ML20127G388
| ML20127G388 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/11/1985 |
| From: | Douglas W, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20127G377 | List: |
| References | |
| 50-413-OL-85-02, 50-413-OL-85-2, NUDOCS 8505210051 | |
| Download: ML20127G388 (31) | |
Text
--
, i 1
s
. ENCLOSURE 1 EXAMINATION REPORT 413/0L-85-02
~ Facility Licensee: Duke Power Company 422 South Church Street' Charlotte, NC 28242 Facility Name: . Catawba- ,
Facility Docket No. 50-413 Written examinations were administered at the Region II Office in Atlanta, Georgia.-
Chief Examiner: d / 8 Approved by: .
fu 5 Brpe K Wilson, Section Chief Date Signed Summary:
Examinations on April 3, 1985 Written re-examinations of I Category were administered to 3 candidates; all candidates passed.
8505210051 850421 PDR ADOCK 05000413 G PDR
4 REPORT DETAILS
- 1. Facility Employees Contacted:
R. Ferguson,' Instructor
- 2. . Examiners:
' *W. G. Douglas
- Chiaf Examiner
- 3. Exaniination Review Meeting At- the conclusion of the written examinations, the examiner met with R. Ferguson to review the written examination and answer key. The following comments were made by the facility reviewer:
- a. 'SR0 Exam Question.8.03 Facility Comment:
The question states "... within 30 minutes or reduce the Power Range Neutron Flux High setpoint...". According tT Technical Specification 3/4.2.1, this statement is . incorrect as it.should be and instead of or. Both answers A or B should be accepted as correct.
NRC Resolution:
Comment accepted. Answer- key changed to accept A or B as correct answer.
- b. RO Exam
. Question 4.03 Facility Comment:
Same question as 8.03, see above comment.
! ~NRC Resolution: ,
l Cominent accepted. Answer key changed to accept A or B as correct answer.
i i
. -.. , - - -~ , . - , , , - ,,.. - -.
, . . - . . _ , ._m._ e .-n ., .,..-. -,n-,
n-
, 2
- 4. Exit Meeting Because this examination consisted of only three individuals, each retaking only one section of the written',- and was administered in the Region II Office, no exit meeting was held.
4
r
/
4 j , fa as% UNITE 3 STATES l
~+ 0,,
NUCLEAR RE'lULATORY COMMISSION
[ g REGION is n [ 101 M ARIETTA STREET, N.W.
g j o ATLANTA, GEORGIA 30303
- ;. .- ' ( ,. c 4 ENCLOSURE 3
..,7 4,? ^ 4
~ ' l
~0 U[S.NUCLEARREGULATORYCOMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: Catawba 1 Reactor Type: PWR WEC4 Date Administered: April 3,1985 Examiner: W. G. Douglas Candidate: MASTER INSTRUCTIONS TO CANDIDATE:
Use separate paper for answers. Write answers on one side only. Staple question sheet on top of the answers sheets. Points for each question are indicated in parenthesis after the question. The passing grade requires at least 70%. Exami-nation papers will be picked up 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the examination starts.
% of Category '.'
Category % of Candidate's
Score Value Category --
Value Total , ;? :
- 4. Procedures - Nonnal,' ' '
30 100 Abnormal Emergency, and Radiological Control TOTALS 30 100 Final Grade %
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature a .
,.e t 1
- 4. ' PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 2
~
~~~~R d6f6L66fddL 66 TR6L"'~~~~~~~~~~~~~~~~~~~~~~
QUESTION 4.01 (1.00)
Which of the following is NOT a symptom of a Unit 1 load rejection? (1.0) a.- Steam dump armed and actuated.
- b. Gen Bkr 1B open.
- c. PCB 14 or 15 open.
- d. EHC turbine runback in progress.
QUESTION 4.02 (1.00)
On a unit.startup, when reactor power reaches 10%, several indica-tions must be verified. Without any operator action, whien of the following is NOT observed at 10%. (1.0)
- a. 'P-7 Lo Pwr Rx Trip Blocked' light off
.b. 'I/R Train A Trip Blocked' light illuminated
- c. 'P-10 Nuclear At Power' permissive light illuminated
- d. 'P-13 Turbine Not At Power' permissive light off GUESTION 4.03 (1.00)
Which of the following statements regarding Axial Flux Difference (AFD) is NOT correct? (1.0) a.- Reactor power can not be increased above 50% rated thermal power unless the indicated AFD is within the target band.
- b. If the indicated AFD is outside the target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cumulative over.a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, with reactor power between 50 and 90% of rated thermal power, either reduce thermal power to less than 50% within 30 minutes nuo -> or reduce the Power Range Neutron Flux High setpoint to
.less than or equal to 55% power within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- c. If indicated AFD is outside the target band and thermal power is greater than 90% of rated thermal power, within 15 minutes, either restore AFD within target band or re-duce thermal power to less than 90%.
- d. Indicated AFD may deviate outside the target band between 50 and 90% of rated thermal power as-long as the cumula-tive penalty deviation time does not exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the indicated AFD is within the acceptable operation limits.
I l
e e: 't .
