IR 05000352/1989013
| ML20248E754 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/26/1989 |
| From: | Conte R, Easlick T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20248E745 | List: |
| References | |
| 50-352-89-13OL, 50-353-89-22OL, NUDOCS 8910050408 | |
| Download: ML20248E754 (147) | |
Text
_ _ _ _ _ _ - _
vi g
- .;y
'
.
e U.S. NUCLEAR REGULATORY COMMISSION
REGION I
' Report N'os.:
50-352/89-13 (OL)
50-353/89-22 (OL)
L Docket Nos.:
50-352 i
50-353 License Nos.~:
NPF-39 l
. Licensee:
Philadelphia Electric Company P. O. Box A Sanatoga, Pennsylvania 19464 Facility Name:
Limerick Generating Station, Units 1 & 2 Examination At:.Sanatoga, Pennsylvania
. Examination' Conducted: June 12 - 16, 1989, and June 19, 1989 Examiners:
A. Howe, Senior Operations Engineer D. Jarrell, (PNL)
G. Buckley, (PNL, Examiner Certification)
M. Riches, (PNL, Examiner Certification)
B. Wetzel, Operations Engineer, RIII (Observing)'
Chief Inspector:
9.2 G ? 7 Theodore A. Eas11ck a perations Engineer.
Date b
S/2 c f
Approved by:
d
'
Richard J. Conte, ChiefF BWR Section Date Operations Branch, Division of Reactor Safety Examination Summary: Written examinations and operating tests were admini-stered to three (3) senior reactor operator (SRO) candidates and six (6)
reactor operator (RO). candidates. The SR0s passed these examinations. The R0s passed the' written test but only five (5) passed the operating test. The one j
RO candidate was not well prepared for the licensing examination, as demon-j strated by failing the walktarough and simulator portions of the Operating
. Test. The candidate performed marginally'during the licensee's audit examina-tions. Except as noted above, the candidates were well prepared for the licensing examinations.
j l
8910050408 890927 _
)
PDR ADOCK 0500 V
a_-_--
_____:_____-_
_. _ - _ _ _ _ _ _
_
. _ _
__
.
.
.,
.-
-
For the purpose of multi-unit.(Limerick 1 and 2) licensing of personnel who i
were previously licensed on Limerick 1, operating tests (plant walk-through)
were administered to two (2) reactor operators. The written examination and simulator part of the operating test were waived in accordance with provisions of 10 CFR 55 and the guidance in NUREG-1021. The R0s passed these examinations.
' A requalification re-examination operating test (simulator part) was admini-stered to one (1). reactor operator. The RO passed this operating test.
.
l
-_-. - - _ -.
- _ _ -
,
DETAILS 1.
Introduction and Overview
,
The' NRC examiners conducted this replacement examination.for three (3)
Senior Reactor Operators (SRO) - one (1) SRO instant, two (2) SRO upgrades and six (6) Reactor Operators (RO). The examinations were administered in accordance with NUREG 1021,-Rev. 5, dated January 1, 1989, Examiner Standards (ES). The results are summarized below:
l R0 l
SR0 l
-l Written i
6/0
3/0 l
l Operating l 5/1
3/0 l
l-Overall l__
5/1
3/0
The NRC examiners conducted a Unit 1 and 2 differences examination for two (2) Reactor Operators (RO). The results are summarized below:
l R0 l
SR0-l l
Operating-l 2/0 l
N/A l
l Overall l
2/0
N/A l
The NRC examiners conducted a requalification re-examination for one (1)
Reactor Operator (RO). The results are summarized below:
l R0 l
SRO l
l PASS / FAIL l PASS / FAIL l l Operating l
1/0 l
N/A
i Overall i
1/0 l
N/A l
2.0 Persons Contacted 2.1 U.S. Nuclear Regulatory Commission
- A. Howe, Senior Operations Engineer
- T. Easlick, Operations Engineer B. Wetzel, Operations Engineer (RIII)
G. Buckley, Examiner (PNL)
M. Riches, Examiner (PNL)
.
___
- _. - -
--_ __
--.
_ _
_ _. _ _ _ _ _ _
L
/
?
l l
l 2.2 Philadelphia Electric Company
- R. Nuntz, OPS Training Supervisor
- L. Hopkins, PSST. Superintendent OPS
- E.-Firth, Superintendent - Training
- D. Weiksner, LOT Lead _ Instructor (G.P.)
H
- M. Martin, LOT Instructor (G.P.)
- B. Sokso, Licensing l
J. Monaghan, Operation (*) Denotes persons attending exit meeting 3.0 Examination Related Findings / Conclusions 3.1 The following is a-summary of general strengths and deficiencies noted on the operating tests. This information is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is required.
Strengths a.
Good use of Technical Specifications by SR0s.
b.
Good overall control board operations by R0s, c.
Knowledge of entry conditions for Emergency Procedures, d.
. Good use of Emergency Trip-200 Series Procedures.
Deficiencies a.
Implementation of step LQ-7, of Trip procedure T-117, for terminating and preventing all injection into the RPV.
b.
Informal communications between crew members.
c.
Inconsistent use of Alarm Response Procedures.
3.2 The following is a summary of general strengths and deficiencies noted from the grading of the SRO and RO written examination. This-information is being provided to aid the licensee in upgrading licensee requalification training programs. No licensee response is required.
Strengths a.
Knowledge of recirculation pump restart limitations.
b.
Knowledge of Thermal Limits.
c.
Immediate operator actions for " Inadvertent Opening of a Relief Valve," OT-114.
d.
Knowledge of Feedwater Control System response on a transmitter failure.
-
_ _ _ _ _ _ _ _ - -
E...
-a I
-
';
p
-
l
'
<
,
t
1
i
Deficiencies a.
Knowledge of hydraulically isolating an HCU and still maintain l
cooling to the rod.
.
t
.b.
Knowledge of basis for " Alternate. Shutdown Cooling," T-115.
L c.
Definition of Delayed Neutron Generation Time.
0 3.3 Training Program Comments
'A review of-the simulator portion of the operating test. indicated l
.
training was weak in the area of " Level / Power Control," procedure
.)
T-117, specifically,-that step in the procedure which requires the
- '
operators to lower level by terminating and preventing all injection
-
into the RPV. Two (2) of the three (3) examination crews had difficulty implementing that step, in that all systems were not
. prevented from injecting as required. This apparent weakness was discussed with the' facility and actions would be initiated to analyze and correct the problem.
Except as noted below, the applicants were well prepared for the licer : mg examinations. The facility provided reference material was' A equate.and in accordance with the NRC's "90-Day letter."-
The licensee was granted a one-week extension on the due date for.
submitting the Personal Qualification Statements (NRC Form 398), for two individuals, after the training department expressed a concern about their satisfactory completion of the training program. This extension was granted to' provide time for the license'e to further evaluate the applicants. The licensee decided that only.one of the two would be recommended to the NRC for a license examination. NRC review of the results of the individual's operating test indicated a wide range of weaknesses. The candidate failed the Control Room Systems and Integrated Plant Ooerations portions of the Operating Test. The candidate did not possess an adeq'uate knowledge in the area of plant system design and operation. The examination brings into question the adequacy of the certification process established by the licensee. This concern was discussed with the licensee when they.were notified of the final examination results. The licensee agreed with the NRC's evaluation and stated in retrospect that the candidate should not have been recommended for a licensing examina-tion.
4.0 Management Meeting On June.1,1989, a pre-examination review was conducted at the NRC Region
.I Office. The licensee was informed that, although a post-examination review was not conducted, comments on the written examination would be accepted. These comments were received at the exit meeting.
-
a_
_ _ _
_ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - _ _ _ _ - _ - _ - _ _
. _ _ - - _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
L..
U
,
The control ' room staff was very cooperative in maintaining an environment
,'
conducive to an operating test administration.
Facility access went smoothly with good support from Health Physics:and l
Security.
1:
The-examination strengths and deficiencies in. section 3.1 and the training comments in section 3.3 were~ discussed along~with possible
- l corrective actions. The final results of the examination were not discussed at its exit meeting.
Every' effort would be made to provide the applicants results in approximately 30 working days.
It was requested that the licensee provide an evaluation report on the individual administered the requalification re-take examination per ES-601, section E.
This report was submitted June 28, 1989, to the regional office and did meet the requirements of ES-601.
Attachments:
1.
Senior Reactor Operator Written Examination and answer key -
2.
Reactor Operator Written Examination and answer key 3.
Facility Comments on Written Examination after facility review
.4.
NRC response to facility comments 5.
Simulator. Fidelity Report.
,
...5
_ - _
}l ATTACH InENT l
,
DRAFT COPY
.
U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 1 FACILITY:
Limerick 1 REACTOR TYPE:
BWR-GE4 DATE ADMINISTERED: 89/06/12 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 orade 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 24.00 4.
REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
32.50 32.50 5.
EMERGENCY AND ABNORMAL PLANT
\\
EVOLUTIONS (33%)
43.50
' 43.50 6.
PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%)
100.0
%
TOTALS FINAL GRADE
~
All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature DRAFT COPY
- - _ _ _ _ _ _ _ _ - - _ - _
-
hE
,
'4.
REACTOR PRINCIPLES (7%)-THERMODYNAMICS Page -2 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
l\\
.,
.
QUESTION 4.01-(2.00)
for EACH of the events below, STATE the order in which the three reactivit Doppler) y coefficients (Moderator Temperature Coefficient, Void, will' affect reactor reactivity (FIRST, SECOND, and. THIRD).
ALSO indicate whether.each coefficient will be adding + or
.
reactivity during the event. Use all three coefficients for each event, a.
A turbine stop valve' fails shut at power (1.0)
b.
One recirc pump trips at power (1.0)
ANSWER 4.01 (2.00)
. a.
Void (+), Doppler (
, MTC
-
b.
Void (-), Doppler (+, MTC
+
[+0.25] for. each + or - and [+0.25] for the order REFERENCE 1.
lL merick: LOT-1450.
2.
Limerick: LOT-1460.
3..
Limerick: LOT-1480.
292004K110 292004K105 292004K101'
293006K113 291004K104
..(KA's)
..
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
i
_ _ _ _
_---_ --____ _ -____ - _ _-____________ -_ _ _ - _ _ ___-
-
~.,
'a-
...
h'.
.
g
.
-
.
,h
.
REACTOR PRINCIPLES (7%). THERMODYNAMICS ~
Page;. 3'
'
4.
{
.(7%) AND. COMPONENTS (10%) (FUNDAMENTALS EXAM)
I L
L
^ QUESTION ' L4.02 (1.00)5 SELECT which ONE -(1); of the following statements correctly defines the Delayed. Neutron _ Generation Time.
m
'The length of time'between.....
(1.0)
(a.). ~ neutron' absorption and subsequent delayed neutron thermalization.
. (b~. );
the production of a delayed neutron and subsequent neutron absorption.
(c.)
the production of delayed neutrons in successive' lifetimes.
'(d.)
delayed neutron thermalization and subsequent neutron absorption.
- ANSWER 4.02 (1.00)
'
(c.)
[+1.0]
REFERENCE \\
1.
Lime' rick': LOT-1420, L.0.'s 5 and 6.
292001K102
..(KA's)
,
..
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
. _ _ _ -.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _
. - _ _ - _
_ _ _
4.
REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 4 (7%) AND COMPONENTS (10%) (FUNDAMENTALSEXAM1 QUESTION 4.03 (1.00)
The power generated by the reactor at the beginning of core life comes from U-235 thermal fission and U-238 fast fission.
Later in core life, larger and larger fractions of power generation are produced by fission of WHICH ONE (1) of the following isotopes?
(1.0)
(a.)
Am-241 (b.)
Cm-244 (c.)
Pu-238 (d.)
Pu-239 ANSWER 4.03 (1.00)
(d.)
[+1.0]
REFERENCE 1.
Limerick: LOT-1420, L.0.'s 5.b. and 9.
292003K103
..(KA's)
~
QUESTION 4.04 (1.00)
STATE the reason that the xenon concentration will INCREASE following a significant DECREASE in reactor power.
(1.0)
ANSWER 4.04 (1.00)
!
The decrease in the burnout term [+0.5] along with the continued production of xenon from iodine at the higher power dominates [+0.5]
causing the xenon concentration to increase.
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
_______-___-____-______ ___-_ _ _-___ _
_.
l
'4.
REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 5 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
REEERENCE 1.
Limerick:
LOT-0950 L.0. 2 b.
292006K102
..(KA's)
\\
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ _ _ _
_-
_ _ _.
,. d i
14. REACTOR PRINCIPLES'(7%)' THERMODYNAMICS Page 6~
(7%)-AND COMPONENTS (10%).(FUNDAMENTALS EXAM)_
,
i-QUESTION-4.05 (2.00)
MATCH'th'e following terms lon the left with their correct definition-on the right.
(Only one correct answer each)
(2.0)_
TERMS ANSWERS DEFINITIONS a.-
Keff:
1..Keff =.1.0 b.
Critical 2.
The fraction of the thermal-neutrons that had been born
~.
Supercritical by the decay of delayed c
neutron precursor, d.-
Excess Reactivity-3.
The fraction of fission e..
Effective Delayed-neutrons born from the-Neutron Fraction decay of a delayed neutron precursor.
f.
- autdown Margin 4.
Multiplication factor
,
-dealing with an infinitely large reactor 5.. Neutron population is decreasing from
\\
generation to generation.
6.
A measure of how far the I
reactor is below the critical condition.
7.
Multiplication factor dealing with a realistic reactor.
This includes leakage.
8.
The amount of additional i
reactivity built into a
"
reactor to allow it to reach full power for its operating cycle life.
9.
Keff > 1 10. A measure of the departure from criticality.
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
__ _ _ _ _ _ __ ___ _ - _ _ _ _ __
__ _
__
.,
4.
REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 7 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
ANSWER 4.05 (2.00)
a.
b.
I c.
d.
e.
f.
6, 0 03
[+0.33] each REFERENCE 1.
Limerick:
LOT-1420.
2.
Limerick:
LOT-1430.
292003K104 292002K110 292002K107 292002K111
..(KA's)
QUESTION 4.06 (1.00)
SELECT ONE (1) of the following statements which correctly describes the effect of an INCREASE in the amount of non-condensible gases in a steam turbine condenser.
(1.0)
(a.)
Condenser pressure decreases.
-(b.)
Circulating water outlet temperature decreases.
(c.)
Turbine Generator megawatts decrease.
(d.)
Condensate subcooling increases.
ANSWER 4.06 (1.00)
(c.)
[+1.0]
l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
i.
_
_
_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ - - -
_ _
--.
-
4.
REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 8 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
REFERENCE i
1.
Limerick: General Electric Thermodynamics Text, Section 6.
2.
Limerick:
LOT-0500.
293007K107
..(KA's)
QUESTION 4.07 (1.00)
SELECT ONE (1) of the following statements that describes a correct heat balance relationship.
(1.0)
(a.)
If the feedwater temperature used in the heat balance calculation was HIGHER than the actual feedwater temperature then actual reactor power is HIGHER than calculated reactor power.
-(b.)
If the reactor recirculation pump heat input used in the heat balance calculation was OMITTED then actual reactor power is HIGHER than calculated reactor power.
(c.)
If the steam flow used in the heat balance calculation was LOWER than the actual steam flow then actual reactor power is LOWER than calculated reactor power.
(d.)
If the RWCU return temperature used in the heat balance calculation was HIGHER than actual RWCU return temperature than actual reactor power is LOWER than calculated reactor power.
l
!
l ANSWER 4.07 (1.00)
l (a.)
[+1.0]
REFERENCE 1.
Limerick:
LOT-1300, 2.6/3.1 2.3/2.9 l
293007K113 293007K111
..(KA's)
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _
. _ _ _.
.
__
_
__
__
. _ _ - _ _
__ _
_ _ _ _ - _ _ _ _ _ _ _ _
_
-_.--
.-
.
.
.q. ;
(4.
REACTOR PRINCIPLES (7%)' THERMODYNAMICS Page 9
- (7%) AND COMPONENTS (10%)-(FUNDAMENTALS EXAM)
'
h:-
-QUESTION'
4.08..-
(1.50)'
'
MATCH the a CONDITION;(ppropriate FAILURE MECHANISM ~(F1-F3) AND LIMITING
,
L1-L3).to each Thermal Limit (a-c) given below.
FAILURE LIMITING MECHANISM.
CONDITION a.
Linear Heat Generation Rate:(LHGR)-
'(0.5)
.b.
' Minimum-Critical Power Ratio (MCPR)
(0.5)
c.
Average Planar-Linear Heat Generation Rate (APLHGR)
(0.5)
FAILURE MECHANISML LIMITING CONDITION
- F1.
Clad cracking from L1. Clad. plastic strain less becoming vapor, than 1%.
" blanketed".E F2.
Clad cracking caused by
_L2.
Maximum clad temperature high stress from pellet of 2200 degrees F.
expansion.
LF3.
Clad melting' caused by L3. Coolant transition boiling.
-decay & stored heat-following a LOCA.
ANSWER 4.08 (1.50)
~
' 0.25'
a.
F2.
+
L1.
+0.25
'
b.
F1.
~ 0.25
+
L3.
l+0.25
' 0.251
'
'c.
F3.
+
' 0. 25.'
L2.
+
l-
!
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
1-
.
. --
_
.
_ _ _ - -
_ -_.... - - -. - - - - _ _ _ _ _
_ - _ _ -.... _ _. - _ _
_ _. - - _ _
, _.. _ _ _. - _ _ _ _ _
-
\\
t
i 14. REACTOR PRINCIPLES:(7%) THERMODYNAMICS-Page 10 a
t 1.7%) AND COMPONENTS (10%)-(FUNDAMENTALS EXAM)-
"
-
I REFERENCE =
fl.'
Limerick:, LOT-1380, L.0. 2.
'
12.
Limerick: LOT-1390, L.0.-3.
.
293009K107.-
-293009K108'
293009K111 293009K112-
..(KA's);
-QUESTION: :4.09
- (1.00).
- During a cooldownLof the reactor. vessel from outside.the control
. room, reactor pressure decreased from 885 psig.to 595 psig in
,
'
,
.one HALF hour.
~
' DETERMINE the reactor cooldown rate in deg/hr. (SHOW all work).
(1.0)
ANSWER.
4.09 (100).
.
First, convert psig, to. psia, by adding 14.7 psi.[+0.25]
- Then, referring to the' steam tables;
.
900 psia. = 532 deg.F [+0.25 610 psia.=488deg.F[+0.25.;
l'
'
532 deg.F -- 488 deg.F =44 deg.F / half
,
- hour, or 88 deg./hr. (+/- 2 deg./hr.) -[+0.25]
REFERENCE.
1.
Limerick:
LOT-1100, L.0. 3.
l, 2.
Limerick: l LOT-1230
,
293003K123
..(KA's)
l l.'
,.
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
.
-
m.m
_mm--.
-.
_-_._-_w_..___.m_m._m
..a m_
_____&a m
_
.
- --
k *.
,
,
4.
REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 11 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
QUESTION 4.10 (1.00)
SELECT the correct statement concerning the operation of a jet pump.
(1.0)
(a.)
As flow exits the jet pump diffuser, fluid velocity increases.
(b.)
The static pressure at the jet pump nozzle is greater than the downcomer annulus pressure.
(c.)
The low pressure at the nozzle discharge draws the surrounding fluid in the jet pump throat area.
(d.)
The constant area of the mixing section maintains the pressure constant.
ANSWER 4.10 (1.00)
(c.)
[+1.0]
REFERENCE
\\
1.
Limerick:
LOT-1290 L.0. 10.
293004K105
..(KA's)
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
_.
. _ -.
_
_
- __
_ _
_ - - _ _
_
.-
_ _ - _ _ _ - _ _ _ - _ _ _ _ - - - - _ _ - _ _ -
- -.
,
i,l
,
.
4.
~ REACTOR PRINCIPLES (7%)-THERMODYNAMICS Page 12 (7%) AND COMPONENTS (10%) (FUNDAMENTALS: EXAM)
-QUESTION- '4.11-(2.00)
' SELECT ONE (1) of the pump curve changes-(column B) which describes the effects. for EACH of the pumping system modifications (column A).
ASSUME one single centrifugal pump is already:in the system. (ASSUME ideal conditions.)
Not all answers may be used and some may be used
,more than once.
.(2.0)
COLUMN A ANSWER COLUMN B Pumping-
.
Pump System Modifications-
' Curve Changes
'(a.) ' Throttle the~ discharge 1. Decreased flow rate
'"
valve on.the existing.
with decreased head.
pump 2. Increased head and (b.)' Add one identical pump increased flow rate.
in parallel.
3.-Double the flowrate (c.) Add one identical pump with the same head.
in series.
..
4.' Increased head with
.(d.) _ Double-the speed of the decreased flow rate.
existing pump.
\\
-5. Double the head with the same flow rate.
' ANSWER-4.11'
(2.00)
l; (a.)
4.
[+0.5]
ma -
l (b.)
4"
[+0.5] J d
(c.) X [+0.5].5
i_
.- (d. )
2.
[+0.5]
I (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _
-
7,"
.
,,
- -
- - - - - - - - -
-
--
,
'/!^ d J.
,
,
m
..
,
,.
4 4. PREACTOR' PRINCIPLES (7%) THERM 0 DYNAMICS'.
.
Page-131
- y-(7%)-AND COMPONENTS (10%)-(FUNDAMENTALS EXAM)'
REFERENCE.
-
b'
- l '.
TLimerick: - ' LOT-1290' L.0. 13-& 16.
l zq
!
l 293006K108-
.. (KA's)-.
-
I e
I ir (1.00)(
1 QUESTION 4.12
,
~ Water' hammer i's Edefined as the. liquid shock imposed on a piping
'
system resulting-from a rapid change in flow.. The factors affecting-themagnitude'of-impulse'forcearetime,(a.)
q
,
[..
,
and (b.)
(1.0).
l o
...
,
i k
,,
i i
ANSWER 4.12 (1.00)'
ci 0.5]
( bat Ceeur n D4fC
^ """^ *h "
" "NS '
\\S % Tne eres %csto4SC To ?A w w.h
!
REFERENCE'
\\
1.
Limerick:
LOT-1291
<
q 291006K114
..(KA's)
)
i ll, j
o
,
-QUESTION'
4.13 (2.50)
-a.
A condensate filter / demineralized is removed from service
['
on high outlet conductivity of 0.1 micrombos/cm and high delta-P-of psid.
(0.5)
!
- b.
STATE why the following parameters are used as indications that filter demineralized should be removed from service.
(2.0)
- 1. High conductivity
~2. High delta-P-l I
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
-
_
- - -
-
-
--
-=-- -- - --
A
-
_
.
.
.
.
_
,_
.
__
-
.
.
g y
>tr,
'
.;
p
"4.
' REACTOR-PRINCIPLES (7%) THERMODYNAMICS:.
Page 14
.g
.(7%) AND COMPONENTS (10%).(FUNDAMENTALS EXAM)
]v i
u
- ANSWER'
4.13 (2.50)
g La..
[+0.5]:
o
~b.
1. (Conductivity is affected by. chloride, pH and other.
impurity concentrations.)
Therefore high conductivity is a' good. indication of degraded water quality.
