ML20245B463
| ML20245B463 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/30/1988 |
| From: | Owen T DUKE POWER CO. |
| To: | Moorman J, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20245B444 | List: |
| References | |
| RTR-NUREG-1122 NUDOCS 8904260118 | |
| Download: ML20245B463 (45) | |
Text
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' I.
ENCLOSURE 3
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' lbuke_ Isver Campany (w,1) git., juno Catan ha %uclear Station -
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- Pu II ?x:is Chorer S C ;!!alin
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DUKEPOWER September 30, 1988.
Mr.-John Munro operai.tr Licensing l.
Section Chief, Region'II US Nuclear Regulatory Commission.
101 Marietta Street, Suite 3100
' Atlanta, Ga 30323 Attention:
Mr. Jim Moonnan b
Chief Examiner'
Subject:
NRC Written Exam Review
. Comments concerning the NRC License Exams given to Catawba Nuclear Station Operators on Sept. 26, 1988 are attached. The comments are divided into RO and SRO comments with each comment referenced to a question and supporting documentation.
Sincerely,
/(/st/ d s-_- /~
T.B.'_Owen
[
Station Manager t
Catawba Nuclear Station CTK/GCD cc.
W.-H.
Barron J. W. Cox H. B. Barron 89042601 PDR 8 890407 V
ADOC 050004 3 PN l
The following overall comments have been c smpiled on the reactor operator and senior reactor operator examinations give, at Catawba Nuclear Station on September 26, 1988.
1.
Many questions in Section 6, two questions in Section 7 and two questions in Section 8 do not appear to be heading toward what we have been striving for in examinations. We have made tremendous headway within the Requal area. That is, making the examinations more operator oriented. These questions are referenced in the attached comments.
2.
Not all questions asked had objectives associated with them and some really djd not tie to the objective referenced.
3.
The questions were taken largely from training handouts, picking out details which were put in the handouts to help the instructor answer
-questions, not to be examined on.
Attached are comments on individual questions.
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l We found these following questions to be excellent and would like to see questions of this type used often.
'We commend you for your effort on these questions.
RO Exam 1.06 1.19 SRO Exam 6.02 7.01 l
I QUESTION 1.03
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ANSWER 1.
b.
2.
d.
FACILITY RESPONSE: This question asks the operator to know whether his power went below % instantly or took 30 seconds or longer. THe referenced handout says "within 30 seconds", which means anywhere from 1 to 30 seconds.
In reality following a reactor trip (responses from transient monitor on trips on Unit 1 and 2 attached) the power drops to < 2 1/2 % in 10 seconds, which if the operator looks at that on the control board meter, it looks like bottom of scale. We realize this in writing our procedures, therefore, we have the operator look at Intermediate Range Amps instead of Percent Power (see attached page from EP).
Request credit for a or b and question be changed for future use to delete 1 second as an option and add 120 seconds.
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c, QUESTION 1.10-ANSWER b.'
FACILITY RESPONSE:.Both responses a and b are correct as shown on the.;tached
-data' book-tables.
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'We request credit for a og b L
.As:shown'on attached table from the data book, it shows in the example at 425 F, the gallons of boric acid to go from 1400 ppm to 2000 ppm is.8032, whereas at.
-normal operating temperature, to make the same change it requires less boron
- (1.e. 7605 gallons), which is what selection "a" states.
The second table' attached show that for any given boron' concentration that the reactivity. associated _with that boron is less at high temperatures than at low
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temperatures.- This: implies less boron in the core at high temperatures, which makes "b" correct.
Therefore,-both. selections a_ and b are correct.
- t QUESTION 2.04
-ANSWER
,a.
.High-High Containment pressure (0.2)- 2/4 CTMT PRESS CH (0.1)
>/=3.0 psig (0.2) or Manual (.2) 1/2 Pushbuttons (0.2)
In coincidence with (0.3) a Containment Pressure Control Signal (CPCS (0.2)
>/=.4 psig (0.2).
(Coincidence required for either Manual or Hi-Hi Ctmt
. press initiation.)-
b.
Ice condenser depleted.
