IR 05000277/1990190
| ML20062D831 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/07/1990 |
| From: | Conte R, Easlick T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20062D828 | List: |
| References | |
| 50-277-90-19OL, 50-278-90-19OL, NUDOCS 9011190064 | |
| Download: ML20062D831 (174) | |
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{{#Wiki_filter:e - h: ' , , t I l II ' NOV 7 1990 U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT - y ' Report'Nos,: 50-277/90-19 (OL) 50-278/90-19 (OL)
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Docket Nos.: 50-277 1 50-278
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i L -License.Nos,: DPR-44 i' I: , DPR-56
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Licensee: Philadelphia Electric Company , i P 0. Box 195 . O Wayne,_ Pennsylvania- 19087-0195 I i ' Facility Name: Peach Bottom Atomic Power Station Units-2 & 3 j Examination At: Delta, Pennsylvania
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Examination Dates:- -September 24 - 28, 1990 i. , ,g'
.# Examiners: T. Fish, Senior Operations Engineer 1 0. NcNeil, Examiner,-RIII (observer) 't B, Orton, PNL . CHIEF EXAMINER: M // -' 7 - fo ,
Theodore A, Eas11ck, Operations-Engineer- Da te -- l APPROVED BY: u//ani //- 7 -9d
' $1 chard J / Can.t(Chief, BWR Section- Date ,0peration!,; Branch,' Division of Reactor Safety , .
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EXECUTIVE SUMMARY
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iWritten examinations and-operating tests were administered to four senior 4 . reactor operator;(SRO) candidates (one of the SR0s received an operating test-
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A requalification reexamination written examination was administered to one
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a reactorfoperator and one senior reactor-operator during the examination week. f
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. (99thfindividuals" passed the written examination, s
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.The. candidates wers prepared for the. licensing examinations with the following e p- exception- -The candidates demonstrated a generic weakness in the' area of
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, (diagnoses, fThree ofcthe four crews eramined indicated some degree of diffi- j , .culty in their ability to, diagnose plart conditions based on control room ; ~1ndications. eThisiweakness -was -obser',ed during the running of the scenarios '
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. :and during';followtup. questioning of the candidates. This weakness was brought- 1
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,, DETAILS 1.= INTRODUCTION'AND OVERVIEW %
The NRC examiners administered replacement examinations to three= senior reactor operator-(SRO) upgrade candidates, one SRO instant candidate (operating . test retake) and six reactor operator (RO) candidates. The
. examinations were administered in accordance with NUREG 1021, Examiner !
Sta'ndards, Rev.,5, dated January 1,'1989. ~ _ _ . ;t
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.a member of training' department staff, the assistant superintendent of-
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' operations (an SRO) and- a member of the NRC -examination team. The NRC
: contractor was' included in.the pre-examination review via telephone
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'i conference, The scenarios used for the examinations were run on the plant specific simulator,.with the assistance of a facility supplied simulator- :
operatori-_ prior to:being administered 'All facility. individuals involved ; with' the: review of fthef examination materials. signed security agreements to
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s' er.sure that there was~no compromise of the examination, i L2.- ' PERSONS CONTACTED' i
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"2.11: U.S. = Nuclear Regulatory Commi ssion R. Urban,? Resident Inspector L2 '. 2 Philadelphia: Electric Company i c '*J. Franz,1 Plant Manager PBAPS
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*JE Cotton, Super _intendent-Operations
*F.~ Polaski, Asst. Superintendent Operations !
*E-. Till, .TraininggSuperintendenti :1
- *R. Andrews, Supervisor-0perations Training
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L*J;LLyter,; Senior Instructor-LOT ,
*R. Birley,sSimulator Instructor *D.-McClellan;: Senior Instructor-LOR *D Foss,. Regulatory J *L 'Sollenberger, NQA ( ?R.' Smith, Regulatory- ' ' * Denotes :those present at the exit cinterview on October 1,1990.
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3. EXAMINATION'RELATED FINDINGS AND CONCLUSIONS 3.1 Examination Results _ Replacement: '
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I l l l .- -Operating I 6/2 l 3/1 l 1 I i l l l . Overall I 6/2 l 3/1 1 1 F l- 1 J Requalification:
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1T R0 I sif6 l l Pars / Fail l --Pa s s/Fa il l.
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3.21 0perating Examination l J Th'e fol. lowing is a summary of generic strengths and we'aknesses noted '
-on the operating tests'. This information is-being provided to aid '
N '.the licensee in upgrading license.and requalificationLtraining programs. No' licensee written' response .is-required.
, l Strengths-
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- Crew' communications.
- Use'of Alarm Response Procedures.- s
- Crew briefings by the SR0s. during scer.arios'.
Weaknesses *
- Diagnoses -of plant conditions based on control room -indications.
. Knowledge of Emergency Response Procedures. (R0s only)
- Ability to use and interpret electrical drawings.
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- 3.3: Written Examination
The following is a summary of generic strengths and weaknesses noted from the grading of- the SRO and RO written examinations. This information is beinq r*ovided to aid the licensee in upgrading license and requalification training programs, No licensee written response is required.. Strengths
- Knowledge of basis for inhibiting ADS after boron injection,
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- Ability to determine conditions required for a rapid shutdown of the Main Turbine.
. - Knowledge of.EHC operation,
- Knowledge of-Core Spray interlocks, SR0sE0nly:= - Ability.to determine Emergency Classifications for a given event.
. Knowledge of T,'s. requirements for reactor coolant chemistry
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R0s Only:
-iMaility' to determine reactor feed pump response to a flow trans-mitter failure'. - Knowledge of methods for controlling Off Gas System release rates.
Weaknesses-
, -Knowledge of RCIC: turbine trips, ' '
Ability to determine available rod motion with a loss of RSCS power.
- KnowledgeLof:the basis for. initiating 0.W. Spray regardless of
' adequate core:coolir.g.
- Knowledge of sensing = points for' Core Spray line break-detection, i' SR0s'Only:
.Abi~lity to determine SLC operability per T.S. requirements.
- KnowledgeLof minimum time to abstain from alcohol preceding any normal scheduled shift.
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- Knowledge of requirements of a Special Report to the NRC concerning Radiologica' Environmental Monitoring.
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L Lic - Knowledge.of SRM count cate increase required to terminate fuel handling operations. [ ,
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!6 - Knowledge'of reason for plotting RPV pressure vs Rx Bldg. temper-
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ature in T-103,-Sccondary Containment Contro'l.
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'** '3.4 Requalification Written Examination
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M. . % ,, y A requalificition re-examination (written examination only) was F w 1: administered.to'one reactor operator and one senior reactor operator 1 4 w' . during the' examination week. Both individuals successfully passed 4 W i , the examination. Due to the limited number of operators examined, ! e f;h ,
.- ' generic; strengths and weaknesses were 'not evaluated. The NRC and j
~ facility grading was in agreement for both-examinations, i h,' ',
, _~ 3. 5 _ Reference-Material
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,In preparation for the written examination, the Chief Examiner a ~ requested tnat the'facil_ity send the Reference Material in advance F g' y. of.the160 day. required-time period. The contractor preparing the written: examination had asked the Chief Examiner'if it was possible' ,t k .
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-to have'the facility send the material early, in' order to ease a
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scheduling problem..LThe facility training department'was extremely y ,>" ! cooperative; and delivered the Reference Material by July 3,~ 199_0, f three weeks:before it'was required'. q w lW q..g (
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S' L0ne problem'with the Reference Material _was identified during +he n a . pre running of'the:simulatoriscenarios. The " Simulator Hardware / : W ' isof twareLMaterials": book, which includes malfunction cause and ' b' y f ef fects information;- was 'not' up-to-date. On: severalJoccasions, expected clarms and actions that were described 11n-the malfunction .i f book-did not occur;- This was brought:.to'the/ attention of theLfacil- 0
& J. * :ity simulator staff. The Chief: Examiner:was- informed that the -
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. training department' was aware of' the problem 'and -it is currently 'i
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:being addressed and corrected as partiof- the simulator certificat;on-process. j y .
4 '. - Exit Interview- ! q
'Q"A f l0'njSeptember-18,1990, aypre-examination review was conducted at the rRegion I Office; . The licensee was. informed that, although a' post-exami-
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j' t M ' nation review was not_ conducted, comments on-the written examination t
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The-exit. meeting was conducted on October ~1, 1990, at the facility train- l 1 ~ ing center. The licensee. representatives that attended the exit meeting
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are listed in section 2. of this re' port, The examination strengths and-weaknesses identified in section 3.2 were discussed. '
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, , _The control room staff was very cooperative in maintaining an environment conducive for: operating test administration.
. Facility-access went smoothly with good support from Health Physics and Security; i
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.During the course of the examination, an Emergency Operating Procedure
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-(EOP) tool locker was found unlocked. The candidate informed the shift supervisor, and it was : secured. At the exit meeting, the exam team-suggested that the tool locker be inventoried. The facility agreed.
-The final results of the examinations were not presented at ths. exit i meeting. The Chief Examiner stated that the results would be contained
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Attachments:
1.: Senior Reactor:Operf tor Written Examination-and answer key
?E L2 _ Reactor 0perator -Written- Examination and answer key [
, 3: Facility Comments on Written Examination
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4. .NRC' Response _to. Facility Comments ! 15 .~ fRequalification Examination Test Items -i 6. ,' Simulation-Facility Report i
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, ' I .' ;% . . . ATTACHMENT 1 l[P 'T- Senior Reactor 0perator Written Examination and-Answer Key.
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T , DRAFT COPY-
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U. S.-NUCLEAR REGULATORY COMMISSION -! SENIOR' REACTOR OPERATOR LICENSE EXAMINATION-REGION: l'
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FAtlLITY: Peach Bottom 2 & 3 > < :
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REACTOR TYPE: BWR-GE4~ ! i m
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?? , DATE ADMINISTERED: 90/09/24 o ,
, CANDIDATE:
; INSTRUCTIONS TO CANDIDATE:
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, \ , Points for.each question are indicated in parentheses after the question. To -;
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epass this examination, you.must achieve an overal1l grade of at least 80%. " Examination. papers wills be picked up .four-and onei half (41/2) hours after ! 4() s!'the examination starts.=
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s, ' i NUMBER.. 1 TOTAL CANDIDATE'S . CANDIDATE'S'
+ ., QUESTIONS POINTS POINTS OVERALL
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-HWE- 1100;00 :
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- All: work ldoneLon this examination is my own. I have neither given i norfreceived, aid,-
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' Candidate's' Signature
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--SENIOR ~ REACTOR OPERATOR' Page 2 !
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. QUESTION: 001 (1.00)
WHICH ONE l(1) of the following is the sequence of operation of the SLC System when .it-is manually initiated by the Control Room operators? i a. One SLC pump-starts / one squib valve fires b. _Two SLC pumps start / one squib valve fires c. One SLC pump starts / two squib valves fire
.d. Two SLC pumps sta-t / two squib valves fire ANSWER:- 001 .(1.00) 'c. (+1.0]<
REFERENCE: 1.~ Peach Bottom: LOT-0310, p. 5, L.O. 5.-
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2.K/A'211000G004-(4.1/4.1)-(1/I)
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QUESTION: - , 002 (1.00) '
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REGION 1
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FACILITY: Peach Bottom 2 & 3 ; REACTOR TYPE: BWR-GE4
> .; .DATE ADMINISTERED: 90/09/24 a CANDIDATE:
f INSTRUCTIONS TO CANDIDATE: :
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, ' Points for each question are indicated in parentheses after the question. To j ' -pass this examination, you must achieve an overall grade of at least 80%.
Examination papers will be' picked up four and one half (41/2) hours after-the. examination starts. ; l
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1 ' NUMBER T01AL CANDIDATE'S ' CANDIDATE'S
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QUESTIONS POINTS POINTS OVERALL
* GRADE (%) ............. .......... ............... ...............
n HbEG- 200,001 i
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? . 9 f: Sr.co- ,, . I s A1.l' work done1on-this examination is my own. I have:neither given
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' Candidate's Signature
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i REACTOR OPERATOR Page 2
, , QUESTION: 001 (1.00)
WHICH ONE (1) of the following is the sequence of operation of the SLC System-when it is manually initiated by the Control Room operators? a. One SLC pump starts / one squib valve fires b. Two SLC pumps start / one squib valve fires c. One SLC pump starts / two squib valves fire d. Two SLC pumps start / two squib valves fire
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ANSWER: 001 (1.00) c. [+1.0] REFERENCE:.
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1. - Peach: Bottom: LOT-0310, p. 5, L.0. 5.
.2. K/A 211000G004 (4.1/4.1) (1/1)
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t QUESTION: '002 (1.00)
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i-In accordance with T-200, " Primary. Containment Venting",'WHICH ONE (1) of-the following primary containment vent paths is the MOST preferred? a. 2" drywell-vent to SBGT b. 2" torus vent to SBGT i I c. 18". torus-vent to SBGT-d. 6" ILRT.line from torus .r RNSWER: 002 '(1.00) b. [+1.0] i l
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REACTOR OPERATOR. Page 3
' REFERENCE'- : -1. Peach Bottom: LOT 1560, pp.-22 and 23, L.O. 1.
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2. Peach Bottom:-T-200,.p. 5.
3. K/A 295010A101.(3.4/3.5) (1/I)
.295010A101- ..(KA's)
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QUESTION: 003 (1.00) ; Normal feed is lost to the Unit #3,120 VAC uninterruptable power supply.- WHICH ONE (1) of the following automatic system transfers will occur?
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a.- .3DD-T-A to E-134-T-B-(120 VAC), b. E.134-T-B (120 VAC) to 3DD-T-A.
~ ! c. E-134-T-B (120 VAC) Lto selected RPS motor generator, , I d. 3DD-T-A to selected RPS motor generator. :
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1 . L : ANSWER: ;003- (1.00)-
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l' -REFERENCE:- , u I
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LOT-0650,: L.'0. 7, FIG. T-LOT-0650-4. !
,c2.-K/A 295003K301-(3;3/3.5).(11/I) .
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. QUESTION: 004 .(1.00) >
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' Concerning' the operation of the Safety . Relief Valves' (SRVs), WHICH ONE (1) of
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. the following will occur when the " transfer / isolation" switch, in the 4 KV busLrooms, is placed in the1 TEST position?
a. The Control Room and the Alternative Control Station will have SRV indication and control.
b .- The Control Room loses SRV indication and control, only the Alternative Control Station will have SRV indication and control, c' LThe Control Room' and the' Alternative Control Station will have SRV indication but only:the Alternative Control Station will have SRV i
> control, d. The' Control Room and the Alternative Control Station will have 'SRV i indication but only the~ Control Room will have SRV control. ,
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. ANSWER: 004 .(1.00): !