1%tt Att,m " laucAwoo or top hea AcGc bch2Tio#'.)[+1.0]
.
2. High' delta-P is an indication of particulate clogging (and_ reduced filtering efficiency.)
- [+1.0]
REFERENCE 1.-
Limerick:
LOT-0520 L.0. 6. c & d.
Limerick: Tech Specs' Bases Po. B 3/4-4-3
,
,.
291'007K108
'291007K109
..(KA's)
QUESTION'
4.14
.'(1.00)i Given the following conditions: Recirculation pumps ~are runnin
';_
constant \\ minimum speed, low thermal reactor. power (approx. 20%)g at
<
.
-STATE how AND why core flow varies (INCREASE, DECREASE, or REMAIN THE SAME) when reactor power is increned by control rod withdrawal.
(1.0)
ANSWER 4.14 (1.00)
-Core flow would increase [+0.5] due to an increase in natural
>
circulation [+0.5].
REFERENCE 1.
' Limerick: LOT-0040, L.0.13.
'291006K112
..(KA's)
l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _
__ -
-
-___
- _ _ - _
_.
.
-
L4. 4 REACTOR PRINCIPLES (7%)' THERMODYNAMICS Page 15 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
.
QUESTION 4.15 (3.00)
'
543.1.A " Start-up of the Recirculation System" limits the number of starts.that may be attempted on a recirculation pumps, a.
With Motor Generator AND recirculation pump at ambient temperature, (1)
pump start (s) may be attempted.
Another pump start may NOT be attempted until a waiting period of (2)
has elapsed.
(1.0)
b.
With Motor Generator. AND recirculation pump warm from at least fifteen (15) minutes operation, (1)
pump start (s) may be attempted. Another pum attempted until a waiting period of (2)p start may N01 be has elapsed.
(1.0)
c.
The RESTART limitations are to protect which ONE (1) of the following?
(1.0)
(1.)
The recirc. pump bearings due to inadequate lube oil being supplied on pump starts by the shaft driven oil pumps.
(2.)
The motor generator windings from overheating due to increased current flow on pump starts.
\\
(3.) ' The power supply to the recirc. pump motors due to possible internal electrical faults causing the pump trips.
(4.)
The fluid drive coupling scoop tubes from exceeding their design cyclic stress limits.
ANSWER 4.15 (3.00)
a.
1. two
[+0.5]
2. one hour
[+0.5]
b.
1. one
[+0.5]
'2. one hour
[+0.5]
c.
(2.)
[+1.0]
l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
_ _ - - _ _ _ _ _ _ - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _
,
_
_
_
p n
y
,
ri
.
~
4. < REACTOR PRINCIPLES (7%)' THERMODYNAMICS ~
Page 16-
~
p,
-(7%)-AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
.m
[.K,
..
. REFERENCE 1.
Limerick: LOT-0030, Pg.~28.
.s
- 2.
Limerick: 543.1.A., 7.1..
<<
291005K106
..(KA's)
QUESTION 4.16 (2.00)
a.-
DEFINE Net Positive Suction Head (NPSH).
-(1.0)
b.
EXPLAIN WHAT happens and WHY to the'available Recirculation
Pump NPSH-if HPCI initiates at 70% power.
(1.0)
-
- ANSWER 4.16 (2.00)
a.
NPSH is difference between total pressure at the eye of the pump and saturation pressure for the liquid..
.
(Equation Acceptable: NPSH = Psuc - Psat)
opsa r up - w.; - wq+ g[-+1.0]
- b. c The NPSH would increase [+0.5] because the temperature of the feedwater'would decrease,.thus increasing the subcooling at the eye of the recirculation pump.
[+0.5]
REFERENCE 1. -
Limerick:
EIH: Heat Transfer and Fluid Flow, Chapter 6, L.0' # 10.9, 10.10.
.
2.
' Limerick:
LOT-1210 3.
Limerick:
LOT-1230.
'
!
291004K106
..(KA's)
I
..
l
,
I l
(***** END OF CATEGORY 4 *****)
L
___
-
__
-
-
-
-
-
mm y-
.
- --- -- - - - - -
- - - - - -
- - - - - -
- -
c-
.
,
'
',g ed i'.X, e
,
S" '
" Sit EMERGENCY'AND' ABNORMAL PLANT EVOLUTIONS.
Page 17..
f (33%L,
,
" 1.g
"
QUESTION :5.01 (l'00)-
.
' N Ascording' to SE-1 " Remote Shutdown" SELECT ONE:(1) of-the-following -
.RCIC system interlocks whichl remain' active when control is -
transferred'to::the~ remote. shutdown panel.-
(1.0)
,'
,
h
~
-- ( a. ). RCIC. turbine trip on_overspeed.
"
'
- (b.)
' Steam supply valve closure on high reactor water level.
,4
- (c.).-
Transfer _'of. suction.from CST.to suppression pool.
(d;):
. Start on low reactor water level (-38").
U ANSWERL
- 5.01~f(1.00) _
(a.):;
~[+1.0].
.1 REFERENCE'
-- 1.-
-Limericki LOT-0735 L.0. 4.f.
- 2.
- L\\imerick:- SE-1.
-
'295016K201-
...(KA's)
'l
,
(***** CATEGORY. 5 CONTINUED ON NEXT PAGE *****)
,
.
.
E
- o+
.
_
,
..
5.
EMERGENCY AND ABNORMAL' PLANT EVOLUTIONS-Page 18-
>
D (33%)
-QUESTION ~
5.02
'(3.00)
,
=Concerning OT-114 (REV. 4) " Inadvertent Opening ofLa Relief. Valve":
FILL in the correct response for each blank in the following
' statements ~on Immediate Operator Actions.
a.
Place loop (s) of Suppression Pool Cooling in service..
-(0.5)'
t tb.
1 Rapid shutdown per GP-4 initiated if the valve-cannot be shut within minutes.
(0.5)
'
c.
- If the.SRV cannot be shut within (1)
minutes or! suppression pool. temperature reaches (2)
deg F,. place the reactor mode switch in (3)
(1.5).
.
d.
.High suppression pool temperature is an entry condition for T-
(0.5);
.
f LANSWER 5.02'
.(3.00)
\\
a.
2 (both) [+0.5].
.
'b.
'I.5 minu'tes-[+0.5]
. c '..1.
2 minutes' ~+0. 5'
.2.
110 deg.F l+0.5l 13.
shutdown [+0.5]
.
d.
.T-102 (Containment):[+0.5]
REFERENCE 1.
Limerick: 0T-114.
295013A102 295013G010 295013G011
..(KA's)
i (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
,
_. -. _ _ _ - _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
_ _
5. ' EMERGENCY AND ABNORMAL ~ PLANT EVOLUTIONS Page 19 (33%)
f'
QUESTION 5.03 (1.00)
SELECT ONE (1) of the following * statements which is an immediate action in accordance with OT-117 "RPS Failure".
(1.0)
(a.)
Perform rapid plant shutdown per GP-4.
(b.)
Initiate rod insertion using the Reactor Manual Control System.
(c.)
Place the mode switch in shutdown.
(d.)
Trip the reactor recirculation pumps.
. ANSWER 5.03 (1.00)
(c.)
[+1.0]
REFERENCE 1.
Limerick: 0T-117.
295015G010
..(KA's)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
,_ _
,
,
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 20 (33%)
QUESTION 5.04 (1.00)
SELECT ONE (1) the following statements which is the basis for the Technical Specification minimum suppression pool level (22 ft).
(1.0)
(a.)
To ensure that the downcomers are submerged and that no blowdown flow can bypass the suppression pool.
(b.)
To ensure that adequate head will be available to the suction of the ECCS pumps.
(c.)
To ensure that a sufficient volume is available to absorb the heat released during a blowdown and not exceed the design pressure of containment.
(d.)
To ensure that the SRV tailpipes will remain submerged so that r,o steam flow can bypass the suppression pool.
ANSWER 5.04 (1.00)
(c.)
[+1.0]
\\
REFERENCE 1.
Limerick: Technical Specifications B3/4-6-4 2.
Limerick: TRIP Procedure T-102 295030G004 295030G011
..(KA's)
.
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
l
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
...-
_ -. _
-
.
. - _.
,.- --
t
- Y._
,
.. c
?
- ,.._ 9 c'
l%
,
5. I EMERGENCY ~AND'ABNORMAliPLANT EVOLUTIONS Page.21-(33%)-
In f,
~
.','
QUESTION 5.05 :' -l(1.00) '
.
. SELECT which ONE (1)'oflthe following failures in the Electro-Hydraulic; Control:(EHC)systemwouldcauseahighpressure
- transient' on the+ reactor. ASSUME no other failures are present-in the system.
(1. 0) '.
(a')-
Pressure': regulator ' A'. fails high.
.
~ (b.);
Pressure regulator ' A' fails low.-
.(c.)
. Pressure setpoint' fails high.
(d.);. Pressure ~setpoint' fails low.
JANSWERL
'5.05 (1.00)-
(c.)
[+1.0]-
REFERENCE:
1.
Limerick:.
LOT-0590 295025K208'
295025A102
..(KA's)
+
.
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
-
,
-
_.
_
-_
_ _ _ - - _ _ _ _ _ _ _ - _ _ - _ _ -
_-
sa
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 22
~
=(33$)
o QUESTION 5.'06-(3.00)
i;,
Concerning the immediate actions on a loss of A.C. power:
a.
Confirming indications are received that a loss of 0FF-SITE power has-occurred.
1.
STATE the TWO (2) DIFFERENT plant components that require starting verification.
~
(1.0)
2.
STATE the TWO (2) system lineups that must be performed in order to supply cooling to the drywell coolers.
(1.0)
b.
Subsequent to the loss of off-site power a loss of ALL A.C.
occurs. STATE the TWO (2) plant responses that must be verified.
(1.0)
ANSWER 5.06 (3.00)
a.
1. 'a.- Diesel Generators
' 0. 5'
+
b.
ESW pumps l+0.5:
\\
[+0.5]
b.
Line up RECW to Drywell Coolers
[+0. 5]
b.
1.
Reactor Scram
~ 0. 5'
+
' 0.5 2.
MSIV Isolation
+
REFERENCE 1.
Limerick:
LOT-1566, L.0.'s 2 & 3.
2.
Limerick:
E-10/20, pg 1 & 2.
3.
Limerick:
E-1, pg 1.
295003G010 295003G011
..(KA's)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
- _____- - -__ _ _ _ _ _ _ _ _ _ - _ _ _ _
}-
"':-
~
-
' - - '
- --~
~
-~~
--
~ ~ ~ -
W4, x'
"' 5; EMERGENCY AND ABNORMAL ~ PLANT EVOLUTIONS
.Page 23
'
-(33%)
-.o r
I UESTION.5.07 (1.00)
Q
'if the. Reactor Water Level reaches 100 inches. STATE the. reason
"
'
for-this action.:
.~ (1.0)
ANSWER.
5.07:
(1.00).
To prevent unnecessary flooding of the main steam lines.
[+1.0]
REFERENCE'
1.
Limerick:
Technical Specifications,.3.11.2.1 a & b.
2.
Limerick:
3.
Limerick:. LOT-1520.-
295008A103 295008G006-
..(KA's)
\\
.
QUESTION 5.08 (1.00)
Concerning the Feedwater Control S the reactor. level setpoint to (a) ystem, the automatic.setdown'of inches'is' initiated-(b)-
seconds after the level decreases to (c)
inches.
This avoids unacceptably (d)
water levels following SCRAMS from high power.
(1.0)
ANSWER'.
5.08 (1.00)
.l*7 R
lhSN(inches)
l a..
b.
(seconds)
c.
12.5'(inches)
d.
high
.[+0.25] each f
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
p
,
- _ - - _ _ - _ _ - _ - - - -
--
.
m s :i-.,
,
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 24 in
.(33%)
i
,
h
' REFERENCE r
?
-1.
Limerick: LOT-550 IV.:A.7.
'
295006K304
..(KA's)
>.
-t
. QUESTION 5.09 (1.00)'
The. TRIP procedure for SCRAM T-100, Step S-7, directs operators.to
" trip (the turbine when generator load reaches 50 Mwatts.1) of the-following statements w SELECT ONE ifor this step.
(1.0)
,e f(a.) '
Assures there is-adequate. capacity of the bypass valves to handle this load transfer.
"'
(b.)
' Guards against overspeed of the turbine by preventing the generator: from tripping on _ reverse power.
- (c.):
Assures that.the End of Cycle Recirculation Pump Trip does not occur.
(d.)
Prevents MSIV' closure upon NSSSS actuation on low steam line pressure.
\\
.
. ANSWER 5.09 (1.00)
(b.)
[+1.0]
REFERENCE-1.
Limerick: T-100 LOT-1560 L.0.-5.
295006K305 295005K304
..(KA's)
L -
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ - _ _ _ _ _ - _ _ - _ _ _ -
-
5. ' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 25 (33%).
QUESTION 5.10 (2.50)
Pertaining to the Trip Procedures MATCH ONE (1) level in the right
~
hand column to each of the function statements in the left hand column.
(2.5)
FUNCTION STATEMENT ANSWER WATER LEVEL a.
Upper limit for Reactor 1.
+ 60 in water level per T-100 2.
+ 54 in b.
Lower limit for Reactor water level per T-100 3.
+ 39 in c.
Top of Active Fuel 4.
+ 12.5 in d.
Level required for T-111 5.
- 38 in
'
Level Restoration 6.
-129 in
e.
Entry condition for T-101 L
RPV Control 7.
-150 in 8.
-161 in 9.
-167 in
\\
ANSWER 5.10 (2.50)
a.
b.
ATR l
c.
9'
s d
e
[+0.5] each
(
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
- - _ _ _ _ _ - - - _ _ - _ _ -
c.,
-
-
,
,
p
,-
,
.,
c
,4
-
S '. EMERGENCY'AND ABNORMAL PLANT EVOLUTIONS Page 26L Id (33%)-
<
X L
REFERENCE:
1.-
Limerick: T-100, T-101, T-111, LOT 1560 L.0.3.
295031A101 295031A102-295031A103-295031A104
.. (KA's).'
.
-QUESTION: 5.11 (1.00)'
Trip procedure T-101 "RPV' Control" is in In accordance..
'with the' T-200 series procedures, TWO (2) progress.other. systems to be used to inject Boron into the.RPV IF Standby Liquid Control CANNOT
'be used are (1)
AND.(2).
(1.0):
.
-.,
A'NSWER 5.11
'(1.00)
'
1.
Control Rod Drive System (CRD)
2..-
Reactor Water Clean Up (RWCU)
j
[+0.50] each REFERENCE \\;
1.
Limericki Trip Procedures: T-101, T-110,-T-111, T-112
'
2.
Limerick: LOT -1562-295037A110'
..(KA's)
(***** CA1EGORY 5 CONTINUED ON NEXT PAGE *****)
___=
. _ _ _
- _ _ _ _ - _ _ _ _ _
._-_- -
.__________:______--_-______---_-___--_---__-__-
. _. - ___ _
,.
'
[
n 5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 27
(334* )
' QUESTION
_5.12-(2.'50) '
Given 'the initiating conditions in COLUMN A, Select the ' appropriate emergency classification from COLUMN B.
EP-101 is provided as-Attachment 2.
(NOTE: ~Each classification can be used more than once or not.at all.
If the initiating conditidn-does NOT meet-the entry level requirements, state NO CLASSIFICATION REQUIRED.)
(2.5)
COLUMN A~
ANSWER COLUMN B.
(Condition):
-(Classification)
a.
Confirmed earthquake of 1.
Unusual Event
.0.08g while at power.
2.
Alert b.
Unidentified leak' rate of 33 gpm from the reactor
- 3.
Site Emergency c.
Main Steam Line break 4.
General Emergency
. outside primary containment with the failure F022A &
F028A MSIV's to close d.
Suppression pool temperature exceeds the upper limit of the heat capacity curve AND RPV level below to Active Fuel (TAF) p of e.-
Offsite doses are calculated to be 3 rem whole body ANSWER 5.12'
(2.50)
a.
2.
[+0.5]
b.
1.
'[+0.5]
c.
3.
[+0.5]
d.
4.
[+0.5]
e.
.4.
.[+0.5]
-
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
_ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ - _
_ -
_ - _. - _ - - _ _ _ _ _ _ - - _ _ - _ _ _ _ - _
_ - - _ _ _ - _ _ _ - _ _ - - _ _ - _ _ - - -
,,.
,
,
,
'
.a.
y
,
f :5.- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 28
,'.2
'
(33%)-
,y i
. REFERENCE.
f..
' 1.
Limerick: ' LOT-1520, L.O. 1 (SRO).
,
- Limerick
- EP-101.1 2.
>
295038G011.
295016G011'
R95002G011
..(KA's)
QUESTION 5.13 (1.50)
,' In accordance with procedure SE-1 " Remote Shutdown", LIST the THREE (3) ways that the reactor can be scrammed if evacuation of the main ~ control. room' is required BEFORE immediate operator action
'can.beltaken.:
(1.5)
ANSWER 5.13
'(1.50)
1.
-Trip the Main Steam Line Rad Monitors (Aux.H Equipment Room) [+0.5]
2.
Open'the RPS breakers-at the 'Y'. panel (Aux. Equipment Room)
[+0.5]
\\'
i3.
Op'en.the RPS breakers at the RPS Breaker Panel-(Inverter Room 1)-
[+0.5]
As.s o Atc.tet AN R esee x e.s 10 Aute:meer uj/ SE-1.
Sies 4. 5. n, 4. s 7, AJb 9.5. A.
REFERENCE 1.
Limerick: SE-1 Rev. 9 pg. 2.
295016A101
...(KA's)
..
L (***** CATEGORY 5 CONTINUED CN NEXT PAGE *****)
'
. _ _ _ _ _
_-___ _______ _ _ _ _ ___ _ _ _ _ -
,
. _ - _ _,
!
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 29 (33%)
-QUESTION 5.14 (2.00)
Concerning T-115 " Alternate Shutdown Cooling":
a.
STATE the reason for maintaining Reactor pressure a minimum of 50 psi AB0VE Suppression Pool pressure.
(1.0)
b.
STATE the reason for maintaining Reactor pressure BELOW 154 psig.
(1.0)
ANSWER 5.14 (2.00)
a.
To ensure that the safety relief valves can be kept open.. [+1.0]
b.
To ensure that the' low head ECCS systems can provide make-up to the RPV.
[+1.0]
(W t Lt. At. S o Accatrr : " To Edsoe.c Sornc.icpT Ecouac Fi.ow REFERENCE M 00 Cr A T A C C c'A E - ")-
1.
Limerick:
LOT 1560 2.
Limerick:
T-115 3.
Limerick:
T-99 295021A104
..(KA's)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
- -
- _ _ _ _ _ _ _ _ _
___ __ - _
- - _ - -
_ - _ _ -
$
f
'
45. ' EMERGENCY'AND ABNORMAL PLANT EVOLUTIONS Page 30 (33%)
<
<
QUESTION 5.15'
(1.00)
OT-112. " Recirculation Pump-Trip" states that if both recirculation pumps have tripped, " Ensure RWCU is in service using two pumps."
SELECT ONE (1) of the following statements which describes the i
basis. for this. step..- ASSUME-recirculation pump trips occur at full
-
power operation.
(1.0)
(a.)
' Increased amount of particulate settle'out under these flow conditions. RWCU in-service will remove most of.the particulate.and reduce the likelihood of instrument plugging on recirculation pump restart.
. (b.)
Enhances natural circulation through the core by increasing the delta-T between the core and the bottom head regions.
. (c.. )
Maximizes the amount of. cold water removed from the bottom head ~ area and reduces the potential for thermal stratification problems.
~ (d.)
Prevents. idle recirculation loops from experiencing excessive cooldown from seal purge flow in-leakage which can cause excessive thermal stress transients on the loop piping on recirculation pump restart.
\\
ANSWER 5.15 (1.00)
(c.)
[+1.0]
REFERENCE.
1.
Limerick: LOT-1540 L.0. 4.
- 2.
Limerick: OT -112 295001G007
..(KA's)
.
.
(***** CATEGORY S CONTINUED ON NEXT PAGE *****)
l
..
___ _---_-_ _ _ _ _ - _ _ - - - _ - - - - - - - - - - - - - - - - - - - - - - -
I
..
. _ _ _ - _ _ - _ - - _ _ _ _ - _ _ _ _ _ _ _
,
R
- 5.
EMERGENCY AND ABNORMAL ~ PLANT EVOLUTIONS; Page 31-l'
(33%)
, QUESTION <
5.16:
(3.00)'
For each ofLthe_ conditions / situations in column A, SELECT ALL TRIP. procedure (s) from column B that should be entered.
(Consider
'the inital-conditions to be that'the plant is at 90% power operations.). Iflnone are applicable, state NONE.
NOTE: Not all
'of the procedures in column B need be used, and some may be used
.more than once.
(3.0)
COLUMN'A ANSWER COLUMN B (Conditions)
'(TRIPProcedures)-
a.
Scram from improper 1.
T-100 SCRAM ranging by operator
_
in intermediate range 2.
T-101 RPV control b.-
Drywell Temp =140 deg F 3.
T-102 containment control c.
Drywell Press = 1.7 psig
,
4.
T-103 secondary
.d.
HPCI area radiation containment control leveis-are 10 times the alarm level.
5.
T-104 radioactive
'
release control e.
Reattor Enclosure HVAC Isolated on~High Rad.
6.
T-111 level restoration 7.
T-112 Emergency blowdown 8.
T-117 tevel/ power control 9.
T-116 RPV flooding l
l L
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
J
_ - - _ _ _ - _ _ _ - - _ _ _ _ ~ _ _ _ _. - -
a
,
.
..
'
<.,,p
'
, y:.f. y 5? -EMERGENCY AND ABNORMAL PLANT EVOLUTIONS:
Page 32
.(33%)-
,,
.
1kNSWER'
5.16
- (3.00)-
a.:
1:
,
<
,b.:
3-
.(112,3'
_
c..
'
d.
1 e..
-4.
,
,
![+0.5] each REFERENCE
- 1.,
Limerick: LOT-1560 Trip procedures -T-100,101,102,103,104.-
295036G011
- 295032G011-295010G011-
'295038G011
..(KA's)
-QUESTION:. 5.17
,(2.00)
.\\
Concernirig condenser vacuum, MATCH ONE (1) SETPOINT (Right Column)-
.to the: automatic action (Left Column).~
(2.0)
Automatic Actio'ns ANSWER-
.'Setpoints-a.-
MSIV closure 1. 25" Hg Vac.
-
I
.b.
Feed Pump Turbine Trip-2. 24.7" Hg Vac.
,
c.
Main. Turbine Trip 3. 22.2" Hg Vac.
d.
Bypass Valve closure 4. 18.5" Hg Vac.
]
5. 11" Hg Vac.
6. 8.54" Hg Vac.
[
7. 7" Hg Vac.
.a :
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
!
l
,
,
'j
.
,
,
i
m
.. -
g
>
7 :j
<
t
,.9I
"
. 5) EMERGENCY AND'ABNORMALIPLANT EVOLUTIONS
' Page 33~
(33%)
- .
,
- LANSWER.
5.17:
(2.00).
"
. a.;
6.
'b. -
'5-
'
c.=
- 3
- d.
,
_
[+0.5] each >
.
REFERENCE y
.
