ML20246J529
| ML20246J529 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/27/1989 |
| From: | Brockman K, Curtis Rapp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20246J493 | List: |
| References | |
| 50-413-OL-89-01, 50-413-OL-89-1, NUDOCS 8905170103 | |
| Download: ML20246J529 (56) | |
Text
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-* UNITED STATES
,y 'A RElog'o NUCLEAR REGULATORY COMMISS!ON
.C [ n REGION il -
- 8 ,j 101 MARIETTA STREET, N.W.
U 2 ATL.ANTA, GEORGt A 30323
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ENCLOSURE 1 EXAMINATION REPORT 413/0L-89-01 Facility Licensee: Duke Power Company Catawba Nuclear Station P. O. Box 256 Clover, SC 29710 L Facility Docket No.: 50-413 Facility License No.: NPF-35 Examinations were- administered at the Catawba Nuclear Station near Charlotte, North Carolina.
Chief Examiner: bW Cuft W. lapp /T m ,_ //b7/89
/ Datd Signed Approved By:_ M n Brockma~n, Chief M/27 /81 Date Signed perator Licensing Section 2 Division ~of Reactor Safety Summary:
Examinations were administered on March 27 - 28, 1989.
A written re-examination was administered to one SR0 applicant, and a simulator only re-examination was administered to one R0 applicant. Both applicants passed these re-examinations.
Three of the four examination comments submitted by the facility were due to incorrect or inaccurate material provided by the facility for examination development.
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8905170103 890504 PDR V ADOCK 05000413 i FDC .
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REPORT DETAILS q l
- 1. Facility Employees Contacted:
W. Barron, Director, Operator Training l G. Spurlin, Senior Instructor, Simulator ]
T. Kiker, Nuclear Instructor {
R. Mayes. Nrrisar Instructor
- 2. Examiner:
- C. Rapp
- Chief Examiner
- 3. Exit Meeting At the conclusion of the site visit the examiner met with representatives of the plant staff to discuss the results of the examination.
One instance of negative training was observed. The use of VCT auto makeup is allowed during simulator training, but is not used in plant.
The operators could become dependant on an automatic system during training !
that is not available during actual plant operation.
The cooperation given to the examiner was noted and appreciated.
The licensee did not identify as proprietary any of the material provided to or reviewed by the examiner.
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U. S. NUCLEAR REOLILATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: ,,,GATOSWO_,_ _ ______ _ ___ _
REACTOR TYPE: ,_ P W B -$j E C 4_ _ ,,,,, _ _, _ _ _ _ _ _ _ _ ,,,, _
DATE ADMINISTERED: _ 8 2 4 9 'j f 2 8 ,,,,_ _,,,_ _ _ ,_ ,,_ _ _ _ _ _
EXAMINER: _ R E G I g t.,L.I l ___ _ _ _ _ ,_ _ _ ,,,, _
CANDIDATE: _ _ M ,57_6__4,. _ _ _ _ _ _ _
10SIBUCI1gNg_,IQ_G9Np1DSIE1 Use separate paper for the answers. Write answers on one tide 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 'C' hours after the examination starts. /.f
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__28695_ _ICI6L __,,,@COBE___ _ M G L U E _ __ _ _ _ ,,,,_.__,._ _ _ _ _ _ _ G S I E G O B L _ _ _,_ _ _ _,_ _, _
__9199_. __9t99 _ _ _ _ . _ _ _ _ _ _._____.,_5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS ,
-I 46.7f
_.0. 2 2 u :_ ._%19950 0 , _. _ _ _ _ _ _ _ _, ,_______,_6. PLANT SYSTEMS DESIGN, CONTROL, l AND INSTRUMENTATION '
O.00 O.00 7. PROCEDURES - NORMAL, ABNORMAL, j EMERGENCY AND RADIOLOGICAL CONTROL
_._ g to g _,_ ,,_ _ 9 t g g , , , . _ _ _ , _ _ _ _ _ _ , _
_._____,,._8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS As. 7,r e ,27_ _ _____ ___ _ _ _ _
...___.__.,_% Totalc ,
Final Grade Al1 wark done on thi n examination i s rm own. I have neither given nor received aid.
Candidate's Signature
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+' NRC RULES-AND-GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1'. Cheating on the examination means an automatic' denial of your application and could result in more severe penalties.
- 2. .Restroom trips:are to be limited and only one candidate at a time may ;
'l e aye . You must avoid all contacts with anyone outside the examination room to avoid even th'e appearance or possibility of cheating.
- 3. Use black ink or dark pencil gnly to facilitate legible reproductions.
, 4. Print your name in the blank provided on the cover sheet of the ex ami n at i on .
- 5. Fill in the date on the cover sheet of the examination (if necessary).
' 6' . Ue9 only the paper ~ provided for answers.
- 7. Print your'name in the upper right-hand corner of the first'page of eact1 section of the answer sheet.
- 8. : Consecutively number each answer sheet, write "End of Cate?)ory _" an appropriate, start-each category on a new page, write gnly 90 gne side: I
.of the paper, and write "Last Page" on the last answer sheet.
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- 9. Number'each answer as to category and number, for example, 1.4, 6.3.
4 4
- 10. . Skip at least ilatgg lines between each answer.
- 11. Separate answer sheets f rom pad and place finished answer sheets' face 1
'down on your desk or table.
- 12. Use abbreviations only if they are commonly used in f aci li ty 1_i_tecatute.
13.-The point value for each question is indicated.in parentheses after the ;
question and can be used as a guide for the depth of answer required. 1 1_4 . Show alI calculations, methods, or assumptions used to obtain an answer !
to mathematical problems whether indicated in the question or not, j
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE DUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of !
the etiamingt only. j l
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examinati on. This must be done after the examinati on has been completed. J 1
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.. [1 . l 9-18.(When you= complete-'your examination,'you shall I
a'. . . Assembl e ..your 'o>cami nati on as f ol l ows:
, --( 1 ) Exam quentions on top.
.(2) - Exam 'ai ds' -- f i gures, tableni etc.
L( 3 ) - Answer'pages including figures which are,part-of the answer.
- b. Turn in your copy of the examination an'd all pages used to answer the ' exami nati on 'questi ons.
-c. Turn in all scrap' paper and the balance of the paper'that you did not use for' answering tho' questions.
-d. Leave the examination area, as defined-by the-examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked. ,
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.k PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
- 6. PAGE. 3 i
DUESTION 6.01 (1.00)
Which one of the following DOES NOT correctly describe automatic operation
'of.the KC (Component Cooling) system on a saf ety inj ection signal . l a) All.non-running KC pumps start.
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b) Aux i1i ary bui 1 di ng non-o.u; senti al header supply and return isolation val ves shut .
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c) Both KC train surge tank isolation valves shut. ;
I d) Both trains of ND heat exchanger isolation valves fully open.
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QUESTION 6.02 (1.00) i Which one of the f ol l owi ng statements reguarding reactor trip system interlocks in correct?
a) When decreasing power below P-10, power range positive and negative rate trips are automatically y blocked.
b) .
the low flow ' ";, N WU ,
Whenincreasingpowe[r trip / above for P-8, f 9 automatical1y onabled.
one 1aop 13 c) When increasing power above P-10, if the operat or fails to block the intermediate range trip, the first indication will be an automatic trip. )
d) When increasing power above P-9, a reactor trip on turbine trip i s automatica11y tlocked.