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' REFERENCE:
11. Peach Bottom: LOT-120, p.,22, L.0. 3.c. ;
, g.E2.JK/A 239002K405'(3.6/3~.7)f(1/I)
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239002K40S: i QUESTION; 005iz(1.00)
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WHICH ONE' (1);of the following- syster;s is designed to prevent the' local fuel
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- a '. Reactor Manual ControlLSysten : l
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b. Rod = Worth: Minimizer-
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c. Rod Sequence Control System id. . Rod' Block Monitor. c
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i RE C10R OPERATOR' Page 5 _
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. ANSWER:~. '005_ (1.00)
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:1 REFERENCE:
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l. Peach Bottom:. LOT-280,'p. 4, L 0, 1.
2.'K/A 215002G004 (3.3/3.4)'(11/11) 215002G004 -..(KA's) - QUESTION: 006'-(1.00) During an emergency the Emergency Director may authorize personnel to exceed administrative radiation exposure limits. WHICH ONE (1) of the following is i the-allowable whole body dose that may be authorized to protect the health and safety .of the public? j a. 5' rem- , f b .' 15-rem 1
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, NNSWER: :006 ' . (.l .00) j u< .j a. .[+1.0); j
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LREFERENCE:
* 1. PeachEBottom: LOT-1730', p.ll, L.O. 5.
' 2. Peach Bottom:.EPR-670, Appendix 1.
3.- K/A 29.4001 All6.-(2.9/4.7)= , "l
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~ . . : REACTOR OPERATOR- Page 6 .. QUESTION:. 007';(1.00)-
WHICH ONE-(1) of the following describes the basis for inhibiting ADS immediately after boron injection? ' a.. To prevent.a loss of boron from the vessel resulting in a reactivity increase.
. b. To prevent a rapid injection of cold, unborated water resulting in a 3 rapid increase in power. l c.. LTo prevent rapid cooldown during depressurization resulting in a
-; reactivity excursion.
, d. .To prevent an increase in natural circulation resulting in decreased voiding-and an increase in power.
I ' ANSWER: 007 (1.00).
b. '[+1.0) l -,i ; 0 ! 1REFFMNCE:
, ~1.-' Peach Bottom: LOT-1560, L.O. 3. I' -2.: Peach Bottom: T-101, "RPV. Power Control", p. 8.
3 1K/A 295014A203-(4.0/4.3).;(1/1)-
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. QUEST 10N:'008
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(1.00):
n WHICH ONE!(1) of the following is the proper response of..the Control Rod ~ l L Drive' System following.the loss of.. instrument air?'
- a. .The. backup scram valves will vent the scram air header.
bi The-inlet / outlet ' scram valves fail closed.- . l c. ;The scram discharge volume vent and drain valves fail open. I d- : The flow control , valves- f ail closed.
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. PLANT-WIDE : GENERICS', 294001 Plant-Wide Generics ,.,
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~ IMPORTANCE K/A NO.- KNOWLEDGE R0 SR0 A1. 01 tAbility to obtain. and verify control procedure copy. 2. 9 3.4
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A1.02 .1 Ability to execute procedural steps. 4.2* 4.2* A1.03 tAbility.to locate and use procedures and station directives related to shift staffing and activities. 2.' 7 3.7
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A1.04 Ability to-operate the plant phone, paging system, and two-way radio. 3.1* 3.2* A1.05 tAbility to make accurate, clear, and concise verbal report s . 3.4 3.8
.A1.06 Ability, to maintain accurate, clear and concise logs, records, status boards and reports. 3. 4 3.6 ,
A1.07: tAbility to'obtain a'nd interpret station electrical and mechanical drawings._ 3.0 3 .' 7 A1.08 tAbility' to obtain and interpret station reference ; naterial such as graphs, monographs, and tables which contain: system performance data. 3.1 3.6
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A l'. 09 - TAbility to coordinate personnel activities inside the '
-control room. 3.3 4.2* > /1.10_ tAbility to coordinate personnel _ activities outside the control room.- 3.6 4 ', 2 * i y !
A1,11- -tAbility to direct personnel activities inside the i ( i , control room. , 3.3 4.3*
A1.12 tAbility-to direct. personnel activities outside the < control room. 3.5 4. 2 -i m A1.13 TAbility,to' locate control room switches, controls, and , indi
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, ' refl_ecting cations, theand to determine desired that they are correctly plant lineup.
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A1.14 tAbility to maintain primary and secondary plant > l- y ' chemistry within allowable limits. 2.9* ~ 3.4 L A1.15 tAbility to use plant computer to.obtain and evaluate i , parametric information on. system and component status. 3.2 3.4 A1.16 tAbility to take actions called for in the Facility Emergency Plan including (if required) supporting or acting as the Emergency Cnordinator. 2.9* 4.7*
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l' 4 K/A catulog: BWR 2-2
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T 1.4. . .: l' ATTACHMENT 4 s NRC Response to Facility Comments
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i FACILITY COMMENT RESOLUTION '
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PEACH BOTTOM EXAM 9/24/90 1. Facility comment accepted-on R0 question 31 and SR0 question 32.
Questions will be deleted.
l 2. Facility comment' accepted on R0 question 13 and SR0 question 14.
Question will graded with full credit given for answers 'a' OR 'b'. 3., Facility comment accepted on R0 question 52. Question will be deleted from the R0 exam only. 1
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NOTE:- Revised point totals: R0 98 pts l SR0 99 pts l l
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M " ATTACHMENT 5 g* M
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:r s REQUALIFICATION EXAMINATION' TEST ITEMS l
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s JWritten' Examination - Part B ,
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j@yfhM' ;0penjReference Examination:
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:- LOR-88-SB-N031(l' pt./ question); LOR-88-RB-NO3-(1 pt./ question)
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$"g . QNUM; . TEST ~ ITEM NO.' TEST ITEM NO.
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1: -157 157 I g"i a; -2 - 13:: -
-452 383-;
410 ci
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383 0 e .:4 L 338- 460 ! 51 188 - 188. '
' : s ' 6c ~ ' L585 585. ':
;7y :323 323 l}
u1 a; c8- 349 -349 ,:
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, 19- > 404 404 ;i
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1931 193
:1E 1 t449? 449; ,:
} ld s-: , 112E ' '
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452' J!
,;13? ' E928? 476- :d
? ',>115l
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i14! L ::138 '- 1338 j
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l17? ! 1616: ?444 M
!181 1633: 21622- d .., .
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, : Written! Examination!- Part4 Al v
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!StadciSihula' tor Examination:- LNo.1~ ' Loss of:.High. Pressure Feedwater (0516R)' '
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20NUM , ; TEST-ITEM NO. >
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-Attachment 5. 2 ATTACHMENT 5 REQUALIFICATION EXAMINATION TEST ITP's Static Simulator Examination: No.2 - Recirc Pump Seal Failure (0511R)
LOR-88-RA2-N3 / SA2-N3 (1 pt./ question) ONUM TEST-ITEM NO,
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1 978
'2- 979 -
3 981 4 982~ 5 993 6 998-7 999 984.(SRO only) ! 8 1611. 985. (SR0 only) 9 1635 - 126 (SR0 only)
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ATTACHMENT 6 l * SIMULATION FACILITY REPORT ! Facility Licensee: Philadelphia Electric Company-y Peach Bottom Atomic Power Station Units 2 & 3 Facility, Docket Nos.: 50-277
- 50-278
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Operating Tests Administered on: September 25-28, 1990 j This formLis.to be-used only to report observations. These observations do not l constitute audit or inspection findings and are_not, without further-vcrifi- 3 cation and review, indicative of non-compliance with 10 CFR 55.45(b). These q
. observations do not. affect NRC certification or approval of the simulation i Efacility other than to provide ~information which may be used in future evalu- 1-ations'., No' licensee action is required in response to these observations. ! ,
a
:During the preparation'and administration of the-operating tests,gthe l
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following items were observed:
-ITEM: DESCRIPTION- -
Recire,- Procedure SC 6C.1.D-2 directs the operator to depress the "A"
:and "B" UPPER RECIRC FLOW LIMITER reset pushbuttons and hold !
s , until ~ repositioning of_.the~ LEVEL CONT MODE switch is complete,
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j This wi.ll prevent a spurious initiation of a Recirc-Pump Runback :1 if any _ feed pump is less than 20*4 rated flow.- During the r.unn-- ~l
:ing off azscenario .thisl action was taken by the operator, per" i
_ procedure, and the runback still occurred.' This'is a known j simulator deficiency.
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LRad. Monit. The l'0f f- Gas ' Stack Radiation- Monitor" indicated high- during a scenario with normal radiation levels in the Off Gas stack.
The simulator' instructor stated ' that this -occurs from time to
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time for no apparent reason.
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* :- Mal f ; The " Simulator Hardware /Sof tware Materials" book, which
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includes malfunction cause and effects-information, was not up' to date. On several. occasions'expe.cted alarms and actions that- .,.
; ' Lwere described in the malfunction book did not occur, This is- i currently being' addressed and corrected as part of the simulator p certification process.
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REACTOR OPERATOR Page 7 L ? ANSWER: 008 (1.00)-
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1. Peach Bottom: LOT 0070, p. 33, L.O. 6.b. -
'2.. Peach Bottom: Facility Question Bank, No. 840, Book 1, pg 145.
3. K/A 295019K201.(3.8/3.9) (11/11) 295019K201 ..(KA's)- i QUESTION: 009- (1.00). ;
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-WHICH ONE:(1) of the following WILL trip the Recirculation Pump Drive Motor
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Breaker,.but NOT lock.the Scoop Tube simultaneously?. , i
" 'a. Suction Vaive 851 open.
b.; Loss of speed control signal, , .. Lc. Lube oil temperature 215 deg F.
d.. Lub'e oil pressure.27 psig for'18 seconds. , f i
.i LANSWER:- 009 ,(l.'00)- '
a..[+l'0)1
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s. j J} REFERENCE: j s s 1. Peach' Bottom: LOT-0030, pp. 37-38,'L 0. 4.g.
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! '2.. Peach. Bottom:-Facility Question Bank, No. 849 .
f -3. K/A'20200lK407-(2.8/2.9)c(II/II)- 1
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tREACTOR' OPERATOR Page 8 t b
: ' QUESTION: 010. (1.00) .
Duringf a transient all:-initiation signals have been received to start the ADS 105 second timer. WHICH ONE (1) of the following will reset the 105 second timer?. ,
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a. Drywell' pressure decreases to 1.5 psig ,
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. b., Reactor water level increases to -145 inches
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: c. 'A' andB' core spray pumps trip off
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'd. -. Transfer / Isolation switches ~ moved to the ' Emergency' position ANSWER: '010 (1.00)'
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i REFERENCE. ; 13, L.O. 5.
' 1.-. Peach' Bottom: t0T-0330, p'. x 2. K/A 218000A405:(4.2/4.2)_(1/1) ij 218000A405 ...(KA's) l
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, LQOESTION 011 ..(1.00)_.
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: WHICH 0NE (1),of:thejfollowing' Main. Turbine Stop Valves has:a servo' valve !
for position control: rather than- a solenoid operated test valve? q a. '11 ', b.. 2 1c, '3 '- d. 4
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REACTOR OPERATOR Page 9 ANSWER: . 011 (1.00) b .1 ( + 1. 0] . REFERENCE: '
"1. Peach ~ Bottom: LOT-0560, pg 30, L.0, 3.a.
' 2. K/A 245000G007 (3.5/3.6) (11/11) ! 245000G007 ..(KA's) l QUESTION:- 012- (1.00) WHICH ONE (1) of the following conditions would require a rapid shutdown of the main turbine?- a;- Loss of. the Main Seal Oil and Recirculating Seal Oil Pumps.
i LossEof the Seal Oil Vacuum Pump. I b.-
.c t . Loss of DC power to the Emergency. Seal Oil ' Pump. -l r .- .
Ed. Lossiof the: Main Seal' Oil: and -Emergency Seal Oil Pumps. ; e
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. ANSWER: .01'2 (1.00) l id. '[+1,0] .
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- REFERENCE:: l q
4 1. Peach-Bottom: LOT-0626;'p'.-16,.L.0.-2. . . 2. Peach Bottom: Facility Question Bank, Book II, No. 1232, p. 306. q 3 1K/A 245000K502 (2.8/3.1)~(II/II)' 1245000K502 ..(KA's)
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QOf,ST10N: 10131 (1.00).
LTheIEmergercy Service Water (ESW). pumps have auto started due to a diesel
. generator start. After 2' minutes the 'B' ESW pump is secured. WHICH ONE (1) ': of. the following actions will' occur if the 'A' ESW pump motor trips on -
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a. 'B'; ESW pump ~will start af ter a 25 second time delay..
. b .1 ECW pump.will immediately. start. !
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c. 'B' ESW pump will immediately start. t d.. ECW pump will start after a 20 second time-delay.
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' ANSWER: '
013 -(1.00)- o' 9329 :
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a.gp)(+1.0)1 3 .j i y REFERENCE:' q LliPeachBottom:LLOT-0680, p. 8, L,0. 2. ! f2.;K/Ai264000A306 (3.1/3.2);(I/I) , i
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REACTOR OPERATOR. Page 11 QUESTION: 014 (1.00) WHICH ONE (1) of the following is the Technical Specification definition of a-Source Range Monitor Channel Functional-Test? a. A qualitative assessment of channel response when the channel sensor is exposed to a source of neutrons.
b.. The injection of a simulated signal into the instrument primary sensor to verify the proper instrument response, alarm, and/or initiating action. .
.c. The comparison by visual observation of one neutron monitoring channel to two other independent neutron monitoring channels measuring the same parameter.
d. Adjustment o_f the neutron monitoring chani .1 such that it responds with the necessary range and accuracy to uown values of the neutron level which the channel monitors.
. ANSWER: 014 (1.00) b. '[+1'.0)
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REFERENCE:- 1. Peach Bottom: Unit 2 Technical Specification, sectionl.0, p.3.
2.' Peach Bottom: LOT-1810, pg 11, L.0.-2..
'3. EQB No.4577 .(Idaho) -4. K/A-215004G005 (3.2/3.9) (1/I) i '215004G005 ..(KA's)
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REACTOR'0PERATOR' Page 12 i
' . QUESTION: _015 (~1. 00)_ ~ ' ;The' Unit'2 High Pressure Coolant Injection (HPCI) System has isolated on low steam pressure. WHICH ONE (1) of the following valve isolations is NOT ,.
I co_rrect?::
-a. Steam. supply valves, M015 and -16, close. l ~ 'b. Suppression pool isolation. valves, M0 57 and -58, close. !
c. Steam line warm-up valve, A0-4807, closes, d. Exhaust line drain valves, A0137 and -138, close.
