ML20247C050
| ML20247C050 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/08/1989 |
| From: | Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20247C036 | List: |
| References | |
| 50-285-OL-89-01, 50-285-OL-89-1, NUDOCS 8905240337 | |
| Download: ML20247C050 (67) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _
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- 4. p APPENDIX U.S. NUCLEAR REGULATORY COMMISSION REGION IV Operator Licensing Exam Report: 50-285/0L89-01 Operating License: DPR-40 Docket No: 50-285 Licensee: Omaha Public Power District (OPPD) 1623 Harney Oniaha, Ne 68012 Facility Name:
Fort Calhoun Station (FCS)
Examination at:
Fort Calhoun Station Chief Examiner:
A F!$f3f J.'L. Pellet, Chief Date ~
Operator Licensing Section, Division of Reactor Safety Approved by:
5[(ffi J.tl. Pellet. Section Chief, Date '
Operator Licensing Section, Division of Reactor Safety Summary NRC Administered Examinations Conducted During the week of April 10, 1989 (Report 50-285/0L89-01)
NRC administered examinations to two reactor operators (RO) applicants.
Both applicants passed all portions of the examination and have been issued the appropriate license.
8905240337 890509 PDR ADDCK 05000295 V
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DETAILS 1.-
Persons Examined SRO 3.
Total License Examinations:
Pass -
0 2,
2 Fail -
0 0
0 2.1 Examiners-John L. Pellet 3..
Examination Report Performance results for-individual examineas are not included in this report as it will be placed in the NRC Public Document Room and these results are not subject to public disclosure.
a.
Examination Review Comment / Resolution In general,' editorial. comments or changes made during the examination, or subsequent grading reviews are not addressed by this resolution _section. This section reflects resolution ~of substantive comments made by FCS. The only-comments addressed in this section are those which were not accepted for incorporation into the examination and/or answer key. Those comments accepted are incorporated into the master.. examination key, which is included in this report. Comments may.be~ paraphrased for brevity. The full text of the consnents is attached.
(1.09)
Delete the question since the criteria supplied in the cited reference do not match any answer given.
J Response A basic understanding of natural circulation, from a theoretical standpoint, is sufficient to determine that the three distractors are not correct indicators of natural circulation.
(1.18)
Since the question states a centrifugal pump but does not
~
provide'the correct answer of eye of the impeller, accept also the top of the inlet as approximately correct.
Response.- For future reference the question will be revised to specify an axial pump.- However, while the eye of the impeller would be a correct answer for the question asked, it was not among the choices given. Of the answers given, only the original key is correct. The answer requested is simply incorrect.
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(1.20)
Delete the question since the difference is primarily in the predicted correspondence.
Response The reference cited supports the original key answer. The fact that this. difference was not accurately predicted is L
insufficient to delete the question.
(3.03)
Accept equally correct answers for-part (e).
Response The rod block signal generates the power interrupt alarm per the cited reference. Answers which generate a rod
~
block and hence the alarm would only be acceptable if rod block were not an answer given.
(3.10)'
For part (a) accept either PPLS or CPHS since either coincident with SIRWT low level will cause RAS.
Response -Part (a) specifies that two answers are required'for full credit. Therefore, the request to accept only on is rejected.
4 (3.16)
Accept as also correct RCS pressure and hot leg temperature.
Response Material supplied only indicated that the requested parameters are affected.
It does not contradict the cited reference that supports the original key.
(3.26)
Acceptalsoanswer(b)duetosystemmodification.
Response Given two correct answers question is deleted due to poor discrimination capability.
b.
Site Visit Sumary At the end of the written examination administration, the facility licensee was provided a copy of the examination and answer key for the purpose of commenting on the examination content validity. -It was explained to the facility licensee that regional policy was to have examination results finalized within 30 days. Thus, a timely response was desired to attain this goal.
c.
Master Examination and Answer Key Master copies of the FCS license examination and answer key is attached. The facility licensee coments which have been accepted are incorporated into the answer key.
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d.
Facility Examination Review Comments-
< The facility licensee comments'regarding the written examination are attached. Those comments which were not acceptable for-incorporation into the examination answer key have been addressed in the resolution section of this report.
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U. S.
NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 4
FACILITY:
FT. Calhoun REACTOR TYPE:
PWR-CE DATE ADMINISTERED:
89/04/10 INSTRUCTIONS TO CANDIDATE:
'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%.
Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY
% OF' CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 24.00 25.00 1.
REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) 25.00 26.04 2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
4 47.00
_48.96 3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
96.00 TOTALS FINAL GRADE 1
l All work done on this examination is my own.
I have neither given nor received aid.
1 i
Candidate's Signature j
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t 1.
REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 2
(7,%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
QUESTION 1.01 (1.00)
Which one of the answers below describes why Technical Specifications
-impose both an upper (positive) and lower (negative) limit to the magnitude of the Moderator Temperature Coefficient?
(1.0) a.
The upper limit is required to ensure reactor stability late in core life.
The lower limit is required to limit the impact of a steam line break early.in core life.
b.
The upper limit is required to ensure reactor stability early in core life.
The lower limit is required to limit the impact of a steam line break late in core life.
c.
The lower limit is required to ensure reactor stability early in core life.
The upper limit is required to limit the impact of a steam line break late in core life.
d.
The lower limit is required to ensure reactor stability late in core life.
The upper limit is required to limit the impact of a'ateam line break early in core life.
f ANSWER 1.01 (1.00)
B.
REFERENCE FCS RXTH 007-005-03 192004K106
..(KA's)
QUESTION 1.02 (1.00)
Why does the reactor continue to generate significant amounts of heat a.
following a reactor shutdown?
(0.5)
.b.
Why is the power level represented by decay heat not indicated by the nuclear instruments?
(0.5)
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1.
REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 3
(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAQ1 O
ANSWER 1.02 (1.00)-
a.
Decay heat is produced from the decay of fission products (fragments) formed during. power operation.
(0.5) b.
The bulk of the decay heat is produced fron fission products which do not emit neutrons (alpha, beta, or gamma emitters) as part of.the decay process.
(0.5)
REFERENCE FCS RXTH 007-005-04 192008K127
..(KA's) f i
I QUESTION 1.03 (2.00).
MATCHING.
Match the reasons listed to the appropriate rod insertion limits,.
Each limit may have one or more reason and each reason may be used more than once or not at all.
(2.0)
LIMIT REASON i
a.
- 1. Assures compliance with power distribution LCOs
- 2. Limits the effects of Xe redistribution on peaking
)
b.
Short term
- 3. Assures peaking factors within limits j
4.
Limits consequences of a rod ejection accident l
c.
Long term 5.
Assures compliance with tech spec LSSS
- 6. Assurec minimum shutdown margin maintained ANSWER 1.03 (2.00) a.
3, 4, 6 b.
2 l
c.
1, 5
(6 answers @ 0.333 ea.)
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'1.
REACTOR PRINCIPLES (7%)' THERMODYNAMICS Page 4
l (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) o REFERENCE FCS LP 7-5-3, p.
47-49
'192005K115
..(KA's)
QUESTION 1.04 (2.00) l MATCHING.
Match the times listed'with'the xenon related parameters listed below.
Times may be used more than once or not at all.
(2.0)
]
XENON PARAMETER TIME a.
Reach equilibrium after large step power change 1.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- b. Peak Xenon after reactor trip from 40% power 2.
.10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />
- c. Xenon free after trip from 100% power 3.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- d. Lowest worth after.large step power increase 4.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> e.
Reach previous equilibrium after trip from 100%
E.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
. ANSWER 1.04 (2.00) a.
4 b.
1 c.
5 d.