- 4. PROCEDURES - NORMAL,' ABNORMAL, EMERGENCY AND PAGE 3
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R I6I5L5555IE~55 T55L
' QUESTION' 4.04 (1.00)
Which of the following is NOT an input into determining conformaace with"the reactor core Safety Limits? (1.0)
-a.- Pressuri=er Pressure
-b. Lowest Operating. Loop Flow
.c. Thermal Power
- d. Highest Operating Loop Tavs GUESTION 4.05 (1.00)
~While operating Unit 1 at 40% power with all 4 loops operatin3, you receive ' Seal Injection Filter A Hi D/P'.and 'NC Pump Seal Water Lo Flow' alarms. .You check 41 seal outlet temperatures, KC flow from NC pumps, and NC pump lower bearing temperatures and you obtain the following data.
NC PUMP 41 SEAL OUT TEMP ~ KC FLOW FROM PUMP LOWER BRG TEMP A 225' 39 spa 215 B 220 40 spa 227 C' 230 41 spm 220 D. 215- 38 spm 210 All temperatures are rising slowly (<1. degree / min). -Which of the following actions should you take? (1.0)
- a. Trip NC pump C and refer to AP/1/A/5500/04, " Loss of Reactor Coolant Pump'.
- b. Trip the reactor, trip NC pumps B and C, then refer .
to EP/1/A/5000/01, " Reactor Trip".
- e. Trip the reactor, trip NC pump B rand then refer to EP/1/A/5000/01, ' Reactor Trip".
- d. Trip NC pump B and refer to AP/1/A/5500/04, ' Loss of Reactor Coolant' Pump'.'
~ .
4 ~.~ PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE- 4
- -----------~~-----------
~~~~RI655L555 CAL 55HTR5L QUESTION 4.06 (1.00)
While operating Unit 1 at-85% power,-an inadvertent boron dilution occurs =which resultsEin a " Control Rod Bank Lo-Lo Limit' alarm.
'Which of:the-following.is an appropriate immediate action in
- cecordance with AP/1/A/5500/13, " Boron Dilution'?- .(1.0)
- a. Emergency borate to clear the ' Control Rod Bank .L.o Limit' alarm.
.b. Emergency berate to clear the ' Control Rod Bank Lo-Lo Limit' alarm.
- c. Stop,the source of the dilution and obtain a chemistry sample to determine required boration.
- d. Stop the dilution process and emergency borate to raise
~
rods to the position they occupied prior.to the inadver-tent dilution.
QUESTION 4.07 (1.00)
Prior to commencing a Natural Circulation Cooldown per EP/1/A/5000/
1 Air it is necessary to borate the NC system to 100 ppa greater than the concentration required to provide a Xenon free Shutdown Margin (SDM) of 1300 pcm at the minimum expected cold shutdown temperature. Which of the following is the correct reason _the shutdown boric _ acid concentration should be _100 ppm greater than necessary to achieve the 1300 pcm SDM? (1.0)'
~
-a.. Due to improper NC system mixing with natural circulation flou.
b.- Due to.possible errors in NC system temperature indica-tions with natural circulation flow.
c.- Due to changes in boron worth with natural circulation flow.
I
- d. Due to restricted reactor vessel head cooling with natural' circulation flow.
QUESTION 4.08 (1.00)
During normal plant 1 operations, which of-the following is the )
caximum S/G primary to secondary differential pressure? (1.0):
-a. ' 1000 psid j
- b. 1200 psid
- c. 1400'psid
- d. . 1600 psid
O- .-
4.: . PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND. PAGE. 5
~~~~Rd656[65 UAE C5NTREE~~~~~~~~~~~~~~~~~~~~~~~~
' QUESTION 4 09 ~ ( 1. 00 ) -
On a unit shutdownr.which of the following is performed between the time power drops below 10% and control banks insertion is-began? (1.0)
- a. ' Select an IR and SR channel on-the NI recorder.
- b. Transfer steam dumps to Steam Pressure mode.
c.. Conduct'a reactivity balance.
- d. . Establish boron concentration to achieve proper shutdown margin.
QUESTION 4.10 (1.00)
On a power increase from 15% to 75% power, the following actions are performed.
- 1. Start a second CF pump
- 2. Verify SSRH highload' valves automatically open
- 3. Check OAC thermal. output measurement and have IRE adjust nuclear instrumentation as required.
- 4. Verify 'P9 - Reactor Trip On Turbine Trip Permissive' light comes on.
Which of the below-is the correct performance order of these actions? (1.0) a.- 3, 2 , - 1, 4 b.- 1, 3, 2, 4
- c. 1, 4, 2, 3
- d. 2, 4r .1, 3 QUESTION ~14.11 (1.00)
An individual has. received a whole body dose of 500-arem so far this
' quarter.- Which of the following would be the maximum additional exposure to;the skin that one could receive without exceeding the-10CFR20. quarterly limits? (1.0).
a.- 750 arem
- b. 1250:arem
- c. 7000 arem
- d. 7500.arem i
l I
i l
. , _~
e 4.3 PROCEDURES' . NORMAL, ABNORMAL, EMERGENCY AND PAGE 6
'~~~~
R56 6E66 65E~ 6ATR6E~~~~~~~~~~~~~~~~~~~~~~~~
- QUESTION 4.12 (1.00)
On.a steam generator overpressure casualty, which of the following
.io_the' correct _ priority (in order of highest'to lowest) of methods to depressuri=e the affected S/G? (1.0)
If_'a void exists.in the reactor vessel, which approach below cropresents the preferred actions taken to collapse the void in
- EP/1/A/5000/2F3, " Void in Reactor Vessel'? (1.0)
- a. Decrease temperature while maintaining _ system pressure.
