Text

Discusses Re Info to Support Util Position Relative to Resolving Issue of Main Steam Line Breaks Inside Ice Condenser Containments & Requests That Info Be Withheld (Ref 10CFR2.790)
	ML20064A574
Person / Time
Site:	Mcguire, Catawba, McGuire
Issue date:	09/04/1990
From:	Tucker H; DUKE POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19302E199	List: ML20064A574;
References
	NUDOCS 9009140124
	Download: ML20064A574 (5)
	v • d • e

{{#Wiki_filter:!p - e y 4 ( -k 7.a ' Duk Mer Cony >any thiil % sa l PO llax 33198 Vice hnident {%arlane, N C 28242 - Nuclear huduction l (?tWktT3-4Ltl j DUKE POWER September 4. 1990 U. S. Nuclear Regulatory Comission l ATTNt Document Control Desk Washington, D.C. 20555-i

Subject:

Catawba Nuclear Station, Units 1 and 2 l Docket Nos. 50-413 and 50-414 f r McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Main Steam Line Breaks in Ice Condenser Plants i Gentlemen: i I I 11, 1989, the NRC staff requested that Duke Power ll By letter dated May h Company review and comment on Argonne National Laboratory's (ANL) l confirmatory analysis which was performed to validate conclusions made relative'to Main Steam Line Breaks (MSLBs) inside an Ice Condenser Containment. Of specific concern were the superheated temperatures the ANL l analysis predicted in the vicinity of the break locations which exceeded the l Environmenta?, Qualification'(EQ) limit of 327'F. My Ictter dated July 17, l 1989 transmitted Duke Power Company's comments which concluded that local R temperatures near the break could exceed the EQ limit, but that there was no i equipment required for MSLB mitigation close enough to the break locations to be affected. Additionally, DukeLprovided a technical justification as to why the COBRA-NC temperature predictions are more accurate than those l predicted by the COMMIX code. My letter dated August 17, 1990 transmitted information to support Duke Power's position relative to resolving the issue of main steam line breaks '? H inside ice condenser containments. The information in the August 17, 1990 letter is considered to be proprietary by Duke Power Company, however, an I affidavit attesting to this fact was not included with the submittal. l i: In accordance with 10CFR 2.790, Duke Power Company requests that the l. attachment to my August 17, 1990 letter FP Considered proprietary by the L NRC. Information supporting this request is included in the attached affidavit. A version of the information in my August 17, 1990 letter, with .the proprietary information marked in brackets is also attached. A non proprietary version will be submitte.d following receipt of the Safety l. Evaluation Report closing this issue. Very truly yours, i ()s1m n m m,- 4 t. s llal B. Tucker MHH-63/lcs 9009140124 900904 D M I PDR ADOCK 05000369 1p* .P PDR i =

/"~; 1 U. S.' Nuclear Regilit;ry Commitrion September 4, 1990 Page 2 1 cci Mr.~ Stewart D.-Ebneter. Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta,' Georgia 30323 Dr. K. N. Jabbour o Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission One White Flint North Washington, D.C. 20555 i-Mr. D. S. Hood Office of Nuclear Reactor Regulation-l U.:S.' Nuclear Regulatory Commission Washington, D.C. 20555 I '[ Mr. P. K. VanDoorn NRC Resident Inspector _ -6 -McGuire Nuclear Station 1 Mr. W. T. Orders Senior.NRC Resident Inspector Catawba NuclearLStation i. 5 ? I I -( i k f l, i' b w

.. y c, u AFFIDAVIT OF T. C. McMEEKIN ? i r-1. I am Vice President, Design Engineering Department of Duke power.- Company (" Duke") and as such have the responsibility of reviewing'the ~ proprietary information sought to be withheld from pubile disclosure in connection with nuclear power plant licensing or rule-making y proceedings, and am authorized to apply =for its withholding Un behalf l of Duke. 2. I am making this affidavit in conformance with the provisions ~of 10 CFR 2.790 of the regulations of the Nuclear Regulatory Commission ("NRC") e and in conjunction with Duke's application for withholding which accompanies this affidavit. 3. I have knowledge of the criteria used by Duke in designating information as proprietary or confidential. 4. Pursuant to the' provisions of paragraph (b)(4) of 10 CFR 2.790, the following is furnished for consideration by the NRC in determining whether the information sought to be withheld from public disclosure

j should be withheld, i

(1): The information sought to be withheld from public disclosure is-owned by Duke and has been held in confidence by Duke and its consultants.- (ii) 'The information is a type that would customarily be held in ) confidence by Duke. The information consists of analysis methodology details, analysis results,: supporting data, and aspects of development programs, relative to a method of ' analysis that provides a competitive advantage to Duke. Ll (a) The use of the information by a competitor would greatly reduce its expenditure in qualifying similar methodologies. l i ~ (b) It reveals aspects of a methodology with potential commercial value to Duke Power. (iii) The information was transmitted to the NRC in confidence and ,t under the prov.isions of 10 CFR 2.790, it is to be received in confidence by the NRC. (iv) The information sought to be protected is not available in public sources to the best of our knowledge and belief. l l

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C. McHeckin (continued) i {;. ?!

.;.,,.(. o F n' ' 14 i AFFIDAVIT OF T. C. McMEEKIN (pane 2) F /" os e (v) The proprietary information sought to be withheld is identified in the report attached to this letter concerning the Main Steam q i; Line Break Superheat-issue. 1 i This information enables Duke to i (a) Characterize the containment response to superheated mass and energy releases resulting from steam line breaks inside containment. V (b) Evaluate the adequacy of systems and components with -l respect to a harsh environment and the environmental a' qualification requirements of 10 CFR 50.49. (vi) The proprietary information sought to be withheld from public l disclosure has substantial commercial value to Duke. .(a) It allows Duke to reduce vendor and consultant expenses associated with supporting the operation and licensing of nuclear power plants. (b) It could be used by other organizations without ,j compensation to Duke. Duke is in the business of / providing such services. (c) The subject information could only be duplicated by competitors at similar expense to that incurred by Duke.. '5. Public disclosure-of this information is likely to cause harm to the o position of Duke because it would. allow competitors in the nuclear industry to benefit.from the results of a significant development i program without requiring a commensurate expense or allowing Duke to recoup a portion of its expenditures or benefit from the sale of the information. 4!' 9 h i m

V'- +8 r. kh N+. i, AFFIDAVIT OF T. C. McMF.F. KIN (Pane 3) i Ted C. McHeekin, being duly sworn, on his oath deposes and says that he is the person who subscribed his name to the foregoing statement, and that the matters and facts set forth in the statement are true. V T.- C. McMeekin M'dayof_$dedg ,1990, Sworn to and subscribed before me this k$/ . && J D Notyfy1iblic [ ' My Commission Expires OdHado /.8, //f3 l I i

= .: e..,, p;,a n. August 09. 1990 4 L ( F Carolina Power and Light Company ATTN: Mr. L. W. Eury ~ F Senior Executive Vice President i, Power Supply P. O. Box 1551 Raleigh, NC 27602

SUBJECT:

EXAMINATION REPORT 261/0L-90-01 C # On' July 9-13, 1990, the NRC administered examinations to employees of your company who had appl.ied for licenses ~ to operate the H. B. Robinson Steam. Electric Plant.. At the conclusion of the ' examination, the = examination p L questions and preliminary. findings were discussed with those members of your l [ staff identified in the Examination Report. Enciosure 1. Copy of the written examination and answer key are included as Enclosuro 2. I A copy of the Facility Comments. to the written examination are included as The NRC Resolution of these connents is included as Enclosure 4. A Simulation Facility. Fidelity Report is included as Enclosure 5. f In accordance with 10 CFR 2.790(a), a copy of this letter and its enclosures t will-be piaced in NRC's Public Document Room. l Should you have any questions concerning this letter, please contact us. ( Sincerely, j (ORIGINAL SIGNED BY T. A'. .ES) Thomas A. Peebles, Chief s Operations Branch i Division of Reactor Safety

Enclosures:

1. Examination Report 50-261

2. SR0 Examination & Answer Key i

3. Facility Comments

4. NRC Resolution of Facility Comments

5. Simulation Facility Fidelity Report

] cc w/encls 1, 3,4 4, & 5: L. H. Martin, Corporate Training Dir, i R. E. Morgan, Plant-Manager -(cc.w/enclscont'd-Seepage 2) gg g. g

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.i y, a. Carolina Power and Light Company- '2 August 29,'1990 cc w/encls 1, 2, 3, 4, & 5: C. R. Dietz, Site Training Director cc w/ encl 1:. State of South Carolina (bec w/ enc 1 cont'd) R. Carroll, Acting Section Chief DRP L. W. Garner Senior Resident Inspector M. Ernstes. Principal Examiner C. Rapp, Chief Examiner-bec w/encls 1 and 5: Operator Licensing Branch, DLPQ:NRR b i . pw/encls '1, 2, 3, 4, & 5: taiRC Public Document Room .Sonalysts, Contractor g l t. i c u 1 r.

FOR PREVIOUS CONCURRENCE - SEE ATTACHED COPY RII:bRP RII:D RII:DRS.

