ML20140E844
| ML20140E844 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/30/1986 |
| From: | Mark King, Lang T, Lanksbury R, Mcmillen J, Plettner E, Mary Spencer EG&G, INC., NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20140E824 | List: |
| References | |
| 50-440-1-85-2, 50-440-L-85-2, 50-440-OL-85-02, 50-440-OL-85-2, NUDOCS 8602040100 | |
| Download: ML20140E844 (73) | |
Text
n U.S. NUCLEAR REGULATCRY CCMMISSION REGICN III Report No. 50-440/0L-85-02 Docket No. 50-440 Licensee: Cleveland Electric Illuminating Company Facility Narre: Ferry Nuclear Power Station Examination Acministered At:
Perry, Ohio Examination Conducted:
Eccember 10, 11, 12, 198',
T. /NMu C
D'a/f >,/>'<:
Plettner, Region III Chief Examiners:
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b'J.Lang,ReNonIII
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trate /
v R.6ksbury,) Region III (Traince) t[Ao/,gp_
IIate dM d 5p n EG&G DYte
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batT' Approved By:/ d i Fc h e hief
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d Operating Licensing Sectinn Da te /
Examjna_t,1,c_n Summary n
10, 1985 ( Rep'oii Diic'eiW6r' 'IO ' TI~,' Yiid') 12, ort No. 50-440/0L-85-02 Examinaticn administered on December Simulator and ara 1 eYaii'iiIa't'icns were a6fiifs'.i/r.
~
ed 1985. There were 15 candidates--five reactor operators and ten senior reactor operators.
Resul_ts : All five reactor crerators and ten senior reactor cperator candidates passed.
0600040100 060130 PDR ADOCK 00000440 G
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REPORT DETAILS 1.
Examiners E. Plettner, Region III Chief Examiner.
Author and grader of SR0 written exam.
M. Spencer, EG&G Co-Author and grader of R0 written exam M. King, EG&G Co-Author of R0 Written Exam T. Lang Region III - Oral / simulator examiner R. Lanksbury Region III - Oral / simulator examiner trainee 2.
Examination Review Meeting Examination review meeting was held on December 12, 1985.
The R0 and SR0 written exam was reviewed for three days by Perry training staf f personnel.
All comments were typed and the Examiner responses are contained in for the RO exam and Attachment 2 for the SR0 exam.
3.
Exit Meeting The exit meeting was held on December 12, 1985 attended by E. Plettner, R. Lanksbury, Perry training staff, and plant management.
The facility was given the names of those candidates who clearly passed the oral /
operating portions of the examination.
2
r PERRY REVIEW COMMENTS FOR THE REACTOR OPERATOR EXAMINATION Answer 1.03:
Student should be given credit for stating that the " Undesirable Condition" is excessive motor currents.
There are other possible negative effects besides damaging the motor windings, (ie. ex-cessive temp., pump tripping).
Any of these should receive full credit, since they are all a result of excessive currents.
Examiner's Resolution:
The answer key, as written, stated the reasons for this being an undesirable condition.
The review comments add more reasons for this being an undesirable condition.
Answer 1.04:
a.
Specific numbers not asked for in the question, so possible responses that address icw reactor pressures or low core flows.
Examiner's Resolution:
The implied requirement for values will be removed from the answer key.
Question 1.04:
b.
Question should ask for phenomenon that would occur below MCPR.
Answer 1.06:
b.
Page 6-22 dicusses the effects of void coefficient from B0L to EOL.
An acceptable answer to this part could also be "Less negative, then more negative late in core life."
This also appears on page 6-36.
I d.
See Part "B" Above.
)
Examiner's Resolution:
J The facility's comment was verified to be correct, therefore, part b was deleted from exam and the point value for section j,
I was reduced by 0.5 points possible.
Part d remained as is, i
because the overall ef fect over core life is less negative.
(Ref. page 6-22)
Answer 2.01:
I b.
Answer key should state only one effect required.
~.
Examiner's Resolution:
Answer key annotated to require only one effect.
Answer 2.03:
1.
Answer should be false.
SDM is incorrect.
Supporting Documents, SDM E-228 page 19 and SOI E-22B page 3 section 4.3 note.
Examiner's Resolution:
Page 19 in the reference makes the answer false.
Changed the answer key to FALSE.
Anser 2.04:
a.
Flow control valve position should not be required for full credit.
b.
Recent plant changes have removed the flow control valve position portion of the downshift.
Some students may be aware of this so credit should be allowed for either answer.
Examiner's Resolution:
Review of the drawing supplied after facility exam review, confirms the facility comment.
Therefore, the " valve position" of the feed-water flow interlock was removed.
The point value of part "a" was reduced by 0.5 points.
Answer 2.06:
a.
There are two ads valves contolled f rom the remoto shutdown panel.
The references noted are incorrect in that they imply that there is only one (C61 SDM).
Correct reference is IOI-11 page 30.
Examiner's Resolution:
Reference was verified and answer key changed to 2 ADS valves operated from R.S.P.
Answer 2.07:
Other possible responses might include MSIVs, DG vent system, or SRVs.
Examiner's Resolution:
Facility comment incorporated into answer key, as possible answers.
2
)
Answer 2.12:
b.
Excessive torque is not a normal condition and should not be required for full credit.
(Torque switch opens when valve reaches full open position)
Examiner's Resolution:
The torque portion of the answer is removed and not required for full credit.
The point valve of section 2 is further reduced by 0.5 points.
Answer 3.01:
a.
A change given to the license class changed the flow setpoint from 600 to 725 gpm and the pressure setpoint from 120 to 145 psig for minimum flow valve.
(The NRC was given this change to the SDM also) b.
Question vague as to how many parts are required for full credit.
Examiner's Resolutions a.
Setpoints changed to 725 gpm and 145 psig.
New reference added to answer.
b.
The answer key was changed to accept either answer for full credit.
Answer 3.02:
Reasons:
1.
Feeds high to overcome void collapse.
2.
Feeds low to prevent icvel eight following reformation of voids.
Levels:
Approx. 220" and 185" Times:
Foods high for 10 seconds Initating Signal:
Level three Examiner's Resolution:
Comments noted - Answer key changed to include second reason and remove recirculation system alarm unit portion of ansaer as re-quired.
Other comments are included in the answer on the key.
Answer 3.03:
This is not really an electrical interlock. The physical design of the control switch only allows one bus to be powered from an alternate power source.
The answer key implies more detail is required for full credit.
3
Examiner's Resolution:
Answer key modified to remove the detail of the relays and contacts.
Description of single switch is the only requirement for full credit.
Point value of this question was decreased by 0.5.
Answer 3.05:
b.
Part 2 should say " Starts any feedwater Booster pump in standby".
Examiner's Resolution:
Answer key changed to add the word " Booster",
Answer 3.06:
Answer key only considers signals sent to the N27/C34 system.
Other possible answers might include signal sent to the E31 (Leak Detection) system.
Examiner's Resolutions Answer key changed to include Leak Detection System as another possible answer and reference added.
Question and Answer 3.08:
b.
Question is very vague as to what is asked for.
Student could say 10 minute TD is longer than 90 second TD or he could say that division 2 has a longer duration due to 10 minute TD plus 90 second TD while division 1 only has 10 minute TD.
Examiner's Resolution:
Due to examiner's misunderstanding of system operation, this portion of question was deleted and 0.5 points removed frem question.
Answer 3.13:
Answer key lists three possible combinations and only two are re-quired for full credit.
Also valve numbers should not be required for full credit.
Examiner's Resolution:
Either valve number or valve description is required for full credit.
Added valve (B) to F006 in the second part.
Adjusted point valves to accept two combinations.
Answer 4.06:
d.
Should allow for either A/#MPP or A/#RFP.
Examiner's Resolution:
Answer key modified to allow either motor or one turbine feed pump of full credit.
Examiner's Comment - Answer 2.05:
Addition review of SDM C-22 discovered the ARI will operate valves F-163 which allows F-010 and F-011 to close.
F-010 and P-011 isolate the scram discharge volume.
The answer key was modified to include SDV isolation as a possible answer.
Examiner's Comment - 2.09:
Further study of SCM-R43 and E-12 revealed addition answer for full credit.
Answer key modified to reflect two possible answer combinations.
5
ES-108-1 Attachment i EXAMINATION GRADING QUALITY ASSURANCE CHECK 0FF SHEET K36'/V CEd Grader (s) Name
/
/
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E Facility f/l/V Date of Exam X
Senior Examination: Operator Post-Examination Procedures Examiner Review Item Descriotion Initial /date Initial /date
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2.
Partial credit consistent for eacn candidate
//1 /-h-Ne eP 3.
Se: tion and cumulative scores enecked for addi-N
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of ae ry ta 4
Grading for all borderline
/ /
cases reviewed (70% 2 2%/
1 section or 80% 2 2% overall) "[f b /~h#
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//i/IIe 5.
Detailed review. 1 question per category, 50% of cate-g
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4 gor 4es, 50% of appifcants 6.
"igN a i.Miag/ lowest passing examinations
':it';:# ':em!"'
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All other failing exam-inations checked to be
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assured of justification
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for failure 8.
Individual cuestion performance enecked for
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training deficiencies, f
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wording problems, etc.
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Grader:
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Contract Rev!awer:IMIE 4 a----* o 4 Date:
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(If applicaDie) o4 Region Reviewer:
Date:
Review Completed:
Date:
Section Chief
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ES-107-1 WRITTEN EXAMINATION QUALITY ASSURANCE CHECX0FF SHEET AUTHOR'S INITIALS /0 ATE ITEM DESCRIPTION 1
Clarity of intent of questions 2
Applicability of questions to facility 3
Category weights correct.
All questions in proper category.
4 Each category total correct and corresponding to weights on the cover sheet 5
End of each category indicated by
/
statement "End of category 6
No question worth more than 20%
V of that category weight 7
Verify that 10 CFR 55.21 and
/
55.22 subjects are covered.
8 No double jeopardy questions 9
Answers clear and concise on L'
answer key 10 References to plant material
?/'
for each question, as applicable V
11 Proper level of knowledge (R0/SRO) 12 Partial credit points indicated,
> g, e
if apolicable
//' A */-3 0,
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/sd e4' /'/#el Date:
Author:
/
Contract Reviewer:
(If applicable) e
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Oste:
// - / > - e f' Region Reviewer:
f %'9 e s Date:
Date:
Review Completed:
(Section Cntef)
Exam
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S-Facility / Unit:
/
// */
Date:
/
Senior / /
' Operator,k'/
PERRY REVIEW COMMENTS FOR THE SENIOR OPERATOR EXAMINATION Question 5.03 Question does not indicate necessity for the detail given in the answer key.
Question did not ask for values for given variables.
Examiners Resolution Values given in answer key were approximations and not required for full credit.
Question 5.04 a.
Question does not ask for amount of subcooling, student should not loose credit if not present 20 BTU /lbm.
b.
Credit should be given for additional sources stated for NPSH.
(i.e., level, system pressure) c.
There are various ways of explaining the third statement in the answer key:
Recirculation, Ratio, etc.
Examiners Resolution a.
Full credit was given for the answer without the amount of subcooling 20 BTU /lbm.
b.
No credit was given for the additional sources stated for NPSH.
c.
Various ways of explaining the third statement were accepted as long as the terminology used conformed to industry standards.
Question 5.07 Student should be given credit for stating that the
" undesirable condition" is excessive motor currents.
There are other possible negative effects besides damaging motor windings, (i.e., excessive temperatures, pump tripping) any of these should receive full credit.
Since they are all a result of excessive currents.
Examiners Resolution Full credit was given for any answer that would or could result from excessive currents like Breaker tripping or excessive temperatures and were added to answer key.
2 Question 6.02 a.
The P71 Booster Pump normally maintains fire water pressure between 100-110 psig.