- b. _ Start a SI pump to increase system pressure while keeping
. temperature constant.
- c. . Increase system pressure using pressurizer heaters while-maintaining. pressurizer level, d .' Fill pressuri=er solid and vent the reactor vessel head.
l QUESTION 4.14 (1.00)
.Following a v' a lid reactor trip and safety injections.which of the statements _below correctly describe the NC Pump Trip Criteria? (1.0)
-a. SI flow indicated and NC pressure < 1500 psis.-
b.- SI flow indicated and p:r level < 10%.
- c. SI flow-indicated and NC subcooling < 0 degrees.
- d. SI flow indicated and NC temperature < 500 degrees.
QUESTION =4.15 (1.00)
.Which of the following is the " working limit' for Beta-Gamma surface contaminationLin a' restricted area? (1.0)
- a. less'than 100 dpm per 100 square centimeters
- b. 'less than 1000 dpa per 100 square centimeters
- c. less - than 2500 dpa per 100 square centimeters
- d. less than 5000 dpm per 100 square centimeters J
r S.
. i t
- 4. . PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 7
~ ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R d656L6GfddL 66 TR6L GUESTION 4.16 (1.00)
In order.to deviate from an operating procedure's sequential order whose permission is required? (1.0)
- a. You cannot deviate _from a procedure without an authorized temporary / permanent procedural change.
- b. Verbal orders of the Ehift Supervisor and Shift Operating ensi neer.
- c. Verbal approval of two operatorst one of which is a super-visor holding a SRO license.
- d. Verbal approval of a SRO licensed supervisor only.
dUESTION 4.17 (1.50)
Indicate whether the statements below concerning a steam generator tube rupture are.TRUE or FALSE.
- o. If all S/Gs are ruptured, then the S/G with the highest narrow range level (smallest apparent leakage) should be used for the subsequent NC cooldown. (0.5)
- b. The preferred method of depressuring the S/G with the ruptured tube is by opening the MSIV bypass valves, assuming the con-denser is available. .
(0 5)
- e. When using EP/1/A/5000/1E2, 'SGTR Alternate Cooldown Using Back-fill', at least 1 NC pump should be running to mix possibly unborated backfill with the NC system. (0.5)
DUESTION 4.18 (1.50)
Indicate whether the following statements regarding Rod Control calfunction2 are TRUE or FALSE.
- c. A-logic ' cabinet failure is identified by an absense of all local power supply cabinet ' Urgent Failure' clarms. (0.5)
- b. If unwarrented continuous rod motion is stopped by placing the CRD Bank Select in manual and rods can be operated satisfactorily, reactor operation in manual can be continued indefinitely. (0.5)
- c. Group height, shutdown bank red insertion, and control bank insertion limits of the 3mdgt Technical Specifications are NOT applicable when in manual rod control following a malfunction. (0.5)
. n 4
s 4.- PROCEDUREq - NORMAL, ABNORMAL, EMERGENCY AND PAGE 8
~
~~~~kI65dL665EIL 56NTRUL'~~~~~~~~~~~~~~~~~~~~~~~
QUESTION 4.19 (2.00)
Fer the following paragraph, choose the correct words from the options
.given after the paragraph that correctly complete each blank.
When paralleling a diesel generator to the grid, the generator voltage should be ___a___ the line voltage. The diesel generator is synchronized to the grid by observing the synchro pointer as it moves slowly in the ___b __ direction and closing the generator breaker when the pointer is ___c __
the vertical position. The power (NW) output of the generator is then reised by adjusting the ___d___.
Choose from the following:
- a. lower than / equal to / higher than (0.5)
- b. slow / fast (0.5)
- c. 5 minutes to / at / 5 minutes after (0.5)
- d. governor control / voltage regulator / stator cooling (0.5)
QUESTION 4.20 (2.00)
M9tch the ECP and actual critical condition relationship in Column A to the required actions in Column B. (2.0)
COLUMN A COLUMN B
- o. Criticality achieved below the 1. Notify the reactor group Tech Spec control rod insertion Unit Engineer or Perfor-limit. mance Duty Engineer with-in 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> and continue
- b. Criticality not reached by upper normal operations.
limit of the ECP band and ECP 2. Fully insert control rods calculation verified by Duty and recheck the ECP Engineer as correct. calculations.
- 3. Insert control rods to
- c. Criticality achieved above the lower insertion limit and minimum insertion limit but recheck ECP calculations.
below the ECP band. 4. Initiate boration at 30 spa of > 7000 ppm while
- d. Appears criticality will be withdrawing rods to stay achieved below the control rod above rod insertion limit.
insertion limit. 5. No action required.
- 6. Criticality may be achieved using 1/M Approach to Criticality procedure.
