not clear as to intent, a s k.
questions of the gueminet only.
- 17. You must sign the statement on the ccver sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.
This must be dene after the examination has been completed.
MASTER CO3Y
-m_.__
f.
.. o 6
1EL When_you complete your examination, you shall:
a.
Assemble your examination as f oll ows:
(1)
Exam questions on top.
(2)
Exam sids - figures, tables, etc.
j!
( 5)
Answer pages including figures which are part of/the answer.
.j-b.
Turn in your copy of the examination and all pages used to answer the examination questions.
c.
Turn in all scrap paper and the balence of the paper that you did not use for. answering the questions.
d.
Leave the e:: amination area, as defined by the examiner.
If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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QUESTION 5.01 (1.00)
~
Criticality is defined'as Keff=1, " fission chain reactien.,s self-sustaining." NAME and simply STATE the process that makes it possible to have what appears to be a self-sustaining react)on at i
Ve+f=0.90?
{'
QUESTION 5.02 (2.00)
You are Shift Supervisor during a startup following a reactor scram.
The RO has withdrawn rods to Keff=0.99 and the reactor is cooling down at a rate of 100 degrees F/hr.
a.
Calculate the REACTIVITY required and TIME it will take for the reactor will go critical with no further rod motion (Consider only temperature ef f ects f or this calculation, assume alpha TM = -1 x
10E-4 Delta K/K degrees F).
(1.0) b.
IF the reactor was at 100% power for 60 days prior to the SCRAM, STATE HOW and WHY Xenon would affect the time calculated in a. above:
- 1) 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the scram?
(0.5)
- 2) 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> after the scram?
(0.5)
QUESTION 5.03 (1.50) 4 I
Increasing recirculation pump speed will cause (INCREASE, DECREASE, or REMAIN the SAME) in each of the fc11owing parameters?
)
1 a.
Actual bundle power b.
Critical power c.
Critical power ratio DUESTION 5.04 (1.00)
During reactor shutdown for refueling, the Nuclear Engineer tells you shutdown margin is O.41%.
CALCULATE Keff.
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QUESTION 5.05 (1.50) g DEFINE " Power Coefficient of Reactivity," and STATE WHICH bther coefficients-DOMINATE it during:
g; a.
Cold Startup?
i~
p A
b.
Power operation?
QUESTION 5.06 (2.50)
Does a power change from 40% power to 30% power take LONGER, SHORTER, or the SAME, as a power change from 40% power to 50% power?
(Assume constant rod speed.)
EXPLAIN your answer for BOTH power changes.
INCLUDE WHICH coefficients of. reactivity cause power to STABILIZE for BOTH situations.
QUESTION 5.07 (1.50)
During your shift, an SRV inadvertently opens at 100% power and 1000 psia, i
Use the Steam Tables or Mollier Diagram to answer the following:
(ASSUME INSTANTANEOUS HEAT TRANSFER AND A SATURATED SYSTEM.)
a.
Determine tailpipe temperature, assuming reactor pressure remains l
constant and suppression pool is at atmospheric pressure.
b.
Is the steam exhausting to the suppression pool saturated or superheated7 c.
Determine at what reactor pressure the tailpipe would reach its maximum temperature if the reactor depressurizes.
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z QUESTION 5.08 (2.00) i s;
Answer'each of the fc11owing TRUE or FALSE:
14 i
a.
During equilibrium power conditions, the negative rea tivity f rom Xenon is equal to the negative reactivity f rom samarium.
b.
Slowing the rate of a power decrease, lowers the height of.the resultant Samarium peak.
c.
The resultant Xenon peak due to a scram from 50% power is larger than one from 100% power.
d.
During an increase in power from equilibrium Xenon conditions, Xenon concentration initially decreases.
QUESTION 5.09 (2.50)
~ Match each of the following statements with the appropriate numbered item:
a.
The limiting parameter that assures PCT will not exceed 2200 degrees F during a design basis LOCA.
I b.
Total power passing through a unit length of fuel rod, l
c.
PLHGR divided by MLHGR limit.
f d.
Safety limit that is not analyzed at < 10% power or < 800 psia, e.
Ratio of actual bundle power to that required to produce OTB in the bundle.
1.
MAPRAT 5.
LHGR 2.
FLCPR 6.
FLPD i
3.
APLHGR 7.
CPR 4.
MCPR 8.
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mIHEBdQpyNSd]QS QUESTION 5.10 (1.50) a.
Define reactor period.
(1.0)
-i b.
As compared to BOL conditions, the effect of delayed neutrons on reactor period at EOL for the same reactivity addition will result in a (SHORTER, THE SAME, LONGER) period.
(Choose one)
(0.5)
QUESTION 5.11 (1.00)
Shaping control rods are (DEEP, INTERMEDIATE, SHALLOW) rods that are used to change the power profile because they (ARE, ARE NOT) affected by shadowing.
(Choose one answer in each parenthesis.)
QUESTION 5.12
( 1. 50 ).
Concerning pump characteristics, state whether each of the following is I
TRUE or FALSE:
a.
The total brake hors nower for two identical pumps operating in parallel is twice he brake horsepower for single pump operation.
b.
Minimum flow valves are provided in ECCS systems to minimize the time the pump is running with shutoff head.
c.
Even with the: circulation pumps off, the jet pumps will enhance i
natural circulation flow.
-QUESTION 5.13 (1.50)
STATC whether the reactor is SUDCRITICAL, CRITICAL, or SUPERCRITICAL for each of the following: (IMMEDIATE CONDITION) a.
Reactor was stable at 10% power, Voids just increased 1%.
b.
Following reactor startup, the reactor is on a constant heatup rate of 50 degrees F/hr.
c.
During a startup, the reactor is at the point of adding heat and period is infinite.
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3 ISEBdQDyN6dIGE DUESTION 5.14 (2.00)
CTATE whether each of the following changes will (INCREASE iDECREASE, or NOT AFFECT) AVAILABLE recirculation pump Net Positive Suction Head
[f, (NPSH):
I a.
Feedwater temperature increases b.
Reactor pressure decreases c.
Reactor water level increases d.
Recirculation; pump speed decreases QUESTION 5.15 (1.00)
Is Keff DEPENDENT ON or INDEPENDENT OF source neutrons?
Briefly EXPLAIN your answer.
QUESTION 5,16 (2.25)
There are TWO primary and ONE secondary mechanisms for heat transfer.
a.
IDENTIFY which mechanisms are PRIMARY and which is EECONDARY.
b.
In transferring heat from fuel centerline to coolant, give an EXAMPLE where each mechanism is dominant.
(State any assumptions.)
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i PAGE 7
.62 _EL8NI_SygIgdg_DEg]GUz_CQNISQL _8ND_INgIEUdgNIGIJQN 1
-QUESTIDN 6.01 (2.00)
LIST the FOUR refueling platform interlocks that will cause's rod block with the platform over the core during refuel.
,e 3d 4pOe-
'I:
Deleid QUESTION 6.02
( 5 6 )
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2, ]T]{- U i., L ETFCINT cu. J Um m.. m._ t a yvu u su,
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QUESTION 6.03 (1.50)
You are operating the RHR in Torus cooling and a small break LOCA occurs.
STATE the signals and setpoints that will switch the RHR to LPCI mode.
QUESTION 6.04 (2.00)
TRUE or FALSE 7 a.
The f uncti on of the Reactor Core Isolation Cooling (RCIC) system is described as. " Provide sufficient makeup water to the reactor such that the core is not uncovered in the event of reactor isolation accompanied by a small-break LOCA."
6.
If the RCIC turbine trips on mechanical overspeed, the trip will be reset when the " reset motor control switch" on panel C04 is turned to "open."
c.
Auto isolation trips will be reset by pushing the "steamline j
isolation" pushbutton on C04.
d.
The RCIC flow transmitter and square root converter supply a flow j
signal to the flow controller which maintains a constant turbine speed over a pressure range of 150 to 1120 psig.
1 QUESTION 6.05 (2.50)
LIST FIVE of the sir signals that will TRIP the High Pressure Coolant Injection (HPCI) System turoine.
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' QUESTION-6.06 (1.00)
TFill in the Blanks)
',;s, 3;
The Recirculation Flow Control System contains a rate limiter that will ultimately limit the rate of power change.
This circuit livits the speed increase to (1)
________% per second and the speed decreasel'to (2) ________% per second.
QUESTION 6.07-(2.50)
During power operation, a " partial" Group II isolation signal is received from the Fuel Pool High Rad Trip at 50 mR/hr.
IDENTIFY the Group II systems that DO ND, isolate.
(Valve numbers are not necessary.)
' QUESTION 6.08 (2.00)
Answer the following questions concerning the Steam Pressure Control System:
a.
The control range of the Mechanical Pressure Regulator is (1) ______
to (2) ______ psig and the control range of the Eletrical Pressure Regulator is (3) ______ to (4) ______ psig.
b.
DESCRIDE how the MPR setpoint is adjusted to serve as the backup regulator.
QUESTION 6.09 (1,80)
The Automatic Pressure Relief System contains 9 Target Rock valves:
)
a.
STATE which valves are used in the Automatic Depressurination System (ADS).
6>r TAe ADS v4/ves b.
WHAT positions are provided on the control switcg?
c.
STATE the FUNCTION of the ADS.
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DUESTION 6.10 (2.00) l ok ' i b ' the ref erence [r,,,
'With the reactor operating at power, a leak develops LOW) l evel u:a leg of the 100" level instrument, resulting in a (HIGH, signal and (AN INCREASE, A DECREASE, NO CHANGE) in drywell/ pressure.
i SELECT one response in each parenthesis and JUSTIFY that anp,wer.
ri' QUESTION 6.11 (2.00)
A situation has developed such that Boron Injection is required and the Standby Liquid Control pumps cannot be operated.
STATE TWO other METHODS and SYSTEMS that can be used to inject baron.
QUESTION 6.12 (1.50) i The Anticipated Transient Without Scram (ATWS) circuitry, in order to meet its design basis, will limit:
i a.
Reactor vessel pressure to less than (1) ________ psig.
b.
Fuel energy deposition to less than (2) ________ calories / gram l
and clad a::idation less than (3)
________% by volume.
c.
Containment pressure to less than (4) ________ psig and suppression pool local temperatures to less than (5) ________ degrees F.
o
. QUESTION 6.13 (2.00)
The Uninterruptible Power Supply uses a static switch to transfer loads to an alternate source.
LIST FOUR conditions that cause this transf er.
l OUESTION 6.14 (1.20) i The IRMs are on range 5 during a startup.
IRM 18 is bypassed and an instrument technician is troubleshooting the power supply.
He mistakenly switches IRM 15 te standby.
STATE the specific plant / system TRIP (s) this caused?
4 i
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' Zt e_ E B99EDUS's5_:_ N9BdBLi_ B BN9B MBL1_ E DEBg E N Cy_ BND PAGE 10 BBD196991GGL..GGUIB96 QUESTION 7.01 (2.50)
Following a LOCA, drywell pressure and temperature are incr, easing.
According to C.5-1203, " Primary Containment Pressure Control," drywell spray can be initiated if torus air temperature and drywe117 pressure are within the Drywell Spray Initiation Pressure Limit (Fi gure '1000-8 ) AND torus water level is below 3 feet.
a.
What is the basis for "Drywell Spray Initiation Pressure Limit?"
(1.0) b.
What is the basis for " Torus Water Level?"
(0.5) c.
What TWO systems must be shut down before initiating drywell spray?
(1.0)
QUESTION 7.02 (2.00)
IDENTIFY the allowable radiation exposure in accordance.with 10 CFR 20 and 4 AWI-11.1.14, " Radiological Protection Standards," without NRC Form 4 or special authorization.
10 CFR 20 Monticello " Hold" Point ilhole Body (1)
_________ (2)
Extremities
________ 3)
_________ (4)
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.Z._C _CBQGE QUBgg _;_UO Bd86 t _8@UOBd86 t_gdEBQEdgy_ ANQ PAGE 11 08210LDEIGBL_GONIEQL DUESTION 7.03 (1.80)
MATCH the pressure at which each of the f ollowing will be performed or will occur during a reactor startup from cold conditions in,accordance with startup procedure C.1, "Heatup and Pressurization?"
fi i
a.
The mechanical pressure regulator is allowed 1.
50 psig g
to open the Main Steam Bypass valve #1 to 2.
80 psig I
verify regulator operation.
3.
100 peig 4.
130 psig b.
The RCIC Automatic isolation signal is reset.
5.
150 psig 6.
200 prig c.
The HPCI Automati c isolation signal is reset.
7.
500 psig 8.
800 psig g
d.
The mechanical pressure regulator override 9.
900 psig
]
is adjusted to open the #1 Main Steam Bypass
- 10. 1400 psig sa valve 10 - 15%.
e.
Electric pressure regulator is verified to assume pressure control.
f.
The Air Ejector Suction Isolation Valve Control Switch is placed in the Auto position.
DUESTION 7.04 (2.00)
You are Shift Supervisor during EOC operation, according to C.2.I, "End of Fuel Cycle Coastdown," it is preferable to maintain reactor pressure at 1008 psig.
a.
WHY?
(0.5) l b.
STATE TWO of the precautions that should be taken if 1008 psig is i
l maintained?
(1.5) l MAS ER CO3Y
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,2,c _ EEDCEDUBE5_:_N9BDBL t _6FNDSUSL, _ gdE SQ5U9 Y_ BMD PAGE 12 BSDI96991G66_G99IB96 QUESTION 7.05 (1.50)
The computer heat balance calculates plant power to be "95N,."
An OD-3 printout shows APRM AGAFs reading:
j
. t r '.
APRM 1 0.985
'/
APRM 2 1.015 TPRM 3 1.000 APRM 4 1.020 l
APRM 5 1.025 l
APRM 6 0.995 a.
WHICH APRMs require adjustment?
-b.
IDENTIFY any action level and actions that you are required to take.
(Include in your answer which APRM channel (s) require the actions ; C -_. -.
.)
DUESTION 7.06 (1.50)
WHEN can an ECCS component be placed in MANUAL or secured in accordance with a CAUTION in C.5-1101, "RPV Level Control?"
LIST TWO conditions and number of indications required.
QUESTION 7.07 (1.50)
TRUE or FALSE 7 a.
Upon control room evacuation in accordance with C.4-C,
" Shutdown Outside Control Room," the actions of C.4-C will be performed in parallel with the appropriate EOPs.
b.
As LPE and RO, you are required to establish control at ASDS Panel C292 immediately upon control room abandonment.
c.
Performance of procedure C.4-C may require vi ol ati on of Technical Specifications; however, because these violations have been identified, reviewed, and approved, immediate reporting of violations in not necessery.
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DUESTION 7.08 (2.50)
The reactor has just scrammed on High Drywell Pressure..Yourl frmary cdi2t; action is to " Verify Automatic actions."
LIST the automatic actions that
-are REQUIRED.
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DUESTION 7.09 (2.00)
According to C.3.IV,
" Operating Requirements During Shutdown / Refueling Conditions," reactor coolant temperature shall be recorded once each hour.
k STATE FOUR locations that this reading can be obtained (in order of preference) and operating status of pumps / systems required for each reading to be valid.
QUESTION 7.10 (1.00)
A complete loss of the Reactor Building Closed Cooling Water CRBCCW)
According to the Bases for duM9 System will affect numerous systems.
it have on the CRD systeg,jwer9hMMu C.4-B.2.5.A,
" Loss of RBCCW," WHAT effect will WHAT potential action should be taken, and WHEN would this action be taken?
QUESTION 7.11 (1.00)
You are the LPE and RO f ollowing a loss-of-of f si te power.
Conditions are such that you must start service water pump 11.
WHAT CAUTION should you relay to your operator price to starting the pump?
QUESTION 7.12 (1.50)
STATF the automatic actions that would occur upon loss of the 13 Bus (ACA 152-308 trips).
QUESTION 7.13 (1.25)
You are the Fuel Handling Supervi sor on back shift.
A situation requires deviation f rom a procedure.
According to D.3.
" Fuel Handling," WHAT must you do to change the procedure?
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r-1 QUESTION 7.14 (1.00).
The reactor scrammed.and reactor water level was < + 0 'ihchss. - You are naar the final step in the EDP 1100 series when drywelltpressure exceeds its limit.
You are required to:
(Choose correct answer)'
J'r ti; s
'I c..
Ignore the change because the series of steps you have'just completed j
'will ensure reactor safety.
1 b.,
' Reenter the 1100 series and the 1200 series, c.
Exit the'1100 series and enter the 1200 series.
d, Exit the EDPs'and enter the appropriate abnormal procedure.
QUESTION' 7.15 (2.50)
Fcr each of the following conditions, determine whether or not emergency
. procedure entry is required.
If entry is required, STATE WHICH procedure (s) to anter.
If NO entry is required, state NONE.
(Consider cach i tem. separe.tel y and' assume no addi ti onal conditions.)
c.
RPV level is + 10 inches.
b.
Reactor power is 12% STARTUP MODE.
c.
Reactor power is 93% one minute after load reject.
d.
GROUP I isolation occurs at > 50% power.
c.
Suppression pool level is 5 inches.
q; f,
Drywell pressure is 2.5 psig.
g.