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T : 6. 6 PL_ ANT SYSTEMS DESIGN. CONTROL, AND INSTRUMENTATION. PAGE 4 l-QUESTION '6.03 (1.00)
Wh'i ch ' one - o f the following. statements correctly describes features of the
-RY/RF (Fire Protection) systems?
a) The auxiliary feedwater pump pits and diesel generator building are protected by halon release systems, b) Deluge ' valves automatically reset when the water supply is secured f; by shutting the manual isolation valve, t) The main fire pumps automatically stop on system high pressure.
.d) Each of the three main fire pumps can meet maximum demand by itself.
DUESTION 6.04 (1.00) i Whi,ch one of the following correctly completes the statement below?
'The turbino driven CA pump will automatically start on __________ low-low level.bistables in any two steam generators or on ___________._________.
a) 1 'of 4; loss of either running motor driven CA pump, b) 1 of 4; loss of off-site power. I 1
c) 2 of 4; loss of either running motor driven CA pump.
d) 2 of 4; loss of off-site power.
i QUESTION 6.05 (1.00)
Which one of the following containment conditions DO NOT cause isolati on of the VP system 7 a) Hi pressure b)- Hi temperature c) Hi humidity d) Hi radiation ,
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I c6S i PLAN'T SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION 'PAGE 5 I
l l QUESTION 6.06- (1.00) {
'Whi ch one of the following correctly describes the effect of an UNDER j compensated IRNI following a reactor trip?. f a). Indicated IR level' will indicate erroneously high, preventing P-6
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f rom ' automatically energizing the SRNI due to the required 2 of 2 l c oi nci dence.
b) Indicated IR level will indicate erroneously low, prematurely energining.the SRNI due to the 1 of 2 coincidence.
c) Indicated IR level will indicate erroneously high, but the SRNI will still be correctl y- energized by P-6 f rom the other channel IRNI.due to the 1 of 2 coincidence. .
d) Indicated IR level will indicate erroneously low, but SRNI will not energine until P-6 issupplied from the other channel IRNI due to the 2 of 2 coincidence.
QUESTION 6.07 (1.00)
I A' reactor trip has occured from 80"/. power and reactor trip breaker "A" f ail ed to open. Which one of the following is correct concerning the oper ati on of the IDE system?
a) No steam dumps will open due to loss of the input for shifting IDE operation f rom the loss of load controller to the plant trip controller.
b) No steam dumps will open due to the presence of P-4 preventing arming of the dumps, f
c) Condenner dumps will operate normally, but the atomspheric dumps
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will n'o t arm or open due to the presence of the P-4 signal.
d) All dumps,will arm and the load rejection con trol l er will cause all dumps to modulate open.
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': 6. ' L PiANT ' SYSTEMS DESIGN, CONTROL. AND INSTRUMENTATION
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.OUESTION 6.OS (1.00)
JWhich one ofthe following is NOT an automatic closure signal for the letdown orifice i sol ati on .' val ves?
I a)' Letdown heat' exchanger outlet high temperature i
b) Low presuriner. level .,
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' c) Containment. i sol ation ;
d) Letdown containment isolation valves (NV1 A and !N2A) shut-
' QUESTION 6.09 (1.00) i Which'one of the following is correct concerning starting of the Positive'
- Displacement Pump (PDP)?
a )- The PDP will not start unless its auxiliary lube oil pump is )
running. i i
b) The PDP will trip if its recirc valve (NV477) is not opened within j 30 seconds after starting, c) The PDP will trip if sufficient oil pressure i s not. sensed within 90 seconds after starting.
d) The PDP will not start if a safety injection signal in present.
i DUESTION 6 10 (1.00)
-Which one of the following will cause the emergency diesel genertor to trip following an emergency start signal?
a) low lube til pressure b) high crankcase vacuum 1
c) generator di f f erenti al d) high jacket water temperature
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6)!2 PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATIDf[ PAGE 7-k r.
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1 QUESTION. 6J11 (0.50) l State the' reason' pressurizer heaters will be'placed in manual r
.and energized-during a baration or dilution. l j
"DUESTION 6.12 (1.00)
Which;one o'f ~ the fallowing components would NOT be affetted fallowing a ,
-lons ' of the VI. system?
a) Polishing demineralized b) ~ Main turbine fire protection system ]
c) To.rnado dampers
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d) Steam dump valves -i i
DUESTION 6.13 (1,00)
Which one of the following statements correctly describes SM PORV response
'to a' main steam isolation signal?
a) If a " manual" isolation is initiated and the SM PORVs are selected to." manual",-the PORV's will close.
b) " Manual " (control room) operation will allow reopening the SM PORVs with.an isolation' signal present without first resetting the i sol ati on signal. !
c) In " auto" SM PORV operation, the hi-hi containment pressure cannot be reset with the isolation signal present.
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d) In'" manual" SM PORV operation, the i solation signal will not prevent 1 placing the SM PORVs in " auto" and closing the SM PORVs.
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- 6. 5 PLANT SYSTEMS DESIGN, CONTROLa AND INSTRUMENTATION PAGE 8 DUESTION 6.14 (l.00) !
Which one of the following does NOT correctly describe the ef f ect of an input signal failure on the IDE systom?
C hannel I cc $/M/87; a) Turbine impulse pressure 3 failing low will . prevent dumps from opening i unless Tavg e>:ceeds Tref by 3 F .
b) Main steam header pressure f ailing low will prevent steam dumps from actuating in steam pressure mode. l c) Tref faili.ng high will prevent stear Jumps from opening due to a low signal to the load rejection controlt er (LRC). ;
I d) Aucti oneered high Tave failing low will effect both the plant trip controller and the LRC.
QUESTION 6.15 (l.00)
Which one of the following statements is NOT correct concerning the effects af a feedwater isolation signal?
a) CF isolation occurs when the reactor trip breakers are open and 2 j out of 4 Tave channels are less than 564 F. I b) The affected unit *s CF pumps are tripped directly on a safety injection signal, c) Feedwater bypass to CA No :le valves are not shut, d) The hi-hi S/G level CF 1 solation setpoint is based on not having carryover into the SM lines.
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-6.~ 4 PLlANT SYSTEMS DESIGIL CONTROL. AND INSTRUMENTATION PAGE 9
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QUESTION 6.1'6 (1.00)
Which one of the' f ollowing statements is correct concerning an input signal failure to the' Steam Generator Level Control System? l a):If the controlling steam flow channel fails HIGH, feed flow
. decreases until the S/G stabilizes at a higher level or a high level l turbine trip occurs.
b) Saf eguards actuation requires coincident signals. f rom redundant steam pressure sensors.
c)' An erroneous feed flow signal will cause the feed regulating valve to reposition accordingly, regardless of whether.the failed channel
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ia selected for control.
d) Level control response will result if a signal failure occurs in any level channel.
t QUESTION 6.17 (1.25)
Match the f ollowing Pressurizer Level Control System failures with
.he correct effect.
t (The same answer may be used more than once. )
FAILURE EFFECT
- a. Channel 1 fails high 1. Full charging flow ,
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- b. Tavg fails Iow 2. No offett j
- c. Channel 1 f ails low 3. Pr level drops to low level f
- d. Tavg f ails high 4. No effect at 100% power !
l se. Channel 2 fails high l
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[56. 'IPLANTESYSTEMS DESIGN. CONTROL. AND -- INSTRUMENTSII DE -
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.DUESTUON ~ 6.[1i3 : .(1.00)
- Whi ch ' one 'of . the if all owing will NOT.cause an " urgent. alarm" in the Rod Control System?
a) Phase, failure.