Containment pressure rising (or stable and > 10 psig)
ECCS and NS systems operating in recirculation mode (0.25 each ans.)
One hour (50 minutes also acceptable) after the accident.
' FACILITY RESPONSE: Then b question asks for four conditions and there are more than four. 'One of the' answers on the key is wrong (i.e.
Ice condenser Depleted) for there'is no way'the operator will know when that occurs. One of the answers is an interlock to open ND containment spray valve, therefore other interlocks should be accepted.
We request the answer to b to become as follows:
Any (4)'four of the following:
1.
ND suction from sump open or in Recirc Mode (Only look for 1 cr the other) 2.
Time since accident > 50 minutes 3.
Containment pressure > 10 psig 4.
._ Containment pressure > 1.2 psig 5.
ND suction from loops closed (ND1 or 2 A train, ND36 or 37 train) 1
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I-QUESTION 2.05 ANSWER The isolation MOV on the MDP supply lines to S/G B or C will close automatically (0.5) if the turbine. driven pump is operating (0.5) and the MD pump of the opposite train fails to run (0.5).
(MDP-B supply to S/G "C" isolates if MDP-A i
fails to start.)
'The isolation MOV on the MDP supply lines to S/G B and C (0.5) will automatically close when the associated MDP discharge flow exceeds 730 GPM.
(0.5)
(MDP-A supply to S/G B isolates if MDP-A discharge flow exceeds 730 GPM.)
FACILITY RESPONSE: The setpoint for runout protection has_ changed to 780 gpm.
l The question asks for two design features and the CA system and there 3 design features.
We request the answer be Any two (2) of the following:
" Answer" w/ 730 changed to 780 The CAPT discharge to A, and.D S/G's is normally closed.
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QUESTION 2.08 l*
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L ANSWER' 1.
'All FOUR (4) RN Pumps start.
2.
RN Pump. discharge isolation valves (1RN28A, 2RN38B, 2RN38B) open.
3.
RN Pump Motor Cooler inlet-isolation valves (1RN11A, 2RN11A, 1RN208, 2RN20B) open.
4.
D/G Jacket Water Cooler inlet isolation valves (1RN232A, 2RN232A, 1RN292B, 2RN292B) open.
5.
Splits the Essential Supply Header 6.
Isolates the Non-essential Supply Header (Any 5 at 0.4 each)
FACILITY RESPONSE: There are more than six (6) automatic actions which occur.
RN discharge isclations and motor cooler isolations open on pump start.
-We request.the answer be:
Any five of the following:
1.
All four.(4) RN pumps start.
2.
D/G KD RX isolation valves open (1RN232A, 2RN232A, 1RN292B, 2RN292B).
3.-
Splits Essential Supply Header (1RN47A, 488, 2RN47A, 48B) 4.
Isolates the Non-Essential Header 5.
Lube Injection Crossover Valves close
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Essential Header Inlet Isolations open 7.'
KC.Hx Inlet'Isolations open 8.
KC Hx Outlet Isolations open 9.
Isolates Aux Blg Vent Header 10.
Discharge to SNSWP opens 11.
RN to' Containment isolates 1
QUESTION 2.11 (a)
ANSWER a.
Automatically closes on a low-low level in the CA CST tank. (0.5)
FACILITY RESPONSE: Valve nomenclature is wrong (see attached). The valve closes on low or low-low level.
We request the answer be:
'. Automatically closes on low (low) level in CA CST.
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i QUESTION 2.13 (a)
ANSWER a.
Describe the design feature that prevents KC Containment Isolation Valve (KC429B) from repositioning during a flooding event. (1.0)
FACILITY RESPONSE:
This is not information required of the operator. There is no objective for this question. The information is not covered in the operators handout and the valve nomenclature is wrong.
What is taught on this valve is attached.
We request that part a_ of this question be deleted.
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QUESTION 2.14 (b)
ANSWER b.
Denergizing the two breakers causes control of the PORVs to fail to the AUTO position (0.25) and indication for " AUTO / MANUAL" is lost (CWF)
(0.25)
FACILITY RESPONSE: This is not required for the operator. The procedure does not address these breakers and the operation of these is not an objective of RO training.