.
'
1; Limerick:- LGS OT-116
- 2. :
- 295002K302; 295002K303 295002K304 1295002K305-(KA's)
..
- QUESTION 5.18
(1.00)
SELECT.0NE- (1) ofithe following' statements which describes the.
effect of a loss of CRD pump 'A' due to low suction pressure.
(1.0)
(a.)
A reactor recirc pump trip on loss.of ' seal purge flow.
(b.)
Automatic ' opening. of strainer ~ bypass. valve and CRD pump 'B'
.
Pauto-start when suction pressure is above'25 " Hg Abs.'
(c.)
The: suction flow path automatically transferring to the CST.
-(d.)
A continuing drop in system pressure unless manual action is taken.
- .ANSWERL L5.18 (1.00)
,
?q\\t
. (d.):
[+1. 0] '
'
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
...
_._u_..
_- __ __ "___
_.. _ _ _ _ _
_.m___m_.._-_m.-__ _ _ _ _ _ _ _ - _ _ _.
____.-_______-.-___m.m_
_ _ _ _ _ _ _ _ _ _ - *
.
_
. _ _ _ _ _ _
,.
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 25 (33%)
REFERENCE.-
1.
. Limerick:
LOT-0070 L.0. 5.a.
2.
Limerick: LOT-1550 L.0. 3.
3.
Limerick: ON-107 295022A202
..(KA's)
\\
l 1-l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
. - _ _ _ _ _ _ _ - _ _ - _ _ _ _ -
,,
_;_,__-_-
_ _ -
- _ _ _
<,
5.
EMERGENCY AND ABNORMAL PLANT-EVOLUTIONS Page'35
'i
(33%)-
'
~
-QUESTION 5.19 (2'.00)
.0ff-Normal procedure ON-113, " Loss of RECW", requires the tripping of the reactor recirculation pumps.if cooling is lost for ten (10)
minutes.
a.
SELECT ONE-(1) of the following statements which describes the basis for tripping the recirculation pumps ten (10) MINUTES after the loss of RECW.
(1.0)
(1.) 'To provide time to insert control rods and stay within the. constraints of the operating map once the recirculation pumps are. tripped.
. (2.') To provide time for the operator to re-establish RECW operability.
(3.) Continued operation of recirculation pumps after ten minutes could damage'the pump seals.
(4'.)
Continued operation of recirculation pumps after ten minutes could warp the pump shaft.
b.
SELECT ONE (1) of the following statements which describes the basis for.the TEN (10) SECOND interval between the tripping of recirculation pumps.
(1.0)
(1.) To prevent initiating reactor level 8 trips due to the level transient that would result.
'
(2.) To prevent placing the reactor in the region of thermal-hydraulic instability.
(3.) To allow time for the first recirculation pump's discharge valve ~to close prior to exceeding its designed operating delta-P.
(4.)
To allow time for the first recirculation pump to coast down prior to tripping the second pump.
I l
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
--
.:- _ - -__ ___ _ _ _ __- - -_ _ - ___- -__- - __ _ _
__ _ _ -___- ___ _ __ _ ____ _ - - -- _ __ _____- ___ __-_ _ - _ -_- _ _,
,
w i; ;,
a l'.
.,
S. ' EMERGENCY AND ABNORMAL' PLANT EVOLUTIONS Page 36-
,
[J (33%)
JANSWER-5.19-(2.00)
a."
' (3. ),
[+1.0]
n'
-
b.
-(1.)
.[+1.0].
'
REFERENCE'
1.-
' Limerick:
LOT-1550 L.0.-3.
~ '
l 2.
Limerick:
Lot-460.
3.
Limericki ' 0N-113.
295018K303
..(KA's)
.
QUESTION'
5.20-'
(1.00)
^
Step 2.4.1 of.0N-119 " Loss of. Instrument Air" states that reactor power should be. reduced.to less than 45%. if instrument air, pressuie drops below 80 psig. SELECT ONE (1) of the following statements which dek,cribes the reason for the power reduction.
'(1.0)
(a.)
Ensure adequate flow to the reactor should the condensate or feed pump minimum. flow valves drift open.
(b.)
Limit the reactivity transient caused by the closure of the MSIV's on a complete loss of air.
(c.)
. Prevent the violation of fuel thermal-limits caused by rods drifting into the core.
(d.)
Limit the reactivity transient caused by the feedwater
~
heater dump valves failing closed.
.
5 ANSWER 5.20 (1.00)
(a.)
[+1.0]
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
a.
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _... _ _ _ _ _. _ _ _ _ _ _
___
_-. -, _ -.
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 37 (33'4)
,
,
REFERENCE 1.-
'
Limerick:
LOT-1550 L.0.3.
2.
Limerick: ON-119 Bases.
295019K203
..(KA's)
\\
.
l (***** END OF CATEGORY 5 *****)
i
-
- _
_ _ _ _ - - _
_ _ _ -
__ -... - - _ _. _ _ - -..- - __ - - - ___ _ _ _.
_ _ - _ _ _ _ _
- .
6'.
- PLANT SYSTEMS (30%)' AND PLANT-WIDE GENERIC Page 38
'
RESPONSIBILITIES (13%)
QUESTION: ~6.01-(l'.00)
'
a.
Reactor water; level has decreased to below -129 inches.
Drywell pressure is 1.2 psig.- The proper ECCS pump (s)
is operating.. ADS. valves will open in seconds.
(0.5)
b.
Reactor water level-has decreased to below -129. inches..
Drywell pressure is 4.6 psig. The proper'ECCS pump (s)
is operating. ADS valves will open in seconds.
(0.5)
o
.
-ANSWER 6.01 (1.00)
a.
'525 [+0.5]
b.
105. [+0.5]
, REFERENCE.
1.
Limerick: LOT-0330, pp. 9, 12, and 13, Figure 6, L.O. 2, 5, and 6.
\\
218000K501
..(KA's)
i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
._ _
_ _ _
_ -.
. _ - - - -
_ - - _ _ _ _ _ _ _ _ - _ - _ - - - _ _ _ - - _ _ - _ _
_ _ _ _ _ _ _ _ _ _ _ _ -
g__
. _ _ -
,. s
.w
.
<
~6.
iPLANT SYSTEMS:(30%) AND PLANT-WIDE' GENERIC
'Page 39
'
RESPONSIBILITIES (13%)-
?>
' QUESTION 6.02
'(3.00)
For each of the reactor water levelsTin Column A SELECT'ALL of,
,'
the plant systems in Column B which would have DIRECT actuations/-
. confirmation setpoints associated with these water levels.
.(3.0)
Column A-
'
W'
(RPV Water Level).
Column B (PlantSystem).
La; level 8 1.~
NSSSS b.
level-3-2.
' c.'
- level 2 3.
.d.
level 1 4.
RRCS-5.
Recire. System 6.
'
-7.
Main Turbine ANSWER.
- 6.02 (3.00)
a.
.3,6,7'.D9G b.
2, 3, 5, 1 D o.'lO Tc.
1,. 3, 4, 6, (5) Ep.7C
.
'd.
- 1, 3 Do.'153
[30.25]-attr* [ i D.2od EAc.w ^B
'
. REFERENCE 1.
Limerick:
LOT-0050; LOT-0180, L.0. 2.a; LOT-0300, L.0. 4;
. LOT-0215, t. 0. 4.a.
.216000K404 216000K405 216000K406 216000K407
..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
,
_____.____._._____________.____.____..___mm___
_ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _
__
,_.
-
-
_
. _
_ _ _ - _, - _ - _
'
,
(6. ' PLANT' SYSTEMS (30%)- AND PLANT-WIDE GENERIC Page 40;
!
'
. RESPONSIBILITIES (13%)
b l
-
l#
.
,
.
. QUESTION.
6.03 (1.00).
SELECT ONE '(1) of Lthe' fo11owing statements-that describes the conditions will cause automatic initiation of the Standby Liquid
.: Control system..lHigh RPV Pressure (1093 psig) AND:'
(1.0).
- l I+
(a.)l Low reactor water level '(-38 ' inches) AND 118 see timer-
.
timed out.
(b.).
No APRM downscale (4%) AND 118 see timer timed out.
(c.)
. Low reactor water, level (-129' inches) AND 118 see timer timed out.
(d.)
No APRM downscale (4%) AND Low reactor water: level
- (-38 inches);
.
ANSWER'
6.03_
(1.00)
(b.)L
[+1.0]-
REFERENCE \\
1.
Limerick:. LOT-0310, L.0.10.
211000A308
..(KA's)
i
,
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
_ _ _ - - - -
. _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _
_ _ - _ _
___ _ _ _ _ _ _ _
-
_.
._
-
_-
__ _ --
__
6.
PLANT S'YSTEMS (30%) AND PLANT-WIDE GENERIC Page 41 RESPONSIBILITIES (13%)
QUESTION 6.04 (1.00)
Technical Specifications for Emergency Core Cooling System (ECCS)
allows "one (1) Automatic Depressurization System (ADS) valve to be inoperable for up to fourteen (14) days provided High Pressure Core Injection-(HPCI), Core Spray System (CSS) and Low Pressure Coolant. Injection (LPCI) are operable."
,
f Concerning the basis for this Technical Specification, SELECT which ONE (1) of the following statements is true?
(1.0)
(a.).
Safety analysis only takes credit for four valves, so one
. valve out of service'for up to fourteen (14) days does not reduce system reliability.
(b.)
-Risk assessment'for these valves indicates a negligible chance for a'second valve failure in fourteen (14) days.
(c.)
Safety analysis only takes credit for HPCI, together with CSS and LPCI to provide adequate decay heat removal from 100%
power for up to fourteen (14) days.
(d.)
Safety analysis shows heat capacity of the suppression pool is conservatively analyzed to allow continuous operation with one (1) fully opened Automatic Depressurization System (ADS) valve.
ANSWER 6.04 (1.00)
(a.)
[+1.0]
REFERENCE 1.
Limerick: Technical Specifications 3/4, 5-2, Basis Section.
218000G006
..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
.
--- --_ - _ _ _
-
.-
..
6.
PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 42 RESPONSIBILITIES (13%)
-QUESTION 6.05 (1.00)
SELECT the one (1) correct response. The opening of a SRV during full power operation would result in:
(1.0)
(a.)
A decrease in indicated core flow due to a decrease in delta-P across the reactor core.
(b.)
An decrease steam flow signal being sent to the feedwater control system.
(c.)
An increase steam pressure signal being sent to the electro-hydraulic control system.
(d.)
An increase in indicated core flow due to a decrease in delta-P across the reactor core.
ANSWER 6.05 (1.00)
(b.)
[+1.0]
REFERENCEg 1.
Limerick: LOT-0120, L.0. 10.a; LOT-0550, L.0. 2.
239002A109
..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
.
.. ___
- -, - - _ _ - - -
6.-
PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC'
Page 43
'
RESPONSIBILITIES (13%)
QUESTION 6.06-(1.00)
ASSUMING full power operation, three-element control, and no operator action, SELECT which ONE (1) of the followin would be the expected Feedwater Control System (FWCS)g statements response if the selected level-transmitter failed HIGH.
(1.0)
"
(a.)
RFP turbines would lock due to loss of level signal input and level would remain approximately the same.
(b.)
Steam and feedflow inputs would compensate for the error signal and level would. stabilize at a slightly lower level.
(c.)
Level input would automatically transfer to the other level transmitter and level would remain approximately the same.
(d.)
RFP turbines reduce speed in response to high level signal and level will continue to drop unless manual action is taken.
ANSWER 6.06 (1.00)
(d.)
>[+1.0]
s
REFERENCE 1.
Limerick: LOT-0550, L.0. 7.c.
!
259002A203
..(KA's)
.
l l
l I
l l
l
!
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
.
- - _ _
-
--.
_ - _ -
- - _ - _ _ _ - - _ - _
.
pg u
k4
- 6. JPLANT SYSTEMSL(30%) AND-PLANT-WIDE GENERIC Page 44-
~'
<
RESPONSIBILITIES (13%)
.
QUESTION 6.07 (1.00)
'
A-surveillance was run to test the ECCS actuation signal'on the-
, Division I. Diesel. Using-the following data and the attached
'
' Tech. Specs.
-
. Diesel RPM: 900 in-7' seconds
'
, Generator Voltage: 4052 in 9 seconds
' Generator Frecuency: 60 Hz in 9 seconds
,e
- Generator' Loac : 2800 kW in'135 seconds
- Diesel: Air Start Receivers::230 psig
- Generator was aligned with the emergency bus and run with the
'
- load that was recorded above for 60 minutes.
a..-
DETERMINE.the operability status of the Division I Diesel Generator (0,5)
b.
. STATE the Tech.; Specs. used for this' determination. ASSUME no.other trip. inputs are being-tested.
-(0.5)
. ANSWER 6.07 (1.00)
Diespl shoul'd be declared IN0PERABLE. [+0.5]
a.-
k b.:
Tech. Spec. 4.8.1.1.2.a.A [+0.5]
-
mw REFERENCE-1.
Limerick:
LOT-0670, L.0. 2.a.
264000G005
..(KA's)
-QUESTION 6.08 (3.00)
STATE _SIX (6) control room indications which could verify that a reactor safety relief valve is open. ASSUME that the Reactor is at 100 % power.
(3.0)
,
'(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
___.:_______
_ _ _ _. _ _ _ _ _
_ _ - _ _ _ _ _ _ - _ _ - _ _ _ - _ - _ - _ _ _ _ _ _ _
.-
e
-
- ,;j
-
-
-
..
>
<
,
h,-
'
O i6. ' PLANT SYSTEMS '(30%) AND PLANT-WIDE GENERIC.
Page 45 RESPONSIBILITIES (13%)
,
'
.
\\;
'
tANSWER
.6.08
~(3.00)
L1. ' generator. load reduction
-
2. ' bypass; valve. closure
'3.
~SRV/ head vent-valve leaking ~ alarm 4.
safety relief valve open alarm
'
'
5.
relief valve position lights 6.
steam flow / feed flow mismatch 7.
increasing suppression. pool. temperature
- s>.
-rAo ec. Taw dny sTx76) $ETEO.50] each; max. [+3.0]
REFERENCE
-
1.
Limerick: OT-114
-
2.
Limerick: Technical Specifications 4.8.1.1.2.a.4.
239002A401
..(KA's)
!;
LQUESTION 6.09 (1.00)
A LOCA occurs concurrent with a loss of offsite power. SELECT which ONE (1) of,the following pieces of equipment must be MANUALLY.
restarted.
(1.0)
(a.)
dyrwell chiller compressors-(b.)
drywell chilled water pumps (c.).
CRD pumps (d.).
'ESW pumps
.
ANSWER-6.09 (1.00).
'(c.)
[+1.0]
_
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
-
_ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _
-
-
- - _ _.
.
. _ _
,
{
'
'
'
,
q r
.6.
-PLANT' SYSTEMS-(30%h AND. PLANT-WIDE GENERIC Page 46 RESPONSIBILITIES (33%)-
'
l<
,
'
' REFERENCE 1.-
. Limerick: LOT-0660, L.0; 6; LOT-0450 L.O. 9.
~ 262001K301 262001K602
..(KA's)
j
. QUESTION
'6.10 (2.00)
~
'.The following plant. conditions apply:
Reactor power 45%'-
Total. recirc ~1oop flow '35%.
' Two recirc loop operation.
.
LReactor power is being INCREASED to 75% with control rod manipulation ONLY.
Using the APRM flow-biased power formulas, DETERMINE if
.this power. increase would result.in a. ROD WITHDRAWAL BLOCK; FLOW-
~ BIASED NEUTRON FLUX SCRAM, Tor NO RESULT. ASSUME total recirc. flow remains constant.
(Showwork).
(2.0)
ANSWER-
_6.10 (2.00)
.\\'
.R. Block
= 0.58W +-50%- [+0.25]
= 0.58*(35) + 50 = 70.3%
[+0.5]
= 0.58W + 59%
[+0.25]
= 0.58*(35) + 59% = 79.3%
[+0.5]
Would result.in a Rod Withdrawal Block
[+0.5]
. REFERENCE 1.
Limerick:
LOT-0270, L.0. 2.a.
~2.
. Limerick: Technical Specifications 3.2.2.
215005A104
..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
______ __ _ _ _ _ t_ _---._ _____ _ _ _ ___ _ _ _ ____ ______ _--_ _ _ _ __ _ _ _ __ _
_
.
u...
,
.
l6. PLANT SYSTEMS.'(30%) AND PLANT-WIDE GENERIC Page 47
'
'
RESPONSIBILITIES (13%)
'
-QUESTION 6.11'
(3.00)
' For each of the.NSSSS group isolations in COLUMN A SELECT all'of-the plant conditions in COLUMN B that would initiate isolation signals.. If none are applicable, STATE NONE. Note - not all of the plant-conditions in COLUMN B need be used,.end some may be used more than once.'(ASSUME: the Mode Switch is in RUN)
(3.0)
COLUMN AJ COLUMN B Group Isolations ANSWER Reactor Conditions a.
MSIV's and Steam Drain-1.
Low reactor water level Lines (IA)
(-42 inches)
b.
Main Steam and Reactor 2.
Main steam line high
~
Sample Lines (IB)
rad (3.5X)
c.
RHR Heat Exchanger 3.
Steam supply low Vacuum Breaker Lines pressure (700'psig)
(IIC).
d.
High drywell pressure Lines (III)
(1.72)
e.
HPCI Turbine Exhaust 5.
Steam line low pressure Vacuam Breaker Lines (90 psig)
~(IVB)'
- AND-high drywell pressure f.
RCIC Turbine Exhaust (1.72 psig)
Vacuum Breaker Lines (VB)
6.
Low condenser vacuum-(11.5 psia)
'
7.
Standby liquid control initiation 8.
Steam line high flow (140%)
,
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
.
_
____ -
_ -
. _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - - _ - - _ - _ _ _ _ _
_.
6.
PLANT. SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 48 RESPONSIBILITIES (13%)
ANSWER 6.11 (3.00)
a.
2,3,6,8j(O D 'O b..
1, 2 D o,sa c.
1, 4 t'o 53 d.
1, 7 r. + o 53 e.
c+o.sn f.
NONE C+o Cl
{+0d5] cacii correct-response-.mm REFERENCE 1.
Limerick:
LOT-0180, L.0. 2.a.
223002K101 223002K102 223002K104 223002K107
..(KA's)
QUESTION 6.12-(1.00)
Given the following scenario, SELECT the ONE (1) trip that caused the RWCU isolation.
(1.0)
\\
-
-During startup, reactor water level is bein0 controlled with the reactor water cleanup blowdown line.
-Reactor water level is slowly INCREASING and the operator FULLY opens the blowdown valve to lower RPV level.
-Some time later annunciator F-2 on panel 186802, "RWCU System Isolated" is received and reactor water level is again INCREASING.
-ASSUME reactor water level is 28 inches; reactor temperature is 320 deg. F; reactor pressure is 75 psig.
(a.)
high filter /demin delta-P (b.)
high downstream pressure (c.)
hign reactor vessel level
]
(d.)
high filter /demin inlet temperature l
("*** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
i j
_--------_-----____J
.
w
-
I.
ie
,
.i 6.-l PLANT. SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 49.
,-RESPONSIBILITIES (13%)
-
t T
) ANSWER'
6.12 (1.00)
- (d. )-
[+1.0]
'
.
e REFERENCE'
-1.
Limerick: LOT-0110, L.O. 7.
!
204000A304 204000KO3
..(KA's)'
QUESTION 6.13'
(1.00)
'During a performance of the 7-day Operability Surveillance on
, Division'1 125VDC Battery System, it was found that Battery 1A1
'did not meets its category "A" requirements for float voltage.
Using the Technical Specifications, DETERMINE which ONE (1) of the
- following statements accurately reflects the status of the DC Electrical system.
(1.0)
(a'. ) - Division I is' INOPERABLE and must be' restored to operability wi' thin 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s-or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
. (b. )'
_ Battery 1A1 is OPERABLE if all of-its' category."B" limits are verified within limits in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and category "A" and "B" limits are met within 6 days.
.(c.)~
Battery 1A1 is INOPERABLE and must be restored to operability within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or verify the operability of the other Division I batteries within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(d.)
Battery 1Al is OPERABLE if all of the remaining category
-
"A" limits are verified within limits and the out-of-limit parameter is restored to operable limits within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
_ - _ _ _ _ _ - _ _ _ _ _ - _ _
_ _ _ _
.
,
- - - - -
,
'
'
.)Yl
'
,
6? PLANT' SYSTEMS-(30%) AND PLANT-WIDE GENERIC-Pag'e S0
'
'
-
RESPONSIBILITIES-(13%)
c cp
--
ANSWER.
- 6i13l -(1.00)
(b.)-
[+1.0].
Eh j s b-so Atte.PTAELE a.
-
P REFERENCE
.o 1.
Limerick: LOT-0690, L.O. 2.b.
.
2.-
Limerick: Technical Specifications, Table 4.8.2.1-1.
n 263000G005
..(KA's)-
n QUESTION 6.14'
(l'.00)
With the reactor operating at 80% power, the operator notices a sudden increase in BOTH reactor power AND water level. SELECT which ONE (1)_of the following events.would explain this transient.
(1.0)
.
(a.)
RFP turbine speed increase.
(b.)
'A main condenser bypass valve opening.
.
T (c.)
An'SRV opening.
(d.)
"3A feedwater heater isolates.
,
- e RNSWER 6.14 (1.00)
(a.')
[+1'. 0]
REFERENCE
.1..
Limerick: LOT-0540, L.0. 13.
,
259001K312
..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ - - -
- - _ - _ _ - - - -. _ - _ _ - - _ _
_ _ -- _. _ _ -- _ ____ _ _ _ -_- _ -_- _-_----_ _ _ _ _ _ _ _
_
-
7_ _ __--, --
_
_
_
d i
i
26.
PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 51
-
b RESPONSIBILITIES (13%):
<,
l
. QUESTION 6.15 (1.00)
SELECT which ONE (1)'of the following' statements is TRUE concerning
,
the Control Rod Drive Hydraulic System response during a. SCRAM 7 (1.0)
-
!
.
!
(a.),
e
'
The. Scram pilot valve energizes to vent the air off the i
Scram inlet and outlet valves.-
i (b.)
The Scram Discharge Volume (SDV) vent andEdrain air pilot
!
valves energize to vent the air off the Scram discharge
volume ~ vent and drain valves.
(c.)
If one of the Scram Discharge Volume (SDV) vent and drain air pilot valves fails to reposition, the Scram Discharge Volume will remain vented ~and drained.-
.
- (d.)
If any scram' pilot valve fails, the action of the backup H
'
scram valves will.cause the-rod associated with the failed l
f ANSWER 6.15
.(1.00)
(d.)-
[+1.0]
l
!
REFERENCE
.
i 1.
Limerick:
LOT-0070, L.0. 5 and 8.
201001K107
...(KA's)
F i
!
!
l l
l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ - _ _
_ - -
6.
PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 52 i
RESPONS!BillllES (13%)
QUESTION 6.16 (2.00)
Answer'the following concerning the Recirculation System:
a.
An Anticipated Transient Without a Scram recirculation pump trip (ATWS-RPT) initiates on or on (1.0)
.
b.