This should also be an acceptable answer.
(Any two for full credit) Reference SDM P71, Revision 2, Pages 9 and 12.
Examiners Resolution Answer included in answer key for full credit.
Question 6.07 The answer key for this question provides only signals provided by the Leak Detection System to the NSSSS System; however, the LD System provides numerous signals, which results in many possible answers.
The question is poorly worded in relation to the answer expected.
Students should be given credit for any combination of four signals generated by the Leak Detection System.
It would be understandable for the student to answer in generalities, (pressure, temperature, flow, delta temperature.) Since the question indicates a definitive number of indications.
Reference:
SDM E31 Examiners Resolution Question and answer were deleted from the exam.
Question 6.10 NC IRM IN0P should be sufficient for credit, without listing possible causes.
IRH Wrong Position /not fully inserted is another rod block.
Reference:
Revision 1, Page 28.
Examiners Resolution IRM INOP was accepted for full credit and IRM Wrong Position /not fully inserted was added to answer key.
3 i
l Question 7.01 a.
The question and answer key were based on a reference that has been deleted from our Administrative Procedures. (PAP-0208) current procedures which govern this issue do not use the term " Administrative... Limits."
It is possible for a student to state the " Federal.
l Limits" or " Administrative... Guides."
Therefore, either 1250 MREM /HR. or 1000 MREM /HR.
should be acceptable, unless otherwise directed by the procedure.
Reference:
PAP-0514.
Examiners Resolution Answer key changed to 1000 MREM /HR and reference changed to PAP 0514.
r Question 7.02 An immediate action that is not listed in the answer key is to evacuate the Containment (
Reference:
ONI B21-1).
Since the question stated "three required,"
the applicant should receive full credit for listing three of the four immediate actions.
Examiners Resolution Evacuate the Containment was not accepted as an answer because of the point value assigned to the question.
The three required responses are one point each for a total of three.
l c
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4 Question 8.06 TCN-005 changes the procedure to eliminate green jurisdictional tags and states the only jurisdictional tags to be used are blue and these are controlled by
,I project administrative procedures, not PAP-1401.
This is a construction oriented procedure, which is not addressed in the license training program.
Examiners Resolution Answer key changed to accept either answer for full credit.
Question 8.08 TCN-001 deleted this reference.
Answer should be per TCN-001 of PAP-0110.
For emergency only.
l Examiners Resolution Answer key changed to correct the reference and answer.
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NUCLEAR REGULATORY CCMM10SICH REACTOR OPERATOR LICENSE EXAMINATION TACILITY:
_IESHI_1_____________
REACTOR TYPE:
_2'dR:QEi_________________
l DATE ADMIN!3TERED:_11112121________________
EXAMINER:
_ELEG.JW_________________
APPLICANT:
131IEUCTION1_IQ_AEELICANIA Use separate paper for the answers.
Write answers on one :nde only Staple question sheet on top of the answer sheets Points for each question are indicated an parentheses after the question. The passing grad 4 requires at least 70% In each category anc a final grade of at least 80%.
Examination papers will be pteked up six (6) hours after the examination starts.
% OT GATECORY
% OT APPLICANT'S CATEGORY J ALUS_ _IQIAL
__SQQHE__
_MALME__ _______ _ ____CAIIOCHI__ _ ________
jy. f 3,ndT'__ _21.11 l.
PRINCIPLES OT NUCLEAR POWER PLANT OPERATION. TilERMODYNAMICS.
HEAT TRANSTER AND TLUID TLOW f M S-.
.11_11__ _21.21
________ 2.
PLANT DES!CN INCLUDING SATETY AND EMERCENCY SYSTEMS 2%fS ai_"T~l__ _11.11 3.
IflSTRUMEllT3 AtlD CONTROL 3 flCRMAL. ADflORMAL.
.12.11__.21_21 l.
PRCCCDURES EMERGENCY AtlD RADIOLOGICAL CONTROL 122.11__ 122_22
________ TOTAL 3 T ! !! A L O r6 A D C _________________%
All work dont on this examination as my own. I have neither Jiven nor reconved aid.
APPLICANT'C SIGNATURE
1.__ER1HC1ELES_CE_HUCLEAR_ECWER_ELauI_CEERAI1CN.
PAGE IEEEMCCINAMICS._uCAI_IRAHEEER_Aut_ELuit_ELCW QUESTION 1.01 (0.50)
Concerntng THERMAL LIMITG:
With regard to MAPRAT.
1.
WilAT 3 the RELATIONSHIP between MAPRAT & MAPLHGR7 (0.75) 2.
The process computer prints out a MAPRAT of 1.05.
Is this acceptable?
(Yes or No)
(0.50) 3.
WHAT physical consequence could occur if the MAPRAT limit is exceeded?
(1.05)
(0.5)
QUESTION 1.00 (0.00) l'ollowing a normal reduction in power from 90% to 70% wttn roctreulation flow, HOW will the following change Cancrease, decrease, or remain the same) AND Wi!Y:
a.
The pressure difference between the reactor and the turbine steam chesL.
(1.0) b.
Final Feedwater temperature.
(1,0)
CUE 3 TION 1.03 (0.00) a.
WilAT s " pump runout" and Wi!Y ts tt an undestrable condttion?
(1.0) b.
Define the term cavitation, and CIVE TWO (2) examples of detrimental effects.
(1.0)
QUESTION 1.04 (0.00) a.
Under WHAT TWO (2) condtttons a: ma x i n.um tesetor power limsted to 25% rather than by MCPR (Core Thermai Power Safety Limit)?
(1.0) t.
WilAT thermal hydraulic phenomenon does operatton above the MOPR Gafety I.tmlt prevent?
(1.0)
(*****
CATCCORY 01 CONTlh0CD CN NEXT PAGC
- )
1-__ER1NCIELER_QE_HUCLEAE_EQUER_ELANI_QEEEAI1QN.
PAGE 3
IEEEMQQINEW1CE._"EAI_IRANEEER_ANQ_ELu1Q ELQW QUEST!0N 1.05 (3.50) a.
Approximately WHAT percentage of neutrons from U-235 are born delayed?
(0.5) b.
The power generated by the reactor at the beginning of core life comes from U-335 thermal itssion and U-338 fast itssion.
Later in core life, larger and larger fractions of power generation are produced by itssion of what two tsotopes?
(1.0) c.
HOW do delayed neutrons contrabute to the control capability of a commercial reactor?
(1.0)
/ 57' QUESTION 1.06 s o. ; e4 Indicate what effect (MCRE NEGATIVE, LESS NCGATIVE. or NO CHANGE) the following changes in core parameters have on the VOID COErrtCIENT Of REACTIVITY:
a.
Increase in void fraction.
(0,5)
L.
co6.uup us 6 taaiva essuuwi ys.. ; ;;.
'TU-44.
c.
Increase in fuel temperature.
(0.5) d.
Increase in core age (3OL to ECL)
(0.5)
(***** CATECORY 01 CONT!!lVED Ott NEXT PAGE
- '***)
2
1.__ER1NCIELEE_CE_NECLEAa_ECWER_ELANI_QEERAILON.
PAGE 4
IEEEMQQINAMICS._HEAI_IEA32EE2_AND_ELuit_ELQU QUESTION 1.07 (3.00)
Alt. t c h each of tho atems in column 1 to the short definttions in column 2?
(3.0)
COLUMN 1 COLUMN 2 (a) fast neutrons I
high energy neutrons (>1.0MeV)
(b) activity 2.
occur indirectly from fission through iIsston (c) delayed neutrons fragment daughter decay (d) reactivity 3.
fractional change in neutron population per generation (e) slow neutrons 4
occur d.rectly from the (f) promt neutrons fission reaction S.
Iow energy neutrons ((0.63eV) 6.
number of distntegrations per unit time of a radtotsotope QUESTION 1.08 (2.00)
Consider a turbine trip from approximately 23% reactor power.
DESCRIBE what would be expected to occur in the plant during the next 15 minutes wtth no operator action. INCLUDE s1;ntiscant parameters such as, temperature (s). pressure. power. etc.
Provido explanations tot plant and parameter conatttons (2.01
(***** CATEGORY 01 CONTINUED ON NEXT PAGE
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i 1-EE1NCIEL E1_Q E_N ECL E AE_ ECW ER_ E L A NI_Q E EE AILQN.
PAGE S
IHEEMCQINAMIC2._EEAI_IRANEEEE ANE_Ek21R_ELC'd QUESTION 1.09 (2.50)
Tho below gragh represents change in moderator temperature coefftetent duttng core life.
Lable each curve (te. Deginning of 11fe or end of 11fel BRIEFLY CXPLAIN why they are different, and BRE! FLY EXPLAIN why each individual curve becomes more negative as temperature increases.
(2.50)
Tamamense en E
01
,y 54 E
5
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1 1
QUESTION 1 10 (2.00)
What two constderations Itmit maximum and minimum (2.0) control rod speed?
QUESTION 1.I1 C1 50)
BRIEFLY discuss the change in vote fraction, doppler effeet.
and feedwater enthalpy due to rectreulation flow rate increase.
The discusston shall include increase, decrease, or to change and an explanatotn as to why.
(1.5)
I QUESTION 1.12 (1.00)
The initial reactor count rate is 100 cps. You add sufficient posattve rt'ctivity to establish a 120 second pertod.
!!c w long will at take the count rate to tacrease tc 10Et OpJ with no addstional oporator action?
(1.0)
(*****
END Of CATECORY 01
- )
.__E ANI_DEElGM_1MCLHQ1NG_SAEEII_&UD_EMERGENC1_EISIEMS PAGE 6
QUESTION 2.01 (2.50)
In the Reactor Core Isolation Cooling (RCIC) system:
a.
What is the cooling water flow path for the RCIC Lube Oil Cooler?
(1.0) b.
How would fatture of the Gland Sect R,_o t a r y Blower affect operatton of the RCIC system?
(one. affect required)
(1.0) db<
~
c.
How is the turbine exhaust line protected from overpressure? (0.5)
QUESTION 2.02 (1.50) a.
Following WHAT MAJOR ACCIDENT would the Emergency Closeo Cooling (ECC) System be used to supply the Fuel Pool Cooling and Cleanup System heat exchangers?
(1.0) b.
Which ECC loop can be operated from the Remote Shutdown Panel?
(0.5)
QUESTION 2.03 (1.00)
Are the statements below TRUE or FALSE concerning the High Pressure Core Spray Diesel Generator System?
1.
The bus EH13 15 powered by the diesel generator due to loss of preferred power.
After the preferred power source is made available pad}the operable preferred power source braker is closed.
The HPCS-DG output breaker automatically OPENS.
(0.5) 2-There are two NORMAL engin stop pushbuttons: 1 in the Control i
Room.
2.
on the local panel.
BOTH pushbuttons are ALWAYS active.
(0.5) l l
(***** CATEGORY 02 CONTIMUED ON NEXT PAGE
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- 1. 2 QUESTION 2.04 d
a.
The reactor recirculatton system cavttation interlocks protect rectreulation pumps, jet pumps, and FCV's when what 4
two condatons exist?
(2.0) b.
If the above menttoned condttons or conditton exist, what C7. f g automatte operation [or interlock [become; active?
h 1
es l
QUESTION 2.05 (1.00)
An Altermate Rod Inserion (ARI) trip signal (Redundant Reacttvity
]
Control System (RRCS)l.or activitation will inttate what two operations?
(1.0)
QUESTION 2.06 (1.50) 1 (a)
How many ADS valves are operable from the remote I
shutdown panel?
(0.53 (b)
Manual initiat' ton of ADS bypasses which permissives in the logic chatn?
(0.5) i Cc). After ADS has inntatad (valves opened), will securing the low pressure systems close the ADS valves?