(See attached).
We request this question be deleted.
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QUESTION'3.06
- ANSWER; a.-
Reactor trip breaker-(0.25) and its bypass breaker (0.25),are both open (0.25)
(Train A or Train B) b.
1.
-Trips the main turbine'(0.20)--
2.
- Actuates Feedwater Isolation (0.20) if Tavg is low
,(less than 564)(0.20) 3.
-Arms the cenUnser Steam Dumps.(0.20)-
4.
Places Plant Trip Controller in service (0.20) 5.
Permits an SI to be reset (after 60 second delay)
.(0.20)
FACILITY RESPONSE: 'To "b" part, additional answers should be accepted. Question asks for four (4), therefore we request the answer be: Any four (4)'of the following (.25 pts each).
1.
Trips the main turbine 2.
Actuates feedwater isolation if Tavg <564 3.
Ams condenser dumps 4.
Enables plant'. trip controller 5.
Disables load rejection controller 6.
Blocks atmospheric dumps 7.
Permits SI signal to be' reset 8.
Fails CF,recire isolation open 9.
CFPT runs back I
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' QUESTION'3.08 l
ANSWER-
.a.
(1) Density compensated (0.15) steam flow (0.15)
(2). Feedwater Header Pressure (0.15)
- (3) Steam Header Pressure (0.15) (2 and 3 may be reversed)
.;(4)~ Actual D/P (0.15)
'b.
UNIT 1 NO LOAD D/P-45 psi (0.25) FULL LOAD D/P 200 psi (0.25)
. UNIT 2 NO LOAD D/P-80 psi (0.25) FULL LOAD D/P 225 psi (0.25)
INCREASE (0.25) - Programed D/P greater than Actual D/P would cause MFW c.
Pumps to increase speed (0.25) to_ raise actual D/P to match Programed D/P (0.25).
FACILITY RESPONSE:
Part (b) of this question needs the answer changed as follows.
UNIT 1 NO LOAD D/P-45 psi (0.25) FULL LOAD D/P 215 psi.(0.25)
D/P-80 psi'(0.25) FULL LOAD D/P 225 psi (0.25)
UNIT 2 NO LOAD-We request that the answer for "c" be:
As on answer key if NO assumptions made.
If'" initially" is assumed to mean < 120 seconds then the answer should be NO response because of lag circuit.
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~ QUESTION 3.09'
. ANSWER
,TheP-7-interlockissatisfied(unblocksat-powertrips)when:
a.
(1) P-10 Interlock is satisfied - 2/4 Power Range Channels. greater than 10% power.
(0.5) or (2) -P-13 Interlock is satisfied - 1/2 Turbine Impulse pressure channels greater than 10% full load.
(0.5)
. b.
When.the P-7 interlock is satisfied the following reactor trips are unblocked:
(1) Pressurizer High Level (2) Pressurizer Low Pressure (3) Low NC flow (4) NCP Undervoltage (5) 'NCP Under-frequency FACILITY RESPONSE: The answer to part (b) has as one of the trips P
-7 enables l-Low NC flow. This should be "2 loop loss of flow" not just Low NC flow.
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4 QUESTION 3.10 (b)
ANSWER b.
The turbine runs back at 20% per minute (0.2) until power drops below 70%
(0.2) or 30 seconds have passed (0.2) since power dropped below 80% (0.2).
FACILITY RESPONSE: The answer needs to include that power initially > 80% is required for the runback to occur.
Runhack rate is not required knowledge of the operator.
We request answer to be :
If > 80% load and one CFPT trips then a runback will occur until < 80% for 30 seconds or < 70% load.
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QUESTION 3.13
- ANSWER a.
All rod motion'in auto (0.2) and manual (0.2) is stopped-(0.2).
The Operator can move other. individual banks (0.2) not powered from the IAC cabinet.
(0.2)
The Urgent Alarm lamp on the Power Cabinet is energized.
(0.25) A Control b
Room " Rod Control Urgent Failure (Power Cabinet)" annunciator is activated.
(0.25) c..
The lift coils (0.2) are deenergized (0.2) and both the stationary (0.2) and movable (0.2)' coils are energized at reduced (0.2) current (4.4 amps.)