RII:DRS RII:N + 7Pe bles l

CRapp MErn[tk%

JMunrc,a DVerrelli 4 08/ /90 08 @ 93 08M/90 08/g%/90 08/ /90 i s

Fj;., "I, ~ .1 e-e- i / UNITED ST ATES a Me ' m NUCLEAR HEGULATORY COMMISslON RE GION 11, O I 1011dARIETTA STREET,N.W. ATLANTA, GEORGI A 30323 t

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....+ / ENCLOSURE 1 EXAMINATION REPORT N0.: 0L-90-01 Facility Licensec: Carolina Power and Light Company H. B. Robinson Steam Electric Plant P.O. Box 790 Hartsville. SC 29550 L Facility Docket-No.: 50-261 ' Facility License No.: DPR-23 ExaminationswereadministeredatH.B.RobinsonnearHarthville.SC. 8/jg/fD Chief Examiner: ew Cdrf Rapp Date ' Signed f Approved.by: ' AS [ I//$ dihMfrL UOhnF.+Munro,SectionChieff Date Signed .,3 Operator Licensing Section 1 Operations Branch Division of Reactor Safety c j

SUMMARY

Examinations administered on July 9-13, 1990, n Written 'and operating examinations were administered to 5 SR0 applicants. A 9 written re-examination was administered to' 1 SRO applicant. Simulator ae-examinations were administered-to 2 SR0 applicants and 1 R0 applicant. All applicants passed these examinations. t ? ' l i e nQ1&n i i &&ty p y v2 w

t y G V p e j REPORT DETAILS i 1. Facility Employees Contacted i l

S. A. Billings, Technical Aide - Regualtory Compliance i
R. L. Barnett, Outages and Modifications Manager
C. R. Dietz, RNPD Manager
J. D. Kloosterman, Regulatory Compliance Director-
C.-A. Bethea, Training Manager
R. E. Morgan, Plant General Manager
R. Shane, Operator Training Senior Specialist
A. Sanders Simulator Manager
R. A. Steele, Operations Coordinator
S. Allen, License Training Manager
J. B. Allen, Operator Training Senior Specialist
T. R. Byron, Operator Training Senior Specialist 1

l L

Attended Exit Meeting 2.

Examiners. t

C, Rapp, Region II T. Guilfoil, Sonalysts I. Kingsley,-Sonalysts B.Maier,RegionI(Observer)

D. Lane, Sonalysts (Observer)

- L. W. Garner, Senior Resident Inspector
- K. Jury, Resident Inspector
Chief Examiner
- Attended Exit Meeting Only l

3. Pre-Examination Review On June 25-26, 1990, representatives of the facility reviewed the written examination at the Region II office. This review was_ conducted to improve examination technical accuracy and ensure all test items were correct and concise prior to administration. 4. Post-Examination Review Following examination administration, a copy of the written examination was left with facility representatives for review. The facility submitted three comments for NRC review. 5. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination. The following items were discussed at the exit meeting.

~ c e y c i e

1) A0P-001, Rod Control System Malfunction, does not include direction for recovery of dropped shutdown bank control rods, s

2) No direction is present for the amount of power reduction or how to l

conduct the power reduction following a failure of turbine runback, r [

3) A0P-14, Loss of CCW, cautions against operating two CCW pumps as

[ required'by the E0Ps. ~ j a

4) Vent cap for seal injection filter is corroded and no hose exists to.

route venting to floor drain, i a

5) Operators were' observed' acknowledging alarms without informing other operators during simulator exaa.inations.

6) ~ FRP-H.1 was not entered even though all AFW flow was going to an unisolable faulted steam generator and providing no primary heat removal. The Critical Safety Function for loss of heat sink states 300 gpm to any steam generator as the entry condition. This criteria fails to consider an unisolated

' faulted steam generator and delays initiation of feed and bleed when required i for core cooling.

7) Foldout 'C' SI Reinitiation Criteria improperly required the operators

. to transistion.to EPP-17, SGTR with Loss of Primary Coolant. This delayed identification and isolation of the ruptured steam generator when no loss of primary coolant existed. Also, Foldout 'C' superceeds Path 2 which has the opeators check for indications of a loss of primary coolant at discrete points in Path 2.- .The cooperation given to the examiners was also noted and appreciated. ~ ' -The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners. } i

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ipa 2s-this.examinationb you mustLachievecanyovera11 grade.ofl-atuleastl80%.

O Examination! papers will beEco11soted ' four 'and 'one: half (4 1/2)?hotirs afte6_ W ',',, w w. s nthy examination 5 starts 2', 4 + 9 37 w 3 3, [..- 4

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.hbN[%Ah MN'A NE+' ft ~ i fjg ^ x M. q ]f;%gi " 'NRC. RULES ANDLGUIDELINES FOR LIC*ENSE EXAMINATIONS Mrihg(theJhdminitratioko)thisLexamnationthe;followingrulesLapply- <s'

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. D J p: a Wr..qCheating on!the examination)meanscan' automatic l denial:pf,your application-m g ;andEcould= result 11n'more severe. penalties.: 42blAfher the 'examinatiori has beenicompleted. -you must sign :the7 statemention? ?' ithetcover sheet indicating that.the work is your'own and you have not: e freceiv'odior:given assistance in completing the examination; This must be- ,idine..AFTER you; complete the examination. ..x %3. Restroom tripsiareLto be limited and'only one candidate;at;a time may 4.i lcavet You must avoid'all contacts _with anyone=outside the examinationi 3 3 room'to avoid evepthe appearance orcpossioility:of cheating. , a-246 Die: black ink"oridark. pencil (only to facilitate. legible reproductionsL W J,. j 550 Print 1youri name _ in: the; blank' provided,in t ho~ upper right-hand : corner,of. ithe-examination. cove sheet. ~ % l l'te your: answers:on thecanswer sheets grovided. '6L Wri If you.need additionalL Tpace to answer av specific: question,.use Ja separate l sheet of the paper ^ 4 [,;(provided and insert.ittdirectlyLafter the specific: question.- DO NOTLWRITE 4 ON THE BACK SIDE:OF THE EXAMINATION QUESTION PAGE. sT 4. MEPidn'tlyo'ur. name! in : the upper, right-hand corner:of each page of theianswer. ,m:1 Osheets.;aThisJmay:be-done after you have completed lyour-examination. ' ['8M - :e,sB foreIpou? turn in'.your'axamination'.. consecutively number each' answer lheet, including-any! additional pages' inserted when writing your answers: u' /onithe examination question,page. la;):U;ecabbbeviations ONLY if they'are. commonly used in facility literature.: $9 1AvoidJusing(symbols such 'as <cor > signs,to avoid a simple, transposition- '4 '.> bcrrordresulting;in an incorrect ~ answer. t m j 3i $dNTheLpointiv'alue-forseachquestionisindicatediin= parent!heses'afterthe 4 question;, Thefamount~of blank space on.anLanswer sheet 11s:NOT:an i m 2 ', f, ' indica *;ionLof^the: depth?ofLanswer required.. J 4,.> l' ..,.% Show'allJe,alculations, methods, or. assumptions used to obtain an answer. 111

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L12. P2rtia12 credit may-beigiven.. Therefore.' answer'all parts of'the question-6' cnd.doinotaleave any" answer blank. NOTE: Partial credit will NOT be-tiveni.on; multiple choice questions. .?' y $130 Proportional grading will be applied. Any. additional-wrong information n LthatLisLprovided will count against you. For example, if a question.iel $'c worthfone pointLand; asks for-four-responses, each worth 0.25 points'and g f ;y'ou1give five responsesileach of your responses will be worth 0.20 points.; 4 "' [If Lone

ofmyour responses is incorrect, 0.20 will be deducted and your-

? total?creditifor"that question =will be 0.80 instead of 1.00 even though .youLhavelfourfcorrect'answere, pl4i Ifl the-intent of a question 1s unclear, -ask questions of the examiner s ionly. c 2 L .l ,v' 4.: ?. hlm b ' ' ~

r- .wr u 3 .1,5' #Whin* turning if your :xamin1 tion, assemb1D thD complct d ::xaminnti~n _ ith esamination questions, examination' aids and answer _ sheets. In addition. ,_ turn in all scrap _ paper.. t 116 To pass the examination, you must achieve an overall grade of 80% or greater. 17 There is a time ~ limit of 4 1/2 hours for' completion of the examination. 18L When-you are done and have turned in your examination, leave the examin-tion area as defined by the examiner. If you are_found in this area while the examination is still in progress, your. license may be denied or r:voked. 1 i h

~ ^ \\ ESWIIOR 9tEACTOR : OPERATOR Pig 3 1 { "~ ANSWER SHEET U i b . Multiple Choice (circle or X your choice) ~ {( If you change your answer, write your. selection in the blank. E. b c d ,:001 a !i. -- 002 a b c d j 003 a b c d 7 [ 004_ a b. .c d iOO5-a b c d i >006-a b c d i 007 a b c d

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S$tIOR REACTOR OPERATOR-P g3.2' 4 ANSWER SHEET i-Multiple' Choice (circle or X'your choice) If'you change your answer, write your selection in the blank. 1 ' 026 a b c d 027 a b c d 028-a b c d 'l 029 a' b c d i '030 a b c d t 0'31 a b c d I '032, a b c d l 033-a b c d 034 .a b c d 035 a= b c d -036 a b' c d l l., .037 a b c d 038. a b c d .i 't 039 a. b c d l' 040 'a -b c d a l 041 a' b c d l-i i:,042 a b c d' l :. =! '043: a b c d 1 044' a b c d L 045' a. b c d e t'- 046-a b c d g 047l match with selected number in the blank

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[ >j {' P 't ..m .v' "_~ m. &S$tIOR %tEACTOR CPERATOR - P2g3 4 U o< a u. j , QUESTION:1001 (1100) -Whidh one of the symptoms from the list below are indications of continuous ro'. '] withdrawal?. 1 1k Tave - Tref. Deviation.'