, ANSWER:. 015 (1.00). ;
:d. [+1.0)
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REFERENCE:!
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11.JPe'achBott'om:LLOT-0340,p.20,'L.0.5.-
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4 a q.c LQUESTION:e016c :(1.00) 1-w iDuring a' Reactor Core Isolation Cooling'(RCIC) operability test,JWHICH ONE N
. (1);.of(the following_ will cause the RCIC turbine to' trip?
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a'. . Turbin'e!. speed is-5500 rpm.
l b.' ! Pump suction pressure:is 17:. inches _Hg vac. r
! ; : c. , 1 Turbine exhaust-pressure'is 48 psig.
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.i [d . . RCic area temperature is 175:deg F. !
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REACTOR OPERATOR _ Pege 13
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iANSWER:' '016' (l.00)_ g b. . [+1.0):
-REFERENCE: I 'l'.- Peach' Bottom:. LOT-0380, pp. 17-18, L.0, 2.
2. K/A 217000K404 (3.0/3.1) (1/I) i 217000K404 ..(KA's)
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QUESTION: 017 (1.00) WHICH ONE (1) of the following is the reason for never operating the RCIC turbine below 2200 rpm? a.- 2200. rpm is 'a turbine critical speed.
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, : ty.- Low speed-will'cause water hammer in the pump discharge line. ;
c. Thel turbine needs. sufficient speed to maintain lubrication.- ! y i
:d. Instability, occurs.in the; turbine speed control logic.
, yANSWER:- 5017l-(1.00)_ *
' =c. [+1.0]- _
i REFERENCE:L tu ;
' , tl.1 Peach Bottom: LOT-0380,' p. 26,'L.0. 8.
2. K/A 217000A208 (3.0/3.1)--(I/I).. 1217000A208 ..(KA's) L
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- QUESTION
- 018 (1.00)
WHICH 1 (1).of the following describes the function of the Shutdown Cooling Valve Reset pushbution during the recovery of a shutdown cooling isolation? a. Automatically opens the inboard LPCI injection valve following a low reactor level isolation, b. Automatically opens the inboard LPCI injection valve following a high reactor pressure isolation, c.. Allows manual operation of the inboard LPCI injection valve following a low reactor level isolation.
d. Allows manual operation of the inboard LPCI injection valve following a high reactor pressure isolation.
ANSWER: 018 (1.00) i t
~ ' c. [+1.0)
LREFERENCE:
,1.. Peach Bottom:' LOT-370, p. 18, L.O. 7, 2. K/A 205000K502 (2.8/2.9) (11/11)
205000K502- ._(KA's)
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' -QUESTION: 019 (1.00) '
WHICH ONE- (1) of the following describes the purpose of the Main Adsorber Bed
.in the Off-Gas Recombiner System?
a. Traps particulate matter. [ b. Dilutes the. hydrogen gas concentration. , c.- -Adsorbs entrained moisture, d. Delays radioactive decay products.
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REACTOR OPERATOR- Page 15 l 3 i
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ANSWER: 019 -(l'.00) -l l l
:d o (+1.0)
t ~. REFERENCE: ,
;1. Peach Bottom: LOT-0510, p. 10, L.0. 2.
.,2.-271000K406 (2.7/2.9) (11/11) i 271000K40s ..(KA's)
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QUESTION: 020 (1.00). 4 While a-primaryy: system is discharging into the reactor building, T-103 !
'QSecondary Containment Control" directs the operator to manually scram the plant before the temperature in the secondary containment reaches an action i level . . WHICH ONE-(l) of the following is the basis for the manual scram? ;
a '. . Limits radiation release, from secondary containment. - b. Reduces'the driving force of the:1eak. .
.c.. ' Allows personnel access:to the' reactor building before the i , Ltemperature becomes.too high.
. .e d.. Avoids the need for-an emergency blowdown.
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o ANSWER:t .020. ;(1.00)' !
% " b. :(+1.0]< , .REFERENCEUl ' .
J ' ls , 21. Peach?Bott'om:cT-103 " Secondary Containment Control,--Bases", pg 8.
h 2. Peach Bottom:: LOT-1560, L.0.13.
1 , 13. K/A 295032K302 (3.6/3.8)s(III/II). p
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-QUEST 10N:~021 _(1.00) f e- T 101, "RPV LControl", directs 'that RPV pressure be controlled between 1030
:and.930 psig with SRVs if any SRVs are cycling. WHICH ONE (1) of the !
following is the basis for maintaining RPV pressure below 1030 psig? ! Controls RPV pressure to within the capability of~high pressure
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injection-systems to inject.
b. Controls RPV pressure below the lowest SRV lift pressure, c.- Prevents RPV damage due to cyclic loading. 1 I
.d.- Prevents _SRV seat damage from cycling. l l
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. ANSWER: 021 (1.00) i b. (+1.0)
i REFERENCE: 1.;PeachLBottom: T-101 "RPV Control - Bases", pg'13. i 12. Peach Bottom:JLOT-1560, L.0, 3.
3. K/A!295007K306~(3.7/3.8) (1/I) 295007K306 ..(KA's)_
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7 + REACTOR OPERATOR: .Page 17 QUESTIONi 022 (1.00)-
' = Uuring the' performance of OT-101, "High Drywell Pressure", which requires maximizing'drywell cooling, the plant operator inadvertently trips two chillers while raising their demand limiter settings. WHICH ONE (1) of the ' .following describes the status of-the automatic RBCCW swap cver to Drywell r : Cooling Water (DWCW) loads?
a. lThe swap-over would not occur'due to DWCW header pressure being normal.
' b. . ine ' swap over would not occur due to rower being available to the
- ;, load centers supplying the chillers.
, c.- The swap-over would occur due to loss of power to the chiller motors.
d.. The swap-over would occur due to the drop out of the chiller motor contacts, t b ,
' ANSWER:: LO22-(1.00).
~ bl. [+1.0),
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1. Peach Bottom: LOT-150,= pg-12,.L.O. 4.
- 2. Peach Bottom
- Facility Question Bank, No. 1566, Book II, pg 513.
L3. K/A 295024K218 (3.3/3.4)-(1/I)
'295024K218L . . (KA'.s).
LQUESTION:LO23,(1.00); LWHICH 0NE. (1). of the following supplies cooling water to. the recirculation ~
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motorigenerator. set lube oil system?
. a .- -Service Water
; *h Reactor Building Closed Cooling Water c. Drywell Chilled Water
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,Jd'.- Turbine' Building Closed Cooling Water
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n) ANSWER:1 023 (1.00) a. [+1.0)
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REFERENCE:
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1. Peach Bottom: LOT-0030, pg 21, L.O. 1.
- 2.: Peach Bottom. Facility Question Bank, No. 69, Book 1, pg 42.
3.;K/A 20200lK107 (3.1/3.2) (11/11)
:20200lK107 ..(KA's)
LQUESTION: 024 (1 00)
. " WHICH ONE'(1) of the following is the plant response to a loss of stator waterLcooling?- 'a.- The recirculation pumps will runback to minimum at the rate of 1% per second.
A turbine trip will ~ occur.if generator amps are not less than 7726
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amps in three and a -half minutes.
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'c. EHC.will runback generator _ load to zero at the rate of 1% per second.
-d. , A turbine trip'will occur if generator amps are not less than 26530 amps'in one minute.
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ANSWER: 024' (1.00) o' b? [+1.0];
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REFERENCE:' l.' Peach Bottom: LOT-0630,'pg.14, L.0. 6.- 2. Peach Bottom:4 Facility. Question Bank,_ No. 627, _ Book I,. pg 138, 3.LK/A1245000K605-(2.9/2.9) (11/11).
'245000K605L ..(KA's)
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- REACTOR OPERATOR Page 19 i /T -QUESTION: 025 -(1.00) \' .. .
Given'the~ following initial . conditions:
. - Reactor = Power 100% - CHC Load Set- 105% - Max. Combined Flow- -110% > - EHC Pressure' Set 920 psig Averaging Manifold 950 psig , .
3, ;WHICH.ONE-(1) of the following is the result of the load limit potentiometer -l
? being reduced to 92%?_'(See attachment I) ;
t-a. Control Valve Position - 92% Steam Flow '! Bypass Valve Position- - 0% Steam Flow b. Control' Valve Position--- 92% Steam Flow-r Bypass l Valve Position ; - 8% Steam Flow' !
! : c.: - Control. Valve Position'- 100% Steam Flow Bypass l Valve Position -
0% Steam Flow .; d.. - Control Valve Position - 100%. Steam Flow Bypass Valve Position. - 8% Steam Flow-i ,
,j 1-i d ; 'ANSWERic [025 ' -(1 ~ 00).. . ,j
b. , [+1.0) i REFERENCE-El./ Peach Bottom: LOT-0590,'T-LOT-0590-6, L.0. 4.. . . . N 1, , .
;2) Peach Bottom:LFacility Question Bank, No.649, Book'11, pg 113.
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QUESTION: 026 (1.00) ! WHICH ONE (1) of the following is the reason that LPRM detectors are not
' required to have gamma discrimination?
a. All gammas are significant in the power range.
s-b. Discrimination is achieved by electrical circuitry in the APRM cabinets.
.c. The detectors do not detect gamma radiation.
d. Fission gammas are proportional to power.
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ANSWER: 026 (1.00) d. [+1.0) REFERENCE: i 1. Peach Bottom:-LOT-0260, pg 6. L.0. 3.
- -2. Peach. Bottom
- Facility Question Bank, No. 1069, Book I, og 202.
3(K/A215005K501.(2.8/2.9)(1/l) 215005K501 ..(KA's)
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QUESTIONi 027 (1.00)
' .WHICH ONE (1) of the following conditions will cause a -half-scram?
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.. a . APRM E is downscale, IRM G:is INOP,' mode switch is in run.- i b. .lRM H-reading 35 range 4, mode switch is in start up, detector is
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' a c. : APRM F'is downscale, IRM D is bypassed, mode switch is in run.
lie- Td. IRM B reading 115/125ths of scale, mode switch is'in start up.
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i REACTOR OPERATOR Page 21 ANSWER: 027 (1.00) a. [+1.0] REFERENCE: 1. Peach Bottom: LOT 0270, pg 11, L.0, 2.
2. Peach Bottom: Facility Question Bank, No. 1103, Book 1, pg 226.
3. K/A 215005K605 (2.9/3.1) (1/I) 215005K605 ..(KA's) l QUESTION: 028 (1.00) WHICH ONE (1) of the following sets of valves receive an automatic control signal as a result of a trip of the Main Turbine? a. Heater Drain Valves and Bleeder Trip Valves, b. Bleeder Trip Valves and Extraction Steam Air Operated Isolation Valves.
c' . Extraction Steam Air Operated Bleed Valves and Bleeder Trip Valves, d. Moisture Separator Drain Tank Motor Operated Isolation Valves and the l Bleeder Trip Valves, j i i ANSWER: 028 (1.00) c.-[+1.,0] l REFERENCE: j 1. Peach Bottom: LOT 0530, pg 15, L.O. 4. I 2. Peach Bottom: Facility Question Bank, No. 1144, Book'll, pg 243. ) 3. K/A 295005K205.(2.6/2.7) (11/11) ; 295005K205 ..(KA's) I i
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' . REACTOR OPERATOR Page 22 r QUESTION: 029 (1.00) A, B, and C Reactor Feed Pumps are operating in master auto, three element control, with A level selected. Reactor level setpoint and level are at 23 inches. Reactor power is 95%. WHICH ONE (1) of the foliowing is the response of the feed pumps and reactor level when the B Feed : low Transmitter output fails low? a. Feed Pumps trip off, reactor scrams on low level, b. Feed Pump speed increases, reactor scrams on high level. , c. Feed Pump speed decreases, reactor level stabilizes below setpoint.
d .- Feed Pump speed increases, reactor level stabilizes above setpoint.
! ANSWER:' 029 (1.00) d. . [+1.0) ~
' REFERENCE:
1. Peach Bottom: LOT-0550, pg 17, L.0. 16.
2. Peach Bottom: Facility Question Bank, No. 1146, Book II, pg 246, 3. K/A 259002K604 (3.1/3.1) (1/1) , 259002K604 ..(KA's) P
' QUESTION: 030 (1.00)
A problem has occurred with the Unit 2 Generator Hydrogen Cooling System.
The problem was c.orrected but hydrogen pressure has decreased to 45 psig.
-The plant is currently carrying 950 MW of real load. WHICH-ONE (1) of the following is the maximum reactive load that can be-carried at 950 MW? ASSUME a lagging power factor. (seeattachmentII) La. 360 KVARs-b. 380 KVARs c. 400 KVARs s
'd. 420 KVARs
REAt; TOR 00ERATOR Page 23 ANSW'ER: 030 (1.00) d. [+1.0) ,
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- REFERENCE: '
1.' Peach Rottom: LOT-0600, pg 36, T-LOT 0600 27.
2. Peach Bottom: 50 50.1.A 2 3. Peach Bottom: f acility Question Bank, No.1219, Book 11, pg 300.
4. K/A 245000K507 (2.6/2.9) (11/11) 245000K507 ..(KA's) h i
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QUESTION: 031 (1.00) ; Reactor operation is allowed to continue following a p of'the "B"
- recirculation pump. WHICH ONE (1) of the following iethods will determine l f
True Core flow? a, A Loop flow B Loop flow , b. A Loop Flow - 1.95(B Loop flow) c. A Loop flow + B Loop Flow
'd. A Loop flow - 0.95(B Loo 410w)
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ANSWER: 031 (1.00)- d.. (+1.0).
, REFERENCE: 1. Peach BotAom: LOT-0030, pg 47, L.0. 8.
2. K/A 295 OlA203 (3.3/3.3) (11/11) 2950 A203; ..(KA's)
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_ _ _ _ _ _ _ _ _ REACTOR OPERATOR Page 24 OVESTION: 032 (1.00) WHICH ONE (1) of the following describes how the Scram Discharge Volume Vent and Drain Valves respond during a reactor scram.' a. Solenoid operated valves energize to reinove control air from the operators of the vent and drain valves, closing them, b. Solenoid operated valves de energize to remove control air from the-operators of the vent and drain valves, closing them, c. Solenoid operated valves energize to supply control air to the * operatars of the vent and drain valves, closing them.
d. Soleno,d operated valves de energize to supply control air to the operators of the vent and drain valves, closing them. . ANSWER: 032 (1.00) b. (+1.0) REFERENCE: 1. Peach Bottom: LO1 0070, pg 38, L.O. 4.f.