Torus temperature 89 degrees F.
h.
Reactor building vent exhaust 3.2 mR/hr.
i.
Reactor shutdown, reactor pressure 1090 psig.
j.
Drywell temperature i s 145 degrees F.
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QUESTION O.01 (1.50) c....
As Shift Supervisor, 4 ACD-4.8, " Bypass Control," identifies ten ( 10')
responsibilities.
LIST SIX of your responsibilities.
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QUESTION 8.02 (2.00)
You are the Shift Supervisor.
According to 4 ACD-4.7, " General Plant Operating Activities," you shall proceed immediately to the control room if any of.four annunciators are received.
LIST those annunciators.
QUESTION B.03 (1.25)
You are Shif t Supervisor and your RO has just completed the Quarterly Flow Rate Test on the Reactor Core Isolation Cooling System (RCIC-).
Answer the following questions in accordance with Technical Specifications 3.5.F.
c.
To be considered operable, the RCIC shall be capable of delivering (1) ________ gpm into the reactor vessel at (2) ________ psig.
(0.5) b.
If the RCIC cannot be considered operable, WHAT other system must.be shown to be operable and at WHAT frequency?
(0.75)
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QUESTION 8.04 (2.50)
.e-The reactor is in Mode 5 with fuel movement in progress. ~You are the Senior LSO on back shift.
Because of a flu epidemic, your^ crew 3,
composition is scheduled as f ollows:
17 1
LSO1 (You)
Y' 1
LSO2 (Limited to Fuel Handing) 1 LSO3 (Unspecified) 1 LO 5
Unlicensed Operators The off going crew is at minimum staffing; 3 unlicensed operators and 3-LSOs have just completed a double shif t.
Three of your unlicensed operators, LSO2, and LSO3 have called in sick.
a.
HOW can you meet your staffing requirements without exceeding overtime guidelines?
(1.5) 6.
HOW long are you allowed to have one man less than required without violating Technical Specifications?
(0.5) c.
If overtime guidelines are to be exceeded, from WHOM must you get authorization?
(0,5)
OUESTION O.05 (2.00)
As Shift Supervisor you have declared an alert because of a high offsite release and have assumed the position of Emergency Director. List four L
responsibilities of the Emergency Director that may NOT be delegated.
_A -
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.Dzi_6DdlMISIS9IlyE_ESQGEQUBESz_GgypIIlgNSi_8ND_LIMIISI1QNS PAGE 17 DUESTION 8.06 (1.00)
The Technical Specifications Section 3.10.D states, "The' Reactor shall be shutdown for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to movement of fuel within the reactor."
The reason for this is:
.f:i.
a a.
This is the minimum time it takes to set up for fuel hbndling.
b.
Decay heat must be below that specified in 3.10.E of the Technical Specifications.
c.
Fuel handling accident analyses are based on 24-hour decay.
I d.
Shutdown margin cannot be calculated until Xe is on its decay I
cycle.
QUESTION 8.07 (2.00)
In accordance with 4 AWI-4.5.1,
" Equipment Alignment Verification Methods," briefly DESCRIDE how you would VERIFY the following valves are in correct position:
a.
A normall y-cl osed manual gate v a l,< e.
b.
A normall y-open seal-wired gl obe val ve.
c.
A motor operated valve (remote),
d.
An air operated valve (light indication defective),
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-QUESTION 8.00 (2.00)
TRUE or FALSE?
k &b a.
If a fire occurs during a reactor startup, all persons >on shift with i
the exception of the Shift Supervisor, the Lead PlantfKquipment and Reactor Operator, and the Plant Equipment and Reactor' Operator can be counted as members of the Fire Brigade.
b.
Fire Brigade composition may be less than minimum for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, provided the necessary people have been called and are coming in to fulfill the requirement.
c.
A small brush fire on Thompsons Island would be classed as a Significant Operating Event.
d.
As Shif t Supervisor, you are responsible f or assuring that a Fire Brigade is available during your shift.
QUESTION 8.00 (2.00)
You are Shift Supervisor on backshift.
Security calls and reports a strong odor of chlerine near the chlorinator room, accompanied by eye and skin irritation.
You also smell it in the Shift Supervisor's office, a.
STATE THREE actions you shoul d take immediately in the control room in accordance with A.4-OO2, " Chlorine."
(1.5) b.
WHAT action should you instruct the Security Shift Supervisor to take?
(0.5)
QUESTION G.10 (1.50)
Section 1.0 of the Technical Specifications states that Secondary Cont ai r.J 2r.t Integrity means that THREE conditions are met.
LIST those conditions.
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I QUESTION 8.11 (2.00)
)
i TRUE or FALSE?
a M
a.
The Technical Specifications require reactor shutdownfif more than 6 "non-fully inserted rods are inoperable," because the reactor cannot meet the required shutdown margin if another withdrawn rod sti cks.
b.
The surveillance requirement for control rods allows one rod in a two-by-two array to be cycled one-notch only once per month instead of weekly.
c.
The Technical Specifications allow the Rod Worth Minimi:er to be bypassed during startup at beginning of rod withdrawal provided a second operator or engineer verifies each withdrawal.
d.
A control rod with an inoperable accumulator is fullv inserted and electrically disarmed; therefore, the accumulator is not considered inoperable.
QUESTION 8.12 (3.00)
You are Shift Supervisor during power operation.
One recirculation pump
-has tripped due to electrical problems and cannot be restored for several days.
The load dispatcher wants you to stay online because of high power demand.
Answer the f ollowing questions with regard to Technical Specification requirements.
Of'erdidy a.
WHAT TWO
'rty limits must be changed and HOW MUCH must they be changed?
b.
The APRM Scram and Rod Blocks must also be reset; given S < 0.58 (W-dw) + 6 2*/., IDENTIFY the term that must be changed and STATE the new value.
QUESTION 8.13
(.50) 7 RUE or FALSE?
In accordance with 4 ACD-3.5, " Plant Operations Key Control," the key,s requi red to shut down the reactor subsequent to abandoning the control room must be logged out of the Shift Supervisor?s key cabinet.
MASii COPY
(***** CATEGORY 08 CONTINUED ON NEXT PAGE
- t)
.Qul_GDd1NIQIG611ME_E60CEQQEE@u_GQNQlIlgN$t_6ND_61dlI@IlgN@
PAGE 20 i.
DUESTION 8.14 (2.50)
Classify each of the f ollowing events with the highest appropriate classification according to A.2-101, " Classification of Emergencies,"
(attached).
If classification is not required, state NONE.a ac The reactor scrammed on low l evel, drywell pressure ihbrapidly increasing, and HPCI failed to start.
I b.
Stack effluent monitor "A" has alarmed and reads 3.2 E6 uti/sec.
c.
Chemistry calls and reports a routine sample of the discharge canal reads 18 cps, d.
The reactor scramn.ed on low level, drywell pressure is increasing, HPCI is injecting, reactor water level is -123 inches and slowly decreasing.
e.
The reactor scrammed on turbine trip; one SRV will not reclose.
MASTER COPY
(***** END OF CATEGORY 08
- )
(****4********
END OF EXAMINATION
- 4********444)
.Dul_ISE98Y_9E NW96 EBB _E9 WEB _ELBNI_9EEBBI19N2_EL91DS1_8ND PAGE 21 IHEB59DYNB0Jgg L
. ANSWERS -- MONTICELLO
-87/09/01-KEETON, J.
ANSWER 5.01 (1.00)
.i..
1 Subtritical Multiplication (0,5) uses source neutrons such,that the numbe'r of neutrons lost in each generation is equal to the number pf neutrons produced from the source (i. e., source critical)
(0.5).
REFERENCE Monticello: Reactor Theory, Chapter 3 292OO2K106
...(KA'S)
ANSWER 5.02 (2.00) 0.99-1/O.99 =
a.
Delta K/K = Keff-1/Keff
=
0.0101 Delta K/K must be inserted (0.5)
Delta K/K = (Alpha TM) (Delta T) 0.0101 Delta K/K =
(-1 X 10E-4 Del te K/K degrees F) (-100 degrees F/hr. )
Time =
- 1 hr
(+
or - O.1) (0,5) b.
- 1) 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after scram Xe is increasing so time would be longer. (0,5)
- 2) 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> after scram Xe is decreasing so time would be shorter.
(0.5) i REFERENCE Monticello:
Reactor Theory, Chapters 4 and 6 292OO6K107 292OOBK105
...(KA'S)
ANSWER 5.03 (1.50) a.
Increase b.
Increase c.
Decrease
( O.5 pts each)
REFERENCE Monticello: Heat Transfer and Fluid Flow, Chapter 9 202OO1K102 293OO9K12:
...(KA'S)
MASTER COPi
.5 c E _IbEQSY _QE _Ny g6[@ B _EQW E S _EL@ NI_Q[E B8IlgN,._ELy lD $ t _8ND PAGE 22 IbEBdODYN@dlGQ
. ANSWERS -- MONTICELLO
-G7/09/01-KEETON, J.
ANSWER 5.04 (1.00)
- 6 SDM = 1-Keff (0.50) r,f-SDM = 0.41%/100% c 0.0041
'/'
1-0.0041 = 0.9959 (0.50) l Keff
=
1 i
REFERENCE Monticello:
Reactor Theory, Chapter 1 292OO2K115
...(KA'S)
ANSWER 5.05 (1.50)
Power Coefficient of Reactivity is the change in reactivity f or a 1%
change in reactor power.
(0.5) a.
During reactor startup, the moderator temperature coefficient is dominant.
(0.5) b.
At power, the void coefficient is dominant.
(0.5)
REFERENCE Monticello Reactor Theory, Chapter 4 292OO4K114
...(KA'S)
ANSWER 5.06 (2.50)
Longer (0.5)
Because the power down transient is limited by the decay of the long-lived delayed neutron precursors (0.5) whereas, the power up transient is dependent on prompt neutrons (0.25) and short-lived delay neutron precursors.
(0.25)
The down transient is stabilized by the void coefficient (alpha V)
(0.25) and the decrease in doppler (alpha D)
(0.25).
The up transient is stabilized by the void coefficient (alpha V)
(0.25) and the increase in doppler (alpha D)
(0.25).
(Accept any reasonable, correct discussion of the effect that doppler and void coefficient have on stabilizing power.)
REFEFENCE Monticello: Reactor Theory, Chapters 3, 4.
and 7 292OO3K106 292OOBK119
...(KA'S)
MASTER COPY
. L' _ItiEDBY_QE_NgCLE@B_EgME8 E(@NI_QEEBBIlh_E691&_8NQ PAGE 23 IUEEdggyN@dlCS
. f5SW! IRS '-- MONTICELLO
-87/09/01-KEETON, J.
ANSWER 5.07 (1.50)
,'i a.
295 degrees F
(+ or - 15 degrees F) b.
Superheated
's c.
450 psia
(+ or - 50 psia)
(0.5 ptu each)
REFERENCE
' Monticello:
Heat Transfer and Fluid Flow, Chapter 3 293OO3K123
...(KA'5) l' ANSWER 5.08 (2.00) a.
False b.
False c.
Felse d.
True
( O.5 pts each)
REFERENCE Monticello: Reactor Theory, Chapter 6 292OO6K105 292OO6K106 292OO6K107
...(KA'S)
ANSWER 5.09 (2.50) i a.
3
)'
b.
5 c.
6 d.
A e.
7 (0.5 pts each)
REFERENCE Monticello:
Heat Transfer and Fluid Flow, Chapter 9 293OO9K106 29 OO9K109 293OO9K111 293OO9K118 293OO9K121
...(KA'C)
I 1
i l
MASTER COP'Y l
l QtE_IMEQBY_QE_NQQ6E88_EQWEB_EL681_QEGEBIlQNt_ELQ19@t_88D PAGE 24 IdEBdQDybf8dlQS j
[
ANSWERS -- MONTICELLO
-87/09/01-KEETON, J.
I l
ANSWER 5.10 (1.50)
YU-I h
a..
The amount of time required for reactor power t o +>. u meme by 1
a factor of e.
(1.0)
'/'
1 6.
Shorter.
(0.5)
REFERENCE Monticello:
Reactor Theory, Chapter 3 293OO9K105 293OO9K106
...(KA'S)
{
i ANSWER 5.11 (1.00)
Shallow (0.5)
ARE (0,5) l l
1 REFERENCE Monticello:
Reactor Theory, Chapter 5 292OO5K110
...(KA'S)
ANSWER 5.12 (1.50) a.
False b.
True c.
False (0.5 pts each)
REFERENCE Monticello:
Heat Transfer and Fluid Flow, Chapters 6 and O 293OO9K105 293OO9K106 293OO9K111
...(KA'S)
ANSWER 5.13 (1.50) a.
Subcritical b.
Supercritical c.
Critical
( O.5 pts each)
REFERENCE f
Monticello: Reactor Theory. Chapters 1 and 7
]
292OOSK105
...(KA'S)
MASTER COPY e
h_____________-.___
5.[ THEORY OF NUCLEAR POWER PLANT OPERATIONu_FLUIQS _AND PASE 25 u
IHEBdQQ10AdlGS A SWERS -- MON TICELLO
-07/09/01-KEETON, J.
ANSWER 5.14 (2.00) i a.
DECREASE
/t b.
DECREASE I['
c.
INCREASE d.
INCREASE (0.5 pts each)
REFERENCE Monticello: Heat Transfer and Fluid Flow, Chapter 6 202OO1K101 202OO1K103 202OO1K105 202OO1K122
...(KA'S)
ANSWER 5.15 (1.00)
INDEPENDENT OF (0.5)
Keff (the neutron life cycle) only considers fission neutrons in the self-sustaining reaction. (Other reasonable correct responses accep-table for full credit.)
(0.5)
REFERENCE Monticello Reactor Theory, Chapter 2 292OO3K101 292OOOK104
...(KA'S)
ANSWER 5.16 (2.25) a.
Conduction - primary (0.25)
Radiation - primary (0.25)
Convection - secondary (0.25) 6.
Conduction - Fuel centerline to f uel surface (will accept fuel centerline to clad surface if assumption that the fuel is contacting the clad ID is stated).
(0,5)
Convection - Clad outer surface to coolant (will accept fuel surface to clad ID across gas gap if so stated).
(0,5)
Radiation
- Clad surface to coblant (steam or water) across void on clad surface.
(0.5)
REFERENCE Monticello:
Heat Transfer and Fluid Flow. Chapter 7 29C.OO7K101
...(KA'S)
MASTER CO?Y
__m__
. k.ul_CL6MI_SYSI5t!S_ DESIGN _CQUI6Q6_@ND_lNEI6yMENI@IlgN PAGE 26 u
- AMOWERS -- MONTICELLO
-87/09/01-KEETON, J.
ANSWER 6.01 (2.00) 1;
.y -
1.
Fuel grapple haist not full up
.y ;
2.
Fuel grapple hoist loaded
';l '
u 3.-
Frame-mounted au::iliary hoist loaded 4.
Trolley--mounted auxiliary hoist loaded (0.5 pts each)
REFERENCE Monticello:
Fuel Handling, LP M8107 L-019 234000K402
...(KA'S)
ANSWER 6.02 (W) Dele Alai et
~20* M c r r r u r i :,,' r ~
^ 52 - 257 A 1; gwiul O. ;: ; :'
_r'
"~. L...
L_. '.:
9;.
t r c r 2 :,
.5:.
(1.0)
"" "^
REFERENCE Mw, L u u l
.s.
^=eccru raJ a,- t : c r W r i '. c r ; -. ;
Ar cu h e, J. m. L i c r
- L._.; ;
...m 4.
l',.P i c, 4 V /
L,.
V / /
m 7-nnnen s e vennnn n, nea m ANSWER 6.03 (1.50) 1.
High drywell pressure EO.25] 2 psig EO.25].
(0.5) 1.
Lo-Lo water level EO.25] minus 47 inches [0.25] and reactor pressure less than 460 psig EO.25] or 20 minutes EO.253.
(1.0)
REFERENCE Monticello:
'
:!:. t Jt 4 *-
E' y seter t h ;9.r.
1.02 LO.5a
~ ' ' -
^
,c
'Jp~ & y/,b,as pu news t/opc e u.id% &c/1Mcn /S}ccohrcalrsU5-(9S}
g,9gm,,,,-f f e a djasf cl'or Sb~ U"~' ^" U"^' 24 b^s-MASTER COPY L
1
I
,7_
. _ P_ R_ O. _ C. E..D..W. iG_ _.
.N_ O.. R_.M_ f_'L_. A i._W..... C F4 R L
'.?'E F C E N C'
/WD PAE.E 37 4
R. A D...I,.O.. L O.. 01.r : A '_ _E. O.t].f. h. D L.
l
~..
)
5 1
cg; >,gj g.._.r
'qa. N r, i t r i..n
.. q 7,e..r..'/ so4 -l'.EE.TC."<i,,
3.
L.
a a
.w k
l i
i l
fttrEDE!Er M C F. I 1 C' 0 ; ) O I' O L.' C':"
CO G " 311 Cfl5 C.~
r7 O; q 4 r~ r, r.> r pJ (3 r, 4
.c 1 e r.) n. t.i J(,g. er
. 1 e n.. e.)e r. '.(31 S
... (f.'r4
?