An End of Cycle recirculation pump trip (E0C-RPT) initiates on a when power is greater than as sensed by first stage pressure.
(1.0)
.
.
,
ANSWER
'6.16 (2.00)
a.
Reactor Water Low Level (-38 inches)
~ 0.51
+
' 0.5 Reactor High Pressure (1093 psig)
+
b.
- +0.5; 30%
+0.5 REFERENCE
\\
1.
Limerick:
LOT-0030.
202001K413 202001K414
..(KA's)
QUESTION 6.17 *(1.50)
Concerning the Control Room Ventilation System, STATE the TWO (2)
conditions which would cause the Control Room Emergency Fresh Air Supply System to initiate.
INCLUDE where each of these conditions a'e sensed.
(1.5)
r (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
______-__
n,.
.
.
,+
i
___
,
ow h
.6.
PLANT SYSTEMS (30%)' AND PLANT-WIDE-GENERIC :.
~Page'53.
'
-
RESPONSIBILITIES (13%)
, l;
'
o ANSWER 6.17 l(1.50)
.a;-
l '.
High' Radiation [+0.5] in the Air Intake Duct' [+0.25]
2.
High Chlorine' [+0.5] in the Air Intake Duct
[+0.25]
REFERENCE
' 1..
Limerick: LOT-0450' L.O. 3 & 5.
'
-290003K101:-
~290003K102 290003K401
..(KA's)
.-
QUESTION 6.18_
(1.00).
The MSIV Leakage Control System exhaust is routed through-the (1)
system and the'(2)
which minimize'the amount of radioactivity released to the environment.
(1.0)
ANSWER:
\\ 6.18 (1.00)
,
1.
Standby Gas Treatment Sysiem -[+0.5]
.2.
Reactor' Enclosure Recirculation System [+0.5]
( Ano Acccer ReAtxot. Eatt.osest Eqost gtpr tout Agr wee r eta Aost sqatu),
REFERENCE-
.
L 1.
Limerick: LOT-0125 L.0.'s 1 & 3.
2.-
Limerick: -5-40.1A.
3.
Limerick: SE-10.
-239003K102
..(KA's)
i
'
l l
c (***** CATEGORY 6. CONTINUED ON NEXT PAGE ***")
1.
_. _..
._
_
_ _ _ _. _ _ _ _ _ _ _
.__________._________m_____._________
__ _ ___- - - _
a
-
_- _ _ _ _ _.
_ _ - _ _ _
6.
PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 54 RESPONSIBILITIES (13%)
QUESTION -6.19 (1.00)
SELECT which ONE (1) of the following systems, in conjunction with the Centrol Rod Velocity Limiter reduces the consequences of a rod drop accident.
(1.0)
(a.)
Rod Drive Control System (b.)
Rod Worth Minimizer System (c.)
Reactor Manual Control System
%
(d.)
Rod Block Monitor System ANSWER 6.19 (1.00)
(b.)
[+1.0]
REFERENCE 1.
Limerick: LOT-0100 L.0. 1.
,
~
\\
201006K105 201006K501 201006G004
..(KA's)
QUESTION 6.20 (1.50)
Concerning the Condensate System during full power operation:
STATE the TWO (2) automatic actions that would occur on a condensate pump trip.
INCLUDE setpoints.
(1.5)
ANSWER 6.20 (1.50)
1.
Recirc pump runback [+0.5] to 75% core flow (60% speed)
[+0.25]
2.
RFP turbine runback [+0.5] to 78% speed [+0.25]
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
I l
I.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
,
.
-
-
-
-.
._.
_ _ -
- - - - - - _
- _ _ _ - _ _ _
t
6. ' PLANT. SYSTEMS (30%) AND PLANT-WIDE GENERIC -
Page 55 RESPONSIBILITIES (13%)
,-
- REFERENCE'
,
1.
' Limerick:
LOT-0520, L.0. 10.
256000K304
..(KA's)
QUESTION 6.21 (2.00)
a..
STATE the: safety limit and limiting safety' system setting
- that protects against-overpressurization of the reactor vesse1~.
(1.0)-
>
b.
.If an~ overpressurization transient occurred that exceeded
~
the safety limit, WHAT agencies / individuals must be notified:
1.
within one (1) hour of event (0.25)-
2. 'within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of event (0.75)
ANSWER 6.21 L(2.00)
.a.
-11 1325 psig
- +0.5]
2.
1037 psig
- +0.5]
'b.
1.
NRC Oper'tions. Center
- +0.25]]
[+0.25 a
- 2. 'Vice President, LGS
[+0.25][+0.25]
Plant Manager Nuclear Review Board REFERENCE 1.
Limerick: - LOT-0010, L.0.1, 2, and 3 (SRO).
~
2.
Limerick:- Technical Specifications 2.1.3, -Table 2.2.1-1, 6.7.
290002K507 290002G005 290002G003 290002G002
..(KA's)
i (***** CATEGORY 6 CONTINUE 0 ON NEXT PAGE *****)
=_z____1__--___________
___-_____---____--_-___--_-__--__----_-_______________a
_
._
_ _ _ -_- -
6.
PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 56-RESPONSIBILITIES (13%).
QUESTION 6.22 (1.00)
FILL in the chart of exposure limits as stated in HP-102,
' Administrative Dose Limits, Guidelines and Notification Requirements."-
(1.0)
ASSUME the following:
1.
A signed and completed NkC-4 Form is on file.
2.
No exposure extensions have'been authorized.
3.
All exposure will be received at PEco facilities.
QUARTER YEAR (MREM)
(MREM)
Whole Body 1.
4.
Extremity 2.
Skin 3.
ANSWER 6.22 (1.00)
' 0.251 1.
2500 WRem
+
2.
15000' mrem l+0.25l
'0.25 3.
6000 mrem
+
' 0.25 4.
4500 mrem
+
REFERENCE 1.
Limerick:
LOT-1705.
2.
Limerick:
HP-102.
294001K103
..(KA's)
QUESTION 6.23 (1.50)
Prior to exceeding a dose control level of mrem / quarter and up to 1500 mrem / quarter, a dose extension request must be approved by the and the (1.5)
s (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _
-
,
_ -..
._
.
Yi;;
'
'
,
,,,I
- j ;.
P J.'
6.
PLANT' SYSTEMS 1(30%?-AND PLANT-WIDE GENERIC Page 57
'
-
RESPONSIBILITIES D3%)
ANSWER'
6.23 (1.50)
1.
1000:
[+0.5]
2..
Department Senior Engineer
[+0.5]
3.
Senior Health-Physicist
[+0.5]
REFERENCE
,
-1.
Limerick:
LOT-1705 2.
Limerick:.
HP-102 294001K103'
..(KA's)
QUESTION 6.24
'(1.50) -
In accordance'with Administrative Procedure A-7, Section 5.5, STATE THREE (3) steps which.the Control Supervisor is authorized to take to limit and control, access to the control' room area.'
(1.5)
\\
ANSWER l6.24-(1.50)
- 1.
. Require all business not pertaining to-the control panels or operating stations be conducted outside of the. " Blue"
,
line.
"
2.
Require pass-through traffic to follow the " Yellow" lined route.
'3.
. Order any individual from the control area whose presence
' poses.a threat or potential threat to plant safety.
4..
Order the immediate departure (or removal) from the control room any unnecessary people when a plant emergency exists.
,
- Any three (3) [+0.5] each; max. [+1.5]
?
l
.(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
_ - - _ _ _ _ _ _ _ _ _ _ _. _ _ - _
__
_
._ - - _ _______ _ _ _ _ _________ -
_
_ - -
9
- -.
f6. PLANT ' SYSTEMS (30%)1 AND PLANT-WIDE GENERIC Page'58 RESPONSIBILITIES (13%)-
,
' REFERENCE
'
'1.
. Limerick:
LOT-1570,.V.G..
2.
Limerick: Administrative Procedure, A-7, Section 5.5.-
f.
- 294001K105
..(KA's)
>
-QUESTION
_6.25'
(1.00)
L SELECT which ONE (1) of the following statements is the basis for
~the change :in' chloride limit from; power operations (0.2 ppm) to cold' shutdown (0.5 ppm).
(1.0)
'
(a.)
'The rate of formation of insoluble metallic corrosion
. products is proportional to'. coolant temperature.
.(b.)
-Galvanic corrosion rate increases proportionally with the coolant temperature.
l
.. (c.)
Stress corrosion' cracking of stainless' steel increases
.with increasing temperature.
-
l (d.).
Oxidation of. carbon steel increases with temperature.
\\
ANSWER-
.6.25 (1.00)-
(c.)
[+1.0].
L l
REFERENCE l~
1.
Limerick: Technical Specifications.
294001A114
..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
i.
_
__
_
_ _ _ _ _ _ _ _ _ _.
-_
_ _ _ _ _ _ _ _ _ _ _ _ _ -
. - _ _ _ _ _ _
6.
PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 59 RESPONSIBILITIES (13%)
QUESTION 6.26 (1.00)
a.
USING the shell prewarming time graph (attachment #1) and given the conditions below, DETERMINE the time at which prewarming the shell will be complete.
(0.5)
Shell pressure increased to 60 psig at 1:30 a.m.
-
First stage shell temperature (initial) - 155 deg F.
-
b.
During shell warming, STATE the maximum limit as it pertains to heat-up rate.
(0.5)
ANSWER 6.26 (1.00)
a.
4:45 a.m. (+/- 5 minutes)
[+0.5]
,
b.
100 deg F/Hr [+0.5]
REFERENCE 1.
Limerick:
LOT-0560 and 0590.
\\
2.
Li'merick:
GP-2, 3.2.1.
3.
timerick:
501.1.A.
294001A108
..(KA's)
QUESTION 6.27 (1.50)
During shift turnover, operators reporting for duty shall receive a verbal report from the previous shift.
STATE the six (6) general topics required to be covered during the verbal turnover.
(1.5)
l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
j l
-
_-_-_-_--_--_--_D
_. _ _ - _ _
_
_ -
_ _ _ _ _ _ _ _ _ _ _ _
,y
!;
N.
[!' [6.' ~ PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 60.
'
. RESPONSIBILITIES-(13%),
L f
'
'
.'
l ANSWER
'6.27'
(1.50)
1.
General operating condition of the plant.
[+0.25]
i.
~2.
Specific operations performed and difficulties encountered
' during the previous shift.
[+0.25]
l 3..
Scheduled plant operations.
[+0.25]
~4.
Equipment outages and maintenance work in progress.- [+0.25]
5.
Status:of safety related equipment and conditions.
[+0.25]
6.
Temporary circuit authorizations.
[+0.25]
REFERENCE
'1..
Limerick: Administrative procedure A-7, Section 5.10.1.
294001A105
..(KA's)
QUESTION 6.28 (1.50)
\\
According'to Administrative Procedure A-7, Shift Operations:
a.
In the control room, the minimum number of licensed operators required to be in the reactor control area of each unit is (0.25)
.
b.
The number of licensed operators assigned exclusively to the reactor in the control room for startup, scheduled shutdown and recovery from a reactor trip is (0.25)
.
c.
The reactor operator at the controls may momentarily be absent from the designated area with permission of the Control Supervisor during an emergency affecting safety of operations for two reasons. STATE the TWO (2) reasons.
(1.0)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
l
_ _.. _ _ - - - - _ - _ _ _ _ - - _ _ _ _ _ - - _ - - _
-
.
-
-
-
__
_
-
_.
> y{ ";
'
,
'
.n
'
r z
- 41 l6. ' PLANT SYSTEMSf(30%) AND' PLANT-WIDE GENERIC-
- Page.61 j,
RESPON51BILITIE5'(13%)
i- '
n.
,,
R h
e'
.
.
-..
-: t.
ANSWER 6.28?
(1.50)-
'
- a.:
1;'[+0.25]!
t b.:
2 [+0.25]
.
,
c.-
Acknowledge' annunciators. [+0.5]
Initiate = corrective actions
[+0.5]
'
.
-l ~d
' REFERENCE-
-.
1.
. Limerick:' Administrative Procedure A-7, 5.1.3.1, 5.4.1,'
<
5.4.3, and'5.10.7.C.
'
- 2L Limerick
- . Technical. Specifications, Table 6.2.2-1.-
f 294001A103,
..(KA's)
QUESTION -
6.29 (1.50).
In'accordance with.the Emergency: Exposure Guidelines, STATE the allowable' doses'(in REM) for the'following situations.
(1.5)
,
WHOLE
'
~
BODY Life Saving and'
,
Reduction of Injury.
1.
OperationLof Equipment'
to Mitigate ~an< Emergency 2.
Protection of Health and Safety of the Public 3.
.
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
.
_ _ _ _. _. _ _ _
__m.
_. ___i___
_m_____._______m_
. _ _ _ _ _ _ _ _ _ _ _ _. _ _
,_._._______________.-m_-____-_mE______
'
-
.
__
L l
. <
6.
PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 62
-
RESPONSIBILITIES (13%)
'
ANSWER 6.29
.(1.50)
1.
[+0.5]
,
2..
25 [+0.5]
3.
5 [+0.5]
REFERENCE 1.
Limerick:
EP-314 294001A116
..(KA's)
QUESTION 6.30 (2.00)
In accordance with Administrative Procedure, A-7," Shift Operations", STATE what FOUR (4) items must be verified to assure that a procedure is valid.
(2.0)
s ANSWER 6.30 (2.00)
1.
Must be stamped in red " Control Copy."
[+0.5]
ha T M W Ac-cR.
2.
Stetion-6 superintendent's (or alternate's) signature (and date).
[+0.5]
3.
QA Superintendent's (or alternate's) signature (and date).
[+0.5]
4.
Date of use must be later than the effective date.
[+0.5]
l
\\
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
. -
_ _ _
_ _ _. - _ _ _ _ _
sc y
- - - ~ - - - - - - -
--
-
.
..,.
,
,
.
.- v.
w
,,
,"
.,
,
.
,
- n. '
.
46.
PLANT SYSTEMSL(30%)5 AND PLANT-WIDE GENERIC Page 63
'
+-
RESPONSIBILITIES-(13%)
'
LREFERENCE
'
...
x
'1.
Limerick: : LOT.1570, L.0. 3..
~
l2.
. Limerick:.? Technical' Specification 6.8.2.
.
,
-r 3.
Limericki.'AdministrativeProcedureA-7,5.2.1'.
'
. i:
.
..
.
.294001A101-
..(KA's)
.
.. ;
i'.
\\-
i i
.
',
-(***** END OF CATEGORY 6 *****)
(********** END OF EXAMINATION **********)
- _ _ _ _ _ - - _ _ _ _ - - _
_ - _ _ -.
- _ _
- _ _ _
_-_
-
o
x n:.,
i
- 3 _e
,
..
- TEST CROSS REFERENCE'
Page 1
- I L
QUESTION; VALUE REFERENCE L-4;014 2.00'
.9000253.
'
.4.02 1.00 9000254
.4.03 1.00 9000255-c
"
.4.0 41-1.001 9000256 4.05
'2.00 9000257.
4.06.
?1.00 9000258 4.07; 1.00 :
9000259 4.08-1.50 9000260.
,
p 4.09'
1.00 9000261:
4.10 1.00, 9000262
'
- 4.11 2.00
- 9000263
!
'
4.12L 1.00-9000264
.4.13 2.50 9000265:-
'!
i 4.14 L1.00 9000266 R
4.15c 3.00
^9000267 4.16 2.00 9000268 i
.
.......
24.00
'
'
5.01 1.00 9000269 5.02 3.00-9000270-l F
5.03.
1.00 9000271
~
5.04 1.00 9000272 5.05-1.00 9000273
~I
,
5.06:
3.00 9000274-
!
5.07 1.00-9000275-l 5.08 1.00'
9000276
-
5.09 l'00a 9000277'
'i
.
5.10 \\ ' 2.50
.9000278:
.5.11 1.00-9000279 5.12-2.50-9000280 i
.O.
900028 l
5.15
'1.00 9000283
'
J
.5.16 :
3.00 9000284
.!
5.17-2.00L 9000285 J
5.18 1.00
.9000286-
!
5.19 2.00 9000287
5.20 1.00 9000288
.......
32.50 i
.
6.01:
1.00 9000298
!
6.02 3.00 9000299 l
6.03 1.00 9000300 l
6.04 1.00 9000301
!
6.05-1.00 9000302
!
6.06 1.00'
'9000303
.
6.07-1.00 9000304 l
. 6.08 -
3.00-9000305
]
6.09 1.00 9000306 i
6.10-2.00 9000307-6.11 3.00 9000308 i
'6.12 1.00 9000309
)
6.13'
1.00 9000310 l
_
- _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_
q
-
_
_ _ _ _ _ _ - _
,
.;q;; '
t.
'
' "*
'
. TEST CROSS REFERENCE Page 2
,
,
-
VALUEL REFERENCEL
,00ESTION'
6.14-
- 1. 0 '
9000311
15.15 1.00-9000312 6.16-2.00 9000313-
'
'6.17-1.50-9000314 6.18 1.00i 9000315 6.19.
1.00 9000316.
'6.20'
1.50; 9000317
- 6.21'
2.00 9000318
6.22 11.00
.9000289, 6:.23.
- 1.50 9000290-6.24-1.50 9000291-
'6.25 r1.00.
9000292 6.26-1.00 9000293
'6.27 1.50 9000294-
-
6.28 1.50 9000295
'
'6.29-
.1.50:
.9000296 6.30 2.00 9000297.
..___.
.
43.50
..___.
mammew 100.0
.g
,
t'
'.-
..
l-
_. - _ _ _ _ _ _ _. _ _ _ _ _ _ _ - _ _ _ _ _ - _
- _ _ _. _ _ __
_-
- _ _ _ _ _ - _ _.
f j W c 4 m E H T ?-
'
.
DRAFT COPY U.-5. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION' 1 l,
FACILITY:
Limerick 1 REACTOR TYPE:'
BWR-GE4 l
DATE ADMINISTERED: 89/06/12 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 25.00~
25.00 1.
REACTOR PRINCIPLES'(7%)
THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
27.00 27.00 2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%).
'
48.00 48.00 3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
100.0
%
TOTALS FINAL GRADE All work done on this examination is my own.
I have neither given nor received' aid.
Candidate's Signature DRAFT COPY l
_ _ _ - _ _. - _ _ _ _ _ - _ _ - _ _ _ _. _ _
-_-____--__-
O
--
<
1.
REACTOR PllINCIPLES (7%) THERMODYNAMICS Page 2 (7%) AND !TMPONENTS (11%) (FUNDAMENTALS EXAM)
QUESTION 1.01 (2.00)
For EACH of the events below, STATE the order in which the three Doppler) y coefficients (Moderator Temperature Coefficient, Void,will affect reactor rea reactivit ALSO indicate whether each coefficient will be adding positive (+)
or negative (-) reactivity during the event.
Use all three coefficients for each event.
a.
Turbine stop valve fails shut at power (1.0)
b.
One recirc pump trips at power (1.0)
ANSWER 1.01 (2.00)
a.
Void (+), Doppler (-), MTC (-)
b.
Void (-), Doppler (+), MTC (+)
[+0.25] for each + or - and [+0.25] each (a., b.) for the correct order
' REFERENCE 1.
Limerick: LOT-1450.
2.
Limerick: LOT-1460.
3.
Limerick: LOT-1480.
292004K110 292004K105 292004K101
..(KA's)
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
1'
_ _ _ _ _ _
_ _ _ _ _ _ _ _ -
,
--
- - -
.
.
.
,-
- i.-REACTORPRINCIPLES'(7%)' THERMODYNAMICS ~
Page 3-J-(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
I t I
QUESTION 1.02-(l'.00) -
i SELECT ONE (1)-of the following statements which correctly completes the definition of'the. Delayed Neutron Generation time.
(1.0)
It is the length of time between...
,
- (a.')
neutron absorption and subsequent' delayed neutron
-
.thermalization.
L(b.)-
the: production of a delayed neutron and subsequent neutron absorption.
,(c.)
the production of delayed neutrons in successive lifetimes.
' (d.)i ' delayed neutron thermalization and subsequent neutron-
absorption.
ANSWER.
1.02 (l'.00) '
(c.)
[ 1.0]-
REFERENCE 1.
Limerick: LOT-1420, L.0.'s 5 and 6.
292001K102
..(KA's)
L i'
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
L-
-
- - - - -. - - - -
_
_. - - - -. - _ _ - - _ _ _ _ - -.. _ _ _ - -. _. - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_,.. _
_ - - - - - -
h.k 4..
y
>
,
0. '
ri I-
-1.
' REACTOR PRINCIPLES'(7%) THERMODYNAMICS Page -4-
-
(7%) AND COMPONENTS (11%):(FUNDAMENTALS EXAM)
1;'
..
' QUESTION l'.03
'(1.00)
.T.he power' generated by.the reactor at the beginning of core life
~
-
comes from U-235-thermal fission and U-238 fast' fission.
SELECT
,
ONE (1)' isotope which, later-in core life, produces. larger and larger fractions of power by fission.
(1.0)-
'
(a.) Am-241'
'
(b;)' Cm-244 (c.)L Pu-238
. (d. )l Pu-239 ANSWER-1.03 '
(1.00)
(d.) [+1.0]-
.
REFERENCE-1.
Limerick: LOT-1420, L.0.'s 5.b. and 9.
~
292001K102-
..(KA's)-
'
,
-(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
___________ _ _ __ _ _ - _ _ __ -
.
..
_
,
_.
_
.-_
,
,
,
- l
,
'
1.
l'.-
REACTOR PRINCIPLES-(7%) THERMODYNAMICS-Page 5
,? y t(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)-
,
'
t p.
,l QUESTION; 11.04.-(2.00)
"
For EACH of-the TERMS-(a.--f.) on the left MATCH the correct-c DEFINITION on the right. -(Only one correct answer each)
(2.0)_
TERMS ANSWER DEFINITIONS ~
a..
Keff-
'1.
Keff = 1
.b.-
Critical 2.
The fraction of the thermal neutrons that had been born by the decay of delayed
~
c..
Supercritical'
3.
The fraction of~ fission neutrons born from the decay of a delayed neutron
..
precursor.
d.
Excess Reactivity 4.
Multiplication factor' dealing with an infinitely large reactor e.
Effective Delayed Nhutron Fraction 5.
Neutron population is decreasing from generation
_
_
to generation.
'f._
A measure of how far the u
reactor is below the critical condition.
l 7.
Multiplication factor dealing I
with a realistic reactor. This L
includes leakage.
8.
The amount of additional L
reactivity built into a reactor to allow it to reach full power for its operating cycle life, o
9.
Keff > 1 10. A measure of the departure from criticality.
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
. -_ -_
_-__ _ ___ _- _ _ _ _ - _ _- _ _ _ _ -
_ _ _
_
.
_.
_
,
<,
,
,
'
,
'1; ~ REACTOR PRINCIPLES (7%) THERMODYNAMICS-Page :61 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
l'
<
t;s K:
ANSWER 1.04 (2.00)
,
"
'
- a.
- 7l j
-
- b.
+
'
c.
9'
d..
'
e.-
2'
f.
6 OV".10(
g
,
L
.
-
l
-[+0.33] each REFERENCE-
.
!
p 1.
Limerick:
LOT-1420.
l 2.
Limerick:
LOT-1430.
