ML20043A748
| ML20043A748 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/02/1990 |
| From: | Dennis Morey ALABAMA POWER CO. |
| To: | Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20042G874 | List: |
| References | |
| FNP-90-0047-TRN, FNP-90-47-TRN, NUDOCS 9005230075 | |
| Download: ML20043A748 (115) | |
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.A 2s y . J. u, rarley Nucist t Plant 141f, - P. O. Drawer 470 - ENCLOSURE:3 y-y~4-l Ashford. Alabam4 06312 -
',' : Telephone 205 899 6166 .
sAlabamaPower nsarkmienc m:vm
,;o February 2 19904
>;FNP-90-0047-TRN-1
, fTheRegional.Administ'rator,: Region?II~ '
Nuclear Regulatory Coumission: 101 Marietta.-Street, N.W.: ', l Atlanta, GA 30323- ;
-ATTN: Mr.: John Munro; The enclosed attachments provide Alabama Power Company's .. ;
- Examination Report for!the licensed.operatorerequalification written examinations given at Farley Nuclearc Plant'on January 31,L1990. y a
For. additional information' please--contact Mr. Lee. Williams:at. (205); L 899-5156',; extension 6106. , Sincerely,o ' >u D. N. Morey .//n General Manag6r-Nuclear. Plant'
. Attachments p DNM/LSW:mgr 'c :-l o ,M cc: File
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1 g i- '. i ATTACHMENTf3
-EXAM KEY MODIFICATIONS-1
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' QUESTION: R0-OPEN REF-NRC #7/SRO-OPEN REF-NRC #6 Using EEP-3 (S/G Tube Rupture)'.determi_ne the correct action to take:
reDarding'RCPs.for.the following plant conditions. A'SGTR has occurred in the 1A-S/G, causing an SI, EEP-O'(Rx Trip.or SI)'and;. EEP-3 have been completed-satisfactorily up to but not including Step 31. '
.A11-3 RCPs are. running, PZR level lis 250 .the SI'has'been terminated and -
. normal-charging and letdowniis'in service RCS pressure equals'1A'S/G:
pressure. . .RCP 18. has a bearing > upper / lower oil- reservoir lo. level alarm in, ) the RCS is within the-limits of Figure 1 and off-site power is-available. The correct response is to:.'L(Circle the correct' response.); A. Trip B RCP~ B. Trip Bland C- RCPs. [ LC. . Trip'A~an'd C RCPs D.- Trip a11L RCPs and verify adequate natural circ I{ l ANSWER: B (4 minutes)
-l 052302E002 POINTS: 1.00 a
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. QUESTION: ~R0-OPEN REF-NRC #7/SRO-OPEN REF-NRC #6:
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" CHANGE MADE:-
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.. . Keys changed'to reflect that the RCS must be within the limits of: ,
Figure 2 vice Figure-1.. ~his was made as.a pen & ink change to'all examinations during the exam when; discovered.,: , r JUSTIFICATION FOR CHANGE:~ Correct typ'ographicalierror. , s
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FNPN-EEP-3 b GDIERA'IOR WBE RUPWRE Revision 8 z
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Step- , Action / Expected' Response. Response NOT_Obtained' I l. I i 1
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31.4.2 -Seal leakoff flow within Figure 1 limits. _FR-154B'
. _FR-154A-31.4.3: Seal differential pressure' greater than 200 psid' .
_ PI-156A (155Ai 154A)- 31,5- Check sufficient RCP oil. 31.5 Do NCYr run RCP(s). without --
~ level.' ,
'sufFeient oil. -
_ RCP 1A (B,C) . BEARING UPPER / LOWER
' OIL RES LO LEVEL alarm (H-71, H-72, H-73) '
clear
- 31.6 Check RCS within Figure 31.6 'Do NOT run RCP(s)1outsideE limits. tFigure 2-limits.
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,31.7 Offsite power and all above 31.7 Verify all RCPs trippeds support conditions-available and adequate-natural for at least one RCP, . circulation ~as;follows.
RCP _1A tripped _1B tripped. _1C tripped a q
************************************************we' J CAUTION On natural circulation, RTD bypass ;
manifold temperatures and associated-interlocks are inaccurate,
************************************************** i 31.7.1~ Steam generator. pressures 1 stable or trending down.
_PI-474, 475, 476 for SG 1A i
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PI-484,'485, 486 for SG la _ PI-494, 495, 496 for SG 1C i t t t t t + 1
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O OL QUESTION:- R0-OPEW REF-NRC #17/SRO-OPEN REF-NRC #18 L Unit One is operating at 100% power when annunciator M71 " FIRE" ist received.' The unit operator reports that.the main control room fire alarm-panel. indicates " AUX BLOG 121' EAST SIDE" is alarming.- The rover is dispatched:to the Pyro panel to investigate.: The rover reports that? fire detection zone "1A-35 ELEY.;121'" is in alarm and will not reset. A. What _ room (s) by number must. be. investigated to determine:the cause:of the alarm? B .~ What. room (s) by number are Technical Specification applicable?J ,
- C. - What room (s) by' number are Appendix R' applicable?.-
4 t D. Is/are the affected area (s): covered by an' automatic. sprinkler system? Ll ANSWER: (5 minutes) A. 205, 207, 208, 209, 222 (.1 each) B. 207, 208, 209 (.25 each) C. 207, 208, 209..222 (.25 each) D. ' -Yes (.25) q i
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=i 052521ET1003R POINTS: 2.50 I a
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(i j' o o - QUESTION: R0-OPEN REF-NRC #17/SRO-OPEN REF-NRC #18 CHANGE MADE:
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Keys answer was expanded to: B. 207,208.209,222(1875each) JUSTIFICATION FOR CHANGE: Answer key was modified to include room 222 in part B'such that all Technical Specification applicable rooms-are included for full credit. Table 1 of 50P-0.4 lists-rooms 207. 208, and 209 as being applicable, a Table 3 lists rooms 208, 209, and 222 as being applicable.~ The
-complete list of all Technical Specification applicable rooms would then be rooms 207, 208, 209, and 222. Proportional grading applied to key. ;
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. (]) {)TCblo1 0000000000000000000oo00c00000000000000000000000 > i CAUTION The required fire watches specified !
in Table 1 assume that there are NO i
- c. inoperable. fire barriers.for the ~~
j affected fire detection zone. Fire ! watch requirements may be more l restrictive if a fire barrier t'r a Knowool in the affected zone is l-inoperable. oj
*********************************************** :i FIRE DETECTION ZONE FIRE WATCH REQUIREMENT.
System 1A-34A Elev. 121' j Aux. Non-RCA , E Room No. .202 - Communication' Room Hourly ** l
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~ System 1A-348-Elev. 121' ;
Aux. Non-RCA' t Room No. 202 - communication Room Hourly ** l ; i System 1A-35 Elev. 121' Aux RCA i Room No. 205 - Corridor 'None , 207 - Corridor Hourly ** - L 208 - Corridor Hourly *t- : 209 - Corridor Hourly ** '
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222 - Corridor Hourly
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- Appendix R requirement
**Pach Spec and Appendix R requirement '
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TABLE 3 1 i UNIT ONE I COVERAGE REQUIRED FOR INOPERABLE i SPRINKLER SYSTEMS 4 TYPE OF SYSTEM ROOM NUMBERS / TITLES TIRE WATCH , 1A-21 167 Storage' Room Hourly +*
++1A-23 .227 vertical cable chase Continuous i El.-1288-0" l 300 vertical-Cable' Chase Continuous **,
l El. 141'-0" 465 vertical Cable Chase Hourly , 1 El.1155'-0" , 466 Vertical Ca,ble Chase Continuous ** El. 155'-0" 500 Vertical Cable Chase continuous ** El. 168'-6"
++1A-25 161 Corridor Continuous **
162 Hallway , Continuous **. j 163 WDS; Control Panel Rm Continuous ** 164 L& HS Tank Room Hourly **- 7 168 CDT Room Continuous **
++1A-27 185 CCW Hx Room Continuous **.
. ++1A-35 208 Corridor Continuous **
209 Hallway Continuous ** 222 Corridor continuous ** 207 Corridor Hourly ** x o Rev. 7
+ Combustible Storage Area.
++ Inoperable when the MASTER OVERRIDE switch is in OVERIDE.
- Appendix R Requirement b, ** Tech Spec and Appendix R Requirement-1 of 9
E, RTYPE: K2.04 (Individual) ._ RTYPE: K2.07 (ifEY)
. TRAINING DEPARTMENT EXAMINATION NAME(*RGVR): Y GROUP: OPS
*DATE: 01/31/90 EXAM NUMBER: SRO OPENREF NRC EXAM TITLE: NRCMERO 'OPEN' REFERENCE" TOTAL' POINTS:
22.00 (*XRET). INSTRUCTIONS
- 1. This is a Rd: hour examination.
- 2. Point value for each question is-indicated in the ques-tion 'neader.
- 3. Answer all questions:
((] On a separate paper. ([]' On the answer sheet by circling or marking the cor - rect response or filling in the blanks. (() On the same page.as the question. .If extra room is needed, use the reverse side of the previous page or use extra paper.
- 4. CHEATING OF ANY KIND IS STRICTLY FORBIDDEN. ANY INDI-VIDUAL CAUGHT CHEATING WILL AUTOMATICALLY FAIL THE-EXAMINATION-AND DISCIPLINARY ACTION WILL BE TAKEN.
- 5. ALL WORK DONE ON THIS EXAMINATION IS MY OWN. TO MY KNOWLEDCE, I HAVE NEITHER GIVEN NOR RECEIVED AID.
FURTHERMORE, I WILL NOT. DIVULGE THE CONTENTS OF THIS EXAMINATION TO ANYONE ELSE WHO MAY TAKE IT. EXAMINEE'S SIGNATURE
/
EXAM GRADED BY: PREPARED BY: // GRADING / MATH REVIEW BY: APPROVED h h Trainlgtl Masidifger/ Supervisor
- INDEXING INFORMATION 2/24/89 r
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! 3 L, 1 [. w, h 0521017"t1042R Points: ' 1.90- Question Number: 1 d , 1 L
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Given the following Unit !I pitit conditions:
- ~-:PER is solid.
Tavg is being maintained constant at 150'F by operation of.. ,
, all three RCPs and RHR train "A," which is operating in the-4 g- cooldown mode.-
- 14w pressure letdown-is. established on "B" train RHR 'with HCV-142 full open and all three orifice isolation valves -
.open..
Seal. injection to all three RCPs la established at - 8 gpm/ pump.-
. - Letdown flow is 120 gpm. ,
- Chkrging flow is'.115 gpm. , ,
m Operators 'are attempting to stabilize pressure "at 400 psig. Which of-the following would be the rm ult of. placing POV.145 h in manual with no further operator' action?' (Circle the cor l-l rect response.) 1. l A. VCT level would increase until LCV 115A diverted.. B .' PRT level would increase, potentially damaging the rup' ture discs. C. =RCP minimum #1 seal differential _ pressure would be lost. D. RCS pressure would remain. stable. $ t.NSWER: B. (5 minutes)- l l ': v K I' _J
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. .1 g >052108DT1017R Points: 1.00: Question Number: 2 i e 1
-i Which:of thh following conditions.would PREVENT:tho' ,
, i manipulator crane trolley:from moving, iAll interlock l 1
;bypassIswitches are in OFF.. (Circle the correct' response.) !
'A.- -The control switch for.the hoist is stuck in-the raise < D position i e _
The. gripper tube'is.in the up disengaged position and-B .1 i
'the. gripper is. disengaged. j a: ,
C. The pipper tube;is fully gip and the. gripper disengaged' ,
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D.. The bridge is in,the-upender area < '
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'7 ANSWER: A. (5 minutes) l
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- l 0523028007 Points: ' 1.00
-Question Number: 3 f I
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.i A tube rupture is known to exist in'the A S/G based on pre SI- :
readings. The level in the A S/C is 15% narrow range and'the-levels in the B and C S/G are below the narrow range j indicationl AFW flow to'each'S/G is'350.gpm and all'threci ! t AFW pumps are running. EEP 3 is,in progress and has been- o- ,. j i completed satisfactorily upito but not including Step 4 , !
.e Determine the correct' response to the'aSove'condit' ions. ,
(Circle the correct response.) I A. Throttle TDAFW and MDAFW'to the B and C'S/G to maintain
>395 gpm, stop feeding-the A S/G. ,
, 1 B. . .Stop the TDAFW and throttle MDAFW to the B 6.C S/Gs ton i maintain >395'gpm, stop feeding-the A S/G.~ .
r C. , Throttle TDAFW and MDAPW~ equally to all'S/GsLto' maintain
>395 gpm..
j s D. Throttle TDAFV and MDAFW to any value, the 15tilevel inc . O the A S/G meets heat sink requirements.,
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I ANSWER: A. (5 minutes) j l ! l-I i i i 1
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j L' 052302808031 Points: ' 1.00 Question Number:: 4: . i
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-A SCTR exists, which resulted in an automatic SI' actuation on
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- pressurizer pressure.. Upon' completion of EEP 0 stepf.23, the' l
. operator observes the;"B". pressurizer safety. valve full open?
l and an uncontrolled level. rise'in'"C" S/G. : Select the- -;
- i correct procedure path from the following. ^ kcirclethe '
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'EEP 0, EEP 3, EEP 1,?ECP 311 ' '
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, h l~ B. EEP Or EEP 3, ECP 3.1. ' -
(= C.. EEP 0,' EEP 3 EEP 1, ESP 1,2
'D. ,EEP 0,;EEP 3, ECP 3.2 l- ;
ANSWER: B.-(4 minutes) i L l l, .* a f i
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t i , 052302E001 Points :-. 1.00 Question.Oumber:- $ w ,
't A.S/G tube' rupture has occurred.. All steps of EEP 0-(Rx Trip: - - -
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'or Safety Injection), and EEPf 3 up to, but not including, '
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. . 1 step 14 have been accomplishedi iThe RCS is. cooled down to ' <
.the temperature required for ruptured S/Gl pressure. All RCPs -.; . f are running.c . Due to a failure of an A0V, : instrument air.'is- ::
?not available to the CTNT. JRCS pressure reduction is.,the ,
next major step, .