.b) Failure of'one DC', power supply-(c)' Multiplexing error
~d) Regul ati on ' f ailure QUESTION 6.19 (1.00)
WhichLone of the following statements, concerning the NS system, is NOT ,
~ correct?
-i a) Containment spray wall automatically teminate at 0.3 psig decreasing . j containment pressure control signal (CPCS) and will automat i ca11 y ' -)
restart at 0.4.psig increasing CPCS., I
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b) .NS' heat exchangers..will align automatically'to the RN system when pump suction swaps from the FWST to the containment sump.
'c)~ Manual init2ation of containment spray must be coincident with 0.4' j psi g CPCS.- '
d').To open NS38D or NS43A (ND spray header containment isolation valves) requires a CPCS signal.
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4 l 6j J PLANT SYSJJEMS DESIGN. CONTROLu -AND INSTRUMENTATION PAGE 11
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' QUEGTION 6.20 l (1.00) f'-.Whichoneofthe.
f ollowing will the operator adjust to control the cooldown rate, when conducting a cooldown using ND, in accordance with OP/1/A/6100/027 a) KC outlet isolation valves from ND heat exchanger (VC-57A and 82B) b) ND heat exchanger outlet valves (ND-26 and 60) c)',ND heat exchanger bypass valves (ND-27 and 61) d) ND heat. exchanger outlet and bypass valvec
' QUESTION 6.21 (1.00)
Which one-of the f ollowing malf unctions would cause a pressurizer l evel
- ii3dication c' 0%7 a) DP call diaphram rupture b) Reference leg rupture c) Impulse line rupture d) Equalizing valve leakage OUESTION 6.22 (1.00)
OP/1/A/6100/01 cautions do not exceed 385 psig NC system pressure when operating in the LOW PRESSURE made. Which one of the f oll owing is the {
basi s f or thi n caution?
a) Prevent closure of the pressurizer block valves b) Prevent isolation of the ND system c) Prevent overpressurization of the NC pump seals d) Prevent opening of the pressurl er PORVs 1
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. 6. i N PLffT' SYSTEMS DESIGN. CONTROL. AND-INSTRUMENTATION PAGE 12 l
(OUESTION 6.23 ( 1. 00) '
Which - one of the f ollowing statements regarding .CF pump speed control'is
, ' correct?
a) At least one Westinghouse and one GE controller must be in AUTO for f1nw balance compensation to be in offect.
b) The Westinghouse control)er is-used for starting the CF pumps while
'in MANUAL and is placed in AUTO when the pump is on-line.
c) The pump speed demand signal is developed from the comparison of the difference beteewn the steam pressure and CF pump pressure with the programmed D/P signal.
d) Flow balance compensation is in effect when the Westinghouse FWP A is in AJTO, With no regard for the status of the other FWP, because the r,etpoint potentiometer is'on FWP A M/A station.
QUESTION 6.24 (1.00)
Which one cf the following would.NOT result in a loss of power tc, MXA when z transferring from LXA to LXF? !
- 3) Place both MXA supply breakers to AUTO then opsn the feeder from LXA allowing the feeder from LXF to close.
b) . Place ONLY the LXA feeder in AUTO then close the LXF feeder allowing the LXA feeder to open.
c) Place both MXA supply breakers in MANUAL and close the LXF feeder allowing the LXA feeder to trip open.
i d) Leave both feeders in their normal positi ons and clone the LXF feeder allowing LXA feeder to trip open.
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' QUESTION 6.25 (1.00)
Which one of the f ollowing describes the ef f ect a loss of RL discharge flow will have on a Liquid Waste system discharge 7 a) The li quid, waste system di scharge valve will close.
b) A control-room alarm will alert the operator to manually stor) the discharge.
c) The discharge will-continue unless EMF-49 (Waste Li quid Discharge Monitor) . also al arms.
d) The discharge will shift to the Standby Nuclear Service Water pond- ,
QUESTIDN 6.26 (1.00)
OP/1/A/6100/01 cautions that stea withdrawal from the S/Gs must be done slowly while at low power. Wh i one of the.following is the correct basis
- -f o r this caution?
a) Prevent MSIV c1c~ are on high steam line flow
-b) Prevent a 1: w steani n- prerrare SI
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c) Preven an uncontr led insertion of positive reactivity d) P avent reducing Tave below 551 F
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U6. # PLANT4 GYSTEMS DESIGN. CONTROL, _AND INSTRUMENTATION PAGE~14 j l
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' QUESTION 6.27 -(1.00) l
. The f oll owi ng. condi ti ons e>;i st for the DRPI. system: 3
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EGW and rod. bottom l'ights for rod.H-B
- Urgent alarm 1, 2, and 3 are lit
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- RPI Urgent alarm is lit f
' Which one of the f ollowing correctly describes the position indicati'on .f or rod H-87 'l a) Indication is at HALF accuracy b) Rod H-8 is fully INSERTED c) Indication is at FULL accuracy 1
.d) Rod-H-9 position cannot be determined QUESTION 6.28 (1 . 00)
Which one of the following correctly describes what the operator must do to
-shutdown the DA transfer pump that was running when a safety injection signal occured? j a) Select , of f on the pump control. switch after the sequencer is reset b) Start the other BA transfer pump c) Insure VCT level is greater than the automatic makeup setpoint d) Roset the BA transfer pump and place the control switch in OFF i
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- PLANT SYSTEMSEDESIGN.JCON_ TROL, ANOTINSTRUMENTATION: PAGE"15 m.
,. c LOUESTI'ON' 6.29 ( 1. 00 )'.
'Which one of the,following-is the purpose of the flow orifice in the Cold.
- Leg' Accumulator (CLA) discharge 1ine?
a) Equalize flow from--the CLAs b) Extend-'the injection time of the CLAs during a LOCA
- c) Provide a met hod' to measure flow f rom .the ' CLAs duri ng a ' LOCA
.d) Provide a. method flow when testing both.CLAs discharge check valves for leakage'
-QUESTION 6.30. (1.00)
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'Which one of the following is the reason-for closing the NI pump.
recirculate on valves bef ore swapping NI pump sucti on ~- f rom the FWST to tho' ND heat excha'nger discharge 7 a) ' Raise- NI . pump di scharge pressure b). Prevent pumping water from the containment sump to the FWST c); Allow pump r.uction and' discharge pressuressto stabiline
. ~dl. Prevent pumping NC system inventory to the containment sump f
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(************* END OF EXAMINATION *************)
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i ATTACHMENTS CATABWA
.SRO EXAM.