1 f.
e.
3 (5 answers @ 0.4 ea.)
REFERENCE 1
97 1
j 192006K112 192006K113
..(KA's)
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L 1.' REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 5
(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXA41
- QUESTION.
1.05 (1.00).
~Which one of the following factors is most responsible for the decrease
.(negative slope) in inverse boron worth (IBW) over core life?
(1.0) a.
ModeratorLtemperature decreases.
b.
Neutron flux increases.
c.
Fission product inventory increases.
d.
Boron concentration decreases.
fANSWER 1.05 (1.00)
D.
60-62 192007K104
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' REACTOR PRINCIPLES (7%) THERM 04XNAMXQS Page 6
(7%) AND COMPON2H7S (11%) (FUNDAMENTALS EKAH1 QUESTION 1.06 (1.00)
Which one of the answers below describes how indicated reactor power will compare with actual reactor power when nuclear instrumentation adjustments are made using calorimetric data with the following errors.
(1.0)
CASE 1:
Actual feed temperature is less than indicated feed temperature.
I CASE 2:
Steam quality is less than the value assumed for the calculation.
a.
For case 1, indicated power will be less than actual.
For case 2, indicated power will be less than actual.
b.
For case 1, indicated power will be greater than actual.
For case 2, indicated power will be less than actual.
c.
For case 1, indicated power will be less than actual.
For case 2, indicated power will be greater than actual.
d.
For case 1, indicated power will be greater than actual.
For case 2, indicated power will be greater than actual.
ANSWER 1.06 (1.00)
C.
REFERENCE FCS 007-007-24 193007K106
..(KA's)
. QUESTION 1.07 (1.00)
Fill in the blanks in the following statement regarding HOW and WHY steam generator (SG) pressure will vary for a constant power and Tave as an increasing number of tubes are plugged.
Blanks may contain one or more j
words or numbers.
SG temperature will decrease because the
__(a)__ (0.5) decreases.
Steam generator pressure will also decrease because the __(b)__ (0.5).
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1.
REACTOR PRINCIPLES'(7%) THERMODYNAMICS Page 7
(7,%) AND COMPONENTS (11%) (FUNDAMENTALS EYA41 ANSWER-1.07 (1.00) a.
total heat transfer area (0.5) b.
secondary side @ saturation conditions OR temperature decreases (0.5)
REFERENCE FCS 007-007-18 193005K103
..(KA's)
QUESTION 1.08 (1.00)
A relief valve on a pipe opens at 885 psig. The temperature of the steam exhausted to the atmosphere is 320 deg. F. The fluid within the pipe is saturated steam. Using the steam tables provided, what is the approximate temperature of the fluid within the pipe, in the immediate vicinity of the relief valve?
(Select one response from below.)
a.
530 deg. F b.
400 deg. F c.
320 deg. F
'd.
212 deg. F ANSWER 1.08 (1.00)
A (Saturated steam at 885 + 15 psia.) (1.0)
REFERENCE EQB GENERIC FUNDAMENTALS FOR CE PWR CE Steam Tables FCS LP 7-7-17, LO 2.3-1 193004K115
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- 1 '. ' REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 8
(7,%) AND COMPONENTS'(11%) (FUNDAMENTALS RYA 41 4
QUESTION 1.09 (1.00)
From the following possible combinations of parameters, select the one combination that indicates natural circulation cooling.
(1.0)
RCS SG Thot Core Exit Teold Subcooling Pressure Thermocouple a.
40 F Stable Decreasing Increasing Tsat for SG Press
-b.
30 F Decreasing Decreasing Stable Stable c.
20 F Stable Tsat for Decreasing Stable RCS Press d.
20 F Decreasing Stable Decreasing Tsat for SG Press ANSWER 1.09 (1.00)
D.
(1.0) e REFERENCE E0P-20, P. 97 193008K122
..(KA's)
QUESTION 1.10 (1.00)
Which one of the below requires the most heat removal during condensation?
(assume steam is of equal quality)
.a.
two pounds of steam at 1200 psig.
b.
two pounds of steam at 600 psig.
c.
one pound of steam at 300 peig.
d.
one pound of steam at 0 psig.
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REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 9
- ( 7,% ) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
ANSWER-1.10 (1.00) i B'(1.0)-
l REFERENCE EQB GENERIC. FUNDAMENTALS FOR CE PWR steam tables FCS LP 7-7-16, LO 1.6-1 j
193003K125
..(KA's)
'l QUESTION 1.11 (1.00)
Which one of the effects below would occur first (at the lowest l
temperature) if core thermal limits were exceeded due to an excessive local power peaking factor?
(1.0) a.
Film boiling.
i b.
Zirconium-water reaction.
c.
Fuel melting.
d.
Clad melting.
ANSWER 1.11 (1.00)
A.
8.1-3, 4
193009K105
..(KA's)
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REACTOR PRINCIPLES (7%) THERMODYNAMIGE-Page 10 (7,%) AND COMPONENTS (11%) (FUNDAMENTALS EYAM)
QUESTION 1.12 (1.00)
Fill in the blanks in the following definition of Pressurized Thermal Shock.
Each blank may consist of one or more words or numbers.
(1.0)
Pressurized Thermal Shock requires a cooldown of the RCS with a decrease in
. average BCS temperature of at least __(a)__ (0.5) for a duration of at
~1 east 10 minutes followed by __(b)__ (0.5).
ANSWER 1.12 (1.00) a.
100 deg's F (0.5) b.
repressurization of the RCS (0.5) l REFERENCE FCS LP 7-7-25, p.
10.1-16 193010K106
..(KA's) l QUESTION 1.13 (1.00) l L
Which one the following describes dide Range Log Channel indication I
during a partial core uncovery compared to the indication just PRIOR to I
core uncovery (uncovered / covered)?
(1.0) l l
a.
10%.
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b.
50%.
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c.
100%.
1 d.
200%.
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l ANSWER-1.13 (1.00) l d'
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REACTOR PRINCIPLES (7%)' THERMODYNAMICS Page il f12%)-AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
REFERENCE L
103 191002K117
..(KA's) 1 l
l QUESTION 1.14 (1.00) l Which one of the following answers describes how RCP
'A' motor amperage will vary during the operation described in each case below.
(1.0)
CASE 1:
Running with two (2) other RCPs when the fourth RCP is started.
CASE 2:
Running with three'(3) other RCPs when the reactor is heated to mode 3.
a.
For case 1, amperage will decrease and for case 2, amperage will increase.
b.
For case 1, amperage will decrease and for case 2, amperage will
- decrease, c.
For case 1, amperage will increase and for case 2, amperage will increase.
d.
For case 1, amperage will increase and for case 2, amperage will decrease.
ANSWER 1.14 (1.00)
B REFERENCE EQB GENERIC' FUNDAMENTALS FOR CE PWR FCS LP 7-7-21, LO 6.1.3 191004K107
..(KA's)
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REACTOR PRINCIPLES (7%) THERMODYNAMIC Page 12 i
(7,%) AND COMPONENTS (21%) (FUNDAMENTALS FYA41 l
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QUESTION 1.15 (1.00)
Which one of the following describes the reason that TCV-211-2 (3 way valve in CVCS) automatically moves to the bypass position?
(1.0)
I a.
Bypass diverts letdown from the boronometer to protect it from high temperature.
I b.
Bypass diverts letdown from the boronometer to protect it from high radiation from damaged fuel.
c.
Bypaso diverts letdown from the ion exchangers to protect them from high temperature, d.
Bypass diverts letdown from the ion exchangers to protect them from high radiation from damaged fuel.
ANSWER 1.15 (1.00) c.