J we
<s
~.6 4
s,
$7 lV "_"d,E f (
'. M /s
'1.SC/
t 1
I 1
I M ; a r ); mr c.it i on c enf t r me:rJ EO.5J e.r i d at1:e cv.; t e : o r t.
c c a l i n c.
- <..= s s u r e d r O., 5 J b v.
i j
n C C f[l(. '2[l
) b (,' 1 ( [, t J b ") b EOa 5]=
( 1 an E j
b 4
i l
$b [I',IU dU ~
i Mavt1celic c. s-. t 10 :.
L. v:i' c,,
T
,,, 7 r. o.'.. c_ o. r< 1 r
4..
1 l
ArJ C W E R 7.07 (1.50) q l
i CalLP a.,
b.
True C.
I B 1 Ef ts' R'E F E.RE N CE Mont; cella:
C.4-C 2 9 5 0 J t.O O Q '
"95016001C
':P503/f20 1 WA'0/
i
- f. f r, f "fl
'.),,
"n t)
(.'
f.") (, )
8.
C J.
E b
a CDi.lp ' 2.i003StiCn 4
[CCC Es ;; * ~3 m i n i t 1 i' l l T T )
NC1C initiSTiOn 5.
Di eGel q u}r er a t ar e i n i t i a t 1.;. r' (k///ftit*Cf,c17 $df"st/*7WCY/bt/%)
(0 ' ~, nt encn i. T.' r. f *., c : i r r,,
is L
,'r
.F J
8
. c y.
,,.; r n
- r. -
i..1 : " n..,
q '..'. i.,
'.m r. n ' ' 1 ' N '
.i ', '
t s.
l l
l l
I LSTED COP 1 1
e
{
\\
s
.. DC.
. A D N O..R. M A L.,.-.E.,M E...R. G..E N C. Y A.. N D PAGE 3r 7. ' ' P9.A. E. DU. T. E.. 5.. _NO R. M A.L a.
l
....O d,
..A.-
j-A P5 WE RE, -- MONTICELLO
-87/39/01-KEETON, J.
I i
4 ANENB.-
7.09 (2.00)
I 1.
' Reci rc-Loop temperature L0,2OJ with recirc pump running EO.203, 2.
RWCU iniet temperature EO 203 RWCU in operation EO.2OJ.
l 3.
RHR Mcal E:;r h ar.c er inlet EO.20] RHR/ shutdown cooling! in oper nian j
rO.2ca.
q 4.
Vess31 thell a nci flenge TCs E0.20] w/above systems s, hut down 5 0,. 20 ].
(0.4 pts for. arranging in preferential order.)
l REFERENCE i
l Manticello:
C.'.IV 205000 GOO 4 205000K103 205000K114
... (l: A " $ )
]
ANCWER
~'. 10
( 1., 00 )
May couse overhettino of the pump s e s.1 s [0,5]; pump m ?. '. be trippea E O,. 3 AFTEri the reartor in scrammed., and the accumulators are recharged [0.4].
REFERENCE Monticello C.4-B."~.5 29501CK10:
... I V A ' C :'
l AN3WER 7,11 (1 00)
Dieml generator power supply to the servic e water pump should be moriitor ed to pres ent o ve r i cm d,
(Euact wording not roucaced for full cred)+.i QF[p rT IC["
M on t i r.71 1 e :
C 4-f: 9.1.1.A,
- Cautto,
?(.H)OOKDOL
. (1 A 9 n' MASTER CCP2
- c. 7.,., ~~ P R. O C..E. D U..R E S...
N..O R. M A L.. A E N O R..M A L._...E..M... E.R G E.. N.C_ Y. A N.D.
_ FACE V
- ~~
~,
-~
, 88DIC-LOGI_GOL..,Ggh,7BQL'
.AfGWERS MJNTICEl.LC
- 9 ~,.' < 07 / 01 -KEETON,
J.
1 A N S W cr.:
7 12 (1 50)
Bus 15 sheds loadc E O. a] L..
.C'
~**
C
- m
[ C. 210 3.
(O.D)
STET 2
11 D/C auta starts.
(0.5)
^
'5.
Em?rgency serv 're t'ater pump n t e r t<:;.
(0.5) l REFERENCE M:.:r. t a c. e. ) o r C,4-D.9
.A 262OO lli.1 M 2d 200117.50:.
.. (KA'5)
ANOWER 7. l ' '.
(1.25)
Have t he concurrence and signe.turet of 2 ORO: E0.5]; ons must be the duty shift supervisor [0.25] and the intent of the procedure must not be changed EO 5]
(1.25?
REFERENCE Mor,t i c el 1 o.:
D.3 2340000001
.(1:A'C' ANGWER 7 14
( 1,. 00 )
b.
REFERENCE Monti c el I c :
C.5-1000
- en,.,., 4 ( n.,
< t c. c.,
w rw
..*l
., - 1.
.t Qs RASTER COPY l
t l
l 1
1 I
1 l
l 1
i
-.Z L.*_.. E80C.EDWBRE r _._UOBt9L.,. GENOGdS!:._El5BCEMCY 0t4Q PAGE
~J 6
,,, R_() D_.. _I.O_ L..O. G...I C_. A L C_O N.T.R....O L.
- (d4GWERS - MON'T ICELLO 07/09/03-KEETON, J.
. ANEWEP, 7.15 (2.50)
+..
NCNE S.
NONE
('101.PPV Leve'. 1102-Pr es sur e., and 1103--Power Contro]
c:.
1100 Serics i
J Si mu) taneous1 y)'
d.
NONE ar.1100 Ceries ( 1101 -Rf"> Leve l. 1192-Pressure, and 1103-Prst 'er
~
-Control Simultaneously) e.
1200 Seri es (1201-SP Temocrature, 1202-DW Temperature, 1203-T>r i m a r y Containment Pressure 3 an c' 1204-CP Level Simultaneously)
(,
l100 a.sd Roo wtrbs tesnivm g,
NONE AfotVi
, E i-
'~T 4_ : cn
+ "'
' ~ ~ -
h.
i.
2 /...-
, _ a s.
4.
c, 6_
L
(-_
i.
1100 Os.ri es 'as alaave Si tr ul t a n eaut.1 v )
j, NONE (0.25 pts eacle, all proceduren that recui r e t= i mul t an eou s entry must be utsted fcr full credit)
REFERENCE Manticelloi C.E 295024G011 2950250011 275030G011 295037G011
... W.A'S)
MASTER CCiPY
- i
. 94.%6?lilUlflB811.W_EBOCEDWSEL _ C9NplZJQNL _ GNO_[JL'JI61]ONE PAGE 3~7 N;'SWERG
- MONTIC:ELLO 07 / 09 / 01 --KEETON,
J.
s AbGWER O.01 (1.50) 2.
Assurino'the use of croposeti bypasses is revi ewed as required prior to authori;ing bypass installation.
2.
Approving ecergent.v byp Essec.,
7.
Maintaining and-controlling bypasses.
4
'wthor 1: : no bypast installation.
5.
I:e vi tmi t ig and authori.-ing removal of bypasses when required 6.
Nati3ying control room personnel oi bypasses to bo installed on Critical Dyntems.
7.
Assure tcmplelicn a-f Jumper Byp ass For:n requi rements.
C.
Assuring the B/ pass and Jumper Log Bool: is properly maintained.
9.
Assering i nciup en s en t ver i f icatione of byonst applications and remosal are conducted as required.
10.
Weekly auditing of the Lypass end Jumper Log 13cci:.
(Any 6.O O_25 pts ench) i REFERENCE I
Manticel1a: 4 ACD-4.O l
212000G001 2 2 3 0 0.1 6 0 0 1 262001G001 254001!'102 (VA'S)
ANCWER 8.00.
'2.00)
Reacter 1evel 2.
heactor p r e s s e -v' i
Reactor s i.. r a rr,
^
4.
Dr yel l pr ensur e f 0. c t r e s.c h i gr:r ERENCE M an :. ; c e l l n : f ACD J.'
21:00 ?tK O
~ P3i o it :o '
- .9 5 0.l K : il 2.:N 025D 02 295 0.' :. 2 : O
... ( l !(, " 3 )
MASTER COPY
3
%I.gdi((LgTO.GIIYE.230CGQQGEL. CObijl!.IOUL_EKi (I,d!.IQllOb'G PACE TO A;)*GWEfiT; -- MONT I CEL'_.O
- 07 /07/0 3 -KEETO.N',
J.
f.
[
~
S I
A!GtfEP U. 03 (1<25.
a.
(.)
400 Opm (O. :5) i, 4wn p ;.. y ( n.. nr )
, m.,
.,s s 2_ -
b.
!. O. 2 S J in medi a t el y E O. 2'5 ] and dail, thers'efter LO.25].
l fEFERENCE j
Monti cel10:
1 echo i c a.1 Sp ec i f i ci+ t i on r::i 3. 5. T~.
1 217000C0@
217000G011
.(KA'E' ANSWFR C.04 (2.50) 9.
Suspend fuel he.ndling EO.53.
The L.O f rom the previous Lhift wil]
sr. s t a s f v t n e 2 l i c en s;:rd operator requirement EO.53 and you c zo"i cel? in anothcr lice nsed (or unlicensed) operator E O. 5 ],,
(An iCO can elao be c al1 ed to continue iuel handling.)
b.
2.haur a
'O,5) 5)[ ldh /A N
b
- t.,
. Plant M E. n a g W ( i )..
j REFERTNT Monticel:o:
' ec t n i ;; a l O.;
- : f. et i ar <
Ni and Tab 2e 6,, 1. 1 4 ACD-J, p ;; 27
- m. ~suy q. n.. 3.,
.. ( p a, r,s,
l AN5WER G.05
( 2,, 00 )
j l
a.
T h e it.:: i rs ;. an ta nutify O f f--si te Emer oencv Menagement A g er.c !. e a,
b.
Anv Prntactann Action ilecommcndations maar to O f f-site Emerganc-Ma r a c sr.rrn t nurncie:.
C l is E 5 : f ) J D t 1 D,~1 Di SIi? [.
C') t.
d.
ITIP i..! O.; i.m J. r:; r <. tQ ~ t, cu j r U r i 31 i t'
- r 2 i i O h,,
i T his d ce s ' F ; ;; r cc c; ' r t ad ma" racis' ion te p osi:r e 1 1 T. i t ii.
[([F[.fif,'h.TT s..,.i c.l
,t.)
b n.
r
.i c...
1 i#..,ev
[ O i.') O [ "'i j h
[ O'(I C' '" I
"' 9 "
"[ l..$,1 *.
( l /,
OASTEP CCPY
9 i
l d
= i S W - A D M I N I.S T _P_4.T..I...V.. _E. _ _F_E D_._C._E..D._U..R.E. G_2._C_O.N_ _D I.T_ _3_ _O_N_C...A. _N D.. L.. I M I _T.A. _T...I-.O..N.._
PAGE 39 2
q N' 1WOG -- MONTICELLO
-07/09/01-l'.EETON.
J.
J
.3 i
1 ANOWER 8.06 (1.00)
{
c.
. ( 1. O )
i REFERENCE Monticelia:
Technica: Speci4: cations ";.10.D Bases.
2340000005
...(KA'S)
ANOWER G., C
(2.00) a.
V e r a. ' y cleted by attempting to turn vel ve handwheel in CW dirrtticn.
b.
Ver i f y. s.ealwi r e in pl ace (also accept visue! verification, i.e.,
v<$ 1 v e uteam and h a.n d w el l stici.s up F.t; o v e valve body).
c.
Vi sue:. by remote light indication (red-open; green-closed).
d.
Viseal by obsers ng pesi tion of valve stem f allcwer.
(O 5 pts each)
REFERENCE.
Menticello-4 AW!-4.5.1 29400!K101
...(KA'C)
ANOWER O.00 (2.Ou) a.
FALSE b.
FALCC c:.
TRUE d.
_ _: TRu[
REFr:RENCE Mrnt :. cel l t :
Technical Op er.
f i c ati on s. 6 1.
A Af:D- ~'.1, 5,12.15 4 A C I
.C.
4. -~ ~
29 OOli? : 6
( t A ' 02 )
MASTEE COPY l
l
.. O_ A.
AD ri ! N T C T_ R A.._ T.....I..V_E_. i_ P O... C..E DU. R._ E__S.a _C.O.N._D_.I._T.I O. N D >,.._ A N D _.L._7 M_ 1 T_A T_..I.O._N E.
PAG 40
' ANEWEEC -
110NTICCLLO
-S7 / 09 / 01 -l' EET ON,
J.
ANEWER O.09 (2.00) n.
1.
Initiate. recirculation niacie of M C R - H 5 ','- E F T Don ECLA's 1"
detected by emp11 J
i
]
3,,
InatiLte ee.mp1ing in ccntrol r oc.m I
4 4.
4 :t i va t.e CFIP A,.2-101
( Eme r a_ en t v. P1an)
S.,
Shutdown (ii } eve) w :.t.r r a n t. J. )
( frl y ' D O, " ptL EHch) b.
- solate norn.a1 HVAC system in cuar dScuse.
(0.5)
RETERENCE Manticellat A,4-002, 3
2940011':11.1
..(KA"C) i i
ANGlJER C,.10 C1.50) j 1.
At least are door in eech access opening i s. closed.
2.
CIGTS a u op er ab l e:.
j I
1 3.
All NP ver.1 system Nto irolttion vs.lves ope e.b3e (or svuured I
in closed position).
J (0.5 pts, ra c_h )
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S.
NUCLEAR REGULATORY. COMMISSION j)NP,.
REACTOR OPERATOR LICENSE EXAMINATION.
@A/ik
. FACILITY:
LigNIlgg6LQ_______________
'h M REACTOR TYPE: '
@WB-@g3__________________
DATE ADMINISTERED:
@ZZQ2/Q1_________________
EXAMINER:
gLBBM2_Ed_______________
fAa CANDIDATE
_________C_______________
'IBSIBugIIggg_Ig_geNDIpeIgi Use. separate paper for.the answers.. Write answers'on.'one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in par entheses 'af ter the question.
The passing grade requires at least 70% -in each category and a final grade of at least 80%. ' Examination papers will be picked up six (6) hours after
'the examination starts.
% OF l CATEGORY
% OF CANDIDATE'S CATEGORY i
l Y6LUE_ _I0186
___@ggBE___. _ y @(U E _ _ _ _ _ _ _ ___ _ _ __ _ _g61gG QS y__ _ _ __ _ __ _ _ __
i29tIU__ _21t@l 1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMDnYNAMIC'S, HEAT TRANSFER AND FLUI' FLOW
_2Dz99__ _2bzgZ 2.*
PLANT DESIGN INCLUDING SAFETY
(
AND EMERGENCY SYSTEMS
_p4.30 2ptM4
________ 3.
INSTRUMENTS AND CONTROLS
. 2Ez19__ _2br2@
4.
PROCEDURES - NORMAL, ABNDRMAL, EMERGENCY AND RADIOLOGICAL CONTROL
_20 1D__
Totals Final Grade All worP done on this examination is my own.
I have neither given nor received aid.
Candi dat e 's, Si gnature dt S 7kM l
l
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS v
q
[
During the administration of this examination the following rules apply:
1.
Cheating on the examination means an automatic denial of your application end could result in more severe penal ties.
2.
Restroom trips are to be limited and only one candidate at a time may leave.
You must avoid all contacts with anyone outside. the examination room to avoid even the appearance or possibility of cheating.
3.
Use black ink or dark pencil onlytofacilitatelegiblefeproductions.
4.
Print your name in the blank provided on the cover sheet of the examination.
5.
Fill in the date on the cover sheet of the examination (i f necessary).
6.
Use only the paper provided for answers.
7.
Print your name in the upper right-hand corner of the fir st page of each section of the answer sheet.
G.
Consecutive y number each cnswer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.
1 9.
Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets f rom pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
)
l
- 15. Parti al credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
I
- 16. If parts of the examination are not clear as to intent, ask questi ons of I
the examiner onl y.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not rece)ved ar been given assistance in l
con plet ing the examinat) on.
This must be done after the examination has
}
been completed.
l
7 - _ _ _ _ _
1Eh,4When you complete your ex ami nati on, you shall:
a.
Assemble.your examination as follows:
)
u i
1 (1)
Exam questions on top.
(2)
Exam aids - figures, tables, etc.
t, Answer pages including figures which are part dh the
~
answer.
)
(3) j b.
Turn in'your copy of the examination and all pages died to answer
)
the examination questions.
c.
Turn in all scrap paper and the balance of the paper that you did
]
not use for answering the questions.
d.
Leave the examination area, as defined by the examiner.
If after i
leaving, you are found in this area while the examination is s>till in progress, your license may be denied or revoked.
.1__EBING1ELES_9E_Nyg6g@B_EgMEB_ELONI_gEgB9IlgN Page 4
2
..ISEBd9DyN8digg2_Ug8I_IB6NSEgB_8ND_ELylD_ELOW
, s' i
l-QUESTION 1.01 (1.00)
,1 l
Crit'icality is defined as Keff=1,
[y
" FISSION CHAIN REACTION is SELF-SUSTAINING."
'1J7 SIMPLY STATE the process that makes it possible to appepr to have a self-sustaining reaction at Keff=0.90?