2. K/A 20100lK406 (378/3.9) (1/11) 20100lK406 ..(KA's)
REACTOR OPERATOR Page 25 QUESTION: 033 (1.00) Orywell pressure increases to 2.1 psig during a core traverse by the TIP system. WHICH ONE (1) of the following describes the response of the TIP system? a. It continues its sequence for the present core position, then * reverses and withdraws into the shield, b. The ball valve. closes regardless of the position of the probe, shearing the probe and isolating the TIP system.
c. The TIP system shifts to manual reverse, withdraws the detector to the shield, and the ball valve closes, d. The shear valve fires regardless of the position of the probe, shearing the probe, and isolating the system.
ANSWER: 033-(1.00) ! c. (+1.0) REFERENCE: 1. Peach Bottom: LOT-0290, pg 18 L.O. 3.
2. K/A 21500lK401'(3.4/3.5) (111/111) 215,00lK401 ..(KA's)
! QUESTION: 034 ('1.00)
WHICH ONE (1) of the following. components allows cooling water flow into the reactor from the control rod drive mechanism when a control rod is fully , withdrawn? a. Stop: Piston Seals b. Unlocking Handle Valve. Disk c.- Drive Piston Seals - d. . Cooling Water Orifice
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REACTOR OPERATOR Page 26 ANSWER: 034 (1.00) - b.~ [+1.0) REFERENCE: 1. Peach Bottom: LOT-0060, pg 19. L.O. 4.a.
2. K/A 201003G007 (3.6/3.6) (11/111) 201003G007 . . (VsA's )
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QUESTION:.035 (1.00) WHICH.ONE (1) of the following is the reason for the Reactor Water Cleanup Drain Header Control Valve (CV-55) to isolate on high downstream pressure?
.
a. Protects the Filter Domineralizers from high flow.
b. Protects downstream piping from overpressurization.
c. . Prevents the system from draining.
d. ' Prevents high flow rate's to Radwaste. [ l ANSWER: 035- (1.00) b. [+1.0) REFERENCE: I 1. Peach Bottom: LOT-0110, pg 10-11, L.0. 7.
'2. K/A 204000K402 (2.7/2.9) (11/11) 204000K402- ..(KA's) , ;
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: . QUESTION: 036 (1.00) 'WHICH ONE (1) of the following conditions will cause a recirculation pump i runback to 60%? ASSUME reactor is at 100% power, a. Recirculation _ Pump *A* discharge valve drifts closed.
b. *B* Feedwater Pump trips off and reactor water level drops to 19
' inches.
, c.- "A" Feedwater flow signal fails low.
d.- Total feedwater flow is 93% and "C" Condensate Pump trips off.
, ANSWER: 036 (1.00) ld e (+1.0) REFERENCE: 14 Peach Bottom: LOT-0040, pg 17, L.O. 3.b.
-2.~ K/A 202002K402^(3.0/3.0).(1/1) 202002K402~ ..(KA's)
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QUEST 10N:J037- (1.00) WHICH ONE-(l);of1the following conditions will cause' the MSIVs to isolate? :
: ASSUME the. reactor. is initially at full power.: L a.- Reactor water level 150 inches.-
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'b.. Main Rsteam flow ~ 120%.
c .' Drywe111 pressure 2.4:psig. 4 di_ -Steam tunnel-temperature 205-deg F. . t
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ANSWER:- 037. (1.00)
'd. [+1.0):
REFERENCE: J
1.' Peach Bottom: LOT 0180, pg 9, L.O. 2.a. . 2i K/A 223002K101 (3.8/3.9) (1/1)
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-QUESTION: 038 (1.00)
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: During re' actor startup, with the reactor at 10% aower, power is lost to the i Rod Sequence Control' System. WHICH ONE (1) of tie following 1s correct ,
concerningtrod movement? ,
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't a. All.' rod movement o1ust be second verified in order for rod withdrawal to continue.. !
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b. The oniy.means of rod. movement will be via a reactor scram. f n ( c. . Rods may.be inserted in accordance with the approved sequence -
' ' package.. .j m '- .. -
d. Rod withdrawal;may continue provided the' Rod Worth. Minimizer is , operable. i m , !
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i n. .. i ANSWER:1 ~038,(1,00)
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b. ; [+ 1. 0) > ; lc ?
. -REFERENCE:' ! . ..
i L 1. Peach Bottom:.l.0T-0100, pg 9.
.2. K/A 201004K301 (3,3/3.4)-(11/11)
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LREACTOROPERATOR page 29
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: QUEST 10N:-C39'(1.00). '! ,,-r s ' 1 'WHICH ONE (1):of the following pumps is powered by the E 12 4160 volt bus? ! ~ " - a~ ' A* CRD Pump f ,
c = b ', - *A" ESW' Pump
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'c. - "A":ESW Booster Pump !'
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.d.s,'*0"'HPSW Pump !
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9 ANSWER:. 039 (1.00)
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t I REFERENCE:s . l
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J).: Peach Bottom:TLOT-0660, pg 6; L.O. 2.. ti 2.K/A201001K20lt-(2;9/3.1)L(1/11)- .
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;;. iQUESTION:: 040; c(1.00),
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'l.WHICH ONE OF;(1)'of the" following:-is:the reason thatEthe: mechanical vacuum a pumpccan'not be used at reactor powers above.5%?. j
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", ' , ; a'. :The pump wi11 experience air b'indingi -
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. A .bk LAhl explosion could occur'inside the pump. d
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t c. The-pump will axceed design: loads. 'l 4A, 1 ..
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...'d. ;.The condenser; atmosphere becomes corrosive t+ the pump' internals.- .}
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(4 ANSWER: 040f(1.00)~ ; b'. . [+1.0)
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i i REFERENCE: ! li Peach Bottom: OT-106,* Low Condenser Vacuum Bases", pg 2, 2. K/A 256000K409 (2.8/2.8) (11/111) ,
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256000K409 ..(KA's) I QUESTION: 041 (1.00) WHICH ONE (1) of the following is minimum contamination levels that designate a contaminated area per PBAPS administrative procedures? a. '20 dpm/100 sq. cm. beta-gamma 1000 dpm/100 sq. cm. alpha b. 20 dpm/100 sq. cm. beta-gamma 100 dpm/100 sq. cm. alpha c. 100 dpm/100 sq. cm. beta gamma 20 dpm/100 sq. cm. alpha t d. . 1000 dpm/100 sq. cm. beta gamma 20 dpm/100 sq. cm. alpha '
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' ANSWER: 041 '(1.00) -
d. [+1.0)
' REFERENCE:.
i 1., Peach Bottom: HP-215, " Establishing and Posting Controlled Areas", pg 2.
2. Peach Bottom: LOT-1730, pg 7, L.O. 1.d.
3. K/A,29400lK103 (3.3/3.8) 29400lK103 ..(KA's) ,
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[;i: QUEST 10Ni042~(1.00)
4 - An operator"is expected to receive a 60 mrem whole body dose when performing i a. job in a Radiation Area. WHICH ONE (1) of the following operators has the i exposure available to complete the job? ASSUME that each operator has an NRC h~ ' Form 4 on file and NO approval.will be given for exceeding PECo ad;.inistrative limits.
I Ldperator Age- Exposure (mrem) o Quarter Year Life - b s :a.. 35 2360 3280 84950. : o ; F > b.- 27 -2275 3945 36570
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K c. ' 39' 2460 3920 ' 99545 [ r ,
$ d. 29 2415 3930 52610 li
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Ls l ANSWER: 042 (1.00).
s d. 1+1^.0) d t ; c
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il. Peach Bottom:-l LOT 1730, pp 9 10, L.0, 3.. 2.'K/A 29400lK103 , o . . .
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REACTOR OPERATOR Page 32 QUESTION: 043 (1,00) WHICH ONE (1) of the following are the administrative controls for the Level I Locked High Radiation Area keys? a. Keys are controlled by Shift Management and requires approval from Health Physics Supervision and Shift Management for issue.
b. Keys are controlled by Health Physics Supervision and requires ' approval from Health Physics Supervision for issue, c. Keys are controlled by Health Physics and requires approval from Health Physics Supervision and Shift Management for issue, d. Keys are controlled by Shift Management and requires approval from Shift Management for issue.
ANSWER: 043 (1.00) b. [+1.0) 4
~ REFERENCE:
1. Peach Bottom: LOT-1730, pg 6, L.O. 1.c.
20 K/A 29400lK105 (3.2/3.7) 29400lK105 ..(KA's)-
. . QUESTION: 044 .(1.00)
WHICH ONE (1) of the following is reason that the operator is directed to shutdown, the reactor following a confirmed jet pump failure? a. LSuspected loose parts in the vessel will cause internal damage.
p b. Inability to maintain 2/3 core coverage following a LOCA will cause unacceptable fuel clad temperatures.
L c. Unbalanced core flow will' cause flux distortions and the potential violation of the thermal limits.
d. Backflow through the damaged jet pump could cause an unobserved entry into the unsafe region of the power to flow map.
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ANSWER: 044' (1.00) b. (+1.0)
' ~ REFERENCE: .
1. Peach Bottom: LOT 0030, pg 48, L.O. 4.a.
2.~ Peach Bottom: Facility Question Bank, No. 1504, Book 11, pg 475.
' 3. K/A 20200lK401 (2.9/3.9) (11/11) 20200lK401 ..(KA's) t-
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QUESTION: 045 (1.00) Unit 2 is operating at 87% power. The Core Spray System is lined up for 9 automatic operation. Inboard injection Valve, M0 12, is shut. WHICH ONE (1) L of the following is correct regarding the operability of MO 12? a. The valve can be manually opened from the Control Room once the Outboard injection Valve, MO-ll, is shut,
[
b. - The valve can be manually opened from the Control Room anytime a Core Spray pump is running.
c. The valve will auto open when the reactor water level is less than-160 inches and the drywell pressure is 2 psig.
d. The . valve will auto open when reactor pressure is less than 450 psig. l
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. ANSWER: 045-(1.00)
a. (+1.0) .. ' REFERENCE: 1. Peach Bottom: LOT-0350, pp. 11 12, L.0. 4.
.2. Peach Bottom: Facility Question Bank, No. 1506, Book II, pg 477.
3. K/A 209001A403 (3.7/3.6) (1/1) 209001A403 ..(KA's)
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QUESTION: 046 (1.00)
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WHICH ONE (1) of the following is the result of pushing the LPCI Lockout i Reset pushbutton?
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a. Allows normal operation of the containment spray valves during a I LOCA.
. b. Allows.the LPCI injection valve, M0 25, to auto close after a LOCA '
- signal has cleared.
L c. Allows LPCI flow to be diverted to torus cooling following a LPCl injection. - L' " d .- Allows the recirculation pump discharge valve, MO-53, to be reopened after a LOCA signal has cleared, j '
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L ANSWER: 046 (1.00) l
.de [+1.0)
REFERENCE: s
~1. Peach Bottom:' LOT 1513, p. 17, L.O. 7, 2. Peach Bottom: Facility Question Bank, No. 1513, Book II, p. 484.
3- K/A 203000K402 (4.1/4.1) (1/l)
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-1 : QUESTION: 047 (1.00)
WHICH ONE (1) of the following switches should NOT be operated during a LOCA
. condition from'1007. power?
r !' a. RHR. Pump Start Logic Resets ; ' b. Containment Spray Valves Manual Override (S17A) ' c. HPSW Override (S19A)
-d. Containment Spray Valve Reset (533A)
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REACTOR OPERATOR Page 35 j
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L r ANSWER: 047 (1.00) do [+1.0)
: REFERENCE:
1. Peach Bottom: LOT-0370, p. 18, L.O. 3.
20 Peach Bottom: Facility Question Bank, No. 1514, Book II, p. 485.
3e K/A 203000A406 (3.9/3.9) (1/1) 203000A406 ..(KA's) QUESTION: 048 (1.00) WHICH ONE (1) of tha following paint colors identifies a normally locked throttle valve? a. green -! b. red c. yellow d. blue
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, ; ANSWER: ~048 (1.00) . >
c [+1.0)
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REFERENCE:- 1. Peach Bottom: A-8, " Control.of Locked Valv'es", pg 7.
2. K/A=29400lK101 (3.7/3.7) ; l t 1 29400lK101 ..(KA's) l' l
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' QUESTION: 049 (1.00) '
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An area of the plant has a dose rate of 130 mrem /hr. WHICH ONE (1) of the following is the area designation? a. Radioactive Material Area b. Radiation Area
[ c. . High Radiation Area ! . 'd. Locked Radiation Area
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ANSWER: 049 (1.00)
'c . [+1.0)
REFERENCE:
.l. Peach Bottom: LOT 1730, pg 5, L.O. 1.b.
2. K/A 29400lK103 p
'29400lK103 ..(KA's)
[ QUESTION: 050 (1.00)
' After the use of an Ignition Source is complete, WHICH ONE (1) of the ! 'following individuals has the responsibility to inspect the affected areas !
continuously for-30 minutes? a.- Dedicated Firewatch b. Technical Specification Firewatch c. Ignition Source Worker d. Work Supervisor-l .. g 1 l L L.
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ANSWER: 050 (1.00) l a. [+1.0) l REFERENCE: 1. Peach Bottom: A-12, *1gnition Source Control", pg 4.
2. Peach Bottom: LOT 1570, L.O. 2.c.
3. K/A 294001K116 (3.5/3.8) 29400lK116 . . (Kr.'s) QUESTION: 051 (1.00) In accordance with 10 CFR 26 " Fitness for Duty Program", WHICH ONE (1) of the following is the minimum time to abstain from alcohol preceding any normal scheduled shift? a.- 2 hours b, 3 hours , I c. 5 hours
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d. 8 hours , ANSWER: 051 '(1.00) [ c. .[+1.0) l e REFERENCE:
:1. 10 CFR 26 2. K/A 294001A103 (2.7/3.7)
r 294001A103 ..(KA's) .
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REACTOR OPERATOR Page 38 c , QUESTION: 052 (1.00) I 9^Jr WHICH ONE (1) of the following Emergency Clas 4dcations is the minimum i classification required for failure of safe systems needed to protect the i public? ! a. General Emergency
b. Site Emergency , c. Alert
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. ANSWER: 052 (1.0 b. (+1.0)
REFERENCE: e 1. Peach ottom: LOT-1520, p 2 K/A 2 4001All6 (2.9/4.7) g 6, L.0, 3. ' , 29 OlAll6 ..(KA's) b QUESTION: 053 (1.00)-
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WHICH ONE-(1).of the following is the reason for monitoring coolant radioactivity? ! a. Monitor for fuel failure -
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b. Monitor for activated corrosion products c. Monitor the amount of Nitrogen 16 being released d. Monitor the amount of Tritium being released
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ANSWER: -053 (1.00) ao (+1.0) REFERENCE: 1. Peach Bottom: LOT 1025, pg 14, L.O. 2.d.