43, 44 191007K104
.(KA's)
QUESTION 1.16 (1.00)
Choose from the list below the pump breaker control switch that, if it were red flagged, would prevent the Emergency Diesel Generator output breaker from closing.
(1.0) a.
Low Pressure Safety Injection b.
High Pressure Safety Injection d.
Component Cooling Water
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REACTOR' PRINCIPLES (7%) THERMODYNAMICS Page 13 (7,%) AND COMPONENTS (11%) (FUNDAMENTALS FYAM)
ANSWER' 1.16 (1.00) c.
. REFERENCE FCS LP 7-13-5, p.'72 191005K111
..(KA's) j
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QUESTION 1.17 (1.50)
Fill in the blanks in the following paragraph dealing with condenser tube
' fouling at Fort Calhoun Station.
Blanks may contain one or.more words or numbers.
(1.5) i i
The major source of condenser fouling is __(a)__ from the Missouri-river, J
During high fouling periods, condenser flow is reversed as often as
__(b)__.
When condenser flow is reversed, plant indications may show a reactor power change of __(c)__.
I ANSWER 1.17 (1.50) a.
sticks, sand, gravel, &'similar debris b.
1~4 x per shift c.
05~30 mw (3 answers @ 0.5 ea.)
77 191006K111
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REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 14 LI,%) AND COMPONENTS (11%) (FUNDAMENTALS EYAM)
QUESTION
.18
( l'. 0 0)
.Which o.a of the answers below describes the location of the onset of tesvitation in a centrifugal pump?
(1.0) c.
Front face of the blade.
b.
Top of the volute.
c.
Top of the inlet.
'd.
' Rear face of the blade.
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ANSWER 1.18 (1.00) d.
REFERENCE
- FCS LP 7-7-21, p.
6.4-4 191004K101
..(KA's)
QUESTION 1.19 (0.00)
Which one of the following describes the reason to maintain zero deviation on the feedwater controllers (FIC-1101/2)?
(1.0) a.
To establish the manual control point.
)
b.
To provide a "bumpless" transfer between control modes.
c.
To enable switching to the HIC standby controller.
[
d.
To ensure the bypass valves are closed at high power.
f' 1
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)
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.a.
Question deleted.
Typographical error: 'FIC' should have been ' HIC' l
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REACTOR PRINCIPLES (7%1 THERMODYNAMICS Page 15 (7,%1 AND COMPONENTS (11%1 (FUNDAMENTALS RYAM)
{
REFERENCE
)
23 191003K111
..(KA's) l l
QUESTION 1.20 (1.00) c Which one of the answers below correctly describes how and why the wide range steam generator level channels (911 & 912) do not correspond to the narrow range readings 7 (1.0) a.
The wide range read low because they lack temperature compensation and flow errors were encountered (venturi effect).
b.
The wide range read high because downcomer density is not constant and flow errors were encountered (venturi effect).
1 c.
The wide range read high because they lack temperature compensation and flow errors were encountered (venturi effect).
d.
The wide range read low because downcomer density is not constant and flow errors were encountered (venturi effect).
ANSWER 1.20 (1.00) d.
39 191002K106
..(KA's)
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1.
REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 16
-(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) l QUESTION 1.21 (1.00) j Which one of the answers below describes failure modes for steam generator level sensor failure due to diaphragm ruptuie?
(1.0) a.
Those used for RPS will read high while those used for FRS will read low.
b.
.Those used for RPS will read high and those used for FRS will read high.
c.
Those used for RPS will read low while those used for FRS will read high.
d.
Those used for RPS will read low and those used for FRS will read low.
ANSWER.
1.21 (1.00) b.
33, 35 191002K109.
..(KA's)
QUESTION 1.22 (1.50)
If a 480V island bus is de-energized with both the feeder breaker and the bus tie breaker racked down, what action is required AND why to close the alternate tie breaxer?
(1.5)
ANSWER 1.22 (1.50)
Either the feeder (0,5) or bus tie breaker (0.5) must be racked up to clear the interlock (0.5) that prevents supplying from two sources.
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' REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 17
)
(7%) AND COMPONENTS (11%)' (FUNDAMENTALS EYAM) 1 REFERENCE FCS'LP 7-13-3, p.
47 191008K107
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'2.
EMERGENCY AND ABNORMAL' PLANT EVOLUTIONS Page 18 (27%)
9
-QUESTION 2.01 (2.00)
'With the Steam Generator Blowdown System in a normal line up for 100% power operation, describe two (2) release paths that exist via the blowdown system, and state whether each of the paths is monitored or not.
(2.0)
ANSWER 2.01 (2.00) 1.
Water entering the blowdown tank flashes to steam.
The tank is vented to atmosphere, so come of the steam and non--condensable gases are released to the environment (0.75), unmonitored (0.25).
2.
Water from blowdown tank pumped by transfer pumps to the Raw Water header (0.75), monitored (0.25).
REFERENCE FCS LP 7-11-25 000037A113
..(KA's)
QUESTION 2.02 (1.00)
AOP-11 directs you to TRIP THE REACTOR if CCW flow cannot be restored within five minutes or a high temperature alarm is received on any of three parameters.
Which one of the following is NOT one of the alarmed parameters?
(1.0) a.
b.
CEDM seal outlet.
c.
RCP seal bleed off.
d.
Detector well cooling coil outlet.
I ANSWER 2.02 (1.00) d.
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'2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 19 (27%)
1 1
REFERENCE I
I O >FCS-LP 7-17-11 EO 1.2, AOP-11 j
000026K303
..(KA's) l
-QUESTION 2.03 (1.50)
[
Fill in the blanks in the following statements concerning verification of Jt RCS heat removal safety function per E0P-01.
Blanks may contain one or l
more words or numbers.
a.
Verify at least one S/G has level:
1.
% NR with feedwater available.
(0.25) 2.
(0.75) b.
Verify steam dump and bypass valves functioning to control:
1.
RCS to degrees F.
(0.25) 2.
S/G pressure _.
psia.
(0.25)
L hANSWER 2.03 (1.50) a.
1.
35-85% (>35%)
2.
Being restored by adequate feed flow.
b.
1.
525-535 2.
850-925
' REFERENCE FCS LP 7-18-1 EO 1.3, E0P-01 000007K301
..(KA's) l
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l 2'.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 20' (27%)
l QUESTION 2.04 (0.00)
According to AOP-19, Loss of Shutdown Cooling, what are the "LAST RESORT" methoos (Flow Paths) for residual heat removal for each of the following conditions.
For each case, describe the complete open/ closed loop path, a.
The reactor head installed.
(1.0) b.
The reactor head removed, transfer canal open.
(1.0)
ANSWER-2.04 (0.00)
Question deleted.
Reference superceded.
REFERENCE AOP-19, P. 3 LP 2-1-41, L.O.
1.0, 1.2 000025K301 000025K101
..(KA's) l QUESTION 2.05 (1.50)
What are the guidelines given in OI-VA-2 on how to IDENTIFY and ISOLATE a i
radioactive leak in the Auxiliary Building which causes a Stack High Radiation Alarm.
(1.5)
ANSWER 2.05 (1.50)
Shut down supply and exhaust fans. [0.5]
Isolate all rooms. [0.5]
Start one exhaust fan and open dampers one at a time while observing monitor until leak is found. [0.5]
(Area monitors may be of some help.)
REFERENCE FCS EQB 000060A202
.(KA's) l 1
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2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 21 (27%)
QUESTION 2.06 (1.00)
Which one of the following is the correct response from the main condenser pressure instrument as condenser vacuum goes from 29" to 15" Hg?
(1.0) a.
a high condensate pressure alarm.
b.
a reactor trip, c.
a main feed water pump trip.
d.
an evacuation pump start signal.