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i ';s 4 After evaluating the above plant conditions, determine the' -l
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l1 required: course-of action in accordance with EEP 3, Restrict' ,
.1 your answer to those items in the procedure.- .
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s ANSWER: Go to ECP.3.3. (4 minutes)- ! s
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go , g 052302E002 . Points: 1,00 Question Number: 61 Using~EEP 3 (S/G Tube Rupture) determine the correct action y to .take regarding RCPs' for the following plant conditions.
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A SGTR~has occurred.in the 1A S/0,-causing an St, EEP.0 (Rx> E Trip'or SI)iand EEP.3 have been completed satisfactorily up to.but not including step 31. A11 3~RCP are running,;PZR' level is,25%,' the SI has been terminated and normal charging p and letdown is in service,,RCS pressure. equalsjlA S/G pres - , sure. RCP 18 has a bearing upper / lower oiltres'ervoir lo , 1
- 2. '
level alarm in,'the RCS is within the l'imits of Figure ,F'and' , off site power is available. "The correct response:is.to: (Circle the correct response.)} , A. . Trip B RCP., ' , B. Trip B and C RCPs. s
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C. Trip A and C RCPs. D. Trip all RCPs and verify _ adequate natural cire, j
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ANSWER: B. (4 minutes)
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t , t I- -i 052302F01043 Points:: l'.00 - Question Numbir 7 , t
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n m Which of the following cohditions would requiro entering s t: .
, o jl M< - PRP.P.1?' (Circle.thel correct response.);
. A. Cooldown < 100* in 60 min.,; temp.250', press 520 psis: ;
, B.- Cooldown < -100* in 60 min. , ^ temp ' 250'~, press 350 psig - 'i l'
O., Cooldown > 100in 60 min., temp 275'; press 1800 psig (l
. D. Cooldown 100in 60 min.,ttemp 275',-press;350 psig- .
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- 052302F03053 Points: l '. 00, ' - Question Number: 8
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;\ ,- \ RCS cold' leg temperature is now.260', -
Two hours agoL the-reactor was critical at 1004 power; one hour,ago', cold leg , t temperature.was 350'.- Procedure FRP P.1 has been completed up to step 19. . Which of the following_isL the' correct-
. responsetotheremainingstepsin-thehrocedure:1 -(Circle the i correct .. response'. ) ; - g; A.' Soak required;-remain in this procedure until soak is completed. Perform no'other actions.
B. ' Soak required'; remain in this* procedure until soak is,' completed and required 100'/hr cooldown is; commenced.-
" C. . Soak required; go to procedure"and step in effect.
D. No soak required; go to procedure and-step,in effect.. 4 t ANSWER: C. (5 minut'es) 6 E
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[7 052520FT1001R Points: 1.00 Question Number: 9 With the plant in Mode-3 at 547', a sustained loss of = instrument air is in progress on Unit 1. 'Due'to problems-with Unit 2 air system, no air from Unit 2 can be used for Unit 1. All' other steps of AOP 6.0 have been completed. satisfactorily.with the exception of restoration; the charg ing pump suction is aligned-to the VCT. Based on the above
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conditions, which of the following statements is true concerning PZR level and VCT level?. (Circle the correct response.) A. -VCT 1. iel and PZR level increasing , B. VCT level and PZR level steady . C. VCT level decreasing and PZR level ~ increasing 4 D. VCT level stable and PZR level decreasing > i l ANSWER: C. (5 minutes) I L i 1
c = i s t 7 4 1 5 052520NT1002R Points: 1.00 Question Number:: 10-
.a With'all systems in' automatic'and all. lineups normal 'the
- plant is at 100% power;' equilibrium conditions. .A'boration
.is in progressitojallow' stepping Bank D rods out.to 228~
steps. -A & B group pressurizer. backup heaters are on to , borateithe - pressurizer. , An'instrumentf failure has just L ' occurred;that caused a penetration room isolation signal to occur. Which'ofLthe following would occur as a result, , assuming no. operator action? '(Circle the' correct response.) -"
'A. Pressurizer pressure, increase until a reactor, trip occurred'on high pressure B. Pressurizer pressure to increase and stabilize at 2335:
on PORVs C. ' Tave to increase due to the' reduction in boration flow i I D. - Pressurizer-' level decrease due totthe reductionlin- <
- charging flow ANSWER: A. (5 minutes)-
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a i 052520NT1010R.' Points'! 1.00: -Question Number: 11 , u- s
-l A refueling accident has occurred in the Unit I spent fuel !
, 7 pool, res'ulting in a,large release of contaminants from~the~ :l damaged assembly., The following plant conditions also exist:
R 2, 7 .and 27A & B indicate pre-event readings. .c { R 5 alarming. " R 10 trending up but not in: alarm.
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-R 14 and 21 trending'up but not in alarm. ]
Rt 24A & B indicate pre-eventLreadings.. ] R 25A & B alarming but slowly trending down. [
. 1 B 91,-B 92, and E 33 annunciators not alarming. <
q t LUpon evaluation of the above' conditions, youlcan~ determine [ that: (circle the correct response'):
?
A. Peak release from the assembly has occurred since R 25A 'i
& B are now trending down.
B. Spent fuel pool area release is being filtered'by;the PRF system and monitored by R-10. - ' r C. A second accident resulting in release of contaminants 5 has occurred in the penetration rooms as ev/.denced by J R 10 trending up.
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D. Containment atmosphere'has been affected'by the accident ; in the spent fuel pool as evidenced by R 14 and 21'being i upscaled. I s ANSWER: B. (5 minutes) h
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052520NT1012R points: ,1,00 ' Question Number: '12 Unit:1 is operating at 1004 power, BOL, steady state when a ' 4:
-penetration room high Ap alarm occurs as'evidencad by B.91 and B.92 annunciators in' alarm. Only one train of penetra-tion room filtration equipment is,able to be started to-reduce pressure in the penetration-room.. No. fuel'aovement or movement of loads in the SFP:are scheduled or are in prog-ress.- Instrument air-to containment is isolated. 'Pressur-iter. level is slowly trending up with the present level.
indicating 654 NR level. Based;on the above conditions", what; Technical SpecificationLaction is required? (circle'the' correct response.) + A. Restore inoperable system within.7-days or be:in at least hot. shutdown within;6 hours.. O B. Restore inoperable system within 48 hours or be in at least hot standby within 6 hours. C. Bestore inoperable system within 7 days or be in at least cold shutdown within 30 hours.:
- Be in at 1 cast hot. standby withLthe reactor trip break
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D. ers open within 6 houra.' ANSWER: D. (Reference T.S. 3.4.4)
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~052520RT1001R- Points: 1.00 ~ Question Number: . . 13- ,
i a i' Unit l'is' shutdown for refueling.with fuel movement in l progress. The audio count rate selector switch is-selected , to H:11 and the speaker' selector. switch 'is 'in NORMAL .i (amplifier.1 supplying the control room speaker and amplifier. j 4- t 2-supplying the' containment speaker). An instrument power 'l fuse blows'on N 31. ~The appropriate' response would be to: 1 (circle the correct response.) q A.- Continue fuel movement,. monitoring theJremaining NI j channels, select N 32 on'the. audio count rate selector.) . B. Stop all fuel movement,_ monitor the remaining NI chan j nels, select N 32 on the' audio count rate selector, J repair N 31; and then continue-fuel movement.' ! C. Continue fuel movement. monitor the remaining NI chan- ! nelsi select N 32 on~the audio count rate drawer,-and- ; then repair N 31'. ; D. Stop all fuel movement. monitor thel remaining NI chan- ! nels, select N 32 on the audio count rate selector, j continue fuel movement, and then repair N 31. ANSWER: B. (5 minutes) f d t
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g i. 052520RT1003R Points: 1.00L - Question Number: = 14 (.
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Unit 1.is operating at 1006 reactor power with Bank D rods at i 218 steps lwhen.a failure of "C" inverter occurs, deenergizing' theC" 120" vital AC distribution panel. : Actions-are--
. initiated in accordance with the appropriate'ARPsLand.the Rover is sent to-transfer 120V vital AC distribution panel Cj ,
to the alternate power supply.. A. How will the operator's ability-to manually; position control rods in the outward direction be affected ~* during the time the.120V vital AC. distribution. panel is deenergized? (.25)' i B. How will the operator's ability to manually. position control rods in the inward direction be affected'during
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the. tine the 120V-vital'AC distribution panel $4-deenergized? ( 25) C. . : What is the reason for any adverse effect,'if any,-on' the' operator's' ability to manually position control rods'? (.5) ANSWER: (6 minutes) A'. Manual rod withdrawal is inhibited (.25). B. Manual rod insertion'is not affected (.25). . C. Hi flux rod stop (N 43 deenergized).(.5). i U c d J i
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.052520RT1024R Points: 1.00: Question Number: ~ 15 A' Unit'One.heatup is in progress following a' refueling. ,
outage in accordance with.UOP 1,1,' "Startup.of Unit from-Cold Shutdown to. Hot Standby;": Keff isi.975,.RCS temperature is 348' F, and the shutdown banks are.being withdrawn. State
~
'the nuclear ins'trumentation channel (s) by' instrument number,.:
that'is(are) required to be operable based on the above.plante conditions in order to enter the<next higher mode. , ANSWER:' (.25 ea.) (5 minutes) N 31 & N 32 r N 35 & N+36
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is 1 052521CT1001R Points: . 1,00 Queseion Number: 16-Based on'the;following conditions, answer the; question below:
- Unit'in Mode 3.
- Tavg is'547'F.
- . Fire h'as occurred in the cable spreading room.
? - Fire resulted in loss of the following MCB indica.
tions and control:
- Normal charging.
- Normal'1etdown'-
-- Seal injection =
-' Control has been shifted to the_HSD panels.
Orifice isolation valve:8149A has been opened,from the HSD panel. Describe'how letdown flow rate can be determined.. Be.spe
-cific about which parameter (s) is(are) and.where the>
parameter (s) can be obtained from based on the above stated-conditions. (Instrument numbers are not required.) ANSWER: (Grader discretion required).(5 minutes) Perform a flow balance on CVCS; system to. include: Seal injection flow (,2) from penetration room indications ( 2). Charging flow (.2) from HSD panel indications (.2)- PZR level (.2) from MCB or HSD panels (not required for full credit) VCT level-from MCB or BTRS chiller room (not required for fall credit) f .. y ~.
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i 052521DT1001R- Points: 1.50 Question Number:- 17 : i i The control room has been evacuated and is inaccessible:due .; Lto's fire in'the control; room.- The plant-was tripped and d control'has'been' established at the=HSD panels, 'The WR Te instrument _at the NSD panels has failed low. Tlie'following. , j stable HSD panel indications exist:- ; S/G 1evel A 626 ' B 634'~ C 62%- l S/G press A 910 psig. B 910 psig C 910 psig j" Charging flow 70~gpa-PZR press 2260 psig ' ' ; PZR level 25%,. - WR Th 565'F: WR Tc Failed low <; , CST > 11' feet ' Neutron flux 300 cps ! A. Using the'above AVAILABLE HSD panel indications,' state ! what indication (s) would be used to determine that natural circulation:is established, per the controlling . procedure for thisl event. s */ i s ? B. State if natural-circulation is' established for the above plant conditions. If ANSWER: (5' minutes) i A. WR T B, Yes,h-(.5) andcire natural S/G'Tsat (.5)~. is established'(.5). g j j I
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s 052521ET1003R- . Points: 2.50. Question Number:: 18 4 . Unit One is operating at 1006 power when annunciator M71 L
" FIRE" is received. The. unit operator reports;that th6 main F- control-room fire alarm panel indicates " AUX BLDG 121'; EAST .
SIDE" is alarming." The' rover is dispatched to'the Pyro panel to investigate. The rover. reports that fire detection zone "1A-35 ELEV. 121'" is in' alarm and will not_ reset. A .' What room (s) by number must be investigated to determine the cause of the alarm? B.. What room (s) by number are Technical Specification applicable? , C. What. room (s) by number are Appendix R applicable? D. Is/are the affected area (s) covered by an automatic. sprinkler system? ANSWER: (5 minutes)~ A. 205, 207, 208, 209, 222.(.1 ea.). B. 207, 208, 209 ', ^; . . )i 12X C. .207, 208, 209, 222. (. 25 ea.) f,/f 7(eh
.D. Yes.(.25)-
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- e a 053002A01004 Points: ' 1'. 00 -Question Number: 19 Evaluate the following plant conditions'in order.to classify.
thelevent: s. Bypass and Permissive Panel ' SAFETY. INJECTION ACTUATED" light is ON
'SI'. FLOW TO COLD LEG HDR, FI 943' indicates 3 c ,35 x 10 gpm MCB annunciators M 41,LM 42, M 43, and M 44 are alarming'(in solid)-
S/U Transformer breakers DF01 and DG15:are tripped SJAE exhaust RR 15' indicates 9 x!105 , SJAE exhaust R 15 indicates 1 xL106 : cpm Which of the~following is the MINIMUM classification for~the. event? (CircleLthe correct reponse.)
, A.: Site' Area B. Alert C. NOUE D, One hour non emergency ANSWER:- A. (5 minutes) o
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053002A01005 Points: 1^ 00 Question Number: '20 A system operator working in Containment fell from some-scaffolding and fractured hisl arm. Health Physics personnel-report that the SO'is'also contaminated. . Which of the
.following RESI describes the required notificationsithat-should be_made. (Circle the correct response.)- <
A. Emergency Director, Recovery Manager, NRC, Security ,
'B. Operations Manageri Emergency Director,: Recovery Manager NRC, Security.
C. Emergency Director, Recovery. Manager,-Alabama. Bureau of Radiological Health, Georgia Emergency Management-Agency,,NRC, Security D. Emergency Director,: Recovery Manager; Alabama Bureau of Radiological ~ Health, NRC,;SecurityE ANSWER: C.:(5' minutes) Basis: EIP.11,13.5 EIP 17, 3.2.11 EIP 26, 5.3 a lI s+= .
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L.01/31/90 AIABAMA' POWER COMPANY p
' EXAM CRADING SHEET EXAM NAME: SRO.0PENREF.NRC' CLAS$'NAME: IJtP 89
; -TOTAL POINTS: ,22.00 DATE GIVEN: 01/31/90 STUDENT'7D / NAME: **. DRAFT ** ./ *************** DRAFT ***************
' QUEST POINT . POINTS QUEST POINT POINTS-'
0- VALUE MISSED # VALUE MISSED- ;' 1 052101FT1042R 1.00 - 1 2 052108DT1017R 1.00. -
.32 052302B007 -1.00 . ~ ~ ~
4, '052302B08031 l'.00 4
- 5' -052302E001. 1.00 .
6 052302E002 1.00 .
,7 - 052302F01043 1.00 .
~8 052302F03053- 1.00 -
9 ' 052520FT1001R- '1.00 - 10 -052520NT1002R 1.00 . 11 052520NT1010R- 1.00 - 12 *=052520NT1012R-- 1.00 - 13 052520RT1001R 1.00 -
- ~
14 052520RT1003R 1.00 - 15 052520RT1024R 1,00 . 16 . 052521CT1001R 1.00 .
,4 ;
17 052521DT1001R 1.50 - 18 052521ET1003R 2.50- . 19 053002A01004 1.00 .' 1 20 . 053002A01005 1.00' . 4
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i TOTAL POINTS MISSED: FINAL SCORE: % i t s i t 17 l.. 2 o G ,
RTYPE: K2.04 (Individual) RTYPE: K2.07 (KEY) TRAINING DEPARTMENT EXAMINATION NAME(*RCVR): KEY CROUP: *S
*DATE:'01/31/90 EXAM NUMBER: RO OPENREF.NRC EXAM TITLE: linEL n'M.~n$r#4rriOdF TOTAL POINTS: 21.00
(*XREF) INSTRUCTIONS -
- 1. This is a 2.03 hour examination.
- 2. Point value for each question is. indicated in the. ques, tion header.
- 3. Answer all questions:
((] On a separate paper. ((] ~ On the answer sheet by circling or marking the cor-rect response or filling in the blanks. [_TC) On the same page as the question. If extra room is needed, use the reverse side of the previous page or use extra paper.. 4 CHEATING OF ANY KIND IS STRICTLY FORBIDDEN.' ANY INDI . VIDUAL CAUGilT CHEATING WILL AUTOMATICALLY FAIL Tile EXAMINATION AND DISCIPLINARY ACTION WILL BE TAKEN.
- 5. ALL WORK DONE ON THIS EXAMINATION IS MY OWN. TO MY KNOWLEDGE, I HAVE NEITHER GIVEN.NOR RECEIVED AID.
FURTHERMORE, I WILL NOT DIVULGE THE CONTENTS OF THIS EXAMINATION TO ANYONE ELSE WHO MAY TAKE IT.. EXAMINEE'S SIGNATURE fld/9 EXAM GRADED BY: PREPARED BY: - GRADING / MATH REVIEW BY: APPROVED / Trainirf Supervisor Handeir/
- INDEXING INFORMATION 2/24/89
' {; sy -
4 052101FT1042R Points: 1.00 Question, Number:- -l' r 1 Given the following Unit l' plant conditions: i
'. PER is-solid.
,Tavg is' being maintained constant at 150'F by operation of all three'RCPs and.RHR' train "A," which is' operating:in'the cooldown mode.
. Low pressure letdown is established on "B" train RHR with HCV 142'fu11 open and all three orifice isolation' valves open.
- Seal injection to all three RCPs is established at 8 gpm/ pump.
Letdown flow is 120 gpm. Charging flow is 115 gpm. Operators'are attempting to stabilize-pressure at 400.psig ;
.Which of the following would be.the result.of placing;PCVE145 in manual with no~further operator action? '(Circle the cor rect response.)
A. VCT level would increase until LCV 115A diverted. B. PRT level would increase, potentially damaging.the rup ture discs. 4 C. RCP minimum #1 seal. differential pressure would be? lost.- . D. RCS pressure would remain stable. ANSWERi B. (5 minutes) y
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O.e ' ; l'.3 IIsf ' 05210$CT1045R Points: 1.00 Question Number: 2' Unit I reactor power is ' presently at 2% and holding.while 'the Unit Operator is making preparations to start uplthe IB SGFP. Annunciator L54, " AIR SIDE SEAL OIL' PUMP OFF," alarms. Upon investigation,-it is determined that the pump has. tripped on'
- overload. The DC' air side emergency seal oil pumpf did not-start automatically and would not start on a raanualfittempt by the operator. Based on thisJinformation, which.of the following is required lto be performed? (Circle the correct response.)
A. Stop the hydrogen side seal oil pump. B. Verify the' seal' oil' backup pump running. 9 C. Reduce hydrogen pressure to 5 psig.. D. Immediately trip the main. generator. ANSWER: (4 minutes)(1,0) '
- ij B. ,
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1, d a p 0523028007 -Points: 1.00' -Question-Number: '3 - Q p '
,y Atuberuptur$isknowntoexistintheA-S/Gbasedon'preSI-i
-rea'dingR 'The level in the A S/G is 15% narrow range.and.the-
.levelsJin'the B and C'S/G are-below the narrow range. ,
indication.- AW flow.to each S/G is 350 gpm and all three y d a- - AW. pumps are running. ,- EEP-3 is. in progress and has been f i
= completed'satiAfactority up' to but- not' including -Step 4.-
') ,-
Determine the correct: response to the.above' conditions,- -
.l (Circle the correct response.),
j, A '. Throttle' TDAFW and.MDAW to the BIand C S/G to maintaiti ll
>395 gpm, stop feedin6 the:A S/G. J j ,
.j B, Stop' the TDAW an'd throttle' MDAW to the B-.& 'C S/Gs; to - ;
maintain >345 gpm, stopl feeding the A.' S/G. l C. Throttle TDAFW and MDAW equally to all S/Gs '.to . maintain; i
>395 gpm; D. Throttle TDAW and MDAWito any value, . the- 15% level ini the'A S/G meets heat sink' requirements.
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l-052302B08031. Points: 1,00 ' Question Number: 4 ! i e 'l i A SGTR-exists, which resulted in an automatic.SI' actuation:on.
]
pressurizer pressure',- Upon completion' of . EEP-0 step '23, the a operator observes the "B" . pressurizer l safety valve fulliopen U Land an uncontrolled level' rise-in-
"C" S/G. . Select the
]
.1 correct procedure path _ from .the following. .(Circle the' I correct response.)
A. . EEP-0, EEP 3, EEP-1, ECP 3,1
.B. EEP 0, EEP 3, ECP-3.1 'C' i
i C. -EEP 0, EEP-3,-EEP 1, ESP-1,2 '! i D. EEP 0, esp-3, ECP-3.2 , l
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- q ANSWER: 'B. (4 minutes)'
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052302B10032~ Points: 1.00: Question Number:. 5
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A large steam break exists on the "B" S/G'inside CTMT.
~
- Select'the-correct procedure path'from the'followingi.:
(Circle the correct response.)': ' - A. EEP 0,1EEP 2, EEP l',~ ESP l'.1-B. EEP 0, EEP-1,.EEP-2, EEP-1,. ESP-1.1L
'sC
- 0. EEP 0,)EEP-2, EEP-l',, ESP 1.3' D. .EEP-0,'EEP-1, EEP-2, EEP 12,- ESP-1,3- '
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, ANSWER: 'A'. (5 minutes): D:-
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> '052302E001 Points: 1.00~ Question Number: 6'
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-:A S/G tube rupture has' occurred.' .All steps;of EEP-0 (Rx Trip-or; Safety Injection),: and EEP-3 up' to, but not-1 including,' "
step 14 have been accomplished, iThe:RCS is cooled.down1to i the temperature required for ruptured ~S/G pressure. -All RCPs.
'are running. -lDue to'a failure of:an A0V, instrument. air'is' I
not,available to the CTMT. -RCS pressure r' eduction is the'-
~
- next major step, n ,
I
- Af ter evaluating'. the above - plant conditions , , determine. the .
. required course?of action in accordance'with EEP-3. Restrict. , o , your answer to-those: items' in.the. procedure'.
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i n } i ANSWER: Go to ECP 3.3. (4 minutes) . A l ':t y i i
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052302E002 Points: l'.00 Question-Number: ;7- ls i f LUsing-EEP 3 (S/G Tube. Rupture),cdetermine-the correct: action -
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to'take regarding RCPs1for'the.following plant conditions. j s , A- SCTR .has : occurred- in the 1A S/G,' causing: an LSI, EEP-0 (REE .
~
. Trip or SI) Land EEP 3;have beenLeompleted satisfactorily up) .
.l to but notLincluding step 31. All 3fRCPs are' running,'PZR -
-level is 25%',E the SI, has been: terminated and normal' charging: q and letdown .is in service,: RCS l pressure equals: lA'S/G pres . ;
sure. RCP 1B -has a' bearing upper / lower oil reservoir lo , level alarm [inf the:RCS is within the: limits of.Figuref;and' tf , :!
.off-site power is available. The correct responseEis to: j (Circle the correct' response.); ,
3
?
t A. Trip-B RCP.
, 1 B. . Trip B and C RCPs.
C. Trip A and C RCPs. .q < D. Trip all-RCPs-and verify adequate natural'cire. ANSWER: B. (4 minutes)
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- 052302E003: Points: 1.00 Question'. Number: 8 !)
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i A'.SGTR has. occurred;' causing,an'SI. EEP-0 was completed and. ;
~
EEP-3l entered. lTheYruptured-S/G was identified as B S/G~and
. isolated. .A.cooldown:was completed from 547 degrees'to 493 < > ci o t degrees, RCS pressure 1500 psig and has not_.yet been reduce'd; , - .
t to terminate the SI,:andiflow.into the.RCS.is still through-
~
the BIT. fThe.foklowinginformation-lisreported: d . 4 CTMT pressure and radiation.levAls;are the same:as' pre-event /; readings, PZR level-is-2%, S/G A and C are.both,at saturation-press for existing RCS. temperature.(600 psig),1 B S/G 1100 Psig. , < j Based on the above.information,' state any actiSn required by~ the 'EEP-3 foldout. page. : Restrict your: answer...to foldout page ; information only.
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.i ANSWER: None. (5 minutes)(No' deduction for monitoring. activities ~ h stated.)'
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. 05230'2F01043) iPoints: ' 1.00'
; Question' Number: 9' Which of the following-conditious-would require:entiering'.
FRP-P.1?' (Circle the' correct: responses)1 , l', Cooldown < 100':in'60-min.,ytemp 250',cpress 5202psig:
'A.-
'B. -Cooldown'.<'100* in 60' min., temp 2505,3 press l350jpsig:
.Cooldown > 100* in 60 min., temp 275', pressz1800 psig-C. .
e s <D.. Cooldown > 100' in 60 min.. tempc275*,. press 350;psig;
; ANSWER:. A. (4 minutes) .,
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d 052302F03053: Points: 1.00 Question Number: 10 RCS cold: leg temperature is nov 260' - Two _ hoursfago. . , the
.n reactor;wasjeritical-at.100% power;onehouriago,Leoldleg: ,
temperature was 350'. Procedure FRP-P.1-has;been. completed upito;stepJ19. lWhich of the-following is the correcti responsetto the remaining steps'in the-procedure: : (Circle-the: correct response.) . A.- Soak required;; remain:in this; procedure until soak isL
; completed. , Perform no other actions.
B .' SoakLrequired . remain inLthis' procedure until,roakris ~1
-completed and;xequired 100*/hr:cooldown:isLeommenced.
C. Soak-required; goLto procedure?and= step in effect. 2
-D. No soak required;;go to procedure andLstep ineeffect; ANSWER: C. (5, minutes)
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]/i ,q7 y .t 052520FT1001R Points: 1.00- Question Number: 11.
- With the plantf;in= Mode 3 at 547* ,= a' sustained loss of -
instrument air-iscin progress on Unit 1. :Due to problems with Unit2; air' system, no airifrom' Unit 2 can be:used.for: .y
- Unit 1. " All other> steps of 'AOP-6.0 have been completed satisfactorily with'the exceptionLof restoration;'the:charg ,
'f ing pump" suction 11s aligned to .th'e VCT. ' Based un the' above conditions', which of'the following statements in true; ,
concerning PZR level and VCT level?J_(Circle' the. correct i 1 response.)- s j A .- VCTlevel'and'PZR-level; increasing, O B. .VCTilevel and PZR level steady ' h C. _VCT level ~ decreasing: Land PZR-level (increasing; D. VCT ievel stable:and PZR level'.decreasingi ANSWER: C. (5 minutes)l i ti
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-- 7 ll ~052520NT1002R Points: 1.00 ' Question Number: 12 j
[ With all systems in automatic and all lineups. normal,'the-
, . .1 L: 1 plant in-at.100% power, equilibrium conditions. A boration'
' u is-in progress'to allow stepping Bank D rods.out'to-228
, i L .. steps. :A 6'.B' group pressurizer backup. heaters.are.on to.
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1 borate the' pressurizer. An instrument failure;haslJust ,
- l. occurred that caused a penetration roomIisolation' signal-to~ [
0 l , . occur. Which of.the following would-occurfas a result, }:' assuming.no operator action?- .(Circle the correct response.').
' A .' ; Pressurizer pressure increaso unti1~a!rt>ctorttrip:,
- occurred-on'high pressure-
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s , si ? -Bi : Pressurizer' pressure 1to. increase anm .tabil'ize at 2335.. i L on-PORVs' i C. Tave to increase due to'the reduction in boration; flow ~ g
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l .D. Pressurizer level decrease due to:the reduction in l+ l charging' flow ' L ,i l . l < ANSWER: A. (5 minutes).
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7___ m [. h I 052520NT1010R- . Points: I l.'00 Question Number: 13 6, t A refueling-accident has occurred in'the Unit lispent~ fuel, pool, resulting in a-~1arge release'.of contaminants from the o c\ I damaged _ assembly. The - following plant con'ditions also exist:
'. ~
- R-2,- 7, and 27A & B indicate pre-event readings. '
1R-5 alarming.. , R-10 trets.tng up-but not in alarm.- 3 i
-R.14(and21'trendingupbutnot[inalarm.
3 R-24A'& B indicate pre-event, readings. ; R-25A; &1B alarming but ' slowly,. trending . down. ,\ ; j: y
'B-917 B-92,fand:E-33' annunciators;not alarming.- .I ;
Upon evaluation of the'above.codditions,J you-can determine. , f:; H that: [;'(Circle the correct response.)! ,' A. ' Peak; release from-the assembly'has occurred since R-25A :- { 9
& B are now' trending down. '
l 1 B. Spent fuel pool area-release-is:being filtered lby.the- . 1 PRF.. system and monitored by.R-10. --i C. i.A'second accident resulting in release of contaminants. '
. has occurred in the penetration roomsJas:-evidenced by 3
.R 10 trending.up.
D. Containment' atmosphere has been affected.by the accident' - in the'~ spent' fuel pool as evidenced by R.14:and 21'being upscaled. . d
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_.. {} t r-. 052520RT1003R' Points:;.1'.00 Question Number: -14~ ! s i 1 1;; _
-Unit 1'.is operating at'100% reactor power.with Bank.D rods.ati .. 218 steps when a failure'.of~"C": inverter-occurs, deenergizing yd
- thel"C"1120V vital-AC distribution panel. ' Actions arei k
3 d3 initiated in accordance-withlthe appropriate ARPsiand-the ,- 1
-Rover'is sent toitransfer 120V vital'AC-distribution' panel _C1 to the' alternate power' supply.
c'c: j A. How-will theLoperatorfs ability to; manually position '
~,\. 'd c\-- :n control rods in the outward direction be affected' V a
during the time;the 120V. vital AC distribution-panel c >;
'is deenergized? (.25)
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How will the operator's ability'to1 manually' position- x- i D __ control rods in the inward direction-b'e affeeted during- -
,. .the time the 120V vital AC= distribution panel is
'deenergized? ( 25)
L 6 I_ > L< - C. What is the reason for any. adverse-effect..if~any, on' N L the operator's ability to manually position control L rods? ( 5) ' ANSWER: (6 minutes) i A. . . ? B. . Manual rod withdrawal-is inhibited-(.25). L C~ Manual rod insertion is not affected (.25). > ! Hiaflux rod stop (N-431deenergized) (,5). I I: ?
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l J .- f r-- H l 1 052521CT1001R Points: -1,00 Question Number: 15'
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i , Based on'the following conditions, answer the-question below: 1: 1
-Unit in Mode 3; ~
x
-- - Tavg' is .'547'F.
Fire has" occurred in the cable spreading room. :i Fire.resulted in loss of the following'MCB;ihdica;\ h tions and control: -e 1 S
- Normal charging ,
. Normal lAtdownU'
..e s
-- Seal' tr.jection -
Control.has been shifted to the:HSD panels. ' Orifice isolation valve B149A has been opened from the HSD! panel:.
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Describe how' letdown flow rate can be' determined.~ 1 Be-lspe . d 1-cific about whichl parameter (s).is(are);gud where-the
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parameter (s) can be obtained from based on.the'above' stated:
] t conditions. (Instrument numbers are not' required.)
ANSWER: (Grader discretion required)-(5 minutes) 1
~i il Perform a flow. balance on CVCS syitem tolinclude: _o j s.
Seal injection flow (.2)' from pene'tration room indications j (.2). T -I Charging flow (.2) from HSD panel indications (l.-2) , PZR level (.2) from MCB or HSD panels (not-required for full.
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credit) ' i VCT level from MCB or.BTRS chiller room (not required for- i full credit) .
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, 1 052521DT1001R' Pointsi 21.50 ; Question llumber: 161 y-
, The control-room has been evacuated'a'ndris inaccessible due- q
^
to a, fire in.the control l room. 'The p1' ant'was' tripped and- > control has been established =at,the HSD panels ~. The WR TcL
.i instrumen' tat.tho'HSDpanelschas;failedlow, 'The following
+
- stable lHSD panel' indications exist:
S/G 1evel _ A >: 'i n ' . LB-63%> . C-62%. s S/G. press 3 .cA 910'psig. EB-910 psig. C-910 psig: ' az
- Charging flow 70'gpm: '
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.PZR press 2260 psig- i-N. PZR level 25%.
WR_hT -; 565'F WR Te~ Failed low CST..
> 11:iect' " '
Neutron flux 300 cps _ tt ' A. Using the above--AVAILABLE HSD panellindications, state
-what-indication (s) would beLused to: determine that.
natural circulation is established liper 'theico'ntrolling - ?!
. procedure forlthis event. j Li 1
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B. State if natural circulation is established for.the ! above plant conditions.- 9 J !:f l 1< ANSWER: (5 minutes) .l - A. WR Th (.5) and S/G T sat (.5). i B. Yes, natu al cire is established (.5). d
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f 1052521ET1003R' Points: 2.50- ' Question Number: 17 e i . t
, : Unit One is; operating at 100% power when annunciator M71- L
; 1" FIRE" is received. 'The unit operator reports that the main f
control room fire alarm' panel indicates " AUX BLDG: 121' EAST- l SIDE";is alarming..<The rover.is dispatched tcithe; Pyro Lpanelito investigate. The. rover. reports-that i tire'detectioni k a , zone "1A-35 ELEV. 121'" is~in alarm.and will-inot reset.
-A. What room (s) by number must be inves*igatedoto determine the cause of the alarm?. 1
;j B. What room'(s) by-number are' Technical Specification 1 i
- - applicable? 7 i
C. What room (s) by.numberiare' Appendix R'applidable?= D. Is/are the affected area (s) covered ^by.an automatic-sprinkler. system?' . g 1 ANSWER: (5 minutes) * .! A. 205,'207, 208, 209, 222 (.1 ea.) B. 207, 208, 209 ( .25 ca. ), JA.?. ( , / 6*7f A.].- ; C. 207, 208, 209,-222'(.25 ea.) i D. Yes (.25)
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052530BT1045R ~ Points: 1,00 Question Number: >18 , i
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-Unit One has ' experienced a loss ~ of -reactor- coolant and EEP 1 -
, is-in progress 'Using the following data ; determine the~ l
. correct-referencefpower setting'.for the Post-LOCALH2 I
~
1
.Recombiner. ' '4 Pre-LOCA Containment conditions..
,e: -Tempebaturei90'F- {
- c. -Pressure O psig
. Post-LDCA Containment conditions JTemperature.120*F- c
. Pressure 8.psigL
, ' ANSWER: ;(1,0)~(4. minutes). ;
1 61 +/-f2 kw (Figure 1, EEP-1) . i c
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.052530BT1046R Points: 1.00) Question Number: 19.
c Atstep.1'ofEEP-1-[(Loss!ofReactororSecondaryCoolant),.
~
..q the STA reports the following'information:
-Adverse CTMT^ conditions. exist and:arefbeing monitored. -RCS 4
. qs pressure is 1250 psig.: liW'T S level is 21' feet.= Core-exit '
.h li .
. .. .I
.: thermocouple temperatures'are 680'F. :Subcooling monitor by,. $
T
-core exit thermocoupleslindicate's 50subcooled. -SG "B"- '
"; i level- is. going, up ' faster than ;"C"1or..."A" SG, but R-15s , ,
R-60s,-'and R-23s are not in alarm. AFW flowzto all SGs is~ .,
>the same.- ij
- 1
~
1 State the action (s)-required. Restrict your answer.to-- .,
- 1 foldout page information~only. l
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.l t ANSWER: (5' minutes)- . u-4 Verify miniflow valves.= ..shut (.5) , 1 Go to EEP-3 (.5) t (No deduction:for monitoring activities.-stated.')
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4 s _- 7g-f01/31/90l- ' ALABAMA'. POWER COMPANY.= c , EXAM GRADING SHEETJ e i
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- EXAM NAME: RO.0PENREF-NRC CLASS NAME: LRP-89; 1 TOTAL POINTS: 21.00 DATE GIVEN:= 01/31/90 STUDENT ID~/ NAME: ** DRAFT **!'/ ***************. DRAFT ***************'
.y
-QUEST POINT -. POINTS QUEST POINT POINTS >
.C' VALUE MISSED # VALUE' MISSED- i 1 .052101FT1042R- 1.00_ - '
2 - 052105CT1045R. 1.00 - 1 3 -052302B007 .
'1.00 ;-
4.- 052302808031: 1.00 : 5 -:052302B10032 <1.00- .- __ 6 '- 052302E001- ;1.00- -
'7 - 052302E002' 1. 00 '- -
052302E003 1.00. .: 9 --052302F01043- 1,00. - 10 - 052302F03053 1.00 11~ 052520FT1001R l.00 - 12 - 052520NT1002R 1.00 -
'13 052520NT1010R 1.00 .
~
.14 - 052520RT1003R- 1.00 7-15 - 052521CT1001Rt 1.00 - '
16 - 052521DT1001R 1.50 - 17 052521ET1003R 2.50 - 18 - 052530BT1045R l'00 -- 19 -052530BT1046R 1.00 - *
, was e E
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e _ TOTAL POINTS MISSED: FINAL SCORE: %. t r 1
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-a RTYPE: K2.04)
(Individual)~ RTYPE:- K2.07. JKEY) TRAINING DEPARTMENT' EXAMINATION
- NAME(*RCVR):. _- GROUP: ' OPS 7
*DATE: 01/31/90 EXAM NUMBER: SRO SS ABN NRC' EXAM TITLE:~ 14dEC./ c:ltSO " ANa8}AlfSTAtic TOTAL POINTS: 13.50-
-(*XREF)'
INSTRUCTIONS. 1. This is a ji 0 - hour examination. ,
.2. Point value for each question is indicated in the-ques.
tion header. 3._ Answer all questions:
.[2] On a separate paper.
((] :On the answer _ sheet' by. circling or marking the cor-rect response or filling inithe blanks.- ( (E) On the same page as the_ question, , If extra
- room is' needed', use-the reverse side of the previous page- '
. ]
1 or use: extra paper. i
- 4. -(.) ,
CHEATING OF ANY KIND IS STRICTLY FORBIDDEN. ANY INDI- o VIDUAL CAUGHT CHEATING WILL AUTOMATICALLY FAIL'THE d EXAMINATION AND DISCIPLINARY ACTION WILL BE TAKEN.' i ! i
- 5. ALL WORK DONE ON THIS EXAMINATION IS MY-0WN. ' TO - MY ~ !
KNOWLEDGE, I HAVE NEITHER GIVEN NOR' RECEIVED AID. .. FURTHERMORE, I WILL NOT DIVULGE THEiCONTENTS OF THIS - , l! EXAMINATION TO ANYONE ELSE WHO MAY Tt.KE 1T. EXAMINEE'S SIGNATURE f EXAM GRADED'BY: PREPARED BY: _
- 2 GkADING/ MATH REVICW BY: APPROVED B W Trair.ttf Menger/ i Supervisor
( l
- INDEXING INFORMATION 2/24/89 4
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' STATIC SIMUIATOR EIAM SCENARIO-4 2.tTE 900131 PREPARED BY R. C. Lullina SCENARIO NO SS AhM1.NRC IC NO 7 EVENT TYPE ARNORMAL (AOP19-1.SCN) - +-
- TASK HO. TASK DESCRIPTION CRO-5033 Perform corrective' actions in response to a q
-malfunction of-the rod control system.
CRO-5379 Apply action statement of Technical Specifica . tions'. j 1. i SCENARIO DESCRIPTION j 1 Initialize at 1004 power,-BOL, with rods in manual.= Initiate-- .. :- - - 1 a dropped rod malfunction with no reactor trip occurring or. ; j required. .
'j
-i SIMUIATOR SETUP j
- Initiate MALF CRF-15A, stationary coil,Erod F6L
- Acknowledge.all annunciatore.that alarm and/oriclear-
- A11ow 15 minutes run time to stabilize-Tavg,ipressure,Jetc.- '
-(900 sec)
- FRZ simulator
- Initiate-exam EQAld
- 1. Determine the correct method for restoring RCS Tavg;to.
_ program value. . ] jl CRO-5033'S/K 240122020405'K/A 000003EA1.05'4'.1/4'.1"
- 2. Determine the reactivity worth of a-dropped rod. 1 CRO-5033'S/K 240122020430 K/A 000003EKl.0313.5/3;8 s:
]
~3. . Explain the consequences of' improperly withdrawing a 4 dropped rod.
1 CRO-5033 S/K 240122020440 K/A 000003EKl.01 3.2/3.7. 4 Explain the. interrelation of the lift coil disconnect. , switches with-the rod' control urgent' failure alarm. 9 CRO-5033 S/K 240109020100 K/A 001050A2'.01 3.7/3'9 .
- 5. Determine if a negative rate trip exists on a' power ;
range drawer. ' CRO-5033 S/K 241540020400 ;/A-015000A3.01 3.8/3.8: 4 a
- 6. Determine the correct Technical Specification action "
requirement. CRO-5033 S/K 240105020080 K/A 000003 generic 8 3.3/3.9 S/K 240122020490 K/A 000003EK3.08 3.1/4.2
- __ -_ _ _ . - O
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STATIC SIMMATOR EIAM SCEllARIO.= . p i DATE 900131' PREPARED BY R. C. Lullina SCENARI0'NO.- SS ARN2.NRC IC 'NO .' - 7~ i
.3 EVENT TYPE 'ARNORMAL (ADP33-1.SCN) .
TASK NO. TASK DESCRIPTION , j
- CRO-5413 Perform corrective actions in response to a- l high alarm'of the radiation monitoring. system. y SCENARIO DESCRIPTI T
. 1
' Initialize ~in any plant condition; Initiate an RMS malfunc- {
tion.- 1 1 SIMUIATOR SETUP -- , -
. - _ . a.
Verify multipoint recorders;on for 15 min' prior to RMS l malfunction-
- Initiate MALF RMS-2K; lE6 cpm,- no-ramp..
Acknowledge all-annunciators thae alarm R
-:FRZ simulator
- Initiate exam G.QALE 5
- 1. Verify the validity of a process. effluent monitor alarm. -l CRO-5413 S/K 247309020500 K/A 073000A4.02,3.7/3.7 l- . .
L-
- 2. Determine the source or cause of high activity utilizing
_ control room indications. 1 CRO-5413 S/K 247309020120 K/A 073000A1.01 3.'2.3.5- .'I
- 3. Determine if failed process radiation monitor is Techni-
, cal Specif,1c.ation related. 31 CRO-5413 S/K 247304020120 K/A 073000 generic' 11 2.8/3.4 9 l
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.$ . -j STATIC. SIMULATOR' EXAM. SCENARIO ,
' SCENARIO NO. SS-ABN1.NRC/SS-ABN2.NRC IC NO.. 7
. :q
. EVENT TYPE. ABNORMAL.
- i. - ".
iv INITIAL CONDITIONS- . -l 4 Time: 5 minutes !
* . Unit'Ifwas-at l'00%_ power. steady state; equilibrium' conditions-when'the:- d indicated. abnormal-event occurred. There-were'no LC0!s.or inoperable ,
.j equipment prior to this~ event. '-
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.052105CT1036R. -Points: 1.00 . Question-Number: 1' !
The' unit is operating at'100% power-with main generator load- i The unit operator, notices'that the'DEHCl system -
~
at 867lMWs. x has.automati: ally transferred.to manual, , Based on.these' l
- plant conditions, whatf are two(2) possible causes of .the DEHC '
- systemitransferring to-manual?c q r
{
. ANSWER: (.5 pts.-each)f(5: minutes)- ]
A. A~ loss of 120V-AC.to the operator. auto controllers (also accept: ~ .a: loss ofE120V AC to DEHC) B. A' failure' of. both' operator; auto controllers ' b r l s E i !
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i 052520FT1002R Points: 11.00, Question Numb'er: 2 1 A: complete loss.of instrument air has occurred and the operator tripped the reactor.from-100% power.- Ten minutes - j
'later,-the; operator' attempted toistop'the.TDAFV pump by shutting the st'eam' admission valves from the MCB.- Tho'TDAFW pump would not stop.~(Which of the'following is the cause? -
-(Circle the correct response.)
~
A. Steam ' admission valves' from BL& C loops are failed open. 'h l due to loss of :iustrument. air. ' l B. Common steam-admission valveiin main steam valve-room is failed open'due to B S/G steam supplyTvalve being ini local. C.- Both main; feed pumpn tripped. D. ' All S/G levels out of: narrow range. 4 1 i ANSWER: D. (4 minutes) i 1 4
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e i 4 052520IT1007R Points:- liSO' ' Question Number: _ 3 bs Unit 1 is in ModA 5 with'the RCS at 178'F and 375Lpsig. A bubble; is being drawn in accordance. with UDP-1.1, "Startup. of - , s' Unit'from Cold Shutdown to Hot Standby " ' Excess letdown has been placed in service-to expedite drawin'g'the babble. All' q initial conditions haveibeen met with'one RCDT pump running--
;and the other,in pull-to lock. The: recycle evaporator.is-running and processing the #1 RHT, The CCW system is:
aligned with.the "C" pump running through thec"C" heat 1 exchanger; The Unit Operator notices that R 17B readings are;- starting to increase.~and that CCW surge tank level'hasl increased 4 inches:since the last set'of log readings. -Based on the above stated, plant conditions; determine:three(3) potential sources oftin1'eakage to the CCW? system,
~
l' l l ANSWER: Any three(3) of the following for .5 Leach. (5 minutes) L, - LTDN heat exchanger. J Excess letdown heat exchanger L - RHR heat exchanger
- RCP thermal barrier l ;RCDT heat' exchanger-
- Charging pump seals
- RHR pump seals .)
k (Minus .25 for sources beyond three-that will ~not result-in' inleakage-or upscale R-17B readings for the' stated plant ' { conditions.)- i' I 1
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F , 052520ST1011R Points: -1.00 .' Question Number:. '4 If the dropped 1 rod will not' move due'to electrical problems and'cannot be' recovered..then which of the following actions- [iscorrect7 (circle the correct response.)- Ai; Continue operation according to Technical Specification 3,1.3.1 action d.3. '
'B. Be:in hot. standby within 6 hours according to'Technicalu Specification 3.1.3'.1 action a. ,
C.' Be in hot standby'within 6 hours accordingLto Technical
' Specification 3.1.3.1 action;b. ,
D. Maintain power. level and align'th'e remaining rods to within 12 steps within 1 hour. s ANSWER: AOP19 1.SCN (5 minutes)' '
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[; m 052520ST1017R= Points:, 1.00L Question Numberi 5. Followingthedroppedrodi-theoperatorsrestoredTavgto, q
. program by operation of the turbine controls. Final power?
- level after.Tavg was restored:to' program.was 86%.' . Prior Lto recovering the dropped rod in accordance with dOP 19..
; power level should be:' (Circle.the' correct response.)
A.- Maintained.at 86% B'.
. Increased-to 95%-
, C. ' Reduced to 81% ,.
D. Reduced to 72%L
.i ANSWERi .AOP19 7 1'.SCN (5 minutes).-
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-33 v3 ita, 052520ST1018R Points: ' 1.00- . Question Number: 6 l e
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'A " rod recovery" is in progress and ha's been performed;
,t satisfactorily:up to but not including step Sl4.5. lDescribe L i 1the method, that you wouldf use to determine the reahtivityf ,
worth of the; dropped rod. - (Actual calculation is not: required.). A 4 , - !;. 5
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ANSWER: AOP19 1.SCN (4 minutes)(SRO only) ,
'(Accept other answers on-a case-by-case. basis which; determine-
- the worth of the dropped rod.) '
Determine the difference = inL the: power defect for; the two! .; power levels (1.0). DE y _ Determine : tha difference in the power defect fo'r; the . power ' levels, taking into account the effect of any boronldilution. performed. .i i tr
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052520$T1019R Points: 1.00 Question Number: 7 While recovering the dropped rod,' the operator is directed to. a zero the pulse to analog convert.cr." li the operator failed to perform this step of the procedure, what, it.any, effect(s).will this have following the dropped rod recovery. on plant operation? AVSWER: AOP19 1.SCN (4 minuttts)(SRO only) RIL computer will show' rods higher than actual (1.0) (or an equivalent statemenc). 4 m
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, 05252 CST 1020R- Points: . 1.00' Question Number:: _ 8.
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t During-the recovery, step 5.4.15 of "the rod recovery proce j dure" was inadvertently.omitted.. =All other steps were, j completed according to, procedure. When the 0ATC placed rEdI conttol-(in MANUAL to adjust; Tavg to within 1 l'F of Tref - ! there was.no rod motion. Which' of the following is' the 'cause l of the l rods failing to move:; (NOTE:- NootherpEoblems' exist-E! in rod cont .01 except' forjomitting ' step 5.4115;)(Circlen the correct response.)i , l 1 A. Logic cabinet urgent failure! j B. Power cabinet. urgent failure
'I
- c. Bank:D rods are indicating greater than- 220; steps, '
pieventing outward rod motion D. Negative. rate rod stop 4 a ANSWER: 'AOP19-l.SCN (5 minutes)(SRO only) . B~~. ; 3 I
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-t 0$2520ST1022R. Points: 2.00 Question Number: 9 I
- 1. Calculate the present QuadrantLPower. Tilt Ratiot(QPTR).
QPTR = 4
- 2. Based ~ on the calculated QPTR, which of'the followbig actions should be taken: (circle'the correct response)
A. RNo action required based on calculated [QPTR. B. Calculate the QPTR'at least once'per hour until the: QPTR is reduced to within its limits. 4 C. Takei actions to correct and verify that QPTR is within its limit within 2 hours after exceeding or-reduce thermal power-< $04 within the;next 2 hours. 4 D. Take actions to correct'and' verify that QPTR is-within'its limit within 24 hours after exceeding or reduce thermal power <;50%,within the'next 2. hours. ANSWER: (AOP19 1.SCN)(12 minutes)(2.0).
- 1. QPTR - 1.007 ,001 (1,0)
- 2. A. (1.0)(Multiple choice answer should be based on calculated QPTR value.)
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*i 052520ST1023R' ,
.Pointsj1 1;00 . Question' Number:: 10 ,
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1 lWhich of the!following conditions would you'expectL+o'i observe " if this ., dropped: t od; event occurred = at EOL? L(Circle the +., j, y , .,.. .
. correct response.)? 1
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A.c - Smaller increase in'Tavs ' s j
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8 LB. ; smallerjdecrenoeinTavg
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f k - C. Orester increase in Tavg ' j 5 , Cre'ater decrease.'in TavgL 4
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ANSWER: 'AOP19el.SCN (1,0)(4 minutss). ' ' , s l ;'
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052521KT1004R Points: -2,00; - Question Number: . 11
=A4 -Liat at least'four(4)' plant parameters or indications' you would use in determining if the RMS al.nra is due to
. . . , fi an instrument failure..(1,0)L.
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('.. B . YES or.NO: HaveallactionsJoccurredthatshbuldhave' >- for this alarmicondition?.(Circle the" 4 correct answer'.)(1.0) ANSWER: AOP33 1.SCN (2.0) (5 minuten) A. Any.four(4)'of.the following for .25 eachL .e-CCW surge tank levels unchanged-
"B" train CCW not in service-Multipoint recorder step change-Charging flow unchanged '
VCT level unchanged' RMS meter pegged high-Both high and low alarm ~1ights; lit Chemistry sample indicates no activity
-Annunciator F 72 alarming .
Front panel indication not indicating per SOP B. YES (1.0) 1
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- 4
(. - [01/31/90, A1ABAMA POWER COMPANY
. EXAM GRADING SHEET l- l EXAM NAME: SRO.SS ABN NRC ' CLASS NAME: LRP.89 h TOTAL POINTS: . 13,50- DATE GIVEN: 01/31/90 I
STUDENT ID / NAME:=** DRAFT ** _/.*************** DRAFT ***************:
' QUEST. POINT POINTS QUEST POINT POINTS O ,
VALUE MISSED # VALUE MISSED
.1". 052105CT1036R 1000 .
2-.:052520FT1002R .1.00' . 3 0525201T1007R 1.50 ~
-4 052520ST1011R 1.00 .
$ . 052520ST1017R 1.00 .
6 052520ST1018R. -1.00 .
- 7. -052520ST1019R 1.00 .
8 052520ST1020R 1.00 .
-9 . 052520ST1022R 2.00 .
10 052520ST1023R 1.00 . 11 - 052521KT1004R 2.00 . M g
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TOTAL POINTS MISSED: FINA1. SCORE: 4 l 1 q y l 1 L _-__ _ _ l'-_
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y 'f r ; I RTYPE: K2.04 (Individual) l RTYPE: K2.07
-(KEY) e TRAINING DEPARTMENT EXAMINATION l NAME(*RGVR): KE Y cR0ue: nw
'*DATE: 01/31/90 EXAM NUMBER: SRO SS EMER NRC EXAM TITLE: NR(M- SR074 EMERCENOVISTATI[N TAL POINTS:'12.50
(*XREF) INSTRUCTIONS-
- 1. This is a /1.U' hour examination.
- 2. Point value for each question.is indicated in the ques.
tion header.
- 3. Anmwer all questions: .
((] On a separate paper. ((] On the answer sheet by circling or marking the cor-
~
rect req onse or filling in the blanks.
'l)
( On the same page as the' question; -If extra room is needed,' use the reverse side of-the previous page. ! or use ext ca paper. ,
- 4. CHEATING OF ANY KIND IS STRICTLY FORBIDDEN.1 ' ANY ' INDI'-
VIDUAL CAUGHT CILEATING WILL AUTOMATICALLY FAIL THE ' EXAMINATION AND DISCIPLINARY ACTION WILL BE'TAKEN' . S. ALL WORK DONE ON THIS EXAMINATION IS MY OWN. ^TO MY . i KNOWLEDGE I HAVE NEITHER GIVEN NOR RECEIVED AID.- FURTHERMORE, I WILL NOT DIVULGE THE CONTENTS OF THIS-EXAMINATION TO ANYONE ELSE WHO MAY TAKE IT. 8 EXAMINEE'S SIGNATURE- , EXAM GRADED BY: PREPARED BY: /c CRADING/ MATH REVIEW BY: APPROVED B h Trainfg Ma%ager/ s. Supervisor- >
- INDEXING INFORMATION 2/24/89 a
STATIC RIMULATOR EKAN SCENARIO 4 DATE , 900131 PREPARED BY R. C. Lulline SCENARIO NO. SS-ERP1.NRC IC NO. 7 j i EVENT TYPE EMERGENCY .! l TASK NO. TASK DESCRIPTION l CRO-5406 Perform required actions for Rx trip with SI. ! CRO 'i357 Perform required actions in response to a loss ; of secondary coolant. j SCENARIO DESCRIPTION :
'l The plant is initially at 100% steady-state with a MDAFW pump inoperable and red tagged, repairs expected to be com-plete in 12 hours > A 4E6 stm line break on B S/G inside CTMT causes an automatic Rx trip, SI, and main stm line isolation. .
CTMT. pressure is > 4 psig, causing adverse CTMT c anditions, f On the SI,. phase A isolation valve 8152 (LTDN isolation) and valves 8107 and 8108 (charging isolation valves) fail to ' close. The simulator is frozen at this time. , SIMULATOR SETUP .; w Init at 100% in IC 7 Fail valve 8152 open (MALF CVC5)
- Fail valves 8107 and 8108 open (C CHGM7-5; CHGM8-5) :
- Trip B MDAW pump (MALF-WM 1B) ,
- Tag out a MDAFW pump (C AWPl-4) +
- Activate steam line break on B S/G inside CTMT (MALF MSSIB.
4E6, 100 sec ramp) Verify Rx trip, SI, and MSLIAS ,
- Stop minipurge fan Place feed reg valve controllers in MAN and shut ;;
- Verify post-LOCA mixing fans and H2 dilution fans running Verify CTMT pressure > 4 psig but < 27 psig (i.e. NO CTMT l l Spray actuation)
- l Verify LCV 1003 closed
- L - Acknowledge Subcooled Margin Monitors -
- FR7. simulator (Prior to CTMT spray actuation!)
Make the following log entry: j "A MDAW PUMP inoperable due to motor core etions; v repairs expected to be complete in 12 hours; LCO is written."
- Start exam GOALS l
- 1. Verificati>n that a phase A isolution has. occurred per attachment 1 of EEP-0.
CRO 5406 S/K 249706002100 K/A 000040 GEN 10 4.1/4.2 J l: r-s
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i ' i- '.' 2. ,Re:ponsi cf the CR0 t3 CTMT pha:6 A n;t being cctuat:d
=w h:n r quir:d..
.CRO 5406 S/K 24970600200 'K/A 0000400EN10.4.1/4.2
- 3. : Verification of,two trains.of.sr.feguards' equipment run-ning-IAW EEP 0.
CR0 5406.S/K 241306000450 K/A 000040 GEN 12L3.8/4.1 .
- 4. . Response of CR0 to faulted S/G indication.-
CRO-5357 S/K 24351502510 K/A 000040EA2.01~4.2/4.7
- 5. ' Identification'of a faulted S/G. '
CRO 5357 S/K:243515021000 K/A 000040EA2.01~4.2/4.7.
- 6. Monitoring'of CSF status trees; CRO 5406 S/K 240610021875 K/A000040 GEN 12 3.8/4.1- .
'7. Recognition that. foldout page'should be monitored con .
tinuously CRO 5406 S/K 240205020340 K/A 0000400EN12 3.8/4.1
- 8. Verification that S/G 1evels are sufficiently maintained.. ,
or AFW flow.is. maintained. .. CRO 5406 S/K 243575020434 K/A 000040EA2.05 4.1/4.5. t
- 9. Recognition of.which S/Gs supply Ateam to the TDAFW; d- pump.
[ CRO 5406 S/K'243515022600 K/A 000046EA1.03 4.3/4.3' , 061000K1'.03 .3.5/3.9
- 10. Precautions associated with isolating:the TDAFW steam' supply from faulted S/G.
J CRO 5357 S/K 246111020170 K/A 000040EA1.03 4.3/4.3-061 GEN 10- 3.5/3.4
- 11. Operation of the CTMT spray system during a steam break.'
n CRO 5357 S/K 242662000150 K/A 000040EK3.06 3.4/3.9.-
- 12. Determination that SI should,be terminated.-
CRO 5406 S/K 240606000343.K/A 000040rA2'.05.4.1/4.5 1 j
, m 1
STATIC SIMULATOR EXAM SCENARI0' ' i SCENARIO NO. SS-ERPI.NRC __ IC NO. 7 : EVENT TYPE EMERGENCY , i i INITIAL CONDITIONS l Time: 5' minutes i ! An emergency event has occurred. Annunciacor G-51 was.the'.first out. Prior to the event the' plant was at 100% steady-state, equilibrium f conditione. 1A MDAFW pump was. inoperable and tagged.out.for maintenance on- ,; the motor. Repairs are estimated to be completed in 12 hours. '
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052$39BT1037R Points: 1.00 Question Number: 1 The operator that was assigned to place the hydrogen analyzers in service reports that neither analyzer willL q
, operate correctly. Chemistry reports that theyLcannot obtaih-H2 grab samples due to faulty equipment. Based on these.
conditions, what would be'the correct action'to take? (circle the correct response.) A. Leave H2 recombiners off until containment ^H2 ! concentration ei varified < 4%. !
- B. ' Start the H2 recombiners and reduce H2' concentration in the containment by using post LOCA vent system for; two hours ~.
I C. Reduce H2 concentration in the containment by tos.ng post LOCA vent system: 'do not start recombiners. D. Start both H2 recombiners even though H2 concentration in containment is not known. ANSWER: EEPl.4.SCN (4 minutes) A. i k
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' Ques tiion' Number: 25 , j
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g j.;h What component (s); if any, must_be operated by the opn atori gf - .s . I to' ensure completion of'EEP 0.immediate operator actions?- -!
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Shut-valvel 8152 . (to complete dA-isolation per EEP 0 attach.
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L- , .' *. <p ,.i L ,: 05253dCT100$R Points:1<1.00' Question' Number: 3 .
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LtoensuretwotrainsofSNflowpathae-aligned? 1: i. q.
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ANSWER:~-EEP2 1.SCN (6 minutes) c g 4
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. Close valves ' 8108 and/or 8107 (1.0)(' < .
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, - 052530CT1011R - Points: 1.00 ' l Question Number: 4 :.
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' A safety injection-has occurred lin.the plant.
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ANSWER:' EEP2 1.SCN (4 minutes) ,
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>- .B.- B S/G (.5)~ l i
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. Points: '1.00 .j 052530CT1014R -Question' Number: 5 If containment spray were to actuate, it should be stopped
.g 1 when: . (Circle the correct response.)-
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? A. <104 spray add: tank level, spray add tank o_utlet valves !
closed, and pressure < 26 psig (due to. adverse contain : i ment) 4 B. <16 psig containment' pressure regardless.of, spray add ; tank level-C. <104 spray' add tank. level,: spray add-tank' outlet valves closed, and containment sump.rectrculated for ! two hours -
+
D. <104l spray add tank level,= spray. add. tank outlet. l valves closed, and <16 psig containment pressure- ' ANSWER: . EEP2 1.SCN (4 minutes) . #
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7 m ( 052530CT1015R Points:, 1.00 Question Number: '6 k Assuming static plant co.nditions remain the samk, except those indicated in the below choices, which'of the following { sets of conditions would allow SI termination when the faulted S/G boils dry?. (Circle the correct response.) { A. 52' subcooling .two SGs at 25% NR, one SG at On WR, AFW ! flow at 100.gpm, RCS' pressure at 1600 psig.and stable', and PZR level at 62% B. 52' subcooling, two SGs at 50% NR, one SG at On NR,'APW flow at 100 gpm, RCS pressure 1600 psig and stable, and PER level at 62%
- C. 52' subcooling 439 gpm APW flow, RCS pressure 1600 psig. '
and stable .and PZR level 12% D. 52' subcooling 450 gpm APW. flow, RCS pressure 1600 psig. and decreasing, and PZR level 62% ANSWER: EEP2 1.SCN (4 minutes) B f
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gg _ . _. 3 rs< i I 052530CT1016R .. Points: . 1.50 Question Number:.
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Assume 130 minutes'of operational' time have-elapsed since the t simulator was frozen. .,The new-following' plant' conditions now
~. , ,
exist:-
- The SI is.still in progress ; a a
g,1 RCS Th and.Te are:260* ,
- RCS. pressure is 1600 psig_and stabla.
- PZR levelfis 954 and' increasing {
Containment pressure is 50'psig ;
- Containment radiation monitors at current valuei (
. Containment semp level;is 6.5Lfeet l 1
.N 30 and N-32 are~ energized l i
- Both source. range SUR indicate .1' DPM i-Based on the above conditions (regardless of'the j r
a circumstances which led to their forniation), answer the' r J i following questions: ::
't
'. A. Which FRPs are required to be implemented? ' B. In what. sequence are'the FRPs requiredi to be imple I mented? j r
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ANSWER: EEP2 1.SCN (4 minutes) ' 1 A. FRP P.1 (.5)' i FRP Z.1 (.5) B. P.1 then Z.1 ( 5) t
'i (Minus .25 for.any invalid orange or red path) m I (Minus .25 for'any yellow path listed'as being required) ;
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; 052530CT1017R- Points: 1.00 . Question Number:- 8' [
L <; How should steam flow to tho' TDAW pump be isolated? (Circle j
, .the correct response.) ..
' a
. A .- 'It is not required to be isolated based on fault location B .- Isolation from the MCB. ,
C. -Isolation from the HSD panels-- >
.t D. : Isolation in.the Mairi Steam valve room ANSWER:- EEP2 1'.SCN (4 minutes) .
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. 052530CT1018R- Points: l'. 0'0 - , Question' Number: 9 j
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j O Base'd'on the present static' plant conditions and assuming l 1 a 65 spa primary to secondary leak causes R 15 to alarm and I
. i indicate full' scale, which of the following"best describes :!
;l the appropriate-emergency classification for those >
. . l conuitions?.-(Circle <the correct response.).
-At Site Area' .c
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.B. Alert .
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q D. . One hour non emergency j a.; ANSWER: EEP2.1.SCN (4 minutes) l s ;f B. (Basis EIP 12, 3.2.2 orf3.2.17 or.3;2.8.a)
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b 052530CT1019RL Points: 1.00 . Question Number: :10 1
- Based on the present' static plant conditions, state thel t .
appropriate emergency classification including the procedure
. .. e and paragraph for your, basis.
1 r ANSWER: EEP2.1.SCN (4 minutes). g , ,, ALERT, EIP 12 ('.5) Paragraph 3.2.17 or 3.2.8.a (.5) , . s f _'Fy', i ..
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- Points: ' 1. 00 :. . ' Question Number: : ll" i
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-- . . 'k Based on the emergency event, thelfirst procedure:used-when, i a: :J 1
i 4 the'.ERP's are entered, should be: .y- , .j n t i .31
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e q D. EEP 2 j 3 ANSWER:. EEP2 1.SCN'.(4 minutes)l > ej B. > c 4 1 $ 1 s'b' i 4 .i - o g h' i- t g w N i F'
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1,. s: , s s iz u.: 052530CT1021k Points: . 1.00- Question Nu'ber:- m '12
.An MSIV closure signal has been generated,Lyet one_ set of MSIVs is indicating not' fully _ closed because:. (circle the correct response.')
to 4 A.. They did not receive the MSIV closure signal'. -
",- B. ' Steam flow is'still_be'ing' directed to the turbine building through the MSIVs.
C. Reverse steam flow from;the steam header to the SG= exists.
'D. They-are required to_ remain open to maintain 1 condenser-vacuum. ,
ANSWER:- 'EE2 1.SCN (4 minutes) C. .. l 1 l a 9 . a q t 3 Y 1 , > a t , o
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- 01/31/90- AIABAMA POWER COMPANY l u
EXAM GRADING SHEET l L EXAM NAME: SRO.SS.EMER.NRC CLASS NAME:'LRP.89 'l J iTOTAL. POINTS: 12!50l DATE GIVEN: 01/31/90 STUDENTID/NAME:'** DRAFT **:-/*************** DRAFT.***************~ j
' QUEST POINT POINTS QUEST ' POINT- POINTS
'O- VALUE MISSED- # VALUE MISSED-l l'. 05253f.ST1037R .1,00 -
L
- 2 .;052530CT1004R 1.00' -
i 3 . 052530CT1005R 1,00 . v 4 052530CT1011R -1.00 . .. 5 .'052530CT1014R 1;00 .- '
- i 6'. 052530CT1015R 1,00 -. ,
7 052530CT1016R' '1,50 . 8 052530CT1017R 1,00 . 9 052530CT1018R- 1.00 - 10 052530CT1019R 1,00 . j 11 :. 052530CT1020R L '1.00 . J
'12 052530CT1021R 1.00 .
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- p TOTAL POINTS MISSED: FINAL SCORE: % _
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RTYPE: K2.04 (Individual) I RTYPE: K2.07 i (KEY) TRAINING DEPARTMENT ETAMINATION NAME(*RCVR): GROUP: OPS 3
*DATE: 01/31/90. EXAM NUMBER: RO SS ABN NRC EXAM TITLE: NRC r - RO :--ABNORMAL' STATIC:. TOTAL POINTS : 11.50
(*XREF) INSTRUCTIONS
- 1. This is a l'. 0 - hour examination.
- 2. ' Point value for each question is indicated in the ques-tion header.
- 3. . Answer all questions:
[~] On a separate paper.. [ ~_ ) On the answer sheet by circling or marking the cor-rect response or filling in the blanks. [b On the same page as the question. If extra room is needed, use the reverse side of the previous page. or use extra paper,
- 4. CHEATING OF ANY KIND IS STRICTLY FORBIDDEN. ,ANY INDI-VIDUAL CAUGHT CHEATING WILL AUTOMATICALLY FAIL Tile EXAMINATION AND DISCIPLINARY ACTION.WILL BE.TAKEN.
- 5. ALL WORK DONE ON TilIS EXAMINATION IS MY OWN; TO MY KNOWLEDGE, I HAVE NEITl!ER GIVEN NOR RECEIVED AID.
FURTHERMORE, I WILL NOT DIVULGE Tile CONTENTS OF THIS EXAMINATION TO ANYONE ELSE WHO MAY TAKE IT; i EXAMINEE'S SIGNATURE l EXAM GRADED BY: PREPARED BY: /A GRADING / MATH REVIEW BY: APPROVED /] o Trainitf MaiWlQsr/ Supervisor
- INDEXING .NFORMATION i l
2/24/89 !
. =. _ _ - _ _ . _ _ . _ _ . . _ _ _ _
STATIC SINU 1ATOR EIAM SCENARIO 2 DATE 900131- PREPARED BY R. C. Lullinz . i SCENARIO NO SS ABN1.NRC IC NO 7 l EVENT TYPE ABNORMAL (AOP19 1.SCN)= L
; TASK NO. IAEK DESCRIPTION CRO 5033 Perform corrective actions in response to a i l
malfunction of the rod control system. , 1 . CRO 5379 Apply action statement of Technical Specifica. i tions. l SCENARIO DESCRIPTION ! Initialize at 100% power, BOL, with rods in manual. Initiate a dropped rod malfunction with no reactor trip occurring ori required. SIMULATOR SETUP i Initiate MALP CRF 15A, stationary coil', rod F6 . f Acknowledge all annunciators that alarm and/or clear l~ Allow 15 minutes run time to stabilize Tavg, pressure, etc. (900 see)
- FRZ simulator ,
Initiate exam , COALS
- 1. Determine the correct method for restoring RCS Tavg to program value. .. t CRO 5033 S/K 240122020405 K/A 000003EA1.05 4.1/4.1 -
- 2. Jetermine the reactivity worth of a dropped rod. ;
RO 5033 S/K 240122020430 K/A 000003ERI.03 3.5/3.8
- 3. Explain the consequences of improperly withdrawing a t dropped rod. ;
CRO 5033 S/K 240122020440 K/A 000003EKl.01 3.2/3.7 ;
- 4. Explain the interrelation of the lift coil disconnect switches with the rod control urgent failure alarm. !~
CRO 5033 S/K 240109020100 R/A 001050A2.01 3.7/3.9
- 5. Determine if a negative rate trip exists on a power
- range drawer.
CRO 5033 S/K 241540020400 K/A 015000A3.01~3.8/3.8
- 6. Determine the correct Technical Specification action requirement. .
CRO 5033 S/K 240105020080 K/A 000003 generic 8 3.3/3.9 S/K 240122020490 K/A 000003EK3.08 3.1/4.2 ; c s - -
-o STATIC SIMULATOR EXAM SCENARIO ,
DATE -900131 PREPARED BY R. C. Lulline
' SCENARIO NO. SS ABN2.NRC 10 NO. 7 f
EVENT TYPE ABNORMAL (AOP33 1.SCN) TASK NO. . TASK DESCRIPTION CRO 5413 Perform corrective actions in response to a. ; high alarm of the radiation monitoring system. , s
. SCENARIO DESCRIPTION Initialize in'any plant condition. Initiate an RMS malfunc' ,
tion, j SIMULATOR SETUP i
- Verify'multipoint. recorders on'for 15 min prior to RMS j malfunction- ;
Initiate MALF RMS 2K; 1E6 cpm, no ramp. Acknowledge all annunciators that alarm ' FRZ simulator Initiate exam , GOALS ,
- 1. Verify the validity of a process-effluent monitor alarm. >
CRO 5413 S/K 247309020500 K/A 073000A4.02 3.7/3.7
- 2. Determine the source or cause of high activity utilizing {
control room indications. CRO 5413 S/K 247309020120 K/A 073000A1.01-3.2.3.5 l f 3. Determine if failed process radiation monitor is Techni-cal Specification related. CRO 5413 S/K 247304020120 K/A 073000 generic'll 2.8/3.4 i 4 x 1
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1 STATIC $1MULATOR EXAM SCENARIO p ~ SCENARIO NO. SS-ABN1.NRC/SS-ABN2.NRC IC NO. 7 EVENT TYPE ABNORMAL , INITIAL CONDITIONS' l
, Time: 5 minutes Unit I was at 100% power: steady state, equilibrium conditions when the:
indicated abnormal event l occurred. There were no LCO's or inoperable equipment prior to this event; l I l i u 1 4
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^
m s) 052105CT1036R Points: 1.00 Question Number: 1 r
' The unit is operating at 100% power with ' main generator load' at 867 MWs.. The unit operator notices that.the DEHC. system has automatically transferred to manual. Based on these plant conditions, what are two(2) possible causes of the DEHC i
system transferring to manual? < e P ANSWER: (.5 pts, eac.h) (5 minutes) A. A loss of 120V AC to the operator auto controllers (also l accept: 'a loss of 120V AC to DEHC) B.- A failure of both operator auto controllers
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~0b2520FT1002R' Points: '1.00- Question; Number: ' 2 -- U
-(
A complete loss of instrument air has occurred ~and the>
' operator. tripped the reactor frem 100% power, fTen minutesf w
-later.:the operator attempted to'stop the TDA R pump'by shutting the steam admissior. Halves from'the MCB.
~
The TDATV pump'would notfstop.- Which of.the following'is'the-cause?~ (Circle.the' correct' response.) , j A. Steam'adiaission, valves'from B.&-C loops-are failsd open
'due to loss of. instrument-air. , j
]
B .- Common, steani admission valve in . main steam ' valve roomlis failed open due=to B;S/G steam supply valve'being in- .. L
. local.. ;
C. 'Both main feed pumps tripped.' D.- All S/G 1evels-:'out of narrow range. . sj ANSWER: D. (4' minutes) i o i a i
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, 0525201T1007R -Points: :1.50 3 -Qdestion Number: 3 ,
y Uniti 3 is'in Mode ~ 5 with' the RCS 'ati 17B?F and 375' psig. A' s - . , , . , t
- bubble J isTheing drawn in- accordince with UOP-1?.1, j "Startup of ,
qj Unit from Cold: ShutdownE to' Hot Standby. "' Excesal letdown lhast . 1
'l
~
been placed in servicetto expedite' drawing lthc[ bubble. All-
. . L ": ,
2 initial conditions have been met' with one' RCDTl pump -runningi 'e o i
; and the ' other: in pull-to lock. The recycle evaporator? is s
'l running land processing thet#1[RHT. , !The CCW system is' ,
aligned with . the; "C" pump running through(the c"C": heat
-exchanger. . The Unit Operator notices:.that R-17B<readin'gs'are-
-1 .
q j starting to increase and 'that, CCW starge tank level' has increased I' inches since ' thellastiset.;cf;1og readings. . Based' d a_ . . . . . :
-on the above stated plant = conditions,:. determine three(3) c s. potential sources: of inleakagei to; ths CCW system.
4
'I e 'r 4
9 3 ' l ANSWER: Any three(3) of the .following for ,5 each. :(5 oiinutes) . L
- LTDN; heat exchanger-
- Excess letdown heat exchanger- ,
- RHR heatf exchanger .#
RCP thermal barrier
- RCDT. heat exchanger 1
9
-fCharging pump seals
- RHR pump seals
-(Minus .25'for sources beyond three that will not result-in inicakage or upscale R-17B readings for the stated plant conditions.)'
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052520ST1002R -Points: 1.00 . Question'Numbhr:; ' In accordance with AOP-19~ " Malfunction of. Rod Control'
,: 4
. System," st,ep;5,4'10 hau the operator."zero the' pulse to analog converter." J1f-the operatcr failed to perform'this-
, step:-of: the procedure s'what, f if any,: effect.(s) will'this' have- -
following the dropped rod recovery on: plant operation ' -i' t i i 4, > l'j
.5-
+- -
2i
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r ANSWER: AOP19-1.SCN (4 minutes)- 'n k
' .' i RIL computer will show rods'highor:than' actual (li.0).- Lf (or;an equivalent statement): ,,
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, 052520ST1004R. Points:;'1.00 Question Number: L$ -
l
,y q While' at ;100% power, a. dropped ' rod event occurred on Unit 1. ,
i 1During the1 recovery, step'5.4.15 of AOP-19 was. inadvertently; j , omitted; , All other steps were completed according to proce)
~~ dure. When f.heLOATC p1' aced rod control; in MANUAL to -adjust Tavg to'withinfi l'F'of Tref, there wasino rod motion'. Which- 4 ofLthe-followinb is thetcause of the rods failing to move: ;
-(NOTE: :No other problems exist-in rod controliexcept for- "'
1 omitting step'5.4.15.)(Circlet the corre'ct response.) A. Logic.cabinetLurgent failure I B. Power cabinet urgent failurei '
- s C. . Bank D, rods-are indicating greater;than 220 steps < :]
preventing outward rod' motion ~ w*
- D. . NeBative: rate rod stop i
j
-l yl1 ANSWER: AOP19-l'.SCN'(5 minutes) , ,
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k 052520ST1007R Points: -- 1,00 -- ' Question' Number: 6 s 8 PM y< , AOP-19ils? in progress and he been performed satisfactor',1y - -
?
D , . - . ' - Describe the, method-:.
. up to:but not including step 5.4.5. :
t l that you would use-to determine the-reactivity worth of the n
^
g a dropped rod,: (Actual calculation is not; required,) l Af r i , i
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1 ANSWER:. AOP19-1.SCN (4 minutes)' , . . .. ; (Accept other answers on a' case'-by case basis which determine- i the worth of the dropped rodi) j Determine the' difference inLthe-power defect for the two 't 1 power levela.(1,0), ;
- l OE j Determine the difference in the power defect for tho' 'r:
1 levels, taking into account the effect-lof any boron n; b ton-H performed. O d o
?
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3 f!' OS2520ST1017R. Points: 1,00 Question Number: .7 d Following the'. dropped rod, the operators restor $d Tavg to- y program by operation of the. turbine
- controls.- Final power =
level after Tavg w Q restored to program was 86%. . Prior - to recovering the' dropped rod'in accordance.with AOP-19,, - power level . shoulci be: f(Circle-the'. correct response,)- A,; Maintained at 86%' 'E
. 1 B,. . Increased-to 95%-
C. Reduced:to 81%
- ?
D, Reduced to172%~ d ' ANSWER: 'AOP19-1,SCN-(5~ minutes)) C 'l
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'052520ST1021R + ...ts : 1'.00l Question Number: 8-
, d
-i a
The present. Quadrant Power Tilt-Ratio'(QPTR)-is: Al 1.004
~t B. :1.007 1
j C. 1;011 iT;
+
, )
D. 1!033 < .; 5
- ANSWER: ' ( AOP19 4l'. SCN)(8 ' minutes)(1.0) >
'a ~ N
- B. ,
.g os-. '
e Uooet Lower;d. - j V- .
- J 195/199. .9799: '202/222' ,9234 -
1
.188/193.-'.9741 '192/206 m,9320: ,
- 1 t:
187/191 .9791. '200/217 - ;9217. < s (185/180 - 9840: 197/213'-!.9249 - 3.9171
'3,702
~!
QPTR :.1.0048 , -QPTR.- 1.0070! # -{
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052520ST1023R : . Points: 1.00c Question ~ Number: a 9: - Which of the following conditiors would you expect to observe.
.if thisLdropped rod event ca. curred,at EOL?-.;(Circle the- ;
correct. response.)l A. , Smaller: increase;in Tavg jj
- , B..
Smaller decreaselin Tavg:- s '; C. Greater _ increase-in Tavg. , t u , =
. . , d Greater decrease in Tavg D- :
l
, , q ANSWER: .A0P19-1.FCNL(l'.0)(4 minutes)
-B.
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7 1052521KT1004R.. Points: 12.00 Question Number: 110'
' A .' List atileast four(4); plant parameters;or indications 9 ;
you1would use in determining if the RMS alarm isidue to'
'an instrument'falidre. (l'. 0) 4
'. j .
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l. B. YES or:NO: Havs'alliactions occurred that should'have l
'for:this' alarm condition?.(Circlefthe- 9 correct answer.')(1,0)1 :1 q
d-1 A A.;dWER: AOP33-1.SCN (2.0) (5 minutes)
]
A ., - Any.four(4) of the following for .25.each"
. )
i CCW surge tank levels unchanged "B" train CCW not- in service Multipoint recorder step change .i Charging flow' unchanged. , 'I
.VCT level. unchanged RMS meter pegged high.
-Both high and low. alarm lights lit -!
Chemistry sampleDindicates no activity. Annunciator F-72 alarmingL Front panel indication not indicating por SOP 1 B. 'YES (1.0)
;l.
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01/31/90T ALABAMA' POWER COMPANY N - EXAM GRADING SHEET .i
.s._ .
E W NAME: RO-SS ABN-NRC- rCLASS NAME::LRP 89
-TOTAL POINTS: 11.50 DATE CIVEN:-01/31/90 STUDENT ID../ NAME: ** DRAFT ' * * ; / , * **** *** ** ***** DRAFT **** ********* *
- 4 .
- QUEST. POINT POINTS -QUEST. POINT': POINTSV
' 0-VALUE' MISSED
# 'VALUE -MISSED .
, s N
1' 052105CIl036R" 1.00 -
~
2 - 052520FT1002R 1.00 -
- 3 .0525201T1007R l'. 50 . --
4 - 052520ST1002R. 'l.00 ~~ 5 -;052520ST1004R 1.00 --
~
;61 iO52520ST100'/R -1.00~ --
7 .052520ST1017R- 1.00- -
-052520ST1021R1 1.00 -
'~ ~
/-
9 - 052520ST1023R .1.00- '- ~' 10 t 052521KT1004R- -2.00 - l
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'l TOTAL POINTS MISGED: FINAL SCORE: %
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1 3 ) i;.: RTYPE:! K 2.04.- ;
~(Individual). ~
1RTYPE: K2.07 '
-(KEY); ;
TRAINING 1 DEPARTMENT T EXAMINATION- [
- y. ;*A o.g !
J NAME(*RCVR): b ' x GROUP: - ONA ' ,
' ~
*DATE: 01/31/90 .
EXAM NUMBER: RO-SS-EMER-NRC
' EXAM TITLE: NhdC--R0L- ' EMERGENCY STATIC. TOTAL' P.O INTS i 10.50.
~(*XREF)* :
, , i 9
~
.k INSTRUCTIONS: , \ l i
- 1. This is a. -h od '
l hourDe aminatifon! -
-t R 2. Point value. forceach question; is -its .aated:in .the ques-tion-header.
~ '
'3. , Answer all questions:-
. ((]' On a: separat'e' paper.
y f
~
[) On the Janswer. sheet' by circling or marking:the' cor - g .I
- rect responseiorifillinglin the blanks. ., s t .
m. (; (E)' On the samelpage as the question. .If extra room isc ' needed, use the reverse' side,of the' previous page .. ' ' ~ l 4 or use extra paper. ,
- 4. CHEATING.0F ANY KIND'IS STRICTLY FORBIDDEN. . ANY INDI : d VIDUAL CAUGHT. CHEATING WILL AUTOMATICALLY FAIL THE: -
EXAMINATION AND DISCIPLINARY ACTION WILLrBE:TAKEN. , t S. ALL WORK DONE-ON THIS EXAMINATION IS MY OWN. . TO MY , KNOWLEDGE, I HAVE NEITHER GIVEN NOR' RECEIVED AID. FURTHERMORE, I WILL NOT DIVULGE THEl CONTENTS'0F THIS'
]' '
- EXAMINATION.TO ANYONE.ELSE WHO MAY TAKE IT. .l i
.1 EXAMINES'S SIGNATURB .,
q
.h f xi EXAM GRADED BY: PREPADED BY: 4 GRADING / MATH REVIEW BY: ,
APPROVED BY
' rain' 'f Marf((fer/
, Supervisor .,
- INDEXING INFORMATION
]
2/24/89 j J =
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L TIC SIMULATOR' EIAM SCE!IARIOT "l
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- DATE 900131 PREPARED BY' R. C. Lulline ,1 '
y y h SCENARIO UO. SS-n Pl . NRC IC NO. '7' y L 1 y EVENT TYPE -EMERCENCY' N' \ h , i L. L TASK NO. TASK DESCRIPTION . k u f -- CRO 5406-
) Perform required actions for Rx-trip with SI.
[; , - sg
. CRO-5357 Perform required actions.in-response"to a los's
,: ~ of ' secondary coolant.i ,
+
l Li l- SCENARIO DESCRIPTION 3 V t t The plant.in: initially lat.100tisteady-state with a MDAFW I ' ~ 3 pump inoperable and red tagged, repairsfexpected:to be com- 1
'L 3
pletein'12 hours.'Al4E6.semlinebreakonB,S/G;insideCTMT .. f causes an; automatic:Rx-trip, SI,'and usin sta line isolationJa 3 2
...._m, __ j p CTMT pressure:is > 4'psig,; causing adverse CTMT' conditions.- +
=On the SI,--phase.A isolation ~valveLB152L(LTDN isolation) and-valves 8107.'and 8108 - (charging. isolation; valves)r fail to
.close. The simulator is frozen ~at this time. i
; SIMUIATOR SETUP ,
a s d
- Init'at.100% in IC 71 l
-- Fe4.1 valve.8152 open (MALF-CVCS) . .
i
- Fail valves 8107f and?8108 ' opent (C-CHGM7- 5 ;; CHGM8-5) = ;
- Trip B MDAFW pump (MALF-WMz 1B)
L s
- Tag out a MDAW pump -(C ANP1-4) _ . .
4 Activate ~ steam line breat on B~S/G inside CTMT (MALF-MSSIB, - j 4E6, 100 sec ramp) . _ l
- --Verify Ax trip, SI, and MSLIAS .;
.Stop :inipurge fan 4 L .
-Pfan feed reg valve: controllers in MANJand-shut (
- Verify post-LOCA. mixing fans'and H 2 tdilution' fans running. ys
- Verify CTMT pressure > 4 psig but < 27.psig'.(i.e.;N0';CTMT .j Spray actuation)
- Verify.LCV-1003 closed.
~- AcEnowledge S'ub' cooled ~ Margin Monitors . .
b FRZ simulator (Prior to CTMT spray actuation!)
~
--Make the following log entry: -i "A MDAW PUMP inoperable due to motor connections;.
. repairs expected to'be complete in 12' hours; LCO is written.
- Start exam EALE
- 1. Verification that a phase A isolation has occurred per j attachment 1 of EEP-0. '1 o
CRO-5406 S/K .' N00M00 K/A 000040 GEN 10 4.1/4.2 y q
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1 O
'-:when r:quirhd.; %g N( ' "
w CRO-5406 S/K_24970600200f K/A1000040 GEN 10 4.1/4.2 t
. . . T. Verifitetion'of two-trains (of safeguards equipment.run- ~,
t- M ning IAW EEP 0. . _
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, CRO.;5406 S/K 241306000450lK/A'000040 GEN 12,3.8/4'1 g
.\~
R- 4. IResponse of.CRO'to f;ulted'.S/Giindication.." s
]
- ,_CRO 5357;S/K 24351E02510 K/A 000040EA2,01 4.2/4~.7 ,
. u-
- 5. Identification'of<a faulte'di3/G. \..
W s CRO-5357'S/K 243513021000 K/A 000040EA2._01"4.2/4.7,
.y , a f y I 6.
4 Monitoring'of,CSF status trees. YY l CRO-5406 S/K 240610021875'K/A000040 GEN 12.3.8/4.1; x < N \L a
.7.. Recognition that_' foldout page 'shouldobe m' nitored 1 con y q tinuualy.; . <
T'f h
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;CRO-5406 S/K 240205020340.K/A 000040 GEN 12'3'.8/4.11 -.
.. .,;~. . . . . . . :. - -
.8. . Verification' that S/G 1evels; are sufficiently maintained' -
J'V :l or:AFW flow,is maintained. ..> , j CRO-5406-S/K 243575020434 K/A 000040EA2.05-4.1/4.S' , q l
- 9. Recognition of which S/Gs supply' steam.to the TDAFW 1
Pump. . _ v s
.L CRO-5406 S/K'24351502L600 K/A 0000 %EAl'.03 4'.3/4i3; '
' ^
061000Kl~.03 T3.5/3.9.c s e -
+
- 10. Precautionsassociatedwith; iso 1'atingtheTk'AFW$steami 1 :;
supply from faulted S/G. .
'CRO-5357 S/K 246111020170 K/A 000040EA1.03L4;3/4.3
'TL
" 061 GEN 10~ 3.5/3.6
]
s -{
- 11. Operation.of the CTMT spray system during avsteam break..
L ,CRO-5357,S/K 242662000150 K/A 000040EK3.06.3.4/3.9' l
.t
- 12. Determination that SI should be. terminated. .l CRO-5406 S/K 240606000343 K/A- 000040EA2.05'4il/4,5: 3 y 5 a.1
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7.. , -.. o SCENARI'0.NO. SS-ERP1.NRC -IC NO. . 77 a
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EVENT TYPE EMERGENCY T- s S , D W 4;
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-Time: 5 minutes ,s' yxw.
JV j $'N 1 4 s c. ,;.
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q ar ' An emergency , event has: occurred.1 Annunciator G-52 was the- first Wt.-- '; D ; Prior' to theXevent thez plant war at 100% steady' state,tequilibrium? ' c : conditionsk 1A MDAFW pump was :ihoperable andt tagged- out forl maintenance on MW (( ( , the motor. lRepai_rs, are estimateotto be" comp 1'etedDin \12? hours.-
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a o a 7 e .. .r M -l "\; ;y 4 4 J;y 1 , x052530BT1037R . Points: '1,'001 - -. Question Number: 1 , 3. _ . l\ - . . . n>
;\\ > i +
v'\\ y i The operator t. hat was assigned to placelthe, hydrogen k,V , ; k % ., a NE F u sanalyzere in serv:lco' reportsLthat ticither analyzer willE
,g . s
.4 ., , - .s Chemistry reports'that-.theylcannot'obtain q '
. operate . correc tly;,' ' , - .
e &
- 1. 9
..u.
.t
*H2' grab samples due'to faulty equipment. ,Basedion =g.
*i.ese5
.c .i n\\ - ' .
- ., , . : s .)
' C conditions a what would be the correct -action' to take?: , a-d >
e tj
,7
.(Circlelthei.correet response.) 1 >
j- . 1 q.,
; . ,, . ..N
.l' -t -
j A. Leavo.01.recombiners 2 off1until containment il 2J' A 4 concer,tration11s v.erified < 401 "t y
-a. ,
1-E ;i - , , p1 B. .Starc the H 2lrecombinersnand reduce' Hj lconcentrat,lon J
$ 4 I I in the containment by using post-14CA vent-systhm for i4 '
two hours. m ! t .- 1
+
, 1, <
< 1
' < =
.,"~ .
Reduce 112 concer,'tkation'in!the containment by,us.ing. O. ~ ',, 3 post-LOCA yent nystem;-.dolnot start recombiners. y 4 m $ mj . . .. . - . q h'i D. StartbotlhH2recombinerseventhbughlH2concentratilon' O'. 1 :l
. in containmentcistnot known.'c :e 7 s!
, i,
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;. ANSWER: EEP1 4.SCN (4 minutes)[ >
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s '052530CT1004R Points: -1.00- Question Number: 2
?
?
- . . ? a What component (s)...if any, must belo.perated by the operator d l,
< mi - to ensure completion of EEP-0-immediate operator actions?
--7
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,. m ANSWER: -EEP2-1,SCN (6: minutes)- ~..
d q; , ' M@ '
- Shut -valve 8152 .(to complete dA isolation perL EEP-0T attach ,
"g
- mentil)(1,0) - ,
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i What cornponent(s), if any, mat- be ~ operated by the _ operator . ; ito ensure two trains of SI. flow path _are aligned?_ .
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B '.. State the major component which initiated the. event. .
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l 1 . l ANSWER: EEP2-1.SCN-(4 minutes) < A' . Steam.orfeedbreak(lossofsecondarycoolant[(.5)
~B,- .B S/G (,5) ,
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- s 052530CT1014R Points:- l'.00 Question Number:- 4 5'
J If containment spray were to actuate, t it'should be stopped--
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- when: -(Circle the correct response.)o A. <10%fspray add. tank level,' spray add tank outlet 1 valves:
closed,'and pressure < 26 psig:(due~to; adverse-contain ' 1
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' B .5
<16 psig containment pressure regardless'of. spray add = .
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-tank level e
C. <10% spray add tank' level',' spray. add-tank outlet' 4' .
. valves closed,_'and containment sump recirculated for- '
-two hours
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}.-=. i 1 D. .-<10% spray add tankLlevel.jspray add tank outleti :-- l valves closed, and <16'psig containment pressure 1 ANSWER: EEP2-liSCN (4' minutes) 0 1
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y, 052530CT1015R- - Points:f -l',00f Question Number:- 6
-- Assvaing sta:.ic. plant' conditions remain the same. except : ,
those indicated in the'below: choices,-;which of thelfollowing ' 3 sets of conditions would allow'SI termination when the- -,; ifaulted S/G boils dry? .-(Circle the correct response,)-. ; [
< l 52* subcooling, twa SGs at 25% NR,. one SG at 0% WR < AW
~
A, , flow at 100.gpm,' RCS_ pressure attl600 psig and stable,, s and PZR level'at-62%
'B, 52' subcooling, two'SGs a*::50%:NR. one SG at 0% NR, l
' flow at--100 gpm. RCS. pressure 1600.psig and stable,fAFWi and <
PZR-level at 62% C. 52' subcooling,' 450 gpur AW flow, RCS pressure .1600 psig and stable, and-PZP level'12% '
.D.- 52' subcooling, 450 gpm AFWSflow,~.RCS pressure 1-1600 psig'
[! and decreasing.:and PZR level--62%: ? 4 ,
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ANSWER: 1EEP2 1.SCN (4 minutes) B , , , o
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s, y e Jr: < OS2530CT1016R Points: ci,50 f Question'Numberi -7. i Assume 30-minutes!of. operational time have elapsed:since the- d simulatorivas frozen.- The new'following' plant: conditions-now 0 exist: ' _The SI is still-in progress
- RCS.Th and:Te are-260*
'- RCS pressure is_-1600.psig and_ stable
PZR level is:95% and increasing
- Containment pressure is>50 psig
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- Containment radiation monitors;at current.valuet -)
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- Containment _ sump level is 6.5Lfeet e!!
- N-31 and N-32 are energized q
- Both source range SUR-' indicate .1.DPM ~
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Based on the'above conditions-(regardless<of;the yI circumstances'which l'ed to>their formation),; answer;ihe 1
,1 following questions: ,
A. Which FRPs are required to be implemented? ' S.; B. In wh'ta ~sequence are the FRPs required toIbe imple-mented? A
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.i ANSWER: EEP2-1.SCN (4 minutes) l A. FRP-P.1 (.5) !
FRP-Z.1-(.5) B. P.1 then Z.1 (.5) t
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Question Number: 8 i I How should steam flow to the TDAFW pump _bh; isolated?{ (Circle'- the correct' response.): A, _-It is not= required-to be isolated' bused o'n fault location
~B. Isolation from t'ne-MCB C. Isolation from the HSD panels A
D. Isolation!in the Main Steam valve. room" y a ANSWER: 'EEP2-1.SCN.(4 minutes). D j (NOTE: ; Based:on HQ MDAFW. pumps operable and'the need to: maintain' secondary beat sink ). s 1
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-Based on..the emergency event. the'first procedure used when- -
1 the ERP's.are entered should be: A .' ECP-0.0 B., EEP C' I
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'B. .
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' An' MSIV closure signal has' been. generated, yect one set of ' ;
4 MSIVs is indic'ating not; fully closed because: -(Circle theJ correct response.)1 ' 5 A .' They.did=not. receive'the MSIV. closure signal. ,. I B... ' Steam flow is~still being.directek to.the. turbine: '
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. ANSWER: EE2-1.SCN (4' minutes) ,
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.01/31/9d. A1ABAMA POWER COMPANT EXAM CRADING SHEET-
, EXAM NAME: RO.SS.EMER.NRC. CIASS NAME: LRP.89
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TOTAL POINTS: 10.50 DATE GIVEN: 01/31/90' - 8 STUDENT-ID / NAME: ** DRAFI **. /'*************** DRAFT ***************: l ( l : QUEST
.O-POINT ' '. POINTS
..VALUE- MISSED.
QUEST POINT' POINTS VALUE, MISSED ' l ;
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2 .;052530CT1004R 1.00 - .- J 3 - 052530CT1005R- '1;00 .
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. ENCLOSURE 5. ;
I SIMULATOR FACILITY FIDELITY _ REPORT Facility Licensee: Joseph M. Fahley, Nuclear Plant Facility. Docket Nos.: 50-348'and~50-364, Operating Tests Administered On: ' January 30, 1990 During. the . conduct of the simulator portion of. the operating tests, the-following items were observed:- Item Description None noted. I i I' h
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