O e
e
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 9
~~~~ - ~~~~~~~~~~~~~~~~~~~~~~~~
RI65UL55iEAL 55NTRUL QUESTION 4.21 (1.50)
Ccaplete the following statement by filling in the blanks with the c0rrect number. (1.5)
During a pressurized thermal shock condition, if NC temperature d: crease has exceeded ___a___ degrees in any ___b___ minute period, then a ___c___ hour temperature soak must be performed.
QUESTION 4.22 (2.00)
CNS AP/1/A/5500/02, ' Turbine Generator Trip *, has an immediate ,
cction step to verify the generator tripped. If the trip occurred
- cn Unit it what would be checked to verify the generator had i tripped? (2 0)
QUESTION 4.23 (2 00)
While refueling Unit 1, you receive a 'ND pump A Discharge High pressure' alarm and note that NC temperature is increasing, while ND flow is decreasing. List all the immediate actions in Ap/1/
A/5500/19, ' Loss of ND Train *, including any psrameters that are vorified in these actions, and what should be done with any fuel in transit. (2.0)
GtlESTION 4.24 (1.50)
- a. On a loss of all AC power, both diesel generators (D/G) should automatically start. If a D/G does not energize, list all actions that are required to be performed. (0.9)
- b. How will NC pump seal cooling be re-established followins a loss of all AC power? (0.3)
- c. Once a D/G is started following a loss of AC power, in how many minutes must RN flow to the KD Hx be established? (0.3)
- 9 I
e
-.----_--1. ._A.__-___ _9*
F-
~
l
'e
- 4. PROCEDURES'- NORMAL,' ABNORMAL, EMERGENCY AND PAGE 10
- ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~E 6E6L5siEAL E5NYR6L ~
ANSWERS -- CATAWBA 1 -85/04/03-DOUGLAS, W.G.
ANSWER 4.01 (1.00) c REFERENCE Cat, AP/1/A/5500/03 ANSWER 4.02 (1 00) b REFERENCE Cat, OP/1/A/6100/01, p. 12 ANSWER 4.03 (1 00) o er G See. Exam Repoh W69 REFERENCE Cot, TS, 3/4.2.1 ANSWER 4.04 (1.00) b REFERENCE Cat, TS, 2.1 ANSWER 4.05 (1.00) d REFERENCE Cat, AP/1/A/5500/08, p.2 ANSWER 4.06 (1.00) b
.___.___1______.__
o,
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11
~~~~R 56 6L66f65L 66 TR6E~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- CATAWBA ~1 -85/04/03-DOUGLASr W.G.
REFERENCE-Cotr'AP/1/A/5500/13r p. 2 ANSWER 4.07 (1.00) e
' REFERENCE Cotr EP/1/A/5000/1 Air p. 2 ANSWER 4.08 (1.00) d REFERENCE Cat, OP/1/A/6100/02, p. 1 ANSWER 4.09 (1.00) b REFERENCE Cate OP/1/A/6100/02, pp. 3-5 ANSWER 4.10 (1.00) b REFERENCE Cate OP/1/A/6100/03, p. 5 ANSWER 4.11 (1 00)
C REFERENCE 10CFR20.101 l
l i
%.______________._____._______ fr
-4
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 12
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R I65UL66f6dE~56 TR6L ANSWERS --' CATAWBA 1 -85/04/03-00UGLAS, W.G.
. ANSWER- 4.12 (1.00) b-REFERENCE CAT, EP/1/A/5000/2C2, pp. 3 - 4 ANSWER 4.13 (1.00) e REFERENCE Cotr EP/1/A/5000/2F3r pp. 4 and 5 ANSWER 4.14 (1.00) c REFERENCE Cotr EP/1/A/5000/01, Enclosure 1 ANSWER 4.15 (1.00) d REFERENCE Cot, Duke Power HP Manuale P. 77 ANSWER 4.16 (1.00) c REFERENCE Cote OMP 1-4, p. 7 l
N W._
r j4 . PROCEDURES . NORMAL,-ABNORMAL, EMERGENCY AND PAGE 13
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~RA5iBE55i5AC 55ETR6L ANSWERS -- CATAWBA 1 --85/04/03-DOUGLAS, W.G.
ANSWER 4.17- (1.50)
- o. FALSE (0.5) b.- -TRUE (0 5) c.
~
'TRUE (0.5)
~ REFERENCE' Cots.EP/1/A/5000/1E, p. 2 and EP/1/A/5000/1E1, p. 4 and EP/1/A/5000/
1E2, p. 1 ANSWER 4.18 (1.50)
.a. TRUE (0.5)
- b. TRUE (0.5)
- c. FALSE. (0.5)
REFERENCE ~
Cat, AP/1/A/5500/15, pp. 3,'5, and 7 .
l ANSWER 4.19 (2 00)
- o. Higher- -(0.5)-
- b. . Fast (0.5)
- c. 5 minutes to (0.5)
- d. Governor control (0.5)
REFERENCE Cat, OP/0/B/6350/11, enclosure 4.4, pp. 1 -2
- ANSWER 4.20 (2.00)
- c. 4 (0.5)-
- b. 6 -(0.5)
- c. 1~ (0.5)
- d. 2 (0.5)
REFERENCE
- Cat, OP/0/A/6100/06, pp. 1-2 1
l
- 7. .