Cyes or no)
(0.5) l i
QUESTION 2 07 (1.25)
The Remote Reactor Shutdown System provides backup control over the operation of what five systems?
(1.2S) 4 i
(***** CATEGORY 02 CONTl!!UED ON NEXT PAGE
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i 1-ELANI_D E SIGN _1NCLUQ1NG_ EA EEI1_AND _EME EG ENCI_ SIEIEM S PAGE 8
QUESTION 2.08 (2.00)
On receipt of a LOCA tsolation signal (level 2 or DW pressure of 2 psig), the vacuum rettef valves F010A & B will shut if open.
a.
How can the shut signal be overridden?
(1.0)
[
b..
Once overridden, the valve will remain open until what two condatons occur?
(1.0)
?
i i
QUESTION 2.09 (2.50) a.
Regarding the Plant Electrical System, the standby diesel generators start automatically upon receiving what signals?
(three required)
(1.5) b.
When a LOCA signal is present to the Standby Diesel Generator System, what two autoshutdown signals or functions are NOT bypassed?
(1.0)
I l
QUESTION 2.10 (3.00) a.
What condittons will shutdown the Safety Related Instrumentation Atr System compersor automatically?
( f o ta r required)
(2.0) b.
The "ON-RESET" position on the Safety Related Instrumentation Air Compressor selector switch provides what function?
(1.0) 1 QUESTION 2.11 (1.50) i' What-three conditions will trtp both Reactor Water Cleanup System Pumps (if running) o r - preven t their startup?
(1.S) i e
4
?
(***** CATEGORY 02 CONTINUED ON NEXT PAGE
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-_E ANI_ RESIGN _1NCL11Q1NG_SAEEII_ANQ_EMERGENGl_E11IEME PACE 9
^
D QUESTION 2.12 C 3.%
3.
Which loop of the Emergency Service Water System suppites the HPCS pump room cooler?
(0.5) i b.
If a Dtvision 3 LOCA Signal is received, what specific automatic g
t i
events occur and to which loop in the ESWS?
(1.
c.
Breifly describe the LOCA override feature of the ESWS.
( include the differences between divisions )
(1.5)
+
l i
l. QUESTION 2.13 (1.00) i l
What prevents flooding of the drywell 1f the suppress on pool makeup system is inadvertently initiated when the reactor vessel ts l
pressurt:ed?
(1.0)
J 1
e t
f i
1 b
b 1
i r
I I
i i
f 3
l
(*****
END OF CATEGORY 02
- 2*)
}
1 EIEUMENIE_ANQ_COMIRQLE PACE 10 L
- ,7
- .
QUESTION 3.01 Concerning the High Pressure Core Spray (HPCS) system:
f a.
What two conditions will cause the mtntmum flow valve (FO12) to auto-close?
Include setpoints.
(1.5) b.
Assume the Containment Outboard Isolation Valve (F004) has been closed by the htgh water level seal-in circuit.
Under what condition and operator action is required to d7,75 reopen F004?
J' c.
What does the amber light between the HPCS pump energized /
deenergized lights indicate?
(0.5)
QUESTION 3.02 (2.50) f Descrtbe the "SETPOINT SETDOWN" circutt used in the feedwater control system.
Cinclude the two reasons levels (0,5) times (0.S),
and initiating signal (s)
C'.
] ) #'
(2.5)
- 0. 5 1
0 QUESTION 3.03
( 1. 30 )
What electrical interlocks or controls prevent simultaneously supplying RPS "B"
from alternate power while RPS "A"
is supplied from alternate i
power?
(1.
)
1 QUESTION 3.04 (2.00) a.
The type of reactor vessel water level instrumentation used at Perry has two disadvantages.
List these two disadvantages.
(1.0) b.
Define vessel zero snd instrument zero.
(1.0) l
(***** CATECORY 03 CONTINUED ON NEXT PACE
- )
1-1NEIRUMENIE_ANQ_QQNIRQLE PACE 11 QUESTION
.3.05 (2.00) a.
What are the 3 input signa 1s to the feed pump NPSH computatton l
circuitry?
(1.0) b.
What functions (2) will the trip signal out of the NPSH circuit provide?
(1.0)
QUESTION 3.06 (2.00)
The Main Steam Line flow Restrictors provide what control functions or signals?
(four required)
(2.0)
QUESTION 3.07 (1.00)
Audible and visual alarms on the Area Radiation Monitoring System alert an operator in the control room of what three conditions?
(1.0) ed QUESTION 3.08
( 2.%
a.
-WW ; t e time delays in Dtvision I and Division !!
Entratnment Spray initiation logic?
(1.0) m
- ). _. :,,..
).
~
4 c.
Once automatically initiat.a. how can the system be secured?
(1.0) i l
QUESTION 3.09 (1.00)
List which RWCU isolation valve will close upon placing the "B"
SLC pump swatch in "RUN".
(1.0)
I
(***** CATECORY 03 CONTINUED ON NEXT PACE
- )
1 1
~.
d.
IkSIEUMENIS_ANQ_CQMIRQLS PAGE 12 QUESTION 3.10 (2.00)
The MSIV category of the Nuclear Steam Shutoff System affeet the j
isolation of the inboard and outboard MSIV's and Main Steam Line l
Drains (MSLD).
Complete the below table identifying the differences in the Trip Logic and the Trip requirements.
(2.0) f MSIV MSLD 4
Trip "A"
Channe! A and Channei
__1__
Channe1 A and Channe1
__3__
Trip "B"
Channe1 B and Channe!
__2__
Channe1 B and Channe1
__4__
( 4 @ 0.25 ea = 1.0 )
REQUIREMENTS MSIV =
5 out of two taken twice Cone, two)
(0.5)
MSLD :
6 out of two taken twice Cone, two)
(0.5)
(For 5 and 6 chose either one or two)
QUESTION 3.11 (2.50) l List the five trip signals initiated at Level 8 (219") from the j
reactor vessel level instrumentation.
(2.5) i I
l QUESTION 3.12 (1.00)
The Intermediate Range Monitors CIRM's) INOP trip operates on what three conditions?
(1.0) l
\\
I QUESTION 3.13 p(.00)
An RHR pump will automattcally trip on three condtttons.
One of these trips is "No Clear Suction Path".
List two of the valve l
t combinations required to start the RilR pump.
NO )
i l
l
(*****
END Or CATECORY 03
- =*)
i li
1-ERCCEQURES - NQEMAL._AENQRMAL._EMERQENC1_ANQ PAGE 13
.EAQlOLQQ1 CAL _CQNIRQL i Gu n n)"
QUESTION 4.01 (2.50)
Ltst the five entry conditions for the Reactor Pressure Vessel Control procedure (PEl-1) ?
(2.5) i QUESTION 4.00 (3.00)
List ON!-E12-1 (Inadvertent Initiatton of ECCS/RCIC) immediate actions.
(!nclude all emergency systems HPCS, LPCS, LPCI, RCIC, and ADS.)
(3.0)
QUESTION 4.03 (1.50)
What are the immediate action steps for an unexplained change in Reactor Power or reactivity while the reactor is operating.
[ONI-CS11 (3 required)
(1.5)
QUESTION 4.04 (2.50)
-g,,,,,,
ON!-C71 " Reactor Scram" list 5 immediate action steps following a full scram.
What are these S actions?
(2.5) i QUESTION 4.05 (2.00) l The PNPP Emergency Plan provides for four (4) emergency classifications.
List these four (4) classifications.
(2.0) l l
QUESTION 4.06 (2.00) i' Reactor power is limited by the feed pump (s) operating arrangement.
Below are the reactor power l arat t s.
List the feed pump (s) arrangements or required for eich power level (2.0) a)
100%
c) 60%
b) 80%
d) 20%
4 i
(***** CATEGORY 04 CONTINUED ON NEXT PAGE
- )
i 1.__ERCCEQUEEE_ _HQEMAL._ARNQEMAL _EMERGENC1_AHQ PAGE 14 RAQLQLQG1 CAL _CQUIRQL QUESTION 4.07 (1.00)
The immediate action for a " STATION BLACKOUT" (ONI-RIO) limits the manual start of a diesel generator from the control room to how many attempts?
(1.0)
. QUESTION 4.08 (2.00)
OAP-0103 shift rettef and turnover, requires the on-coming Supervising Operator (50) to review seven togs and/or instructions.
List four (4) of these items.
(0.0)
QUESTION 4.09 (1.00)
How are annunctators which have been defeated visually identified?
(1.0)
QUESTION 4.10 (1.00)
Explain how to reset the RCIC turbine if tripped due to (a) mechanical overspeed and (b) Division 1 RCIC System isolation trip.
(1.0)
QUESTION 4.11 (1.00)
Startup Test Instruction (ST!-J11-003) " Fuel Loading" describes the operator actions if any neutron monitor indicates an unexplatned or unexpected increase in neutron multiplication during fuel loading.
List these two actions.
(1.0)
QUESTION 4.12 (3.00)
In the procedure for Evacuation of the Control Room (ONI-C61)
What are the six immediate actions you are to perform prior to exiting the Control Room?
(Assumtng you have adequate time.)
(3.0)
(***** CATECORY 04 CONTINUED ON NEXT PACE
- )
1-ERQCEQUEEE - UQEMAL _AENQEMAL._EMERGENC1_ANQ PAGE 15 RAQ1QLCG1 CAL _CQUIRQL QUESTION 4.13 (1.50)
When may unitcensed personnel operate the controls in the Control Room which directly affect the reactivity or powar level of the reactor?
(1,5)
OUESTION 4.14 (1.00)
Following telephone conversations with the S.O.C.
System Dispatcher, that information should be entered in the Reactor Log?
(two items required)
(1.0)
(*****
END OF CATECORY 04
- )
(*************
END OF EXAMINATION
- )
___Ed1HCLEkER_CE_ NUCLEAR _ECWER_ELANI_QEERAILQN.
PAGE 16 IHERMQQ1NAMICE._EEAI_IRANEEER_ANQ_ELu1R_ELCW ANSWERS -- PERRY 1
-85/12/09-KING.
M.
4 4
I I
AMSUCR 1.01 (2.50) 1 MAPRAT = APLHCR / MAPLHGR Limit (0.75) 2.
No (0.50) 3.
The' clad temperature can exceed 2200 F (1.0) during 4
(1.25)
RETERENCE SSES Thermal Limits Perry - Perry Nuclear Power Plant Thermal Sciences.
Chapter 12 Pages 12-4 and 12-5.
ANSUER 1.02 (2.00) a.
Decreases [0.25).
There is less steam flow, therefore, less pressure drop through the main steam lines (0.751.
(1.0) b.
Decreases (0.25).
Less extraction steam from the turbine to heat the feedwater (0.75).
(1.0) l REFERENCE EIH liest Transfer Lesson Plan, pp. 75 & 78, and E!H Nuclear Training, p.
10.4-11.
l Perry - MPL N32/C85, figure N32-3 MPL N36 i
i i
I i
EE1MQ1ELEE_QE_EMCLEAE_EQUEE_EL&HI_QEEE&IlCM.
PAGE 17 IEEEMQQlS&MlCE._dEAI_IEAMEEER_&MQ_ELElC_EkCW ANSWERS -- PERRY 1
-85/12/03-KING, M.
ANSUER 1.03 (2.00)
I" f
- *Y #
a.
Running a contrifugal pump at minimun head and maximum capacity (0.5).
Runout causes electrical over d.4 # / s c i e evi,r heating, possible electrical damage, and Inkely
,,fgg7-trapping off line (0,5).
(1.0) b.
Cavitation is the flashing to vapor of liquid in the pump suction or a low pressure area.10.51 Cavitation results in any or all of the following:
excess vibration and noise, reduced pump efftenney, pttttng
- . d corrosion of pump tmpeller (not limited to these 5)
(2 required at 0.25 each)
(1.0)
RETERENCE CPNT HT & Core Thermal Char.