2. Rod, Control Urgent Failure-e

3. Over: Power' Delta-T Rod Stop.

j L 4.. Reactor Power.- Turbine Power Mismatch. a.' 1, 2,. 3 l p j P 1, 2, 4 - J Jb. ~ 1 f> c. 1,~3,'4 N 1 L, d.. '2, 3, 4 -j f 5 QUESTION: '002 (1.00) n (Tha following alarms'and indications exist in the Control Room: j - P.R. DROPPED ROD ROD WDRL'STP alarm - P.R. CHANNEL DEVIATION alarm '2 Rod Bottom Lights lit. 1 - Reactor power'70% 1 Which one.of the following describes the required operator response to this event'in accordance with AOP-001, Malfunction of Reactor: Control System?. i a. -Manually: withdraw control rods to match Tavg and Tref

b. -

Monitor nuclear power and maintain steady state conditions ic. Open the Lift' Coil' Disconnect Switches for the dropped rod r d.< Proceed with an orderly shutdown to Hot Shutdown condicions ] b I Y I' E l' t

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) d l . "s 4.* PCg3' 5-l . setrom itzhCTORL CPERATOR i s 4 1 A 'dUESTION: '003 (1.00) WhichLone of-the following' correctly states-a-condition for' terminating SI ' i .during' Adverse. Containment Conditions? O. Pressurizer. level indicates 10% b. ! Narrow range SG. level indicates-25%

!c.;

RCSLSubcooling indicates 25 deg F Ed.- RCS pressure indicates of'1520-psig and stable 0"- 1 o-QUESTION: 004 (1.00) 'Tho-plant:is. operating'at steady-state 60% power. ' In accordancri with 3th AOP-18, RCP~ Abnormal Conditions, an IMMEDIATE manual reactor trip'is, ) rcquiredLif* 1 RCP A. seal differential' pressure equals 220 psid and is increasing. .]; 7 a. b.- RCP.B frame' vibration equals 3 mils. l c. RCP C upper motor bearing temperature; equals 200 degrees F and is increasing. d.. RCP-A shaft vibration equals 17 mils. I -i bi '.l.3 1 D ' i i U . i

w s f.S$(IOR MEACTOR CPERATOR P293 6 L QUESTION:.005 (1.00) Th3 following conditions exist in the control room: Reactor power - 72%

RCP A vibration

-3 mils on frame and 17 mils on shaft RC PUMPS SHAFT SEAL WTR LO-DELTA P alarm RC PUMPS 1ABYRTH SEAL ID DELTA P alarm n -RC PUMPS SHAFT #1 SEAL LEAK HIGH TEMP alarm CCW: inlet temp to RCP A thermal barrier - 98 degrees F RCP A motor bearing temperature - 165 degrees F Which one of the following is the correct operator response in'accordance' with'AOP-18, Reactor Coolant Pump Abnormal? a. rapidly + reduce power to.< 40% and trip RCP A. 'b.. close RCP A #1 seal leakoff isolation valve. L 'c. trip the reactor, turbine, and RCP A and enter PATH 1. d. determine the leak' rate from #2 seal and refer to AOP-016. LQUESTION: 006 (1.00) t A2Oume ALL emergency boration paths are available. Which one SHOULD NOT be "i uccd if Emergency Boration is required and the plant is to be maintained

ct power?

a. Open FCV-113A (concentrated boric acid control val".e) and FCV-113B' -(makeap stop valve). b. ,Open LCV-115B (RWST to charging pump suction valve) or CVC-358 (LCV-115B bypass valve) and close LCV-115C (VCT outlet valve). c, .Open FCV-113A (concentrated boric acid control valve) and FCV-114B (VCT makeup stop valve). -d.. Open MOV-350 (boric acid to charging pump suction header valve).

F.: m i,,CCIOR hEACTOR' OPERATOR P;g3 7 t , QUESTION: 007. (1.00) Which one of the actions from the list below are immediate actions taken for -0 MAJOR UNISOLABLE LEAK in the Component Cooling Water System? Assume CCW ~ curge tank level is lost. 1. . Trip the reactor and the turbine and follow PATH 1. I 2. Rotate operation of charging pumps to maintain oil temperature less than 220 degrees F. 3. Stop all three CCW pumps. 4. Stop all RCPs two minutes following loss of CCW flow. a. 1, 2, 3 b. 1, 2, 4

c..

1, 3, 4 d. 2, 3, 4 i QUESTION: 003 (1.00) Which one of the actions from the list belos are the actions specified for los of condenser vacuum per AOP-0127

1. Verify standby vacuum pump starts.

2.. Reduce turbine load. 3. Stop one heater drain pump. i 4.' Start standby circulating-water pump. .J a '. 1, 2, 3 b. 1, 2, 4 c. 1, 3, 4 1 d. 2, 3, 4 l 1 i I

'l ,.S'?.IOR MEACTOR OPERATOR P'g3 8 i 4 j QUESTION: 009 (1.00) -Which one of the-following conditions constitutes a LOSS of containment' integrity as defined in Technical Specifications? l c. A manual containment isolation valve is operable and open. j b. A manual containment isolation valve is inoperable and shut, c. An automatic containment' isolation valve is inoperable and open. d.- An automatic containment isolation valve is inoperable and shut. QUESTION:~010 (1-00) Tha basis for depressurizing all intact steam generators to 160 psig in ctcp 9 of FRP-C.1, " Response to Inadequate Core Cooling," is to: a. ensure core exit thermocouple temperatures are reduced to less than-1200 degrees F. b. reduce secondary pressure to aid in recovery of steam generator water level. c. reduce RCS pressure to aid in recovery of reactor water level. d. enhance natural circulation cooling of the reactor core. QUESTION: 011 (1.00) Which one of the following would be an indication of a control bank failure to move during a power increase from 50% to 100%? O. ROD CONT SYS URGENT FAILURE alarm, b. High pressurizer level indication and possible alarm. c. High pressurizer pressure indication and possible alarm. d. Increasing Tavg and possible RC SYS HI/LO TAVG alarm. -.-1 =

fi, a-S?,'IOR hEACTOR OPERATOR PCg3 9'

s 4

CUESTION: 012 (1.00) =Which'one of the actions from the list below are symptoms of loss of an In;trument Bus?

1. " Runback OperhLing" light on turbine governor control valve panel

2. Charging pump suction switch over to RWST.

3. Load reduction.

4. Steam dump actuation.

a. 1, 2,.3 b. 1, 2, 4 c. 1, 3, 4 d. 2, 3, 4 i rQUESTION: 013 (1.00) Which one of the following electrical loads would lose power if off-site End on-site (all AC power) were lost? a '. . Emergency' bearing oil pump b. RCP oil lift pump c.- -Emergency lighting 4 d. ' Generator air side seal oil backup pump i i i

_i va e 'E SWNIOR' REACTOR OPERATOR' Page 10 1 -a I n ^ QUESTION: 014 (1.00). [ LWhich-one'of the-following describes.the reason for evacuation of the

ControliRoom and;the use-of the Dodicated Shutdown. Procedures (DSP) when a-fire' occurs-in the Control Room?

[ al {U ,ah The fire and resulting smoke would require the use of respirators in-the Control Room, which would affect safe operation of the. a s plant. The'resultin smoke.and toxic gas'would hinder the operator's

b. abilitytomon$torplantstatusfromtheControlRoom, requiring

- control locally. .c. ,The fire has the potential tx) destroy-plant controls or their power ~ [ ' cables when Tavg is greater than 200 degrees F.' .d. The fire has the potential for damage to the security access which would violate access control system for the Control Room,ications. control required by Technical Specif j T ' QUESTION: 015 (1.00) LThe unit'has-experienced a loss of all AC power. Following a manual start Lof Diesel Generator "A"1s unsuccessfulbuses E-1 and E-2 are still'deenergized. Manually onergizing E-1 aiid E-2 The major concern on a loss of all 'AC_ power.is... q inadequate core cooling. a. = b. -inadequate RCP seal cooling. c.: loss of primary pressure contro. -d. loss of secondary heatsink. I i ZZ s s -- ) 1 1 i j o y f L

c h,x}""[,,6 /P. i 4 ,? 'c s cpp.R .Y: o M'n g 1:RMEACTOR OPERATOR. c; 88 P2g3 111 q 9 g6,7.. g,. #, J i .e jf ' I f .1 i f - s j l QUESTION: 1016L - (l'. 00); 9 ..z-A[incorrdanceiwithAOP-12,: Partial-Lossof<condenserVaccum?M/>) tWh ) 4 9p,, 1, f.it M 4c k' Condenser vacuum reaches.11 inches Hg backpressure' i .ca /g .jb.lb Condenser DP reaches'36Lin. H20-

i.{

3.y' +- - c.: Condenser hotwell= level reaches 75%. M elf L, ' ~ ' 5 d W d '. ',LENhaust hood-temperature reaches 150~ degrees:F: ,+q M i.$ [, i j l.. li".N o. L iil "s f.iQUESTION:J 017-: (l'. 0 0 ) ' .? y ;N u 3 /[J',FRP-S.1,-" Response ~to. Nuclear Power Generation /ATWS"?Which one of:the a 3 ,i q. o Wi s 1.. Emergency borate.

y

' ' "f "2.1 Check for and eliminate / sources:ofl positive. reactivity.- "i i l3.. Verify subcriticality. "ld .w .P ' ' -4. Establish Safety Injection flow.to RCS.. .+ , dig', D E. ' 4- '? g '{: t 1, 2,a3

Phi, j((:lb.[

.1'r'2, 4. n x, l. a a c. 1, 3 ', - 4 s k. i C -d.- .2,. 3,. 4 i: n q 1 a.T j Q sg .i h t} I m il s i s i i 4 iji ..I'!l

(E l a h fSI!!NIOR' YEACTOR OPERATOR ~ P;g3'12 ?:' E LQUESTION: '0181 (l'.00)' LWhishione~of the'following describes the basis for: establishing hot leg 3 r circulation fc11owing a large break LOCA?. ~ =c; To terminate boiling-in'the hot legs and to ensure balanced cooling' nc of the core. t b. To' terminate boiling.in the hot legs and to prevent boron precipitation. c. To terminate boiling in the core and to: ensure balanced cooling of the core. d. LTo terminate boiling'in the core.and to preven'. boron-precipitation.- .I QUESTION: 019 (l'. 00 ) Thi basis for ensuring / control of. steam generator levels during Natural

Circulation is:

a. to' prevent unnecessary positive or negative reactivity insertions-caused:by varying cooldown rate. L .b. to prevent an. excessive cooldown rate. ( .c. to-provide continuous flow to the steam generator to ensure steam

[

generator tube integrity. Ld. to provide a stable heat sink for decay heat removal. t -QUESTION:~020 (1.00) -Wh'ich1one'of.the fol' lowing Functional Restoration Procedures should have first priority'.if they are all in a RED path condition? 0. FRP-P.1, " Response to Imminent Pressurized Thermal Shock"

b!