.= 'e )
s
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 14
--- EA5i5C55iEAC 55RfE5C------------------------
ANSWERS -- CATAWBA 1 -85/04/03-DOUGLAS, W.G.
< ANSWER 4.21 (1.50)
- c. 100' -(0.5)
- b. 60 (0.5)
- c. 3: (0.5)
REFERENCE' Cate -EP/1/A/5000/2Dir pp. 16 ANSWER 4.22 (2.00)
- 1. Gen Output Bkrs (1A and 18).open (0.4)
'2. MODS (1AG, 1AT, 1BG, 1BT) open (0.4)
- 3. Exc Field Bkr open (0.4)
- 4. Gen-DE-Exc Bkr (relay) open (0.4)
- 5. Man / Auto Reg Switch " Man
- light lit (0.4)
. REFERENCE Cat, AP/1/A/5500/02, p. 3 ANSWER 4.23 (2.00)
- 1. Verify adequate ND suction supply .(0.3)
- a. P:r level > 10% or (0.1)
- 6. NC vessel level > 10% (0.1)
- 2. Attempt to restore affected ND train (0.5)
- 3. Secure fuel handling operations (0.3) if in transit, direct operators to place in safe position (0.2)
- 4. Maintain baron concentration stable (0.5)
REFERENCE Cate AP/1/A/5500/19, p. 2 4
l
- c. . .. .e.
I I. 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15 l --- EA5i5E55isAE 55sfE5E------------------------
t ANSWERS ---CATAWBA 1 -85/04/03-DOUGLAS, W.G.
I l ANSWER 4.24 (1.50)
I Reset train related-D/G load sequencer (0.3)
- c. 1.
- 2. Manually start affected D/G .
(0.3)
- 3. Dispatch operator to investigate failure of D/G to start (0.3)
- b. Obtain key (0.1) and dispatch two (0.1) operators to establish pump seal injection (0.1) (0.3)
- c. Two minutes (0.3) t i
REFERENCE Cat, EP/1/A/5000/03, pp. 2 and 3
(
i I
l i
9
Ii UNITED STATES p Ho
- J og'o,,,
NUCLEAR REIULATORY COMMISSION 1 g REGION 11
~f
> E 101 M ARIETTA STREET, N.W. l ATLANTA, GEORGIA 30303 l o,
' . . . . * *k[ y^r ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMMISSION I"l w
.e
- ' I
- SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: Catawba Reactor Type: PWR-WEC4 Date Administered: April 3, 1985 Examiners: W. G. Douglas Applicant: M MTER INSTRUCTIONS TO APPLICANT:
Use separate paper for the answers. Write answers on one side only. Staple question sheets on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70%. Examination papers will be picked up 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the examination starts. ..
- ) 44., .. TF Category -
Value Total Score Value Category y%
30 9 100 8. Administrative Procedures, Conditions and Limitations lo 43 0 100 TOTALS Final Grade %
All work done on this exam is my own, I have neither given or received aid.
Applicant Signature ,
G
\'
s s
_ _ _ . _ _ . _ _ . _ . . . 8 S
p- .
'o ;
e . . -
- L
-s
- 8.- ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS- PAGE 2
= QUESTION 8. 01 (1.00) '
Which statement below regarding shift turnover is NOT correct? (1.0)
- a. During the' turnover prdc.ess, the off going operator shall i explain each entry on the Turnover Sheet, with the excep-tion of sections marked N/A.
- b. Tasks in progress at the time of shift turnover dictate )
that thes turnover will take place at whatever location the task is being performed.
- c. The Shift Operating Engineer is responsible for maintaining and Senerating all turnover sheets.
- d. The off going Unit Supervisor should sign the ' Transfer of. Shift Responsibilities' after the oncoming Unit Supervisor has signed it.
! l QUESTION 8.02 (1.00) l l
Which of the following statements concerning access to containment-12 NOT correct? (1.0)
- a. If the Reactor Building is to be entered while the NC system is > 350 de3rees, the ' Buddy System' must be used.
- b. Following a. reactor shutdown, control of containment
-access may be transferred to a responsible person posted at the personnel hatch.
- c. When personnel are inside the annulus, the annulus door shall remain closed and locked except during passage in and out of the annulus.
- d. During the time the reactor is critical, permission must be received from the Unit Supervisor before entering the Reactor Building.
.1
^ '
I e- ..
e
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 3 GUESTION 8. 03. (1.00)
-Which of.the following statements regarding Axial Flux Difference (AFD) is NOT correct? (1.0)
- a. Reactor power can not be increased above 50% rated thermal power unless the indicated AFD is within the target band.
bi If the indicated AFD is outside the target band.for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cumu'lative over a 24-hour period, with reactor power between 50 and 90% of rated thermal power, either j reduce thermal power to less than 50% within 30 minutes or reduce the Power Range Neutron Flux High setpoint to q 1ess than or equal to 55% power within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. )
- c. If indicated AFD is outside the target band and thermal power-is greater than 90% of rated thermal power, within 15 minutes, either restore AFD within target band-or re-duce thermal power to less than 90%.