L.P.
Per7y - Perry Nuclear power Plant Thermal Science, Chapter 17: Pages 17-38 and 17-20.
ANSWER 1.04 (2.00) a.
Critical power operations with reactor pressure (785 ps1g10.51 CR core flows (10%CO.51, (1.0)
T r a n s i t i o n b o t t i n g t,0 rf (1.0) b.
REFERENCE HATCH Q & A Bank e's 1-54 and 1-57 Perry - Perry Tech. Spec., Page 2-1 Perry Nuclear Poner Plant Thermal Sciences, Chapter 12: Page 10-5.
- = _. _ - -.. - -.._-. __ - _
l i__ER1NCIELEE_QE_NECLEAE_.EQWER_ELAMI_QEERAI1CN.
PAGE 18 IEERMQQ1NAMICE._EEAI_IRANEEER_&ME_ELu1D_ELQW PERRY 1
-85/12/09-KING.
M.
ANSUERS I
i
{
ANSWER 1.05 (2,50) i a.
0.65%
C0.5) b.
Pu-239 and Pu-241 (1.0) c.
Delayed neutrons increase the average neutron generation time (0.75) l lby a factor of more than 10001 Increasing the control time of the reactor. (0.25)
(1.0) s.
t REFERENCE l
Grand Gulf Rx Phystes pg. 31-34 i
j Perry - Perry Introducton to Nuclear Reactor Operations, Chapter 3 Pages 3-11 and 3-31.
l I
i
/ '
ANSWER 1.06
)
l I
J a.
More negative.
(0.5)
I
-L.
e;:*.;.'
is.;;
{
I c.
More negative.
(0.5) i I
I d.
Less negative.2 (0.5) j REFERENCE l
Perry - Intro to Nuclear Ops.,
p.
6.29.
l l
}
o
- 1 __5.R1EC1ELEE_QE_MECLEAE_EQWER_ELAMI_QEERAI1QR.
PAGE 19 IllERMQQIMAMICS. liEAI_IRANSEER_AN2_Ekult_ELQW
~I ANSWERS -- PERRY 1
-85/12/09-KING.
M.
j 1
ANSWER 1.07 (3.00)
I : a 4 : f 2 : c 5 = e i
3 : d 6
b I
4 OR i
a 1
d = 3 4
7 b : 6 e : 5 c = 2 f
4 (6 e 0.5 ea a 3.0) l RETERENCE d
Annotated River Bend BWR-6 Transtents Porry - Introduction to Nuclear Reactor Operations, Chapter 3: Page 3-33.
1 4
ANSWER 1.08 (2.00) i i
following a turbine trip at 29% power there will be no scram. The turbine bypass valves will handle all the generated steamt0.51. However, due to a loss of extraction steam there will be a gradual but marked 4
i decrease in feedwater temperature.IO.51 Due to the moderator temp-erature coefftetent, reacter power will begin to increaset0.51 As reactor power increases pressure will increase as during normal oper-l atton.[0.51 (2.0)
I 1
REFERENCE i
Grand Gulf RPS, Rx Theory L.P.'s and Procedure 03-1-01-1
-Perry - Perry MPL C71, Page 30. Sectson !!.C.S.
j Perry introduction To nuclear Reactor Operations, Chapter 6.
l f
l i
l i
I i
1-__ER1NCIELEE_QE_ NUCLEAR _EQWER_ELANI_QEER&IlQN.
PAGE 20 IHERMQQ1NAMICS _EEAI_IRANSEER_ANQ_Eku1R_ELQU ANSWER 3 -- PERRY 1
-85/12/09-KING, M.
i ANSWER 1.09 (2.50)
Ca) : End of life (0.25)
I 4
Beginning of life (0.25)
(b) :
At EOL, the some effects are seen.but the increase in f ts greater than the decrease in the other three because of fuel l
burn-up and increase in moderator to fuel ratto.
(1.0)
Each of the curves become more negative as temperature increases because the coolant change in denstty per degree ts larger at higher temperatures.
(1.0) l REFERENCE Perry - Introduction to Nuclear Reactor Operation, Chapter 6: Pages 12 and 14.
Figure 6.3 J
^
ANSWER 1.10 (2.00) 4
- 1. Maximum control rod speed is intended to Itmit the rate at which control rods can be withdrawn during reactor startup.
Tast reactivity insertion rate results in short periods and could cause reactor core to rapidly overheat and become damaged.
(1.0) 2.
The rate of control rod speed must be suffletent to cvercome xenon reactivity decrease during burnout.
(1.0) i
-RETERENCE j
Perry - Introduction tc Nuclear Reactor Operations.
Chapter 71 Pages 7 - 10.
l I
r l
l i
P.__5&lMC1 ELE 1_QE_MUCLEAE_EQWER_ELAMI_QEER&ILCM.
PAGE 21 l
j -
IEERMQQIEAMICE._EEAI_IEANSEER_ANQ_ELula_ELQW
' ANSWERS -- PERRY 1
-85/12/09-KING.
M.
ANSWER 1.11 (1.50)
Votd fraction : Decrease (0.25)
The void fraction is slightly smaller because the negative affects of doppler are compensated for by the void fraction.
(0.25)
Doppler effect : Increase (0.25)
As power increases the fuel temperature increases.
This temperature increases causes doppler to add negativity.
(0.25) l Enthalpy : Increase (0.25)
The increased reactor power allows more extraction steam to be drawn off thus increases inlet enthalpy.
(0.25)-
4 REFERENCE j
Perry Nuc. Pwr. Plant Thermal Sciences, Chapter 9: Page 9-8.
I f
l ANSWET 1.12 (1.00) 4 9.21 minutes or 552.62 seconds (1.0)
Pf : Pt a e Etime/pertod 4
10E4 : 10E2 : e Ettme/120 10E4/10E2 = e Ettme/120 f
in(10E4/10E2) : time /120 i
4.61 = time /120 I
4.61
- 120 = time 4
552.62 sec : time REFERENCE l
Perry introduction to Nuclear Reactor Operations, Chapter 4; Page 4-4, PP 4.3.
4 l
4 L
i lw -..
e g
L ELAHI_QE11GN_1NCEun1NG_EAEEIl_AM2_EMERGENC1_11EIEME PACE 22 ANSWERS ~-- PERRY 1
-85/12/09-KINC. M.
i i
i ANSWER 2.01 (2.50)
I i
a.
From RCIC pump discharge to cooler and returned to RCIC pump j'
suction.
(1.0) j b.
Steam leakage would occur from turbine resulting in airborne d
contamination tn RCIC room aK possibly system isolation due j
high' area temperature. ICAF)C4 (1.0) i c.
Rupture ciaphragms which exhaust to annulus.
I FO45 will not open if exhaust isolation shut (Interlock)
Turbine trip on high exhaust pressure i
It of 3 required)
(0,5)
I i
l REFERENCE i
Ferry - SDM, E51, pg.
8, 22, 25, 26. and Fig. 1 l
1
'5 i
ANSWER 2.02 (1.50)
F i
i a.
LOCA (1.0) l I
b.
ECC Loop A C0.5)
REFERENCE Perry - SDM-P42, page 10 and 17 l
l i
ANSWER 2.03 (1.00) 4 T)MTE /'A ')I 6 s
(0,5) i 1.
3.
False i The LOCAL / REMOTE swatch will select the active button I (0.5)
I i
Pages h}f
. REFERENCE i
a 18.
Perry - SDM E20Bi Rev.2.
i i
r 4
l
)
i e
t b
j f
i 1, _ -, - -, -. _. _. -.,. _ - _, -.. _. _ _, -.,,. _ _ _ _ -,, -.. _. _ _. _, _ _ _ _ _ _. _ _. _ _ _ _ _ _. - _ _ _ _. _ _
_P AMI_QE11GM 1NCEUD.1MG_EAEEI1_ASQ_EMERGEHC1_EXEIEME PAGE 23 ANSWERS -- PERRY 1
-85/12/09-KING.
M.
e L' J<,
ANSWER 2.04
%)
M a.
1 Low total feedwatet flow (3.43X10E6 lbm/hr) [0.51 m ainoa
.e 2 51:
-..;i
.1
, ^"-ya: - suma 4 0.,4 % openg sa.+n t-fiv. vaia uvi 'i + qst YTW' '
N) 2.
Steam dome (0.51 / pump suction line (0.51 temperature differential low (8 T degrees delta T) I detta T value (1.0) not required I i
b.
1.
pumps automatically downshift (0.5) 2.
interlocksbeome active to revent fast speed operation by allowing only slow speed pump starting togte to be used LO.Sl (1.0) 1 1
REFERENCE Perry - SDM B33 Rev.
3, page 14 ANSWER 2.05 (1.00) 1.
block instrument att supply to scram air header (0.51 2.
vent scram att header (0.51 (1.0)
/
3 C /*ti l? l of
'i-)/jasf l
Z.
} L C.,
^
,u. L i: n. ~
u.s
'~
REFERENCE y,
Perry - SDM C22: rev.
3, page 2.
4 7,6 (1.50)
ANSWER, 2 0
Q( n r e,dt e l
I
- ', 2 (0.5)
(a)
//j!
4iE (0.5)
I (b) reactor water level (c) no (0.5)
RETERENCE Perry - MPL B21Ci Rev.
3.
pages 9,
16, & 18 MPL C61 : Rev.
1, page 2 lOI-$2 l' s lf
]
i l
l
___ELANZ_QESLQN_1NCLUQlMQ_EAEEI1_ANQ.EMEEQENC1_11EIEME PAGE 24 ANSWERS --' PERRY 1
-85/12/09-KING.
M.
ANSWER 2.07 C1.25) 1.
Emergency Service Water (ESW)
~
2.
Emergency Closed Cooltng (ECC) 3.
Automatic Depressurisation (ADS) or Nuclear Botter System 4.
Restdual Heat Removal (RHR)
F-S.
Reactor Core Isolatton Cooling (RCIC)
(5 9 0.25 ea.)
D.
I'/ $ 5' I G L I
. ')
YE/)[ ( Orj/i:p f REFERENCE Perry - MPL C61: Rev.
1, page 1 ANSWER 2.08 (2.00) i a.
Valve overridden by taking control switch to open.
(1.0) b.
1.
The LOCA isolation signal clears (0.251 and drywell pressure is at least equal to containment pressure (0.251.
(0,5) l 2.
The operator takes vals-control switch to close.
(0.5)
I REFERENCE Perry - MPL M16: Rev.
1.
page 4 l
}
ANSWER 2.09 (2.50) a.
1.
loss of voltage on associated class 1E bus l
2.
high drywell pressure
/
3.
Iow reactor vessel water level (3 @ 0.5 ea)
I b.
engine overspeed (0.5) and diesel generator lockout relay (0.51 (1.0)
REPERENCE Perry - SDM RIO: Rev.
1.
page 38 SDM R43: Rev. 3 pages 6 & 9
.b Nik h - lQ h t.'/ 3 f) ? Jr E $ ll* ~ l l t
,\\
.y i
\\
/c O r' /4
/.
s y
- 3. di> he 4h..a.s On ik:oc m m o Ev.:
a.__ELANI_QE11GN_1NCEun1NG_1&EEIl_ANQ_EMERQENC1_111TEME PAGE 25 ANSWERS -- PERRY 1
-85/12/09-KING. M.
ANSWER 2.10 (3.00) a.
1.
expiration of the purifier cartridge useable life 2.
failure'of the automatic condensate drain system 3.
high discharge air temperature 4.
Iow tube oil
/d/i#
S.
motor overload (4 required e 0.5 ea) b.
The ON-RESET is used to restart the unit should it be shutdown on a malfunction of the automatic condensate drain system.
(1.0)
REFERENCE Perry - SDM P57; Rev.