FACILITY RESPONSE: We request that the answer be:
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. a.
All rod motion (auto and manual) (0.4) is stopped (0.2).
The operator can move other banks not powered from affected cabinet with bank select (0.2) b..
Same as answer key c.
The lift coils (0.2) are deenergized (0.2) and both the stationary (0.2) and movable (0.2) gripper' coils are energized with reduced (freeze) (0.2) current.
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QUESTION 4.13 (a).
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ANSWER L
?a.
-Reduce letdown flow (0.5) to 45 gpm (0.5).
Align thelCCPs to the FWST (open the NV-Pumps Suction ~ valves from th4e FWST
.1NV-252A and 253B) (0.5).
.Close the VCT Outlet Isolation valves'(1NV-188A and 189B) (0,5)
Start CCP 1B (0.5).
~ FACILITY RESPONSE: The NCS leak AP has other first immediate actions per attacheds We request the answer to-be:
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Anylfour (4) of'the following:
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1.
If Pzr press or level begins to drop uncontrollably go to EP01 to initiate S/I.
2.
Check Pzr level: Ati of increasing to programmed level 3.
If level decreasing, reduce to 45 gpm letdown flow.
4.
Check Pzr level stable or increasing.
5.
If Par level continues decreasing then start additional NV pumps 6.
If 2nd NV pump.to be started swap suction to FWST.
7.
Refer to Controlling Procedure for Unit OPS and begin shutdown l
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l Question 4.14 l
ANSWER a.
PLUS or MINUS 500 pcm.
(0.25) b.
Continue normal ops., Notify reactor engineer (0.25) i (Will also accept notify Shift Supervisor)
Borate (0.25) at greater than or equal to 30 gpm (0.25) while withdrawing c.
control rods to maintain criticality (0.25) until the controlr ods are above rod insertion limits (0.25)
FACILITY RESPONSE: The answer should also accept 105 gpm of 2000 ppm vs 30 gpm of 7000 ppm.
See attached.
..y QUESTION 4.16
- ANSWER
'(Since the valve is in the safety injection system it would'be-locked with a.
a tamper seal.) The two individuals would both verify that the valve has a l
-tamper seal (0.4) and that'the seal is intact (0.4).
bi 1.
Contact the Shift Supervisor immediately and do not reposition the valve without the Shift Supervisors permission.
(0.4) c.
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' Observe the mechanical open/ closed window on the breaker cubicle.
2.
Observe the indicating lights on the breaker cabinet.
3.
Observe the indicating lights on the breaker control switch.
4.
Observation of the operating conditions (such as the amp meter for a pump motor) or control room breaker indication.
(0.2 each answer)
FACILITY RESPONSE:
The answers should include the following:
a.
For an NI throttle valve, the required IV is different depending on whether the person is setting the valve to the required position first or just checking it.
We request the answer for (a) be:
As stated on answer key or 1.
The 2 persons work together 2.
The verifier observes the initial physical alignment or verification.
3.
The verifier checks for proper system parameters (e.g. flow or temperature)
We request the answer to (b) to include but not count off if.not there, the following.
(The valve position may be changed to correct an obvious problem H
such as a leak).
We request the answer to part (c) become:
Any four (4) of the following.
First 4 as on answer key.
5.
Look at the racking position in the breaker cubicle.
The question did not say that breaker position meant open/ closed, so it could be interpreted as racked position.
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B QUESTION 4.17 (a)
ANSWER The only limit in question is the 500 mrem limit for the first 5 weeks a.
which has not been exceeded. (0.5)
FACILITY RESIONSE: Per intrastation letter (File No:CN-750.00) attached, the new dose limits for personnel in operations is 500 mrem for the entire quarter.
We request the correct response for full credit not include "for the first 5 weeks".
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QUESTION 4.18 (b)
ANSWER b.
Radiation Control Area is an area within the restricted area where personnel monitoring is required (Reactor and Aux buildings except for CF l
and electrical equipment rooms) (0.4).
FACILITY RESPONSE: The answer should be as stated on answer key or as shown on attached from System HP Manual, f
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./. QUESTION 5.07 (c) i r
ANSWER.