-OUESTION 1.02 (2.00)
The reactor is operating at 50% power when a f eedwater controller malfunction results in a total loss of feedwater flow.
A reactor scram will' occur due to low reactor water level.
Prior to the scram, reactor power will decrease.
Provide two reasons (include cause and ef f ect) for the' power decrease.
Include the reactivity coefficient that reduces power for each reason.
QUESTION 1.03 (2.00)
Concerning the core thermal limits:
For each condition given below, INDICATE whether it will cause an INCREASE, a DECREASE, or have NO EFFECT on Critical Power.
1.
Local Peaking Factor (LPF) INCREASES 2.
DECREASE in inlet subcooling 3.
INCREASE in reactor pressure
- 4. Axial power peak shifts from BOTTOM to TOP of channel l
(*++**
CATEGORY 1 CONTINUED ON NEXT F' AGE *****)
4
f' ~
1 1
Page 5
1.
PRIEdglPLEg_ gE_ Nyg6E AR_.EQW ER_ PL@N T_QPER9TigN2 3
.IUEBb9DYN6digg3_UE81_lBOUgEEB_GND_ELylD_ELgW l
.s '
j DUESTION 1.04 (1.50)
For the f ollowing transients, STATE which coefficient of reacti vi ty;
]
alpha T, alpha D, or alpha V changes reactor power FIRST and what EFFECT 1
it has on power (i ncrease/ decrease).
'g I
a.
A control rod is notched out two notches.
~
b.
Isolation of a feedwater heater string.
I c.
Relief valve lifting (opening).
QUESTION 1.05 (1.50) a.
STATE HOW the percentage of delayed neutrons produced in the CORE varies over care life and WHY.
b.
STATE HOW delayed neutrons contribute to the control capability of a commercial reactor.
DUESTION 1.06 (2.00) a.
Define the term Net Positive Suction Head.
(0.5) b.
Explain the importance of proper system venting for centrifugal pump operations.
(0.75) c.
Explain how operating a pump at shutoff head may cause overheating of the pump.
(0.75)
QUESTION 1.07 (1.00)
During high power operations (>60%), WHY is it more desirable to change power with recirculation flow than with control rods?
(1,0.
(
Y l
t 1
F
(*+**+
CATEGORY 1 CONT INUE.D ON NEXT PAGE ***+*)
9 nwm,---
]
f__ESlgCIE6E@_QE_Ugg6E98_EQWEB_ELONI_QEEB8IlQN Page' 6 i
, THERMODYNAMIC @i_ HEAT TRANSFER AND FLUID FLQW-i QUESTION
'1.08 (1.50)
DESCRIBE HOW;and WHY the discharge head of the core spray pump is affected.
f or. each of ' the f o11'owing. (Consider each condition sepdrately and
~
' assume NPSH is maintained in all cases.)
C;)
a.
Torus pressure increases.
b.
Torus water temperature increases.
QUESTION 1.09 (1.00)
Pellet-Cladding Interaction (PCI) failure was found to be dependent
.upon FIVE factors.
LIST four (4) of these f actors.
QUESTION 1.10
( 1'. 00)
EXPLAIN why dryers are installed in the off-gas system.
QUESTION 1.11 (0.00) deleted QUESTION 1.12 (0.00)
Deleted I
DUESTION 1.13 (2.00)
Reactor power is at 95% and control rod manipulations are in progress'per Reactor Engineer instructions. You, as Reactor Operator (RO), notice readings on the four rod display indicated a power decrease when & rod was withdrawn from notch 36 to 40.
A check of the LPRMs in quest i on show no malfunction. What is the cause of the power decrease?
E:< pl ai n your answer.
i
(****+
CATEGORY 1 CONTINUED ON NEYT PAGE
- +**)
____m-_.
L
. 1g PRINCIPLES OF NUCLEAR POWER PLANT OPERATION Page 7
[
3
.IBEBd9DYNed1Cg,_SEBI_IB8NSEEB_8Up_E6 gip _E60W L
QUESTION 1.14 (1.50)
EXPLAIN how natural circulation flow is achieved in'the-reactor.
Include' in your discussion the flow path and the motive' force for the flow.
- i
'I OUESTION 1.15 (1.00)
I STATE.TWO reasons for performing rod pattern exchanges.
QUESTION' 1.16
' ( 1. 75) a.
The reactor is operating at 20% power.
CALCULATE how long it would take to raise power from 20% to 40% with a 400 second period.
Show all work.
b.
STATE if a power change from 40% to 60% would take MORE TIME, LESS l
TIME, or THE SAME TIME as a power change from 20% to 40% with a 400 second reactor period for both power changes and EXPLAIN WHY l
I i
l i
l i
l
(+++**
END OF CATEGORY 1
- ++*)
i l
l
---.m
uh _' PLANT DESIGN 1NGLUDINQ_g@Egly_8ND_EMER@ENgX' Page 8
~
e
.EXEIEd5 QUESTION 2.01-(1.50)
Answer the following concerning the Motor Control Centegs MCC-133B and MCC-143B (swing bus):
{
a.
STATE how to determine if the automatic transfer scheme is aligned for automatic operation.
b.
LIST what-two (2) conditions will prevent automatic transfer of the Motor Control Centers upon a loss of voltage.
QUESTION 2.02 (2.25) a.
STATE the conditions necessary for initiation of ECCS Load Shedding.
b.
LIST five-(5) Of the eight (8) loads which are shed due to ECCS load shedding QUESTION 2.03
'2.50)
LIST five (5) of the six (6) conditions which must be satisfied to allow.
automatic closure of the 4.16 KV source breaker (ACB 152-502) to supply Bus 15 from # 11 Diesel Generator.
QUESTION 2.04 (1.75)
' STATE why the BN4 and BN5 breakers must be open prior to opening the a.
Number i Generator 345 KV disconnects, b.
LIST the required conditions for the Generator Anti-Motor Rel ay initiation.
c.
STATE the automatic actions of the Generator Anti-Motor Relay.
QUESTION-2.05 (2.50) a.
LIST the conditions that aut omati cal l y place the RWCU filter / demineralized into hold.
b.
LIST the autonatic trips for the RWCU pumps.
(*****
CATEGORY 2 CONTINUED ON NEXT PAGE *****)
l
2c__ELONI_DEQ1@U_ldCLUplN@_@@ Eely _6ND_QUEBGENCY Page' 9
,ieXSIEde QUESTION 2.06 (1.00)
STATE.whyfthe. Reactor Recirculation pumpmotor.startind;attemptsare limited.
t
.e t
$i I
QUESTION 2.07 (2.00) ~
LIST four-(4) areas of the Reactor Recirculation System / pump and/or motor that the Reactor Building Closed Cooling Water (RBCCW) System cools.
I QUESTION 2.08 (2.40)
LIST six (6) Of the eight (B) Main Condenser System /Offgas System TRIPS and ISOLATIONS.
(EXAMPLE:
The mechanical vacuum pump will trip and its suction valve will shut on a main steam line high rad.)
QUESTION 2.09 (1.50)
The minimum condensate flow f or two condensate pump operation is 5000 gpm but the recirculation valve setpoi nt is 6000 gpm.
EXPLAIN why the additional flow is required.
1 QUESTION 2.10 (1.75)
)
i i
a.
LIST the Standby Gas Treatment (SBGT) System automatic initiation j
i SIGNALS.
1 b.
EXPLAIN why both heater handswitches are neve 71 aced in the ON position when operating the SBGT system in Mf'.
l'.
QUESTION 2.11 (2.40) j Each control rod position indicator probe contains fifty-three (53) reed switches.
Forty-nine (49) of the switches are for control rod position I
indication from position 00 to position 48.
LIST the position, type of indication provided, and purpose for the other I
four (4) reed switches.
(++++*
CATEGORV 2 CONTINUED ON NEXT PAGE
- +**)
I m____..u__
.$ __E66N1_pg@l@B_INGLUplNg_S8EgIy_8Np_EDEBgENCY Page 10'
.SX5IEd3 QUESTION 2,12-( 1. 20)
. A flow-indicator is not provided f or Standby Liquid Control (SBLC).
STATE four (4) indications that can be.used to verify flow foI1owing an SBLC
!?/
system actuation.
l' DUESTION 2.13 (2.25) a.
STATE TWO systems that can be used to inject boron into the Reactor Vessel other than Standby Liquid Control, b'
The Standby' Liquid Control (SBLC) system is designed to provide sufficient reactivity compensation.to shut down the reactor from rated power to zero power.
This includes the 3% Delta K/K shutdown margin.
LIST FIVE additional reactivity gains / additions that must be compensated for by the SBLC system as specified by the system design bases.
1 l
l
(***** END OF CATEGORY 2 *+*++)
T.d__IdSIB9dENIg_8ND_QOUIBOLS; Page 11 a
J
'OUESTION 3.01 (1.75) h a.
LIST the components / systems that receive a signal from the LPRM Flux Amplifier.
i b.
EXPLAIN how bypassing an LPRM can generate an APRM INOP Trip.
):
QUESTION 3.02 (2.25)
The reactor is operating at 75% power when the Electric Pressure' Regulator fails and the Pressure Control. System shifts to the Mechanical Pressure Regulator.
STATE how the following parameters INITIALLY change and WHY.
a.
Reactor Pressure b.
Cor e Flow i
c.
Reactor power DUESTION 3.03
-( 1. 50)
LIST the required sig.als for automatic initiation of the ADS a.
System.
b.
LIST the required signals for automatic initiation of Low-Low i
Set Relief valve operation.
l QUESTION 3.04 (1.00) a.
STATE WHICH Reactor Water Level range indicates the ACTUAL level inside the shroud.
I b.
LIET the Jet pumps that are f ully instrumented.
I
'DUESTION 3.05 (2.40)
LIST si:: (6) automatic actions that occur at the Low-Low Wat er Level Trip.
(+****
CATEGORY 3-CONTINUED ON nlEXT PAGE
- )
~
~
Qt__~NSIBydENI@_@ND_CQNIBQ6@
Page 12 QUESTION 3.06 (2.00)
LIST four (4) inter]ocks that must be satisfied before a-reactor feed pump 1l will start.
- ).
QUESTION 3.07 (1.75)
The. reactor is operating at power.
State the effect on the recirculation flow control / recirculation system due to the following conditions:
(ASSUME NO REACTOR SCRAM) a.
Reactor power is 30% when the operator shifts the "A"
recirc pump M/A transfer station to AUTO.
b.
Reactor power is 95% with recirculation flow control in master manual.
ThL full open indication on the "B"
retircualtion pump discharge valve (MO 2-53B #12) is lost.
(NOTE:
The recirc pump #12 discharge bypass valve MO 2-54B is open)
I QUESTION 3.08 (2.25) a.
LIST the four (4) p] ant systems or components that recieve rod position information from the RPIS.
b.
STATE what automatically occurn upon reciept of an RPIS INOP.
c.
STATE the indications that will be recieved when a rod IS NOT being notched and an even numbered reed switch opens.
QUESTION 3.09 (1.50) a.
STATE how the RCIC Turbine speed signal is generated.
b.
EXPLAIN how the RCIC Turbine speed is controlled when the RCIC system is at rated ficw.
1 i
(*****
CATEGORY 3 CONTINUED ON NEXT PAGE
- )
\\
Page 13 3.
INSTRUMENI@_AND_G9NISQL@
l l
QUESTION-3.10 (1.50) a.
With the Recirculation System Motor Generator L(Reci.rc M/G) field breaker closed, the constant signal generator positions the scoop tube to the 50% load (SO% unloaded) position.
STATE the reason for this signal.
,,.7 sit b.
STATE the PURPCSE and SETPOINT for the Recirc M/G ismatch Bypass unit.
QUESTION
'.11 (1.20)
STATE the automatic trips resulting from a Main Steam Line High Radiation alarm at 4 R/hr.
QUESTION 3.12 (1,60)
During operation of the RHR syster, in the Shutoown Cooling Mode, the operating RHR pump automatically trips.
STATE four (4) possible causes for the RHR pump trip.
DUESTION 3.13 (1.00)
LIST FOUR (4) of the five (5) conditions that will remove all LPRM input to the Rod Block Monitor (RBM) Channel.
DUESTION 3.14 (1.60)
The reactor is in the Startup Mode at three percent (3%) power.
All SRMs, IRMs, and APRMs are operating.
LIST the alarms and indicating lights that would result if the IRM Channel 12 mode switch is shifted from operate to standby.
QUESTION 3.15 (1.00)
STATE why APRMs 2 and 5 or 1 and 6 are in the bypass state when not otherwise required.
l l
l
(
(+++++
END OF CATEGORY 3 **++*)
]
i
.4, PBOCEDURES - NQBd863_8BNQBd861_EMEBgENCy-Page 14 Jr
. AND RADIOLOGICAL CONTBQL.
1 9
l QUESTION 4.01 (2.00)
STATE the.10'CFR 20 and Monticello Station-quarterly whole body exposure
?
limits for the' followings (ASSUME NO AUTHORIZATION'HAS BEEN GIVEN TO EXCEED ANY HOLD POINTS) li! '
.Q
-a.
A twenty (20) year old man with,no NRC Form 4 on file and no i
previous exposure, b.
A twenty-five (25) year old man with an NRC Form 4 on file and 2000 mrem lifetime whole body exposure.
OUESTION 4.02 (2.40)
One of the. main objectives during accident conditions is to assure
" adequate core' cooling."
STATE the three (3) available methods (in their order of preference) to assure adequate core cooling; and how each method can be verified, as described in Operations Manual C.5.1.
I QUESTION 4.03 (1.75)
A normal shutdown is in progress per " Normal Shutdown," OPS Manual C.3.
a.
At what power level is the RWM automatically placed in service and what parameter is used to determine the power level?
(0.75) eorced.
b.
STATE the power level at which the RWM rod blocks are cr (0.5) c.
STATE what is required to bypass the RWM if it is inoperable during a shutdown.
(0.5) l l
DUESTION 4.04 (2.00)
STATE four responsibilities of the control room operator as outlined in EPIP A.2-101, Classification of Emergencies.
l
(+****
CATEGORY 4 CONTINUED ON NEXT PAGE *****)
1
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.4, PROCgpUBgg; _NgBM863_8pNgBMAL3_EMESggNGY Page 15
,E8ND_B8DI96001G86_99dIB96
{
QUESTION 4.05 (1.95)
'In. accordance with the approach to. criticality steps.id ';the cold i
'startup procedure, C.1, answer the following.
(
f q.
4
' x a.
STATE the Operator's required actions if critihal$fydoesnotoccur within the predicted critical rod pattern band indicated on Predicted Critical for Plant Startup f orm #2159.
b.
DESCRIBE.how an operator knows when the reactor is critical.
DUESTION 4.06 (1.00)
~'
Neither CRD pump will operate.
STATE what condition (s) require the.
reactor to be scrammed, as described in Operations Manual C.4.B.1.3.A,
" Loss of CRD Pump Flow."
Assume the plant is at 80% power.
QUESTION 4.07 (2.00)
An ATWS has occurred.
All scram valves have been verified open.
LIST
.THREE (3) methods IN THE PREFERRED order to insert the control rods, as outlined in OPS Manual C.4-A:
QUESTION 4.08 (1.50)
STATE when Temporary Procedure Changes CAN change the SCOPE or INTENT of an approved procedure, as described in 4 ACD-15.2, " Procedure Review and Approval."
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.h.
PROCEDUBED_ _NQRMAL _SBNQRMAL _gMEBGENQY-Page 16 2
2 1
c,AND RADIOLOGICAL CONTROlj A
i 4
QUESTION 4.09 (1.00)
.TRUE or FALSE
, jj p Answer the f ollowing questions concerning 4 ACD-4.7j "Sgneral Plant
]
?f.
d.
Operating Activities":
?
9; The Shift' Supervisor shall notif y the LPE and hO when leaving j
a.
or returning to the Shift Supervisor's Office / Control Room area.
j b.
ROs are required to inform the General Superintendent Operations when they do not meet the medical qualifications delineated in
QUESTION 4.10 (2.00)
Operations Manual Procedure C.4-B.9.2'A,
" Generator System Failure,"
Immedi ate Operator-action step 1.
states, " Verify AUTOMATIC ACTIONS."
LIST the FOUR (4) Automatic Actions listed in Procedure C.4-B.9.2.A.
QUESTION
'4.11 (2.00)
In accordance with 4 AWI-4.5.1, " Equipment Alignment Verification Methods,", STATE how the' correct position of the valves listed in a.
through d.
below are VERIFIED:
a.
A normally-closed raanual gate valve.
b.
A'normally-open seal-wired gl obe valve.
l c.
A motor operated valve (remote),
d.
An air operated valve (light indication defective).
QUESTION 4.12 (4.00)
Operations Manual Procedure C.4-A,
" Reactor Scram," Immediate Operator action step 1.
states, " verify AUTOMATIC ACTIONS".
LIST EIGHT (8) of the ELEVEN (11) Automatic Actions listed in Procedure C.4-A.