REGION II 99/03/28 i1 I
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-ANSWER KEY cATaswa .j SRO EXAM
- ^ a .
REGION II 89/03/28 i -,
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[:..s; *' THEORY'OF NUCLEAR-POWER PLANT-OPERATIONuEglIDS u AND PAGE 18 p-; ^; THERMODYNAMICS
(. IAN'SWERS ' --- CAT ABWA -89/03/28-REGION II 1-1 l
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- ':"6.
- PLANT S_YSTEMS' DESIGN. CONTROL. AND INSTRUMENTATION PAGE 19.
1 ANSWERS 1--'CATABWA -89/03/28-REGION II
}:
' ANSWER 6.01- (1.00) c)
REFERENCE OP-CN-HO-KC, LPSD Training Objective #6 KAs- OOOOOOA304 (3.6/3.7)'
.'0080004304 . . .' ( KA ' S )
. ANSWER 6,02- (1.00) b '. -
REFERENCE CNS-Electrical System Description, ENB, CNSD-172-02, pp. 4-1 to 5-2.
- KA
- : 015000K405-(4.3/4.5) 015000K406 (3.9/4.2) 015000K407 (3.7/3.8) 015000K405' 015000K406 015000K407 ...(KA'S)
ANSWER 6.03 (1.00) f -d.
REFERENCE CNS Lesson Plan OP-CN-HO-RFY, ENPF Objecti ves 4 & 5
~CNS System Description, RY & RF, CN-1223.OO-49, pp. 14 & 16
'KA: OG6000K401 (3.1/3.7) 086000K402 (3.0/3.4)
OB6000K401 086000K402 ...(KA"S) l L
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- PLANT'$YSTEMS_
DESIGN. CONTROL; AND INSTRUMENTATION- PAGE 20 c i ANSWERS':.- CATABWA. ~B9/03/28-REGION II I' .
- ANSWER
' 6',04 ( 1., 00 )
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REFERENCE.
, ' CNS Electrics 1 System Description, CA, CNSD-0147-01, p. 14.
. KAr ' LO61000K402 (4.5/4.6)'
061000K402 ...(KA'S)
ANSWER' - 6.05 (1.00).
b..
. REFERENCE CNS Electrical System-Description, VP, CNSD-0156-03, p. 6
.KA: 103OOOK102 (3. 9/4.1 )'
103OOOK102- ...(KA'S) .
' ANSWER - 6.06- - ( 1. 00 )
'a.-
REFERENCE CNS, Electrical System Description, END, CNSD-172-02, p. 4-3.
KA: 015000K407-(3.7/3.8)
'.015000K502 (2.7/2.9) 015000K407 015000K502 ...(KA'S) l~
I' g
l-i i )
l l
L.
q '
'u i"6.NPtANT' SYSTriMS ' DESIGN. CONTROL,-AND INSTRUMENTATION' PAGE 21 4'
'.z
_ ANSWERS; a CAT BWA? -89/ 03 / 28--REG I ON II ANSWER :6.07. (1.00) ci: >(P-4".inputifrom "A" trip breaker prevents arming'of the atomspheric h , dumps. . Trip contro11ery will. Work normally due to correct P-4 input-from "B" trip breaker.)
REFERENCE OP-CN-STM-IDE, LPSOl Training ~Objectivos.5, 6LO
- KA: ' . 041020K417 - (3. 7/3. 9) 3.7/3.9-
-041020K417 ...(KA'9)
~ ANSWER "6.08 -(1.00) a.
REFERENCE 1
CNS Electrical System Description, NV, CNSD-0157-01, p. 10
.KA: OO4020K403 (3.0/3.4):
lOO4020K403- ...(KA*S)
~l ANSWER '6.09 (1.00).
.c.
l REFERENCE OP-CN-PS-NV, LP50 Training Obj ecti ves 2, 5 & 6. ,
l KA:~ OO4000K604 (2.9/3.1)
OO4000K604 . . . -( K A ' S )
l lY s I n.
- u. ..
- v. y
[ g .* PLANTGYSTEMS DESIGN. CONTROj. AND INFl,RUMENTATION PAGE 22 -'
l
. ANSWERS'- CATABWA.
- -89/OJ/28-REGION II ,j l
LANSWER 6.10 (1.00)
,cy REFERENCE
- OP-CN-HO-DG3, Diesel'Generatc,r System, p. B. 1 OP-CN-DG-DG3,'LPSO' Training. Objective #6. l (KA ' .0640,00K401' (3. 9/4,2) . I
.064000K401 . . . ( K A S )
k 1
(ANSWER '6.11 (0.50)
.To keep pressurizer baronJconcentration within 50 ppm of.NC.
REFERENCE
..OP-CN- I P E-HO , Pzr Pressurte Control, p. 9, LPSD Training Objective #8.a
'KA s . -004000K601 (3.1/3.3) 004000K601 ...(KA'S)
-ANSWER 6.12 (1.00) b) -(Served by station air system)
. REFERENCE
- OP-CN-HO-VI, Instrument Air, pp. 12 &: 19, LPSD Training Objective #2 KA: 078000K302 (3.4/3.6) 078000K302 ...(KA"S)
L, 1
1
- t l \
L l-p 1
l l
1 i
i d6. +' PLANT SYSTEMS DESIGN. CONTROL u AND If_STRUMENTATION PAGE 23 h
1, ANSWERS -- CATABWA -89/03/28-REGION II I
ANSWER .6.13 (1.00)
.b..
l t' REFERENCE
'OP-CN-HO-SM, Main Steam System, pp. 11 t< 12, LPSD Training Objective tt8.a
'KA: 039000K405 (3.7/3.7) 039000K405 ...(KA'S)
' ANSWER 6.14. (1.00)
' c)
- a. <r ,7 1 . o ,c g, f
REFERENCE OP-CN-HO-~ I D E , Steam Dump Control System, pp 8 L 9, LPGC Training Obj. #8 KA - 039000K106 (3.1/3.c) 039000A204 (3.4/3.7) 039000K106 039000A204 ...(KA'S)
ANSWER 6.15 (1.00) l c.
REFERENCE OP-CN-HD-CF, Feedwater System, pp. 29 & 30, LPSO Training Objective #9.d l KA: 059000K102 (3.4/3.4)
!. 059000K104 (3.4/3.4)
- h. .
059000K419 (3.2/3.4)
} 059000K102 '059000K104 059000K419 ...(KA'S) 1 p
L p
1 I
i l..
I' l;.
'f/.,iPLANTSYSTEMSDESIGN.
A CONTROL. AND INSTRUMENTATION ~ PAGE-24 h* ANSWERS--CATABWA -89/03/28-REGION II ANSWER 6.16. (1.00)
.b.
REFERENCE JOP-CN-HO-IFE, Steam Generator Lvl Cnt1, pp. 10-14, LPSD Training Obj. #1.c KA: 035000K401 (3.6/3.8) 035000K401 ...(KA'S)
- -ANSWER 6.17 (1.25)
.0.25
( each) l a. 3
- b. 2
- c. 1 l d. 4 l e. 2 1.
l REFERENCE CN-OP-ILE-HO, P:r Level Control System, pp. 9& 10
.CN-OP-PS-ILE, P:r Level Control System, LPSD Training Objective #7.d KA: 011000A210 (3.4/3.6) 011000A211 (3.4/3.6) l 011000A210 011000A211 ...(KA'S) i l
l1 ANSWER 6.10 (1.00)
'b.