. d. Indicated AFD may deviate outside the target band between 50 and 90% of rated thermal power as long as the cumula-tive penalty deviation time does not exceed i hour during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the indicated AFD is within the acceptable operation limits.
QUESTION 8.04 (1.00)
Prior to unbolting the reactor vessel head, the minimum boron con-contration must meet which of the following requirements? (1.0) i a.- 2000 ppm OR enough to ensure keff is less than 0.95, whichever is LESS.
b.- 2000 ppm WITHOUT regard to keff.
- c. Enough to ensure keff is less than 0.95 WITHOUT regard to concentration.
e ..e e
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 4 GUESTION 8. 05 (1.00)
Which of the following statements concerning' Shutdown Margin (SDM) censiderations is correct? (1.0)
- a. With Tavs less than 200 degrees, the SDM requirements are increased because of the possibility of a positive MTC.
- b. The most restrictive condition-for SDN requirements occur at EOL, with Tavs at no load temperature, and is associated with a rod ejection' accident.
- c. When in Mode 2 with keff less than 1.0, adequate SDM is ensured by verifying the predicted critical rod position is above the rod insertion limits.
- d. HIf one. rod is known to be partially inserted and untrip-pable, an increased allowance for the entire rod worth shall be made to the SDM requirements.
QUESTION 8.06 (1.00)
If a safety limit is exceeded, the Nuclear Regulatory Commision Operations Center shall be notified _____. (1.0)
.a. Within i hour.
- b. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- c. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. . Within 30, days.
QUESTION- 8.07 (1.00)
In what Modes.are the containment hydrogen mitigation systems roquired to be operable by Technical Specifications? (1.0)
- a. Mode 1 only
- b. Modes 1 and 2 only
- c. Modes 1, 2, and 3 only
- d. Modes 1, 2, 3, and 4 only QUESTION 8.08 (1.00)
Technical Specific'ation 3/4.2.5, DNB Parameters, gives limits for two DNB related parameters. Which of the following choices con-tains those two parameters? (1 0)
- a. Tavs and NC System Flow
- b. Pressurizer Pressure and NC System Flow
- c. NC System Flow and Nuclear Power j d. Tavs and Pressurizer Pressure t
'81 >6 0
,s.
'8. ~ ADMINISTRATIVE ~ PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 5 QUESTION .8 09 - (1.00) .
The process of determining an instruments accuracy by visually- 'A-ccaparing the. indication to other: independent instrument channels cassuring.the same parameter is defined in Technical Specifications _ ,
4 co a t - '(1.0)
- s. Channel Calibration b.- Channel Check e .- Channel Functional Test d.- Channel Verification QUESTION 8.10 (1.00)
In order-to deviate from an operating procedure's sequential order whose permission is-required? (1.0) a.. :You cannot' deviate from a procedure.without an authorized
-temporary / permanent procedural change.
-b. Verbal orders of.the Shift Supervisor and Shift Operating Engineer.
- c. " Verbal approval of-two operators, one who is a supervisor holding a SROLlicense.
- d. Verbal approval.of a SRO licensed supervisor only.
QUESTION 8.11 (1.00)
Which statement below pertaining to logkeeping is correct? (1.0)
- a. Prior to the end of shift, the Shift Supervisor shall
. review and initial both.the Control Room and Unit Super-visor Logbooks.
- b. The Shift Operating Engineer, .or his designee, shall review the Unit Supervisor Logbook each shift.
- c. A blank line should be used following each los entry.
- d. If' stamps are used, they must be issued by the Shift Operatin3 Engineer.
QUESTION 8.12 (1.00)
Which of the following-conditions require a Shutdown Margin calcu-lation (verification) to be performed within one hour? (1 0) a.- A baron concentration change of greater than 20 ppa.
- b. Going out of the' Axial-Flux Difference target band.
- c. Detection of an inoperable rod.
- d. Reactor startup commencing greater than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after shutdown.
r.
c.-
o' sa
'8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 6 QUESTION 8. 13 (1.00)
During a fire emergency, two people are assigned as Technical Ansistants to the. Fire Brigade. Which of the following correctly identify these two people? (1.0)
- a. Assistant Shift Supervisor and a Nuclear Equipment Operator.
- b. A Security Officer and a Nuclear Equipment Operator.
- c. Two Nuclear Equipment Operators.
- d. Two Security Officers.
QUESTION 8.14 (1.00)
Which statement below is correct regarding control of High Radiation koys? (1.0)
- a. High Radiation keys will be controlled and issued by the on-shift Health Physics Supervisor.
- b. High Radiation keys will be issued at the beginning of each shift to operators requiring access to high radiation areas.
- c. Two sets of master keys exist, with one set in the key locker in the Shift Supervisor's office and the other set in a sealed box in the Health Physics office.
- d. High Radiation keys can be transferred from person to person during the issue period as long as the Shift Super-visor is notified.
QUESTION *8.15 (2.00)
Indicate WHETHER or NOT the following conditions REQUIRE that the plant be in Hot Standby within one hour.