1 y
l i
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i
[__PBQGEDUBES-NORMAL ABNORM 8La_Et]EBGEtjQX Page 17 3
, SUD_B8R196gelG86_G991696
. QUESTION 4.13 (1.50) i I
When can an ECCS component be placed in MANUAL or SECURED in accordance with~a CAUTION in C.5-1101, "RPV Level. Control?"
.p.I a;;
STATE TWO conditions'and any indications required for confirmation.
I l
i-I
)
1 1
1
(***** END OF CATEGORY 4
- )
(*******+++
END OC EXAMINATION **+*******)
.l[ PRINCIP6g@_Q[_Nyg65AB_EQWEB_ELANI_QEER8TigN Page 18 2
.ISEBdODYU8 DIGS _dE8I_IBSUSEEB_8ND_E691p_E69W 2
MASTER COPY ANSWER 1.01' (1.00)
Subcritical. Multiplication (0.5) source neutrons-are equal to the number of neutrons lost in each generation (i.e.,
source critical)
(0.5).
REFERENCE I
Monticello: Weactor Theory, Chapter 3 292OO3K106
..(KA's)
' ANSWER 1.02 (2.00) 1.
(The decreased feed flow results in) decreased subcooling which adds negative reactivity due to the moderator coefficient.
(1.0) 2.
Recirculation pump downshift adds negative reactivity due to the void coefficient.
3.
(The reduced feedwater flow results in) decreased subcooling which adds negative reactivity due to the void coefficient.
4.
(Provided the candidate states the assumption that the recirculation pumps trip on low reactor water level) decreasing reactor level adds negative reactivity due to the void coefficient.
(any one of reponses 2, 3 or 4 for 1.0 points) l REFERENCE Monticello Reactor Theory, Chapter 4 292OO8K126 292OO4K114
..(KA's)
ANSWER 1.03 (2.00) 1.
Decreases 1
i 2.
Decreases 3.
Decreasen 4.
Decreases (4 0 0.5 pts each)
(****>
CATEGORY 1 CONTINUED ON NEXT PAGC +++**-)
l i
1 1
1 l
j i
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..e.-
ih_ _ EB10 GIE L E g_ g E_ Ugg 6 E BB_ EgB EB;E66 NI_ g E E B @Ilg N,5 Page 19
-,INEBd9DyN6digh _Ug61_IB8NSEEB_8MD_ELg1D_E69W REFERENCE
~
Monticello HT&FF, Ch 9, pg 9-26, 28, & 29 293OO9K122 293OO9K124 293OO9K125
..(KA's)
ANSWER
-1.04 (1.50)
-1 a.
Alpha D increases power (0.5) 6.
Alpha T increases power (0.5) c.
Alpha V decreases power (0.5)
REFERENCE Monticello Reactor Theory, Chapter 4, L.D.
3.3 and 6.3, pgs. 37-45 292OO4K105 292OO4K110 292OO4K114
..(KA's) l ANSWER 1.05 (1.50) a.
Decreases CO.25] due to the production of Plutonium 239 (Pu 239) or Pu 239 and Pu 241 which has a lower delayed neutron fraction than U-235 EO.5].
b.
Delayed neutrons increase the average neutron generation time, CO.25]
which slows dow'n and stabilizes reactor power changes EO.5].
REFERENCE l
Monticello Reactor Theory, Chapter 3, L.D.
4.6 and 5.6, pgs. 3-29, 3-30, j
3-31, and 3-33 l
292OO3K106 292OO1K102
..(KA's) 1 1
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l l
}
l Page 20
- -1c__PBINg1PLES OF' NUCLEAR POWER PLANT OPERATION2
-.IBEBdODXN8d1Gei_HE81_IB86SEEB_8NQ_E6919_E6QW ANSWER 1.06 (2.00) a.
NPSH is the dif f erence between total pressure at the eye of the pump and saturation pressure.
(0.5) 7 y.
' 'g b.
1.
To limit starting current-(0.125) ij -
2.
Minimize any fluid hammer in the downstream piping.
(0.5) 3.
Minimize the possibility of losing the pump prime (0.125) l The. pump adds heat to the fluid due to viscous friction to cause c.
eventual cavitation and pump damage due to insuf ficient cooling.
(0.75)
Any discussion of the fluid to pump friction will be accepted for full credit.
REFERENCE Monticello HTFF, Chapter 6, pages 6-108, 109, and 6-76 293OO6K117 293OO6K112 293OO6K110
..(KA's)
ANSWER 1rO7 (1.00)
Changing power with recirt ation flow changes total core power (0.5) while keeping the flux profile relatively unchanged OR to avoid localized flux peaking (0.5).
REFERENCE Monticello Reactor Theory, Chapters 5 and 7 293OO8K125-
..(KA's)
ANSWER 1.00 (1.50) a.
The same delta pressure is developed by the pump so as the suction pressure increases so will the discharge head. (0.75) b.
As temperature increases, system resistance to flow decreases (lower viscosity) therefore head decreases.
(0.75)
REFERENCE Monticello, HT O FF, Ch 7, pg 111 f
209001A102 209001A101 209001K102
..(KA's) l
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CATEGORY 1 CONTINUED ON NEXT PAGE **+++)
l L_______________________________.
n _ _ - _ _ _ _ _
l Page 21
- 11__EBIN91ELES_9E_NUGLE68_E9EEB_EL8NI_9EEBBI19N2
..IUEBdODXU801GS4_SE8I_IB9NSEEB_6ND_EL91D_EL9W o.
' ANSWER 1.09.
(1.00).
Fuel' rod absolute power. level y;
Fuel' exposure (Durnup) ifI Rate of power. increase Previous power history if
' Duration of. power-increase
'(Will also accept Requiren a Minimum Power Threshold."
(An'y 4 at 0.25!each)
REFERENCE Monticello HT & FF, Chapter'(7, L.O.
7.2, pg. 9-47 293OO9K 13'2
..(KA's)
ANSWER 1.10 (1.00)
The preheaters are installed to remove moisture which would prevent j
the'recombiner catalyst f rom operating properly. E 1. 01 t
REFERENCE-
' Monticello HT & FF, Chapter 3, L.O.
4.2'and pp. 3-32 271000K111 271000K302
..(KA's)
ANSWER 1.11 (O.00) deleted REFERENCE Monticello Reettor Theory, Chapter 6, L.O.
2.5, pgs. 6-10 and 11 292OO6K111 292OO6K112
..(KA's)
ANSWER 1.12 (O.00)
Del eted i
i J
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l
'1 1
L'
3- =-
.[3_ ' PRINCIPLES OF NUCLEAR EOWER PLANT OPERATION Page 22 2
LIbEBM9DyN8dlC@2_bg61_IB9N@[EB_@ND_ELylp_ELOW o
.i.
REFERENCE l
'.jg i
. ANSWER 1.13 (2.00)
': q :;
i
.f :
Reverse power effect E0.5]. Caused when withdrawal 'o f a shallow rod raises power low in the bundle EO.50] which causes an increase in the void fraction [0.253, which adds negative reactivity EO.253, offsetting the positive reactivity effects of.the rod withdrawal EO.53.
(alternate wording accepted)
TREFERENCE Monticello Reactor Theory, Chapter 5, pg. 5-25 292OO5K104
..(KA's) l 2
ANSWER 1.14 (1.50)
I 1
As water around the fuel is heated, it expands and becomes less dense EO.753.
The (weight) or downward force of the cooler water in the downtomer area exceeds the force of the warm water in the core.
i The resultant pressure difference causes the water in the jet pumps to be forced downward by the water in the annulus EO.75].
REFERENCE Monticello HT & FF, Chapter 8, pages 53-57 293OO8K134
..(KA*s)
ANSWER 1.15 (1.00) i l
f 1.
Promote even fuel burnout. (0.5) i 2.
Promote even control rod worth.
(0.5)
REFERENCE Monticello Reactor Physics, Chapter 7, page 7-21 292OO5K110
..(KA's)
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I
.[__ESINCIPLESOFNUCLEARPOWERPLANTOPERATION Page 23 3
. IMESD9DYU8Dics,_UEGI_I68NSEg6_GNp_E66J1p_E6QW
' ANSWER 1.16-(1.75) v a.
t= E.in (P/Po) (period)3 r
V
- ,f!.
s; E0.25]
P = 40%
Po = 20%
period.= 400 sec i
(.693) 3 (400)
(In 2) (400)
=
t=E in (40/20) (400)3
=
=
EO.753 277.2 sec b.
Less time from 40 to 60 than from 20 to 40. E O. 25 3.
Power is an exponential f unction and 40 to 60 is a smaller power change.E.05]
REFERENCE Monticello Reactor Physics, Chapter 3, 292OO3K108
..(KA's) 1 1
I i
1 1
l j
l 1
I 1
1 l
3 lk 1
1
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j
.Zz__EL8NI_DEDIGU_INGLUDIN9_58EEIY_8dD_EMEBGEUgy Page 24
..SYSIEdE-ANSWER
=2.01 (1.50)
'i The setup / lockout switch must be:in the setup position [0.5]
a.
4[
b.
1.
An overcurrent/ bus fault' [0.53 9l 2.'
The setup / lockout switch in the lockout p'ositpon
[0.53' REFERENCE-Monticello Lesson Plan M 8107 L-040 262OO1K403
..(KA's)
ANSWER 2.02 (2.25) a.
1.
Essential bus power not supplied by its normal source EO.53 2.
Core spray system is initiated E0.53 b.
1.
Instrument air compressors 2.
Service air compressors 3.
Drywell cooling recirc fans 4.
RHR service water. pumps 5.
Fuel pool cooling pumps 6.
Service water pumps 7.
RBCCW pump 8.
Control rod drive pumps 9.
Combutible gas control system (CGCS) 10.
Cooling tower pumps and fans
[any 5 at 0.25 each]
REFERENCE Monticello Lesson Plan M 8107 L-039 264000K405
..(KA's) s
(+**++
CATEGORY 2 CONTINUED ON NEXT PAGE
- +)
j
shz_ PLANT'DggigNjlygyUplNQ_gAEETy_AND_gMERQgNgy~
Page 25
..SYSIEMS ANSWER 2.03 (2.50) 4 1.
Diesel at voltage (within 10% of rated voltage)' i};.
'j,
'2.
- 1AR transformer de-energiced
- 3.
All source breakers to BUS 15 open.(ACB-152-511, 501 and 308) 5.
Breaker control switch on COO panel in auto
' l:
4.
Bus and breaker lockout relays reset 6.
Bus transfer lockout switch in set up (any 5 at 0.5 each)
NOTE:
Will accept any of the.following in place of #2 1.
Loss of voltage on lowside.of 1AR transformer 2.
Loss of voltage on essential bus for > 10 sec 3.
Degraded voltage on essential bus for > 10 sec REFERENCE
'Monticell o Lesson Plan ' M 8107 L-039 and Ops ' Manual, Secti on B. 9. 8 and B.9.6' 264000K506 264000K303
..(KA's)
ANSWER 2.04 (1.75) 1
.To prevent arcing damage to the disconnects ~EO.5]
a.
b.-
1.
BN4.or BN5 closed CO.25]
2.
345 KV disconnects closed E0.25]
3..
Turbine stop valves closed CO.25]
c.
Trips the BN4 and ONS breakers E0.53 REFERENCE Monticello Lesson Plan M 8107 L-034 262OO1K404 262OO1K402 294001K107
..(KA's) i m3 1l'
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CATEGORY 2 CONTINUED ON NEXT P A G E * *+ + + )
.__________]
7 57.
r FLANI_pggl@N,.lyCLyp1NQ_g8FETy_AND_gMERggN9y.
.Page 26 i
SYEIEdD-7,'
SANSWER 2.05
( 2. 50 )'
a.
1.
Low flow E O. 53-2.
High's*rainer D/P EO.53 d'
3.
High' filter /demin D/P EO.5]
- ?
.(
b.
1..
. Pump bearing cooler high temperature EO.53 2..
Full closure of'the return isolation valve'(MD-2399) EO.25]
or either of the inlet -isolation valves (MD-2397.or 2398) not full open. [0.253 REFERENC'<;
Monticello Lesson' Plan'M 8107 L-030 204000K110
..(KA's)
ANSWER 2.06' (1.00)
To prevent overheating and possible' motor damage due to the starting current heat.
-or-To prevent thermal and mechanical stresses to the.
motor.fromLetarting current' heat.
(either answer 1.0)
. REFERENCE-Monticello Lecson Plan M 8107 L-029 202OO2AOQ9
..(KA's)
ANSWER 2.07 (2.00) 1.
Recirc' pukip motor upper thrust. bearing and guide bearing oil cooler EO.53 2.
Recirc pump lower guide bearing cooler EO.53 3.
Lower seal system heat exchanger and seal region cooling jacket EO 53 4.
Upper seal heat exchanger [0.5]
REFERENCE Monticello Lesson Plan M B107 L-029 202OO1K403
..(KA's)
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CATEGORY 2 CONTINUED ON NEXT FAGE +++++)
.m-L.-_
I4 dh__E699IlDE5199_IU969DIUS_S9EEIY_899_EDEBDEUGy Page 27
, SYDIEUS-i f iNSb!ER 2.08 (2.40) l 1A 1.
The MVP.cannot be started unless backwash recieving tank vent valve (OG-28)is shut
?!
+ :d OG-29isopenedwithouttheifdpbypassswitch l2.
The MVP will trip if in bypass l
7.
The seal water circ pump will stop on a main steam line high rad The air ejector suction valves close if:
4.
high off gas pressure 5.
high off gas temperature 6.
main steam pressure.less than 100 psig 7.
Rx scram if condenser vacuum <23"hg (bypassed with main steam pressure <'600psig) 8.
Turbine trip if vacuuta <20"hg 9.
High of f gas flow-10.
Low dilution steam flow
~1 1.
High eductor di scharge pressure 12.
High offgas radiation levels 13.
Two of the three analyzers disabled in the operating train (Any 6 at 0.4 pts each)
REFERENCE I
e l.-
Monticello Lesson Plan M0107 L-011 and M8107 L-OO9 271000K408 2/1000K301
..(KA's)
. ANSWER 2.09 (1.50)
The add 2t2onal flow providen cooling LO.5]
for the SJAE LO.53 and steam packing condenser EO.5]
W I
I I
J l
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CATEGORY 2 CONTINUED ON NEXT PAGE ++++-+)
N
'e 1
L-_..-._______
l
.Ni__EL691_DEH196_ING69 DIN 9_S6EEIY_6dD_EMEBQgNGy-Page 28
..iSYEIEUS
.W l REFERENCE Monticella' Ops Manual, Section B.6.5 256000K107
..(KA's)
~*
j,4.
Q.'
ANSWER 2.10 (1.75) j a.-
1.
Rx b1dg-vent plenum high rad CO.25]
2.
Refuel floor high rad E0.253 3.
High drywell pressure EO.253 4.
Rx-low l evel-E0.25]
5.
Rx b1dg vent high-high ef fl uent.
[0.253 b.
Prevents overheating the charcoal adsorber bed and/or warping the-aluminium bed trays -or-The heaters should not be used while in manual operation because the heaters will not trip on high temperature.
(either answer for 0.5)
REFERENCE Monti cello Lesson Pl an M 0107 L-OO8 261000K401
..(KA*s) t l
N l
l l
l l
1 i
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l 1
i l
Ic_-_____
ih2 PLANT 'pggigN_1Ng6 Lip 1NG_SSEEIy_SNp_gdEBggNgy Page 29 l
i
,.SYSI5d2 j
u 1
1
-ANSWER 2.11 (2.40) s Position I ndi cati on.
}l.
Purpose J
l
.1.
Full in/OO position Green background light-
" Full-in position l
'fndication (0.2) i (0.2) on the tens. digit on the full core display (0.2) i
- 2. -
"Just above full-in Keep the green light.
In this case there switch (0.2) in the full core would be no number display window displayed on the if the rod has full. core display drifted upward past (0.2) the 00 position (0.2) 3.
Full out/48 position Red light background Full out position (0.2) on both. digits on the indication (0.2) f ull core display (0.2) 4.
Just below the 48' Used in a nummary Indication that the
. position (0.2)'
circuit to annunciate drive is not rod overtravel (0. 2 ) '
coupled to the rod (0.2) i L
' REFERENCE Monticello OPS Manual, Section D.5.4, page D.5.4-3 214000K105 214000K401
...(KA's)
ANSWER ~
2.12 (1.20) a.
decrease in reactivity /(power) b.
SLC storage tank draindown.
c.
pump running indication, d.
SQUID indicating light out.
e..
Steam flow from vessel decreases.
(Any 4 @ O.3 pts ea)
(++**+
CATEGORY 2 CONTINUED ON NEXT PAGE +++++)
5__EL6BI_ DES 10N_ING6991N0_SeEEIY_GND_EdEB9ENGY Page 30 SYDIEUS
. REFERENCE Monticello SLC, B.3.5, pg B.3.5-0010 211000A107 2110004102 211000A103 211000A101
..(KA's)
Il~
1,.
'f-
. ANSWER 2.13 (2.25) a, 1.
CRD pump (with a hose from SBLC)
EO.53 2.
RWCU (boron added to the RWCU system then injected)
LO.5]
b.
1.
Change in alpha viods 2.
Change in alpha doppler as fuel cools 3.
Xenon decay after the peak 4.
Change in alpha T from hot to cold 5.