REFERENCE OP-CN-HO-IRE, Full Length Rod Cntl. Sys., p. 16, LPSD Trg. Obj. #10
~KA: 014000K405 (3.1/3.3) 014000K405' ...(KA'S) 1 L
1.
1 L
-.' . .p =
6 N PLANT' SYSTEMS' DESIGN.,-C'OtJTROL'.'AND INSTRUMENTATION.
~
PAGE 25
'6 >
-)
' EANSWERS[-- CATABWA .89/03/28-REGION II h-
[. ' .
l- 1 r.
- l I: ANSWER' -6.19 ' (1.00) i ib) (must . be manually aligned) '
- l. .
p . g.
REFERENCE.
OP-CN-HO-NS, Containment Spray,'pp. 9& 11, LPSD Trg.-Obj. #3.c,.3.g.& 4.c q KA:. :026000K102'(4.1/4.1) 026000A101^(3.9/4.2)
<O260COklO2 026000A101 ...(KA'S) 'l ANSWER 6.20 (1;00) -
16 ) -
' REFERENCE
'CNSi OP-CN-HO.ND pg. 2d,25 LPRO LO#-6-B .
-005000A101- ..(KA'C)- !
' ANSWER 6.21 (1.00)
~c)
REFERENCE CNS: -OP-CN-SS-.IG pg. 9-LPRO LOM 6c-011000A211. ...(KA'S) l
' ' L 6. -' I PLANT SYSTEMS" DESIGN, CONTROL.-AND INSTRUMENTATION PAGE'26
, 4 ANSWERS -- CATADWA -89/03/28 -REGION II
.1 ANSWER 6.22 (1.00)
REFERENCE
-CNS: OP/1/A/6100/01 pg 3 of 32 (Retype tt 15)
.3.8/4.1 010000K403 ...(KA'S)
L.
-ANSWER 6.23 ( 1. 00) c)
REFERENCE CNS: OP-CN-IWE-HO ;
2.5/2.8 l 059000K405 ...(KA'S)
ANSWER 6.24 (i.00) c)
i REFERENCE !
CNS: EP Lesson plan j 2.8/3.1 ;
062OOOK403 ...(KA'5)
I i
i I
1 l
N.'t-PLANT SYSTEMS DESIGN. CONTROL.u AND INSTRUMENTATION PAGE 27 ANSWERS -- CATABWA -89/03/28-REGION II l
l ANSWER 6.25 (1.00) a)
REFERENCE CNS: OP-CN-SS-RL 1
- 3.6/3.6 068000A302 ...(KA'S) ,
ANSWER 6.26 ' ( 1. 00) d)
REFERENCE CNS: OP 1/A/6100/01 2.6/~.7 3.3/3.6 2.7/3.1 03 000 A 103 039000A205 039000 GOO 5 ...(KA'S)
ANSWER .6.27 (1.00) d)
REFERENCE CNS: EDA Lesson plan 2.9/3.1 014000G008 ...(KA'5)
.j r e jp r
., ,. k
-]'; f[ ? PL' ANT ' SYSTEMS DESLGN. - CONTROL AND INSTRUMENTATIOff ' PAGE 281 -
c .. 1 1 . ': .
s q
- l. ;. ANSWERS 4 CATADWA. --89/ 03 / 28-REG I ON II .j i 1
.)--,
l' -i.- .: 1
- - ANSWER 6.28 (1.00)
" d ) '.
~
REFERENCE:
,J2.4/2.9 i013OOOK603 ...(KA"S) 1
, ANSWER 6.29: (1.00) i d
b) o I
REFERENCE CNS: CLA Lesson plan 3.4/3.9' 006000K602- ' . . . - ( K A 'J )
ANSWER 6.30 '( 1. 00)
!b)
REFERENCE
'CNS: NI Lesson plan 3.4/3.7-061000G010 ...(KA'G) 1
= - - _ _ _ - - - _ _ - _ _ _ - _ _ _ - - - - _ _ - . _ _ _ . - _ _ _ _ _
ENCLOSURE 3 67 . PLANT SYSTEMS DESIGN. CONTROL. AmD I Nw r RUMENTAT IDN PAGE -3 i:
~I.,
GUESTION 6.01 (1.00) *
- Which one'of I the following DOES NOT correctly describe automatic operation I of the KC (Component Cool i ng) system on a saf ety injection signal.
a) All'non-running KC pumps. start.
' b) Auxiliary building non-essential header supply and return i sol a t i on valves-shut.
c) Both KC train surge tank i sol ation val ves shut.
d) Both trains of ND. heat exchanger i sol ati on val ves f ull y open.'-
4
(..... c AT_ .. _ _ cN _ T _ .....,
QUESTION 6.01 i
Selections "b" and "d" are also correct since low FWST level must be present at the same time for these to occur. Please refer to the reference (6.01).
We recommend that the question be changed for future use to "Which one of the following DOES NOT correctly describe automatic operation of the KC system on a safety injection signal with Low FWST level also present?"
I l
l .
j
Com/Mest Coolid t esson l ha
. OP-CN-PSS-KC-March 16, 1987/SMJ
( Page 10 of 14 Reference L 01 fhne' /
b .' List of Components
- 1) ND Hx
- 2) ND Pump Mech Seal Hx
- 3) NI Pump Motor Coolers 4) NV Pump Motor Coolers-
- 5) CA Pump Motor-Coolers
- 6) NS Pump Motor Coolers
- 7) KC Pump Motor Coolers
- 8) NV Pump BRG Oil. Cooler
- 9) NV Pump Speed Reducer Oil Cooler
.10) NI Pump BRG. Oil Cooler
- 11) Post Acc. Liq. Monitor Sample Cooler.(A Train Only)
- 12) ND Pump Motor Cooler F. Auxiliary Building Non-Essential Header (OBJ ENPF/ISS/RO/SRO #3)
- 1. Surply and return isolations both normally open.
- 2. FJpply 50A, 53B, Return ~1A, 2B.
- a. Close on:
2 I E W FjlSTJ ol)ci 3s7 dd*Su(rgeTank o
- 3) :7o518 lev 51""If trhih*F6
- b. Controlled from CR and ASP
- 3. Components Cooled
- a. H2 recombiners (2)
- b. Waste gas comp (2)
- c. Recycle evap..pkg.
- d. Waste evap. pkg.
- e. Seal water.Hx (1)
- f. Fuel pool cool Hx (2)
- 1) Temporary piping can be installed between Unit l's and Unit 2's KF Systems so that Unit l's SFP can be cooled by 2A KF Hx and vice versa.
- g. PD Pump oil cooler (1)-
L h. KF pump motor cooler (2) l- 1. Sample Rx
- j. Letdown Hx
- k. All flow controlled except-1)' Evaporator concentrates Ex's (Manual isolations) l
- 2) Letdown Hx is Temperature Controlled (Manual / Auto Station MC10)
- 3) KF Hx Manual loader in Control Room
- 4) KF Pump Motor Cooler and PD Pump Oil Cooler (Manual)
- 5) Waste and NB Evaporator Components G. Reactor Building Non-Essential Header
- 1. Sup}17 and return isolations both normally open.