2. K/A 294001All4 (2.9/3.4) 294001All4 ..(KA's) l
' QUESTION: 054 (1.00) . l WHICH ONE (1) of the following is the maximum allowable hours a licensed ! individual is allowed to work during a single pay period without prior ! approval? ; a. 56 hours ! b. 60 hours c. 72 hours d.- -84 hours I ANSWER:. 054 (1.00) l "
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b. [ + 1'. 0)
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REFERENCE: ! 1. Peach Bottom: A 40, " Working Hour Restrictions", pg 4, 2. Peach Bottom: L01 1570, L.0, 2.g.
3. Peach Bottom: Facility Question Bank, No. 14, Book I, pg 14.
..! 4. K/A~294001A103 (2.7/3.7) 294001A103 ..(KA's)
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i-QUESTION: 055 (1.00) GIVEN the following plant conditions:
- Reactor Power 2% - Reactor Water Level 20 inches NR !
c - Drywell Press 2.2 psig
- Drywell Temp 130 deg F
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- Torus Room Temp 90 deg F
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e WHICH ONE (1) of the following sets of procedures must be entered?
! : T-101 "RPV Control" .T-102 " Primary Containment Control" ' ' ; T-103 '" Secondary Containment Control" a. T 101 and T-102 b. 'T 101 and T-103
=c.. T 102 and T-103 F '
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d. T-101, T 102 and T-103 . t
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ANSWER: t (1.00) a. [+1.0)
' ' REFERENCE:,
, i 1. Peach Bottom: LOT-1560, L.0. 2
- 2. K/A 295024G0ll (4.3/4.5) (1/I)
295024G011 ..(KA's).
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QUESTION: 056 (1.00) Unit 2 is operating at 75% power when a high drywell pressure signal is received. WHICH ONE (1) of the following valves will receive an isolation signal? a. HPCI Vacuum Breaker Isolation Valve (M0-4245) b. Main Steam Line Drain Valve (MO 74) c.. RWCU Outlet Valve (MO 69) d.. Torus Water Cleanup Pump Suction Valve (MO-71)
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ANSWER: '056-(1.00) d'. [+1.0)
: (REFERENCE: ;1.-Peach Bottom: LOT-0180, pg 11, L.0. 2.
2. K/A 295024K207. (3.9/3.9) (1/I) ) 295024K207 .
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I QUESTION: 057 (1.00) WHICH ONE (1) of the following sets of plant parameters will cause the
' trip of the "B" Turbine feed ? ump?
a. Reactor Water Level 38 inches i Turbine speed 4500 rpm l Turbine bearing vibration (inboard) 3 mils L . Pump Suction press 300 psig (for 8 seconds) Condenser Vacuum 24 inches Hg
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b. Reactor Water Level 40 inches Turbine speed 5100 rpm
Turbine bearing vibration (inboard) 2 mils l 320 psig (for 10 seconds)
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Pump Suction press i Condenser Vacuum 27 inches Hg c. Reactor Water Level 42 inches Turbine speed 5800 rpm ,
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Turbine bearing vibration (inboard) 4 mils
, Pump Suction press 350 psig (for 5 seconds)
Condenser Vacuum 22 inches Hg , d. ' Reactor Water Level 36 inches Turbine speed 5700 rpm Turbine bearing vibration (inboard) 4.5 mils Pump Suction press 310 psig (for 9 seconds) Condenser. Vacuum. 18 inches Hg ANSWER: '057 -(1.00) ; d. [+.1.0) i REFERENCE: 1. Peach' Bottom: LOT-0540,pg15,L.0.4,(seeTP-059,rev.2).
. 2. K/A 259001A310 (3.4/3.4) (1/II) 259001A310 .,(KA's) ,
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! .. i REACTOR OPERATOR Page 43 i f QUESTION: 058 (1.00) , I- WHICH ONE (1) of the following describes the results of a loss of "A" Feedwater Heate- Train?
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a. Core inlet subcooling decreases Actual bundle power decreases P Critical power ratio decreases -
b. Core inlet subcooling increases Actual bundle power increases
' Critical power ratio decreases
! c. Core inlet subcooling decreases ' , Actual bundle power increases Critical power ratio increases d. Core inlet subcooling increases ' Actual bundle power decreases O Critical power ratio increases L, ANSWER:.- 058- (1.00)
! b.. [+1.0] f REFERENCE: 1. Peach Bottom: LOT 1820, pg 10, L.O. 3.
2.: Peach Bottom: Facility Question Bank, No.1595, Book II, pg 523, 3.' K/A-295014K202 (3.7/4.2) (1/l) L ! 295014K202' ..(KA's)
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P i I REACTOR OPERATOR Page 44 V QUESTION:'059 (1.00)
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During a Station Blackout, if E 2. E-3, or E 4 Diesel Generators f ail to ,~. start automatically then SE II, " Station Blackout *, directs the operator to do a manual quick start. WHICH ONE (1) of the following is the reason why
< 'these diesels are specified?
G a. They ensure sufficient cooling for the diesels, b. They ensure power to the RPS buses.
c. They provide normal control functions for Alternate Shutdown.
' d. They provide sufficient cooling to all RHR heat exchangers. l
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ANSWER: 059 (1.00)
'a. [+1.0)- .
REFERENCE:
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1. Peach Bottom: facility Question Bank, No. 1598, Book II, pg 526.
2. Peach Bottom: LOT-1555, L.O. 4 f 3. K/A 295003K202 (4.1/4.2) (II/I)
-295003K202 ..(KA's)
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QUESTION: 060 (1.00) CA* Recirculation Pump is ready to be restarted after it tripped while the plant was operating at 100%. WHICH ONE (1) of the following data sets ! supports the restart of the."A" Recirculation Pump. ASSUME APRM gain = 1.0 and reactor saturation temperature is 538 deg F. ;
'a. APRM Scram Setpoint 65% ! Average APRM reading 48%
Bottom Head Temp 420 deg F o "A" Recire Loop Temp 485 deg F
"B" Recirc Loop Temp 515 deg F
"B* Rectre Pump Speed 44%
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I' b.- APRM Scram Setpoint 78%
: Average APRM reading 52% '
F Bottom Head Temp 415 deg F
'A' Recirc Loop Temp- 490 deg F *B" Recire Loop Temp 530 deg F "B* Recirc Pump Speed 47%
i c. APRM Scram Setpoint 86%
+ Average APRM reading 55%
Bottom Head Temp 465 de F
"A" Recire Loop Temp 480 de F e 'B" Recire Loop Temp 520 de F "B".Recirc Pump Speed. 52% .
. .d. APRM Scram Setpoint 81%
Average APRM reading 49%-
' Bottom Head Temp 435 deg F
'A" Recirc. Loop Temp- 415 deg F :
"B" Recirc Loop Temp 500 deg F-
"B" Recire Pump Speed 45%
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ANSWER:L 060 -(1.00) b. [ + 1. 0) ' E REFERENCE: .
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n ! 1.JPeach Bottom: LOT 0030, pg 43, L.O.- 4.J. i e,- 2. Peach Bottom:. Facility Question Bank, No. 1565, Book 11, pg 512. .; f; 3. K/A 202001K410 (3.3/3.4) (11/11) ^
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l, L' :20200lK410 ..(KA's) , .
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__ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ r . .- ! l REACTOR OPERATOR Page 46 I QUESTION: 061 (1.00) p
' During a reactor startup, the excess flow check valve for Me L194A reference :
leg shuts. WHICH ONE (1) of the following is the response of the INDICATED level as reactor pressure increases? , ' a. Level increases as the pressure increases on the variable leg.
, b. Level decreases as the pressure increases on the reference leg.
E c. L194A will fail low as the pressure is felt equally on both legs.
f d. L194A will fail high as the pressure is felt equally on both legs.
I, , t r L ANSWER: 061 (1.00)
0 a.
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~ REFERENCE:
I 1 Peach Bottom: L'0T-0050, L.0. 7.
. , 2.-Peach Bottom: Facility Question Bank, No. 1563, Book'II, pg 510, 3.-~K/A 216000K510 (3.1/3.3) (1/l) 216000K510 ..(KA's) 4
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i ..a L- , c QUESTION: 062- (1.00) r.
l The.E-1 diesel generator is running for a surveillance test when a rupture in I
. the Emergency Service Water piping causes a complete loss of cooling to the
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. E 1 diesel. WHICH ONE (1) of the following conditions will cause the diesel t to trip? f a.- High crankcase pressure.
b .- High. Jacket coolant pressure, c. High>1ube oil temperature.
l. .d. High ' fuel oil temperature. ; j f I
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kEACTOROPERATOR Page 47 ANSWER: 062 (1.00)
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c. [+1.0).
REFERENCE: 1. Peach Bottom: LOT-0680, pg 14, L.O. 10.
2. Peach Bottom: Facility Question Bank, No. 1564, Book !!, pg 511.
30 K/A 295018K101 (3.5/3.6) (11/11) 295018K101 ..(KA's) , k QUESTION: 063 (1.00) WHICH ONE (1) of the following individuals is responsible for directing the
:overall PBAPS ALARA Program?
a.- ALARA Health Physicist , b. - Senior Health Physicist i
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c. Plant Manager ,
, d. - Vice President PBAPS t p
L ' ANSWER: 063-(1.00) c. [ + 1. 0) ' ,
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L REFERENCE:' l zPeach Br,ttom: LOT-1770, pg 8 , L.0. 3.
-2. K/A 29400lK104 . 294001K104_ ..(KA's)
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- REAC10R/0PERAiOR.' - - Page 48 g.
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QUESTION: 064 (1.00)- .;
'Within WHICH ONE (1) of the- following areas in the plant is portable radio communicationiallowed?=
4 a, Cable Spreading Room
, b. Process Computer Room !
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. c.. Control Room [ .
d.- Refuel . F1oors-
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.r " l ANSWER: 064 (1.00)
o N d. ~(+1'0) . i gj !
, ~ REFERENCE:
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.l. Peach Bottom:' A'-9, " Plant Communication Systems", pg _2.
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] , 12 K/A 294001A104 (3.'l/3.2) -
l 294001A104 _..(KA's)- j
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a : QUEST' ION:-065 (1.00); b' ;WHICH ONE (1) of_ the' following is' the operator action for a control rod 1 '
' drifting out fr ,minotch 24- while;the plant is 'at 67% power? .
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an Perform an!individualLrod scram. ! i
'b. Withdraw the- rod- full' out and do a. coupling check.
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- c .L Deselect'the rod on the RMCS ,
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'd;; InsertLthe' rod-full _.in using th'e EMERG IN switch. !
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ANSWER'. : '065-(1.00)
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[ , REACTOR OPERATORL Pege 49
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' REFERENCE:: ; .e 'l. Peach' Bottomt ON 121, " Drifting Control . Rod", pg 1.
2i Peach Bottom" LOT-1550, L.O. 2.'
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': 3.; K/A 295014A103. (3.5/3.5) (1/1)
295014A103 ..(KA's)
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QUEST 10N: 066: (1.00) ]
.Given the following Control- Rod Directional Control Valve sequence: ,
The~ 123 and 121 valves cycle open for 2.9 seconds then close,' then the 120 l
' valve ' opens and' stays open. WHICH ONE-(1) of the following is the rod motion' that; results? t
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'a';
. Continuous insertion-
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ib! Continuous withdrawal. i hh, Jc.; -Single' notch insertion N ' d. zSinglel notch withdrawal.
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t lANSWER: '066! _(1.00) i
, ! : ch :[+1.0): i
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~ " MREFERENCE: V; ; R:1.tPeach Bottom:fLOT-0080,_T-LOT-0080 2, L.0'.LI. l 12./K/At20100lK410(3.1/3.0):(1/11)
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. = QUESTION:'067. (1.00)_
-Power is lost'to'the EB0P 250 VDC. battery charger for 37 seconds and then i restored. WHICH ONE (1) 'of the following conditions will occur following '
power restoration? i-a. The battery. charger will have to be manually reset. ! b. The charger will pickup the load and keep the battery on iloat. !
:
c. The charger will . pickup the load and supply an equalizing charge
.to the battery, i
l d., The' load will remain on the battery fer one hour and then the charger
, will automatically reset. .;
e ; t ci ANSWER:: :067 -( 1. 00) .
' .c., [41.0] f ' :
a ' REFERENCE: El.LPeach Bottom:.LO'T-0690, pg.9, L.O. 2.c. '
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L.'2 K/A 295004K201_(11/11)
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iQUESTION:'068 -(l'.00);
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FWHICH ONE -(1) of;the following lines on the Power to Flow Map defines where. 1
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ithe recirculation' pump; cannot be operated. above 10% until fe'd flow is ;
; greater than?20%?J if 'a.: Minimum Flow Control: Line.
l *, ' Jb.: Design Flow Control. Lin'e n, , 1' k
; Natural. Circulation Line
' c .~ ' d.. APRM Rod Block Monitor Line ' s-l
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l REACTOR OPERATOR Pege 51
m ANSWER: 068'(1.00) [ a "?
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a.- [+1.0] I w l REFERENCE: 1. Peach Bottom: LOT-0040, pg 22, L.0. 19.a.
,2. K/A 202002G005 (3.3/3.4) (1/l)
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a' 202002G005 ..(KA's)
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,? QUESTION: 069,f(1.00).. !
E Upon11oss 'of the Turbine Building Closed Cooling Water System, WHICH ONE (1) i
, ,of. the following loads is automatically backed up by the Reactor Building 1 Closed Cooling Water. System? !
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La.: ~CondensatePumpjCooler. j
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b . .. Joy" Air Compressor-
.c.. . CRD' Pump ' Lube '011.' Coolers -
,d. Isolated Phase Bus Coolers
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.: ANSWER: --069 (1.00)f j ,Y c ..; -;[+1. 0]'; -
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.a+ tREFERENCE:4 ., . + 'l}E. Peach: Bottom: LOT-0430, pg 6,: L.0. 4. ! ?, 2..K/A 295018A1011.(3.3/3.4)'(11/11) j ' ,
2950}8A101_ ..(KA's). j
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QUESTION: 070.(I.00)
, ~WHICH ONE (1) of. the- fo11' o wing is a basis for allowing operators to : initiate _ Drywell Sprays regardless of whether adequate core cooling is ;
assured?
-a.- To prevent excessive drywell-to-torus differential pressure. .;
b '. . ETo maintain t'o rus water level below the vacuum breakers.