1 ANSWER 2.06 (1.00)
D.
REFERENCE FCS LP 7-11-4 000051A202
..(KA's)
QUESTION 2,07 (1.00) l Which one of the following is the correct first operator action to attempt i
to terminate a spontaneous CEA withdrawal?
(1.0) l a.
manually trip the reactor.
b.
place the CEA selector switch to "0FF".
c.
initiate emergency boration.
d.
place the in - hold - out switch to "IN".
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'2.
- EMERGENCY:AND'5BNORMAL PLANT EVOLUTIONS Page 22 o
(2_7%)'
I L
..'. ANSWER 2.07 (1.00) la.
B .
! REFERENCE.
FCS LP 7-17-27 E0 1.1, AOP-27 000001G010
..(KA's)
QUESTION 2.08 (1.00)
Which one of the following is the correct operator response if reactivity control'is not established per EOP-1, " Reactor Trip 7"'
(1.0) a.
open the clutch power supply breakers and emergency borate, b;
initiate safety injection and open the clutch power supply breakers.
c.
emergency borate and open MCC 3B1 and 4A1 supply breakers.
I d.
open MCC 3B1 and 4A1 supply breakers and initiate safety injection.
1 ANSWER 2.08 (1.00)
A.
I REFERENCE l
1 FCS LP 7-18-1 E0 1.4, E0P-1 000024K302 000029A111
..(KA's) l l
1
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1
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 23 L2.7%)
i QUESTION 2.09 (1.00)
Which one of the following DOES NOT qualify as a boration flow path per
)
. Technical Specification 2.2 on the Chemical and Volume Control System?(1.0)
-a.
Safety injection pumps can take suction'from the boric acid tanks.
b.
Safety injection pumps can take auction from the SIRW tank.
l c.
Charging pumps can take suction from the SIRW tank.
d.
Charging pumps can take suction from the boric acid tanks.
ANSWER 2.09 (1.00) f^*
{
. REFERENCE FCS TS 2.2 Basis, p.
2-18, 19 000024G008
..(KA's) l QUESTION 2.10 (1.00)
A malfunction in the prereuriser pressure measurement "A" channel
.(A/P1A-102Y) causes the output to go to minimum.
Which one of the following is the proper system response to the malfunction?
(1,0) a.
High Pressure and TM/LP Channels "A" trip causing a reactor pre-trip.
}
b.
High Pressure and TM/LP Channels "A" trip causing a reactor trip.
I l
c.
Only High Pressure Channel "A" trips causing a reactor pre-trip.
d.
Only TM/LP Channel "A" trips causing a reactor pre-trip.
I 1
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I 1
1
2d EMERGENCY-AND ABNORMAL PLANT EVOLUTIONS Page 24-127%).
. ANSWER 2.10' (1.00)
D.
?
-REFERENCE FCS LP 7-12-25, LO 1.03, 007-12-26-H-25-1.03-0001 000027A216
..(KA's)
- QUESTION 2.11 (1.00)
. When evacuating the control room due to a fire, control room personnel should remove which one of the following?
(1.0) a.
Key for Auxiliary Shutdown Panel and the turning gear hand jacking tool.
b'.
The station log and the key for the' Auxiliary Shutdown Panel.
c.
The turning gear hand jacking tool and the transceivers.
d.
Transceivers and the key for the east switchgear room.
. ANSWER
'2.11 (1.00)
I D.
REFERENCE AOP-6, Pp2-4 000068G010
. (KA's)
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EMERGENCY-AND ABNORMAL PLANT EVOLUTIONS Page 25 (27%)
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1 i
l QUESTION 2.12 (1.00)
The STEAM GENERATOR TUBE RUPTURE Procedure (EOP-04) cautions the operator early.on to avoid use of HCV-1040 and FW-10.
The reason for this caution is to avoid (1.0) t a.
-unmonitored release of activity to the environment.
b.
filling the SG to the steam header before RCS depressurization.
c.
unnecessary contamination of the steam and feed system piping.
d.
depressurizing the SG'to facilitate RCS-SG pressure equalization.
ANSWER 2.12 (1.00)
A.
REFERENCE E0P-04, P. 5 000037K305
..(KA's)
QUESTION 2.13 (1.00)
Which one of the following correctly describes the STEADY STATE conditions with respect to program values, for the given parameters, following a rod drop at full power with no reactor trip and no operator action?
(All systems are in the expected manual / auto condition.)
(1.0) a.
T-ave below, pressurizer level at program, RCS pressure at program.
b.
Pressurizer level below, RCS pressure below, T-ave below.
c.
RCS pressure above, T-ave at program, Pressurizer level above.
d.
T-ave above, Pressurizer level below, RCS pressure at program.
c.
Pressurizer level above, RCS pressure above, T-ave above.
l
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EMERGENCY AND ABNORMAL' PLANT EVOLUTIONS Page 26-
-(27%)-
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ANSWER 2.13 (1.00) 1
\\
A.
REFERENCE BASIC REACTOR THEORY, FCS SD PZR LEVEL & PRESS CONTROL 000003K116 000003K105 000003K103
..(KA's)
- QUESTION 2.14 (1.90)
Which one of the following conditions is LEAST likely to cause an increase
{
in area radiation indications in the spent fuel pool area?
(1.0) a.
Tritium release in the building.
b.
Lifting the core source element out of the pool.
c.
Drop in pool level to bottom of transfer gate seal.
1 1
d.
Radiography of welds in transfer canal.
)
)
ANSWER 2.14 (1.00)
A (1.0) (Tritium is a weak beta emitter, all the others have a gamma
)
component.)
I REFERENCE FCS LP 7-12-3, EO 3.20, BASIC RAD CON /HP J
I 000036K202
..(KA's) l 1
(
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EMERGENCY AND ABNORMAL PLANT EVOLUTIORE Page 2'/
( 27% )
l 1
1 QUESTION 2.15 (1.00)
L During recovery from a small break LOCA, Which one of the following actions wili reduce a void in the vessel head?
(1.0) a.
operate Pressurizer sprays
-b.
secure all Reactor Coolant Pumps c.
operate Pressurizer heaters d.
secure High Pressure Injection Pumps ANSWER 2.15 (1.00) c.
000009A238
..(KA's) 1 l
' QUESTION 2.16 (1.00) i During a small break LOCA with reactor vessel level at 100%, the operator is allowed to throttle or stop Safety Injection flow if (1.0) a.
RCS subcooling > 20 deg.F. Pressurizer level >/=45%, and >/=1 SG available.
b.
Pressurizer level >/=45%, both SGs available, and RCS Cold Leg temperature < 580 deg.F.
c.
>/=1 SG available, RCS subcooling > 20 deg.F, and Pressurizer pressure
>/=1950 paia.
d.
RCS Cold Leg temperature < 580 deg.F, Pressurizer pressure >/=1950 paia, and both SG available.
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'2.
' EMERGENCY AND ' ABNORMAL PLANT EVQMJTTONS Page 28-(27%)
ANSWER 2.16 (1.00)
E A.
. REFERENCE
..(KA's)
-QUESTION 2.17 (1.00)
The reactor has experienced a Reactor Trip.
An early step of E0P-01 has you. trip.the turbine.
If it did not manually trip and is causing' continued cooldown, the operator is initially directed to (1.0) a.
shut the turbine stop and intercept valves manually, b.
shut the MSIVs and bypasses.
c.
take the control fluid pumps to pull-to-lock.
d.
initiate SIAS manually.
ANSWER 2.17 (1.00) c.