3, page 6 ANSWER 2.11 (1.50) a.
1.
RWCU suction from containment outboard isolatton valve, G33-F001, less than 90% open.
(0,5) 2.
RWCU suction from containment inboard i s o l a t i o n v -s i v e,
G33-r004, less than 90% open.
(0.5) 3.
Suction flow to the RWCU rectreulation pump is less than iO gpm.
(0.5)
REFERENCE
_ Perry - MPL G336 Rev. 3 page 12 l
i l
i L
a-ELAMI_DEELGM 1NCLUQLEG_SAEEII_AHQ_EMERGEMC1_11ETEME PAGE 26 1
ANSWERS -- PERRY 1
-85/12/09-KING. M.
1 i
D
( 3.M ANSWER 2.12 a.
Loop C (0.5) b.
Loop C (0.51 discharge valve F104 starts to open, at 15%
l the Loop C pump motor starts, the discharge valve continues to open until full open (0.51 e:
- x.......
iv.3m, u a v v i o p. e. 5. 2 4. /)
(1.
I valve number not required 1 p
c.
Override is included into the control circuits for all three ESW pump discharge valves. F130A & B and F140 (0.51.
To override an automatic initiatton signal the control room operator can position E I T!!ER the pump or valve control switch to STOP/CLOSE for Dtvtston I & !!
[0.51.
For division
!!!. the operator places the pump C control switch to STOP 10.51 (1.5)
RETERENCE Perry - SDM P4Si Rev.
3, page 2 & 13 ANSWER 2.13 (1.00)
The top of the drywell weir wall has sufficient free board height to account for the increased supperssion pool level.
(1.0)
REFERENCC Perry - MPL G43: Rev.
1.
page 13 I
1-IM2IEEMENIE_ANQ_CQMIRQLE PAGE 27 ANSWERS -- PERRY 1
-85/12/09 Kl.NG, M.
jet
- A s r y
ANSWER 3.01 (5. 5 0 r Q5Egpm OR
/
Th :
Q J2d'psig.
(1.5) a.
High flow @
Low discharge pressure b.
1.
Reactor vessel water level decreases below Level 8.
fo!! owed by the operator depressing the high water level seal-in RESET pushbutton on panel P601.u, t... r~~
OR 2.
Reactor vessel water level ecreases to Level 2 generating a Davtston 3 low level LOCA signal.
(.75) c.
Indicates the pump control switch has been placed in the STOP position while a LOCA signal is sealed-in.
(0,5)
REFERENCE Perry - SDM E22A, pages, 2,
19, & 21.o.~72'F/rJJse / q.o C.t7 C
t?l k L h l c Cir rJ l l'Q S-91 C2
' {U OI 0Yf
~
Thts ctrcutt-helps ; c -;,pr enn t-a.--M g 5 !e"e! ':i; e! the ! edwa tes--
s m
r: := !O E01.
luf M e^.
O.
ttrt-W ' = g
=
(g,;7 The seldown circuit automa,tLcally LOWERS the level setpoint tp_,1.9,.incdes (0.25) after
[ p, $)
a 10 second (0.51 S S 'in ct level signal [0.251.
The inttnating signal for setpoint setdown is a Level 3 4. p.
i.vm 4e-o+*4m-uM4---L-ha t-s+n.14-4 -- L a.v e4 4.-4 & g na 4 -4+-t h e-r e a e tm r rockr e -s y st em-t -1,0J (2.5)
RETERENCE Perry - SEM N27/C34: Rev.
4, pages 16 & 17 ANSWER 3,03 (1.
)
I Placing Power Source Selector Switch in the " ALT-A" positton energt:es a relay (K2A) which completes the circutt to RPS Bus A.
If power is lost the 343 "B"
and the operator turns the Selector Swttch to Bus "B",
this will deenergt:e Bus "A"
h because the Selector Swatch is a ' break before make* swttch.
Both Buses are now deenergt:ed.
(1 h) l i
REFERENCE Perry - SPM C-71, Rev 4,
page 26 and Tagures C71 C71-4A i
'$___lN111HMEMI1_AND_CQEIRQL1 PACE 28 PERRY 1
-85/12/09-KING.
M.
ANSWERS ANSWER 3.04 (2.00) a.
11 The water level reference leg will tend to flash to steam during large pressure transtents in the reactor vessel.
(0.5) 2)
The normal temperature of the reference leg water is much lower than the temperature of the water in the reactor vessel?
[ Vessel level will be lower than indicated level.1 (0.5) b.
Vessel sero the lowest point on the inside of the vessel bottom head.
(0.5)
Instrument zero - top of active fuel or 363.5" above vessel sero. (0.5)
(only one required)
RETERENCE Perry - SDM B21, Rev.
3, pages 10-11 ANSWER 3.05 (2.00) a.
Inputs - Suction header pressure (0.341 Teodwater temperature (0.331
- Pump suction flow (0.331 (1.0) b.
Trip signal 1.
Alarm on P680 (0.51 0.
Start signal to any feedwater pump in STANDBY [0.51 (1.0)
L
??OO 5 iiiliL REFERENCE Perry - SDM N27/C34: Rev.
4, pages 28-29
'l-1M1IELIMENI1_ANQ_CQEIEQL1 PAGE 29 i
l ANSWERS -- PERRY 1
-8S/12/09-KING, M.
l ANSWER 3.06 (2.00) 1 1.
Provides steam flow signal to the three - element feedwater
)
controller.
I 2.
Provides input to the feedwater level programming circutt.
t 1
3.
Provides a steam flow signal to steam Inne dratn valves, 4.
Provides individual steam line flow indication. (4 e 0.5 s 2.0)
(2.0) 1
[
2-d6 jd h5/SC7/6,5l f, /T A
~
REFERENCE i
Perry - SEM N27/C34: Rev.
4, page 22 2LM 6 31 pa
< 3 i
ANSWER 3.07 (1.00) j 1.
Radtation levels that are 2 x background.
(0.331 4
)
2.
Radiation levels that are 3 x background.
[0.331
[
4 3.
Selector circuit loss of power / signal.
(0.34)
(1.0) t' i
i REFERENCE l
Perry - SDM D21. Rev.
3, page a 1
d i
ANSWER 3.08 (2..
t I
(10 minute delay) in Loop A to assure adequate e
a a.
Dtvtston !
core covering and cooling is provided by all 3 e
LPCI loops.
(0.5) l Division !! - (90 second delay) to allow Loop A (Division !)
l time to depressurtse containment.
(0.5) i i
m.
s.:'_
i c.
Any intt ating signal cleared (0.51 and depressing manual reset (1.0) button [?.51.
i l
REFERENCE i
Perry - MPL Ela 1t e v.
3, pages 31-32 i
$___ld11EEMENI1_AUQ_COMIRCLE PACE 30 ANSUERS -- PERRY 1
-85/12/09-KING, M.
ANSUER 3.09 (1.00)
Dtvtston valve F001 (1.0)
REFERENCE Porry MPL- 033; Rev.
3, page 14 ANSUER 3.10 (2.00)
MSIV's MSLD Trip "A"
Channel A & Channel __C__
Channel A& Channel __D__
(0.5)
Trtp "B"
Channel B & Channel __D__
Channel B & Channel __C__
(0.5)
MSIV one-out-of-two-taken-twice (0.5)
MSLD two-out-of-two-taken-twsce (0,5)
REFERENCE Perry - SDM B21: Rev.
1, page 2 ANSUER 3.11 (2.50) 1 Main turb1ne tr p (0.5) 2.
Reactor feed pumps trtp (0.5) 3.
RCIC steam supply valve closure (r045)
(0.5) 4.
HPCS inlection valve closure (T004)
(0.5) 5.
Scram (0,5)
REFERENCE Perry - SDM B21. Rev.3. pageS
~.
2.
IE11guMggIE_ANQ_cQgIRQLE PAGE 31 PERRY 1
-83/12/09-KING.
M.
ANSWERS ANSWER 3.12 (1.00) 1.
when the high voltage drops below a preset level (0.34) 2.
when one of the modules is not plugged in (0.33) 3.
when the OPERATE-CALIBRATE switch is not in the OPERATE position (0.33)
REFERENCE Perry - SDM C71. Rev.
4.
page 20
\\
ANSWER 3.13
%.00) 1.
Either RHR ACB) suppresston pool suction valve F004A413) [0.51 sr fuel pool storage tank suction valvi F066A(B) open (0.51.
(1.0)
S I'~
g 2.
Shutdown cooling suction valve F006A [0.51 and shutdown cooling outboard and inboard valves F008 and F009 are open (0.51.
_L&-rT' REFERENCE Perry - MPL E12: Rev 3.
pages 34-35
LI__ERQCEQHREE-NORMAL._ARUQEMAL_EMERGEMC1_AHQ PAGE 32 RAQ1QLQG1 CAL _CCMIRQL ANSWERS -- PERRY l
-8S/12/09-KING.
M.
ANSWER 4.01 (2.50) 1.
Reactor level is less than 177.7 inches or unknown.
2.
Reactor pressure is greater than 1065 psig.
3.
A condition exists which requires a MSIV isolatton.
4.
Drywell pressure is greater than 1.68 psig.
S.
A condition extsts which requires a reactor scram and reactor power is either a) above 4% or b) connot be determined.
CS 9 0.5 ea = 2.S)
REFCRENCE Perry - PEl-1 Rev.
1.
Draft 4,
Page 2 ANSWER 4.02 (3.00) 1.
Confirm misoperation (0.251 by at least two (0.251 independent indications, if the initiation is valid enter PEl-1, RPV Contrl (0.5) 2.
If the emergency system initiation has been vertited to be inadvertent:
a.
Stop the running emergency system as follows:
1)
HPCS In tlatson - Take the itPCS PUMP switch to STOP.
(0.S) 2)
LPCS Instration - Take the LPCS PUMP switch to STOP.
(0.5) 3)
LPCI Initiation - Take the RiiR PUMP A (B, C) switch to stop.
(0.5) 4)
RCIC Initiation - Manually trip the RCIC Turbine by depressing the RCIC TURBINC REMOTE TRIP pushbutton.
(0.S) b.
If permissives for ADS initiation were met, depress ADS A and 3 LCGIC SEAL IN RESET pushbuttons.
(0.5)
REFERENCE Perry - ON!-E 12-1, Rev.
2, page 3
1-ERQCEQHRES - NCRMAL._ARNQWWAL _EMERGENCI_ANQ PAGE 33 RAQ1OLOGICAL_CCNIRQL ANSWERS -- PERRY 1
-85/12/09-KING, M.
ANSWER 4.03 (1.50) 1.
For an unexplained increase in reactor power, place RECIRC LOOP A& B FLCW CONTROLS in MAN and restore power to less than or equal to the power prior to increase.
(0.5) 2.
If unable to quickly terminate an unexplained power increase, perform a rast Reactor Shutdown'.
(0.5) 3.
If a portion of the control rods scrammed, arm and depress the RPS MLANUAL SCRAM CH A, B.
C and D pushbuttons.
(0.5)
REFERENCE Perry - ONI-ON1-C51; Rev.
2, page 3 ANSWER 4.04 (2.50) 1.
Place the REACTOR MODE SWITCH IN S:'UTDOWN.
(0.5) 2.
Verify reactor power is decreasing as indicated by the nuclear instruments.
(0.5) 3.
When reactor power is less than 4%,
trip the main turbine.
(0.5) 4 Vertfy reactor pressure is being maintained with bypass valves and/or SRV's.
(0.5) 5.
Verify reactor water level stablizes near 200 inches (183, inches if Setpoint Setdown is acuated).
(0.5) l REFERENCE l
Perry - ONI-C71 Rev.
1, page 3 4
l J
4
'[-
tRCCED.11EE1_:_NQRMAL._AENQHMAL EMCRGENCL.AND.