> c.: 'To maintain:drywell pressure below the Drywell Spray Initiation Limit.
d. < To ' dilute drywell hydrogen and oxygen concentrations to prevent a I L containment explosion. ,
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i u ANSWER: -070.(1.00); i yd. . [ +1. 0) - i
, +. I g REFERENCE:- 1
- El. Peach Bottom
- -LOT-1560, L.0, 3. ,
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2.K/AL295024A117(3.9/3.9)--(1/I)
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295024A117 ... (KA's) i l t
: QUESTION:J071' (1.00) . -
r i p WHICH 0NE (1) 'of the 'followingiconditions must exist .if T-213 "Decnergize
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i' < Scram Solenoids" is to~ be an effective method for alternate rod insertion? a, 'ARI.has been initiated.. L4 .b.. Scram discharge . volume vent and drain valves are open. !
.c; Stram valves are closed.
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'.d.: Scram air: header has been vented.
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l j ANSWER- 07.1_ -(l'.00) c.; [+1.0)' _
REFERENCE:L i 1.cPeach Bottom: T 101, "RPV Control - Bases", pg 5.
m .2. Peach Bottom: LOT-1560, L.0. 3.
m "3e K/A 295037K307:(4.2/4.3) (1/I) I 295037K307- -. . (KA's)
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a 'I + QUESTION: 072..(1.00) i t
: Total- loss of the uninterruptable A.C. power will result-in a reactor scram. : ' -WHICH ONEJ(1)Lof the following-conditions is the reason for the scram? l-ASSUME no operator action?has been taken.
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. Loss'of_ power to thet RPS buses.
Lb. ; Loss -of control signal to the feed pump logic and a recirculation :[
' pump runback will cause a scram on.high level.
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c., ' Loss of power to-the nuclear instrumentation will cause the reactor t
, to scram on APRMs downscale. ?
Ld. Loss of Main' Steam Flow signal will cause ta group I isolation and ;
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subsequent high power scram.
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LANSWER:. 072. (1.00)
:b', L(+1'0], I
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. ' REFERENCE:- !
1.: Peach Bottom: ON-ll2, " Loss of Uninterruptable A.C. Power", pg.1.
2. Peach Bottom:~ LOT-1550, L.0, 2 _ 3..K/A 295003K305-(3.7/3.7):(II/I)- ; L295003K305 ..(KA's) i
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3. .... REACTOR 20PERATOR; Page 54 __ QUEST 10N: 073 -(1.00)
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l Unit 2 experiences a- Shutdown Cooling isolation. WHICH ONE.(1) of.the
, following conditions caused.-the isolation? , .-a.
' Reactor water level is +46 inches.
if' .b. Drywell- temperature. is 137 deg- F.
c. Drywell pressure is 1.75 psig, d., Reactor _ pressure is 78 psig.
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!NNSWER:L 073- (1.00)
id. ~[+1.0]--
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REFERENCE:1 1.-Peach Bottom: LOT-_0180, T-LOT-0180-3, L.0. 2.f.
2.'~K/AT295021A206 (3;2/3.3).(111/11)-
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u U 4-1:g.f-i, .. 1. REACTOR OPERATOR Page 55
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y -QUESTION:1074 (1.00)
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While: operating.at; full power both CRD puns trip on Unit 3 and they cannot be restarted. According to ON 107., "Itss of CRD Regulation function", WHICH l ONE (1) of-the following sets;of conditions will require a rea: tor scram? ' a.. Reactor Pressure is 645 psig.
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, ,CRD Charging Water Header Pressure is 1380 psig.
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~2 CRD Accumulator Trouble indicators are lit, b. Reactor Pressure is 575 psig, i CRD Charging Water Header Pressure is 1400 psig.
. 3 CRD Accumulator Trouble indicators are-lit.
n c.: Reactor Pressure is.650 psig, i CRD Charging Water Header Pressure is 1460'psig. !
.4 CRD Accumulator Trouble indicators are-lit.
i d.. , Reactor Pressure is 590 psig, o ~
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CRD Charging Water Header Pressure is 1490 psig.
12~CRD Accumulator Trouble indicators are lit.
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' ANSWER:-' .
074' (1.00)i l
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b.-[+1.0].
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REFERENCE:-
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11. Peach Bottom:LON-107, " Loss of CRD Regulation Function", pg l.
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;2'. Peach Bottom: LOT =1550, L.0.12. o L 3.1K/A5295022K10le(3.3/3.4)- (11/11)
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% ;LQUESTION:-075 -(1.00):
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Unit-2 has entered'OT-114, " Inadvertent Opening of a Relief Valve" and the j torus temperature-is now 97 deg f. WHICH ONE (1) of the following is the i
.immediate operator action? '
a .-- Runback- recirculation pumps. l b.' - Reduce turbine inlet pressure to 900 psig. ' 4 c. ' Enter'T '102_and execute it concurrently.
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.t d.. . Scram thel reactor.
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ANSWEP.: 075 (1.00)'
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q-f i . REFERENCEi. ! y" il.LPeach Bottom: 0T-114, " Inadvertent Opening of a Relief Valve", pg .l.
2e Peach Bottom: LOT-1550,'L.0. 2.- ;
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132 K/A'295013G0ll1(4.1/4.4) (11/1) 295013G0ll ...(KAf:); l c N-QUESTION:L076L . (l'. 00) -
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' 3 WHICH 'ONE' (1)'of- the' following is the reason that the Turbine ' Generator. is 1 manually tripped at 50 MWe following a-reactor scram?. 1 t: a'. - Prevents.an uncontrolled pressure transient.by subsequent automatic
< trip.-
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tb. Allows foria- more controlled turbine cooldown. '
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c. Guards against turbine overspeed due to loss of load following an D' , automatic trip. !
.d . .. Prevents . turbine damage due to moisture -carryover at low loads. -i
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EREACTOR OPERATOR Page 57 y
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; ANSWER:- -076 (1.00) * c,- [41.0) > ;
REFERENCE: t 1. Poach Bottom: T 100, " Scram.- Bases", pg.2.
2. Peach Bottom: LOT-1550, L.O. 3. .' 3.;K/A 295006K305 (3.8/4'.0) (I/I) .; 295006K305 ...(KA's) .. Es. . . l
, ; QUESTION: 077 (1.00)
4 .WHICH ONE (1) of the followingLeonditions would be a Safety Limit violation? i
'a.- lWhile : operating. at full power the- Unit. 3.HPCI and ADS systems are - -
declared / inoperable.
Lb.; With: Unit,2-operating at 70% power, tne main turbine and reactor feed. l
= pumps trip ~at'48. inches-RPV level.
' ' The reactor scrams on' low RPV ,~ t level..
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.c. - Unit 3 is operating at 22% power and the EHC pressure regulator i fails. The reactor pressure-drops to 820 psig:before the reactor
. scrams-
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T d .; "During' the . Refuel of Unit 2, RPV level isolost due to; an unisolable
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4. 11eak. Level. drops to -165 inches before it is restored to -15 inches
- with emergency systems.
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ANSWER: '077_' (1.00).
g. f .d U(+1;0)? !
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. REFERENCE: +
o ' fl. Peach Bottom: Unit' 2 Technical Specifications,1.1.C.
L2.HPeachsBottomE LOT;1820-!L.0. 1, , 4 L3', K/A 295009G003,(3.4/4'2).-(1/I)
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LREA(! TOR OPERATOR Page'58 ! QUESTION:::078 '(1.00)'
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WHICH ONE (1).:.of the' following describes why lowering RPV level during an
'ATWS: reduces = reactor power? -a.. Inhibits. natural: circulation and increases void fraction. [
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b!- Prevents temperature stratification which results in localized power i y . peaks.
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. , r: c. ' Allows increase in moderator. temperature' and steaming rate through -
open SRVs to' promote steam cooling, , d... Promotes evaporative cooling'by' increasing steam flow.
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ANSWER:: 078: (1.00)
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, 'a.- [+1 0]j r . REFERENCE:. I < 'l. . Peach Bottom::T-ll7, " Level and Power - Bases", pg 1.
2? Peach Bottom: LOT-1560,'L.0. 4.
3..'K/AL295037K303 (4.1/4.5) (I/I)
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M(QUESTIONif079.(1.00);L
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; WHICH ONE -('l) of the- following .is a major. concern of having drywell :!
gtemperatures;in. excess of 135 deg-F? a a., , Excessive. stress on,the primary cont'ainment, y
,b.. Violation 'of the .Drywell' Spray -Initiation Limit.
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:c. ' Damage-of. electrical equipment inside drywell.-
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Violation' of the Heat. Capacity Temperature Limit.
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REACTOR OPERATOR' Pege 59 - I 'd l ANSWER: 079 -'-(1.00) .
> 'c. [+1.0)- ,
I REFERENCE: '
, :1. Peach Bottom: T-102, " Primary Containment Control - Bases", pg 15.
~2. Peach Bottom: L0b l560, L.0. 3.
3. K/A 295028K202-(3.2/3.3)-(11/11) :
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' i-QUESTION: 080- (1 00) i
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( WHICH 0NE. (1) ~ of- the.following is a consequence of having the torus water
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. temperature above'180.deg F?
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L a'.1 Damage:t'o the torus structure.
" b. . Inadequate NFSil to the RCIC or HPCI-pumps.-
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c. ' Violation;of the Heat: Capacity Temperature Limit. ,
[d; 1 Entry into the unsafe regioniof the RHR Vortex Limit. !
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, "ANSWEk: ~080 (1.00)
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1. Peach > Bottom:.T-102, " Primary Containment Control ; Bases", pg 3. ! 2h Peach Bottom: LOT-1560, L.0.u6'. J
'3.'K/A2295026K101'-(3.0/3.4) (l1/I)' i
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, , :,- -REACTOR OPERATOR Page 60 F QUESTION: 081-'(1.00)- ;During a controlled reactor shutdown the Offgas System activity approaches the Main Stack release rate limit. WHICH ONE (1) of the following is the-required method.to control.the release rate?- '
i a., Crack open the-condenser vacuum breakers.
- b. ._ Trip-the mechanical vacuum pump.
c. . Isolate ~the Offgas System, d. : Dilute system flow with auxiliary steam. -I i j
, ! ANSWER: .081 ;(1;.00) .!
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t i REFERENCE: 'i ? .1. Peach Bottom:~A0-8.2-2, "Offgasl System Operation During Controlled
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,, ' Shutdown if High Offgas Activity Exist",-pg 3. -! )1 2. Peach Bottom: LOT-0510, L.0. 4
- 3.~ Peach Bottom:' Facility Question. Bank,- No.1140, Book II, _ pg 239.
j; c4.< K/A 271000A204 (3.7/4.1) -(11/11) '! 4 j '271000A204 ,~..(KA's), i e
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j LQUESTION:f082: (1.00). ]
- , .WHICH 0NE (1); of'the following.is the normal source of steam to the Reactor- !
O : Feed Pump Turbines at 90% reactor power?.
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[ a. "A"~ Main Steam Line down stream of the MSIVs. ! b.' ;"C" Main Steam Line inside the'drywell.
c .1 Outlet of the "E" and;"F" Moisture Separators, w
- .d. -Inlet of:the
. "E" and "F" Moisture 1 Separators.
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= ANSWER:. 082. (1.00) 3 E '
.c. [+1.0) i REFERENCE:'
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. 1. Peach Bottom: LOT 0540, pg 5 L.0, 5. '
2e Peach Bottom: Facility Question Bank, No. 1153, Book II, pg 252. . 3. K/A'25900lK120 (3.1/3.2) (I/II)
. 25900lK120 ..(KA's) .f i
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QUESTION:LO83 (1.00)
, (WHICH ONE (1) of the following is the maximum allowable total reactor coolant system leakage rate over 'a-24 hour surveillance period?
, a, 5-gpm
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b. 15 gpm
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4 c. - 25. .gpm;
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:d. 135 gpm i
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,1 ANSWER:' 083 (1.00)'
, .cb.H :(41.0)
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uREFERENCE: i 11 : Peach Bottom: LOT-0130,' pg 13; L.0, 7. 3
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K2.:K/A 223001K104 (3.1/3.2)-(1/I) 22300lK104- ..-(KA's).
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i jQUESTION: 084 L(130)[ Unit 2 is ~ operating. at L]OO% power and sustains a complete loss of Instrument Air. :WrilCH ONE--(l). of the following systems is available for level AND-pressure control?.L o
. - a.- ADS a b.- 'Feedwater c. RHR
'd .~ - 'HPCI
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fANSWER:. 084l-(l'00); d. '[+1.0)-
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' REFERENCE:' l 11.. Peach. Bottom:.0N-119,." Loss'of Instrument Air", pg 1. i
;.. L2. Peach Bottom: LOT-730, L'.0. 5.
-3. K/A 295019K217 (2.7/2.7) (11/11)j
;
' 295019K217, ,..(KA's)-
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juESTION:0852 ( l . 00)_-
\ "GP 2, " Normal Plant Start-Up",Lrequires operators to open.1 1/2Lbypass ' valves. :
to avoid " Batch Feeding". WHICH 0NE- (1) of the following .is' the : reason. that
.
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? Batch Feeding" should be~. avoided?-
- at iTo-stopl pumping' vibrations in:the long path recirc return line. !
- b. To. minimize temperature fluctuations on the feedwater nozzles. '
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' c.. To avoid' cycling moderator temperature.
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d.- To ' prevent unnecessary thermal _ stress on the reactor fuel . ! o
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g-REACTOR OPERATOR-- Page 63
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ANSWER:. .085 .(1.00)- b7 [+ 1 t. 0] i JREFERENCE: ' lel Peach Bottom: GP-2, ~ " Normal. Plant Start-Up", pg 40.
~2.~ Peach Bottom: LOT-1530, L 0, 4.
13.: Peach Bottom: Facility Question Bank, No. 1165, Book II, pg 265. , 4.. K/A 25900lK101.(3.6/3.7) (1/11)- .i 259001K101 u..(KA's)
, f , .. r-QUESTION: 086 _(1.00)
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'l '
WHICH ONE (1) of the following-Fire Protection systems has a header that is '
< ynormally pressurized with nitrogen? .I al. Cardox.
~ I
.l l , . b '.- DelugeL i a
c.- .Wet' Sprinkler
*
d.- Pre a'ction-.
- , ,
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:: ANSWER:' ?086 .(1.00)' '
, .
-!
Ld'.:[+I'.0];
.
.
)
i REFERENCE: w: u.g , 1./ Peach Bottom:. LOT-0685, pg 11, L.0. 5. -
-l :2.K/A:286000K406.(4.4/4.4)-(II/II) ,
1286000K406 ..(KA's) 'j
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' <, I :. . ' REACTOR OPERATOR Pa0e 64 ,
QUEST 10N: 087- (1.00)' WHICH'ONE (1) of the following is the callection point for low conductivity
.