TRUE or FALSE c). A reactor is critical at 10 E -08 amps in the Intermediate Range.
If the neutron source is removed, the neutron level would drop to a lower value and then remain constant.
FACILITYRESySE: Due to the relatively small neutron contribution from the
' source at 10 amps the reduction in power level will not be detectable on the control-board excore nuclear instrumentation meters.
It is agreed that the neutron level will decrease to a lower value, but what the operator will see will.not be significant enough to read on the meter. We request the answer.to be true or false.
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r,.-Q EsgTON 5.19 (b)
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ANSWER l
b)-
-During normal operations, what is the a Delta h) across the reactor core?
pprox. enthalpy rise / change (in-FACILITY RESPONSE:
By using these tables the studentsWe teach sa able to use these.
Ah as 81.9 BRU/lbm.
require students to be g
We request ihe acceptable answer could have developed the
' to 84.4 BTU /lbni,
)
i range be from 81 BTU /lbm
(
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V QUESTION 6.05 ANSWER l
a) The synchronizing disconnect switch must be closed.
b) The alternate AC source breaker must be closed.
FACILITY RESPONSE: This is not requried knowledge for License Candidates and is not specifically tied to an objective. We request the question be deleted.
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QUESTION 6.06 r
ANSWER a)
Failure of the alternate source.
b)
Alterante source goes off frequency by more than.7 Hz.
(0.25)
(= or
.3 Hz)
FACILITY RESPONSE: This is not required knowledge for License Candidates.
There is no specific objective tied to this question. We request the question be deleted.
- - - - -.g_w.. _a u --
- - - - - - ~ - -
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QUESTION 6.07' ANSWER CA62A CLOSE CA58A CLOSE CAS4B CLOSE CA46B OPEN CA50B CLOSE CA42B OPEN FACILITY RESPONSE: For this pump runout protection to perform it's function,' the turbine driven CA pump must also be in operation. With the question as stated, the turbine driven pump will not receive a start signal. We request the answer.should be as per attached drawing.
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QUESTION 6.09 (b)
ANSWER b.
Lower (0.5) i i
FACILITY RESPONSE: We request that an addition of the following be made to the
' KEY' response, but not to be required for full credit:
SUR (Startup Rate) Higher l
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QUESTION 6.10 (a)
ANSWER 3 cond. dumps only (0.5)
FACILITY RESPONSE: The question, as stated, may imply that the controller is enabled.- This would mean that all 5 dumps would be open. We request the acceptable answer be 3 or 5.
Condenser dumps will be the only dumps armed so only 3 dumps will M an open signal. A signal will be generated from the. load rej controller to all 5 banks. The question is not clear as to what point in the system we are looking at.
The proctor was asked by some students what "could" meant and he said that.it wasn't necessarily which dumps received an open signal. This was not conveyed to all the students. We respectively request 3 or 5 be considered as correct based on the students assumption.
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QUESTION 6.10 (c)
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ANS'JER
~6 deg. F (0.5)
The question requires the student to We do not FACILITY RESPONSE:have memorized the training graph handout.T require students to memorize graphs.We request this part of objective for this question.
question 6.10 be deleted.
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QUESTION 6.11 ANSWER By adjustment of the thumb wheels for each bank (0.5) in the BOU in the a.
logic cabinet. (0.5) b.
By the + or - push buttons (0.5) for the BOU in the logic cabinet. (0.5)
FACILITY RESPONSE: The question asksfor a response which is not required knowledge for license candidates. There is no specific objective tied to this question.
We request this question be deleted.
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QUESTION 6.13 ANSWER The Non-linear (gain unit) (0.25) - converts the power mismatch signal to an equivalent temperature error signal.
(0.25)
(The larger load changes the larger the effect.) The low and high gains are variable according to power mismatch.
Increasing the gain for a range of mismatches increases the initial I
output of the channel initiating rod motion more quickly.
(0.25).
The variable (gain unit) (0 25) - minimize overshoot on large power changes.
(0.25) Reactivity changes at lower power levels have a smaller effect on the rate of thermal power levels than reactivity changes at higher power levels.