I 292003K104 292002K110~
292002K107-292002K111
..(KA's)-
b
_ QUESTION
'1.05 (1 ~.00)
SELECT ONE (1) of the following statements which describes the
'l purpose;of the End of Cycle Recirculation Pump Trip (E0C RPT).
(1.0)
l
\\
(a.)-
Adds negative reactivity quickly by void formation to
i function as a backup to the control ~ rods.
,
L (b.)
' Adds negative reactivity _.in addition to the control-rods upon a turbine trip to compensate for the lower rod worth
!
at EOC.
'L(c. )
' Adds negative reactivity during a turbine trip to l
'
compensate for the longer time required for the control
)
rods to reach the high flux region of the core.
!
.(d.)
Adds negative reactivity to compensate for smaller l
beta, effective caused by buildup of plutonium and burnup of
w
!
l
ANSWER 1.05 (1.00)
.
(c.)
[+1.0]
l
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
l
-__
_ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ -
_
_
_ _ _ _ -
ps
't
.
>
@
- f y
.
I.
REACTOR PRINCIPLES (7%)' THERMODYNAMICS Page 7 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
"
lI REFERENCE'
1.
Limerick:
LOT-0040, pp. 12,-20,_21, and 23.
I
,
,
...
292008K126
..(KA's)
'
<
j i
,
QUESTION'
1.06 (1.00)
ly
,
4,
,
'For'EACH of the TWO (2) Thermal Limits given below MATCH the appropriate Failure Mechanism (F1-F3) AND the Limiting Condition (L1-L3).
(1.0)L
.
'
!'
THERMAL LIMIT, FAILURE LIMITING MECHANISM CONDITION
.
.
.;
.
,
. a.
Linear Heat Generation Rate.(LHGR)
L',
. b.- Average Planar _ Linear Heat
!
Generation Ratel(LHGR)
j i
' FAILURE'MECHANI'M LIMITING CONDITION S
- (F1.)
t, lad melting caused
_
(L1.)
Coolant transition boiling
<
'
by decay heat & stored-i heat following a LOCA.
t3
(F2.)
Clad cracking caused (L2.)
Clad )lastic' strain less
'
,
from becomming vapor.
' than 'T blanketed.
'(F3.) Clad cracking. caused (L3.) Maximum clad temperature
!
by high stress from of 2200 degrees F pellet expansion.
!
'i
!
l
' ANSWER
'1.06-(1.00)
i
~;
(F3.)'
+0.25?
i a
' 0.25 i
(L2.
+
L+0.25l l+0.25 b.
(F1.
l-
_(L3.
.
,
l l'
(***** CATEGORY -1 CONTINUED ON NEXT PAGE *****)
-
r
. _ _. - _ _ _ _ _ - - _ - _ _
,
.
Jp
,
,
'1.
REACTOR' PRINCIPLES (7%) THERMODYNAMICS Page 8-
!
(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
!
)
E,
. REFERENCE-
- J
,
1.
Limerick: LOT-1380, L.0. 2.
.
1293009K119,
..(KA's)
l
,
QUESTION 1.07 (1.00)
SELECT ONE (1) of the following statements which describes a correct R
heat' balance' relationship.
-(1.0)
.(a.)
If'the feedwater temperature used in the. heat balance calculation was HIGHER than the actual feedwater temperature then actual reactor power is HIGHER than calculated reactor
.
. power.
(b.)
If the reactor recirculation. pump heat input used in the heat balance calculation was OMITTED then actual reactor powe'r is HIGHER than~ calculated reactor power.
'
(c.)
.If the steam flow used in the heat balance calculation was
,
LOWER than'the actual steam flow then actual' reactor power is LOWER than calculated reactor power.-
(d.)
If-.the RWCU' return temperature used in the heat balance calculation was HIGHER.than actual RWCU return temperature than actual reactor power is LOWER than calculated reactor power.
ANSWER 1.07 (1.00)
-(a.)
[+1.0]
. REFERENCE 1.
Limerick: LOT-1300, 2.6/3.1'2.3/2.9 293007K113 293007K111
..(KA's)
.(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
-
. _ _ _ _ - _ _ _ _ - _ _ _ _ - _ _ - _ _ _ - _ _ _ _ _ _
_ _
_ -
-
-
- - - -
,
,
.
,
%
1.
REACTOR PRINCIPLES-(7%)' THERMODYNAMICS
_Page 9
~(7%) AND COMPONEN15 (11%) (FUNDAMENTALS EXAM)
p l QUESTION 1.08
~(1.00)
g
..$ ELECT ONE (1) of-the following statements which correctly describes
the effect of an INCREASE -in the amount of non-condensible gases
- in a steam turbine condenser.
(1.0)
'
'(a.)
condenser-pressure decreases (b.)
circulating water outlet temperature decreases (c.)
. turbine generator megawatt output decreases (d.)
condensate subcooling increases ANSWER-1.08 (1.00)
(c.)
[+1.0]
F REFERENCE o
'1.
Limerick: -General Electric Thermodynamics Text, Section 6.
!-
.2.
Limerick:' LOT-0500.
293007K107
..(KA's)
r
!
- QUESTION:
1.09~
(1.50)
i During a cooldown of the reactor vessel, reactor pressure decreased from'885 psig to 595 psig.in one half hour.
DETERMINE the reactor cooldown rate. ~ (SHOW all of your work).
(1.5)
n L
i (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
__- ___________________ __-_______ _ _ _ -
_ - _ - _ - _ _ - _ _ _
_
i
- 1.
REACTOR PRINCIPLES'(7%) THERMODYNAMICS Page 10
'
(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)'
.
- <
LANSWER-1.09 (1.50)
First, convert'psig, to psia, by adding 14.7 psi.
[+0.50]
Then, referring to the steam tables; 900 psia. = 532 deg.F
- +0.25; 610 psia. = 488 deg.F 0.25
+
Then calculate using the correct formula; 532 deg.F - 488 deg.F =44 deg.F / half hour
[+0.50]
(or 88 deg.F / hour)
(will allow a variance of (+) or (-) 2 degrees)
REFERENCE 1.
Limerick:
LOT-1100, L.0. 3.
'293003K123
..(KA's)
QUESTION 1.10 (1.00)
. STATE,TWO (2) reasons WHY feedwater heating improves power plant efficiency.
(1.0)
i ANSWER 1.10 (1.00)
1.
The. energy recovered in feed heating would otherwise be lost to the main condenser.
[+0.5]
2.
Less heat is required from the reactor to reach the desired conditions
[+0.5].
REFERENCE 1.
Limerick:
LOT 1230, L.0. 2.
293005K105
..(KA's)
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
-
_ _ _ _ _ - _ - _ _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ - _ _ _ _ _ _ _
_ _ _ _ _ - _ _ _ _ _ _ - _ - - _ _ _
_ _ -
_ _ - _ _ _ _ _ _ _
_
_ _ _ _ _ _ _ _ _ _ _ _ - -.
,
w.
,.
$$.
'!.
.
...
REACTOR PRINCIPLES'(7%): THERMODYNAMICS-Page 111 qd 1.
.
.
.
~
'
(7%) AND COMPONENTS (11%)-(FUNDAMENTALS EXAM)
>
'
,
s
..}
QUESTIONJ 1.11
'(1.00)
Given'the' conditions that the reactor is in start up..at.the point
- of. heat up but prior to boiling.
SELECT ONE (1) of the~ following statements which correctly describes Lone: type of heat. transfer from the fue1~ to the reactor coolant.
(1.0).
L(a.)
Heat transfer through the fuel pellet is via convection.
~
<
'(b.)
Heat transfer'across the fuel clad is via convection.
~
'(c.) Heat transfer' through' the laminar water layer is via conduction.
(d.)
Heat-transfer from the laminar film into the bulk of the-coolant is via: conduction.
ANSWER.
1.11'
(1.00)
. (c. ).
[+1.0]l l REFERENCE (
,1.
Limerick: LOT-1350, 293007K101-
...(KA's)
QUESTION-1.12 (1.50)
Water hammer is defined at the liquid shock imposed on a piping
. system resulting from a rapid change in (a.)
.
.The factors affecting the magnitude of impulse force are
- time,(b.)
, and (c.)
(1.5)
.
,
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
OT6
>
'
g
,
,
,
(';7 i l
L'
_
,
,{
.I.
-REACTOR' PRINCIPLES =(7%) THERMODYNAMICS Page.12 l
(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)-
,
p.
.
'
ANSWER 1.12
.(1.50)
.(a.
flow-
- +0.5; (b.
mass
+0.5
[+'.5] or ucele m h C+a 153 (c.
velocity
REFERENCE 1.
Limerick:
LOT-1291, L.0. I and 2.
291006K114
..(KA's)-
QUESTION 1.13 (1.50)
.
' SELECT ONE' (1) of the_ pump curve changes (right column) for each ~of the.three pump modifications (left column).being considered.for a constant speed single centrifugal pump system. (ASSUME ideal conditions)..Not all answers may be used and,some may be used more than once.
(1.5)
PUM{ MODIFICATION ANSWER PUMP CURVE CHANGES a.
add one. identical 1.
decreased flow rate pump in parallel with decreased head capacity b.-
add one: identical 2.
increased flow rate pump in series with increased head
~
capacity c.-
double the speed 3.
double the flow rate
'of the original with the same head pump capacity 4.
decreased flow rate with increased head capacity 5.
same flow rate with double the head capacity (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
_ _ _
_ _ _ - - _ - _ _ _
_ _ _ -
_ _. _
-
-
..
,
1 L
. s_
,
..
.. > _
"
w fli : REACTOR PRINCIPLES (7%)-THERMODYNAMICS?.
..
-Page.13
'
'
i (7%) AhD COMPONENTS (11%)-(FUNDAMENTALS EXAM)
, v, 1-i J
ANSWER-
.1.13: -(1.50)
e a.
3..
- +0.5[
<
,T b'..
5.
, 0.5
+
'
0. 5,
.
S
.c.
2.
+
.
' REFERENCE.
Limerick: SLOT-1290; L.0. 13,..16.
.
291004K104-
~293006K113
..(KA's)'
QUESTION 1.14
. '(2.50)
,
'a..
- A condensate. filter / demineralized is' removed from service on high outlet conductivity of 0.1 micromhos/cm and high delta-P of-psid.
(0.5)
.b..
STATE WHY the following parameters are used as. indications
~
_
that filter demineralized should be removed from service.
High conductivity.
(1.0).
<
g 2.
High' delta pressure (l'0)
.
.
ANSWER-
.1.14-(2.50).
a.-
[+0.50]
b'.
1.;(Conductivity is affected by chloride, pH and'other g-((a c, Im-impurity concentrations.) High conductivity is a good - or-g g c(ep(eg indication of degraded wate.r quality.
[+1.0]
2.-High'. delta-P.is an indication of particulate clogging
-
(and reduced filtering efficiency.)
[+1.0]
&
. 7 -.
.(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
.
- _ - - - _ - _
_ _ _ _ - _ _
-
_ - - _.
1.
REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 14 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
REFERENCE 1.
Limerick:
LOT-0520 L.0. 6. c & d.
2.
Limerick:
Tech Specs Bases Po. B 3/4-4-3 291007K108 291007K109
..(KA's)
QUESTION 1.15 (1.00)
G1VEN the conditions of: recirculation pumps are running at constant minimum speed; low power conditions (20% thermal power).
STATE HOW and WHY core flow varies (INCREASE, DECREASE, REMAINS THE SAME) as reactor power is increased by control rod withdrawl.
(1.0)
ANSWER 1.15 (1.00)
Core flow would increase 1:+0.5] due to an increase in natural circulation [+0.5].
REFERENCE
\\
1.
Limerick: LOT-0040, L.0. 13.
291006K112 293008K129 293008K137
..(KA's)
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
- _ _ - _ _ -
___ - - -
.
-1.
REACTOR PRINCIPLES (7%) THERMODYNAMICS-Page 15
_
(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
QUESTION 1.16 (3.00)
543.1.A " Start-up of Recirculation System" limits the number of i
starts that may be attempted on a recirculation pump.
a'.
With the motor gene'rator and recirculation pump at ambient temperature, (1)
pump start (s) may be attempted.
,
Another pump) start may NOT be attempted until a waiting i
period of-(2 has elapsed.
(1.0)
b.
With the motor generator and recirculation pump warm from at least fifteen minutes of operation, (1)
pumpstart(s)
may be attempted. Another pum L
until a waiting period of (2) p start may NOT be attempted has elapsed.
(1.0)
c.
SELECT ONE (1) of the following statements which describes
,
what the RESTART limitations protect.
(1.0)
'
i (1.)
The recirc.-pump bearings due to inadequate lube oil I
being supplied _on pump starts by the shaft driven l
oil pumps.
(2.) The motor generator windings from overheating due to
,
'
increased current flow on pump starts.
'
(3.)
The power supply to the recirc pump motors due to possible internal electrical faults causing the pump trips.
,
l l
(4.)
The fluid drive coupling scoop tubes from exceeding
!
their design cyclic stress limits.
l ANSWER 1.16 (3.00)
a.
(1)
two [+0.5]
(2)
one hour [+0.5]
b.
(1)
one [+0.5]
L (2)
one hour L+0.5]
c.
(2.)
[+1.0]
l J
i (***** CATEGORY I CONTINUEU ON NEXT PAGE *****)
f l
_ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ - _ - - _ _ _ _ _ _ _
.,
__
.-
_
-_
,
_
,
i
..t m
yu I
.
.
.
1.
REACTOR PRINCIPLES-(7%) THERMODYNAMICS Page 1.6'
i
(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
l
,
-)
l
[.
REFERENCE'
"
.
-
- 1. -
-Limerick: LOT-0030, Pg. 28.
!
2.-
Limerick: 543.1.A., 7.1.
!
l p
291005K106
..(KA's)
,j
.
l
..
i QUESTION 1.17 (2.00)
l a..
DEFINE Net Positive Suction Head (NPSH).
(1.0).
-l b.
. STATE the effect (INCREASE, DECREASE,.or REMAIN THE SAME)
on available Recirculation Pump NPSH.if HPCI initiates at
!
70% power AND EXPLAIN WHY this effect occurs.
(1 ~.0)
j
<
i
!
I
'
' ANSWER 1.17-(2.00)
j
'NPSH is the difference between' total. pressure at the eye of
!
'
a.
- the pump. and. saturation pressure. for the liquid. (Will
.
!
- -
accept the equation equivilent; NP!H = Psec - PsoC7 [+1.0]
i
= S-He - He tHz T l
b.
LThe NPSH would increase [+0.5] because the temperature of a
the feedwater would decrease, thus increasing the subcooling j
at'the eye of the. recirculation pump [+0.5].
l
'
,
l REFERENCE
'
t 11. -
Limerick:
EIH: Heat Transfer and Fluid Flow, Chapter 6, l
'L.O..# 10.9, 10.10.
.j
291004K106
..(KA's)
I
,
(***** END OF CATEGORY I *****)
t
.-.
_
_.
.-
- - _ _ _ _ _ - - - _ _ _ - _ _ - _ _. _ - - - - - - _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
-.
.
-
._
_
_ _ -
- _ _.
j
..;,
.
!22 ' EMERGENCY AND ABNORMAL' PLANT EVOLUTIONS Page 17;
l:
(27%).
- '
'
l
.
.
..
l'f
~ QUESTION.
2.01 (1.50)
j i
STATE THREE-(3)' symptoms.of a jet' pump-failure 'according to ON-100.
(1.5)-
-
l-;
'
' ANSWER 2.01-(1.50)
.!
i
' 1.-
Unexplained drop in reactor power.
I 2.'.
Unexplained rise in core-flow indication.
i
!
13.
Unexplained rise in recirculation flow' to the loop containing-
{
the defective jet pump.
!
4.
Unexplained drop in indicated delta pressure on the jet-pump sharing the riser with the defective jet pump..
Any three (3) [+0.5] each; max. [+1.5]
REFERENCE
,
-!
-1.
L{merick:LON-100.
l
-
295001K206 295001K207 202001K301 202001K502
..'(KA's)
'I i
!
. QUESTION :2.02; (2.50)
l i
During refueling operations, the control room operator observes
'
~ that the Source Range Monitor count rate is' increasing.
STATE l
FIVE (5)'immediate actions according to ON-120 " Fuel Handling
Problems".
(2.5)
.
!
l l
j (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
_ _ _
-
_ _ _ _ _ _ _ _ - _ _ _ _ _
_
__
_ _ _ - _ _ -
,
_ _ _ _ _ _ _ _
i
-
l 52. -EMERGENCY AND' ABNORMAL PLANT EVOLUTIONS'
Page 18
,
(27%)
L LANSWER<
-2.02 (2.50)
'1.
Raise the. fuel assembly from the core so it clears the
. upper grid.
,
l 2.
Evacuate the fuel ficor.
3.
Inform supervision.-
'
4.
Ensure all'insertible control rods'are inserted.
5.-
' Notify Health Physics.
~
5.
LNotify. Reactor Engineering.
7.
Do not resume fuel _ handling operations without permission
'from Superintendent'of Operations.
Any five (5) [+0.5] each; [+2.5]~ max.
.
! REFERENCE'
1.
Limerick:. LOT-1550.
2.
Limerick: -ON-120.
3.
Limerick: ON-120 Bases.
295014G010 295023G010
..(KA's)
\\;
QUESTION 2.03 (1.00)
-Trip Procedure T-101, "RPV Control," is in progress.
In accordance with the T-200_ series procedures, TWO other systems to be used to Linject boron into the RPV IF the Standby Liquid Control CANNOT be used are (1)
and (2)
(1.0)_
.
ANSWER 2.03 (1.00)
(1)-
Control Rod Drive System (CRD)
[+0. 5]
(2)-
Reactor Water Clean-Up (RWCU)
[+0.5]
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _
. _ _ _ _
_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - - _ _ - _ _ - _ _ _ _ _ _ -
_
. _ - _ _
l
1
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 19
!
(27%)
l l
l l
REFERENCE 1.
Limerick: TRIP - T-101,'T-110, T-111, T-112.
2.
Limerick: LOT-1562.
i
._.
295037A110'
..(KA's)
QUESTION 2.04 (2.00)
Pertaining to the TRIP procedures MATCH ONE (1) level in the right I
column-to each of the function statements in the left column.
EACH level can be used more than once.
.(2.0)
i i
FUNCTION STATEMENT ANSWER LEVEL a.
upper limit for reactor 1.
+60 in.
water level per T-100.
2.
+54 in.
b.
lower limit for reactor water level per T-100 3.
+39 in.
c.
Top of active fuel 4.
+12.5 in.
'
d.
Entry condition for T-101 5.
-38 in.
RPy control 6.
-129 in.
[
7.
-150 in.
-
8.
-161 in.
9.
-167 in.
ANSWER 2.04 (2.00)
,
a.
b.
C.
9 If
'
d.
[+0.5] each (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
_
_ _ _ _ _
_
_ _ _ _ _ - _ _ _ -
- __-
,-r
?
L; ',
'
,
Ib,-;
2.
EMERGENCY:ANO-ABNORMAL PLANT EVOLUTIONS Page 20
! '
(27%)-
l.-
-
REFERENCEL
'1.:
Limerick:J T-100, T-101,-and T-111.
2.
Limerick:~ LOT-1560, L.0. 3.
295031A101L l295031A102 295031A103 295031A104
...(KA's)
~
'
'
-
. QUESTION' '2.05-
.(1.00)
"
The~ TRIP. Procedure for Scram, T-100, Step S-7,: directs;operatorsJ to1tripithe' turbine when generator load reaches 50 MWatts.
SELECT:
u
,
ONEL(1) ofsthe,following statements which describes the reason
"
.for;this step..
(1.0)
L(a.)-
Assures there is adequate capacity of the. bypass v'alves to handle this load transfer.
- .
. (b.~)
Guards against'overspeed of the turbine _b
- generator.from. tripping on reverse power.y preventing the.
H (c.)'
Assures lthat~ the End-of Cycle Recirculation Pump trip does not occur.
>
-(d.).
Prevents MSIV closure upon NSSSS actuation on low' steam 1(nepressure.
ANSWER
.2.05 (1.00)
'
(b.)
-[+1.0]
REFERENCE 1.
Limerick:
T-100.
2.
Limerick:
LOT-1560, L.0. 5.
295006K305 295005K304
..(KA's)
(***** CATEGORY 2 CONTINUE 0 ON NEXT PAGE *****)
.
_.
.
- - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ - _ _ _ _ _ - _ _ - _ _ _ _ -
,.9 my
"
,
,
y' 4 "
'
'
,,. _
...
%
7.,
, ' :' a,_,
'2.
iEMERGENCY AND ABNORMAL PLANT' EVOLUTIONS Page 21:
&9-(27%)
"
&
,
QUESTION
~2.06:
(1.00)-'
Concerning.the Feedwater Control S
.
thereactor. level.setpointto-(a)ystem,:theautomaticsetdownof-(inches)-isinitiated E,
!!
.(b)'
seconds after the level decreases to (c)-
- inches.
.
H
.This avoids: unacceptably (d)'
' water. levels following-
'
- SCRAMS.from high' power..
(1.0)
n f
,
,,
2.06
.-(1.00)..
..
,
.
ANSWER.-
-
a
nches)
- '-
b 10 (seconds) '
-
c 12.5:(inches)
'
'
'(d high~.
.
-[+0.25]-each!
,
l'
~ REFER'ENCE -
pn
,.
. Limerick:c LOT-550, IV.A.7.
L
~1.
'
,
295008K304
...(KA's)
3..-
>
(***** CATEGORY 2 CONTINUED.ON NEXT PAGE *****)
..
a
---_---_---a----------a.-a--a-----------u--.---,_
.- - _ _ _ - - - _ _
--,---a---.,---,--
-
y six
-p.r,
,
,
'
+
p
~ EMERGENCYJAND ABNORMAL PLANT EVOLUTIONS Page 22 k'
2.
L:
(27%)
"
l-QUESTION. 2.07-(2.00)
. FILL in the blanks from.the' list provided.-
t To hydraulically disarm the directional control valves for a control rodhydrauliccontrollunitclose.the:(a)
and (b)
= isolation valves.
To maintain cooling to the control drive
- mechanism the -(c)
,(d)'
and cooling isolation-valves should remain.open.
(2.0)
LIST 1.
insert
. 2.
scram discharge
~
3.c drive 4.
' withdraw 15.
exhaust
'
6..
charging
' ANSWER-2.07 (2'.00)
(a)
-3.\\ drive)
(b)
5.
exhaust)
(c)
1.
insert)
(d)
4. (withdraw).
(a..and b. may be reversed and c. and d. may be reversed)
[+0.5] each REFERENCE 1.
Limerick: ON-104, Rev. 5, p. 1.
'
295006K203
..(KA's)
-QUESTION 2.08 (1.00)
. STATE the TWO concurrent conditions which cause the main turbine to automatically run-back generator load to 22.5% (no-cooling-load rating).
(1.0)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
.
_ - - _ _ _
_ _ _ _ _ _ _ _ -
,
...
o.
p!.
t
,
..t 1 2. EMERGENCY AND' ABNORMAL PLANT EVOLUTIONS Page'23 (27%)
'
L
..
- ANSNER'
'2.08 (1~.00) -
'
,a.
..High'statorcurrent(greaterthan7469' amps)
[+0.5]
tb..