- 2. Supply 228B, 230A, Return 3A, 18B
- a. Close on:
I- 1) Sp signal
- 2) Lo-lo level in train related surge tank
- 3) Lo Level in FWST following Ss. (37%)
Rev. 07/02-20-89/TSR
R OWAft%If 0Yl'41 00SOh)
, io 0 ;._
OP-CN-PSS-KC March 16, 1987/SMJ Page 9 of 14 l]eference d.O/ ,
p4ge 2.
- 5. Asto start
- a. Train related blackout
- b. Ss
- 6. Controls j
- a. Control Room (
- b. Auxiliary Shutdown Panel .
f
- 7. Location (Unit 1 - Aux. Bldg. 560', Unit 2 - Aux. Bldg. 577) i C. KC Hx's (ENPF/ISS/RO/SRO.#2) l l
- 1. Tube Side RN - Easier to clean i
- 2. Shell side KC
- 3. KC pressure > RN pressure
- a. Tube leak to RN
- b. Keeps excessive Chlorides out of KC-
- c. RN flow temp, controlled
- 1) KC out 100 F 2)' High Temp. Alarm 125 F
- 4. Location - Aux. Bldg. 577'
- 5. The "KC HX A(B) RN Outlet flow-lo" annunciator was constantly in alarm during normal operations in the "KC TEMP" mode due to relatively low heat load. An NSM was installed to eliminate this nusiance alarm by interlocking each annunciator with a Ss signal such that the alarm will only be enabled while a Ss signal is present. It also provides a 72 second time delay after the Ss signal to allow the RN valve to stroke full open.
D. EMF's (RO/SRO OBJ #7)
- 1. Sample Flow to KC Surge Tank
- 2. EMF 46A and B
- a. Hi radiation signal
- 1) Provides an alarm only
- b. Indication of:
- 1) NC in-leakage 2). Possible KC activation E. Essential Header (ENPF/ISS OBJ #4, RO/SRO #6)
- 1. Provides cooling to ESF Components
- 2. Manual valves normally open
- a. Only component normally isolated on essential header is
$ldM[n5$($hSai o'nESplor'IEleveliiri"FWSTh7
'following i Ss!
a) 5000 gpm b) Low Flow Alarm 4750 gpm
- 2) ND Hx outlet auto opens on Ss or loss of VI.
- 3) Controls provided for isolation and flow control by the operator during Normal operations.
- 4) S resets on MC-11 for 57 and 82 (ND HX outlet)
Rev. 07/02-20-89/TSR f.
i J
p ,
b;: PLANT SYSTEMS DESIGN. CONTROL. AND' INSTRUMENTATION PAGE.16 ,
.4 QUESTION 6.14 (1.00) 1 Which one'of the following does NOT correctly describe the effect of an
{
input signal failure on the IDE system?
a) Turbine impul se pressure failing low will prevent dumps from opening unless Tavg exceeds Tref by 3 F.
I b) Main steam header pressure failing Icw will prevent steam dumps from actuating in steam pressure mode.
c) Tref failing high will prevent steam dumps from opening due to a low signal to the . load rej ection controller (LRC).
d) Auctioneered high Tave f ailing low will effect both the plant trip controller and the LRC.
1 4
I i
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
QUESTION 6.14-Option "a" and "d" need changing as fo11cws for "d" and only "d" to be correct.
a) Turbine impulse pressure ' %nnel II instantaneously failing low will prevent dumps from opening us. ass Tave exceeds TREF by 3 F.
l d) Loop C Tave failing low will affect both the plant trip controller and the Load Rejection Controller.
i We recommend changing to the above for future use.
l I
_ _ _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ ____.__-_m_______. ____ __.- .__ .__-__._____m-- __.____
Steen Damp I.em P/E_
OP-CN-SYS-STM-IDE
.Refereme 0/7 Mey 7, 1eS5,cES/
4 P e /cg L Page a 6f 12 :;
- 4. Modulates condenser dumps if the' arming signals are satisfled and no blocks exist. .)
- a. Press Mode Selected R b.: C-9
- 1) . Condenser Vacuum > 20" Hg.
-2) 1/4.RC pump bkrs closed.
- c. No P-12.
H. hkmv&P??3mv"??
Rejoction? Controller
- 1. Used during' load rejection to prevent a large T "#* increase-on loss of load.
'2. Enables by select switch in "T,y," and no Reactor. trip (P-4 Train-B).
- 3. Comgares T to.T and modulates all~ banks as'necessary.
- 4. A3Fdead*Eandex50ksonthecontrollertoallowrod control.to actuate to decrease T
- 5. Modulates dumps.open one bank at*a* time.
.a. Bank one open fully, then Bank 2 starts opening, etc.
- b. See handout for setpoints.
- 6. Arming Signals (OBJ RO/SRO #6b, 6c, 6d)
- a. "T " mode selected
- b. C-N'or C-7B actuated.
- 1) C-7A arms condenser dumps.
- 2) C-7B arms atmospheric dumps.
- c. NO Reactor Trip (P-4 Train A)'- atmospheric dumps,
- d. C Condenser Dumps
- 7. Signals L'oad
- a. Rejection $ tied $6F?tisrb'insElmpulsEWrEdi boadIdete 'r'e~
lj7bfffir"e^iii*chdnnsl*than reactor contr516sePfok*
T- calculation.
- b. Loads 5halgoesthruIsol.amptoderivativecircuit.
- c. Derivative circuit. generates output signal proportional to rate of change of< impulse pressure.
- 1) Output zero for nonchanging pressure signal.
- d. Load Reduction Bistables
- 1) 10% Step load decrease or 5% per min, a) Energizes latching relay, b) Activates C-7A interlock (1) LOSS OF LOAD INTLK COND DMP VLVS.
c) With C-9 activated, will arm banks 1, 2, 3.
(1) Energizes arming solenoid. valves.
(2) C-9 not activated will block arming signals (Banks 1, 2, 3) d). C-7A Reset (1) Take "STM DUMP SELECT SWITCH" to " RESET"
- 2) 30% step load decrease, or 15%/ min a) Energizes latching relay b) Activates C-7B interlock (1) Loss of load INTLK Atms. DMP. VLVS.
Rev. 01--l-27-88/SMJ
CNS )
Rg Cw[e] ksson
. Refereace d.ly pge zk2 ,
4 .
TMF j 3 E
'"" -fvg ""
C-16 im ====O y MLW t
~ 5.>- cL. b ll JL
=9-12 CF l ee t. ir 1r "I# I*** W OtviaE on gfg t/ 9 3 .. , . . .
g T-avg auCf. M3 f.ev0 P2R LEVEL h.
ig g[Q"CNh."N.