LFRP-C.1, " Response-to Inadequate Core Cooling" c.-

FRP-H.1', " Response to loss of Secondary Heat Sink" d.-

FRP-J.1, " Response to High. Containment Pressure" v 3: .I+ ~ ,,J..

- ~ - i[, ~ < .) .' S1!!NIO.R hEACTOR OPERATOR., Pag 3;13 i l-l / Qt1ESTION: ~ 021-(1.00) l l Which one:of the conditions from theilist below require emergency _boration'in_ '. cccordance with AOP-002, " Emergency Boration"? -] 1.JAbnormal control rod insertion. 1

2. Unexplained increasing RCS temperature or nuclear. power.;

L 3 '. Increasing nuclear 1 flux-or count rate when shutdown. -

4. Two or-more' control rods not fully inserted after a reactor trip.

a. 1, 2, 3 ~ b. 1,- 2, 4' c.; 1, 3, 4 . d.; 2, 3, _4 =i -QUESTION: _022 (1.00) Which.one of conditions from the list below are symptoms of accidental' release liquid waste in.accordance with AOP-008, " Accidental Release of~ Liquid Waste"? 1.-WASTE'CONDENSATELTANK "C" HI-LOW LEVEL alarm. l 2.' VOLUME CONTROL ~ TANK HI/LO LEVEL alarm.

3. MONITOR TANK NO. 2 HI-LO LEVEL alarm at the waste disposal' boron recycle-panel.

4. RWST.HI-LOW. LEVEL' alarm.

s a. 1, 2, 3-bd 1, 2, '4 c. 1, 3, 4 -d.- 2, 3,.~4

n> (( w. SdNIOR.MEACTOR OPERAMRT Pag 3:14 </:. .-QUESTION: 023:..(1.00) Which'one of the. actions from the list below are major action: categories'of EP: CFCulted! Steam Generator Isolation"? t' "1. Check main;steamline isolation.

2. Check for at least one non-faulted'S/G.

3.; Prepare to cooldown to CSD. 4.< Check for=S/G tube' rupture. 3 -l e.. ' 1, : 2, - 3 l s X b '.. 1, 2, 4 F c.- 1, ' 3, 4 s- . d '.. '2, -: 3, 4' t .i +... QUESTION: 024 (l'. 00) [ Procedure'EPP-1,-" Loss.of All AC Power" is in.effect when a steam line' rupture occurs on-"A";S/G. Mhich one of_theJfollowing statements is the. correct course of action? 'a. Enter EPP-11,. " Faulted Steam Generator Isolation", and-take required actions._ b. Enter PATH 1 at Point "A" and initiate-Safety Injection. _c. ~ Stay in'EPP-1 until power is restored. h (' d. Enter PATH 2-at Point "J" and terminate Safety Injection. [i p

11 l

l 1: ?

$1 l ] JSENIOR' REACTOR' OPERATOR-peg 3 15 I i a QUESTION: 025- =(1.00) .A complete and sustaine'd loss of Instrument air has occurred. Which one of.the following correctly describes the FAIL positions of the valves licted?; c. . CLOSED:' Auxiliary Pressurizer Spray (CVC-311), Emergency Makeup to. Charging Pumps. Suction (LCV-115B), Feed Reg. Bypass valves, Primary Water'to Blender (FCV-114A) b. CLOSED: Feed Reg. Valves, Charging Flow to Loop 1 (CVC-310A), VCT d Makeup (FCV-114B), Heater Drain Tank Emergency Dump to Condenser-(LCV-1530B) i .c. OPEN: Charging Flow ~ Control Valve (HCV-121), Steam Generator Power Operated Relief Valves, Hotwell Level Control Valve (LCV-1417A),. J ' Blended Flow:to Charging Pump Suction (FCV-113B) d. OPEN: Boric Acid to Blender (FCV-113A), Letdown Line Stop (LCV-460A), Charging Flow to Loop 2 (CVC-310B), Excess Letdown Flow (HCV-137). QUESTION: 3 026 (1.00) i -PATH 2 has the operator check the " ruptured steam generator pre =9ure 1 grsater than 200 psig". Subsequent steps direct the operator to dump steam from thecintact S/G(s as rapidly as possible in order to establish cdequate subcooling ma)rgin. The basis for checking ruptured S/G pressure .graater than 200 psig is to ensure...-(Choose ONE) fa, that no secondary side break existslin the ruptured steam generator prior to beginning the cooldown. v; _ ! b. that RCS pressure will be less than the ruptured S/G pressure after the cooldown to stop primary to secondary leakage. 1 L c.- that the operator blocks the High Steam Flow / Low Steamline Pressure -SI signal when RCS average. coolant temperature is below-543 degrees j' F. d. 'an optimal RCS temperature is established which could preclude a i return'to criticality during the subsequent rapid RCS cooldown.- J l \\ I t 4 I ~

,r9, n; w

( '.

~~

i 5

n a-1 iu '_. (W < 1 'lSdiIOR hEACTOR-OPERATOR! uca s;;y Pag 6116I + B' I 4l: n f t::

s 1

{;4QUE} TION:1027 1(1. 00). m a 5.d.tWhichione of'the following> temperatures would'be^ read on;the1 Pressurizer' H 1 >PORV: temperature indicator:if a PORV.was leaking? (Assume an~ideali ith rmodynamiciprocess a; pressurizer-pressure.of.2000 psig, and'a;PRT4 ( g (prgssure of-5-psig.) e

a'. '

160:Deg.LF' v y+, b. < '210'Deg.'F. o E, c.*

230'Deg. F m

1 d.

260 Deg. F

,j O! / QUESTION: 028- (1.00)

Which-one.of the following Intermediate Range (IR). Nuclear. Instrumentation-

' Channel-indications would allow the: Source Range reactor tripito be blocked ! W onta power-increase in accordance with GP-003, Normal' Plant Startup From. Hot. Shutdown to Critical?- G'[ a. -Both source range channels >-5X10(5) cps b. .Any source range: channel >.5X10(5) cps c.; Both-intermediate range channels > 1X10(-10) amps c d... Any intermediate range channel > 1X10(-10) amps' 1 1 LQUESTION: 029-.. ( 1. 0 0 ) ~ iWhich one'of the following valves failing open would result'in a loss of- .the "A" train of Residual Heat Removal System ability to perform its Emergency Core Cooling System function.-(RHR) Assume' failure occurs prior to. Scfety Injection-(SI). actuation signal. J a.' SI-856A, SI pump miniflow recirculation line isolation valve. b. SI-866A, SI hot leg injection line isolation valve. c.: SI-863A,.RHR pump discharge'to RWST isolation valve. d. SI-862A, RHR pump suction from RWST isolation valve.

$. ;{f'!' A' ~ . u; i l _ Q;bkO k P2g f17 .l q"[p m.R MF CTOR' OPERATOR y r, y / w [, ,a } e NQUESTION:;030jE(1.00)' j , a s //ThM plant is operating; at'200%? power with the-:following'. instrument. M 4 PJfr= dings.< ~' q ny. + w, W, T:. 2 *A" ~ steam - generatorc level':: ^ T1 '22% 24%' L26% 4 n*B" steam' generator level: 24%. '21% . 25%; ,M., ql

C" steam-generator--levelt.23%

32% , 24%- t 6!/

Pressurizer level:.

88% 90% 93%-- 4 8 i:l c { Pressurizer: pressure: 1900 psig 1800-psig -1860fpsig;" f f I 41 1 f4 89%- ~92% "A" Eloop': reactor coolant flow: 87% t y "B" bloop reactor coolant flow:89% 91% ~93% ,3 4 .- (, g.f?"C" loop:. reactor. coolant flow:90% 92% '93% j er 3 o 4Whirb"onelof-the'following:. reactor trip signals'should have'been generated?j iti v.[ {a. ' Steam generator lo-lo level. 1 I We, b.- . Low pressurizerilevel fp ; l'

[

F 'y~~ l .a ' ic L Low pressurizer pressure m[y i "% d. RCS low flow i %+. m y u (. QUESTION: 031: (1.00) + Which'one.of.the following items correctly states =one of the bases for the ~ i j tripping the RCPsfin FOLDOUT "A"? t a s t t a. - . Minimizes.RCS; pressure at key;1ocations. i -b. Conservesicoolant inventory during a small? break LOCA. t [ ic. . Prevents? accident consequences from exceeding 10CFR100'criteriak 7 Ld.: -Reduces,overall plant electrical loads during.a signifibant plantI 4 event. 4 i. l L:L l. I (.[ j ;. l l ,i e ?? I-l. 1; l $o

1 g su 8 fLSdNI5RMEACTOROPERATOR; Paga 18 . r?+ 1 V I QUESTION: 032 (1.00). f . Which one of.the following' correctly describes the effects on plant ,fcp; rations should a LOSS OF DC BUS."A" occur. ] 4. Reactor' trip, generator lockout signal, 4KV Bus 4 and 5 deenergized,:feedwater isolation. ? - b. Turbine trip, backup:OCBs open, Auxiliary feedwater start, pressurizer PORV PCV-455C lost. c. Reactor trip, turbine-trip, generator OCBs: fail to' trip, L pressurizer PORV PCV-456 lost. d.. Reactor trip, generator lockout, feedwaterLisolation, auxiliary i feedwater start. -QUESTION: 033. (1.00) Which one of the following conditions will result in complete loss of Main-- Fcadwater? a. Loss of a condensate pump with.both main feedwater pumps running,

b. :

Any one" steam generator level reaches 75%'of level, c. Loss of=a condensate pump if only 1 condensate pump is running. d. Loss of a main feedwater pump if only one feedwater pump is running. 5

"~ ~ ,4 qp ' c t :#, . y- ;, ,$SdkIORhEACTOROPERATOR' P;g3'19: m t -QUESTION:-0341 (1.00), le 4Whichione of-the actions from'the' list below are immediate-actions of AOP-019, y i:CM31 function of RCS-Pressure-Control" for a HIGH RCS pressure?- l e 1.:IfLPORVs open,-verify they close when RCS pressure reduces to n% the closing-setpoint.- T, 19' '2. Verify pressurizer. spray valves open..