REFERENCE FCS E0P-01 000007A101
..(KA's) l I
[ QUESTION 2.18 (1.00)
L If offsite power is lost during refueling operations, what operator action ia required to assure that both buses 1A3 and 1A4 are energized?
(1.0) l -
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'2; EMERGENCY AND ABNORMAL PLANT EVOLtJTIONS Page 29-
{
(27%)
ANSWER 2.18 (1.00)
The operator must take the LPSI pump control switch for the operating SDC loop to off.
(1.0)
37; E0P-02 000056K204 000056K302
..(KA's)
QUESTION 2.19 (1.00)
Dur2ng a loss of all AC power why is the operator cautioned about cooldown of tae RCS below no-load Tavg?
(1.0)
ANSWER 2.19 (1.00)
Cooling below no-load Tavg without makeup may cause loss of RCS pressure and inventory control.
(1.0)
REFERENCE
4 000055G007
..(KA's) l t
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2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 30 j
(27%1 QUESTION 2.20 (1.00)
Which one of-the following operator actions is required if two rods move erratically when motion.is demanded?
(1.0) a.
Place the mode selector switch in the off position.
b.
Match turbine load to actual reactor power.
c.
Determine the shutdown margin per ST-SDM-1 without erratic rods.
d.
Manually trip the reactor and go to, " Reactor Trip Procedure," E0P-01, t
ANSWER ~
2.20 (1.00)
-a.
REFERENCE FCS AOP-2-2 000005A203
..(KA's) f fQUESTION 2.21 (1.50)
Fill in the blanks in the following statements concerning process radiation monitors measuring RCS activity.
Blanks may concern one or more words or numbers.
l h
a.
Process Radiation Recorder RR-214 in high alarm indicates RCS activity is high.
(0.5) b.
Process Radiation Monitor PRM-1 in high alarm indicates RCS l
activity is high.
(0.5) c.
Process Radiation Monitor PRM-2 in high alarm indicates RCS i
L activity is high.
(0,5) l c
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EMERGENCY AND' ABNORMAL PLANT EVOLUTIONS Page 31
( 27% ) -
' ANSWER 2.21 (1.50) a.
gamma (gross) OR I-135 b.
gamma (gross) 1 c.
iodine-135 j
000076K201
..(KA's) l QUESTION 2.22 (1.50)
Place the four choices below in the order in which they should be used (most preferred, or used first, to least preferred, or used last) to fight a fire in the Cable-Spread Room.
(1.5) a.
Halon.
b.
CO2.
l c.
ANSUL.
d.
Water.
ANSWER 2.22 (1.50) a-b-c-d (0.5 for each switch necessary for this order)
REFERENCE FCS AOP-6-40 000067A108
..(KA's) f
(
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r,.
2.
EMERGENCY AND ABNORMAL PLANT EVQLpTIONS Page 32 I
(27%)
L l' QUESTION 2.23 (1.00).
1 Which one of the following is the single exception to the Technical Specification requirement that containment integrity be maintained at any time when-the reactor vessel head is removed?
(1.0) a.
During testing of no more than one (1) CEDM.
b.
When'at least three (3) decay heat removal paths are available.
c.
'During the administrative verification that manual' containment L
isolation valves are locked closed.
d.
If boron concentration is greater than refueling concentration.
i ANSWER 2.23 (1.00) d.
2-30 000069G003
..(KA's)
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h
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PLANT SYSTEMS
( 3.
(38%) AND PLANT-WIDE GENERIC Page 33 l
RESPONSIBILITIES (10%)
- QUESTION 3.01 (1.00) i l
Which one of the following is the correct minimum withdrawn position for a non-trippable CEA?
(1.0) a.
100 inches b.
107 inches
.c.
114 inches d.
121 inches ANSWER 3.01 (1.00) i c.
p.
2-50c i
001000G005
..(KA's) i QUESTION 3.02 (1.00) l Which one of the following will NOT cause the RPS reactor trip breaker I
undervoltage coil to open the reactor trip breaker?
(1.0) a.
Activation of either channel of the DSS.
b.
Activation of either channel of the RPS.
c.
Depressing the manual scram puchbutton on the RPS cabinet.
i d.
Removing voltage from the coil.
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[; 3.
PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page 34
. RESPONSIBILITIES (10%)
k-
- ANSWER 3.02 (i.00) b.
j REFERENCE j
74-75 001000K603
..(KA's) q l
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PLANT SYSTEMS (38%) AND PLANT-WIDE GENERTC Page 35 RESPONSIBILITIES (10%)
i l
l QUESTION-3.03 (1.50)
. MATCHING.
Match each of the alarms below with.the appropriate cause.
Each cause may be used more than once or not at all.
(1.5)
ALARM
- a. Rod Position Deviation Low Limit
- b. Rod Position Deviation Reed Switch e.
Out of Sequence Rod Block
- d. Power Dependent Insertion Limit
- e. Rod Drive Power Interrupt
{
1.
CAUSE During rod withdrawal, any group above Lower Limit Setpoint before all lower group D have reached their Upper Sequential Permissive.
2.
Any one of the shutdown rods is below its 120-inch exercise limit.
3.
The group deviation is four (4) inches, as sensed by the plant computer.
4..
The group deviation is eight (8) inches as sensed by the plant computer.
5.
The group deviation is eight (8) inches as sensed by the Metroscope.
Rod block.
6.
7.
Excessive group overlap.
8.
Power greater than 10EE-04% with group one less than 118 inches.
9.-
Power greater than 10EE-04% with group two less than 122 inches.
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L 3l PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIG Page 36 L
RESPONSIBILITIES (10%)
" ANSWER 3.03 (1.50) l l
a.
3 b.
5
.c.
1 l
d.
8 1
e.
6 (5 answers @ 0.3 ea.)
l
- p. 53-58 001050A201
..(KA's)
-QUESTION 3.04 (2.00)
Fill in the blanks in the following Technical Specification bases for the Reactor Coolant system (RCS).
Blanks may contain one or more words or
- numbers, a.
lThe limitations on the radioactivity of the reactor coolant ensure that the resulting __(1)__ hour doses at __(2)__ will be well within the limits of __(3)__ following a __(4)__ accident.
(1.4) b.
Permitting operation to continue for limited time periods with reactor coolant activities above allowed limits accommodates __(1)__ which may occur following changes in __(2)__.
(0.6) i
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PLANT SY3TEMS (38%)'AND PLANT-WIDE GENERIC Page'37 3
RESPONSIBILITIES (10%1 ANSWER 3.04 (2.00) a.
1.
2 2.
the site boundary 3.
10 CFR 100:
4.
SGTR '(4 answers @ 0.35 ea.)
I b.
1.
iodine spiking 2.
power- (2 answers @ 0.3 ea.)
- p. 2-9 002000G006
..(KA's) l QUESTION
- 3. 05 =
(1.50)
' Operating Instruction RC-11 instructs the operator to verify natural l
circulation by checking that hot leg and core exit thermocouple are NOT l
abnormally different.
l i
a.
What is the minimum temperature difference from those below that I
indicates an abnormal difference during natural circulation?
(0.5)
I 1.
5 degree F l
2.
10 degrees F 3.
20 degrees F 4.
40 degrees F i
b.
What is the significance of an abnormal difference in these temperatures?
(1,0) l l
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1.
1 1.
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3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 38
)
L
. RESPONSIBILITIES (10%)
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1 ANSWER 3.05 (1.50) 1
\\
a.
2 (0.5)
{
b.
A.significant temperature difference indicates that the natural circulation flow is low (such the core exit and hot leg are not well coupled).
(1.0)
REFERENCE i
61; CEN-152 Rev.