Improper /non. uniform mixing 6.
Sol uti on leakage from the reactor 7.
Soluta an dilution when shutdown cooling is placed in service (Any 5 at 0.25 pts each)
REFERENCE Monticello Lesson Plan M 8107 L-OO4 211000K501 211000K503 211000K105
..(KA's)
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i
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t b
v'
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Page 31~
n ANSWER 3.01 (1.75) a.
1.
Rod Block Monitor EO.253 2.
APRM channel E0.253 6'-
- 3. -
Process computer E0.253 f'
4.
.1, 5.
del eted 6.
deleted b.
When.the APRM' count circuitry counts'less than the preset number of LPRM input signal s to an APRM channel, the count circuit will trip and generate an APRM INOP Trip.
(0.75)
REFERENCE Monticello Lesson Plan M 8107 L-066 and M 8107 L-069 215005K104 215005K103
..(KA's)
! ANSWER 3.02 (2.25) a.
Increase [0.253 due to the control valves throttling shut in response to the pressure regulator system shifting from the EPR to the MPR and the MPR setpoint being at higher than the EPR EO.53.
b.
Increase EO.253 the increased pressure reduces the void content of the two phase mixture in the core. Less two phase flow, less restriction to core flow EO.53 -or-no indicated flow change
~EO 253 due to the small change in pressure no change in core flow would be indicated-
[0.53.
c.
Increase [0.253 higher reactor pressure collapses voids and a negative void coefficient adds positive reactivity and increases power EO.53.
REFERENCE Monticello Lesson Plan M 8107 L-048, Reactor Theor,y, Chapter 4 and HT and FF, Chapter 8, pg 8-41 241OOOK101 241OOOK102 241000K301 241000K302
.(KA's)
I
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7
' 3 __INEISUMENI@_6NQ_GQNIBQL@
Page 32 t
i ANSWER
'3.03 (1.50) a.
1.
Low-Low Rx Water Level (at or below -47 inches)
? i-2.
At least one RHR or CS pump running (disch pqess > 85 psig).
o.
3.
Delay timer timed out af ter Rx level < low-loh level (107 set after water level at - 47 inches)
(3 at 0.25 pts each) b.
1.
Handswitch in auto EO.25]
)
2.
A reactor scram signal present EO.25]
3.
At the high pressure setpoint EO.25]
4.
deleted 5.
deleted i
REFERENCE.
Monticello Lesson Plan M 8107 L-025 239002K401 218000K501 218000K403 239002K402
..(KA's) l ANSWER 3.04 (1.00) a.
Lower 400 (core flooding 400")
EO.5]
i b.
1, 6,
11 and 16
[0.53 REFERENCE Monticello Lesson Plan M 8107L-056, pages 11 and 13 216000K501
..(KA's)
I f
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- +)
1 m__.m__.___
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_INSIEWMENID_8NQ_GQUIBgLD Page 33 ~
>?
ANSWER
-3.05
( 2. 4 0 ) '-
1.-
Initiate HPCI 2..
' Initiate RCIC
' lj l" 3.
Recire pump trip 4.
PCIS Group Isolation _(Group I) 1 5.
Diesel start 1l:
6 '.
Enable CS and LPCI (pumps start if Rx pressure <450 psi'g) 7.
ATWS (9 sec. time delay)
- 0..
. ADS
-(107 sec time delay)
(Any 6'at O.4 pts'each)
REFERENCE Monticel'lo Lesson Plan M 8107 L-056 and Ops Manual, Section,8.3.3 216000K104 216000K102 216000K101 216000K107 216000K106 216000K105.
..(KA's)
ANSWER 3.06 (2.00) l '.
Suction pressure
(> 85 psig)
- 2. -
Lube oil pressure
(> 5 psig) 3' Recirc valve open 4.
reactor water level
(<
48 inches) 5.
IW-98-1 and 2 open
-or-reactor injection shutoff valves located in the drywell
~ (Any 4 at 0.5 pts each)
REFERENCE.
Monticell o Ops Manual, Section B.6.5, 259001K105 259001K101
..(KA's) l'
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d __INSIEUMEUIS_8ND_CQNIBg65 Page 34 ANSWER 3.07 (1.75) a.
The control system will generate a step. increase to the setting of the master controller and the recirc pump speed;will increase to the master controller setting EO.5].
The rate 11imi ter will control the speed increase at 2%/sec E0.253.
2['s.
I b.
Loss of discharge valve open indication removes the bypass signal f rom the speed limiter and the the speed limiter generates a 24%
signal CO.5].
The "B" pump will slow to 24% because an interlock prevents the mismatch summer from generating a scoop tube lockup E O. 5].
REFERENCE Monticello Ops Manual, D.5.8, pg B.5.8-2,3,4 and B.1.4, pg B.1.4-30,31 202OO2K407 202OO2K402
..(KA's)
ANSWER 3.08 (2.25) a.
1.
RWM 2.
Process Computer 3.
Full core display 4.
Four rod display E4 at 0.25 each]
b.
Rod select block
[0.5]
1 c.
1.
Blank full core display EO.253 l
2.
Dlank four rod display E0.25]
3.
Rod drift alarm E0.253 REFERENCE Monticello Ops Manual, D.S.4 214000K107 214000K101
..(KA's) i l
i
(++**+
CA TEGORY 3 CONTINUED ON NEXT PAGE +++**)
l
-i __1bSIBUMENIS_8ND_CQUlggLS Page 35 ANSWER 3.09 (1.50) a.
Speed is determined by the frequency of an AC vo'Itage signal CO 25]
it passes a; magnetic speed generated by=a 48 tooth gear E0.25] as pickup unit EO.253 y,,
b.
RCIC turbine speed is controlled by comparing actdp1 turbine speed to with required turbine speed, generated by the ramp generator / flow controller, CO.25] which generates a signal to adjust the turbine steam flow EO.25]
REFERENCE Monticello Lesson Plan M 8107 L-OO3 217000K203
..(KA's)
ANSWER 3.10 (1.50) a.
The signal ensures that when the recirc M/G fi eld breaker is closed that there is sufficient break away torque to start the Recirc pump. (0.75) 6.
Bypasses the scoop tube mismatch lockup signal when Recirc M/G speed is less than 25%.
(0.75)
REFERENCE Monti cello Lesson Pl an M 8107 L-047 202OO2K405 202OO2K402
..(KA's)
ANSWER 3.11 (1.20) 1.
Reactor Scram
[0.43 2.
All MSIVs shut E0.43 3.
Mechanical Vacuum Pump (MVP) trips EO.2] and MVP suction valve shuts EO.23 REFERENCE Monticello Lesson Plan M 8107 L.-077 271000K408 212OOOK105 223OO2K101
..(KA's) r l
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CATEGORY 3 CONTINUED ON NEXT PAGE +++++)
t 3:__IN@IBgMENIS_8ND_GgNI6965 Page 36-L ANSWER.
'3.12 (1.60) 1.
Overcurrent 6y r a,
c
~
vessel )gj.
. pressure or 75 peig 2.
High RHR pump suction pressure (40 psig Rx suction pressure)
' O,'
(1,jh 3.
Low reactor vessel level
(+9 inches) 4.
High drywell pressure (2 psig in the drywell) 5.
Closure of the pump suction valve (any 4 at 0.4 each)
REFERENCE Monti cell o. Lesson Plan M 8107 L-023 and M 8107 L-070 205000K403 205000K402
..(KA's)
ANSWER 3.13 (1.00) 1.
Edge Rod Selected 2.
No Rod Selected 3.
RBM Channel Bypassed 4.
Reference APRM Downstale 5.
Null Sequence - No Balance (Any 4 0 0.25 pts each)
REFERENCE Monticell o OPS Manual, Section B.5.1, page B.5.1.2-25 215002K102
..(KA's)
^
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CATEGORY 3 CONTINUED ON NEXT PAGE
- +***)
-A_ _ _ _ - _..
Page 37
.N[__IUSISUMENI@_SND_GQUIBgLS t
e u*
b o ANSWER-3.14 (1.60) 1.
IRM A Hi-Hi/Inop alarm 2.
' Rod Block Alarm i
3.
1/2 Scram Channel A alarm 4.
Red-IRM 12 Hi"Hi/Inop Light
. (4 @ 0.4 pts each)
REFERENCE Monti cello OPS Manual, Section B.S.1, pgs. B.5.1-28 to B.5.1.1-40 215003K402 215003K401
.. (KA 's) l ANSWER 3.15 (1.00)
The LPRMs supplying APRMs 1 and 5/ 2 and 6 are shared [0.53.
A shared
,LRPM failing high could'cause both APRM channels.to attain their scram setting EO.53.
(1.0)
RDERENCE Monticello OPS Manual, Section B.D.1, pgs. B.5.1.2-19 and 20 215005K104
..(KA's) i 1
(++**+
END OF CATEGORY 3 *****)
l I
w L\\
Page138
'- at__ES9EEDUBED_:_NQBUO63_ ABNORMAL _EMgBQgNgY 3
..'OND_BSDI96991G96_99 NIB 96
. ANSkJ,d 4.01 (2.00)
NRC Monticello-jf y.
a.
1.25. Rem / quarter (0,5) 1000 mrem / quarter'to.5)
);I b.
3 Rem / quarter (0.5) 2000 mrem / quarter (0.5)
LREFERENCE
- Monti cell o 4 AWI-11.1.14, pages 4 and 5 294001K103
..(KA's) l ANSWER 4.02-(2.40)
IN ORDER OF' PREFERENCE 1..
Core submergence.[0.303 verif y by 2 means of level indication that l evel is above TAF [0.53 2.
Spray cooling [0.'303 verify by one core spray system operating at or above design conditions [0.53 3.
Steam cooling.CO.30] verify by use.of steam flow over fuel and out of vessel via SRV's as per EOP (cannot be verified by direct indication)
{0.5}
REFERENCE Montice lo EDPs C.5.1 - 2003, pages 2, 9,
and 10 C.5.1
.2004, pages 2, 7,
8,
&9 C.5.1 - 2006, pages 2 & 7-33 295031K304 295031K303 295031K302
..(KA's) 1 i
I
{
l l
l i
)
1
(+++++
CATEGORY 4 CONTINUED ON NEXT PAGE +++++)
J l
1 t
l
.*d.
PROCEDURES LNORMALA_ADNQSM863_EMESGENGY Page 39
. 8N9_B8D196991G06_99 NIB 96
+
ANSWER 4.03 (1.75) a.
RWM placed in service automatically at <= 35% poweq as measured by steam flow.
(0.5) b.
RWM rod blocks become effective @ 20% (0-20%).
(Cl5) c.
If the RWM is inop checklist #2169 must be completed
-or-a second independent operator or engineer shall verify that all l
rod positions are correct prior to rod insertion and shall ensure the console operator follows the rod program. (either answer 0.5)
REFERENCE Monticello Normal Shutdown, C.3, pg C.3-OOO6 201006K407 201006K404 201006K104
..(KA's)
ANSWER 4.04 (2.00) a.
The control room operator shall immediately notify the Site Superintendent of any events that may be classified as emergency
( 0. 5:
conditions.
- b. The operator shall attempt to verify any indications.
(0. 5:
- c. The operator shall assi st the Site Superintendent in assessing the indications and determining the class-l (0.5:'
ification of emergency.
- d. The operator shall take immediate actions as dictated by plant procedures and his general knowledge to control the event and place the plant in a safe condition.
(0. 5 '
(The candidate's answers need not be verbatim to the above)
REFERENCE Monticello EPIP's, A.2-101, pg 4.
2575000G011
..(KA's) l
(*++++
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- +*++)
L_-__-__
' ~
4:
J-Laza_BB9EEDUBED_:_NgBUSL2_8BNg8d863_gdgB@gNgY Page 40 3..GND_BSD196991G86iG9 NIB 96' l ANSWER
.4.05 (is ;?
a.
'1.
1 Discontinue rod withdrawal
-2.
Maintain.the reactor.subtritical 3..
Notifyfthe Shift Supervisor l7,1.
I.
-(3 0 0.4 pts ea) b.
' Neutron Flux rises EO.253 with a constant (stable) period EO.253 without additional control rod withdrawal EO.253.
(0.75)
REFERENCE Mont i cel l o, Startup Procedures, C.1, Col d StaEtup, Approach to Critical, pgs 25 and 26 292OOSK108 201000 GOO 2 201000 GOO 1
..(KA's)
. ANSWER 4.06 (1.00)
When the second " accumulator low pressure" alarm is received.
(1.0)
REFERENCE Monticello OPS Manual, Section C.4-B.1.3.4, page 4
.201001A210 201001A204 295022K301
..(KA's)
ANSWER 4.07 (2.00)
.a.
Reset the scram and manually scram the reactor.
If rod motion is observed, repeat.
(0.5) b.
Reset scram and individually scram those rods not f ully inserted.
(0.5) c.
Use the reactor manual control system to insert rods.
(0.5) l
-Correct order, as above EO.5].
REFERENCE Monticello OPS Manual, Procedure C.4-A, pages 7 and 8 295037K307
..(KA's) l
(++*+*
CATEGORY 4 CONTINUED ON NEXT PAGE
- )
-I(__ES99EDgBgs_:_N9Bbe61_0BN9Bd862_EMEBggNQY ~
Page 41
- 0ND_BSD196991GOL_G9 NIB 961
- .~
ANSWER 4.OG (1.50)
During emergency situations when procedure changes areTNecessary to 00.53.
prevent injury to' personnel (including the public) CO.5j or damage to the.
facility EO.53.
,..i!:
o-REFERENCE' Monticello 4 ACD-15.2, page 7 2950000010
..(KA's)
ANSWER 4.09 (1.00) a.
True (0.5) b.
True (0.5)
J-REFERENCE.
1 Monticello:
4 ACD-4.7~
212OOOGOO1 295006 GOO 2 295031 GOO 1 295025 GOO 1 295024 GOO 1
..(KA's) l l
l ANSWER 4.10 (2.00) 1.
Turbine lockout replay trips CO.253 when loss of adequate field current relay actuates EO.253.
2.
Generator. breakers trip if system frequency remains at 58.5 H: EO.253 or.less for 15 seconds f ollowing generator lockout relay trip EO.253.
3.
Turbine trips EO.253 if generator lockout relay actuates EO.253.
4.
Reactor will scram EO.253 when turbine trips EO.253.
REFERENCE Monticello OPS Manual, Volume C, Procedure C.4-B.9.2.A 262OO1K603 262OO1K105
..(KA's) i l
(+++**
CATEGORY 4 CONTINUED ON NEXT PAGE *****)
i l
n.
- 4.. PROCgQQBEg_ _NQBM863_8SNgBM862_EMEBgENgY
'Page 42 BNQ_BBQ196991gG6_ggyIBQL ANSWER 4.11 (2.00)
Verify closed by attempting to turn valve handwheel in CW direction.
a.
A*
b.
Verify sealwire in place (also accept visual verification, i.e, valve stem and handwell sticks up above valve bodyf.
c.
Visual by remote light indication _(red-open; green-closed).
d.
Visual by observing position of valve stem follower.
(0.5 pts each)
REFERENCE Monti cel l o:
4 AWI-4,5.1, pages 2-4 294001K101
..(KA's) 1 I
1 I
(**+++
CATEGORY 4 CONTINUED ON NEXT PAGE ****+)
9
ll
. h. - PROCEDUBES - NORMAL ABNORMAL _gMgBGENgy Page 43 i
ti 3
j-l' 889_B0D19690190L_99NI896 I
\\
l i
p
)l 1
i l
ANSWER 4.12 (4.00) l l
f ull y ' inserted into' the { core.
1.
All withdrawn control rods 2.
Scram discharge volume vent and drain valves closef.
l rr.
3.
The pressure regulatory will operate turbine contro!l valves and j
bypass valves to maintain pressure at the pressure setpoint.
4.
Feedwa'ter flow will be reduced by the reactor level control system, in most cases after an increase in feedwater flow from collapse of steam voids in the reactor.
- 5. -
The turbine exhaust hood sprays will initiate when the turbine control valves cam position reaches 15%.
6.
Condensate demineralized unit discharge valves will close and holding pumps will start when flow through a unit decreases to 800 gpm.
7.
When feedwater flow drops below 20% (1.33 x 10E6 lbm/hr) the recirculation pump speed will automatically be reduced to 30%.
B.
Feedwater pump recirculation valves will modulate to' maintain 3300 gpm flow through the pump.
9.
The condensate recirculation val ves will open to maintain 3000 gpm flow through the pump.
10.
The tubine-generator unit will motor, causing a turbine trip if not already tripped from another reason.
11.
With the made switch in RUN and turbine stop valve inlet pressure less than 840 psig, the MSIVs will close.
(Any 8 @ 0.5 pts each)
REFERENCE Monticello OPS Manual, Volume C, Procedure C.4-A 295006K207 295006K204 295006K202 295006K201
..(KA's)
AN5WER 4.13 (1.50)
Micoperation confirmed LO.5] and adequate core cooling is assured EO.5] by at 'j emst 2 independent indications LO.5].
(1.5)
(+++++
CATEGORY 4 CONTINUED ON NEXT PAGE
+****)
a
.dz__EB99E9LJBE!I_ _N9BdOb2_6EN980GL2_EdEB@ENgY.