- a. In Mode 1 with one cold les injection valve failed in the closed position. (0.5)
- b. In Mode 1 with UHI accumulator at 1850 ppm boron. (0.5)
- c. In Mode 1 with RCS pressure having exceeded 2000 psig. (0.5)
- d. In Mode 1 without primary containment integrity. (0.5)
z
.f 4'e
- 8. ADMINISTRATIV
E. PROCEDURE
S, CONDITIONS, AND LIMITATIONS PAGE 7 QUESTION 8. 16 (2.00)
Indicate WHETHER or NOT the Technical Specifications require action to be taken within one hour for the following conditions.
- c. In Mode 1 with one full-length rod immovable but within 12 steps of the group counter demand position. (0.5)
- b. In Mode 5 with one pressuriner code safety valve inopeable. (0.5) c.- In Mode 2 with one pressurizer PORV block valve inoperable. (0.5)
- d. In Mode 1 with only one operable charging pump. (0.5)
QUESTION 8.17 (2.00)
Answer TRUE or FALSE to the following.
-o. Entry into an Operational Mode may be performed even if the conditions for the Limiting Condition for Operation (LCO) are NOT met provided the ACTION requirements are subsequently satisfactorily completed. (0.5)
- b. If a LCO is NOT met and the ACTION statements are NOT appli-caple, then the Senior Reactor Operator has the authority to disregard that particular LCO. (0.5)
- c. If RHR pump A is inoperable and the B emergency diesel is then declared inoperable, RHR pump B is still considered operable. (0.5)
- d. Failure to complete a Surveillance Requirement on operable equipment within the specified time interval (plus any allow-able extension) shall constitute a failure of the component to meet its operability requirements. (0.5)
GUESTION 8.18 (1.50)
Indicate whether the statements below regarding Safety Tass / Stickers
' ore TRUE or FALSE.
- n. If independent work on a component ta33ed out to another work supervisor is to be done, placement of separate safety tags is required. (0.5)
- b. If the supervisor having operational responsibility cannot be located to retrieve a red tag stube verbal approval of the appropriate Work Group Superintendent is sufficient to recall and remove the red tag. (0.5)
- c. When a white tag is authorized for removal by the supervisor having operational responsibility, the tags are removed and brought to the supervisor who compares the tags to the stubs in his possession to ensure they agree. (0.5)
F o 3 .
s -
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 8' QUESTION 8,.19 (1.50)
Indicate whether the statements below regarding valve position verification are TRUE or FALSE.
- c. To verify a manual valve in the closed position, it should be cracked off its seat and then reclosed. (0.5)
- b. To verify a valve in the locked closed position, the lock should be removed and the valve moved in the closed direction. (0.5)
- c. To verify a valve in the throttled position, assuming operation will not cause adverse effects, the valve should be moved through its stroke. (0.5)
QUESTION 8.20 (2.00)
Indicate whether the following exposure lie'.ts are FEDERAL REGULA-TIONS, CATAWBA ADMINISTRATIVE LIMITS, or CAYAWBA EXTENSION LIMITS.
- a. 6 rem /qtr Skin Exposure (0.5)
- b. 2.5 rem /qtr Whole Body (0.5)
- c. 18.75 rem /qtr Extremeties (0.5)
- d. 300 mrem /qtr Neutron Exposure (0.5)
GUESTION 8.21 (1.50)
Match the RCS leakage types in Column A to the Technical Specifica-tion limits in Column B. (Assume plant is at normal press / temp) (1.5)
Column A Column B
- 2. From RCS into cold les accumulator b. 1 spa
- 3. From unknown location c. 10 spa
- 4. To NC pump seal supply d. 30 gpm
- 5. Nonisoble fault on RTD bypass line e. 40 spm
- f. 50 spm
7
~* sa s
8.- ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 9
~ QUESTION 8. 22 (1.50)
Match the following reactor trips with the design accident it is
, dasigned to protect against. (1.5)
REACTOR TRIP ACCIDENT
.o. Overpower Delta T 1. Power excursions during low power operation.
- b. Intermediate Range High Flux 2. Control rod drop
- 3. DNB
- c. Undervoltage RCP Bus 4. Control rod drive housing rupture
.d. Overtemperature Delta T 5. No fuel pellet melting and > 1% cladding strain.
- o. Power Range Positive Rate 6. Loss of heat sink
- 7. Uncontrolled rod cluster assembly withdrawal from suberitical conditions.
QUESTION 8.23 (2.00)
List the FIVE bases for the minimum temperature for criticality limit of the Technical Specifications. (1 0) l l
l
O so s -
- 8. ADMINISTRATIVE PROCEDURESr CONDITIONS, AND LIMITATIONS PAGE 10 ANSWERS -- CATAWBA 1 -85/04/03-DOUGLAS, W.G.
ANSWER 8.01 (1.00)
O REFERENCE Cotr OMP 2-22, pp 2 - 4 ANSWER 8.02 (1.00) c
-REFERENCE Cat, Station Directive 3.1.2, pp. 1 &2 ANSWER 8.03 (1.00) o er b See E n h port W 69 REFERENCE Cate TS, 3/4.2.1 ANSWER 8.04 (1 00) d REFERENCE McG, TS, P. 3/4 9-1 Cat, TS, p. 3/4 9-1 ANSWER 8.05 (1.00) -
c REFERENCE McG, TS, pp . 3/4 1-1 and B 3/4 1-1 Cate TS, pp. 3/4 1-1 and B 3/4 1-1 ANSWER 8.06 (1.00) a
_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ ~
o 3 o s .