3, p. 2-16 002020K514
..(KA's)
QUESTION 3.06 (1.00)
Which one of the following answers describes RCS hot leg (Th) and cold leg (Tc) temperature response during a reactor coolant pump (RCP) coastdown in a loss of forced cooling transient from 100% power?
a.
Th and Tc will decrease.
b.
Th will increase and Tc will decrease.
c.
Th will decrease and Tc will increase, d.
Th and Tc will increase.
ANSWER 3.06 (1.00)
,a.
REFERENCE
-FCS LP 7-11-20, p.
61 003000K502
..(KA's)
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3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 39 i
RESPONSIBILITIES L10%1 I
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fQUESTION-3.07.
(1.50)
MATCHING.
Match each of the conditions below with the component (s) which act(s) to control it.
Each component may be used more than once or not at all.
(1.5)
]
CONDITION COMPONENT l
- a. High Ictdown temp (470 deg's F) 1.
LCV 101-1 2.
TCV 202 g
- b. High pressurizer level 3.
HCV 204 l
4.
PCV 210 j
c.
High letdown flow (155 gpm)
- d. CIAS (PPLS OR CPHS) i
- e. High intermediate press (550 psig)
ANSWER 3.07 (1.50) a.
2 b.
1 c.
3 d.
2&3 e.
3 (5 answers @ 0.3 ea.)
REFERENCE FCS LP 7-11-2 E0 1.2 004000K405 004000K101
..(KA's)
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l 3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 40 l
RESPONSIBILITIES (10%)
- QUESTION 3.08 (1.00) j Which'one of the annuers below describes the function of the shutdown cooling system two position keyewitch, " SHUTDOWN COOLING INTERLOCK PC-118A FAILURE. MODE OVERRIDE HC-347/3487" (1.0) a.
.Used to override the automatic signal in the event of an AI-40B bus power failure.
b.
Used to override the automatic closure signal to permit manual operation of the valve with_ pressurizer precoure above interlock.
c.
Used to override the automatic signal to permit manual adjustment of chutdown cooling heat exchanger flow.
d.
Used to override the automatic signal in the event of a loss of shutdown cooling system integrity during shutdown cooling operation.
ANSWER 3.08 (1.00) a.
27 004020K603
..(KA's) 1 1
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3.
PLANT SYSTEMS (38%i AND PLANT-WIDE GENERIC Page 41 RE,SPONSIBILITIES (10%)
QUEE/ ION 3.09 (1.00)
Which one of the actions below describes the actions required by Technical Specifications if the operating shutdown cooling pump is lost during refueling?
(1.0) i a.
Verify that the other shutdown cooling pump is available.
b.
Verify that alternate cooling such as CVCS is available.
f c.
Restore shutdown cooling flow within six (6) hours or cease fuel handling activities.
d.
Cease fuel handling activities.
l l
ANSWER 3.09 (1.00) d.
REFERENCE i
37-38 005000K307
..(KA's)
{
[ QUESTION 3.10 (2.00)
I With regard to an Engineered Safeguards Control Recirculation Actuation l
Signal (RAS):
a, What signal (s) is/are required coincident with a SIRWT low level signal to generate an RAS 7 (two answers required)
(0.5) b.
What are three (3) control functions initiated by a RAS (valve numbers I
are NOT required)?
(1.5) l L
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' PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIG Page 42 RE,SPONSIBILITIES (10%)
NSWER 3.10 (2.00) a.
PPLS (0.25)-& CPHS (0.25) b.
1.
Trip / lock.out the LPSI pumps.
2.
Open HPSI & containment spray suction from containment.
3.
Close HPSI & CS cuction from SIRWT.
4.
Isolate SI pump minimum flow recirculation line.
5.
Establish full-CCW flow threigh SDC hx. (any 3/5 @ 0.5 ea.)-
14 006020A304
..(KA's) i
)
l QUESTION 3.11 (2.00) j Fill in the blanks in the follow statements regarding pressurizer spray:
l a.
The pressurizer spray valves are __(1)__ type valves with a capacity of approximately __(2)__ gpm each.
(0.8) j b.
It only takes gpm of spray to keep up with all 900 kw of heaters.
(0.3) l 1
c.
The " mini-flow" spray valves are set to pass gpm each.
(0.2) d.
Energizing heater banks one and two will cause require spray flow to flush the pressurizer liquid volume in approximately hours.(0.3) j c.
If spray to pressurizer differentia 1' temperature is greater than i
__(1)__ degreee F then spray initiation must be __(2)__.
(0.6) j l
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-PLANT SYSTEMS '(38%)~AND PLANT-WIDE GENERIC Page 43 RESPONSIBILITIES (10%)
1
- ANSWER 3.11 (2.00)
(
a.
1.
globe (0.3);
2.
140-+/-10'(0.3) b.
50~55 (0.8) c.
1~2 (0.2) d.
2 (0.3) e.
1.
200 (0.3);
12.
recorded (0.3)
p.
21 010000A401
..(KA's)
' QUESTION 3.12 (1.50)
What are two (2) of the three (3) purposes of the Containment Air Cooling and Filtering System during a design basis accident?
(1.5) i ANSWER 3.12 (1.50) 1.
Recirculate air to prevent hydrogen pockets.
t 2.
Remove heat from containment to maintain pressure < design (60#).
3.
Reduce fission product inventory.
(any 2/3 @ 0.75 ea.)
REFERENCE f
11 013000A102
..(KA's)
L L
)
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- 3.
PLANT SYSTEMS LEE %) AND PLAMI-WIDE GENERIC Page 44 RESPONSIBILITIES (10%)
4 l
l i
- QUESTION 3.13 (1.50) l
. Match each of the core mimic light colors to the appropriate MATCHING.
rod' height description.
Each description may be used more than once or not at all.
(1.5)
I COLOR DESCRIPTION
- a. Amber 1.
Upper electrical limit 2.
Upper rod stop l
- b. Blue
- 3. Shutdown group lower limit 4.
Rod motion occurring l
- c. Green
- 5. Rod deviation detected
- 6. Above four-(4) inches
- d. Red 7.
Lower electrical limit j
.r.
i
- e. White ANSWER 3.13 (1.50) a.
2 b.
3 c.
7 d.
I e.
6 OR 4 if PLCEA specified (5 answers @ 0.3 ea.)
h REFERENCE FCS LP 7-12-26, p.
44, 45 014000K401
..(.KA's) l
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PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 45 u
RESPONSIBILITIES (10%)
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l -QUESTION 3.14 (1.00) l l
MATCHING.
Match each of the power supplies listed below to the appropriate fan cooler.
Each supply may be used more than once or not at all.
(1.0) l FAN POWER SUPPLY l
- a. VA-3A 1.
1B3A l
2.
1B3B i
- b. VA-3B 3.
1B4C 4.
1B4D
- c. VA-7C 5.
1B3A-4A 6.
1B3B-4B L
- d. VA-7D 7.
1B3C-4C 8.
1B3D-4D ANSWER 3.14 (1.00) a.
1 b.
3 c.
7 d.
18, 27 022000K201
.(KA's) j i
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13.
PLANT SYSTEMS (38%)(AND PLANT-WIDE GENERIC Page 46 RESPONSIBILITIES (10%)
QUESTION 3.15 (1.00)
Which.one of the following helps spring force to hold the Main Steam Isolation Valve disc shut?
(1.0) e.
Air pressure.
b.
Downstream steam pressure.
c.
Upstream steam pressure.
d.
Motor operator.
' ANSWER 3.15 (1 00) c.
15 035010K601
..(KA's) j QUESTION 3.16 (1.00) 1 Which one of the instruments below would provide the first observable i
indication of a loss of feedwater event while at power?
(J.0) i
)
a.