Page 44 OND_B8D196991G86_G9NIBQL x
REFERENCE.'
Monticello:
C.5-1101 209002 GOO 1
.(KA's)-
- o. s ?. i, :
e
- t..
g4-se
- -Pf.;.
,4 h ! i
?
l
-l l
j i
4 I
(
(+++++
END OF CATEGORY 4
- )
(********** END OF EXAMINATION **********)
l
. J
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(
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j 1
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=
=
=
=
=
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se
=
=
=
e=
Xenon Response to Steady-State Power Decrease i
mes-l ms I
1 2
m a
=
a m
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i i
i 3
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=
=
=
=
w em 1
n Xenon Response To Steady-State Power increase 1
1 4
ATTACIMENT 1
,l e'
I a
I L-_-_.______-__-___
....]
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Xenon Response to a Reactor Scram I
l i
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4 ATTACHMENT,la 1~
9 0,
5 i
O i
p EQUATION SHEET s
f = n er.
Y = s/t Cycle efficiency = I'
'I '
2 u = e5 -
s = v,t + hac E=
a = (vg - y )/t
~
2 A
- AN A"
o*
g a v, + a EE = huv v
PE = msh a = e/g A = in 2/tg = 0 693/tg.
q 8 " '
(c,)(ts) 7
%(*"} * (tg+e}
AE = 931Aa b
" k AT I = I,e"I*
p
. v=
l
, 6 = n47 F
= wj r r=r/,1,-/rn.
l 2=
I m (t)-
TM,= 1.3/p F = P, 10 f
RYL
- 0.693/p tI F = P, a I
' SUR = 26.06/7 I
sCR = 5/(1 - K,gg) j T = 1.44 or f1'gg)
CR,= s/(1 - E,gg,)
o sua = 26 3,,
"If ~"aff}1*C8fl~~Keff}it f
2 T = (1*/o ) + [(f t o)/A,gg ]
o y = 1*/ (,_ p M = 1/(1 - K,gg) = CR /CR0 g
~P aff' M = (1 - K,gg)0 (1 - K,gg)g
/
8 " IE
-1)/K,gg = R,gg/Kaff SDM = (1 - K,gg)/K,gg aff
~3
[L*/TK,*gg.] + [I/(1 + 1,gg )]
1* = 1 10 seconds T
p=
aff.e 0.1 saconds"I
~
F = I(V/(3 x 1010) g A
I = ur Idgg=1d22 Id =1d UATER PARAMETERS g
2 2
R/hr = (0.5 CE)/d g,,,,,,)
l 1 gal. = 8.345 1ha R/hr = 6 CE/d (feet) 1 gal.
3.78 liters MISCE 1.1.ANEOUS CONVERSIONS 1 ft = 7.48 gal.
10 3
1 Curia = 3.7 x 10 gp, Density = 62.4 lbs/f t l
3 Density = 1 gm/cm 1 kg = 2.21 1ha 3
Heat of vag orizations = 970 Etu/lba 1 hp = 2.54 x 10 BTU /hr 0
Heat of fusica = 144 Btu /lba 1 N = 3.41 x 10 Beu/hr g Atm = 14.7 psi = 29.9 in. I'g.
1 Stu = 778 f t-lbf I ft. H O = 0,4335 lbf/in
!' inch = 2.54 cm 2
"F = 9/5'c + 32 l
'C = 5/9 ('r - 32)
=
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===== 20% CCCCCC
~~~ ~
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NQ I
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=
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I I
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I I
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L
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1 se
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R3 s
idteom/7; M,Msfsteem
__?
sesen:me esnowet ensam me4es seni8. I hen been ekstremad tem 7;
..d,. ;.t ad Trenepart nepart es et seene (Ospyright. Iss7, my 7he amerkan society er anschenical Engineers.)
TaWe 1 Pr7-tiet of satursted sts8m and saturated water (temperature).
Volume,ft /lb Emeholpy,Stu/lb Entropy,Stu/lb s F 8
Wueer Evep Steam Weter Evep Steam Water Esop Steam T7 n
O v,
n, n
s, e,
e h
32 OD8859 OD1602 3305 3305
-CD2 1075.5 1075.5 0.0000 2.1873 2.1873 32 35 0.09991 SD1602 2948 2948 3D0 1073A 1076A 0.0061 2.1706 2.1767 35 40 0.12163 OD1602 2446 2446 8.03 1071D 1079.0 0.0162 2.1432 2.1594 40 45 0.14744 0D1602 2037.7 2037A 13.04 1068.1 1081.2 0.0262 2.1164 2.1426 45 to
. 0.17796 CD1602 1704A 1704A 18D5 1065.3 1083.4 CD361 2.0901 2.1262 50 i
80
/
0.2561 021603 1207.6 1207.6 28.06 1059.7 1087.7 OD555 2.0391 2.0946 60 70 03629 OD1605 868.3 868.4 38.05 1054.0 1092.1 0D745 1.9900 2.0645 70 80 05068 021607 633 3 633.3 48.04 1048A 1096.4 OD932 1.9426 2.0359 to 90 0.6981 0D1610 468.1 468.1 58.02 1042.7 1100.8 0.1115 12970 2.0086 to 100 0.9492 CD1613 350.4 350.4 68.00 1037.1 1105.1 0.1295 1A530 1.9825 100 i
110 1.2750 CD1617 265A 265.4 77.98 1031A 1109.3 0.1472 1A105 1.9577 110
=
120 1.6927 OD1620 203.25 203.26 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 130 2.2230 0D1625 15732 157.33 97.96 1019A 1117A O.1817 1.7295 1.9112 130 140 2A892 021629 122.98 123.00 107.95 1014.0 1122.0 0.1985 1.6910 1A895 140 150 3.718 OD1634 97.05 97D7 117.95 1008.2 1126.1 0.2150 1.6536 1A686 150 100 4.741 SD1640 77.27 77.29 127.96 1002.2 1130.2 0.2313 1.6174 1A487 160 170 5.993 0D1645 62.04 62D6 137.97 996.2 1134.2 0.2473 1.5822 1A295 170 140 7.511 E01651 50.21 60.22 148.00 990 2 1138.2 02631 15480 1A111 180 190 9.340 0D1657 40.94 40.96 158D4 984.1 1142.1 0.2787 15148 1.7934 190 300 11526 CD1664 33.62 33.64 168D9 977.9 1146.0 0.2940 1A824 1.7764 200 210 14.123 CD1671 27.80 27.82 178.15 971.6 1149.7 0.3091 1A509 1.7600 210 212 14.696 CD1672 26.78 26.80 100.17 970.3 1150.5 0.3121 1A447 1.7568 212 I
220 17.186 OD1678 23.13 23.15 188.23 965.2 1153.4 0.3241 1A201 1.7442 220 f
230 20.779 CD1685 19.364 19.381 198.33 958.7 1157.1 0.3388 13902 1.7290 130 240 24.968 OD1693 16.304 16.321 20BA5 952.1 1160.6 03533 1.3609 1.7142 240 l
f 350 29.825 CD1701 13A02 13A19 218.59 945.4 1164D 0.3677 1.3323 1.7000 250 360 35.427 OD1709 11.745 11.762 228.76 938.5 1167.4 03819 1.3043 1.6862 260 f
270 41A56 OD1718 10.042 10.060 238.95 931.7 1170.6 0.3960 1.2769 1.6729 270 i
300 49.200 CJ01726 BA27 S.644 249.17 924.6 1173A 0A098 12501 1.6599 200 300 57550 CD1736 7443 7A60 259A
$17.4 1176.8 OA236 1.2238 1.6473 290 300 67D05 021745 6A48 6A66 269.7 910D 1179.7 CA372 1.1979 1.6351 300 210 77.67 OD1755 5.609 5A26 280.0 902.5 1182.5 OA506 1.1726 1A232 310 Sto 3954 OD1766 4A96 4.914 290.4 894.6 1185.2 CA640 1.1477 1.6116 320 840 117.99 OD1787 3.770 3.788 311J 878A 1190.1 OA902 1D990 15392 340 360 153.01 CD1811 2 S 39 2.957 332.3 362.1 1194.4 05161 ID517 15678 350 800 195.73 041836 2317 2.335 353.6 844.5 1198.0 05416 1D057 15473 300 400 347.26 E01864 1A444 1A630 375.1 825.9 12014 05667 0.9607 15274 400 430 30818 RD1994 1.4808 1A907 396S 806.2 1203.1 05915 03165 1.5080 420 440 38154 ED1926 1.1976 1.2169 419.0 785.4 1204.4 0.6161 CA729 1A890 440 480 466.9 0D196 0.9746 0.9942 441.5 763.2 1204.8 0.6405 03299 14704 460 880 966.2 CD200 01972 0.8172 464.5 739.6 1204.1 0.6648 'O.7871 1A518 400 900 gBOS OD204 0.6545 0.6749 487.9 714.3 1202.2 CA890 03443 1A333 500 S30 812.5 02209 05386 0.5596 512.0 887.0 1199.0 0.7113 0J013 1A146 S20 540 962.8 02215 0A437 OA651 536A 657.5 1194.3 0.7378 BA577 1.3954 540 900 1133.4 CD221 03651 0.3871 562.4 625.3 1187.7 03625 BA132 1.3757 560 000 1326.2 CD228 0.2994 0.3222 589.1 509.9 11792 0.7876 03673 1.3550 500 800 1543.2 SD236 0.2438 02675 617.1 550.G 1167.7 CA134 05195 1.1330 000 830 17962 62247 0.1962 0.2208 646.9 506.3 1153.2 0A403 CA689 1.3092 820 440 2059.9 CD260 0.1543 0.1002 679.1 454.6 1133J 03686 CA134 1.2821 440 f
000 23653 CD277 0.1166 0.1443 714 S 392.1 1107D 03995 03502 1.2498 640 800 2708.6 02304 CD008 0.1112 758.5 310.1 1068.5 03365 02720 1.2006 000 l
J 700 30943 02366 CD386 0D752 822.4 172.7 995.2 0.9901 0.1490 1.1390 700 MB 33082 Ra508 0
CD508 906D 0
306D 1D612 0
1D612 7063
~
n
~
34 y
Table 2 Properties of estursted steam and estwated w8ter (presswe)
Enthalpy,et 4 Emerapy,th@ aF tasegy,thafth Weisne.a*/lb eser ~
Esop Steam Water temp Steam Water Esop Steam mater Steem yW s
a, a.
s s
v aAmos atmS eAle02 Sa02A 3302A SAO 10 M.5 10753 8
2.1872 8.1872 0
10213 tages Ele M A23 Select 2045.5 39455 SAB 1071A 1076A OA061 2.1706 3.1786 SAB 10222 Ste 3.15 46A63 941802 2004.7 3004.7 13.50 1067A IW1A 0A271 2.1140 2.1411 13A0 1925.7
&1l ESS 53.140 041403 15363 1826J 2122 1063.5 154.7 34422 2 3738 2.1180 2122 1018.3 mm 4 30 64AS4 841404 1939.7 1939.7 92 &4 1967.1 199.7 0A541 Sales IMOD 3234 1032.0 4 30 4 40 72300 041406 792A 792.1 4032 1052A 1033.3 0A799 1AM2 2A662 4032 1934.7 440 El 79.006 SA1607 d41.5 6413 47A2 1048.6 1996.3 OAR 25 13446 2AB70 47A2 1086.9 SS Es 05218 041500 S40A Mo.1 5325 10453 1988.7 0.1028 13146 2A215 5324 1038.7 as 3.7 90.09 SA1610 48633 466.M 58.10 1042.7 11003 OJ 12956 2A083 98.10 1040.3 E7 SA MJB OA1611 411A7 411A9 62.39 10403 1102.6 R1117 137M 13970 G229 1041.7 48 E9 9824 OA1612 308A1 38SA3 66J4 1030.1 1104J 0.H64 13006 13870 4624 10423 SA 1A 101.74 0A1614 33339 333.60 40.75 1036.1 1105A 4.1326 13455 13751 98.73 1044.1 1A RA 12627 0.01623 173.74 173.76 M.03 1022.1 1116.2 0.1750 1.7450 1.9200 94.03 1051A 2A 3A 141A7 OA1630 118.71 118.73 109.42 1013.2 1122.6 02009 1AB54 12964 100.41 1056.