.
radwaste?' , I a. Waste Collector Tank- ) be Floor Drain' Collector Tank l c .- . Reactor Building Floor Drain Sump i
, d. - Waste' Sample Tank x- j l
l i ANSWER: m 087'(1.00) >j
. a. ;. l [+1.0) l , ; REFERENCE:
, ?1.LPeach Bottom: LOT-700,.pg 10,.L.'O. 2. , 2.-l Peach Bottom:'. Facility Question Bank, No. 1188, Book II, pg 276. j
. .3 K/A>268000G00.7'(2.8/3.1) (III/III) l 268000G007' .-(KA's) .
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' . QUESTION: 088 i(1.00):
Upon loss 'of cooling' water to the fuel Pool Cooling Heat Exchangers, .WHICH -
= 0NE (1)'off the following systems will provide . backup cooling? !
s
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ta.- ' Service Water h b.. -High Pressure Service Water
'c.. " Reactor Building Closed Cooling Water .
' '
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Ed.- Turbine Building Closed Cooling Water ;
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,., -REACTOR 0PERATORi Page 65
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s . ANSWER: 088 (1.00).
- i c. -
[+1.0): '
!
REFERENCE: l' Peach Bottom: LOT-0750, pg-10, L.0. 3.
2. K/A 233000G007-(3.2/3.3) (Ill/III)
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233000G007' -..(KA's)- ' i.
QUESTION: 089 (1.00) I c ,
;WHICH ONE (1) of< the following describes the required orientation of a fuel assembly -in, the: reactor. core?
S, c a .J .The-tab on the bail handle points to the control rod.
% The two: buttons on' the channel-face the control rod. , The serial' number on the bail is right side up as viewed from.the ' control-rod,
,
t
.b. 'The-tab on.the;bailLhandle points to'the control rod.. .
TheLtwo bu' ttons on the channel face the outside of the fuel cell. l
.The serial number on the bail is right side up as. viewed from l outside the fuel cell, c.. -The tab on the bail; handle pointst away from the' control- rod. .
h
!The two-buttons on the channel face the outside.of the fuel-. cell. 1 'The serial number on the bail is right side up- as viewed from the . control. rod.
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sd' . fhe; tab.on'the bail handle pointsLto.the control' rod. '!
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The :twoLbuttons on the channel face the control' rod. . q L The serial-number on the bail'is.right side up as _ viewed from outside- l
, ; the' fuel cell, f ,
'! 4 ' ' LANSWER: = 089 - (1.00) I
- . .. .a. *:[+1 0] .
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REACTOR =0PERATOR' Page 66 ; , y _ REFERENCE: I
. .l. Peach Bottom: S0-'18.7.A-2, pg 4.
{ 2.J K/A 234000K505' (3.0/3.7) (l11/1I)
', 234000K505 ..(KA's)
:
;
<
-QUESTION: 090 (1.00)
l WHICH ONE (1) of theLfollowing is the-plant response to a High Radiation trip of the Control Room' Vent Process Rad Monitor?
,
a. : Air. conditioning. supply fans trip.
r
* ' . b .' . Dampers in the fresh air supply shift to bypass the air conditioning ,
supply. fans.
. c .- Dampers-to the h'igh efficiency filters close.
- '
,
d; . Both emergency supply fans start.
_
.r ..['NSWER- '090 (1.00)
a. [+1.0)L l w . ,
. REFERENCE:
y
' .1. PeachEBott'om: LOT-0450, pg 10, 1.0, 2. ! <
J2. K/A;290003K401'(3.1/3.2)1(II/II)l
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. REACTOR OPERATOR: Page 67-
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- QUESTION: 091 (1.00).
i-During full power-operation the level in the _ Scram Discharge Volume slowly -
' increases. WHICH 0NE (1) of the following is the level at which'a Rod Block >
is. expected?- a. 5 gallons f b.- 10 gallons c.' 25 gallons d. 50 gallons
>
ANSWER: 091. L(1.00)-- 3
! -_c._ [+1.0]
I
-;
R'FERENCE': E
' ' Peach Bottom: LOT-0070., pg'26, L.0. 10.
.
; -2 :K/A 20100lK108 (3.4/3.4) (1/11) . (20100lK108. ..(KA's) -
t
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QUESTION: 092 -(1.00)
'WHICH;0NE (1) of the'following are the pressures that the core spray line -
break detection system senses during_a line break? i, a. ' Below core plate. pressure and top of. core pressure. , b. Above core plate: pressure,and top of core pressure, c. -Below core plate pressure and outer annulus pressure.
I r d. Above core plate-pressure-and outer annulus pressure. ;
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_K {3 . REACTOR OPERATOR : Page 68 '
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ANSWER: 092l .().00)1
'd. (+1.0)
<
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I / LREFERENCEi i
, -1. Peach-Bottom:-LOT-0350, pg 11, L.0. 6. I s
2. K/A120900lK404 (3.0/3.2) (1/I)' i
,
20900lK404 ._.(KA's) i QUESTION:c093--(1,00) j JWHICH_0NE (1)- of the following describes the normal operation of the HPCI
.
;
' Minimum Flow Recirculation Valve (MO-25)? .;
'
; a. Normally close'd,' automatically opens on-HPCI- initiation and remains open unti1- manually closed -from the control room. !
a
"
b' . . :Normally open, automatically close's after HPCI initiation and system ' flow is, greater than 1200.'gpm. i
.r Normally open and.is manually closed from the control room after HPCI
~
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c.e l initiation. .l a
,
Ed. Normaly1~ closed,; automatically opens' after HPCI' initiation and closes
-
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" . !af ter, system flow 'is- greater than 1200 gpm.' ;
+,
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ANSWER: . :093 ;(1.00) 'il ..
,
, fd.;;[+1.0] '
,
i REFERENCE:
*
?' ilOPeach' Bottom: LOT.-0340,.pg 8, L.0, 3.
T2. X/A 206000K418 (3.2/3.3) (I/l) ; p" , > , 206000K418 ..(KA's) ll: . .
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' REACTOR (OPERATOR;- Page 69
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.. . > i o J0VESTION: 094- (100) i
:
'The RCIC' System _has initiated on a valid initiation signal and has operated 1 Jfor 15 minutes.1 The following conditions now exist:
- !
'RCIC Steam Line Flow 175% l
- RCIC Area Temperature 180 deg F
- Reactor. Pressure- 125 psig
~
- Reactor Level- < +48. inches
. WHICH ONE:(1)L of thenfollowing is the RCIC System response?;
' a '. 3 Steam Line. Isolation 1 Valves, M0-15 and -16, close.
- bl . Minimum Flow Valve, M0 27, closes.
'
' 'c. ' Exhaust;Line Drain . Valves, A0137 and -138, close.
'E
' d .t _ Steam Line Isolation Valve, M0-131, closes,
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, SANSWER: 094~ (1.00)
"' d. [+1.0).
, REFERENCE: 41 :PeachiBottom:" LOT-0380,'pg:18,.L.0. 2. .;' E2..,K/A295008K206(4;3/3.6)1(I1/11)
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QUESTION:- 095 (1.00)
;Ast a fuels bundle is placed into the vessel the SRM count rate it observed to l-increase.t The bundle is not adjacent to an SRM. WHICH ONE (1) of the ,
following. is' the amount that the SRM count rate may increase before fuel l handling must be terminated?-. ;
! . a '. .25% j i
Lb. 50%- .;
>
:c. : 75%
,
t'
-d.- 100%-
_ e .. !
(ANSWER- :095 (1.00)-
1d'.' [+1.0) j
!
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REFERENCE;-
, 1./ Peach Bottom: FH-6C,L " Fuel . Movement and Core. Alteration", pp 7 and 13. I E2. Peach Bottom:. LOT-0760, L.O. 5.- ~3.LK/A295023A106;(3.3/3.4)'(III/I)-
295023A106- ..(KA's)-
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QUESTION:3 096 (1.00) y l LThe Shift Manager has just ordered a control-room evacuation.
WHICH 0NE (1)
: of the following. is' NOT< an. immediate operator' action?
g. la.- Trip the ' recirculation 1 pumps.
b.. Transfer-house loads.
.! c; ' Man'ually1 scram .both reactors. j
:d. Bypass drywell instrument' nitrogen.
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REACTOR OPERATOR Page 71 ! I ANSWER:- -' 096 (1.00);
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.
a - 1[+1.0]: ' q
' > ' REFERENCE- i l
1.fPeach Bottom: SE-1, " Plant Shutdown from the Remote Shutdown Panel", pg 1. ; 2. Peach Bottom: LOT-1555, L.0. 3. l 3. K/A-.295016G010.(3.8/3.6) (II/I)
.
l ' 295016G010 j
..(KA's) i . . .. ,
sQUESTION: 097 (1.0,0)- WHICH ONE (1) ofLthe'following is the reason for the plot of RPV pressure vs !
:; Reactor Building area temperature in T-103, " Secondary Containment Control"i l '
a.- LDetermines the entry requirements into the Reactor Building during a f
.
,
: transient.- j!
.,- i b;4 Establishes:a leak rate of ' primary coolant' leakage into Secondary Containment ~.
.
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. Determines the reliability of the _RPV level instrumentation. !
-. d . - Indicates the loss of Secondary Containment -integrity. :li .}
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LANSWERf L097.' (1.00)
[ :c.- (+f.0]1 .
y. , 1 LREFERENCE; V1'.iPeach Bott'om: .T-103, " Secondary Containment Control".
-"
':2.LPeach Bottom: LOT-1560, L.0.-6.3.
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. ~ '
n3.;295032K104:(3'.1/3.6)-(III/II)
' - >
L295032K104 ...(KA's)
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REAC ROPERATbR^ Page 72 j l
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1 x ' QUESTION: 098: .;(1.00)' [
.
.
;WHICH ONE (1) Lone of the~.following is the basis for tripping the Recirculation '
. Pump's within 10. minutes following a total loss of the Reactor Building Closed Cooling Water; System?:
>
a. To insert l negative reactivity to aid in reactor-shutdown.
~ b.; To. prevent Recirculation Pump seal damage, c.. To reduce the cooling load on the on the backup cooling system. 4
^
d. To prevent damage to the Recirculation. Pump motor windings.
'
: ANSWER:. 098, (1.00) '
o
, .
bL (+1.0)- l
. ,
'
' REFERENCE:L 11'.=PeachBottom:j0N-113," Loss;ofRBCCW",pg1. '
,
52.= Peach Bottom: I.0T- 1550 ' lJ.0. ' 2. ..
'
q.. 3k K/A 295018K101 , 7 (3.5/3.6) (11/11)
:295018K101.
.
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$ )QdESTION: 099hl(1,00)J .
f
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~
; WHICH ONE (1) ?of tthe'following' systems, when lost,- will cause a high : air
;,inleakage to?the, Main Condenser AND;a large decreaselin condenser vacuum?- ;!
.a n !h . a .; [ Circulating! Water u
a
' b. : cSeal; Steam _ - , t .
I gcc ::0ff' Gas /Recombiner- .
'
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. a +Ld. , Air: Ejector
,
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y + 1 43 'e - ) tREACTOR OPERATOR'
Page-73 j
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: ANSWER:- -099-(l.00)- .
, ,
'
: bt [+1.0)-
,
REFERENCE: i li Peach Bottom:~OT-'106, " Condenser Low Vacuum - Bases", pg 3.
.
'
2.: Peach. Bottom: LOT-1540, L.0. 2.
,
, 3.;K/A 295002K211 (2.6/2.7) (11/11) ;
295002K211 ..(KA's) t
' -QUESTION: 100 (l '. 00) . ' ;WHICH ONE:(1) of.the following will be inoperable from the emergency shutdown , ' panel 'following a loss of- Uninterruptable AC Power? !
I fa. Emergency; Service-Water Pumps
',
'
~b. LRCIC -Steam Supply . Valve 1(M0-15)
Ec . : .SRVs E,'H, and L-K d-. HPCI!
,,
n ,. ,- q
, (ANSWER:- ,1001'(1.00)_ i -
i Mbr.1 {+1'0) .
;t U'- '4 LREFERENCE:' ,
b 'IL Peach. Bottom: ON-ll2, " Loss of: Uninterruptable AC Power", pg 1. ~l , "~
' 2. Peach' Bottom: LOT-1550, L.0, 2.
. l
.'3CK/A'295003K204-(3.4/3.5)-(II/1)' _3
. .y
'295003K204 ..(KA's) -.1 q
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-
i (********** END OF EXAMINATION **********)
:
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:-______.--__._: -.- _.
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:Vr y, o - > .+ ATTACHMENT 3 pp ;g ' Facility. Comments on Written Examination ,
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* \e PHILADELPHIA ELECTRIC COMPANY I - 4 PEACll BCilTOM ATOMIC POWER STATION O' R. D.1, ikn 208 ' .
Delta, Pennsylvania 17314 t r:4cu m<nwn-rua rou ss os e xcittance pl7) 456 7014 l Jr,
L s Sep; amber 28, 1990
$t i
l ? Mr. Richard J. Conte, Chief i Operations Branch :! Division of Reactor Safety [ U.S. Nuclear Regulatory Commission l JRegion 1 . . j
# 475 Allendale Road King of Prussia.:PA; 19406 .
,
...', SUBJECT: . Facility Comment on Written' License Examination Administered at !
{,l Peach Bottom Atomic. Power Station, September 24, 1990
Dear Mr; Conte:
[
The a'ttachment to!this letter documents the, complete formal comnent-' .I
?[ " ' '
summary of the Reactor Operator License Written Examinations administered on )
'
; September. 24, 1990.; The majority of'the referenced supporting documentation, i-
'of;which portions are attached -can be found.in materials forwarded to your-- 1 JofficeLfor exam preparation.-
:r
, a
Sincerely .-
;
*
E. A. Till< i Superintendent - Training' t '
'
EAT /JWL cig-EAttachments-
~ . cc:. J. B. Cotton ; , ,T. A. Easlick, NRC q .J. F." Franz- ^'
i 0; B.i Miller,' Jr. l PBT: File. ! l
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l OVEST10N8 031 L
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Reactor operation is allowed to continue following a trip of the "B"
< ;ecirculation pump. WtilCil ONE (1) of the following methods will determine True Core flow?
a. A Loop flow - 0 Loop flow b. A Loop flow - 1.95(B Loop flow) c. A Loop flow + B Loop flow d .' A Loop flow - 0.95(B Loop Flow) ANSWER: 031(1.00) d. (41.0) REFERENCE: 1. Peach' Bottom: LOT-0030 .Pg. 47, L.0. 8 2. K/A 295001A203 (3.3/3.3) (11/11) 295001A203 . , ( r.A ' s 's FAClllTY COMMENT: Reactor Operator 031. Delete entire question. Question requires candidates _to havememorizedaformulacontainedwithinaprocedure(OT-112) follow-up section, whereas the referenced objective (LOT-0030. Pg. 5, L.O. 8) only requires an understanding of the bases for any procedural step. Additionally, the referenced ability (AA2.03) requires candidates only to have the ability to.
determine actual core flow following partial-loss of forced core flow. The question does not measuste the ability to use the formula but rather the knowledge of the exact formula.-
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LOT.0030 l
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. , L' 202001.K$.06 e. ATWS Recire Pump trip l 202001.K5.'07 f. Natural circulation ! l
..202001.K$.30 g. Motor generator set operation
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202001.K6. 6. Explain the effect that a' loss or malfunction of the ! f" , following will have 'n.the o Reactor Recirculation System:
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cf 202001.K6.01- a. ' Jet pumps
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"' - -202001 K6.02 b. Compon'ent cooling water systems :
i i 202001.K6.03- c. A.C. power .. T
' ') , 202001.K6.04 d.- D.C. power !.