This variable gain enables the mismatch channel to provide adequate control at lower power levels, as well as stable operation at high power levels.
(0.25)
FACILITY RESPONSE:
The question does not require gain unit names as part of the response.
We request the names not be required for full credit.
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QUESTION 6.16 (b)
ANSWER a) 1.
ASP transfer.
(0.3) 2.
Emergency low level in either pumphouse pit.
(0.3) b)
See attached drawing. Each valve position is worth (0.1)
FACILITY RESPONSE: Additional information given to ensure complete list of valves and valve positions.
QUESTION 6.18 ANSWER a) 1800 ppm (0.25) of sodium tetraborate (0.25) at 9.0 to 9.5 b)
Enhances iodine absorption.
(0.5)
(ph for corrosion control)
EACILITY RESPONSE: The answer key does not give a point value for the "ph" response. We request a point value of
.25 be given for the "ph" response and reduce the point value of 6.18 (b) to.25.
This will keep the total point value of the question at 1 point.
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QUESITON 6.20 (b)
I ANSWER b.
Tape stationary (for 30 min.) then advances in fast speed (17 in./ min.)
until clean tape positioned for sampling.
FACTLITY RESPONSE:
" Program" allows the operator to select a time from 0 to 30 min.
The answer key requires a response of "30 mins".
The referenced page 11 item 6.b.1)c) is only an example of how it operates.
If 30 mins. were selected by the operator.
We request the "30 mins." not be required for full credit. The answer should state the time is selectable. (0-30 min).
This was discussed and agreed on at the pre-exam review.
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q QUESTION 7.05 ANSWER a.
(1.0)
FACILITY RESPONSE:
Per the attached AP/1/A/5500/16 Case IV; There is no correct response given.
Response (a)jsnotcorrectbecauseareactortripis required due to channel 35 reading 7E, amps.
y Response (b) is not correct because it references EP/1/A/5000/01 which the operator does not enter until the reactor has been tripped.
We request this question be deleted.
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l QUESTION 7.09 ANSWER a) 1000 b) 5000 c) 20
.d) 100 FACILITY RESPONSE: This question asks for knowledge not required of License Candidates.
The objective referenced does not require this knowledge.
We request this question be deleted.
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i QUESTION 7.13 (b)
)
j ANSWER b.
IF the candidate has classified as an ALERT - only ONE (1) (the following) immediate action necessary:
" Initially notify individuals / organizations" (1.0)
IF the candidate has classified as Site Area Emergency
- Following THREE (3) immediate actions are necessary:
" Initially notify individuals / organizations" (0.33)
" Conduct Offsite Protective Actions" (0.33)
" Conduct Onsite Protective Actions" (0.33)
FACILITY RESPONSE: Memorization of RP immediate actions is NOT required knowledge per Operations Management Procedure 1-4 (Attached)
We request that question 7.13 (b) be deleted.
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l QUESTION 7.14 (a)
ANSWER a.
1.
Verify " Power On" light lit.
(0.25) 2 Position " Check Source / Operate / Trip Adjust" switch to the " Check Source" Position.
(0.25) 3.
Verify meter needle swings upscale. (0.25) 4.
Return switch to " Operate" position.
(0.25)
FACILITY RESPONSE:
" Source Check" will not work unless the " Power On" light is lit. This should not be part of the required response.
We request " Verify POWER ON Light it" not be required for full credit.
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QUESTION 7.14 (b)
ANSWER
(
i b.
1.
Verify alarm condition (0.25)
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Ensure auto fuctions (if applicable)
(0.25) 3.
Check activity levels at other corresponding points (0.25) 4.
Notify HP or radwaste chemistry personnel (as appropriate).
FACILITY RESPONSE: The question requires the student to have memorized annunciator response procedures. These procedures are readily available to the control room operators and are not required for memorization per OMp 1-4.
(See attachment to Question 7.13 Facility Response).
We request this question be deleted.
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QUESTION 7.15 ANSWIR 1.
Event Number 4.1.7 - Fires and Security Actions 2.