3. Initiate auxiliary spray.

4. Verify pressurizer heaters off.

g , 4. c.i 1,2,3 l er "1 b.- '1,~2, 4-l c., 1,'3, 4 g h d. "2,.3, 4 jfQUESTION: 035 (1.00) Which one of the following. states the TWO procedures'that lead to FRP-H.1, ,cLoss of Secondary Heat Sink"? f 5 a.! iPATH l and: PATH 2 ~ rL b; CSFST for heat. sink and PATH 1 F i c. PATH ~2 and CSFSTLfor heat sink 'd b ' PATH 2 and EP-11 n 4 1 JQUESTION: 036 (1. 00)~ !Which one of the following is.the basis-for terminating safety injection ? flow during the performance of PATH 2? i o S a. To minimize the cooldown affects caused by the tube rupture. 4 S b. Toiestablish normal charging and letdown for RCS chemistry colitrol. c. To prevent filling the pressurizer, thus lifting the pressuriter t-PORVs. d.' To prevent overfilling the ruptured steam generator. ~ u s i, { + +

y f 's ),516410R REACTORf 0PERATOR - ' Pag $"20] j P a O' QUESTION: O'37 l (1.00)[ l V.iWhich-onefof;the following'groupsLof parameters;are= entry conditions for! LAOP-016,'< Excessive Primary Plant: Leakage,.While at 100% power,t steady. state: c:nditions?- 9 . a '.

1. Increased;VCTimakeup frequency 2.wIncreased charging flow.

j 13." Letdown 11 solation-J '4.L;Steamtgenerator blowdown radiation monitor alarm ,9 Eb. '1. Containment' temperature-increasing l

2., Increased charging flow 3.' Decreasing pressurizer level >

I (4~.-Containment sump pump operation? g c. l'. Steamigenerator; blowdown isolation o c2. Letdown isolation ,3.LDecreasing pressurizer level u-4.EIncreased charging: flow 3 l d. '1.cContainment' temperature increasing-2.l Letdown isolation. i 13L:l Increasing-steam: flow- ~ 44;RCS(temperature decreasing: .I lA . QUESTION:7038,.(1;00) a LWhich'onefof the followingfactions will. occur as a result of a malfunctionTof;the' Reactor Make-up System control? a. JAutomatic make-up will be isolated if a flow-deviation condition exists for 45 seconds. "b.= LCV-115B. closes:and LCV-115C opens on LoN-Low level ( in the VCT. ,c. achargingLpump, speed will increase. 'd..>iLCV-115A opens to holdup tanks atL20.2".in'VCT.

f h

l t l T~x t L e-fi Y' d r , ;- n. ~ ; 1 m

YR fr, Q ^ ^ ^ y' 3; i M 'i % u-. t %,S8IqR[ REACTOR-OPERATOR- 'P gol21, '4 , g, s,'y q j y.7 ~, g',in-QUESTION ) 039: !K. ' 4 (1.00) ( $'.KcfLcn:automaticifunction if the' radiation'leve11 incr Which!one of1the following' Area Radiation;. Monitors results-in the'actuationL i a 20tpoint?' y a n e,3 j s E G.. "R-1,. Control Room Area-tin. [, R'-2, :. L i d Conta' nmenti Area ] i ' c.1

R-7, Incore Inst. Cubicle Area ~

~ { y. g+ d.E R-9, Letdown Line-h 4 'I. I h; ' iQUESTION: 040 ~(1.00) .V. ( p '. f. 3 .Tha following/ indications exist-in the control room: j INSTR AIR HDR PRESS LO alarm i .Pressurizerg levelLis.80%1and increasing ' l - VCTLlevel-is,.16% and, decreasing. f,

- Main-feedwater' regulating valves are closing y

h0 sWhIch one of the'following" summarizes the action required for this event r 'in accordance'with.AOP-017',, Loss of Instrument Air? .E

a.:

Trip-the reactor and fallow PATH 1. b.- . Manually divert.1'etdown to the VCT. 1 4 / -c.. Initiate; shutdown,per GP-006. . d.- -Manually make-up to thetVCT. aM x-o 3; QUESTION: E041 (1.00) r ~ ~ 'I

-Which oneiof the following items indicates er confirms that a' controlling:-

pressurizer _ level channel has: failed high? .j Ia. All pressurizer heaters are off. f -.All-pressurizer spray valves open. b. f c. Charging pump speed control is at minimum. s L ld.. Remaining pressurizer level channels begin to increase. o .t: 4 s' 2, 3

'}

m,;

t J-c 1 51:-.... ? =' , a ,SE!NIQR REACTOR Opr$idRL Pag 3 22 4 a 1 1 'i !iQUESTION: H04 2 ' L(1. 00)' Y -fWhich one'of,the.follo$ing correctly describes an INTERLOCK' associated with tho operat, ion'of the Fuel Transfer System? c ~ The1 Gripper Tube'must be " full'up" to energize the trolley drive. at To' raise:th'e'upender, the conve b;'fofotravel,theconveyor.carandlforcarmust-beattheextremeend fting frame must'be in line, and u the: transfer motor.must be on. 1 c. Thergate valve on the Containment Vessel side.of'the fuel = transfer-tube must-be fully:open before traverse of the car can begin.; a 1 d' The transfer car may:be moved only-if the permissive switch on the C Spent Fuel Pit' Side control-console is~in the permissive position. o QUESTION:.043 (1.00) Which one of the following sets of loads is started on BLACKOUT SEQUENCE 5 londing?' a. Safety Injection pumps ~A, B.and C.. 1 - b. HVHtUnits 1, 2, 3 and 4. ,~c. RHR pumps A and B.

d.

Service Water pumps A and C. QUESTION:1044 (1.00) ,Which' conditions or actions will actuate BOTH Motor Driven Auxiliary Faedwater Pumps? 3 . c. 'Anyltwo steam generators with one of three detectors at -Lo level'. b.~ Loss of power to the El Emergency Bus. L,

c..

Any-one steam generator with two of three detectors at Lo-Lo level. 1 d. Any two steam generators with two of three detectors at Lo level coincident with one main feedwater pump tripped. oo l L t j -l s 'w

i f

g. 3 1

l,gn;b ' i;-)y y o! 'it nA J,.- y. s .:g r p '*I av r-y; _ _iy .g ..,.,,r E l'l .f, eM-s %S IOR REACTOR $ OPERATOR 1 i1 l~ ' l ! ' I

'i

4 +

, ' g., ].. ; i t LP0g3;23i~ g w Wj/ *,tr. m i-y ;y R,, 1p ,; j -. 4 m. ,#h . }' ! N' i -p ',i .. ),i i.. h QUESTION:j045L (1200) f g ): ') .lm, t. 1 4 ~ ~ i 4 4 ' W Which one of the following signals!will-cause*only)ONE Main Feedwater! Pump 4 jW t3 trip. (AssumefapproprlateLlogics are satisfled., W7,A; 2. - TLowalubeloil, pressure.C mT. Q_< _ o gil b., lHigh steam generator: level.. .n z c. High:feedwater pump' discharge' pressure. 't %*r. .RCS pressure -c1715.psig.

(: h. i

-d.. t W ,1 f s 1 f 4.QUESTIONd1046' _ (1. 00) - l. o "f, ?c.Which:oneTof-the following-SprayjAdditive TankLconditiorm are required; j" f - before the reactor-could!beimade critical?-^ ' _a. '2550 gallons (of 30%;byJweight of~ sodium hydroxide. y_ Jb. .2'450 gallonsL 'of'l 33_% by weight of L sodium. hydroxide.: =i i:f '2550-~ gallons of,27%dby1weightLof' sodium-hydroxide._. 'c.. d.' 2400 gallons of;25% b'y weight of sodium hydroxide. p 1! o. P. i ..,f 3 g [ i s' L - s e i' c t,-< ,) r l-e. 1 I o p

t., o-

.t Q j <! p 7 1 ~ l l 4 e 4 e = w w

w ^^ ^ uq., g-L n._ 3, p 9 t + i ((-:h hh3[ L ?d 'e MSI!hIlOR-REACTOR. OPERATOR Pigs 24

j g

o 4, wy c h:- g y s fQUESTION:l047l-l(2.00) 0 t p ; MATCH each of the automa' tic. actions listied in Column ALwith its ass'ociated-f j3;VCT=levelcsetpoint listed in Column B..(Items listed'in Column B may be i n eu Cd more than;once.:or not.at'all.)- 1 m' Column B-. ) e-Column'Ai ,w, _- E a.4 LCV-115A- (Diversion ' Valve)-; FULL OPEN-. to HUT.- fl.L.5.2" -1 ;-. i ~ t r <b.' Automatic Makeup starts 12. 7.3"- 4 og j m-c.' Emergency LOW-LOWIlevel' 3. : 12. 4 "- q 7 ld. ;LCV-115A.'(Diversion-Valve) returned'to-VCT ! 4. 116. 6"- 1 t s y . 5.= 20.2" l!y ,6..24.4" 4 '7. 45.6"E 8. 51.6" L 9. 62.7"- O L;