PAGE 34 R&Q1CLCG1 CAL _CONIRQL i
ANSWERS -- PERRY 1
-85/12/09-KING.
M.
ANSWER 4.05 (2.00) 1.
Unusual Event (0.5) 2.
Alert (0.5) 3.
Site Area Emergency (0.5) 4.
General Emergency (0.5) d REFERENCE Perry - Emergency Plan - Rev.
4.
pages 4-1 and 4-2 i
r ANSWER 4.06 (2.00) a)
100%
2 RTP C0.S) b)
80%
60%
1 RTP (0.5) d)
20%
= 1 MFP C0.S) i REFERENCE Perry ONI-N27. Rev.
2, page 2 ANSWER 4.07 (1.00)
Diesel starta from the control room are Itmited to one attempt.
(1.0) j REFERENCE Perry - CNI-R10, Rev.
O, page 2 l
i
[
, - _...,... _ ~. _....,.. _ _ _ _ _,, _,.. _ _ _.... _ _.. _. _ _ _... _ _ _... _,,
'A-
'EROCEQ'lRES - NORMAL._AREQEMAL _EMERQENC1_AHa PAGE 35 EAR 1QLOGICAL_CQNIRQL ANSWERS -- PERRY 1
-85/12/09-KING, M.
ANSWER 4.08 (0.00) 1.
Section A of OAP-10103 Att 3 2.
Revtew SO Log 3.
Review LCO status 4.
Review Daily instructions S.
Review Control Room Instructton Change Log 6.
Test and Review Annuciators.
7.
Revtew computer alarms (4 at 0.5 each 2 2.0)
REFERENCE Perry - OAP-0103, Rev.
O, page 17 ANSWER 4.09 (1.00)
A pink dot shall be placed on the affected window.
(1.0) i j
REFERENCE
,I Perry - PAP-1401, Rev.
2, page 10 ANSWER 4.10 (1.00) a.
Locally reset the trip device by pulling the mechanical trip rod to the reset posttion.
(0.5) l b.
Take the RCIC TURBINE TRIP THRT V.
LATCH (!ESt-fS10) to close.
(0.5)
REFERENCE l
Perry - SO!-ES1, Rev.
1, page 11 i
l l
ANSWER 4.11 (1.00) 1.
Reactor Scrammed (0.5)
[
2.
Core Alterations suspended (0.5)
I L
.. _=- -
'i-__'ERCCEQuRC1_ _NCRMAL._ARMQEMAL._EMERGENC1_ANQ PAGE 36 RAQ1QLQG1 CAL _CQEIRQL F
ANSWERS -- PERRY i
-85/12/09-KING.
M.
REFERENCE Perry - ST1-J11-003. Rev.
O, page 5 ANSWER 4.12 (3.00) a.
1.
Arm and depress the Dtvision 1.
2, 3 and 4 Manual Scram pushbuttons and vertfy all control rods inserted.
2.
Place the Mode Switch in the Shutdown posatton.
3.
Trip the turbine Generator.
4.
Verify NMS indicates decreasing power level.
5.
Verify station loads have automatically transferred to the Startup Transformer, otherwise, manually shift station loads to Startup Transformer.
6.
Place the Division 3 Diesel Generator DIESEL CONTROL TRANSTER switch to LOCAL.
(6 required e 0.5 each)
(3.0) i REFERENCE Perry ONI-C61, Rev.
1, pages 1-2 ANSWER 4.13 (1.50)
Operation allowed for training [0.51 when authorized by the Unit or Shift Supervisor (0.51 and under the d i r e c t i o ri a nd in the presence of a Itcensed operator (0.51.
(1.5)
REFERENCE i
Perry PAP 0201. Rev.
1.
Page 6 i
ANSWER 4.14 (1.00) i t.
Dispatcher's name 2.
Time of call J
l 3.
Essence of the conversation Cload request should be written verbatim).
(2 0 0.5 ea = 1.0) i REFERENCE Perry - OAP-0201, Rev.
O.
Page 4 h
\\
f
- R-99 m i'd i u.
(.
e U.S. NUCLEAR REGULATORY COMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
Perry REACTOR TYPE BWR-GE 6 DATE ADMINISTERED: December 10, 1985 EXAMINER:
E. Plettner APPLICANT:
INSTRUCTIONS TO APPLICANT:
Use separate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question.
The passing grade requires at least 70% in each category and a final grade of at least 80%.
% of Category
% of Applicant's Category Value Total Score Value Category 25 25 5.
Theory of Nuclear Power Plant Operations, Fluids and Thermodynamics 2.3 E
25 6.
Plant Design, Control and Instrumentation 25 25 7.
Procedures - Normal, Abnormal, Emergency and Radiological Control 25 25 8.
Administrative Procedures, Conditions and Limitations 19 100 100 TOTALS Final Grade All work done on this exam is my own, I have neither given nor received aid.
Applicant's Signature
CATEGORY 5 - Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics 5.01 Referring to the Boiling Heat Transfer curve Fig 1.0 match the region marked "A" through "E" on the curve with the appropriate mode of heat transfer below:
1.
Nucleate boiling (0.5) 2.
Subcooled boiling (0.5) 3.
Film boiling (0.5) 4.
Transition boiling (0.5) 5.
Force convection (single phase flow)
(0.5) 5.02 Reactor power is being increased on a 50 second period, a.
How long does it take to increase power from 2kw to IMw?
(1.0) b.
What reactivity is associated with the 50 second period?
(1.0) 5.03 Briefly describe the effect of delayed neutrons on the following:
a.
Mean neutron lifetime (1.0) b.
Reactor period (1.0) c.
Neutron flux decay following a scram from full power (1.0) 5.04 Why does a recirculation pump have more NPSH at 100% power than at 10% power? Include the sources of NPSH in your answer.
(2.0) 5.05 The Perry 1 reactor is taken to criticality from a cold condition and then placed on an 80 second positive period.
a.
From control room nuclear instrumentation, how can the operator tell when the heating range has been reached?
(Rod position and recirculation are held constant.)
(1.0) b.
In which of the following intervals was the heating range entered? Explain the reason for your answer.
(Show all work)
(1.5)
Interval 1 - reactor power increased by a factor of 6 in 143.3 seconds.
Interval 2 - reactor power increased by a factor of 3 in 99.0 seconds.
Interval 3 - reactor power increased by a factor of 5 in 128.8 seconds.
(Note:
The intervals may not be in sequence.)
5.06 Define rod shadow.
(1.0) 5.07 What is " pump runout" and why is it an undesirable condition?
(1.0) 5.08 What are two reasons a centrifugal pump should be started with the discharge piping filled and the discharge valve shut?
(1.0) 5.09 Flux shaping is performed for two important reasons.
What are these two reasons?
(1.0) 5.10 Fill in the table concerning BWR thermal limits.
I I
Cause of failure Limiting Condition Thermal limit i
I a.
PLHGR I
l (1.0) b.
MAPLHGR l
l (1.0) c.
MCPR l
l (1.0) 5.11 What is water hammer and how does it affect a piping system?
(1.0) 5.12 The tabulation below illustrates REACTIVITY COEFFICIENT VARIATIONS due to increases in several core parameters.
For each condition (a-f) listed below, INDICATE how the VALUE of that coefficient varies if the indicated parameters are INCREASED.
(Answer witn more negative, unchanged, or less negative.)
(3.0)
CORE PARAMETER MODERATOR CORE FUEL CORE TEMP VOIDING TEMP AGE COEFFICIENT VOID COEFFICIENT (A)
(B)
MODERATOR TEMP (C)
(D)
COEFFICIENT FUEL TEMPERATURE (E)
(F)
COEFFICIENT 2
5.13 A motor driven centrifugal pump is operating at rated flow.
You start closing down the discharge valve. Which of the following statements best describes the parameter changes that will occur with this action?
(1.0) a.
Flow remains constant, discharge pressure remains constant, motor amps increase, net positive suction i
head increases.
b.
Flow decreases, discharge pressure increases motor amps increases, net positive suction head increases.
c.
Flow decreases, discharge pressure increases motor amps decreases, net positive suction head decreases.
d.
Flow decreases, discharge pressure increases, motor amps decreases, net positive suction head increases.
5.14 Boiling water reactors are designed to have "under moderated cores." Which statement best describes under moderated?
(1.0) a.
The ratio of moderator to fuel is such that the temperature and void coefficient will both be the same (both positive or both negative).
j b.
The ratio of moderator fuel is such that increasing moderator density increases Keff.
c.
The ratio of moderator to fuel is such that the amount of under moderation increases during core life.
d.
The ratio of fuel to moderator is such that increasing moderator density will decrease Keff.
END OF CATEGORY l
}
3
CATEGORY 6 - Plant Systems Design, Control and Instrumentation 6.01 a.
Following WHAT MAJOR ACCIDENT would the Emergency Closed Cooling (ECC) System be used to supply the Fuel Pool Cooling and Cleanup System heat exchangers? WHY?
(1.0) b.
Which ECC loop can be operated from the Remote Shutdown Panel?
(0.5) 6.02 In regards to the Perry Fire Protection System:
a.
What two methods are used to maintain the WATER Fire Protection System static pressure greater than 80 psig?
(1.0) b.
How do each of following CO2 Fire Protection System valves fail upon loss of electrical power?
1.
Master Control Valves (0.5) 2.
Selector Valves (0.5) 6.03 If the following alarm was to annunciate (ISO Phase Bus Hydrogen trouble):
a.
What would be your immediate actions if it were not an instrument failure?
(1.5) b.
What would be the cause of the alarm annunciating?
Assume that it was not an instrument failure.
(0.5) 6.04 What are three temperature interlocks associated with the Recirc Pump B temp interlock alarm?
(1.5) 6.05 Following the automatic start of a Diesel Generator six (6) conditions must be satisfied in order for the Diesel Output breaker to close. What are four (4) of the six (6) conditions?
(2.0) 6.06 For each of the RCIC System component failures listed below, state whether or not RCIC will auto inject into the reactor vessel.
--If it will inject, provide one potential adverse effect or consequence.
--If it will not inject, briefly explain why.
Assume no operator actions, and the component is in the failed or misaligned condition at the time RCIC receives an auto initiation signal.
a.
The turbine exhaust valve (F068) is misaligned closed, and the RCIC System receives an auto initiation.
(1.0) b.
The minimum flow valve fails to auto open (stays shut) when the system conditions require it to be open.
(1.0) 6.07 What four signals are provided by the Leak Detection System?
(2.0) 6.08 With regard to the Rod Control and Information System (RCIS):
a.
The operator accidentally selected a rod out of sequence and received a rod block.
He depressed the R0D SELECT CLEAR pushbutton on the Operator Control Module and then attempted to select the correct rod but could not. Why?
(1.0) b.
What indication (s) would the operator see when a ganged rod is:
1.
more than one (1) notch out of alignment while driving?
(0.5) 2.
more than two (2) notches out of alignment while stationary or moving?
(0.5) c.
A control rod drive (CRD) is bypassed by the " Drive Bypass" function on the Rod Gang Drive System.
Under what normal (not scram) condition (s) can the CR0 move while in this bypassed condition?
(0.5) 6.09 In regard to the Feedwater Control System:
a.
Why is Level Programming" necessary?
(0.75) b.
Is " Level Programming" continuously done throughout a power increase to full power? Explain.
(0.75) 6.10 List the trip functions and trip actions with normal setpoints that are associated with the intermediate range monitors (IRMs).
Four required for full credit.
(2.0) 6.11 List the basis for each of the following RPS trip signals.
1.
Hi RPV pressure (1.0) 2.
Hi RPV level (0.5) 3.
MSIV closure (0.5) 4.
MSL Hi Rad (0.5) 5.
SDV Hi level (0.5) 6.12 While operating at 100% power, the plant suffers a complete loss of instrument air.