W: s ..:'aG .i ,.3 NUCL(AR PQ( R I "*E " # "*
C POWR MIEMnTCN 8
- 88 8 - PROTECilm jr e ' 61616 Nuc E5A P R M C9euttR
-+ FJ m c" 4 l FILifR l
, l FILTER l If ,,
T-REF 1r PROGAAM 0(Alvef f vf C- 16 4====
W RECORDER 4=======
1r NON-LlNEAR
,r Cw. .--.- g w =
.fr.ww 4
+ COWTER 1r 1r
~
FIL ER E IA 4
T-81EF T.avo M SMatCM . O , RNOR \ g euCf. Mi favG C9414D 1 l
6 88 CN-IC IRE-22 I" 2/10/87
"' Reactor Control w.
l NEDRR/88 N DRR l TRAISElEW l
QUESTION 6.24 (1.00)
Which one of the f ollowing would NOT resul t in a loss of power to MXA when transferring from LXA to LXF7 a) Pl ace both MX A suppl y breakers to AUTO then open__the f eeder from LXA allowing the f eeder- f rom LXF to close. '
b) Place ONLY the LXA feeder in AUTO then close the LXF feeder allowing the LXA feeder-to open, c) Place both MXA' suppl y breakers in MANUAL and close the LXF f eeder allowing the-LXA feeder to trip open,
- d) Leave both f eeders in their normal positions and close the LXF feeder allowing LXA feeder to trip open.
l 1
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
I i
i
. i JQUESTION 6.24 Selection."a", "b", and "d" are not possible manipulations.
We recommend the following change for future use:
"Winich one of the following is the correct method to swap from normal to .
alternate supply to MXA?" )
l Then selections "a" through "d" could remain as is and "c" still would be the ]
correct answer.
i
- _ . _ _ . . _ . ~ . _ _ _ _ - . . - _ - _ . . . _ _ _ _ .
Referenco 6.24 The attached drawings are all sections of electrical elementary CNEE-0211-01.06 (i.e. Normal feeder to MCC 2MXA on 2LXA).
- 2 Shows the contact development for the Auto / Man selector switch.
- 3 Shows the contact development for the trip /close switch.
- 4 Shows that the breaker M/A control must be in Manual (contacts 15/16 and 7/8) to Trip (contact 3/4) or Close (contacts 1/2).' If the Alternate breaker is closed it must be in " Manual" (contacts 11/12) and the breaker on this drawing also in " Manual" (contacts 3/4).
I
W
'/
l Refenence 6.24
- e. REr. o.GS.
EPO-N2 CrW-2312. 03-31 2LXM IFR. W/D LMIT 3 -
2LXR CNW-2312. 03-32 2LXR nFR. W/D IPf!TS 4 & 5 l CtW-2312. 03-47 ELXF nFR. W/D t, NIT 3 i o 2LXF 2LXF nFR. W/D UNITS 4 6 5
= 2LCCP1 CfW-2312. 03-48 CtW-2312. 03 -30 DEVICE INTERffLS Ct+-2707-02. 01 ELXA OPE LIFE DIRGRAW Ct+-2703-02. 01 2LXF OPE LIff DIRGRAW CNWT-2754-02.01 - ELXR WIRE TABLA.ATIONS
- 2LXF WIRE TRSLARTIONS ..
CNWT-2754-02.06 CNWT-2754-05. 01 ELCCP1 WIIE TABLLRTIONS r.f _ n ';' T'*\*
CREE-0211-01. 54 2LXF NORM. FDR. TO WCC 2MXR ' i '
?
CNEE-0211-01. 69 LORD CENTERS SYNCHt0NIZING CIRCUITS .INFORMATION (MFR.)h 52 CONTACT d BREAKER O(~CNM-1312.03-14 SH. la2
~ . -
= .
g_gCEfyg WORKING COM 9
o OCT 141980
/p CONTROLLED NUCLEAR DU KE POW ER COMP ANY CATAWBA NUCLEAR STATION UNIT 2 ELEMENTARY DIAGRAM 600V LORD CENTER
- 2LXA COMPT. *5C :
NORMAL FDR. TO 600V MCC 2MXA 3 @
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5 pas >M
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< SPPftE 7 9 X N N/R5C__
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, . QUESTION 6.26 (1.00)
OP/1/A/6100/01 cautions that steam withdrawal from the S/Gs must be done clowl y while at l ow power. Which one of the f ollowing is the correct basis
'for this caution?
a) Prevent MSIV closure on high steam line flow b) Prevent a l ow steam line pressure SI c) Prevent an uncontrolled insertion of positive reactivity d) Prevent reducing Tave below 551 F
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
7--,.
QUESTION 6.26 The startup procedure Limit & Precaution 4.6 in OP/1/A/6100/01 addressed in this
- question does not state the reason for the precaution. The justification document references the Westinghouse Plant Startup from Cold Condition to Minimum Load, pg. 1:7, items 28 and 29. This document (attached) gives only one reason and that is to " avoid rapid cooling of the roactor coolant". This makes "b", "c", or "d" correct.
We request credit for selection "b", "c", or "d".
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ATTACHMENTS
.1 DUKE POWER COMPANY PROJECT CATAWBA NUCLEAR STATION, UNITS 1 AND 2 Swop ORDER. DCP-490
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WESTINGHOUSE PROPRIETARY DATA This document .s the property of and contains proprietary informesson owned ny the Westinw house Electric Corgeration, Nucteer Energy Systems, and is transmitted to you in conf dence and trust and is to be returned upon request. No permission is granted to pun-lish, reproduce transtrut or dreciose to another any mformation Contained in this document,
.n whole or in part, without ene prior written permission. in each case, of an authorized emprove of md corporation. .
WESTINGHOUSE ELECTRIC CORPCR ATION Nuclear Energy Systems P.O. Bos 355 Pittsburgn, Pennsylvania 15230 APPROVAL ORIGINAL 155UE REv. t Rf V. 2 AUTHOR
, SHOP ORDER HOLDER Page of _ Pages
' -1 :'
(EFfER ENCE A 6.2.6 288BIIN8II$M@iME!
s- TIITARTUPIFROMTC0[.D~CONDIT10 w-c.wn.-~- f 6 MIN-a a-.w ._IM,UM_t.0AD' j
A. PURp0SE'
-This~ instruction describes the startup of the reactor plant from a refueling or cold shutdown condition to minimum load. The proper reactor coolant pressure, temperature and flow are established and the reactor is brought to a low power condition.
The instruction is in three parts:
I. Steam Bubble Startup II. Water Solid Startup III. Reactor Coolant Heatup B. INITIA!. CONDITIONS ._
- 1. The reactor coolant loops, the pressurizer and the reactor vessel are completely filled (venting operation completed).
- 2. The reactor coolant boron concentration is at the cold shutdown or refueling value.
- 3. The reactor coolant pumps are stopped.
- 4. The reactor coolant temperature is 160'F or less and vented to the pressurizer relief tank through the open power operated relief valves.
- 5. The Residual Heat removal System is in operation as required to main-tain the reactor coolant temperature less than 160*F. The RHR inlet
' isolation valves electric power supplies are locked out.
'~
- 6. The pressurizer relief valves are in manual control and open. All of the safety valves are operable.
REFEREHCE L 16
,y 25.
L Continuous flow should be maintained in the pressurizer spray lines L
to protect the lines' from themal shock and help maintain uniform water chemistry in the pressurizer. Low temperature alarms are pro-vided to indicate insufficient bypass flow.
26.