QUESTION: [048 (l'. 0 0)

J y o l' Th2 Liquid Radwaste' Evaporator-Feed Pump will AUTOMATICALLY cut-off on 9% i .lsval'in;the1 Waste-Holdup Tank and onL..... (Choose ONE)- l-ze M 1 a.. liquid-Waste; Disposal System effluents Radiation Monitor HIGH i p.i; alarm.1 l"k. 1 H

b.;

low pump discharge pressure. l a c;:

high' evaporator'shell pressure.

l; l d. : Clow evaporator c'ooling water flow. \\'> ,i , -( s ;o i l 't l 'l i 1 ;, 1 l s F/t l i l l. l 1 l c

et, - . l 3 m v: en 1 ,SENI(R REACTOR OPERATOR;

Pago : 25' y

-QUESTION:.049' (1;00). Which one of the following correctly! delineates the power supply from the yc_480VAC bus to the7 rod: control power cabinets? S. Reactor Trip" Breakers to MotorfGenerators to Generator Breakers: 1 "b.. Generator Breakers'to Motor' Generators to Reactor TripJBreakers

c. :

-Motor Generators to Generator Breakers to Reactor Trip Breakers' d.- ' Motor Breakers to Reactor: Trip Breakers to Motor Generators + x r QUESTION:.050 L(1.00) Tho power level input tx) the ROD BANKS A/B/C/D EXTRA LO LIMIT alarm is 'dsrived from: ma. auctioneered median Tave f .b. Tref-c.. N-44 nuclear power level l d. auctioneered' median delta-t t -QUESTION: 051 (1. 0 0). 1, l, .All' Reactor Coolant Pumps must be stopped after-a phase "B"' containment oicolation because: - a. CC-730 closes resulting in a loss of cooling water to RCP motor bearing. coolers. 1 b. instrument sensing lines for seal water flow transmitters isolate d resulting in loss of indication. t c. seal-water return CVC-381 closes resulting in loss'of cooling to all the RCP seal-packages. 'd. SW-34A,-34B, 34C, and'34D close and isolate cooling water to'the containment air recirculation. coolers resulting in-RCP motor E winding high temperature. t 3 4

Qf T ~ ~ ~ wi. m -V ;plMI(RIREACTOR[ OPERATOR

i '..

1 -[zm S Pago 26-n [O@u + j ' 't as, t "r -- QUESTION:-052l (1.00)1 o a:;w JWith' reactor power?in-the" intermediate' range'if one:(1)fIntermediate Range ( '%-NuclearzInstrument1(IRNI) is OVERCOMPENSATED,'the indicated 11RNI power j{R'lnge: Nuclear Instruments lcvelswill be (1)- than thecactual' power' level. =The1 Source ^1 (2) automatically. energize when ?!Ltho.. lowest-reading IRNI reaches its setpoint'during_a= reactor shutdown- -!i; = j .l.Which?one-~of the'following correctly completesLthe above' sentence 7 a% i h ~ 'a; (1) flower,'(2):will p'niv n Uj b. (1) lower, (2) will-not }il;l: n ff c.- (1)fhigher, (2)Lwill o (p : ' d h- -(1)' higher, (2) will not 4(j; W: NkQUESTION: 053- (2.00)- [M. MATCH lthe'following rod bank and mode of operation in' COLUMN A-with the: correctyrod' speeds:in COLUMN B. Column A_ . Column B h.hi '

a. Manually' WITHDRAWING control

= 1 '. 8 spm E 4 bank "B" H 2. 24-spm-6 _b.; Automatic INSERTION with-Tave greater than_ Tref by12-degrees' 3. 40,spm ? c.? Automatic-INSERTION lwith.Tave' greater 4. 45 spm than-Tref by-4 degrees 5. 68'spm Y d.I utomatic INSERTION with Tave grea.ter A f than1 Tref:by 6 degrees

6. 72 spm

.1 c l-ia i ,;m 7 I' I, .I:c i I it-I y p. l: f) + J [ -th i.- L a

lv- ~ X 7r -' '. -~n1~. a x w w l'L. g' Jf .o q x u, ( y Yb ' hy _ h p y,7 6: lPagT 27k

4 W,88'NOR[ REACTOR!O[kERATOR

~' 3 ( l.. -

g I

h; ph),.p 9.c-vi i I - ?5 ,g' x. i ,' j i m ~; j..,,,. i n 1 1 ~, i ,r n.< ,i .- p e. F : QUESTION: F054j ;(1.00): Y" c 1 lk..Which onel off thel following iisithe) purpose : of j the P ead band)in - the rod: speed : l d ,,4 program?. g 4 a, h, //

a..

' i 1Elim' nate bistabli chattiering n M ,, ' < b.'- Eliminate continuous:rodistepping, a _3, a e, + a 'n M. fc b-I Eliminate Tave' errors' 7, _ ' d. ; . Eliminate over-responset y q - ~ [d. s )I mlw 4. 7 L.3 ,k y y o. * % QUESTION (055;.(1.00) i)! j as o. ad ..J { What is the. reason' for ' LIMITING-the number. of RCP starts 'in ~ a given. period?- , i.

4

. a r-fMinimizeipitting.offstarter' contacts'.. o.

b.3 Prevents excessive torsional stresses lon the motor' shaft.

es . :, a. . ms , V'c. . Prevents? overheating:ofxthe motor'. windings. s id @ Minim'izes axial ~-wearLonithe' seal. package, m 4 _g ti 1' # i ,y ci- -QUESTION:[056 (1.00): l 'r.A 1WhichLone offthe followingiconditions.will= result in STEAM LINE' ISOLATION?_-- - d i m.1 yy ~ h M i ?a c 3 iHigh steam lineLflow. .n af b) i Manual = containment spray. signal'. H w p I[ c [ Automatic con'thihment' spray signal. g t v,. ,,'e l d.. H, H i g h.zsteam generator level, m, o. e.7 i .. I .,s ,,p [.P (,, N, O i I-i k ' hI ;': 3 m 4 lf k,, :d y, .t [ '-!s. pk ", ", gg " ci $Q ; ' .:> ^ ' ' gap y,o.. pW i.; ; .r a E 3.z E',, t i.<- u h *...i.' '4 t 11 ;te i', ! 'f l, 3 : i} m o llx_, ' d ' Dl1.5 :, l b. s L u u w' < w,. .i

.aj J4] k. h Y ?~ T d.[( l f T l j 'MNNIOR[ REACTOR: OPERATOR! Pag 3 28/ . m' i - G 4 u p: ~g h i 4 rd '; ly ti 2 -/ i!, j; - j i-3 3

u..

iQUESTION: LO57- - (1. 00 ):- (Whichhonelof the following. statements is;the: highest temperature-the-incore-. ,thermoco,uples'can indicate?? ( St ai; J530 deg:F-1 pl g. '1650'deg,F b ' N ci rl 2300 deg. F ~ j' 'a 'd k-l3000'deg:F ~ + Q). t ai '

fNUESTION

i058 (1. 00);

'Which one of the following? conditions will= result-_if DC bus "B"'is lost e f,land;off-site power is stillLavailable? pj ~ a. r. [A:j ' 4"B" main feedwaterypump' trips. i .y .b. "B" EDG starts,)theifie, flashes and the output breaker'close's. R a;11; ' j p !:'. - j (f p c.- "B" train Safety; Injection Actuation. I sd. - "B"'AFW pump startsiand feeds B steam generator only. w QUESTION: 059- (1. 00') ^ YLWhichfone of-the following. signals will activate a containment isolation. Si -phase "B"? s a. -- 'l set'-J22of 3. Containment.High Pressure.- ~ bi <2: sets "2:of 3 Containment High Pressure. ~ c. 1' set - 2 of^3 Containment High-High Pressure, j d. 2 sets- ,2'of 3' Containment High-High Pressure. 1 -l '!i.. M ~ 1 4 .z e .i.

dil"iYN?C n-l[ [h n$pyn0hb" n m p t %S IdR,. REACTOR OPERATOR -PIgsi29. ?

q q @m ; m >

l r i ,, n n L KQUESTION:1060' (1.00); .)

~ '& ;p r P

f Tichnical Specifications' state'thatfwith the Quadrant' Power Tilt Rati'o~ s 4 J gr::aterothan-1.02 but-less than 1.09, the.o j reduceiQPTR-to within its limits or reduce perator must, within two hours,. thermal power > The two hour. time; allowance for operation with-a-tilt condition 1 greater ~than.1.02 but j .lcIshthanl1.09:is provided'to. allow time for:. i:L corrective action 1:i the' event' of 'xe' on redistribution following'- I '., _ ' (r.m ' power-changes. a. n S '4 1 P4.f4(b.- identification andicorrection of a dropped or misaligned' rod.' ] we 1 L' M lc.- boron concentration changes to restore.the QPTR to less than.1.02. l;D li. Lidentification"and correction of a failed-excore detector. 2 -l yQUESTION:1061 (1.00)- j t

If. pressurizer level transmitter.LT-459 is selected.for control when'the.

j 'l f.1s reference. leg.for LT-459 develops a slow. leak,'which'of the:following' Y s'dsscribes initial-instrument'or plant response? 'LI-459 LI-460 PZR LVL INDICATION PZR LVL INDICATION

VCT LEVEL

,1

a.