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q '202001.K6,0$. e. -Control rod drive system
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a . . . . .
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1202001.K6.06 f. Recirculetion system motor generator sets a
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202001.K6.07
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g.- Feedwater flow .
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202001 K6.09 h. -Reactor water level 1 ~0"f . ;i ,
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F 202001'.KG.04- [7. Describe the' system purpose and/or function, a p .cg, ,
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y r < , i> t 18.1 Concerning 0T.112, *Recirculaiion Pump Trip" m n.
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ta. State'the. entry conditions:
(,l, b..' State:the immediate-operator' actions '
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c. State the bases for any procedural step _, s ;r ~ , j
.< 9, Concerning ON.100 * Failure of a-Jet Pump"' !
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a. State.the symptoms ,j
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/r t , M,'3- b. State the operator actions -. a
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c. State the bases for any symptom or procedural stepi l c
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g ny l202001.KG.07 10. Describe the purpose and function of major system
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E 1, components and controls'.
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Describe the recirculation system flovpath,
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> l Emergency / Abnormal Plant Evolutions .
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APE: 295001 Partial or Complete Loss of Forced Core Flow Circulation !*'
. v.3 APE:
IMPORTANCE K/A NO. ABILITY , R0 SR0 - AA1.03 RMCS: Pl a n t-S pe c i fi c . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 2,7 AA1.04 Rod control and information system: BWR-5&6.......... 2. 6 2.8 AA1.05 Rec irculation fl ow control system. . . . . . . . . . . . . . . . . . . . . 3.3 3.3 9,
AA1.06 Neutron noni tor ing sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3 3.4 AA1.07 Nucle ar boiler instrumentation system. . . . . . . . . . . . . . . . . 3.1 3.2, - > AA1.08 Standby liquid control: BWR-1........................ 2.5* 2,8; . 10.
AA2. Ability to determine and/or interpret the following as ; they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE s
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FLOW CIRCULATION : J gg,
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3 ' AA2.01 Po we r / f l ow ma p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5 3.8 Neutron monitoring.................................... 3.1 ; AA2.02 3.' 2 AA2.03 Actual core flow...................................... 3.3 3. . 12, 1 AA2.04 Individual jet pump flows: No t -BWR -18 2. . . . . . . . . . . . . . . 3.0 3'.1 4-
- AA2.05 Jet pump operability: Not-BWR-182.................... 3.1 3.4 AA2.06 Nuclear boiler instrumentation. . . . . . . . . . . . . . . . . . . . . . . . 3.2 3.3
, a SYSTEM GENERIC K/As ]
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1. tKnowledge of system status criteria which require the F
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notification of plant personnel. 2.9 3;. d
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3' p 2. tKnowledge of which events related to system operation / status s D should be reported to outside agencies, .0* 4. M
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y 3. tKnowledge of limithg conditions for operations and safety #
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limits. 3.2 4.,
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4. tKnowledge of bases in technical specifications for limiting conditions for operations and safety limits. 2.8* 3.7 f.
.; D '.I 5. Knowledge of the annunciator alarms and indications, and use a of the response instructions. 3. 4 33L
, !X 1 6. Ability to locate and operate components, including local n ?
controls. 3. 5 3'. 4 - -
.i 7. Ability to explain and ar;Uy all system limits and 'i I '
precautions. 3. 3 3. $ - 8. tAbility to recognize indications for system operating
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parameters which are entry-level conditions for technical - specifications. 3. 5 4.2 ? 3
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~K'/A catalog: BWR 's 4.2-2 :M i M ./A ca
I' ! t.. QUES 110Ns 013 ; L
The Emergency Service Water (ESW) pumps have auto started due to a diesel generator start. After 2 minutes. the 'B' ESW pump is secured. WHICH ONE (1)
of the following actions will occur if the 'A' ESW pump motor trips on t overcurrent?
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a, 'B' ESW pump will start after a 25 second time delay, b. ECW pump will innediately start,
, c. 'B' ESW pump will innediately start.
d. ECW pump will start after a 20 second time delay.
I ANSWER: 013(1.00) t a. (41.0) r REFERENCE: 1. Peach Bottom: LOT-0600. Pg. 8. L.0. ? 2. K/A264000A306(3.1/3.2)(1/I) 264000A306 ..(KA's)
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FACILITY COMMENT: f Reactor Operator 013. Candidates could select either a. or b. since answer ~b.
l is supported by Lesson Plan LOT-0410, pages 10-11. Item C.2.b per Lesson Plan Objectives 2 and 4.a.
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LOT.0410 Rsv. 007 PEN /tvj Page 2 of 19 i PHI 1ADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION HOT LICENSE TRAINING PROGRAM LESSON PLAN IIILE: Emergency Cooling Water System PURPOSE: ! Familiarize the license (d) trainee with the Emergency cooling Water System design, function, and control.
OBJECTIVES: Upon successful completion of this lesson, the RO/SRO student will be able to answer the following objectives in an exam or walkaround format with a minimum of an 804 success rate.
- 1. State the purpose of the ECW System.
- 2. Describe the automatic start features and interlocks associated with the ECW System.
- 3. State the basis / reason for any cautions or notes found in the ECW system operating procedures when provided a statement of the caution or note.
, 4.- Describe the flow path for the ECW System under the following abnormal situations:~ ,
* a. Loss of ESW '* b. Loss of Conowingo Pond as a Heat Sink 5. Given a' set of conditions, use plant procedures to discuss the operator's required actions for: * a. A startup of the Emergency Cooling Water System 1- *
b, 'A shutdown of the Emergency cooling : J -* c. Makeup to the Emergency Cooling Tower
* d. Decreasing the water level in the Emergency Cooling Tower Reservoir
*- e. Using the Emergency Cooling Water Pump at an En.ergency Servict Water Pump
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Page 10 of 19 l l SUBJECT MATTER OUTLINE SUPPORT INFORMATION
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2. Auto Start Signals: ESW, ECW pump autostarts required feeder bus a. 36 seconds after: voltage > 954 and control l switch in its (spring 1, 1) D/G Low Speed Relay (LSR) actuation (D/C
> 250 RPM).
return to) Normal position.
.! . 2) MCA relay actuation, b. Low discharge pressure on running ESW pump. l
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3. Manually stopped <l C. ECW Pump ,
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1. "Stop/ Start / Pull to Lock / Normal * control C.26D switch, 2. Automatic Operation Following D/G start or MCA relsy actuation. Control switch in Normal and properly flagged.
TIME'
(in ame.) EgggI L
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0 . Diesel generator start (LSR 250 RPM) or MCA relay. f-36 Both ESW pumps & the ECW pump start E Bus voltage > 954 of rated . 45 ECW pump auto trips if ESW pressure .;; established..if not, ECW pump continues to 3 run , i'y . . 80 if ESW pres.sure is still not established -
*ESW Wash to' Pond VLV MO.0498 Open*
annunciator alaras to alert the operator to
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3 7 '" ' a condition which requires the M0 0498 valve '
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to be closed while it is still open. ECW . , , pump-discharge valve-(MO.0841) automatically ; opens..
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-The ESU Booster Pump in ' Auto Standby * At this point there.is a starts 30 seconds after M0 0498 is shut if complete flovpath from tho'
the ESW Booster Pump selected to ' Auto * has reservoir through the-
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LOT.0410
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Page 11 of 19 SUBJECT MATTER OUTLINE SUPPORT INPORMATION not developea sufficient discharge pressure diesel coolers back to the And M0 0498 (ESW discharge to the river) hat Emergency Cooling Towers, been shut for at least 30 seconds. An ECT fan should be started, b. Auto starts if ESW system pressure drops < 30 psig on PS.0246A while MCA or D/C LSR relay is actuated. And B D. ECW Pump Discharge Valve (MO 0841)
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1. Valve has no control switch. (Operates off of Valve status lights are on ECW pp. control switch or automatically from C26D ler,1c.)
2. Automatically ypens: a.. Immediately opens following manual ECW pump start, b. 80 seconds after initial automatic start signal if ESW pressure is low.
3. Closes when ECW pump control switch is taken to
"STOP" or " PULL TO LOCK", ' E. ESW Booster Pumps (2)
Three. position switch ("Stop/ Auto / Auto. Standby") C123 Switch contacts are maintained 1. "Stop" . stops the pump.
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2. " Auto" starts the pump when MO.0498 is fully completes path back to closed, cooling tower.
3. " Auto. Standby" . pump will sturt if other pump Discharge pressure < 40 has not developed sufficient discharge pressure psig And M0 0498 (ESW discharge to the river) has baen shut for at least 30 seconds.
~ 4. ' Both pumps have low suction pressure trip and < 12.1" Hg vacuum for lock out. This is likely should the running 10 see time delay.
ESW pump (s) trip.
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".. LOT 0680 '
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Page 2 of 17 - l' , i, - FilIIADELTHIA ELECTRIC COMPANY PEACil BOTTOM ATOMIC POWER STATION HOT LICENSE TRAINING PROGRAM LESSON PLAN
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TITLEt Emergency Service Water (ESW) c PURPOSE: I
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I-L l'arr.lliarize the license (d) trainee with the Emergency Service Water System f unction, components, operational aspects and their effect on safe facility operation.
OBJECTIVES!
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i b Upon successful completion of this lesson, the RO/ BRO student will be able to answer the following objectives in an exam or walkaround format with a p minimum of an 804 success rate:
* 1. State the purpose of the system 264000A3.06 * 2. List the condition which will automatically start the E.S.W. -
r pumps,
, * 3. List'the heat loads cooled by the E.S.W. System.
- 4. State which system backs up the E.S.W. System and describe how it is automatically initiated.
- 5. Given an E.S.W. system simplified diagram, discuss major $
flowpaths.
- 6. Given an'E.S.W. system control device or indication, describe its operation. ,
* 7 '. Describe'the E.S.W. System Emergency.Shutdowm and l Alternative Shutdown capabilities.
B. Given a' set of conditions, use plant procedures to discuss - the operator's required actions for: ! L
* a. Startup of the E.S.V. System ( *: b. Shutdown of the E.,$.V. System $
c. Eig~r. racistiot. condition it. tnt E.i .i tifiuer.: ..
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LOT 0680 R;v. 006
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Page S of 17 5 __
( 1 SUIVECT MATTER OUTLINE SUFPORT INPOP.MATION 2. Af ter both ESV purrps are verified started, < 25 psig on PS 0240A cr B one can be secured. If the running pump then for 25 seconds loses discharge pressure it auto starts the second pump.
3. Both ESV pumps are backed up by auto start of < 30 psig on PS 0246A Emergency Cooling Water pump as long as a And B pump auto start signal is present (covered in 3
, more detail in ECW system).
B, Pump Control Switches (START /STOP/ NORMAL)
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Spring return.to "Normala on panel C 26 B, C 0. Sluice Cate Operation Unit 2 MO 2233 A,B o Unit 3 MO 3233 A,B
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1. Each unit's pump structure has 2 sluice gates Sluice gates are located which are controlled by indivitlual (4 total) j s on the Inner Screen switches on the C123 panel (" Raise / Lower ). a Structure Building West wall. i I 2. Taking both unit-control switches to " Lower" (LitT causes: f m. Service water pumps on an associated unit j to trip. ! b. Screen wash pumps on an associated unit to trip.
c.,ESW wash to pond Valve MO 0498 OPEN
" alarma . ,
1) Valve must be closed from C123 panel using the control switch within 200
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seconds of operating the * PERMIT TO CLOSE" pushbutton 2)'An ESW Booster Pump will automatically [ start when MO 0498 is fully closed !
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3. Automatic pump bay level control (106' ' elevation) is initiated via gravity drain and
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l Bay levels may be manually ,
'HO 2804 A,L (MO 3804 A,L) when the sluice controlled using LC- !
gates are fully shut ' 2(3)804A,B on C123. j
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l QUESTION . 052 WHICH ONE (1) of the following emergency classifications is the minimum , classification required for failure of safety systems needed to protect the ' public? a. General Emergency b. Site Emergency c. Alert f o d. Unusual Event p
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ANSWER:- 052(1.00) b. (41.0)
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REFERENCE: ; 1. Peach Bottom: LOT-1520 Pg. 6. L.0. 3 ' 2. K/A294001A116'(2.9/4.7) ! 294001A116 -..(KA's) " FACILITY COMMENT: Reactor Operator 052. Delete entire question. Question. requires ~ candidates to
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classify an Event. The referenced site' objective (LOT-1520, Page 2, L.0. 3) l requiresionly that emergency classifications be identified and listed in order l of severity. The referenced plant-wide generic K/A (A116) is not applicable to , Peach Bottom Reactor Operators since only SR0 s are required to classify events. '
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LOT 1520 Rev. 004 RKB/tvj l
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Page 2 of 26 ,
; .i-PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION HOT LICENSE TRAINING PROGRAM LESSON PLAN .
l TITLE: l' PBAPS Emergency Response Plan
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4 PURPOSE:
, To familiarize the license (d) trainee with the purpose and objectives of the Emergency Plan.
- t-QBJECTIVEE:
-l Upon' successful completion of this lesson, the RO trainee will be able to:
1..' Identify the basis for' emergency planning.
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'2. Define the Emergency Planning Zones'(EPZ).
< 3. . Identify the' classes of emergencies, in order of severity. ,
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4 Identify th'e Emergency Response Facilities, their locations, and
: functions.
'l , S. Define the4 role of the Emergency Response Organization (ERO).
l: 6.'-Identify, by'ERO title,- key personnel within the Emergency Response -i l
' ' Organization,.for both'the initia1Lphase and for the recovery response '
l. phase of the emergency.- !
.7. Identify and describe the basic responsibilities of the PBAPS Emergency {
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Response Teams. !
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l , 8. Identify the~ notification methods to.be used by the PBAPS Emergency ~ .
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l Response Orgenization. l
'l 9.1 Discuss'the need to maintain emergency preparedness and the methods to ,
accomplish a high level ofLpreparedness.
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