RCS pressure.
b.
Pressurizer level.
c.
Reactor power.
d.
Hot leg temperature.
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3; PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 47 f RESPONSIBILITIES (10%)
' ANSWER 3.16 (1.00) b.
54-57 035010K301
..(KA's)
QUESTION 3.17 (2.00) a.
Which one of the choices belew reflect the basic sizing criteria for the steam' dump and turbine bypass valves?
(1.0) t 1.
. Sized to prevent steam safety lifting on turbine trip at 100%.
2.
Sized as large as-possible without damage to the condenser.
1
-3.
Sized to remove decay heat immediately after reactor trip.
i I
4.
Sized to provide minimum steam flow required for turbine startup.
]
b.
Which of the RCS average temperatures below is the lowest that is sufficient to actuate steam dump quick opening?
(1.0) j 1.
535 degrees F.
i 2.
550 degrees F.
3.
565 degrees F.
i 4.
580 degrees F.
?
ANSWER 3.17 (2.00) j a.
1.
b.
3.
J
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-3.
PLANT SYSTEMS (38%)'AND PLANT-WIDE GENERIC Page 48 i-
' RESPONSIBILITIES (10%)
' REFERENCE FCS-LP 7-11-17,-p. 25, 27 041020K409
..(KA's)
QUESTION 3.18 (1.00)
Which one of the following reasons describes why carbon dioxide is used to I
purge the main generator?
(1.0) a.
Better. thermal. capacity.
b.
Low molecular weight reduces windage heating.
c.
Reduced oxidation and corrosion.
'd.
Reduced danger of explosion.
1 i
ANSWER 3.18 (1.00) l I
d.
l REFERENCE FCS LP 7-11-14, p.
20 045000K501
..(KA's) i QUESTION 3.19 (1.00)
Which one of the RPS reactor trips below would be expected to trip the reactor for a turbine trip from 100% power if the anticipatory trip from the stop valve closure did not function?
(1.0) 1 a.
High power level.
b.
Steam generator pressure.
c.
TM/LP.
d.
Pressurizer pressure.
i
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PLANTLSYSTEMS (38%)'AND PLANT-WIDE GENERIC Page 49 j
i RESPONSIBILITIES (10%)
i ANSWER.
3.19 (1.00)
)
l d.
g f
.)
-REFERENCE l
56 045050A101
..(KA's)
QUESTION 3.20 (1.00)
Which one of the answers below describes what should trip the main feed-I water pumps (MFP) if all condensate pumps tripped (including standby)?(1.0) a.
. Condensate pump interlock.
b.
MFP motor ~ current overload, c.
Steam generator isolation eignal.
d.
ANSWER 3.20 (1.00) d.
-REFERENCE FCS LP 7-11-11, various pages 056020K301
..(KA's)
. QUESTION 3.21 (1.00)
.On which two (2) control room panels is indication of the feedwater isolation valve position (BOTH regulating and containment isolation) available?
(1.0)
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~ 3; -PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Pageu50 r
RESPONSIBILITIES (10%)
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i ANSWER 3.21 (1.00)
CB-10 (0.5) and AI-43A (0.5)
{
- REFERENCE 4
39 059000A306
..(KA's) i
. QUESTION 3.22 (1~.50) 1 MATCHING.
Match operator type and failure for loss of motive power mode to each of the isolation valves listed below.
Each operator type may be used more than once or not at all.
(1.5)
ISOLATION VALVE TYPE OPERATOR & FAILURE MODE
Motor - fail as is 2.
Motor - fail closed
- b. Main Steam Bypass Valves 3.
Motor - fail open; 4.
Air - fail as is
- c. Feedwater Isolation Valves 5.
Air - fail closed 6.
Air - fail open
- d. Feedwater Containment Isolation Valves 7.
Spring - fail open 8.
Spring - fail closed e.
Feedwater Regulating Bypass Valves 1
l l
ANSWER 3.22 (1.50) a.
8/5 b.
1 c.
1 d.
1 e.
5/8 (5 answers @ 0.3 ea.)
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PLANT SYSTEMS (38%1_AND PLANT-WIDE GENERIC Page 51 RESPONSIBILITIES ( lSjQ
?
L L REFERENCE FCS LP 7-12-10, p.
39-46 059000K419
..(KA's)
QUESTION 3.23 (1.00)
Which one of the following sets of parameters would generate an AFAS? (1.0) i Steam Generator RC-2A Steam Generator RC-2B I
Pressure Level Pressure Level al 800 psig 50% WR 600 psig 40% WR b.
400 psig 30% WR 450 psig-30% WR c.
700 psig 45% WR 550 psig 25% WR AL 550 peig 45% WR 400 psig 40% WR ANSWER 3.23 (1.00) c.
22 061000K402
..(KA's)
-QUESTIONL 3.24 (2.00)
Fill in the blanks in the following paragraph dealing with controlling l
steam generator levels with AFW.
Blanks may contain one or more words or numbers.
(2.0)
After AFW auto start, steam generator level will cycle between __(a)__ % WR and __(b)__ % WR by causing __(c)__ to clear on the higher level.
This j
will control AFW flow by __(d)__.
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,, RESPONSIBILITIES (10%)
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' ANSWER 3.24 (2.00) a.
32 b.
60 c.
AFAS (4 answers @ 0.5 ea.)
~ d.-
closing throttle valves (HCV-1107A/B or HCV-108A/B)
REFERENCE FCS-LP.7-11-1, p.
63 061000A101
.(KA's)
. QUESTION 3.25 (1.00)
Which one of the loads below describes the minimum load that should be maintained on the Emergency Diesel Generator to protect against reverse power?
(1.0) a.
20.KW.
b.
100 KW.
c.
500 KW.
d.
2500 KW.
ANSWER 3.&5 (1.00) b.
145
- 064000A107
..(KA's)
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PLANT SYSTEMS (38%) AND PLANT-HIDE GENERIC
'Page 53 RESPONSIBILITIES (10%)
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i QUESTION 3.26 (0.00)
Which one of the following answere describes the control room ventilation system response to a VIAS 7 (1.0) a.
Place VA-64 in service.
b.
Place VA-46A and VA-46B in service.
c.
Trip VA-46A, VA-46B, VA-63, and VA-49.
-d.
Shut PCV-860A, PCV-860B, and PCV-860C.
I
~ ANSWER 3.26 (0.00)
Que.stion deleted.
Plant modification made a & b correct.
8-19 072000A301
..(KA's) f
! QUESTION 3.27 (1.00)
Which one of the process radiation monitors listed below will cause a VIAS on high radiation?
(1.0)
}. - a.
RM-050.
f b.
RM-053.
c.
RM-057.
f j
d.
RM-059.
)
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"[3; ' PLANT-SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 54 RESPONSIBILITIES (10%)
ANSWER 3.27 (1.00) a.
- p. 24-32 073000A101
. (KA's)
' QUESTION-3.28 (1.00)
Which one of the following describes why Technical Specifications require
^Gt'least one circulating water pump in operation with flow approximately
~120,000 gallons per minute?
.(1.0) a.
The minimum flow assures condenser availability during power operation.
b.
The minimum flow is required to assure TPCCW availability, c.
The minimum flow is required to assure proper operation of the vacuum priming system.
d.
The minimum flow is required to assure adequate liquid waste disposal.
ANSWER 3.28 (1.00) d.
REFERENCE
[
FCS TS 2.9.1.1.d(i),
p.
2-42 0750G0KiO2
..(KA's) l
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RESPONSIBILITIES (10%)
I
)
j QUESTION 3.29 (1.00)
Which one of the following plant air pressures is that value at which the
'first control room alarm is received?