Loss of stator cooling (low coolant-inlet pressure or
..
hightemperature.onthestator.bulkcoolant. outlet)
[+0.5]
REFERENCE-1.' -
Limeribk:
LOT-0600.
2.
. Limerick: ON-114.
. 295005K204.
..(KA's).
' QUESTION
- 2.09
' (1. 50)'.
- STATE the THREE (3) entry conditions for T-104 " Radioactivity Release Control." For'EACH entry condition INCLUDE the setpoint or action.
(1.5)-
ANSWER-.
2.09'
(1.50)
.a.-
North Stack Monitor '[+0.25], (exceeds) 1.0 x 10E-2 (uCi/cc)
[+0.25].
b.'
South Stack Monitor [+0.25), (exceeds) 1.2 x 10E-2 (uCi/cc). [+0.25]
c.
. Reactor Enclosure Steam Flooding Damper [+0.25]
actuation
[+0.25]
REFERENCE 1.
Limerick: T-104 295038G011
..(KA's)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
.
. - _ _ _ _ _
_ ____ _ _ _ __-___ _
__ _ -
. _
__
,
.
-
,
y
,
u
,s
,
,
,.
1 2. -EMERGENCY AND ABNORMAL" PLANT EVOLUTIONS.
Page 24'
i
.(27%)
i b
.
1 i
QUESTION: - 2.10 -
(3.00)
l ti-l Concerning OT-114 (Rev. 4), " Inadvertent Opening of: a Relief Valve":
~ FILL in the correct response for the following statements from the IMMEDIATE ACTIONS section of OT-114.
a.
.P1 ace
. loop (s) of suppression pool cooling ~in
service..
(0.5)
l l
'
,b..
Rapid shutdown per GP-4 is initiated if the relief valve CANNOT be shut within minutes.
(0.5)'
'
!
e.
c.
If the SRV cannot be shut within (1)
minutes or
_;
suppression pool. temperature reaches (2 deg F, place the. reactor mode switch in (3))
position.
(1.5)
j L.
-d.
~ High Suppression Pool ~ temperature.is an entry condition
~
. for TRIP procedure-(0.5)'
.
y ANSWER 2.10 (3.00)
!
a.
two.(both)
[+0.5)
I D.
1.5 minutes
[+0.5]
c.
(1) 2 minutes-
'0.51
+
' 0.5'
(2) 110 deg F
+
(3)-shutdown-
!+0.5
'
d.
T-102
[+0.5]
,
,
REFERENCE
-
i 1.
' Limerick:
0T-114 l
295013A102 295013G010 295013G011
..(KA's)
l
!
i I
!
l l
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
l
"
C
_ _ - _ _
- - - - _ - - - - _
.- - -. - - - -
--
-
- - -
-
-
-- l
sj
2.
EMERGENCY AND ABNORMAL PLANT E'iOLUTIONS Page 25
(27%)
QUESTION 2.11 (2.00)
Off-Normal procedure, ON-113, " Loss of RECW," requires the trip (ping of the reactor' recirculation pumps if cooling is lost for ten 10)
minutes.
a.
SELECT ONE (1) statement which describes the basis for tripping the recirculation pumps ten (10) minutes after the loss of-RECW.
(1.0)
(1.)
To provide time to insert control rods and stay within the constraints of the operating map once the recirculation pumps are tripped.
(2.)
To provide time for the operator to re-establish RECW operability.
(3.)
Continued operation of recirculation pumps after ten (10) minutes could damage the pump seals.
(4.)
Continued operation of recirculation pumps after ten (10) minutes could warp the pump shaft.
b.
SELECT ONE (1) of the following statements which describes thebasisfor.theTEN(10)secondwaitbetweenthe tnpping of the first and second recirculation pumps.
(1.0)
(1.)
To prevent initiating reactor level 8 trips due to the level transient that would result.
(2.)
To prevent placing the reactor in the region of thermal-hydraulic instability.
(3.)
To allow time for the first recirculation pump's discharge valve to close prior to exceeding its designed operating delta-P.
(4.)
To allow time for the first recirculation pump to coastdown prior to tripping the second pump.
i (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
_ _ - _ _ _ _ _ _ _
,
-
_
.__ _ _,
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 26
--
(27%)--
.
ANSWER 2.11 (2.00)
a.
(3.)
[+1.0]
b.
(1.)
[+1.0]
REFERENCE 1.-
Limerick:
LOT-1550, L.0. 3.
2.
LOT-460 3.
ON-113 295018K303
..(KA's)
. QUESTION 2.12 (1.00)
SELECT ONE (1) of the following statements which describes the effect of a loss of CRD pump "A" due to low suction pressure.
(1.0)
(a.)
A reactor recirculation pump trip on loss of seal purge flow.
(b.)
Aqtomatic opening of strainer bypass valve and CRD pump "B" auto start when suction pressure is above 25 inches Hg Abs.
(c.)
The suction flow path automatically transferring to the CST.
(d.)
A continuing drop in system pressure until manual action is taken.
ANSWER 2.12 (1.00)
(d.)
[+1.0]
l REFERENCE 1.
Limerick:
LOT-0070, L.O. 5.a.
'2.
Limerick:
LOT-1550, L.0. 3.
3.
Limerick: ON-107 295022A202
..(KA's)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
l
_ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
.
- - _.
h.-
,;
,
p 2.
EMERGENCY AND ABNORMAL PLANT EV0Liffl0NS Page 27 (27%)
'
l QUESTION 2.13 (2.00)
,-
Concerning condenser vacuum, MATCH ONE (1) SETPOINT (right column)
to the AUTOMATIC ACTION (left column).
(2.0)
AUTOMATIC ACTION ANSWER SETPOINTS a.
MSIV closure 1.
25 in. Hg Vac, b.
Feed pump turbine trip 2.
24.7 in. Hg Vac.
c.
Main turbine trip 3.
22.2 in. Hg Vac.
d.
Bypass valve closure 4.
18.5 in. Hg Vac.
5.
11 in. Hg Vac.
6.
8.54 in. Hg Vac.
7.
7 in. Hg Vac.
ANSWER 2.13 (2.00)
g a.
b.
c.
d.
[+0.5] each; max. [+2.0]
REFERENCE 1.
Limerick:
LGS OT-116 2.
Limerick:
LGS LOT-1540 f
295002K302 295002K303 295002K304 295002K305
..(KA's)
{
l ("*** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ -
q;,
- - - - -
-- _ _ --_-_
,
,p
..t
,
o
-
>
,
2;: EMERGENCY AND ABNORMAL: PLANT EVOLUTIONS'
Page 28 (27%)-
i i.
QUESTION-2'.14
'(1;00)-
ID LIf control is transferred to the' remote shutdown-panel, SELECT ONE (1)-
"
of the' following RCIC System-interlocks which will remain active.
(1.0)
(a.)-._RCIC turbine trip on overspeed.
(b.).
Steam supply valve closure:on high reactor water level.
'(c;) -
Transfer of suction'from the CST to suppression pool.
,
o.,.
'(d.).
Start on low reactor water level (-38 inches).
' ANSWER 2.14 (1.00)
.
" ( a'. ) ' [+1.0]~
R'EFERENCE
.1, Limerick:
LOT-0735, L.0. 4.f.
2.
qmerick:
SE-1.
29501dK201
..(KA's)
QUESTION 2.15 (1.50)
In accordance with SE-1 " Remote Shutdown" LIST the THREE (3) ways the reactor can be SCRAMMED if evacuation of the main control room is required'BEFORE immediate operator action can be taken.
(1.5)'
/
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
i
_ _ _ _
_._
-__ - _-__ -,
_
_ _ _
--.
_
_
-,
_
_
_
_ - _ _ _ -
- _ -.
-_ - -
f 2;
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS..
Page 29 (27%)
L
'
- ANSWER'
2.15-(1.50)-
' 1..
Trip-the Main Steam Line Radiation Monitors SC~I step 4,$./ e g y L 4
~
..,c (Aux. Equipment Room). [+0.5]
were y
g 2.
Open the RPS Breakers at "Y" Panel
.5F-i.s+ep /g4.EA eprkeb7 e
(Aux.'EquipmentRoom)
[+0.5]
surd 3.
Open the RPS Breakers at the RPS Breaker Panel (InverterRoom1)
[+0.5]
. O p $ d s fa g (, g, 3. ef u M e a path
,
REFERENCE 1.
Limerick:
SE-1, Rev. 9, p. 2.
295016K201
..(KA's)
QUESTION 2.16 (1.00)
OT-112, " Recirculation Pump Trip," states that if both recirculation pumps have tripped, " ensure RWCU is in_ service using two pumps."
SELECT ONE (1) of the following statements which describes the basis foh this step. ASSUME recirculation pump trips occur at
' full power operation.
(1.0)
(a.)
Increased amount of particulate settle out under these flow conditions. RWCU in-service will remove most of the particulate and reduce the likelihood of instrument plugging on recirculation pump restart.
(b.)
~ Enhances natural circulation through the core by increasing the delta-T between the core and the bottom head regions.
(c.)
Maximizes the amount of cold water removed from the bottom head area and reduces potential for a thermal stratification problem.
(d.).
Prevents idle recirculation loops from experiencing excessive cooldown from seal purge flow in-leakage which can cause excessive thermal stress transients on the loop piping on recirculation pump restart.
(*****' CATEGORY 2 CONTINUED ON NEXT PAGE*****)
_ _ _ _ _ _ _ _ - _ _ _ _ _ _
_ _ - _ _ _ _ _
. _ _ _ _ _ - _
- 2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 30 (27%)
~
ANSWER 2.16 (1.00)
- (c.).
[+1.0]
REFERENCE 1.
Limerick:
LOT-1540, L.0. 4.
2.
Limerick: 0T-112 295001G007
...(KA's).
QUESTION'
2.17 (2.00)
'In accordance with Trip Procedure T-100 " SCRAM," Caution number 20, STATE TWO (2) conditions in which ECCS pumps may be secured.
(2.0)-
ANSWER 2.17 (2.00)
a.
confirmed misoperation
[+1.0]
-b.
adequate core cooling is assured [+1.0]
REFERENCE 1.
Limerick:
T-100 295021A104
..(KA's)
i (***** END OF CATEGORY 2 *****)
_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ -
m-
,
3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 31 RESPONSIBILITIES (10%)
i
,
QUESTION
.3.01 (2.50)
n j
STATE FIVE (5) control room indications that could verify that
.
an SRV valve is open OTHER THAN increasing suppression pool
'
temperature.
(2.5)
ANSWER 3.01 (2.50)
l a.
generator load reduction
.b.
bypass valve closure c.
SRV/ head vent valve leaking alarm d.
' safety relief valve open alarm e.
. relief valve position lights f.
gteamflow/feedflowmissmatch
O"2
.tAnyfive(%[)L+0.5bac%&
h; max. [+2.50]
REFERENCE 1.
Limerick: OT-114
\\
239001K309 239001K603
..(KA's)
QUESTION 3.02 (3.00)
Concerning the Reactor Recirculation System:
a.
STATE the TWO (2) input signals which automatically initiate the Anticipated Transient Without Scram (ATWS) Recirculation Pump Trip (RPT).
(1.0)
b.
The THREE (3) input signals which automatically initiate the End Of Cycle RPT are (1)
'(2)'
WHEN at (3)
%
power, turbine first stage pressure.
(1.5)
c.
The ATWS RPT or the E0C RPT opens the two (2) RPT breakers located between the (1)
and the (2)
(0.5)
.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_ _ _ _ - _ _ _ _
_ _ -..
. ;-_ -___ ____
--
_ _ _ _
-.
. _ _ _
_ _ _ _ _ _ _ _ _ _ _
3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 32
,
RESPONSIBILITIES (10%)
'
h ANSWER'
3.02 (3.00)
IL ' Reactor Water Low Level (-38 inches for 10 seconds).
a..
[+0.5]
2.
High Reactor Pressure (1093 psig)
[+0.5]
b.
1.
Turbine Trip (Stop Valve Closure):.[+0.5]
,
L
'2.
Lopd Reduction (Control Valve Fast Closure)
[+0.5]
.3.
3q% Power) [+0.25] at turbine.first stage pressure [+0.25].
c.
(1) MG Set
[+0.25]
(2)
Recirculation Pump Motor [+0.25]
REFERENCE 1.
Limerick:
LOT-0040, pp. 12, 20, 21, and 23.
202001K413 202001K414
..(KA's)
QUESTION
.3.03 (2.00)
' STATE F0yR (4) input signals which automatically start the Standby Gas Treatment (SBGT).
For EACH of the (4) input signals, INCLUDE the setpoint.
(2.0)
ANSWER 3.03 (2.00)
1.
Reactor Low Level; -38 inches 2.
High Drywell Pressure; 1.68 psig 3.
Reactor Enclosure High Radiation; 1.35 mrem /Hr.
4.
Reactor Enclosure to Outside Atmosphere Low Delta Pressure;
-0.1 inch H20 5.
Reactor Enclosure to SBGT Connecting Valves Failed; Open Any four (4) [+0.5] each; ([+0.25 for the input signal;
[+0.25] for the setpoint)
2.0 mkb 6,
bk beA Sgl k laMleh j l
N O'I '
7..
92d lbs. 4e 0>dsk Smosp ea 6 bdkSess c'-j
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
- _ _ _ _ _ _ _-__ _ _ _ _-_
_
'
.
{.',
l
- 3.
PLANT = SYSTEMS (38%) AND-PLANT-WIDE GENERIC Page 33-RESPONSIBILITIES-(10%)
"
,
- REFERENCE g
E i~1.
1.imerick:
LOT-180,'III.W;2,-LO 2-a, b, c.
2..
Limerick:~ LOZ-0200,.,III.I.1, LO 7.
+
1261000K401 272000K306
..(KA's)
,
'
QUESTION 3.04'
(3.00)
Concerning;the^ Recirculation Flow Control System,' MATCH all applicable conditions-in COLUMN 2 to the respective actions
in COLUMN.1.
(NOTE: not all conditions in Column 2 will be used, and some' actions may have more than one applicable condition)_
(3.0)
COLUMN 1
~ COLUMN 2 ACTIONS'
ANSWER CONDITIONS
- a.
.20% Minimum Speed 1.
Total feedwater flow is less than'20% for 15 secs.
'
b.
~75% Flow Limiter 2.
Reactor water level is less than 27.5 inches
\\..
-AND--
c.
'28% Speed Limiter individual feedpump flow :
is less:than 20%
d..
M/A station is-set at 20%
or less 4.
fluid drive oil high temperature - over 210 deg. F 5.
Total feedwater flow is.
greater than 90%
-AND-Less than three condensate pump breakers are closed 6.
Lube oil ~ low pressure (10~
psig)
lO (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
L_
_
_ - _ _ _ _
y
.;
,
'
p (-
- 3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 34-
'
. RESPONSIBILITIES (10%).
i<
ANSWER
'3.04 (3.00).
a..
b.
2, 5-c.
I d.
4,'6
' [+0.5] each; max. [+3.0]
,
- REFERENCE;
~
1.-
Limerick:
LOT-0040, LO 3, 4, and 5, pp. 9,18, and 19.
202002K603 202002K605 202001K101'
202001K119
..(KA's)
QUESTION'
3.05 (1.00).
a.
Reactor water level has decreased to below -129 inches.-
Drywell pressure is 1.2 psig..The proper.ECCS pump (s)
-is operating. ' ADS' valves will open in seconds.
(0.5)
.b.
Rgactor water level has decreased to below -129 inches.
Drywell pressure is 4.6 psig. The proper ECCS pump (s)
is operating. ADS valves will open in seconds.
(0.5)
ANSWER 3.05 (1.00)
a.
'525
' 0.5;
+
' 0.5 b.-
105-
+
REFERENCE l
1.
Limerick:
LOT-0330, pp. 9, 12, and 13, figure 6, L.O. 2, l
5,-and 6.
218000K501 218000A402
..(KA's)
i.
..
L'
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_
__
__
_. _ _ _ _ - _ _
_
!
.3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 35 RESPONSIBILITIES (10%)
QUESTION 3.06 (2.75)
For each of the NSSSS group isolations in COLUMN A, SELECT all of
'
the plant conditions in COLUMN B that would initiate isolation signals. Note - not all of the plant conditions in COLUMN B need be used, and some may be used more than once. (ASSUME: the Mode Switch is in RUN)
(2.75)
COLUMN A COLUMN B Group Isolations ANSWER Reactor Conditions a.
MSIVs and Steam Drain 1.
Low reactor water level Lines (IA)
(-42 inches)
b.
Main Steam and Reactor 2.
Main steam line high Sample Lines (IB)
rad (3.5X)
c.
RHR Heat Exchanger 3.
Steam supply low Vacuum Breaker Lines pressure (700 psig)
(IIC)
d.
High drywell pressure Lines (III)
(1.72)
HPCI\\. Turbine Exhaust 5.
Steam line low pressure e.
Vacuum Breaker Lines (90psig)
(IVB)
- ANC-high drywell pressure (1.72 psig)
6.
Low condenser vacuum (11.5 psia)
7.
Standb liquid control initia ion
>
8.
Steam line high flow (140%)
l L
l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_ _ _ _ - _ _
,
_
._ _ _________ _ _
'
ll 3.
PLANT: SYSTEMS'(38%)' AND PLANT-WIDE GENERIC
'Page 36
- RESPONSIBILITIES (10%)
y r,.A.
ANSWER 3.06; (2.75)
a..
'2,3,6,8 b.o 1,7 2 c. -
'1,T4 d.l 1, 7 e.-
5-f.
NONE
[+0.25] each correct response
.
REFERENCE-
.
1.
Limerick:' LOT-0180, L.O. 2.a.
223002K101 223002K102 223002K104 223002K107
..(KA's)'
(QUESTION _ :3.07 (3.00)-
'For EACH of the Reactor Water Levels in COLUMN A, SELECT ALL of the. plant systems'in COLUMN B which use that level for actuation-or'confi pation' input signals. NOTE: there may be more than one.
answer f6.r each Level.
(3.0)~
COLUMN'A.
ANSWER (s)-
. COLUMN B Reactor Water Plant Systems
. Levels a.
level 8 1.
NSSSS b.
level 3 2.
RPS c.
level 2 3.
ECCS d.
level 1 4.
RRCS 5.
Recire. System 6.
RCIC 7.
Main Turbine (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
..
m
_m________m___
.um_*___.a-m
___-___-----_.u.ms______-__.-em___
_ - _... _ _ _ _ _ _. - - - - - -
_. -. _ _
_
_-. _ _
__.m_._
_____m
7--
,
-
'
J E 31 ' PLANT SYSTEMS:(384
\\ND PLANT-WIDE GENERIC
.Page 37
RESPONSIBILITIES-(1 4)
q-
,
,
I
' ANSWER 3.07 (3.00)
?
a..
- 3, 6; 7y4 b.
2,: 3, ' 5; /
"E.
1,3,4,(5)',6
'd.
1, 3 maxim &$ f 0*
e REFERENCE 1.
Limerick:. LOT.-0050;; LOT-0180, L.). 2.a;. L)T-0300,. L.O. 4;.
LOT-0315,.L.0. 4.a.
216000K404 216000K405 216000K406
.216000K407-
..(KA's)
~QdESTION 3.08 (1.00)
SELECT ONE-(1) of the following statements ~ that describes the conditions which will cause~ automatic initiation of. Standby Liquid
~. Control - (SLC). High RPV pressure (1093 psig) AND:
(1.0)
(a.)
- lhw reactor water level (-38-inches) AND 118 see timer
~ timed out.
~(b.).
no APRM downscale.(4%) AND 118 sec timer timed out.
!(c.)
low reactor water level (-129 inches) AND 118 see timer
timedcout..
(d.)
no APRM downscale 4%) AND low reactor water level
(-38 inches).-
LANSWER 3.08 (1.00)
.L(b. )
[+1.0]
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_
_ _ _ _ _ _ _ _ _ _ _ _ _ -
'~
wy; r
.l l,.
a
,
i k
3h PLANT: SYSTEMS'(38%)'AND PLANT-WIDE GENERIC'
Page 38.
RESPONSIBILITIES (10%)-
F
,
\\;
REFERENCE
_
- 1. :.
Limerick:
LOT-0310, L.O. 10.
'
~211000A308-
..(KA's)
QUESTION: 3.09-(1.50)
'
L
.Concerning-Standby Liquid Control System:
,
a.
STATE the effect of a loss of. Instrument Air on the control
..
-' room SLC tank level indication.
(0.5)~
p b.
LSTATE'TWO (2) additional SLC control room indications a
other than the SLC tank level indicator which can be used to p
verify. that the SLC tank level has decreased.
(1,0)-
ANSWER:
3.09.
(1.50).
a._
(decreases to) zero
[+0. 5]
i.:
b..
SLC tank Hi/Lo level alann
'+0. 5'
2).~RunningSLCpumpstrip
+0 5.
REFERENCE 1..
Limerick:
LOT-310.
'
211000A101
..(KA's)
{ --
[-
.-(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
.-------.--------------------------__---------------_-__--.-_---_---------x----
- _ - -
-r--
.
,
)
'
.
-13C ' PLANT. SYSTEMS 2(38%) AND PLANT-WIDE GENERIC Page 39.
'
RESPONSIBILITIES (10%)
,
,
. QUESTION 13.10 (2.50)
.The following plant conditions apply:
s Reactor. power 45%;
- Total recirc -loopLflow 35%
Two recirc loop operation Reactor power is;being INCREASED to 75% with control rod manipulation
ONLY.. Using the APRM flow-biased power formulas; DETERMINE whether
.this power' increase.would: result'inta.R00 WITHDRAWAL BLOCK," FLOW
- BIASED NEUTRON FLUX-SCRAM, or N0' RESULT.
SHOW work.' ASSUME that total; recirculation flow remains constant.
(2.5)-
.
i ANSWER.
3.10
~(2.50)
R. Block-.= 0.58W + 50%.
-[+0.25]~
= 0.58(35) +.50% = 70.3%
[+0.75]
= 0.58W + 59%-
[+0.25]
=0.58(35)+59%=79.3%'
[+0.75]
Wouldrekult.in'aRodWithdrawalBlock
[+0.5]
REFERENCE 1..
Limerick:
LOT-0270, L.0. 2.a.-
2..
Limerick: Technical Specifications 3.2.2.
215005K505 215005A104 202001K123
..(KA's)
{-
(***** CATEGORY. 3-CONTINUED ON NEXT PAGE *****)
c
_
___
. _ _ _ -
-_
_
. _ _ _ - - _ _ _ _ - _
-.
- j-
,
13. ~ PLANT SYSTEMS'(38%) AND PLANT-WIDE GENERICL Page 40
-
RESPONSIBILITIES (10%)
>
E
. QUESTION 3.11 (1.00)
ASSUNING full' power operating, three-element control,.and no
- operator action, SELECT ONE (1) of the following.which would be.
~the expected Feedwater Control System (FWCS) response if the-selected level transmitter failed HIGH.
(1.0)
- n (a.)'
RFP turbines would' lock due to loss of level signal; input and level would remain approximately the same.
'(b.)
Steam and feedflow inputs would compensate'for the error
.
'
signal and level would stabilize at a slightly lower level.
(c.)
Level input'would automatically transfer to the other level:
transmitter and level. would remain approximately the same.