How will valve operations be affected (open, close, or fail as is) for the following valves?
(3.0) l 2
1 i
a.
Feedwater pump recirc flow control valves b.
NCC surge tank make up valves c.
MSIVs d.
Temp control valves for TBCC HXs e.
Scram valves f.
Flow control valve (s) for CRD system END OF CATEGORY l
3 i
CATEGORY 7 - Procedures, Normal, Abnormal, Emergency and Radiological Control 7.01 According to the Perso.7nel Radiation Protection Requirements:
a.
What is the administrative whole body dose limit (s) for an individual 20 years or older, who has a completed lifetime occupational exposure history record?
(0.5) b.
Based on 10 CFR 20, what is the maximum allowable accumulated whole body exposure for a 38 year old person?
(0.5) c.
When taping protective coveralls, when wearing two pairs of coveralls or when a wet suit is worn over one pair of coveralls, only the outer pair normally need taping.
(TRUE or FALSE)
(0.5) d.
What are the whole body dose limits for lifesaving actions?
(0.5) e.
What are the whole body dose limits when immediate action is required to prevent serious injury?
(0.5) 7.02 What are an operators immediate actions for a stuck
]
open SRV?
(3 required for full credit)
(3.0) 7.03 According to your turbine and/or generator trip procedure your immediate actions require you to PERFORM one action and verify that five (5) others occur.
a.
What is the first action the operator is required to 1
PERFORM?
(0.5) b.
The operator is required to verify five automatic actions occur; one of which is to verify that the Control, Main l
Stop, and Intermediate valves shut.
What are the other four (4) actions?
(2.0) 7.04 If a control room evacuation were required according to ONI-C61 " Evacuation of the Control Room," the reactor operator must perform six (6) things before he leaves. What are these six (6) things?
(3.0) 7.05 While maintaining hot shutdown, Reactor Engineering informs you that surveillance testing on the RHR shutdown cooling mode loops need to be performed.
a.
As the Supervisor, can you permit this surveillance test to take place? Justify your answer.
(1.0)
b.
WhMe performing the test, the operating RHR pump trips
.. -"'d
'd will not restart.
State your actions.
(1.0)
- 7. v i
- tions are performed upon confirmation (1.5) 6 7.07 ONI-N36 " Loss on
'er Heating" states that the immediate s
action would be to reou.:e recirculation flow.
The first subsequent action is to insert CRDs.
a.
Of the two actions above, which is more likely to prevent a scram? Explain why.
(1.0) b.
Why is each action performed?
(1.0) c.
If a scram were to occur, what would be the cause?
(0.5) 7.08 What are your two immediate actions on the loss of DC Bus D-1-A (non-divisional system A)
(1.5) 7.09 What are your immediate operator actions (three required for full credit) following a RCIRC Pump A bearing oil level 10.
alarm?
(1.5) 7.10 Perry has an ALARA program that involves all station personnel.
The program is based on four relatively simple concepts or principles.
What are these four concepts or principles and provide a brief explanation of each.
(2.0) 7.11 Control rods can be declared inoperable because of mechanical interference of friction.
List three (3) other reasons why a control rod may be declared inoperable.
(1.5) 7.12 What are an operators immediate actions on a complete loss of the service water system in accordance with ONI-P41?
(1.5)
END OF CATEGORY 2
CATEGORY 8 - Administrative Procedures, Conditions and Limitations 8.01 With regard to the Emergency Planning Instruction:
a.
In which of the four (4) emergency classes would you place the following:
(2.5) 1.
Transport of a contaminated individual to an offsite hospital 2.
Tornado striking facility 3.
Control room evacuation with shutdown controlled at Remote Shutdown Panel 4.
A 7 gpm increase in unidentified leakage within the last 4 hrs
)
i " ' '
5.
An ATWS ( o s s...,,.
- t. P e de'-
b.
Concerning the Operations Support Center (OSC) 1.
Who is in charge of the OSC?
(0.5) 2.
Where is it located?
(0.5) 3.
Under what condition (s) is it activated?
(0.5) 8.02 Per PAP-0512, Radiation Work Permits, a RWP shall be initiated for work activities associated with the existence or anticipated occurrence of any one of eight (8) conditions.
List five (5) of these eight conditions.
(2.5) 8.03 Per PAP-0205, Operability of Plant Systems a.
List two (2) conditions that would allow independent verification requirements to be waived.
(1.0) b.
Who grants this waiver?
(0.5) 8.04 List and/or describe three situations that would require filling out a potential LC0 tracking sheet.
(3.0) 8.05 a.
What is the minimum number of people required for the fire brigade?
(0.5) b.
Who by title make up the fire brigade?
(1.0)
.o 8.06 PAP-1401, Equipment Tagging, addressed the control and use of five different tags.
Identify each of the tags and give a brief description of its use at Perry.
(2.5) 8.07 Regarding shift relief and turnover at Perry Plant 0AP-0103 a.
When must the Shift Technical Advisor (STA) be present during Shift Supervisor turnover?
(0.5) b.
WhattwomajorthingsmusttheShiftSupervisor do prior to accepting or turning over the watch?
(1.0) 8.08 Under what conditions may a licensed operator leave the horseshoe area without relief?
(1.0) 8.09 What is the definition of the following:
a.
Operating Condition (0.5) b.
Standby Readiness Condition (0.5) c.
Secured Status Condition (0.5) 8.10 What is the pressure limit at which you must have a motor driven or turbine reactor feedpump running?
(0.5) 8.11 All drywell penetrations required to be closed during an accident condition must meet one of two criteria. What are these two criteria?
(2.0) 8.12 What is the rated thermal power in MWTs according to your tech specs?
(0.5) 8.13 Under what conditions is suppression pool temperature allowed to be above the 90 degree max average? (Three required for full credit.)
(3.0)
END OF CATEGORY END OF EXAM 2
fki #['k t
I wn.a.
Urh t
i ANSWERS - CATEGORY 5 - Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics 5.01 1.
c (0.5) 2.
b (0.5) 3.
e (0.5) 4.
d (0.5) 5.
a (0.5)
Ref.:
Perry Thermal Sciences, p. 9-6 5.02 a.
P = Poe /T (1.0) t t = T in P/Po 1000 t = 50 in 2
t = 310.7 sec b.
T = B p/Lp (1.0)
T = B/1 + LT T =.0075/(1 + (.1)(50))
T =.0013 delta k/k Ref. :
General Reactor Theory 5.03 a.
Delayed neutrons increase the mean neutron lifetime from l'*)
approximately 1 = 1x10 4 seconds to 1 = (1-B) +
BT =.0976 seconds provided reactivit is less that B.
b.
In a prompt reactor, T = 1/p, while in a delayed reactor, Q.0)
T = (B p)/Lp = (B p)T/p.
For a reactivity addition less than B, the delayed period is considerably longer than the prompt period.
c.
Following the prompt drop, neutron level in the core is (l.o}
sustained by the decay of fission product precursors.
The shortest lived precursors cause power to decrease fairly rapidly as they decay.
Oecay of the longest lived l
precursor, Br 87, limits the final rate at which power 4
decreases to a -80 second period.
l Ref. :
Perry Nuclear Reactor Operations, p. 4-34
5.04 Recirc pump NPSH at power >20% is primarily dependent on Feedwater (FW) Flow Subcooling (0.5).
There is substantially more FW Flow at 100% than at 10% (0.5).
In addition there is proportionately more cool FW Flow than Hot Return Flow from separators and dryers at the higher power (0.5).
Subcooling at 100% is approximately 20 degrees F (0.5).
Ref.:
Fluid Theory 5.05 a.
Operator can notice that period has become longer and that power change on IRMs, SRMs is leveling off and turning around.
(1.0) b.
(From P = Poe /T t
T=
t Interval 2 (0.5):
4 In P/Po the period has lengthened from 80 seconds.
The other intervals have 80 second period (1.0)
(1.5)
Ref.: General Control Room Indications; Perry, Intro to NR Operations, pgs. 4.18-4.19 5.06 Rod shadow is an effect in which the repositioning of one control rod changes the reactivity worth of adjacent rods or causes a change in indicated power when actual power level has not changed.
(1.0)
Ref. :
Perry Nuclear Reactor Operation, pgs. 7-12 5.07 Increase in pump flow due to loss of backpressure (0.5).
The increased flow causes the motor to draw more current and possibly damage the motor winding (0.5).., % y. h, 4
<m m.
4,.,..% o, Ref.: NRC Exam Bank 5.08 Water hammer; excessive starting current; runout (2 of 3 necessary for full credit)
(1.0)
Ref.:
NRC Exam Bank 5.09 a.
Prevent exceeding thermal limits (0.5) b.
Optimize fuel burnup (0.5)
Ref.: Perry Nuclear Reactor Operation, pgs. 9-11 5.10 a.
PLHGR fuel pellet expansion 1% plastic strain in (1.0) clad b.
MAPLHGR decay and stored heat 2200F clad temperature (1.0) after LOCA c.
MCPR OTB transition boiling (1.0)
Ref. :
Perry Thermal Science, pgs. 12-6 and 7 2
5.11 Dissipation of fluid momentum by sudden flow stoppage characterized by a pressure shock wave which can result in damaged pipes.
(1.0)
Ref.:
Perry Thermal Science, pgs. 14-17 and 18 5.12 a.
More negative (0.5) b.
More negative (0.5) c.
More negative (0.5) d.
Less negative (0.5) e.
More negative (0.5) f.
Less negative (0.5)
Ref.:
Standard Nuclear Theory 5.13 d (1.0)
Ref.:
NRC Question Bank 5.14 b (1.0)
Ref.:
l'RC Question Bank END OF CATEGORY 1
3
ANSWERS - CATEGORY 6 - Plant Systems Design, Control and Instrumentation 6.01 a.
LOCA (0.5).
Nuclear Closed Cooling is isolated from the Fuel Pool Cooling and Cleanup System (0.5).
b.
Loop A (0.5)
Ref.:
SDM, P42, pgs. 10 and 17 6.02 a.
Pressured maintenance tank (0.5) and a jockey pump (0.5).F?'
U+
M1 b.
1.
OPEN (0.5) 2.
CLOSED (0.5)
Ref.:
SDM, P54(WTR), p. 2; P54(C02), p. 29 tem r 1 e.01 m. n gt 6.03 a.
Immediate actions as listed are:
1.
Determine whether the alarm is due to high hydrogen or analyzer malfunction.
2.
If hydrogen concentration is above 40% of the lower flammability limit, perform the following actions:
(0.5)
(a) Trip the generator (0.5)
(b) Conduct a Fast Reactor Shutdown, if necessary (0.5)
NOTE: ONLY PART TWO 0F THE ANSWER IS GRADED BECAUSE THE QUESTION SPECIFIES THAT THE ALARM IS NOT DUE TO AN INSTRUMENT FAILURE.
b.
The cause of the alarm to annunciate would be the following:
1.
25% of the lower flammability limit for hydrogen is reached.
(0.5) 2.
Conbustible Gas Vapor Analyzer inoperable.
NOTE: ONLY PART ONE OF THE ANSWER WAS GRADED BECAUSE THE QUESTION SPECIFIES THAT THE ALARM IS NOT DUE TO AN INSTRUMENT FAILURE.
Ref.: OM6, ARI-R13-1 6.04 a.
Temperature difference between reactor vessel bottom drain and reactor steam dome temperature is greater than 100 degrees F.
(0.5) b.
Temperature difference between Recirculation Pump AS suction temperature and reactor steam dome temperature is greater than 50 degrees F.
(0.5)
c.
Temperature difference between the two loop suction lines is greater than 50 degrees F.
(0.5)
Ref.: ARI-833-35 6.05 1.
Engine speed greater than 425 RPM 2.