After any significant change in charging flow, the reactor coolant
! , pump seal injection flows should be checked and adjusted if necessary.
27.
The control rod drive mechanism cooling fans must be turned on if the temperature of the reactor' coolant is greater than 350'F.
- [t : . When the reactor is critical at low power, steam removal from the steam generators which could expose the reactor to large unexpected 1 energy withdrawals must be. avoided. Therefore, when the reactor is critical, steam being used to warm lines, to operate the air ejector and gland steam system or for other auxiliary uses or to warm up the i
main turbine and feed pumps must be under strict administrative control to ensure the steam is drawn slowly, y9L During steam plant warmup, draw steam slowly and regulate feedwater .__
additions carefully ) Q @ [ y h k [56] k d h k h h 5I @
30.
The reactor must not be taken into the power range until the hydrogen concentration in the coolant is at least 15 cc/kg.
- 31. Do not exceed a steam generator primary to secondary differential pressure of 1600 psi during nomal plant operatiens.
D. INSTRUCTIONS Part I - Steam Bubble Startup This procedure may be used if the reactor coolant chemistry is within
.t specification for hot operations and the reactor vessel head and steam generator tubes are filled with coolant. The pressurizer is filled and is vented to the nitrogen atmosphere of the PRT through the open relief valves.
ENCLOSURE 4 NRC Resolution of Facility Comments SRO Examination Question 6.01 NRC Resolution: Comment accepted. Confusion by the examiner between Sp and Ss signals lead to incorrect structure of the question. The question will be corrected to reflect the difference between Sp and Ss signals.
Question 6.14 NRC Resolution: Comment noted. Reference material provided by the facility for examination development incorrectly stated Tauct failing low has no effect (Ref.1).
The facility snould correct this error to correctly reflect the effect of Tauct failing low. Additionally, supporting da:umentation provided by the facility was inadequate because it did not address signal failures effect on the IDE system. Further research by the examiner was required to resolve this comment.
Question 6.24 NRC Resolution: Comment noted. This question was derived from the facility question bank provided for examination development (Ref. 2). The facility should correct this question to use possible manipulations as distractors.
Question 6.26 NRC Resoultion: Comment noted. This question was derived from the facility question bank provided for examination development (Ref. 3). Additional documentation not originally supplied for examination development indicates the bases for this caution is excessive cooling. Since choices b), c), or d) could be affected by excessive cooling, the question does not adequately discriminate and will be deleted from the examination.
The facility should correct the question bank to reflect excessive cooldown as the basis for this caution.
(REF. 1) op.cg_go_3pg January 2, 1986/QW/
Page 8 of 9 m
I.)
E. Wrmm1 Shutdcwn
- 1. Below 10% pacer, select STEAM PIUSS control node.
- a. Ensure STM DLNP CTRL in Auto and set at 1092 peig.
- b. Verify T is = 2"P of T,g.
- c. Nierify S7M DtNP DEMAND indicated "Zero".
- d. Transfer to T .
- 2. Set pressure controllar to maintain no-load operating conditions of 1092 peig._
- 3. If the unit is to be maintair ! in hot stanty cxrxiition, the venting of steam will be redLod to zero as the resichal heat removal requir- :ad.i, are rdwai- -
- 4. If the unit is to be trought to cold shutdown, stean dump is continued to the condenser.
- 5. Man cooldown reaches the P-12 Io-Io T point (553 F), turn y both steam durip channel switches to tO INILK positions . ./
F. -- .tary) .
NME: It is not m**ry to operate both staan dung channel switches simultaneously.
- 6. Steam dung will be permitted to Bank I cooldown cordenser dung valves providing condenser is available.
- 7. The bypass is reset by turning both steam dunp channel switches amentarily to TP/ RESET.
- 8. If T avg rises above P-12, the bypass will be reset automatically, 5.0 Failure o'f Irput Signals A. Auctioneered High T,
- 1. Fails High - would efaset plant trip and IJic.
- a. Causes large demand signal, however, dumps would be blocked because:
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OP-CN-fD-IDE
.(REF.1 con,t) January 2,1986/GW/
Page 9 of 9
.1) No Icad Rejection
- 2) No Beactor Trip
- 2. Fails Iow - No Effect B. T rd
- 1. Fails High - wnlld effect Icad Rejection Controller
- a. Rxald prevent dtznps fran cpenig due to a low signal to the IJIC.
- b. Ex21d require manual operaticn to reduce T,.
- 2. Fails Iow
- a. Generates a T to the dutrps
-T rd mismatch causig an cpenig signal C. Turbine Irpulse Pressure (G-II)
- 1. Fails High - affects C-7A, C-7B
- a. No etfact
- 2. Fails Icw
- a. Could aun C-7A, C-7B if fails rapidly.
- b. Dimps will not open unless T, Ws T gg by 3 F.
D. Main Steam BW Presstre
- 1. Fails High - affects Stean Pressure Controller.
- a. hbuld cause an opening signal to be generated. If "SIM PRESS" is selected, the du::ps will open and try to brig pressure down.
- 2. Fails low
- a. Stea:n dumps wuld not actuate in pressure nede.
Rev. 00/01-02-86/GN
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( ) 1 PT You have been instructed to swap the power. supply to MXA from LXA to LXF. What procedure would be used to perform the swap without losing power to MXA? (select one)
A. Place both MXA supply bkrs to " auto" and then open the feeder from LXA allowing LXF feeder to close in.
B. Place only the LXA feeder in auto, close in the LXF feeder allowing the LXA feeder to open C. Place both MXA supply bkrs in " manual" and close the LXF feeder. LXA feeder will tip open D. Leave both feeders in their normal position and close the LXF feeder, LXA feeder will trip open.
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ANGWER: C.
REFERENCES:
KSA -062-7 (3.2/3.3)
EP Lesson Plan OBJECTIVES: ENPF: N/A ISS:10 RO:10 SRO:10 Feb. 19, 1985 Page EL_EP_14
.~
(REF.-4)'
ev .
( ) 1 PTS While at low power level, steam withdrawal from the S/G must be slow. What is the basis for this precaution? (Select One)
A.- Prevent receiving a high steam line flow MSIV closure.
B. Prevent the core from going critical.
C. Prevent reactor power from decreasing.
D. Prevent reducing Tave below 551 F.
s 4
I ANSWER: D 1
REFERENCES:
KSA 039000 - A1.03 (2.6/2.7)
OP/1/A/6100/01 CBJECTIVES: ENPF: N/A ISS: NA
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RO: 9,10 SRO: 9,10 1
1 Jan. 10, 1985 Page ST:1_SM_23
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ENCLOSURE 5 SIMULATION FACILITY FIDELITY REPORT i .: -
l Operating Tests Administered On: March 27, 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 's required in response to these observations.
During the conduct of. the simulator ~ portion of the operating tests, the
.following items were observed.
ITEM DESCRIPTION Pressurizer Controller is more sensitive than in control room. Alarms on Pressure minor RCS temperature changes, but does not in plant.
Controller This could indicate unrealistic changes in Tave.
Auto VCT Auto makeup is not used in plant. Operators must manually Makeup mcintain VCT level. Simulator initialized with auto makeup in service and training allows the uses of auto makeup.
_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _