ML20247L027
| ML20247L027 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/17/1989 |
| From: | Casto C, Curtis Rapp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20247L015 | List: |
| References | |
| 50-327-OL-89-01, 50-327-OL-89-1, NUDOCS 8908010127 | |
| Download: ML20247L027 (29) | |
Text
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UNITED STATES
[ La htc(""o
, NUCLEAR REGULATORY COMMISslOM
$ "' s . REGION ll
[ , )[b .101 MARIETT A STREET. N.W.
l e AT t.ANTA, GEORGI A 30323
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f ENCLOSURE 1 EXAMINATION REPORT NO. 50-327/0L-89-01 REPORT DETAILS Facility Licensee: . Tennessee VLiley Authority ,
Sequoyah Nuclear Plant 5N.157B Lookout Place
. Chattanooga, TN 37401 FacilityDockht'Nos.: 50-327 and 50-328 Facility License Nos.: DPR-77 and DPR-79 The examination v:as administered' at the U. S. Nuclear Regulatory Commission
' Region II office in Atlanta, Georgia.
~
, Chief Examiner:
dh Al /d-m C vt's W. Rapp //
7/6/A9
/Dafte ' Signed Approved By: . z/m 2t f ChWIes A. Casto, Chief
, <c d "7//Mff Date Signed Operator Licensing Section 1 Division of Reactor Safety Summary:
A written re-examination was administered on May 12, 1989, to one R0 applicant
~
who passed.
l 8908010127 890717 PDR ADOCK 05000327 V PDC L____
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, . REPORT' DETAILS, h <
- 1. Facility- Employees Contacted:,
- C. T. Benton,- Director.'-' Operator Training B. Lake,' Senior Instructor -i Simulator -
2L Examiners:
. *C, Rapp.
'R..McWhorter.
- Chief Examiner
- 3. - Exit Meeting
' Since the .re-examination was given at the Regional; office, no exit meeting wasLconducted..At the conclusion of the re-examination, a copy of the examination was given to members'of your. training: staff for review.
One weakness was noted during' development of the examination. Ths:
- reference material provided did' not: contain information on adverse containment criteria. During the. pre-administration review, it was stated this information'is presented but was not in any lesson plan. This information should be included in lesson plans to' insure it is consistently taught to'all license candidates.
The licensee.did not identify as proprietary any of the material provided
.to or reviewed.by the examiners.
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y________. . _
i i $ l U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _SggggYAH________________
REACTOR TYPE: _PWB-WEge________________
DATE ADMINISTERED: _@94QDflg________________
EXAMINLR: _BEGlgN_Il_______________
CANDIDATE: ___
IIE
_____f__Q_pf_______
INSIBuCI1gNg_IQ_g6NDID8IEL Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets, Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
- YB6UE_ _IQIGL ___SCgBE___ _y8LUE__ ______________CGIEGQBY_____________
- 9z99-- _ 9z99 ------_____ ________ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW O.00 0.00 ?. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 0.00 0.00 3. INSTRUMENTS AND CONTROLS
_22z99__ Z199tOO___________ ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
_2Z.00 % Totals Final Grade All work done on thi s examination is mv own. I have neither given nor received aid.
Candidate's Signature
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. . . . . . 1 o iNRCJRULES:AND GUIDELINES FOR LICENSE EXAMINATIONS '
'i DuringLthe: administration of this examination - thef f ollowing rules applyt - ;
-11 . Cheating' on the examination means an automatic denial of your; application and could:resultlin c morefsevere penalties.
s
- 2. JRestroom trips are to.be. limited-and only-one candidate.at a time may.
, leave. You'must. avoid'all contacts'with.anyone outsidefthe examination i
=,I
, Eroom=to avoid even the. appearance or possibility of cheating.
q
- 13. . UseLblack ink or~ dark pencil gnty to facilitate legible reprod6ctions. -j L4 . - Print your name -in the blank _ provided on the cover sheet of the examination.
S., Fill inithe date on the cover sheet of the examination (if necessary) .
[6. -Use'only the paper provided for answers.
- 17. ' Print.your name'in the upper right-hand corner of the first page of gach section of..the answerysheet.
B. Consecutively number each answer sheet, write "End.of Category __" as appropriate, start each category on a new page, write gely gn gne side-of'the' paper, and write "Last Page" on the.last answer sheet.
- 9. Number'each answer as ta category and number, for example, 1.4,-6.3.
- 10. Skip atileast threg lines between each answer.
- 11. . Separate answer sheets from pad and place finished answer sheets f, ace
-downlon your-desk.or table.
- 12. Use1 abbreviations only if they are commonly used in f acility;11tecattatg.
4 13. ' The point . val ue f or. each question is indicated in parentheses af ter. the question and can be used as a guide for the depth of answer required.
. 114. Show all calculations, methods, or assumptions used to obtain an answer I to mathematical problems whether indicated in the question or'not.
I 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER DLANK.
16, If parts of the examination are not clear as to intent, ask questions of L the examiner only.
l 17..You must sion the statement on the cover sheet that indicates that the o work . i s your own and you have not received or been given assistance in completing the examination. This must be done after the examination has
.been completed.
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f.*f g 28.JWhen yoticomplete'y'our; examination, you?shall:
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.Assembie yourfexamination as'fo1Iows:-
a,
-(1) ,.Ex a,m. questi ons - on top.
-(2) ' Exam' aids - figures, tables, etc.
g.,,
( 3 ) '- Answer pages including. figures which are.part.of ,the' answer..
- b. LTurn . iri your. copy. of .the - exami nation and a11 ' pages used to answer the - ex aminati on questi ons.
r
- c. Turn in'all scrap; paper and.the balance of th's. paper that you d'id
,not.use for answering'the questions.
- d. Leave the examination area, as. defined by the examiner. -If after leaving, you are found in this area while the' examination is still' in progress,..your license may be denied or revoked.
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r l- fSi PRINCIPLES OF' NUCLEAR-POWER PLANT;OPERNTIONI 'PAGE 2 bis -
THERMODYNAMICS. HEAT TRANSFER,AND Ft,UID FLOW'.
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1 PAGE I 3:
5"$ ~PLMT DE$iGN E INCLUDING SAFETY'AND' EMERGENCY S'YSTEMS_
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~(***** END OF CATEGORY 03'*****)
= - _ _ - _ = _ _- _ _ _ __ __- . _
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, f 4.~ PROCEDURES - NORMAL.-ABNORMAL.- EMERGENCY AND. PAGE. 5.-
" ' BSDIOLOGICAL CONTROL-
[GUESTION: x4.01 (1.50) a.- State'-the" parameter, including associated .value, which indicate' adverse containment conditions..(0.50) ti.
~
. Why1are various parameter limits referenced-in EOPs different under adverse containment conditions from those used before adverse containment conditions are reached? (1.00)
' QUESTION 4.02 (1.00)
With the reactor operating at 90% power,'the " Rod Control Bank ~
Limit Low Low" alarm comes in. After the alarm-is acknowledged and announced, what immediate operator action is required?
DUESTION 4.03- ( .1. 00 )
MULTIPLE CHOICE
- With the . pl~ ant operating in mode 1, " A" CCP i s inadvertently ~
' man. tally stopped. Select the one-action that is allowed by procedure to' restart "A" CCP with the minimum time elapsed since being.
stopped.
a) ' Restart. motor i mmedi atel y b) Allow motor to coast to a stop and then restart ,
I g c) Allow motor to cool while standing idle f or approximately l H 20 minutes and then restart l l
d) Allow motor to cool while standing idle for approximately 1 45 minutes and then restart I l
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% l4,' PROCEDURES - NORMAL. ABNORMAL. EMERGENCY'AND :PAGE 6-
[ RADIOLOGICAL' CONTROL r
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- QUESTION 4.04 ~( 1. 00 F l
L MULTIPLE CHOICE... .
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[i iconditions ~ has' .the~ highest priority- f or. . operator response?' -
l
' a)' CONTAINMENT red path b ) '. .
SUBCRITICALITY -- ' orange path
(
c) . HEAT SINK -. red p'ath
-- d ) . CORE COOLING - orange path DUESTION ..4.05 ( l'. 00 )
hULTIPLE CHOICE ~
- Select' the' LOWEST : emergency classification 'f rom the list below that frequires~ activation of the Technical Support Center.
.a)~ --
Notification of Unusual Event.
b), lert c) Site' Area Emergency
-d)
General-Emergency
(
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( * * * * *' 1:4TEGORY . 04 CONTINUED ON NEXT PAGE *****) j
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- 4. 4 PROCEDURES M JORMAL. ABNORMAL. EMERGENCY AND
- PAGE 17 g . RADIOLOGICAL CONTROL d
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? QUESTION 14.06' (-1. 00 ) , 1 r
p.
- M TCHING' '
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' Forg each; 1eakage descri. bed? in column. A, pick the applicable leakage d 2 4 classification f rom.' column- D. .Each leakage classification may be y
qused more than once or'may not be used at'all.- '
Column'A ' Column B i a.1 S/G tube-leakage- 1. CONTROLLED ,
i
- b.;
Pressurizer saf ety valve. seat leakage- 2. PRESSURE DOUNDARY-
? 1c .' RCP seal water-supply. 3. IDENTIFIED' l
id . - Seepage'through.a cracked RCS wide-range 4. UNIDENTIFIED 4 Tc' .RTDi wel d QUESTION' 4.07' ( 2. 00)' 1
~
E-O',[REACTORLTRIP OR:SAFETYLINJECTION, step 7, directs that main
- f eedwater (MFW) isolation- be verified. State'the 4 specific items
- that 'must ;be veri fied to accomp1'ish thi s step.
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-Q ESTION' 4.08 . ( 1. 00) i c< What:are the 2 reasons for transferring to hot: leg recirculation?
(1.00)- 1 QUESTION 4.09 (0.50)
'ES-1'.2, TRANSFER TO RHR CONTAINMENT SUMP, contains a caution to stop SI pump
. pressure. Why is this caution requi*ed during the recirculation mode'but not during the' injection mode?
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(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
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~4h '~ PROCEDURES '- NORMAL'. ABNORMAL.~ EMERGENCY AND PAGE '8' i '-RADIOLOGICAL CONTROL-l
. QUESTION 4.10 (1.00)
- ar Why;does ES-0.3,' NATURAL CIRCULATION COOLDOWN,. limit cooldown rate to 50-F/hr?'
- b. -What- is the condition stated in ES-0.3 that . requires minimum NC'subcooling to'.be increased from 50 F to 100 F7
-QUESTION < 4.11 (1.00)
"What'is~the-basis / reason for-the note in ECA-0.0, LOSS OF ALL AC, SPOWER, to monitor the~ status; trees for i nformation only and not to
_-implement FRGs?
QUESTION' 4.12 -(2.00)
Fler.FR-S.1, RESPONSE TD NUCLEAR' POWER GENERATION /ATWS, list the 4 required actions if 'the expected response is NOTLOBTAINED for the
'following immediate action stopt 1l Open Reactor' Trip-Breakers '
- a. Pn1 M-4 or M-6 l OUESTION 4.13 (1.00) cMULTIPLE CHOICE Which one of the f ollowing must authorize emergency dose limits?
a) RC Superintendent b) Shift Operations Supervisor l
c) Plant Manarar d) Site Emergency Director i
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(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) ,
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io ; 4. - - PROCEDURES -- NORMAL s ABNORMALo EMERGENCY'AND PAGE 9' RADIOLOGICAL CONTROL __
qc L . QUESTION ~ 4.14 (1 00) e
~With mi d~ loop . operation inf progress while in . mode 5, the. fallowing indications,are observed in'the control room
- 1. ' Erratic RHR motor current (oscillations between high
. current values and low current values)
- 2. Erratic RHR: pump flow F State the.2 immediate' operator actions required by AOI-14, LOSS OF RHR. SHUTDOWN COOLING.
, ~ QUESTION 4.'15 ( 1. 00')
MULTIPLE CHOICE Which one of - the f ollowing conditions requires tripping the affected RCP7 ;
a) Stator temperature ='240 F ,
l b) Motor amps = 600-A !
c) Seal water flow = 4 gpm
'd)' Lower' bearing temp = 230 F l 1
OUESTION 4.16 (1.50) 4 i
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- List 3 conditions that require emergency baration.
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1 14I PROCEDURES NORM L. ABNORMAL.'= EMERGENCY' ND LPAGEJ10 RADIOLOGICAL CONTROL L
v
,'7, QUESTION 4.'17 ; ( 1~. 00) p.-
. iMULTIPLE' CHOICE!
p eNhich one of the following'sy'mptoms requires BOTH a manual reactor 4 itrip 1 ANDf manual - saf ety 3njection-if neither_had occured
- 5. automatically y?
.a) : Containment pressure.= 1.3 psig-b) Pressurizer pressure i 1850 psig c) LPower = 30%, loss of flow in two loops d) . Power a= '49%, . pressurizer l evel = 92%.
,.+.
$ QUESTION f.4) 18 ' ( ,00) :
-MULTIPLE ~ CHOICE -1 Sel ectithe one f action that 'i s NOT. required by FR-S.1, RESPONSE TO ,
NUCLEAR: POWER GENERATION /ATWS, if turbine trip cannot be verified f ol l owi ng . reactor tri p.'.
a)- . Trip 1the generator output breaker b) Close:MSIVs'and bypasses.
.. c ) ' Trip turbine from main, turbine front standard-
.d) Stop.and PULL-TO-LOCK both EHC pumps 1
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@14b PROCEDURES -- NORMAL. ABNORMAL'. - EMERGENCY AND' PAGEc11 :1
, W RADIOLOGICAL: CONTROL m ,j <
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QUESTION' 4.19 (2.00)'
4 . . , . . . . . . . . ]
' List! the. component"or components t hat would be" used: to control each.
- of . the f ollowing . parameters ' f rom the auxili ary i control. rcom .or-backupf coritrols 'af ter evacuation ot. the control. room.
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-RCS pressure i -
, ' bs - Pressurizer level i t c. : Steam; ganerator'. f eed d.- Steam. generator pressure QUESTION' /4.20' :(1.00)
' List four means listed-in E-3,. Steam Generator Tube. Rupture, which
- may-be used:to identify;the ruptured generator.
~
fQUESTIO'N 4.'21 (1.00)
- Answer the following questians--in reference ta the performance of' Lthe Emergency Recovery Guidelines (ERGS).
a.- .
'If theicontingency action (RNO column) cannot..be performed or is not successf ul,_ and f urther contingency instruction. is not provided,. what1is the operator's next action?
b.- Undercwhat' circumstances may the operator proceed to the'next step prior.to the completion of a task in progress?
-QUESTION 4.22 (1.50)
PerLFR-C.1, Response to Inadequate Core Cooling, list three methods for-regaining core cooling.
(*****. CATEGORY.04 CONTINUED ON.NEXT PAGE *****)
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- g. LQUESTION 4.23' :( 1. 00) '
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? Perf RCI-3, Personnel . Monitoring, which one: ofi the; f allowing;is, requ' red i : '
r when a; pocket. chamber reads in excess of 3/4 scale?..
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l -- .'a ) ' Notify o
RC and remain i.n'the area'unti1 RC arrives.
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.. b ) .' Natifyr:the Shift Supervisor and. leave the area.
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~c) ' Fieport - to the. control. room and exchange: the pocket' chamber.
d)_ .
.. Report.to RC and have the. pocket' chamber reset.
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SEQUDYAH RO, EXAM REGION II ;
89/05/12 e
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- ;1,-MPRINCIPLES OF NUCLEAR
- POWER PLANT' OPERATION. PAGE"13
,. THERMODYNAMICS,-HEAT TRANSFER AND FLUID' FLOW JANSWERS"-# SEQUOYAH'.
-89/05/12-REGIbNII:
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-89/05/12-REGION-II lc I
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- .! ANSWERS '- - SEQUOYAH '-89/05/12-REGION.'II
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RADIOLOGICAL CONTROL
- ANSWERS 1--ESEQUOYAH' -89/05/12-REGION II-V.
A t l V l ANSWER: 4.01 (1.50)
- a. l'. Containment presrure (0.25) = or.) 2.80.psig ( 0.' 25 ) ' (accept l
" phase. B," - f or 4 ull' credi t) ~
ba < Adverse containment conditions may cause significant errors
-in ;the =-indications of . instruments. located ;inside ' containment.
(1.00)
REFERENCE ECCS. Lesson Plan 7.4.5,14.2, 4.4
'OO6040K304' OOOOO9K321. OOOO11K312 ...(KA'S)
ANSWE9 4.02 ( 1. 00)- j l
~. Borate' i mmedi atel y (0.75) atI.'>.or = tc 10 gpm,(0.25')
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REFERENCE ,
~GOI .5, c Normal Power Operations,. Precaution IV.C i 4.1
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-' I. REFERENCE.
G I GDI.-4, ' APPARATUS OffERATION, ,6C '-i MOTOR ? DPERATING AND ' STARTING LIMITATIONS , s. o,
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s . 062OOOA401'
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M, ANSWER' 4.04- ( 1. 00)-
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" REFER'ENCE iFR-0, STATUS: TREES-
' 4. 3, L 4. 5g 4. 2, - 4.1, - = 4.1, 3;O
'OOOO74G012 000074G011 OOOOO9G011 OOOOO9G012 000040G011
-000040G012. 2.(KA'S)
. . ANSWER. 4.05 '(1.00)
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=REi~ERENCE-
- Sequoyah Emergency Plan
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/ RADIOLOGICAL CONTROL-h ANSWER $6~-;SEQUOlAH -89/05'12-REGION-II / >
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- ANSWER ' ; 4'. 06
- ( 1.'00)
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'h REFERENCE MTECHNICAL: SPECIFICATIONS, .1. O, DEFINITIONS '
13.2, 3.1,.3.3,.3.2 l.
/ODOO37A2:0 000000G008 002000G011- .003000G011 ...(KA'S) i r !
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3 EANSWER .4.07; i2.00)
- a. MFW isolation valvos (0.25) - CLOSED -
(0.25)
'b.; ~MFW reg Walves (0.25) CLOSED;(0.25) ica .MFW' putnps 00. 25): -- TRIPPED - (0.25) ,
d '. . MFW-(0.25) indicates no flow (0.25) '
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- REFERENCE.
E-0,l REACTOR' TRIP.OR SAFE 1Y-INJECTION -
4.2 00000:G010 ...(KA'S) i
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- ANSWER- '4. 08 - ~ (1.00)
L(1) . Stop' baron' plating ( 0. 50) ..
.( 2) . Stop boiling in top of core (0.50) ;
l REFERENCE ES-3.1,-TRANSFER TO HOT LEG RECIRCULATION and SON lesson plan for EMERGENCY CDRE COOLING SYSTEM 3.O l OOOO11K313. ...(KA'S)
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- 4 p oROCEDUR,ES~'--NORMAL jBNORMAL.i EMERGENCY AND PAGE 19- -!
- g. RADIOLOGICAL CONTROL ,
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A N S W E R S -. ~ '- S E Q U O Y A H -89/05/12-REGION II y
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'ANGWER' 4.69' . (0. 50) j SI' pump'.miniflow;. valves:are shut (during recirculation but.open-(duri og linj octi on); (0.50) 4: ,
j t REF ERENCE c.:
.ES-1.W2,1 TRANSFER'TO RHR CONTAINMENT SUMP
- 3. 41 . . _
'l JOO!a000GO10- ...(KA'S) l tANSWER' 4.10 . ( 1. 00) , ,
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-a .:: . Prevent ~voidingTin' reactor. vessel; upper head ~ (0.50 each)~ j fh.7 1_ess than.-3 CRDM fans' running -
l i-REFERENCE- l 1ES-0.3, NATURAL CIRCULATION COOLDOWN i
- L 4 ;
r ' .OOOO74K301.
...(KA'S) !
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' ANSWER :4.11 ( 1. 00) .l
'None of the electrically. powered safoguards equipment used.to.
- restore' critical safety functions is operable (FRGs are written; l assuining at least one saf ety ' bus is. e..ergized) . l
' REFERENCE
.ECAaO.0, LOSS OF ALL AC' POWER .
.4.3:
OOOO55K302 ...(KA'S)
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)-'~4j' PROCEDURES-NORbAL? ABNDRMAL. EMERGENCYi 4ND o .PAGEl20-1p ~RADIOLOGIGSh CONTRO1 9; _
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.:ANSWERE' - SEQUQYAH . - 8 9 / 0 3 / 1 2 - R E 6 1 0 N' I I .- !
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l i L- ANSWER i4.-12L (2.00) il f; .i
! . < I i T1." Decrease' turbine load (O.50) !
I s 2. .- : Veri f y ' tauto rod - i nserti on' (0.25) ,'or. inanually insert rods' -]
-(0.25) (insert rods. (0.25) to maintairi T-avg -at T-ref (0.25)) j n 33. .
"Open reactor trip. breakers at M3. Set. Room (accept " locally") ,1 h' .(0.50) '!
sOpen,breakeracto control rod MG sets ~(at 480V Unit B'oardst
~
L (4. (0.25) and hotify inst-t3 close P-4-contact (0/25)
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L 1-REFERENCE FR-S.1,iRESPONSE TO NUCLEAR POWER GENERATION /ATWS 4.5- .,
>OOOO29G010 ...(KA'S).
'l ANSWER 4.13 (1. 00) .
d) i (REFERENCE .j
!EPIP-15, EMERGENCY ~ EXPOSURE GUIDELINES j 3.1 -l 194001A116 ...(KA'S)
ANSWER ~ ' 4.14 ' . ( 1. 00 )
- a. Reduce RHR. flow ( 0. 50) -
l
.' REFERENCE
'ADI-14, LOSS OF RHR SHUTDOWN COOLING, Section-D 4 '. 0.~ . .
LOO 5000G014 ...(KA'S) j i
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- .e : i 4 l, 40 PROff%DURES -' NORMAL. ABNORMAL. EMERGENCY AND PAGE 21
-rRAD7.? LOGICAL CONTROL
' NSWERb - SEQUOYAH -89/05/12-REGION II ,
l J
f ANSWER 4.15 (1.00). .
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REFERENCE :
- ADI-23,. REACTOR: COOLANT PUMP SEAL ABNORMALITIES -
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'003000A202 ...(KA'S)
ANSWER- .
4.16. (1.50)
' A:y three (3) of the following at (0.50) each:
1.. Failure of rod cor. trol cluster to fully insert following reactor trip (350 gal / rod per.ES-0.1) (0.50) 2 .' Uncontrolled increase.in reactor power ' (as indicated by Nuclear Instrumentation) (AOI-34) (0.50)
- 3. 'ATWS (FR-S.1) (0.50)
- 4. Tave <= 540 F and no SI (360 gal at => 75 gpm of => 20,000 ppm baron).
. 5. Tavp, . < 500 F and no SI (> 2500 at => 75 gpm of =>-20,000 ppm baron)
' REFERENCE CVCS Lesson Pl an, Enabling Objective 5 3.8 OOOO24G011 ...(KA'S)
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r4 '. - PROCEDURES ' NORMAL'. ABNORMAL;' EMERGENCY AND- PAGE.22
, [l&DIOLOGICAL CONTROL
.ANSWERSL-- SEQUOYAH- -89/05/12-REGION II ANSWER. 4.17, ( 1'. 00)
~ b )'
REFERENCE ECCS Lesson' Plan.
4 '. 3
-000009G010 ...(KA'S)
. ANSWER- 4.18 - ( 1. 00);
. .a )
REFERENCE-FR-S.1, RESPONSE.TO' NUCLEAR POWER GENERATION /ATWS
- 4. 5 -
eOOOO29G010 ...(KA'S)
ANSWER 4.19 (2.00) 1
- a. Pressurizer heaters (0.25) and pressurizer spray (0.25)
(normal or aunitiary spray) ll 1
- b. Centrifugal' charging pump (0.25) and charging flow control 1 valve (FCV-62-93C) (0.25) ci- MDAFW (0.25) and TDAFW (0.25) pumps
.d. Steam relief salves (PORVs) (0. 50)
REFERENCE SONP - ADI--27A. Control Room Inaccessibility at Power or Hot Standby,
' - Para. ItI.A, TV SON, Opeator Certification Tr ai n i n g ,, LP: ADI-27 (week 14-9),
objective 1 l' 3. 9 l
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" 4. - ' PROCEDURES-- NORMAL, NBNORMAL. EMERGENCY AND~ PAGE 23
- RADIOLOGICAL-CONTROL
, ANSWERS -- SEQUOYAH -89/05/12-REGION II.
l ANSWER 4.20 ( 1'. 00 ) i Any .f otir of the f al1owinos (0.25 each)
- 1. - Unexpected ri se .in. steam : generator 11evel
- 2. . Steam generator blowdown monitors (RM-90-120, 121,.or 124) ;
-3. -Rad Con survey of ma'in' steam lines ;
4; Rad Con survey of blowdown lines '
._5., iChem 1ao samp1e REFERENCE ;
SONP~E-3, Steam Generator; Tube Rupture, Step.3.
4.4
'00003BA203 ...(KA'S) '
1 ANSWER '4.21 ( 1. 00) .
a '. Proceed 'to the next step (or substep) in the lef t hand column (0.50) i
- b. Ensure the task in progress is proceeding satisf actorily -
j (0.50) ]
REFERENCE SON, Operator Certification Training, LP Introduction to Emergency
~R2covery Guidelines (ERGS) .(week 7-1), objectives E and F 4.1, 3.8 194001A102 OOOOO7G012 ...(KA'S)
. . ANSWER. 4.22; (1.50) l l .Any three.at 0.50 each i
-1; Reinitiation of high pressure safety injection
- 2. Rapid. secondary depressurization 3, RCP restart :
' 4 .1 Opening pr'_Jsurizer PORVs REFERENCE l
-SDN, Operator Certification Training, LP: Function Restoration !
LGuidelinas (week 7-8), objective C l p ~ 4. 0, 4. 5 - !
- l. 'OOOO74K311 OOOO74K103 ...(KA'S)
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QjNPROCEDURES - NORMhL.' ABNORMAL". ' EMERGENCY AND PAGE 24.--
- RADIOLOGICAL CONTROL :j 1
/ IANSWEMS'- -SEQUOYAH
--89/05/12-R$GION II.-
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? ANSWER- -4.23 (1.OOE l
,;Any theee at'O.50 each: .j'
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'SNP LRCI-3',.6.5
-2.l8/3.4 3.3/3.5 194001K103. .194001K104 _.a.(KA'S)
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