Up to rated voltage 3.
Preferred and alternate breakers open 4.
Low bus voltage 5.
Breaker racked in 6.
No bus lockout (0.5 ea)
Ref. :
Perry Lesson Plan, Standby Diesel Generator and Auxiliary, p. 8 6.06 a.
Will not inject (0.25); steam isolation valve (F045) is interlocked closed if the exhaust valve (F068) is closed (0.75).
b.
Will inject (0.25); possible damage to pump from overheating or at low flows (0.75).
Ref. :
Perry Lesson Plan (E51) RCIC 6.07 1.
Main steam line tunnel and pipe routing in Turbine Building high ambient temperature and differential temperature; (0.5) 2.
RWCU System high differential flow; (0.5) 9 3.
RWCU System area high ambient temperature and differential temperature, and (0.5) 4.
RHR System area high ambient temperature and differential temperature.
(0.5)
Ref.:
Perry Lesson Plan B21B, p. 33 NSSSS 6.08 a.
Depressing R0D select clear inhibits further rod selection unless re-depressed.
(1.0) b.
1.
"NEXT" on Rod Display Module Gang Position display (0,5) 2.
" Misaligned" on Rod Display Module Gang Position display (0.5) c.
If " gang" mode is selected (0.5)
Ref.:
Perry Systems Description Manual - C11(RCIS),
pgs. 26, 30 and 43 2
6.09 a.
At high steam flows a lower actual level in the vessel is required to maintain a constant carryover.
(0.75) b.
No.
Biasing does not occur until >45% steam flow.
(0.75)
Ref.:
Feedwater Control, N27 6.10 IRM Downscale-5/125 of scale = rod block (0.5)
IRM High Flux-108/125 of scale = rod block (0.5)
IRM Inop.-low high voltage
-module unplugged
-mode switch not in operate (0,5)
IRM High-High Flux-120/125 of scale-scram (0.5) se m w., e..k../ & A t
,..A.1
- c. t s iw k.
Ref.:
Nuclear Instrumen ation
,7 4,A g, g.)
e som CSI(.itrvi), CaJ.Is 9.2 8 6.11 1.
Pressure increase adds positive reactivity (0.5) also could cause breach of fission product barriers (0.5).
2.
Offset positive reactivity addition by cold water addition (0.5).
3.
Anticipates pressure and flux transients following an MSIV closure (0.5).
4.
Detects gross fuel cladding failure (0.5).
5.
Scrams the reactor while a sufficient volume exists to do so (0.5).
Ref. :
Perry Exam Bank No. 0305 6.12 a.
Open b.
Closed c.
Closed d.
As is e.
Open f.
Closed (0.5 ea)
Ref.:
Perry Exam Bank No. 0320 END OF CATEGORY 3
ANSWERS - CATEGORY 7 - Procedures, Normal, Abnormal, Emergency and Radiological Control 7.01 a.
1250 arem/ quarter " * " *
(0.5) b.
5 (N-18) = 5 (38-18) = 5 x 20 = 100 rem (0.5) c.
False (0.5) d.
100 rems (0.5) e.
25 rems (0.5)
Ref.:
Perry PAP-0208, pgs. 7, 9, 16, 13; PR-2, p. 4; and PAP-0208, p. 13, respectively 7.02 a.
Attempt to close the SRV by taking its control switch from AUTO to OPEN and back to AUTO.
(1.0) b.
If the SRV remains open, take its control switch from AUTO to 0FF.
(1.0) c.
If the SRV remains open, deenergize the SRV solenoids by removing the applicable control power fuses at Panel 1H13-P628 and P631 (see Attachments 1 and 2).
(1.0)
Ref.: ONI-821-1 7.03 a.
Trip the main turbine b.
1.
Generator brks open 2.
Normal supply brks trip 3.
Startup supply brks close 4.
Generator field brks trip (0.5ea)
Ref.:
Perry ONI-N32, p. 2 7.04 1.
Arm and depress div. 1, 2, 3 and 4 Manual Scram pushbuttons and verify all control rods inserted.
2.
Place the Reactor System Mode Switch in the " Shutdown" position.
3.
Trip the turbine generator.
4.
Verify neutron monitors indicate a decreasing power lever.
5.
Verify station loads have automatically transferred to the Startup Transformer on tripping the turbine generator.
6.
Place the div. 3 diesel generator " Diesel Control Transfer" switch to local.
(0.5 each) Six required for full credit.
Ref.: ONI-C61, Evacuation of the Control Room
7.05 a.
Yes (0.25).
One RHR shutdown cooling mode loop may be inop. for up to two (2) hours for surveillance testing, providing the other loop is in operation (0.75),
b.
Immediately initiate corrective action to restore one ASAP (0.5). Within one (1) hour establish coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once an hour (0.5).
Ref.:
Perry Exam Bank, No. 0217 7.06 a.
Sound the " Fire Alarm" and announce the location of the
("O
- fire, b.
The Shift Supervisor shall direct SAS to request response (0 8) by the offsite fire company by telephoning the Perry Township fire emergency number 259-3664.
c.
The Fire Brigade shall report to the scene.
(* O Ref.:
Perry ONI-P54, p. 2 7.07 a.
Inserting a CRD will be more likely to prevent a scram because it will bring you farther away from the flow biased scram setpoint.
(1.0) b.
You decrease recirc flow to decrease power so the effects of a scram Would be less, and by decreasing power you decrease steam flow, thereby decreasing feed flow.
CRD insertion is performed to increase the margin between the flow biased scram setpoint and actual power, and to prevent exceeding any local thermal power.
(1.0) c.
High Flux - APRM High OR Flow Biased APRM Scram (0.5)
Ref.:
Perry ONI-N36 and Standard Nuclear Principles 7.08 a.
Verify that Reactor Narrow Range Level Channel "A" is selected.
(0.5) b.
Transfer RFPT B gov mode control to manual.
(0.5)
Adjust feedwater flow with the RFPT B manual speed control to the normal operating range and match RFPT A speed.
(0.5)
T Ref.:
Perry ONF-R42-4, p. 3 7.09 1.
Reduce flow in both Recirculation loops to 50% of rated flow or less.
(0.5) 2
2.
Monitor Recirculation Pump A parameters and check for a loss of lubrication to the pump.
(0.5) 3.
If the loss of lubrication is confirmed by high bearing temperatures and/or high vibration, secure the Recirculation Pump and implement ONI-833-2, Loss of One or Both Recirculation Pumps.
Ensure compliance with Technical Specification (later), Recirculation Loops.
(0.5)
Ref.:
Perry ARI-B33-12 7.10 1.
Design or modification to provide engineered controls on exposure.
(0.5) 2.
Time minimizing time in radiation areas.
(0.5) 3.
Distance maintaining as much distance as possible between the worker and the radiation source.
(0.5) 4.
Shielding provide shielding of the source or the worker.
(0.5)
Ref.:
Perry PAP-0118, p. 2 7.11 1.
Slow scram insertion times.
2.
Associated accumulator inoperable.
3.
Rod uncoupled and not able to recouple.
4.
Position indication faulty.
Any 3 0 0.5 ea.
Ref.:
Perry Exam Bank, No. 0301 7.12 a.
Start the standby Service Water pump (0.5) b.
Complete a fast reactor shutdown (0.5) c.
Transfer the Reactor Recirculation pumps to slow speed (0.5)
Ref.:
Perry ONI-P41 END OF CATEGORY 3
ANSWERS - CATEGORY 8 - Administrative Procedures, Conditions and Limitations 8.01 a.
1.
Unusual Event (0.5) 2.
Alert (0.5) 3.
Alert (0.5) 4.
Unusual Event (0.5) 5.
Site Area Emergency (0.5)
Re f. :
Perry EPI:
EPI-A1, pgs. 7, 49, 7, 9 (with T.S. 3.43.2,
- p. 8), and 6, respectively b.
1.
Maintenance Coordinator or Maintenance Supervisor (0.5) 2.
On the 599' and 574' elevation of Control Complex adjacent to the Rod Controlled area control point and the Health Physics / Chem. areas (0,5) 3.
At an Alert or at discretion of Emergency Director (0.5)
Ref.:
Perry EPI:
EPI-A7, p. 2, 1 and 3, respectively 8.02 1.
Rad levels greater than or equal to 100 mrem /hr 2.
Removable contamination a.
greater than or equal to 1000 dpm/100cm2 beta gamma b.
greater than or equal to 100 dpm/100cm2 Alpha 3.
Airborne with total isotopic MPC ratio greater than or equal to 1 4.
Neutron radiation areas 5.
Handling of licensed byproduct material 6.
Entry into Containment and/or drywell 7.
As required by Plant HP or HP Supervisor 8.
Work involving the opening of radioactive or potentially radioactive systems Any 5 9 0.5 ea Ref.:
Perry PAP-0512 8.03 a.
1.
rad exposure greater than 25 man-millirem per lineup (0,5) 2.
lineup requires entry into a high radiation area (0.5) b.
Unit Supervisor (US)
(0.5)
Ref.:
Perry PAP-0205, p. 1 8.04 1.
Operational condition decreases which results in LCO action statement no longer applying; however, increase in operation condition would return you to Active LCO.
(1.0)
2.
Any T.S. related component / parameter are found to be inoperable or out of limits, even though they are not required to be operable in present operational condition.
(1.0) 3.
T.S. components are inoperable, even if you meet minimus T.S. requirements.
(1.0)
Ref.:
Perry 0AP-1701, p. 4 8.05 a.
5 members (0.5) b.
Supervising operator (0.5) 4 security personnel (0.5)
Ref.:
Perry PAP-0110, p. 4 6.2 8.06 a.
Red tag - warns all personnel that the device must not be operated (0.5) b.
White tag - permits the operation of a device by an authorized representative of a specific element (0.5) c.
Yellow tag - warns all personnel that a grouc,d or grounds may have been established on a circuit (0.5) n Wa
- d.
PRD Jurisdictional tag green in color and are used in all areas that have been transferred to the operations section e f=i.*4 AM.
(0.5) e.
Information tag - manila-buff in color and are used to provide additional information on guidance of a temporary nature.
(0.5)
Ref.:
Perry PAP-1401
& Tc w *ar 8.07 a.
When the reactor is in Modes 1, 2 or 3 (0.5) b.
Complete the SS relief / turnover checklist 0AP-0103-1 (0,5)
Provide any additional information not covered on the checklist (0.5)
Ref.:
Perry 0AP-0103, p. 3 f ' (g,,}
h Gm7*["/ (0.5) 8.08 a.
Verify receipt of an annunciator alarm (0.5) b.
Initiate corrective actions on back panels Re f. :
Perry PAP 016, p. 5 6.3.3 d= p.,.4<.a..
b Tu -c8 I c h 1'AP ello
&^
^^j: - l :)
2
8.09 a.
It shall be performing or capable of performing its intended function in the required manner as specified in the appropriate System Operating Instruction.
(0.5) b.
It shall be ready to automatically perform its intended function in the required manner as specified in the approorfate System Operating Instruction.
(0.5) c.
It shall be secured as specified in the appropriate System Operating Instruction.
Ref. :
Perry 101-4, pgs. I and 2 8.10 300 psig (0.5)
Ref.:
101-1, p. 16 8.11 a.
Capable of being closed by an OPERABLE automatic isolation system, or (1.0) b.
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as provided in Table 3.6.4-1 of Specification 3.6.4.
(1.0)
Ref.:
Perry T.S., p. 1-2 8.12 3579 MWT (0.5)
Ref.:
Perry T.S., p. 1-7 0
8.13 105 F during testing which adds heat to the suppression pool.
(1.0) 0 110 F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.
(1.0) 0 120 F with the main steam line isolation valves closed following a scram.
(1.0)
Ref.:
Perry T.S. 3.6.3.1 END OF CATEGORY 3
-