INCREASES DECREASES -INCREASES 1 ~ b. DECREASES INCREASES INCREASES-c. INCREASES DECREASES' DECREASES: .d~ . DECREASES. INCREASES DECREASES' a i i , QUESTION:: 062' (1.00) ~ Hydrogen Recombiners must be activated when hydrogen' concentration inside-p

containment ~ reaches:

l p 1a. 2.5%. p i b.' 3.0%. L c.- j3.5%. 1 o I d.- 4.0%. H u 1 ,h-w;.

m -7 lm' . _ 'llli t i,-_ n f>,SN,IdRfREACTOR PERATOR' . Ptg:a 3 0 --- 9 fi:. e, .s i I. (> 4 (QUESTIONt 063;,(1.00); iA:Gume"steadyt state:o W1transmitterPT-444ifa$erationat.100% power.:jThe_PressurizerPressure'. 1s to 2370;psig. -Assume a. step change and; assume Ethat pressurizer pressure control 1: is-in automatic. i 1Th3Limmediate'autom'aticl responses of the=systemcwill;be: ~ t

>4 9.

J-a! power operated relief valve PCV-455C^' opens,= spray, valves-open,. ^ pressurizer variable heaters;de,-energize.; 4 (b.: spray. valves open, all(. pressurizer heaters 1 energize. 1 c c.; spraycvalvesuclose, pressurizer variable and: backup: heaters, energize.? -d. power' operated relief'valveT PCV-455C and PCV-456-open, spray. valves open,,all pressurizer heaters de-energize.- q o j QUESTION: 064I .'-(1.00)

7. l Which one ofcthe:following signals will trip theLEmergency Diesel Generator.

q AFTER:an; EMERGENCY START?

i

, a '. High,crEnkcase pressure. Low = lobe oil pressure. b. y c.- Engine overspeed. -j N Ld. . High jacket water temperature.- u i i 7j idUESTION: 065 (1.00) l i Whichlone of the following fuel handling tools is pneumatically operated? i Ea.- Guide, Tube Cover Handling Tool l. 'b. Control Rod Drive Shaft: Unlatching Tool d c. . Thimble Plug Handling Tool 1 o d. Irradiation' Sample 6andling Tool a. s s i l l

ww, 1; a < ;Q % i ~ ylt

Lt:;.g

? y Qlc.w_ s y; a u e a j g W..ujg e u 1 4 n JNSENIO.RtREACTOR' OPERATOR 4 PagW.311 s. w. ( f( M a ${ } -q; 3 j '7! O c g4 ht -[- ) j @; QUESTION:10663L(1.00)! ' l& C r, 'il 1 > & Which oneiof:thelfollowing ^ conditions'or events.will resultfin,a: DECREASE; D4!4nitheiOverpoweriDelta-T setpoint?' M%, ;P ; y q a.I iPressurizerl Spray Valve sticks'open for 154 seconds 1(assume no'- 4 . O $!MB, reactor; trip).; 3 w,y ..~ C '1 .\\ g e J x-lb' u "A:poweriascension-from<75%1.to 100% power.- m ph$$c.) Afreac. tor coolant'boration is[ initiated at 50% power.- J A ] nk ,9 M

idh

. Delta flux;at 100% power" increases from'+10'to +13. l

4. !.7.

v J g. o, eq j f, i I i.'. i hESTION:7067- :( 2 '. O d ) ' m;,. ,..s <ts ' !1 x tMATCH theJreactorltrip in Column A with the correct associated' protection 1 1 N/M it:isLdesigned to provide listed:in! Column B.-;(Items in Column B may be-Ql1.,un d moretthan once or not atiall.) 2 1 4 ' K COLUMN-AJ COLUMN B-l a; jn 1 i faR 7 ' Overpower l Delta-T~ 11.~ Power Excursion From. Low-- ~ Power W. i i - x F,<

. b. -

- Overtemperature Delta-T "2.-Rapid Reactivity-T ' Excursion 4 MH c. ' Intermediate Range High Flux 3. Exceeding Linear Power' $;W' s e . Rating n (KW/ f t) ' .t.h d '. Power Range High Flux -~High 4'. Excessive Void Formation g + 5..Startup Acclaent: k

6. De arture From Nucleate-Bo ling

.i g4 1 i

9) J s"

( 5 Ml: w ~ ' <; } y i t F.; ;. 5. f I l g '\\ i ?).90.m I i ??.W.

f ,T 'i + "l %:uj gn W- ~ -N,,,, ,Q y^ :.. a: .g g. G V ;.. ~ g, SENIOR REACTOR'OPERATORJ 1 Pag 3x 32::- ~,m ,m ~ seg i m .mb- ' jfl

Y' s

y;-

,1 71 7 UESTION:10681 (1.00).

Q l> [ s JWhich one of;the following:will'cause the "A"' steam'generatorn(S/G):maini'0 J x :fctdwater regulating., valve;to initially go to the OPEN position?, Assume no: ? cp;rator. action taken;. W, .h <S/G: narrow range 11evel transmitter fails HIGH. H L.

3. s.

A , b. : S/G faddwater flow; transmitter fails-HIGH. , s f

c.;,.S/G steam flowLtransmitter fails'HIGH.

[

1

'dk S/G pressure trans'mitter: fails LOW.. 3g 1 { QUESTION:1069' (1.00) o s.. describes-a: design feature f[Whichoneof..the'following" statements' correctly? of:the-Halon. System,in:the cable spreading room .a. There are two1means of manual release.- =! h a i Eb' ALventilation' period immediately follows.the Halon trip. i 4 OnlyLone train ' c '. - " actuate the. sign (A or B) has to. sense a fire hazard condition'to- ,Yg al. - h Id.. cSixty'(60)' seconds is allowed for activating the " ABORT" feature.. j y .m "h . QUESTION: 2070; (l'. 00) ~ 4

ThfRCS! wide range T-hot' instrument signal'is used as Lan input ~ to:

4 'a. Jcalculated' loop Tave. b.. -; core (subcooling monitor. .c c a l c u l a t e d :- l'o o p.D e l t a - T. t!

c. :

'd.. rod control system.: ,a L 9; .s. I i (

~~ ~ x.a e ..T 3 .-r,h.; 1

~

s c i

v;F

'% e. L.JENIOR:. REACTOR (OPERATOR' Ptg M33: 1 J.- f3 n y i, ; 'l 1 Jj , f " $ TION:7071 $(1.00) 0i 2 1~kg;N... ~,. $/Thiplant'isLoperating1at: 60%? power when:theiloop 3. Delta-T.: indication'- i $ # fails.LOWiand-loop'3.Tave" indication fails HIGH..The most probableLcause. J ,1 J for.theseLindications.is that:. loop 3. e r O-L !T-h'ot failed high., y A. ? 4 b. IT-hot L f ailed ;1ow. 1' H c.1.:T-coldTfailed1high. e 7, e-M d.. LT-cold failed low. i t ,[ QUESTION:-. 072. (1. 00) - a .x j Whtn synchronizing the generator!to the grid,/GP-005," POWER OPERATION", "Edirects the operator to adjust turbine speed until.the synchroscope is rotctingislowly in thecfast direction'. The two parameter indications providedLby the synchroscope are difference'and. difference; p :(colect'.ONE)- a h c.. icurrent; voltage .{. ' b. : frequency; current . c '. . frequency;. phase f d '.~. l current;. phase, y

x j

t. QOESTION: 7 073. - (l'. 00)- , I

Which one: of.the:following correctly lists the loads supplied'by the,4160 d

'VACLBusL1?: m 1 a l0.[ 1 Circulating: Water. Pump C, pts and Fan Equipment, Reactor Coolant. O Pump-A. t nbF pts-and Fan Equipmet,-Station' Service-! Transformer'2B, Heater Drain M,, '. Pump"A.

c..

.S/GLFeedwater Pump A, PTe and Fan' Equipment, Station Service y . Transformer =2A. ,c: 4,; g 'dO pts and Control Power Transformer, Station Service Transformer 2D, A Condensate Pump A.

v N

L ~ y t i l m 1 a,-

w \\ :' 1 UNiNIO,R$3tEACTOR ' OPERATOR: Paga 34 I

"QU

^ i g'< /P

fQdESTION: 074..(1.00) u

n I

[Which oneiof the following correctly lists those items / components-located

v{in/onithe-"A"mainsteam.linebetweentheS/GandtheMSIV?.

l= fa. Supply to steam seals, taps for pressureninstrumentation, four main steam: safety-valves, flow nozzle. b[ Four main' steam safety valves, supply to" steam. driven AFW pump, V i flow nozzle,:one power operated relief valve. l y' Supply.to steam driven-AFW pump, one mainisteam?safet evalve, taps c. four: power operated rel ef valves.- a fpr pressure instrumentation, l id. ' Flow nozzle, point for secondary sampling' system',; supply to steam d V, seals,.three power operated relief. valves. ' QUESTION: 075 (1.00)' .Th:t and'the. can be used to maintain the: required water .lcv31 in the Spent Fuel Pit in the event of a leaking Spent Fuel Pit Cooling System. (select ONE). L a.. VCT; Charging Pump b.- Boric Acid-Tank; Boric Acid Transfer Pump c.- RWST; Refueling Uater Purification Pump 'd.- Primary Water Storage Tank; Primary; Water Pump j j IQUESTION: 1076 (1. 00). >Which one of the following trips is interlocked with P.7 permissive? l a. Source Range Reactor Trip b. ' Pressurizer High Pressure Trip ic. Single Loop Low. Coolant Flow Trip '1 d. Two Loop Low Cociant Flow Trip =l 5 J

~ ,c m g.. ~. .d E, M;?i s + q.. ;n~

=

3. yt ..'N .. i

l 4-

/ p,- +. ; l. .j 4 W' ....,.5-sn.

. SENIOR REACTOR! OPERATORL

< P2g 3 3 5 -: ) .. + a. ! ' f. j[f [4 - ^ g' : y' j 5 ' i j -, ) w J,( + l QUESTION: E 077j, (1.' 00) m Whibh one ofdtheLfollowingLisia purpose"of1the interlocks' associated,with th'e. J lRHR-l loop isolation" valves'(RHR-750.andf751)?,' . w

a.