Notification of Unusual Event FACILITY RESPONSE: Per RP/0/A/5000/01 page 8 of 14, event #4.1.7, some students assumed an ongoing security event was in progress, which would be an " Alert".
We request that " ALERT" status also be accepted as a correct response.
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j QUESTION 8.01
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ANSWER' a) 1.0 pt)
Students were given Tech Spec 3.0.4 as revised by Amendments d ts FACILITY RESPONSE:However, the reactor trip system instrumentation table t 48 and 41.
were given was from a previous amendment, butThis created confusi ii was Based upon tb s, t
l applicable and whether Tech Spec 3.0.4 was applicable or no.The latest 3.0.4 c and 41.
answer A or B should be accepted.
examiners at the pre-exam review.
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l QUESTION 8.02 ANSWER
- d. (1.0 pt.)
FACILITY RESPONSE: The exam proctor, when asked by Ashok Bhatnagar, told Ashok to apply the facility interpretation to this Tech Spec and consider only one train of ECCS to be inoperable.
Due to this clarification given by the examiner, answer b should be considered correct as well as answer d.
This was discussed at the pre-exam review and the question was changed such that only one answer was correct. However, this man was given the interpretation and told l
that only train was operable.
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QUESTION 8.19
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ANSWER 5 (0.5 pt) i FACILITY RESPONSE:
Per OMP 1-4 (Use of Procedures) Attachment 2, Page 2 of 2, I, This is the responsibility of the Support Technician. Also, Station Directive 4.2.1 (Development, Approval and use of Station Procedures) states that there is no maximum number of changes permitted prior to rewrite. Based on this, we request this question be graded leniently and consideration be made for those that didn't remember all 3 circumstances.
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4 QUESTION 8.24 ANSWER Perform action b of T.S. 3.2.1 (1.0 pt.)
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(Restore indicated AFD to within target band limits within 15 min or )
2.
(Reduce thermal power to less than APL of rated thermal power and discontinue Base Load operation within 30 min.)
FACILITY RESPONSE: As calculated, largest AFD (out of target) is 2% out.
This requires the correct answer to be "No action required".
We request the answer key for required response be "No Action Required".
This was discussed at pre-exam review and agreed that a band would be provided when changed to a RAOC question.
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ENCLOSURE 4 SIMULATION FACILITY FIDELITY REPORT Facility Licensee:
Duke Power Company Facility Licensee Docket No.:
50-413, 50-414 Facility Licensee No.:
NPF-35 and NPF-52 Operating Tests administered at:
Catawba Nuclear Station Operating Tests Given On:
September 27-29, 1988 During the conduct of the simulator portion of the operating tests identified above, the following apparent performance and/or human factors discrepancies were observed :
Malfunction NVX18 Letdown heat exchanger leak to KC-No mass addition was noted in the KC surge tank.
Malfunction RNX-2 ' A' RN pump strainer blockage - No signs of blockage are.
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simulated until there is approximately 95% blockage.
Blockage must be increased to 98% before any significant blockage occurs.
Malfunction DGX-1 Diesel fail to start -'This malfunction does not allow the diesel to start manually with a failure of the auto start feature only.
Malfunction NVX-22 VCT level controller 5760 failure - This malfunction did
.not work in that failing 5760 high did not cause NV172 to divert to the HUT.
Malfunction NCX-52 Loop 'A' RTD failed low - With this malfunction active, an
" Emergency Low Tavg" alarm, among others, comes in. Taking the Tavg defeat switch to defeat for channel A should clear this alarm.
It does not.
Malfunction NCP-07 Reactor Coolant Pump bearing oil reservoir leak - (Run on
' A'. NCP) The malfunction description states that with this leak it will take i
15 minutes' to get the high vibration alarm. The high vibration alarm was received in 2 minutes, with an RCP trip occurring 1 minute later.
l Malfunction NCX-2B Override PORV 34A shut - This malfunction did not work, There is no way to simulate the failure of a Safety Injection pump to start i
I automatically on an SI signal and allow it to be started manually by the operators. This lack of flexibility affected the administration of exams in that the candidates could not be tested on their ability to recognize off
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normal' occurrences during a Safety Injection.