(d.)
RFP turbines' reduce speed in response to high'1evel signal
'
and level wi11' continue to drop unless manual action is'taken.
ANSWER
'3.11 (1.00)
=(d.)
[+\\ ]
1.0
.
~ REFERENCE 1..
Limerick:
LOT-0550, L.0. 7.c.
259002A203 215002A202
..(KA's)
l l
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
i
_ _ _ - _ - _ _ _ -
_ _ _ _.. _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _
_ _ _ _ _ - - _
_ _ _ - _ _ _.. - _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ - - _ - - - _ _ _ _ _ - _
.....,
r.
'3; PLANT SYSTEMS-(38%)-AND PLANT-WIDE GENERIC'
Page 41 s.
RESPONSIBILITIES-(10%)
u l:
i.
-QUESTION
'3.12.
.(1.50).
'
-
Concerning the Reactor Protection System (RPS), SELECT the ONE.(1):
.
most; limiting condition for each of the conditions given. MODE
' SWITCH.IS IN RUN. NOTE: Actions may be used more than once or not at all.'
.(1.5)
"
ANSWER
. CONDITION ACTIONS a.
APRM "B" flow unit-fails downscale.
1.
Rod Block t.
b.
RPS Bus "B" shifts from Normal to-2.
- Alternate power: supply-3.
Full Scram c.. SCRAM Discharge Volume water. level
.at 15 gallons ANSWER 3.12
'('1. 50)'
a.
'2.
- b.:
2.
c.
1\\
[+0.5] each REFERENCE 1.-
Limerick: -LOT-0300, L.0. 4, 5,.and 9.
212000A202 212000A204 212000A214 212000A217
..(KA's)
'(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_
. _ _ _ _ _ __
- _ _ _ _ _ _ - _ _ _ _
_ _ _ _
_ _ _ _ _ - _ _ _ _ _ _ - _ _ _ - - -
__._
3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 42-RESPONSIBILITIES (10%)
QUESTION 3.13 (1.00)
With the reactor operating at 80% power, the operator. notices a sudden increase in BOTH reactor power AND water level.
SELECT ONE (1) of the following events which would explain this transient.
(1.0)
(a.)
An SRV. opens.
(b.)
A main condenser bypass valve opens.
(c.)
RFP turbine speed increases.
(d.)
"3A" feedwater heater isolates.
ANSWER 3.13 (1.00)
(c.)
[+1.0]
REFERENCE 1.
Ljmerick:
LOT-0540, L.0. 13.
259001K301 259001K312
..(KA's)
.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- _ _ _.
I 3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 43 RESPONSIBILITIES (10%)
QUESTION 3.14 (1.00)
SELECT ONE (1) of the following which describes the control rod drive hydraulic system response during a SCRAM.
(1.0)
(a.)
The scram pilot valve energizes to vent the air off the scram inlet and outlet valves.
(b.)
The scram discharge volume vent and drain air pilot valves energize to vent the air off the scram discharge volume vent and drain valves.
(c.).
If-one of the scram discharge volume vent and drain air pilot valves fails to reposition, the scram discharge volume will remain vented and drained.
(d.)
If any scram pilot valve fails, the action of the backup scram valves will cause the rod associated with the failed scram pilot valve to scram.
ANSWER 3.14 (1.00)
(d.)
[41.0]
REFERENCE 1.
Limerick:
LOT-0070, L.O. 5 and 8.
201001K107
..(KA's)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
_-_
.
3.
PL. ANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 44 f-RESPONSIBILITIES (10%)
QUESTION 3.15 (1.50)
FILL IN THE BLANKS for the following statements pertaining to the DC Electrical Distribution System.
a.
Division I and II battery has two batteries; each with cells.
(0.25)
b.
Division I and II are capable of supplying (3)
(1)
VDC and (2)
VDC to loads for up to hours following a loss of AC power.
(0.75)
c.
Each safeguard battery has a charger which converts VAC to DC voltage to charge the battery.
(0.25)
d.
Battery compartments are continuously exhausted by fans which vent directly to the stack.
(0.25)
ANSWER 3.15 (l'.50)
a.
[+0.25]
b.
(i)
125
- +0.25]l (2)
250
+0.25
'0.25[
(3)
+
c.
440 4[+0.25]
or 4to d.
North [+0.25]
REFERENCE 1.
Limerick:
LOT-0690.
263000A101 263000K602 263000K102 263000K103
..(KA's)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
. _ _ _ _ _ _ - _ _ _
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
-
I.l Of
' 3.-
PLANT' SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 45 RESPONSIBILITIES (10%)
R, QUESTION 3.16 (1.00)
)
The fast closure of the Turbine Control Valves is an input to the
.j
'
Reactc,r Protection System. : SELECT ONE (1) of the following a
statements which describes the basis for this RPS trip.
(1.0)
!
(a.)
To prevent rapid depressurization due to a sudden TG load j
increase leading to NSSSS closure of MSIVs.
'
'1 (b.)-
To' prevent a pressure spike and resulting SRVs opening
!
due to the loss of heat sink.
(c.)-
To backup the End of Cycle Recirculation. Pump Trip and i
lessen the severity of the pressure transient.
i (d.)
To anticipate the pressure / neutron-flux / heat-flux transient.
.
<i ANSWER 3.16.
(1.00)
!
' (d. ).
[+1.0]
-l
\\
REFERENCE.
1.
Limerick:
LOT-0300, L.0. 4.
245000K307
..(KA's)
i i-l i
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ -
_ _ _ _ _ _ _ _ _ _ - _
_
_ _ _ _ _
. _ _ _ _
^
g
.j i
h,
.l
,
, h
~3.
PLANTISYSTEMS (38%? AND PLANT-WIDE-GENERIC-
.Page 46 H
'
- RESPONSIBILITIES 00%)
I l
,,
LQUESTION 3.17: l(1.00)
' Pertaining to the Traversing Incore Probe.(TIP) System, FILL-IN-BLANKS usingithe list of tenns below..
'
!
u
-
j
,
.
"
'a.'
The TIP System provides:(1)'
indication of neutron-a
-
flux distribution in'the core at (2)
locations.-
(0.5)
j
'
The TIP. System is used for'(1)
calibration.and.
!
b.
r for process computer (2)
'
distribution calculations.
(0.5)
TERMS LPRM flow-radi al_-
-power-IRM axial-i
..
.
.
(1.00)
L JANSWER
.3.17 i
ja..
(1)
axial. [+0.25]
(2)
radial
[+0.25]'
l b.'
(1) 4.LPRM ' [+0.25]
o-(2)
power [+0.25]
REFERENCE 1.
Limerick: LOT-290
,
.215001G004
..(KA's)-
= QUESTION 3.18 (1.50)
l STATE.THREE (3) rooms which use chilled water from the Control Enclosure Chilled Water System for HVAC cooling.
(1.5)
.(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
.., _
. _ _
-
i..
I[.
.
s 3L -PLANT: SYSTEMS{38%)'AND PLANT-WIDE GENERIC Page 47
'
RESPONSIBILITIES-(10%)-
'
t
-
ANSWER (3.18?
(1.50)
L 1.
-Control' Room-
=2..
Auxiliary Equipment Room 3.
Emergency Switchgear Room
<T 4.
Standby Gas Treatment Rooms 5.
Battery Rooms
/ any: three'- (3) : [+0.5]. each; max. of [+1.5]
>
'
,
I REFERENCE.
E 1.-
Limerick:; LOT-450, p. 32., LO 7.
- 290003G007'
288000K503
..(KA's)
QUESTION 3~.19 (2.00)
Given the following conditions;
. Reactor Thermal Power - 25.7%
~
Core Flow - 43%
7Recircula\\ionPumps-Bothonatminimumspeed Steam Dome Pressure - 765 psig STATE the-Safety Limit _which has been violated AND.briefly F
DESCRIBE your answer.. INCLUDE in your description the parameters
.which constitute exceeding'the Safety Limit' AND their values.
(2.0)
ANSWER 3.19 (2.00)
,
Thermal Power shall not exceed 25% of Rated Thermal Power with the reactor vessel steam dotue pressure less than 785 psig e-or.the core flow less than 10% of rated flow.
[+1.0]
Thermal' Power exceeds 25% of Rated Thermal Power [+0.5] and the reactor vessel ~ steam dome is less-than 785 psig [+0.5].
i (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
,
__-_____-_____-____-_-----&----A---.n--------
- - - - - " -
_ _ _ -
.
\\
'
.
.]
-
-3.
' PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC p
RESo0NSIBILITIES (10*)
,
Page 48 i
!
,
$ REFERENCE j
,.
M
.
<
. -.
1.
Limerick:
Technical Specificaitons 2.1.1.-
l
- 2. -
Limerick:-- LOT-1380.
-l
,
l e
290002K507.~
...(KA's)
!
'.
.
l-QUESTION 3.20'
(3.00)
l The_ High Pressure Coolant Injection (HPCI) process lines isolate automatically due to conditions being monitored by the Nuclear
Steam Supply Shutoff System (NSSSS).
For EACH of the THREE (3)
,.
'"
listed conditions which are monitored for NSSSS Group IV isolation, STATE the setpoint AND the reason for the isolation.
(3.0)l l
l CONDITION SETPOINT REASON FOR ISOLATION'
-l a
a.
HPCI Steam Line.
(1)
(2)
i delta-Pressure High b.
HPCI' Steam Supply (1)
-(2)
Low Pressure c..
HPCI Exhaust Diaphragm-(1)_
(2)
\\
High Pressure-
. ANSWER 3.20:
(3.00)
'
i a..
1..
300% [+0.50]
2.
Indicates a steam line rupture.
[+0.50]
b..
1.
100 psig- [+0.50] '
l 2.
Ensures high enough steam pressure to run turbine.
[+0.50]
c..
1.
10 psig
[+0.50]
2.
Indicates a rupture disk failure.
[+0.50]
, REFERENCE-
_ 1..-
LIMERICK:
LOT 180 III.G
.
206000K610 272000K304
..(KA's)
l
!
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_ - _ _ _ _
_ _ - _
_-__ __--_-__ - _
- _ _ _ _ _ _
. _ - _
,
03.
PLANT' SYSTEMS '(38%) AND PLANT-WIDE' GENERIC Page 49 s-
. RESPONSIBLE 1 TIES (10%)
! QUESTION 3. 2'1I (2'.00)
'
STATE FOUR,'(4) items.that must be checked;to assure.that a procedure is.v'alid in accordance with Administrative-Procedure A-7 (Shift Operations)-
(2.0)
.
' ANSWER.
3.21 (2.00)
- 1. -
Must be stamped in red " Controlled Copy." [+0.5]
or Pimt M4 2.
Station Superintendent"(or alternate's) signature (and
- date). -[+0.5]
3.
0A-Superintendent (or alternate's) signature (and date).
~[+0.5].
~
4.-
Date of use must be'later than the effective date.
[+0.5]
REFERENCE
- 1.
Limerick:. Lesson.P1an.T-LOT-1570-3.
.2.:
Liherick:. Technical Specification 6.8.2.
-3.
Limeri~ck: -Administrative Procedure A-7, Rev. 8, p. I?,
5.2.1.
294001A101-
..(KA's)
QUESTION 3.22 (1.00)
Given the condition that you are performing a non-routine activity on a component using a valid procedure and you reach a step in which you believe you should NOT. follow the procedure as written, STATE TW0.(2)' actions you should take in accordance with
~ Administrative Procedure A-7 (Shift Operations).
(1.0)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
o
[ _'
_ _... _. _
_. - _ _ _ _ _.. _.
- _ _. -. - - -. _. _ _ - _ -. _ _ -.
_. _ -. _ _ - - - - - -. _ - - - _. - _ _ _ - - - - - - - - - - - - - - -
_
y
.,
'3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 50 RESPONSIBILITIES (10%)
ANSWER-3.22 (1.00)
1.
Place the component into a stable and safe condition. [+0.5]
(accept stable or safe)
2.
Notify shift supervision.
[+0.5]
REFERENCE 1.
Limerick: Administrative Procedure A-7, Rev. 8, p. 13, 5.2.1.
2.
Limerick: Lesson Plan LOT-1570, Rev. 002, p. 15, D.2 (a.,b.).
29G01A102
..(KA's)
QUESTION 3.23 (1.50)
According to Administrative Procedure A-41 " Procedure for Control of !'lant Equipment":
a.
The person who is responsible for coordinating the individual verification of Blocking Permits application AND removal is the (0.5)
.
b.
Permission to release equipment or systems for maintenance or surveillance testing shall be granted by the OR the (1.0)
.
l ANSWER 3.23 (1.50)
a.
Chief Operator b.
-Shift Superintendent
[+0.5]; Control Supervisor [+0.5]
REFERENCE 1.
Limerick: A-41 294001K102
..(KA's)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
--
-- - -- D
.. ~
_,.
.y
'"3$
PLANT SYSTEMS (38%) AND PLANT-WIDE GENEkIC.-
Page 51-RESPONSIBILITIES (10%).
(
QUESTION 3.24 l(1.00)
" !During shift turnover, operators' reporting for duty (4)'of the
.(1.0)...
shall-receive a-verbal report from the previous shift. STATE FOUR general topics required to be covered during the verbal turnover.
ANSWER 3.24 (1.00)
-1.
General operating condition of the plant.
-
-2.
Specific operations performed and difficulties e'ncountered during.the previous shift.
3.
Scheduled plant operations.:
l4.
Equipment outages and maintenance work in progress..
.
5..
Status of safety _related equipment and conditions.
6..
Temporary. circuit authorizations.
Any four (4) for [+0.25] each; max. [+1.0]
REFERENCE-1. -
. Limerick:
Administrative Procedure A-7, Rev.
8,'" Shift Operations, Section 5.10.1','p. 27.
294001A105
...(KA's)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
'
_ _ - _ _ - _ _ _ _ _ - _ _ _ - _ _ - _ - - - _ _ _ _ _ _ _ _ - _ _ _ -
Pg -
,
,
,
3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 52-RESPONSIBILITIES (10%)
m..
-QUESTION 3.25 (1.25)
a.
USING the Shell Prewarming Timegraph (Attachment 1) and given the conditions below DETERMINE the time at which prewarming the shell will be complete.
.
Shell pressure increased to 60 psig at 1:30 a.m.
First stage shell. initial temperature was - 155 deg' F.
at 1:30 a.m.
(0.75).
b.
During shell. warming, STATE the limit for the Maximum heat-up rate.
(0.5)
ANSWER 3.25 (1.25)
a.
4:45 a.m. (+/- 5 minutes)
[+0.75]
b..
100 deg'F/Hr [+0.50]
-
REFERENCE 1.-
L}merick:
LOT-0560, " Main Turbine and Auxiliaries."
2.
Limerick:
LOT-0590, " Electro-Hydraulic Control Logic."
3.
Limerick:
GP-2, 3.2.1.
4..
Limerick:
S01.1.A.
294001A108 245000K502
..(KA's)
l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _
_ -.
_ -_ _______-____-_ _ _ ___ ____- _ _
.
% -
'
'>
sg
,
.
,
g
,.
A E3.
PLANT SYSTEMS (38%)- AND PLANT-WIDE GENERIC:
Page 53
'
-
RESPONSIBILITIES-(10%)
,
QUESTION. 3.26
.(2.00)
'
FILL in the chart to.the exposure limits of HP-102,
" Administrative Dose Limits, Guidelines and. Notification Requirements." ASSUME a completed and signed Fors
.NRC-4 is on file and.no exposure extensions have been
,
authorized;for Quarterly Exposure.
If exposure limits L
,do not apply for a particular category, enter NA'for not'
applicable.'
(2.0)
.
QUARTER-YEAR
(MREM)
(MREM)
'Whole Body 1.
4.
.
' Extremity 2.
-
l Skin ~
3.
ANSWER 3.26 (2.00)-
N
,
1.\\.~2500 mrem
' 0. 5'
+
a.
' 0. 5'
2.
15000 mrem
+
' 0. 5'
-3.
6000 mrem-
+
4..4500 mrem..
l+0.5l
!
~. REFERENCE
,
i
'1.
Limerick: LOT-1705, Rev. O, VII.
2.
Limerick: HP-102.
i 294001K103
..(KA's)
'
-,
QUESTION 3.27. -(1.50)
In accordance with Administrative Procedure A-7, STATE THREE (3)
'
steps' which the control room operators are authorized and required to enforce in order to limit.and control access to their control
. area of authority.
(1.5)
,
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
i L__:___.___-
- x. - __
_ - - _ -... _ _. - - _ - _ _ _ _ _.
. _. _. _.
- _ _ _ _ _ _ _ _ _ _ - _ _
___-_- --.
_______ ----_-____.._._. _--__-_-.-__-.
__-___b
'
'
. - - _ _ -
3. -PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 54 RESPONSIBILITIES (10%)
ANSWER 3.27.
(1.50)
- 1.-
Forbid access to the front or rear of all control panels.
[+0.5]
2.
Require verbal requests to cross the " red" line (surrounding
'
their bench board panels).
[+0.5]
3.
Order the immediate departure (or removal) of any unnecessary people from the control room when a plant emergency exists.
[+0.5]
j REFERENCE 1.
Limerick:
LOT 1570, V.G.
2.
Limerick: Administrative Procedure A-7, 5.5.
294001K105
..(KA's)
QUESTION 3.28 (1.00)
Technical Specifications set maximum limits on chlorides ir: the reactor cholant system to prevent damage to materials in contact with the coolant.
SELECT ONE (1) of the following which describes the basis for this limit.
(1.0)
(a.)
Chlorides catalyze the oxidation of carbon steel.
(b.)
Chlorides cause stress cracking of the stainless steel.
(c.)
Chlorides increase galvanic corrosion at dissimilar metal junctions.
(d.)
Chlorides increase the formation of insoluble metallic corrosion products.
ANSWER 3.28 (1.00)
i (b.)
[+1.0]
)
l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
L L-_-____-______-___
lN$a$.g..WYNN .hY
'e
- b
'
'
,,
m r-
-
-
-
- - - - - -
- - - - - - - - - -
m-b.
+
-- :
,
-
,
i
-
,
..,,e'
1 q;
.
m
'
r..r,.
i...i 1 l,
-
f. "
.
i
,.
,.i
.
..
O>
~ 3s PLANT SYSTEMS (38%) AND' PLANT-WIDE GENERIC Page 55
.
i):
'
. RESPONSIBILITIES (10%):
'
rY; a
g 1-r',-
REFERENCE, y
- f.:p
- Limerick
- -(Technica13 Specifications.
y
,
p L294001A114'
-204000A302-
- ..(KA's).
-
.-s b
~..
-
lr'
[
l3 in Lp
. ;..
I
'
.
L
!-
,
.
I m.
(***** END OF CATEGORY 3 *****)
(**********'ENDOFEXAMINATION**********)
o
__
__ _
. - _ -. _ -. -
__
- - __- --- - - __ ---_ _-.__.-_ _ -_ -.--.-- - - _ _ _ _
- _ _ _ _ _ _ - _ _ _ _ _
, _, lr.
.
.
~3?
i
,
s
{ ",,
c
"
[?
n-l TEST CROSS REFERENCE:
Page 1
'
- '
OUESTION
'VALUE. REFERENCE
'
%
'1. 0 11
.2.00-90002
"
'1.02:
1.00-90003-
1.03-
.1.001 90005~
?1.04 2.00 90006.
- 1.05f 1.00:
90017.
,
L 1. 06 '. -
1.00
.90004
?
1.07-1.00
.90007-E L1.08 L1.00 90008.
'
f 1.09 -
1.50 90009 1.10
.1.00l 190010 1.11-1.00 90016 L1.12-1.50
.90001 11.~ 13 1.50 90011
-
1.14J 2.50.
'90012.
,.1 1.15.
.' 1. 00 ;
90013 f'
'1.16 3.00-90014 1.17.
2.00:
90015
"
......
25.00 2.01 11.50 90018 2.02=
2.50
.90019-
- 2.03-
~1.00 90020 2.04'
2.00 90021-2.05-1.00 190022 2.05'
1.00 90023
' 2.07.;
2.00
=90024 2.08 1.00 90025 2.09' 4
'1.50-90026 2.10 3.00 90027
' 2.11'-
2.00 90028 L
2.12 1.00 90029 2.13 2.00 90030 2.14 1.00 90031 2.15 1.50 90032 2.16-1.00 90033 2.17 2.00 90034
......
27.00
'
3.01 2.50 90035 3.02 3.00 90044
.3.03 2.00 90045 3.04 3.00 90046 3.05 1.00 90047 3.06 2.75 90048 3.07 3.00 90049
'3.08 1.00 90050 3.09.
1.50 90051
.3.10-2.50 90052 3~11 1.00 90053
.
3.12-1.50 90054 3.13-1.00 90055 3.14-
'1.00-90056 3.15'
1.50 90057
V
_
_
- - - - _ _ _ - _ _ - --____--_ _ _____----_ -.______--___ _ -_ _ - - - _ _
-
h Ai
'
y
' l; '
Ljo
.
'
'
'
'
MQ.N. '
.
' f _
g' g
f.;
'
TEST / CROSS REFERENCE.-
.Page-.2
,
,.
g
)
L
.0UESTION-VALUE ' REFERENCE li 3.16-1.00'
90058-r!
3.17'
1.00'
90059-
~
cz
- 3 '.18 '
'1150
.900601
+
- 3.19
'2.001
.90061
.
i3.20
'3.00 90062 i; ?
'3.21
- 2.00.
90036
-
3.22:
'1.00L
.
'
'3.23-
'1.50f-90038 90037a
.
I/F 3.24 1.00:
90039-
.3.25 1.25
'90040
,
3.26 2. 00 '.
- 90041-3.27-1. 50
90042
'3.28
' 1.00 :'
90043'
-
.......
48.00
'
........
-
i55:5
,
..
l:; _-
o
[
\\.~
f.
-
.,
k l
I c
-
e
_
___:_.
--- - _ _ _ _
. _ - _ _ _. _ _ _
_--__-_--___--____________---____A
_.
_ _ _ - _ _
-
- -
'O i ATTAC.H (6 6tJT
~
NRC REACTOR OPERATOR EXAM (6/12/89) RESPONSES Category'1:
Reactor Principles (7%), Thermodynamics (7%) and Components
!
(11%)
(Fundamentals Exam)
Question 1.12.a.
Additional correct response should be " Direction".
Reference:
_ LOT-1291, Page 5, VI. A.3
......................................
Question 1.12.b/c Additional correct response should be
" Acceleration" or "Ar.ea".
e Reference:
LOT-1291, Pages 4 and 5 VI. A.3. a,b.
" Acceleration" V. B. 1
" Area" (Similar question SRO 4.12)
.......................................
Question 1.13 As discussed at the Pre. Exam review, this question was changed in order to clarify the intent of the question. Assume ideal conditions was added in order for the examinees to "zero in" on the generic theory behind adding same size centrifugal pumps in series / parallel.
Ideally, the best you can get by adding a second pump in parallel is double the flow rate at the same head capacity (Assuming EQ system i
(resistance to flow) Curve).
Additionally, the best you can get by adding one in series is the same flow rate with double the head capacity.