(1.0) a.
108 psig.
b.
102 psig.
c.
96 psig.
d.
90 psig.
ANSWER 3.29 (1.00) c.
24 078000A301
..(KA's)
QUESTION 3.30 (1.00)
Which one of the following plant air pressures generates an automatic close signal to PCV-1753, the service air header isolation valve?
(1.0) a.
70 psig.
b.
80 psig.
c.
84 psig.
d.
94 psig.
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' PLANT SYSTEMS-(38%) AND PLANT-WTDE GENERIC Page 56 RESPONSIBILITIES (10%)
LANSWER
'3.30 (1.00) b.
17 l
079000K401'
..(KA's) 1
. QUESTION 3.31 (1.50) l A Very High Radiation field exists in an area which cannot be controlled by locked access.
What three (3) alternate measures are required by Technical Specification section 5 to control access?
(1.5)
ANSWER 3.31 (1.50)
The area shall be:
~1.
roped off such that an individual at the rope boundary is exposed to
<= 1000 mrem /hr.
2.
conspicuously posted.
3.
a flashing light shall be activated as a warning device.
(0.5 ea)
. REFERENCE.
FCS TS 5.11.2, LP 7-9-3 EO 2.0 194001K103
..(KA's) k i
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'3.
PLANT SYSTEMS (38%I AND PLANT-WTDE GENERIC Page 57 RESPONSIBILITIES (10%)
QUESTION 3.32 (2.00)
The,following relate to Hold and Caution Tag requirements.
a.
Who will request the hanging and clearing of " Hold Order" tags?
(0.5) b.
According to Standing Order O-20, in what two (2) situations will
" Temporary Clearance" tags be used?
(1.0) c.
Describe a general situation / condition in which the use of " Caution" tags is warranted.
(0.5) 1 ANSWER 3.32 (2.00) a.
System operator (system operations /906 personnel) (0.5) l I
b.
1.
When equipment is to be operated in a test position or mode (such l
as trip checks, motor rotation checks, Limitorque operator
)
settings, etc.) (0.5) i 2.
When necessary to allow system / equipment usage for unusual l
circumstances. (0.5) c.
1.
When special instructions in the operation of components must be exercised. (0.5)-
OR 2.
During system turnover to specify components and systems under OPPD control. (0 5)
REFERENCE FCS LP 7-15-3 EO 1.1, 5.1, S.O. 0-20, rev 19, p 3.
i 194001K102
..(KA's) 1 QUESTION 3.33 (1.50) i a.
What members of the Plant Fire Brigade report immediately to the fire area?
(0.75)
'b.
What is the minimum number of Fire Brigade members that must be onsite l
at all times and how long.may there be leso than the required minimum onsite?
(0.75) l l
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PLANT SYSTEMS'(38%) AND PLANT-WIDE GENERIC-Page 58 RESPONSIBILITIES (10%)
L.
- ANSWER 3.33 (1.50) a.
Fire Brigade Leader (LO*) (0.25)
Two other operators (equipment / aux operators) (0.25)
Two security force' personnel (0.25)
I b.
5 (.25)
Ne more than two hours. (0.5)
REFERENCE FCS Standing' Order G-28,rev 11,p 6; T.S. 5.2.2
]
L.
194001K104 194001K116
..(KA's)
QUESTION-3.34 (1.50)
I MATCHING.
Match each of the access descriptions listed below to the appropriate badge color.
Each description may be used more.than once or not at all.
(1.5)
BADGE COLOR ACCESS DESCRIPTION 1
a.
White 1.
Unrestricted access to protected and vital areas
-l b.
Red 2.
Acceca to non-vital areas outside protected area c.
Green 3.
Access to protected area and non-radiation vital d.
Yellow 4.
Access to vital areae outside RCA 5.
Visitor or escorted access only f
f_ ANSWER.
3.34 (1.50) 5.
f.
a.
[
b.
l' h
c.
3/4 (3 answers @ 0.5 ca.)
l d.
Part deleted due to typographical error in descr. 2 (out-not inside).
l-l fo
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1E PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIG-Page 59 RESPONSIBILITIES (10%)
REFERENCE FCS Standing Order G-39, p.
2-4
-194001K105
..(KA's)
-QUESTION 3.35 (1.00)
Fill in the blanks in the following table with the-appropriate numbers giving minimum license staffing per Technical Specifications.
(1.0)
Operating Mode License Core Cold Power Type
. Alteration Shutdown Operation SRO
_(a)__
_(b).__
__(c)__
__(d)__
ANSWER 3.35 (1.00) a.
2.(including SRO-FH) b.
2 c.
1 L
d.
2 (4 answers @ 0.25 ea.)
-REFERENCE FCS TS 5.2-1,.p.
5-2 194001A103
..(KA's) i
?
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PL' ANT SYSTEMS (38%) AND' PLANT-WIDE GEMERIC Page 60 RESPONSIBILITIES (10%)-
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I
. QUESTION 3.36 (1.50) l MATCHING.
Match the appropriate valve type with each of the valve numbers listed.below, which are shown on the attached P&ID.
Each valve type may tx3 used'more than once or not at all.
(1.5)
Valve Number Valve Type a.
CL-106 1.
Diaphram 2.
Gate b.
CL-104 3.
Globe 4.
Butterfly c.
HCV-620 5.
Plug 6.
Angle d.
CL-119 7.
Check ANSWER 3.36 (1.50) a.
1-b.
4 c.
3 d.
2 (4 answers @ 0.375 ea.)
REFERENCE FCS P&ID Symbol List, 11405-MECH-1 194001A107
..(KA's) l l
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PLANT' SYSTEMS'(S8%) AND PLANT-WIDE GENEBIC Page 61 1~
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1 QUESTION 3.37 (1.00)
I 1
i
.Which one of the following choices describes the-person most responsible 1
l for ensuring that radiation exposure remains as low as reasonably L
achievable?
(1.0) a.
Manager - Fort Calhoun Station L
b.
Supervisor - Radiation Protection I
l c.
Field Health Physicist d
4
]
d.
Radiation Worker i
ANSWER 3.37 (1.00)
D.
REFERENCE-FCS Standing Order T-1, p.
1 194001K104
..(KA#s) l
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(********** END OF EXAMINATION **********)
]
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IWtc LICENSE EXAMINATION HANDOUT EQUATIONS CONSTANTS. AND CONVERSIONS 6=di*C*deltaT 6=U*A*deltaT p
P = Po*10sur*(t)
P = P *e /T SUR = 26/T t
T = 1*/p + (p-p)/X p T=1/(p-p)
T=(p-p)/Xp p = (Keff-1)/Keff = deltaKeff/Keff p=1*/(T*Keff)+Jeff/(1+%T)
A = In2/tg = 0.693/tg E = 0.1 seconds-1
-u*x I = Io*e CR = S/(1-Keyf) 2 R/hr = 6*CE/d feet Water Parameters I gallon = 8.345 lbm = 3.87 liters 1 ft3 = 7.48 gallons Density 0 STP = 62.4 lbm/ft3 = 1 gm/cm3 3 eat of vaporization = 970 Btu /lbm Heat of fusion = 144 Btu /lbm 1 atmosphere = 14.7 psia e.29.9 inches Hg.
J4iscellaneousConversior.s I curie = 3.7 x 1010 disintegrations per secord i
I kilogram = 2.21 lbm I
I horsepower = 2.54 x 103 Btu /tr i
1 mw a 2.41 x 106 8tu/hr l
I 1 inch = 2.54 centimeters i
f.
degrecs F = 9/5 69rees C + 32 degrees C = 5/9 (degrees F - 32) 1 Btu = 778 ft-lbf l
._.