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 11 CNSWERS -- CATAWBA 1 -85/04/03-00UGLAS, W.G.
REFERENCE McG, Station Directive 3.13, p. 1 and 10CFR50.72(b)
Cot, Station Directive 2.8.1, p. 6 of enc 1 (2) and 10CFR50.72(b)
ANSWER 8.07 (1.00) b REFERENCE McG, TS, pp. 3/4 6 33 Cot, TS, pp. 3/4 6-31 & 32 CNSWER 8.08 (1.00) d REFERENCE McG, TS, p. 3/4 2-22 Cct, TS, p. 3/4 2-15 ANSWER 8.09 (1.00) b REFERENCE McG, TS, p. 1-1 Surry, TS 1 0-3 Cat, TS, p. 1-1 ANSWER 8.10 (1.00) e REFERENCE Cot, OMP 1-4, p. 7 ANSWER 8 11 (1.00) d REFERENCE Cot, OMP 2-A, pp. 3 - 7
> - - - - - _ _ - - - _ - - - - - , _ , . - _ _ _ - _ . - - _ _ . - - _ . - - - - - - - . _ - - - - - - - _ _ _ _ . _ - - , _ _ _ _ - - - - - - _ - - - - - _ . - _ -_ _ _ - - -ar.- -.___-_-*- -_-- -- _ ._,A- a_.:
o 3 o r
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 12 ANSWERS -- CATAWBA 1 -85/04/03-DOUGLAS, W.G.
ANSWER 8.12 (1.00)
C REFERENCE Cote TSe p. 3/4 1-1 ANSWER 8.13 (1 00) c REFERENCE Cote Statior. Directive 2 12.2, p. 2 CNSWER 8.14 (1.00) b REFERENCE Cot, OMP 2-9, pp. 5 and 6 ANSWER 8.15 (2 00)
- a. NO (0.5)
- b. NO (0.5)
- c. YES (0 5)
- d. NO (0.5)
REFERENCE Cate TS, pp. 2-1, 3/4 5-1, 5-3, & 6-1 ANSWER 8.16 (2.00)
- c. YES (0.5)
- b. NO (0.5)
- c. YES (0.5)
- d. NO (0 5)
RFFERENCE Cote TS, pp. 3/4 1-10 & 14 and 3/4 4-7 & 10 l
l t _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . . _ _ _ e
,__y - - - - - - _ _ _ - _ _ _ _ _ - . _ _ _ _ _ _ _ - - - - - - - - - - - - - - - -
o .s o 4 *
- 8. ADMINISTRATIVE PROCEDURES CONDITIONS, AND LIMITATIONS PAGE 13 ANSWERS -- CATAWBA 1 -85/04/03-DOUGLAS, W.G.
CNSWER 8.17 (2.00)
O. FALSE (0.5)
- b. FALSE (0.5)
- c. FALSE (0.5)
- d. TRUE (0.5)
REFERENCE Cotr TS, p. 3/4 0-1 and B 3/4 0-1 ANSWER 8.18 (1.50)
- o. TRUE (0.5)
- b. TRUE (0.5)
- c. FALSE (0.5)
REFERENCE Cote Station Directive 3.1.1, pp. 6e 8, and 18 ANSWER 8 19 (1.50)
- c. FALSE (0 5) ;
i
- b. TRUE (0.5)
- c. TRUE (0.5)
REFERENCE Cote OMP 1-4, pp. 10 and 11 ANSWER 8.20 (2.00)
- o. ADMIN (or EXTENSION) (0.5)
EXTENSION (0,5) b.
- c. FEDERAL (0.5)
- d. ADMIN (0 5)
RFFFRENCE Cote Station Directive 3 8.5, p. 2 and 3.8 6, p. 2 and 10CFR20.101 l
1
m e
C 4, O 4 *
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 14 ANSWERS -- CATAWBA 1 -85/04/03-DOUGLAS, W.G.
C.NSWER 8.21 (1.50)
- 1. c (0.3)
- 2. b (0 3)
- 3. b (0.3)
- 4. e (0.3)
- 5. a (0.3)
REFERENCE McG, TS, p. 3/4 4-19 k- Cot, TS, p. 3/4 4-20 ANSWER 8.22 (1.50)
- o. 5 (0.3)
- b. 7 (0 3)
- c. 3 (0.3)
- d. 3 (0 3)
- o. 4 (0.3)
REFERENCE Cot, TS, p. B 2 7 ANSWER 8.23 (2.00)
- 1. MTC within analyzed range (0.4)
- 2. Trip instrumentation within operating range (0.4)
- 3. Above P-12 setpoint (0.4)
- 4. Pzr capable of being operable (0.2) with a steam bubble (0.2) ,(0.4)
REFERENCE Cot, TS, p. 3/4 1-17 5
_s-.---___________-__-____,.,..n--- ..