SA 4A 15236 0A1636 9043 90.64 12032 2006.4 1127.3 0.2199 1A428 13626 120.90 1060 2 4A SA 16224 OA1641 73.515 7353 130.20 1000.9 1131.1 02349 1A0P4 1A443 130.18 1063.1 SA GA 170 25 0A1645 61.967 6138 13043 996.2 11342 0 2474 1.5820 12294 1M21 1065A GA 7A 1MA4 041649 58434 5845 144A3 992.1 113bS 0.2581 1.5587 1A168 144A1 1067A FA S.O 182A6 0A1453 47.328 4735 15037 9885 1139.3 OJ6M 1A354 1A060 15034 10092 SA SA 19827 OA1656 42J05 42A0 156.30 985.1 1141A 0 2760 1.5204 1.7964 1MB 1070s SA le 19321 OA109 38404 3542 16126 982.1 1143.3 CJS36 1.5043 1.7879 16123 10723 IS 34m6 212.00 SA1672 M.782 2620 180.17 970.3 11505 03121 1A447 1.75E8 100.12 1077A 14,896 15 21325 0.01673 N 274 2629 181.21 969.7 11503 0J137 1A415 1.7552 181.16 10773 15 30 22736 OA1643 20A70 20287 196.27 960.1 1156.3 0 3358 1J962 1.7320 196.21 1082.0 30 30 250.M 0A1701 13.7266 13.744 218.9 M52 1164.1 0.3642 1J313 1A995 218A 10B73 30 40 26725 0A1715 104794 10 497 236.1 913.6 1169A 0.3921 1844 1A765 236.0 1992.1 40 00 asim 0A1727 84967 8314 250.2 923 3 1174.1 0.4112 12474 JA506 250.1 1095 3 80 80 292.71 021738 7.1562 7.174 262.2 915.4 11774 OA273 12167 1A440 362A 1008.0 W
70 302.5 OA1748 6.1875 6205 272.7 9073 1100.6 0.4411 1.1905 1A316 272.5 1100.2 30 00 312A8 SA1757 SA636 5.471 382.1 9005 1183.1 0.4534 1.1675 1A20B BIS 1102.1 80 to 330 2 OS!M6 4A777 4295 290.7 3944 11853 OA643 1.1470 1A113 290.4 1103.7 to Sep 327 2 0A1774 4A133 4A31 298 5 358.6 1187 2 0A743 1.1384 1A027 238.2 11062 380 130 341.27 OA1799 3.7097 3.728 312.6 8773 1190.4 OA919 1A060 13879 312.2 1107.6 130 140 353At 801003 3J010 3219 325.0 SEBA 11934 0 5071 1AGS1 1.5752 334 5 1109.6 340 Sep 368.5 401815 2A155 2334 336.1 859A 1195.1 05206 1A435 1A641 335.5 1111 2 340 1
Sep 373 5 DA1827 18129 2531 M62 050.7 11963 0.5328 1A215 1.5543 M5A 1112 5 ISO 300 381 2 0A1839 IJ889 227 355.5 842A 11983 0.5438 13016 1A464 364A 1113.7 300 350 40037 ODIMS 13245 18432 SM.1 325 2 1201.1 0.5679 03585 1A264 3M3 1115 2 880 300 417.5 SA1839 1A238 13427 394.0 808 3 1202 S 0.5882 0 1223 1.5106 382 S 1117.2 300 350 431J3 0A1913 1J064 12255 4093 794.2 1204A SA050 0AB09 1ASIB 408 6 1118.1 350 400 ease SA193 1.14162 1.1610 424.2 700.4 1204A AA217 03630 1AS47 422.7 1118.7 400 400 456 2 SA195 1A1224 1AB18 437J M7.5 1204A 0A300 03378 1A738 435.7 11183 480 900 46731 0A198 S.90787 03276 4495 755.1 1904.7 OA490 02148 1A639 447.7 1118 3 000 900 47634 SA199 A32183 02418 460 5 7433 1204.3 0A611 0.7936 1AS47 484 3 1118 4 550 000 abE30 0 0201 E74962 E7005 471.7 732A 1903.7 0 4723 0.7738 1Ae61 480 5 1118.2 000 700 901 5 04205 OSB505 0.0556 491 4 710.2 1201A 0.0038 0.7377 1A304 MSS 1116 3 700 000 51421 82209 034009 0 9800 509 2 4094 1199.4 0.7111 p.7061 1A163 806.7 1115.2 800 J
900 531 5 4 4212 E47988 4A009 526.7 GAS.7 11964 0.7279 43753 1A0Bt 523.2 11134 900 l
3000 team 02216 842436 OA400 542.6 480.4 1192.0 0.7434 SA4M 1N10 5384 11104 880 1100 986 3 04t20 SA7863 OA006 567 3 6315 1189.1 0.7578 84216'13794 561.1 1107.5 1880 1300 SEF.hD Sat 23 434013 83625 5713 613A 11844 0.7734 OA000 IJSR 546 3 11043 13
'4300 577At SA227
&30722 0.3299 SSE.6 9044 11802 0.7843 85733 1J677 980.1 11003 1 1400 WFW Sat 31 827871 83018 508 5 S M.5 11753 0.7986 0.5007 13474 9823 1057.1 1980 WE3B SA235 425372 82772 611.7 908.4 1170.1 SA005 0.53R5 1273 806.2 1093 1 1980 3000 EEE RO257 R14N6 8.153 672.1 4662. 11383 CA625 SA256 1 JOB 1 862 4 19884 N00 GE11 SAat6 E10309 0.1307 731.7 M1A 10k33 03139 0.3306 1245 718 5 10323 300 3800 M SA343 A85073 4B50 8013 218.4 18R03 6373B E1001 1.1419 782 3 973.1 8000 290L2 1547 SA808 8
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RA141 137M 1ABE# 1890 2A400 SABR2 2.1300 2.17M 2 SSA4 38430 lle.M 114.73 S
5 81 86.91 e2A7 5MA 19864 ISta ISB3 'lF47A agetA 042J4) s 03395 SAs 44AB Slat 57A4 43AB $8A0 M.9B 8034 4 3.1757 22101 3243012M4 8J046 SJB 0.1295 f 1J55 1A003 1A173 1A002 2A186 RA003 2 SA161 e
S.02 41206 Ret SARS 73A33 77A07 as &
100BA 29399 33963 37385 41AB6 46A78 4926 19863 MSBA 30802 1747A J000 09321) s 1584.5 IIM.5 1239A 1387J 13352 13832 1433.2 1483A i
SA161 SA1864 l
e 0A47 43435 46A20 4BA05 32 JOB 95J SS 6
esas 30BA9 gism)s 0.1395 82980 1A134 1A720 13242 1747A 18033 15M.3 19863 36803 3033.1 22366 25A28 3BA57.31A66 MA45 37A58 41296A *133 04161 SA186 1239.2 5
1ASM 2A244 e
!!91A 13005 IA397 13921 1A397 23.1M M.SD 36.183 27.676 29.las 30 4 S.05 188.11 1803A 0.1295 02940 1
17.195 18 499 30.199 21 497 19052 16384 1982.7 IM Q27.96) s 14.165 154B5 14825 15337 2A669 2ABB9 2.1224 0.0161 0A146 11036 12A24 1285.0 '1333.6 1382 5 1432.11A065 13476 13B60 2A224 1236A e
S 6 GS.10 IS IS 1186.6 1.M05 14143 1 A624 16A52 MASO 17A48 ISA45 19A41 0.1295 0J940 1A992 1802A 9A00 10A25 11A3B 12A46 ISA50 14.452 19815 1431J 14813 15332 19453 M 9 67.25) s 8354 e 0A161 SA186 7.257 1233.5 1283.2 1332 3 1J134 1J951 1A188 1A612 1A024 80 6 S.15 lee 20 1181 4 11.981 12381 13ABI 15229 14.5U/
992J1) e <0.1295 82339 l14492 9 319 10275 10229 15324 HMA 1638A 3524 1M6A 200j 6214 7A18 7J94 S.940 1AB00 2A131 2A446 2A?lo 2.1041 1730 5 13813 1530A 1300 5 1430.5 1481.1 e 0A161 0A146 OS175 t1 A790 1.7M9 1J842 1A209 13702 1.90D9 1A454 SAAD 10A60 11A80 11A59 S0 & GS21 15 24 36034 0 12 44) s 0.1295 S m 39 OA373 4A35 S. Set 6.216 6333 7A43 8.000 S.865 9288 16B7A 189 I400 4 1532A 1944.4 12539,1A205 1A552 1AuB3 2A199 200 4161 Sale 6 OD1 M 1227A 12793 1829.6 13795 1429J e 0 1A451 4826 35 29 369.77 027A2) s 0.1295 0 3 39 0 4371 34516 13006 IJ546 1A0366.1928 63006 7.2060 7.7006 82119 8 800 4 1802A 15ABA 3437.1 18813 17462 4A786 44341 5.1637 64833 142SA 1479A 1531A 13349 1AEAD 13906 A161 0A166 0A175 G831 3533 38921 12M.1 1277A 1328.1 13784IA246 13635 1A001 f
e O 94127)s 0.1295 8 5 39 OA371 1 A296 1A872 1.7376 1J8292995 5J364 6.1799 4AGB6 7 met 7 130 t 18967 2000.9 1746A 1801.7 ]
SA661 33526 4A119 43585 E34332 M79.1 1530A 1983A1AR28 1 ALM 1350) l 8.0161 6 0186 0 4175 12203 12753 13263 ISUA1.M62 12071 13461 e
5 37 38 38 300A5 14005 1A806 1J196 4132 53945 5.7N1 E1822
$40 6 0.1395 8839 OA370 320$0 SA413 3 B480 42420 4A295 5 053A4) s 1
1J499 1J919 1A310 1A678 1A027 IJ 3
1876 4 34272 1478A OA161 88146 0.0175 1217A 12733 1325 A e
0842 BAB42 assap 4
1.3906 1A622 1J039 4AS05 41907 5.1300 SA057 E801 380 4 03394 8 3 38 0A370 0635$)s 2A4M 3A433 SA093 33621 4.1084 1ES2A SEREA 2
14MJ 1477J 1529.71 AIM 13545 13834 0A16148166 84174 1213A 12712 13244 19753 85.47 BGB47 30022 1A3M 14000 IJ362 IJ784 e
9 DB 430U 4A138 4312 52191 5A30 180 6 E1394 asana OA370 1.5743 A 1M64 1800.9 EMSA 13224 13M.3 14255 14NA 15393 23908 2JM7 SA581 33783 34915 4AO 0732) e 25 0A16182186 0A174 GBA2 3551 388A6 1210.1 e
1.7239 46 0.1394 t2 pas R4300,1.8003 1/M2 1A776 3 Ass 2 Sm37 1A278 4.1700 4A1 380 6 tate's RA662 ras 72 2.M10 2.190B8475 3 1527 4 19 pSIAO) s 76 1AD76 1.7405 IJWD1 1A173 1AEM OA161 tales 68174 64186'1863.5 13192 1371 A 14234 546 kWA3 27045 375.30 1.9051 1A602 e
SAM 6 SAM 4 SJ W 34721 3B0 6 al394 SAB37 R4308 0.96671J986 2A044 22363 2A407 2A500 2A5 56 1 9 83 38EBA 1 M S 4 179 (400 97) s 572 CAlt6 08141 ¦ OA174 eBR 8574 270 14 375.15 1357J 1315.2 18ESA 798 1J192 1.7991 e
0 3.1471 SJp06 1.5703 142M 1A 1 ADD 13028 1E70 RAB32 RJG52 RA445 0.1394 4237 BA307 03065 330 m 9E9 13862 1419.2 8471A 1534.7 157 (41735) s 000
, AAls! 8815 4 AIM 92186 12514 1311A 1.M11 Bat 3R AS 27024 37521 1. Seal 1 A O U 1 A6 4 I JEOD 1A799 23390 3 s attaB t m 36 04867 asses age 1A151 15233 ISMA SEB12 3806.2 1 AD55 1 2 e431J3) 1A499 1APA1 1AM3 1853A M17A 1470.1 1Ae06 1AB00 1J355 IJE32 1.755 13825 1 y
e tale S9146 SAIM 88162 1M6.1 1307A 5 5 35 97 27033 37527 1A382 13B01 1 APg2 12256 1AIO7 2AM6 1.19U 22 s klan 42935 84306 SM63 3
400 BAD t 1.19M 1J087 1 A307 1.5708 PS84A 4E29.1 3034A 1740 1
GH4.80) k 1367J M12J 1486A 1620J 1A702 1 ADOS 1A123 1A678 1A000 IJ371 1J730 1mEB e tale Sales 8 AIM 68106 1291.2 1898.1 SS 385.19 270.51 575JBSADM SA000 l1AA21 IJ885 age 6
4467A1) e al33 SmB4 a
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Propertlet of supe 2hested steem and on::M water pomperature and pressure)
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9ssvershme.F ans 300 WO 300 400 500 800 700 20 900 8000 1100 SWO 120 1400 1900 In.
60161 04146 04174 0A188 OJM4 0.M56 BA7M 1.3882 IJ008 1A003 1A100 1A211 1.7252 latte 1A000 30 a m.38 38542 27030 375A9 12193 1290.3 1351 3 14083 1483A 1517A 1571A 3827A.10824 17383 17954 e
getasp e 0.1292 0283 0A862 SAG 67 1A000 15329 1AS44 1A351 14740 1J196 1.7517 EJOIS 14184 13404 13732 40141 Dales SA174 0A186 SA204 0.7928 4A072 1A102 1.1070 1J023 12948 1200 ; 1A757 1.9647 1830 339 6 NA4 See.86 270AD 37541 48733 18814 1MSA 1403.7 1460A 1514A 1980A 38344,1930J 17272 17943 e
OISAS) s 0.1291 02932 E4300 0A865 SAASD 1.9000 13673 1A164 1 A800 1 ABF0 1.7335 1J079 13006 18318 13617 0A161 04186 OA174 0A146 OA304 04774 0 7838 03799 03531 1A470 1.1389 1J005 1 m 13869 1A446 500 4 70.11 &#AB 27127 37573 487AB 1271.3 1339.2 1399.1 1466A 15114 19863 1422J 1678.9 17354 17323 e
C1821)s 01290 0m30 043s3 0.5e62 SAeS5 1 Ame9 144e4 1Asso 14413 1Ae07 1J175 1.7522 1Je51 ISIM 1Aes4 0.0161 OAle6 04174 0A186 04204 09869 CASSS 67713 04504 0.9M2 0S508 1A720 1.1430 12131 IJB25 4
900 6 70.37 170.10 271.26 37534 eB7A3 IMO.6 1832J 1394A 1452.2 1908 3 1964.4 1820.6 16U.1 17M.1 1791 4 e
93135)s 0.1290 02t29 OA357 0249 04081 1A659 1A311 1AS22 1A263 1A662 1 JOB 3 1J382 1J713 13028 12329 OA161 0A146 0A174 0.0106 0.0204 03137 04000 04875 0.M03 02295 03066 02622 1AEG6 18B01 1.1529 3000 t 70 63 17033 271A4 37536 487.79 1249.3 1325 9 13ep.6 1448.5 1904A 1961.9 1618.4 16753 17323 1790J e
S44M)s 0.1299 0m28 0.4355 0.M47 04476 14457 13149 1M77 14126 1A630 1A005 1J296 1.7989 1J905 12207 e
0A161 02146 CA174 04185 04203 04531 0.5440 04188 04865 01505 03121 03723 02313 0 9094 12408 1100 6 70 90 170.96 271A3 SMAB 407.75 1237J 1318 3 1384 3 1444.7 1902A 1H9.4 M163 1673A 1731A 17992 966JS) s 0.1209 0m27 OA353 0.5644 04472 1 A259 1A996 1A542 14000 1A410 14787 1.7141 1J475 IJ793 13097 00161 0A166 0.0174 04185 04203 CA016 OA905 OMIS 0A250 OAS45 0.7418 0.7974 03519 03055 09544 1300 6 71.16 1703B 27132 SMJO 487.72 1224 2 1311 3 13793 1440D 1449 4 1966.9 M14.2 1671 A 1729A 1787A e
5 67.19) s 0.1208 0J926 0.4351 0.5M2 0.0008 1A061 1A051 1.5415 1.9083 1A298 1 A679 1 JOBS 1J371 1.7401 1J906 0A161 OA186 00174 0A185 0.0203 0J176 CA059 0.4712 0.5282 03000 0A311 04798 0.7272 01737 03195 3400 6 71.e4 17124 272.19 3MA4 48745 11M.1 1296.1 1369.3 1433.2 1493.2 1951A 20003 1488A 1726J 17852 e
OS7A7) s 0.1287 02B23 OA348 OM36 04859 1.3652 1A575 1A182 14670 13006 1A484 1AS45 1.7185 IJt,0B 1J815 I
e 0.0161 0A166 02173 00185 04202 0.02M 0.M15 04032 04555 OA04i 0.5482 CA015 0A336 04748 0J153 8800 6 72.21 171A9 27237 3M 69 48740 616 77 1279 4 1358 5 1425.2 1446 9 IM66 1805.6 18643 17232 17823 0I0437) s 0.1286 0m21 0 4M4 0.9631 0.6851 03129 1 A312 1 A968 1A478 1.5916 1 A312 1A678 1J022 IJM4 1.7657 e
0A140 0A186 0.0173 0A185 0.0202 0.0235 0 3 06 0.3500 03908 0A426 OAS36 01229 03809 0.9900 SA343 BEED 6 72.75 172.15 27295 3M33 487.96 615.98 1 M 1.1 I M 7.2 1417.1 3400 6 1M1.1 1801.2 1880 7 1720.1 IN9.7 i
W1AR) s 0.1384 &3918 04341 03626 SAM 3 SA109 1A054 1A788 1.5302 15753 1 Alt 6 1 ASIS 1ABM 12204 1.7516
'e 02140 SAIG6 02173 OA1H E0201 OM33 02488 OJ072 035M DJM2 04320 SAe00 03027 BA365 BA805 MB0 4 73.26 172A0 27332 SU.19 487.53 614AS IM09 1353A 1408.7 1447.1 15362 1986 3 1867A 1717A 17n.1 93520) s 0.1283 02916 0.4337 0.9621 0A884 OA091 IJ794 1A578 1.5138 1.9403 1A014 14391 1AMS 1.7075 1J339 e RA140 CAle6 02173 02184 0 4200 0.0230 0.1681 0.2293 02712 0.3068 03300 0.3032 03000 64269 OA529 3 00 6 7457 173J4 274.27 an32 457.60 612.05 1176 7 1803A 1306.7 1457.5 1522.9 19863 3M73 1700.2 177& 4 9 0& 11) s 0.1300 02910 SA329 0A000 0.4815 CA048 IJ076 1 A129 1A766 1A360 13703 1ADM 1A466 14796 1J116 0A140 60146 00172 0A183 04200 OM3B 0.0082 0.1799 02161 024M 02770 SJOBS 63382 04522 02753 3000 4 75AB 1MAB 275.22 37847 487A2 610.0B 1000.5 1M7A 1863.2 1440.2 MODA 1574A MIRA 1701A 1M1A e
M33) s 0.12U O2904 OA320 0A097 A47M 08009 1.1M6 1.3082 1A429 1ADM 1.5434 13841 1A214 1A861 Imes 02140 CA186 02172 0A183 0A199 OA227 04335 0.198B 0.1987 02301 OMM 0327 03086 03291 03510 EED 6 MA 1753 275A 370.7 457A 400 A 800A 1260.9 1853 4 1483.1 1903A 1570.3 3654A 198.3 1M12 e
D065)e 0.12M 02502 SAll? Ettet 047B8 OJ994 03705 1.3615 1A300 1Att6 13335 13740 1A1M 144U 1m06 OA140 SalM 04172 04183 CA199 0.0225 0A007 03364 0.1764 SJ006 ODN 0563 02794 02995 0319B 3000 6 772 17s 4 276.2 379.1 67A 40B 4 779.4 12MA 18382 H22.2 1495.5 1M33 M292 stb 3A 1757.2 s 03274 SEED 04312 0A805 047U 0.7973 03508 13242 1A112 1A709 1 AIM 13618 1A002 143S8 14001 OA1H DAIM OA172 04182 04198 0A223 OARS 7 0.1062 &l463 61752 0.19M A3210 03411 02601 02783 GBD 6 703 1772 2D.1 379 4 57.7 0064 M 3.0 1174.3 1311 4 1403A 14B13 1952 2 3819 4 1885.7 17904 e
s 03271 ESEIS SA304 DA673 BAMO 03940 SAM 3 12754 1AB07 1A461 1A975 13417 1AS12 1 AID ISIS 0A198 041M 92171 04181 SS196 0A219 Baset SABel &1038 0.1812 0.1539 E1718 0.1880 02060 0503
- EED 6 31.1 1793 279.1 21.2 4E81 804A 746.0 8042 9 12623 13644 5482.1 355.1 30E09 36702 1737A e OJM6 031 04387 Rege0 04736 0J300 SD153 1.1983 1.3307 1A001 1AGS2 13061 134B1 13063 1A216 0A190 04183 02170 60100 04196 OA216 0A296 BA007 0A757 0.1000 0.1221 03381 &1944 01884 61817 e
EED 6 08.7 3813 314 3827 438.6 802 3 736.1 045.1 11053 1323A 5422J 1906 9 19824 MM.2 17M.2 e eatts 6570 04271 6883B OAsea 0J836 Os0M 1A176 13615 1.3674 1A229 1AMS 131M 1.9443 19962 02188 48188 E0170 0A100 E0103 BA213 SANS BASM DA673 Sasl6 &l004 0.1180 &tatB R14M &lM2
'8 ggg, #
8EA 3844 MBA M42 MBS 901J 739J gola 11MS 1381.7 13R22 14B24 1963.1 1838 6 1711.1 8 E1852 &MRS SA296 03007 &aA63 SJ777 64336 tale IJet6 1J171 1Je04 1A486 1ARIO 13355 1A736 l
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