The answers on the original draft copy were correct as stated during the Pre-Exam Review and should be as follows:
a.3 b.5
c-2 l
'
J Re ference :
LOT-1290, Pages 8 and 9 a - G.5 a and b b - G.6 a and b c - G.8 a
'
(Similar question SRO 4.11 parts b, c, and d)
L_______________-.__.
-
_
I
- - _ _ -. _ _ _.
-.
_-
._ _ _ _ _ _.
- _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _
.
.,-
NRC REACTOR OPERATOR EXAM RESPONSES (6/12/89)
- Continued Question 1.14 b.1
' Alternate answer would be " Indication of ION exchange _ depletion" or similar-wording, b.2 Alternate answer would be " mechanical blockage" or similar wording.
(Similar question SRO 4.13)
......................................
Question 1,15 As discussed at the Pre-Exam review, this question can be correctly answered different ways depending on assumptions.
First, since the examinees weren't
provided an operating map (Power.to. Flow) this
required them to assume conditions.
Secondly, the question did not state " Limit your answer to initial response".
For these reasons, correct responses to this question are:
1.
As written in the answer key.
OR 2.
Decrease due to two. phase-flow resistance OR
'
\\
3.
Increases initially then decreases due to two phase flow resistance.
Reference:
LOT-0040, Page 25 i
'
B.2.b.2) and T. LOT-0040 8 (Similar Question SRO 4.14)
l
.......................................
Question 1.17 a As discussed at the Pre-Exam Review, it was agreed to accept the equation equivalent for NPSH.
A correct equation equivalent may also include the elevation (static) head term and/or the friction head loss term.
Reference:
LOT.1290, Page 5 D.1.b (Similar question SRO 4.16a)
a
- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
>
s
,
E'n
-
"n.
sr
>
.
.
.
.
NRC REACTOR OPERATOR E)UV4 RESPONSES (6/12/89)
- Continued
<
%
CateForv 2:
. Emergency and Abnormal Plant Evolutions (27%)
Question 2.04.c-Correct response is
"8" (.161 in.)
-
Reference:
T.101 bases, Page 20 RC/L.5 Discussion
'
(Similar SRO Question 5.10)
l
........................................
!
Question 2.06.a Correct response is 17 inches, n
Reference:
LOT.0550, Page 11, 7.b (Similar SRO Question 5.08)
....................................--
Question 2.15 As discussed at the Pre-Exam Review, this question was changed to ask the three ways per SE-1.
Request you consider candidates responding with, similar, correct, wording as to that which is in the answer key.
For example, answer key states "Open the RPS breakers at "Y" panel".
Similar wording - Open circuit 13 on "Y" panel.
_ Reference:
SE-1, Page 2, Steps 4.5.1, 4.5.2, 4.5.3
.\\'
(Similar SR0' Question 5.13)
i
__________________________________j
- ___
!
,,
.,
..
NRC REACTOR' OPERATOR EXAM RESPONSES -(6/12/89). Continued Catevory-3:
Plant Systems (38%) and Plant-Vide Generic Responsibilities (10%)
Question 3.01 Other correct responses would be the causes of the alarms for the open SRV and similar wording for the relief valve positon lights. These responses are:
.
Acoustic Monitors Tailpipe Temperatures Reference:
Alarm Response Cards (ARC's)
ARC.MCR-110 Page 10 ARC-MCR-110 Page 11 (Similar question SRO 6.08)
......................................
-Question 3.0.2.b.3 Answer key requires:
"30% power at turbine first stage pressure" for full credit.
Exam question provided:
% power, turbine first stage pressure. Correct
__ response therefore is 30.
Reference:
RO Exam Question 3.02.b and Answer Key.
\\
(Similar Question SRO 6.16 Part b.is correct as stated on SRO Exam / Key)
.......................................
Question 3.03 Other correct responses are:
Refuel Area High Rad; 2.0 mrem /hr Refuel Area to Outside Atmosphere Low Delta Pressure; 0.1 inch water Reference:
Technical Specifications pages.3/4 3 15, 3/4 3-16, 3/4 3-22 Trip Function 7.c Trip Function 7.f Table 3.3.2-1 Notation c Trip Setpoint 7.c Trip Setpoint 7.e (No Similar SRO Question)
i
-.
- F
,
~ NRC REACTOR OPERATOR EXAM RESPONSES'(6/12/89I
. Continued Question'3.06.f Delete answer f (None) from answer' key.
Question 3.06.f did not appear on RO exam.
It-did appear on SRO exam.. Question 6.11.
Reference:
RO Exam 3.06.f and answer key.
.
(Similar SRO Question 6.11, which is correct as stated.)
.................................
Question 3.07.b Additional correct response for Level 3 (+12.5 inches) is Response 1 (NSSSS).
It is an isolation signal for groups IIA and IIB of NSSSS.
Reference:
GP.8 Pages 128, 129, and 130.
.(Similar SRO Question 6,07.)
.................................
Question 3.15.c Other correct response is 480.
LGS uses 440 VAC and 480 VAC interchangeably.
Reference:
LGS FSAR Page 8.3-1 Description 8.3.1.1 (No Similar SRO Question)'
................................-
Question 3.18 Additional correct responses are:
-\\
Remote Shutdown Panel Room Computer Room Reference:
P61D M-78 Sheet 2 of 4 (No Similar SRO Question)
...............................
-
Question 3.21 For the response " Station Superintendent" (or alternate) the title Plant Manager (or alternate)
is now used at LGS.
Reference:
Technical Specifications, Page 6 13, Procedures 6.8.2 (Similar SRO Question 6.30)
..................
................
l
_________ __-_-_-_____ -
-
,
-
_.. _
_ _ _ _
_
.
NRC SENIOR REACTOR OPERATOR EXAM (6/12/89) RESPONSES (Continued)
' Question 3.23.b For the response " Control' Supervisor" the title applies to the SRO in charge of the Control Room.
,
Other titles-used for this position at LGS are:
. " Room Supervisor"
" Shift Supervisor" Reference:
Technical Specifications,-Page.6-1, Responsibility 6.1.2 (No Similar SRO Question)
\\
l l
{
!'
_ _ _ - _ _ _ _ _.. _ _ _ _ - _ -
- -, _ _ -.
.
I
!
.
.
(6/12/89) RESPONSES
,
.
NRC SENIOR REACTOR OPERATOR EXAM
.1 Category 4:
Reactor Principles (7%), Thermodynamics (7%)'and Components i
(10%)
(Fundamentals Exam)
l
Question 4.11.
As discussed at the Pre-Exam review, this question was changed in order to clarify the intent of the question. Assume ideal conditions was added in order for the. examinees to "zero in" on the generic theory behind adding same size centrifugal pumps in serias/ parallel.
Ideally, the best you can get by adding a second pump.in parallel is double the flow rate at the same head capacity (Assuming E0 system (resistance to flow) Curve).
Additionally, the best you can get by adding one in series is the same flow rate with double the head
'
capacity.
The answers on the original draft copy were correct as stated during the Pre-Exam Review and should be as follows; b-3 c.5 d-2 Reference:
LOT-1290, Pages 8 and 9 b - G.5 a and b
\\
c - G.6 a and b d - G.8.a (Similar question R0 1.13)
.................................
s Question 4.12.a Additional correct response should be " Direction".
!
Reference:
LOT-1291, Page 5, VI. A.3
..................................
Question 4.12.b/c Additional correct responae should be
'
" Acceleration" or " Area" Reference:
LOT.1291, Pages 4 and 5 VI. A.3, a,b -
" Acceleration" V. B. 1
" Area" (Similar question R0 1.12)
l
. _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _
575
!r.
.
-
NRC SENIOR REACTOR OPERATOR EXAM RESPONSES (6/12/89)
- Continued Question ~4.13 b.1 Alternate answer would be " Indication of. ION exchange depletion" or.similar wording.
b.2-Alternate answer.would be " mechanical blockage" or similar wording.
(Similar question R0 1.14)
...................................
Question 4.~14 As discussed at the Pre-Exam. review, this question can be correctly answered different ways depending on assumptions.
First, since the examinees weren't provided an operating. map (Power-to-Flow) this-required them.to assume conditions.
Secondly, the question did not state " Limit your answer to initial response".
For these reasons, correct responses to this question are:
1.
As written in the answer key.
OR 2.
Decrease due to two-phase-flow resistance l
l OR
'1
\\
3.
Increases initially then decreases due to two phase flow resistance.
Reference:
LOT-0040, Page 25 B.2.b.2) and T-LOT-0040-8 (Similar Question R0 1.15)
..................................
Question 4.16 As discussed at the Pre. Exam Review, it was agreed to accept the equation equivalent for NPSH.
A correct equation equivalent may also include the elevation (static) head term and/or the friction head loss term.
Reference:
LOT-1290, Page 5 D.l.b (Similar question RO 1.17a)
. _ _.. -.
.
- -
t
-
NRC SENIOR REACTOR OPERATOR EXAM RESPONSES (6/12/89)
Continued
'
[.
Catenorv-5:
Emergency and Abnormal Plant Evolutions (33%)
l L
L
~
Question 5.08.a Correct response is 17 inches.
Reference:
LOT.0550, Page 11, 7.b (Similar RO Question 2.06)
...................................
.
Question 5.10.c Correct response is
"8" (-161 in.)
Reference:
T-101 bases, Page 20 RC/L.5 Discussion (Similar RO Question 2.04)
.....................................
Question 5.13 As discussed at the Pre-Exam Review, this question was changed ta_ask the three ways per SE-1.
Request you consider candidates responding with similar, correct, wording as to that which is in the answer key.
For example, answer key states "Open the RPS breakers at "Y" panel".
Similar wording - Open circuit 13 on "Y" panel.
\\
Reference:
SE-1, Page 2, Steps 4.5.1, 4.5.2, 4.5.3 (Similar RO Question 2.15)
....................................
Question 5.14 Correct response is "To ensure sufficient cooling flow through the core."
Reference:
T.115 Bases Step AK-ll Discussion (No Similar RO Question)
_ _ - _ _ _ _ _ - _ _ _ - _ _ _ _ - _ _ _
-
_ _ _ _.__ _ _ _ _ _ _
3..
<
r?
l NRC SENIOR REACTOR OPERATOR EXAM RESPONSES-(6/12/89)~. Continued ji L.
Question 5.16.c.
As discussed at the Pre-Exam Review, entering T.100 on 1.68 psig drywell is not incorrect, but is not necessary since 1.68 psig requires entry to T.101.
It was agreed that response 1 would be added to
_
part c, but would be bracketed (' ).
Therefore, the answer key to part c would read:
(1), 2, 3 Reference:
SRO Exam Question 5.16.c and Answer Key (No Similar RO Question)
......................................
Question 5.20 Basis for this step in ON.119 " Loss of Instrument Air" also states that, a reactor scram, should it occur, would be a less severe transient when initiated at a lower reactor power.
Answer
'B',
Limit the reactivity transient caused by the closure of the MSIV's, should also be considered as a correct response.
Reference:
ON-119 Bases Page 3 Step 2.4.1
(No Similar RO Question)
i
\\
i i
_ - _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ - _ -
-__
__.
_ _ _ _
-
_
y
NRC SENIOR REACTOR OPERATOR EXAM RESPONSES (6/12/89)
- Continued Catenorv 6:
Plant Systems (30%) and Plant. Wide Generic Responsibilities (13%)
Question 6.02.b Additional correct response for Level 3-(+12.5 inches) is Response 1 (NSSSS).
It.is an isolation signal for groups IIA'and IIB of NSSSS.
Reference:
GP-8 Pages 128, 129, and 130.
(Similar RO Question 3.07)
.................................-
Question 6.07.b With the information provided, the answer.for part
'b'
should be Tech. Spec. 4.8.1.1.2.a.5 vice 4.8.1.1.2.a.4.
. Tech. Spec. 4.8.1.1.2.a.5 refers to the load (i.e., 2800 kw).
Secondly, the question as worded, " Surveillance was run to test the "ECCS" actuation signal" may lead the candidate to Tech. Spec. Surveillance Requirement 4.8.1.1.2.e.5, which is an ECCS actuation test signal.
.
This Surveillance Requirement requires the diesel to run unloaded and operate in standby for 5 minutes.
l Using the data supplied:
\\'
Generator Load:
2800 kw in 135 seconds would make that Surveillance Requirement fail, and declare that diesel INOP per Tech. Spec. 4.8.1.1.2.e.5 Reference:
Technical Specifications Pages 3/4'8 3, 8 4, 8 5 4.8.1.1.2.a.5 4.8.1.1.2.e.5 (No Similar RO Question)
.................................-
Question 6.08 Other correct responses would be the causes of the alarms for the open SRV and similar wording for the relief valve position lights. These responses are:
Acoustic Monitors Tailpipe Temperatures Reference:
Alarm Response Cards (ARC's)
ARC.MCR.110 Page 10 ARC-MCR-110 Page 11 (Similar question RO 3.01)
...............
-............. - -.
. _. _ _ _ _
____.______-_-____-__m._______.____
_. _ __
.
NRC SENIOR REACTOR OPERATOR EXAM RESPONSES-(6/12/89f - Continued Question 6.13 Without providing a specific float voltage, the candidate may elect to be conservative and also consider the float voltage.not within the allowable i
value for category B which would lead him to choose answer (a) which is:
(a). " Division 1 is INOPERABLE and must be-restored
. to operability within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in 110T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."
Reference:
Technical Specifications Pages 3/4 8-10, 8-11, 8-12, 8-13 Table 4.8.21-1 Notes (1) and (3)
Action: On page 3/4 8 10 for INOP Battery.
~
(No Similar RO Question)
.......................................
Question 6.30 For the response " Station Superintendent" (or
alternate) the title Plant Manager (or alternate)
is now used at LGS.
Reference:
Technical Specifications, Page 6-13, Procedures 6.8.2 (Similar SRO Question 3.21)
\\
I i
i
_ _ _ _ _ _ _ _ _
--__ ___
._
_.
J j ATTAchi M Erd H
'
'
Limerick Exam.- 6/12 - 6/16/89'
R0 Written Exam
' Facility Comments and Resolutions L
. Question 1.12.a.
L The. question asks-for a completion of-the definition for Water Hammer. The l
stem of the question is verbatim from the-facility training material,.I. A.1.,
Partial credit will be considered for each response which describes a Ate of water hammer AND which is grammatically correct; for example, the facility suggested " direction."
Question 1.12 b./c.
The question is seeking three factors which affect the magnitude of the impulse force.
Time is given.
The facility training material' formula for impulse -
force'is F=M x V/t. The correct response for full credit, therefore, would be " mass" and " velocity."
Partial credit [+0.25] for " acceleration" will be given only if the second response is " mass" completing the formula F=Ma.
Answer key is modified.
Reject the facility recommendation to allow the additional response " area."
V.B.1 is a review of the calculation of mass of water in a pipe in a discussion of the momentum of water.
Question 1.13
. Accepit facility comment, correct answers will be change to a. 3, b. 5, c. 2.
Answer key is modified.
Question 1.14 b.1 Comment accepted. Answer to include alternate response " indication of ion exchange depletion." Answer key is modified.
Question 1.14 b.2 Answers similar to " particulate clogging" only will be accepted.
Question 1.15 As agreed to in the pre-exam review, the candidates response will be graded as per the answer key. Other responses such as facility recommendation 2 and 3 wilI be considered for full credit if assumptions are stated and the response is correct, i.e. flow change is stated AND the reason for the change is stated and. correct.
Question 1.17 a.
Comment accepted.
Answer key is modified to change the equation equivalent for NPSH to NPSH= Hp-Hf-Hvp-H _
_
____.
,
Page 2 Limerick R0 Written Exam Facility Comments and Resolutions Question 2.04 c.
Comment accepted. Answer key is changed to "8" (-161") for correct response.
Question 2.06 a..
Comment accepted. Answer key is changed to "17 (inches)" for correct' response.
Question 2.15 Comment accepted. Responses in agreement with SE-1 steps 4.5.1, 4.5.2, and 4.5.3 will be accepted. Answer key modified to include comments.
Question 3.01 Comment accepted. Added " Acoustic Monitors" and " Tailpipe Temperature" as acceptable responses.
Question 3.02 b.3 Comment accepted. Added parentheses around % power in the answer key.
Question 3.03 Comment accepted. Answer key modified to include (1) Refuel Area High Radiation; 2.0 mrem /hr, and (2) Refueling Area to Outside Atmosphere Low Delta Press'ure; (-) 0.1 inch water.
Question 3.06 f.
Comment accepted. Removed answer "f. None" from key.
Question 3.07 b.
'
Comment accepted. Added 1. NSSSS" for level 3. to answer key.
This makes each response worth 3.00/13 = [+0.231] with a maximum question value of [+3.0].
Question 3.15 c.
Comment accepted.
"480" will be accepted as equivalent to 440. Answer key modified.
Question 3.18 Comment accepted.
Added the Remote Shutdown Panel Room and Computer Room to the answer key.
_ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ -
Q
-
'
.,
,
- '
4s a.
'
<
"
,
i'q.; -
- ','
'
- Page 3 Limeridk R0 Written Exam-
- Facility Comments.and Resolutions-
,
M'
Question'3.21'
p Comment accepted. Modified answer. key to add "or Plant Manager."
,
,
,
. Question 3.23 b.-
Comment! accepted. Answer key is' modified to include " Room Supervisor" or-
~
i!
" Shift Supervisor" as a correct response.
Comment to Facility:
It is a poor administrative policy to allow two or'three.
<
- different designations (titles) apply:to one position.
l:'
.
\\.
1
}
.
-._m..a
_m.
-_
__
_.____.-...-___m-
_ _ _. - _. _ _. _ _ -. - _ _ - - -.. -. - - - - - - - - - _ -. _ - - - - - - - - - - - - -
--
C, s'
"
c.
-
.i s
.
.
-
,
..
j
'
'
'
,
,
,
,
.- J
.
.
.
')
Ku,
' Limerick ~ Exam 1--6/12L.6/16/89 R
,
b
.SR0 Written' Exam' '
j ('
? Facility Comments and Resolutions l
lx
[
. Question 4.11'
y
,
Comment Accepted. Correct answers will be changed to a.3, b.5,'c.2.
Answer l
key,is modified.-
.,
,
-
Question 4.12~a..
-
Comment is not applicable to the SR0 exam.
g
!
. Question 4.12 b./c.
.
-Comment; refers.to'4.12'a. and.b.'~of SR0 exam.
The question is-seeking three' factors which affect the magnitude'of the impulse
!
force.. Time'is given. The facility' training material formula for impulse j
force is F=M x V/t. 'The correct response for full credit, therefore,.would-l be " mass" and'" velocity."
.' l
,.
.
Partial credit [+0.25];for " acceleration" will.be given only if the second
.)
' response is " mass" completing the formula F=Ma.
Answer key is modified.
i
{
-
. Reject the facility recommendation to allow the additional response " area."
V.B.1,is:a' review o.f the calculation of mass of water in a-pipe in a discussion
'of.the momentum of,ater.
'
w Questfon4.13b.1 Comment accepted. Answer to include alternate response " indication.of' ion =
'
exchange depletion." ' Answer key is modified.
'
Question 4.13.b.2
'i Answers similar to " particulate clogging" only will be accepted.
!
-
-Question'4.14 As, agreed to in the. pre-exam review, the candidate: response will be graded
>.
.as per the answer key. Other responses such as facility recommendation 2 and 3 will be considered for full credit if assumptions are stated and the response is correct, i.e. flow change is stated AND the reason for the change is stated and correct.
Question 4.16 a.
Comment accepted.
Answer key is modified to change the equation equivalent for NPSH to NPSH= Hp-Hf-Hvp-Hz.
I
.s 1___
_ _ _ _ _ _ _ _ _ _ _
_ _ _ _. _. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_
_
k. ~.,
+
,
,.
,
,,
.
,
,
.
- Page 2
?
Limerick.SRO Written Exam y
facility Comments and Resolutions 1.
. Question 5.08 a.
.
Comment accepted. Answer key is chanpd to "17 (inches)" for correct response.
1, LQuestion 5.10 c.
Comment accepte'. Answer key is changed to "8" (-161") for correct. response.
d-Question 5.13-1 Comment accepted.
Responses in agreement with SE-1 steps-4.5.1, 4.5.2, and 4.5.3 will be accepted.. Answer key modified to include comments.
. Question 5.14 a.
Comment rejected. LOT-1560,' p. 20 of 1 and T-115 Bases, Step AK-14 1(Discussici), state that the reason for maintaining reactor pressure 50 psig above' suppression pool pressure.is to assure the SRVs stay open.
Question 5'14 b.-
.
Comment accepted. ' Answer key will be modified to reflect the change.
-Question 5.16 c.
-Commept accepted. ' Answer key will be modified to reflect the change. This does hot affect th'e point values for he question.
. Question 5.20'
Comment' rej ected.
The explanation of Step 2.4.1 in ON-119 makes no mention
'of a reactivity transient.
there is no mention of concerns about reactivity transient being caused by the closure of the MSIVs anywhere in the procedure.
A reactivity transient would only occur on a fast closure of.the MSIVs'which is-not addressed _in the Bases. The only item.in ON-119 that concerns the MSIVs is_a note on page 8 of 10.
Note: MSIVs may begin to drift close.
This. note applies'to the ability to maintain the main condenser as a heat sink. The MSIVs are closed in Step 2.7.2 a and b to protect the turbine and condenser from overpressurization.
<
-Quest' ion'6.02 b.
Comment accepted.
Added 1. NSSSS" for level 3. to answer key.
This makes each response worth 3.00/13 = [+0.231] with a maximum question value of [+3.0].
_ _ _. _ _ _ _ - _.
.
.
. - ~
_.
.___, _-.
Page 3 Limerick SRO Written Exam Facility Comments and Resolutions L
Question 6.07 b.
-
Acc'ept the change of T.S. 4.8.1.1.2.a.5.
Answer will be modified to reflect the change.
Reject the. suggestion of T.S. 4.8.1.1.2.
5.
There is no mention of generator load in that surveillance requirement.
Question 6.08 Comment accepted. Added " Acoustic Monitors" and." Tailpipe Temperature" as acceptable responses.
Question 6.13 Comment accepted. Answer key will be modified to reflect the change.
l Question 6.30
!
Comment accepted. Modified answer. key to add "or Plant Manager."
Comment to Facility: For exam preparation in the future, it would be helpful if the Bases for the TRIP Procedures could be included in the reference material.
\\
)
.
_ _-_____________ _____-__-______-____-- - _
,
n
,
.
c
. Attachment 5
SIMULATION FACILITY REPORT Facility Licensee: Limerick Unit-1&2 Facility Docket No.:
50-352/50-353
'Operat'ing TAsts Administered on: June 13-15, 1989 This form is to be used'only to report observations. -These observations do
- not constitute audit or inspection findings and are not, without further-verification'and review, indicative of non-compliance with 10 CFR 55.45(b).
,These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations.
No licensee action is required in response to these observations.
During the conduct of the simulator portion of the operating tests, the following. items were observed (if none, so state):.
ITEM DESCRIPTION r
1.
ATWS During the ATWS scenario Reactor Power was 63% and turbine was tripped, only 8 bypass valves were open
'
(out of nine) and the SRV were closed after only going open for a short period of tine.
L 2.
Dry Well With both Reactor Recirculation Pump. seals lost and the recire. pump secured Dry Well pressure never increased.
f i
'