1.Ensuresloverflow to theIRWST. l ' k Prevents 1 draining of the.RCS. c d * r.c.b f PreventsJ overpressurizat'ioni of RHR. system.- h Nf fdL Ensures adequate NPSHifor,the'RHR pumps. >n ., ) ; 1 .u.,

K.

1 , QUESTION: 078: l(1. 00)l ,c - r:s ..S Ths CCWcSystem:hasideveloped a' leak with CCW pump:"A" running.-The automatic ~ Lactionithat occurs;when theLCCW pump."A" discharge pressure-decreases.to178 P319 -. is.: J 4 ' L a '. 'autiomatic makeup initiates' to' the Surge Tank.. p y -b.. CCW.to the RHR Heat Exchangers is51ates. ~~ r Lc. 'the! standby.CCW pumps "B" and:"C" start.. d.: 'FCV-626, CCW return from RCP Thermal Barriers-closes. n - cQUESTIONi1079s (1. 00 )., 9 ?Whibh onelof the following statements correctly describes one; feature of the.

PRT?:

a..

LThe:PRT'has!a' low level alarm'at'50%. V .b." TThe.CCW: relief' valves discharge to the PRT. ""_ w ,+ i Jc. 'The:PRTlhas a vacuum breaker.to preventLcollapse. [ r e 'Ud. : ~ Thel PRT relieves excess tank pressure:directly to cont'ainment. ,1 ), l, ';U s p. .i 1f n-y ~ 4 t f 'y } < j :'

,S$NIO NEACTOROPERATOR; Pega 36 ~ QUESTION:: 080'.(1.00)

Which one of: the following' items correctly states one'of'the' design purposes; c; ct:the' condenser! steam dumps?

((' a.' Ensure core-cooling following a main steamline isolation. ~ b. ' Provide ' pressure' re13 ef ' fori the steam generators. i o -Limitatmosphe'ric release duringia; load rejection. -c. d. Reduce the condensate subcooling in the condenser. t s .i 1 QUESTION:'081 _ (1. 00) - = Th3' MINIMUM manning requirements _for REFUELING operations (during fuel movement) includes: t i 0. Shift Foreman (SRO),. Refueling SCO (SRO), one Control. Room Operator (RO);and Reactivity Monitor / 1/M Plotter. .b. . Shift Foreman,(SRO), Refueling SCO (SRO), STA and' Reactivity Monitor / 1/M: Plotter. i c. Refueling SCO.(SRO)~, STA, Fire Protection Technical Aide and Reactivity Monitor / 1/M Plotter. d. Shift Foreman'(SRO),Jone additional SRO,,two Control Room . Operators (RO) and STA. i 1 QUESTION: 082 (1.00)' } .Which one ofLthe-following correctly states the MAXIMUM permissible work N routine for: a licensed operator on shift? ' i' o; Less than or equaleto-16 hours straight not including turnover, b. More than or equal to 12 hours off between 12-hour shifts. c. Less than or equal to 94 hours per 7 days. -d. No more than 14 consecutive days without 7 consecutive days off. I' I' l.

W 8.;, S$NIO,R,itEACTOR OPERATOR peg 3'.37- + 1 .I'" V QUESTION: 083-.(1.00) i Which"one of.the' following pair of redundantiinstruments.contains at: ils st"one instrument'that is considered to be out of tolerance? y ~JL1700,- 2300 psig instrument reads 2000 psig with a'similar-a. -redundant instrument reading 2020 psig. b. A 0"- 80%-level instrument. reads ~22% with.a similar redundant d -instrument reading 19%. c; !A 0'- 1400 psig instrument reads 1100-psig with.a similar < redundant instrument reading 1045 psig d.. A'O - 4 X 10E6 lbs/hr instrument reads 2.5 X-10E6 witu a'similar iredundant instrument reads 2.7 X 10E6. ,JQUESTION:f084-(1.00). =Which"one of thesfollowing-systems'does NOT r re an Operational' Work ! Procedure prior to conducting maintenancg

A'xiliary Feedwater.

u a. ? bl Main Steam. c. ,Se Water. Control' Room Ventilation. $ $ QUESTION: 085 (1.00) M:5 Which one of the following is an action required by the Shift Foreman in ~the Control Room in the event of a-fire in the plant? { a. Lact as Team Leader for the Fire Brigade. Lb. Act as'a member of the Fire Brigade. m c. Ensure five shift members are assigned to the Fire' Brigade. ?/ d.~ - Ensure members of the' Fire Brigade are properly equipped. I! , ' ' hi _g. ~ l

{!

L

O AblIO,R REACTOR OPERATOR P2g3 3B QUESTION: 086 (1.00) Which one of the following statements is correct concerning a secondary chemistry parameter which exceeds its Action Level 1 specification with 'the unit on line at 60% power? a. Return the parameter to within its normal value within one week of initiating AL-1 or initiate AL-2 fc. those parameters having AL-2 values b. Initiate a power reduction to less than 30% within 12 hours of li initiating AL-1. Return the parameter to its normal value within it 100 hours of initiating AL-1 or initiate AL-2 for those parameters having AL-2 values. -c. Shutdown to the appropriate temperature within 12 hours of initiating AL-1 and correct the condition and establish the start-up values prior to reactor startup. d. Continue power operation. Action Level 1 does not apply until greater than 70% power. QUESTION: 087 (1.00) Steps preceded by a bullet (*) in the EOP network indicate which ONE of the following?- } a. The steps must be performed in the order listed. I b. The steps must be performed simultaneously. c. The steps should be performed only if directed by the Shift Foreman. d. The steps may be performed in any order. 4

m a-o. j ?!E D L. ]. ABNIO,R REACTOR CPERATOR P0g3 39 lh.<

h Y y

QUESTION: 088 (1.00) Y n an EMERGENCY situation where it is necessary to' enter a High I ' R diation Area for repair efforts the whole-body. dose should be limited- \\tos a. 15 REM b. 25 REM c. .75 REM d. 100 REN H LQUESTION: 089 (1.00) - I,;A 25 year old. licensed. reactor operator has the following exposure hictory c'i Lifetime whole body dose - 34 REM Ourrent quarterly whole body dose - 400 MREM A30uming his exposure is properly documented, what is the maximum additional whole body exposure this operator can receive this quarter. ond still comply with 10 cFR.207 a. 600. MREM bi 850 MREM [ c. 1600 MREM d. 18a5 MREM .o A b r' i .L r 1 _2.___m___ _ _. _ _. _ _ _ _ _ _ _. _..

$$lNIO,R iLEACTOR OPERATOR P g3 40 I ,o S? QUESTION 090 (1.00} Which one of the following combinations states the dose rate limits llin mREN per hour) above which-the associated area must be posted as a HLgh Radiation Area or a Locked High Radiation A~9a? i High Radiation Area L,ked High Radiation Area a. 10 1000 b. 10 10,000 c. 100-1000 d. 100 10,000 i QUESTION: 091- (1.00) Which one of the following is issued by the Shift Foreman? l a. Station Clearance b. Line Clearance [, c. Local Clearance { ~d. Caution Clearance QUESTION: 092 (1.00) Which one of the following statements concerning the use of CAUTION tags is correct? a. They can be used in the place of a Clearance. b. They.are used for system hydrostatic tests. c. They will be issued for OWPs. d. They can be used to isclate a component for maintenance.. 1 i

[SEi!O,R'NEACTORCPERATOR P g3 41 i ) i i ~ ~ Q'UESTION: 093- (1.00) l When directed by an.EOP, a-foldout page should be opened. These foldouts contain action steps that must be performed. With the foldout in use, at .whkt point should these actions be taken? t

a..

When the foldout page is first opened. b. When the symptoms associated with that foldout are noticed. .c. When a stable plant condition is reached. d.- When the SRO feels that the change in. plant status will have no adverse effects on the recovery efforts. l t I QUESTION: 094 (1.00) Wh3t is the lowest level of declaration requiring the Technical Support C:nter to be activated?- a. An Unusual Event l b. An Alert c. A Site Emergency [ m 'd. A General Emergency [ P QUESTION: 095 -(1.00) Which one of the following Site Emergency Coordinator Responsibilities .cnn be delegated to qualified personnel? Implementing"those Plant Emergency Procedures.necessary to I a. support emergency repair. b. Making the decision to notify off-site authorities. c. Recommending protective actions to authorities responsible for c_f-site emergency measures, i d.. Reclassifying the emergency. L 1-l: I

g. )$NIOR' REACTOR CPERATOR P g3 42 QUESTION:-096 (1.00) j 'Which one of the following sets of parameters lists the applicable Technical Specification limits for Reactor Coolant System chemistry and activity?- t Iodine Activity Chloride Concentration Oxygen Concentration i (uci/gm) (ppm) (ppm) t a.. 0.1 0.15 0.1 l b.- 0.1 1.5 1.0 c. 1.0 0.15 0.1 d; 1.0 1.5 1.0 J -i QUESTION: 097 (1.00) PATH 1 directs the operator to, " Verify two SI pumps' running". When used l 3.in the previous example, the term " VERIFY" means: i a. To erform a physical action which determines.the-status of-equ pment'and direct / perform a change in status if found out of. des red position. b. To observe an expected condition or characteristic; to determine;- to ascertain. c. To. watch or monitor; to visually take note of; to pay attention to. d. To attend to displays to determine equipment operating conditions 4 h I (********** END OF EXAMINATION **********)

pbI0R'NEACTOR' OPERATOR P;ge '1-1 A N S.W E'R 'EY a lT ritt -n ,_001' 'c-002 d- '.003 b 004 c 7 005-b e r o. =006. 'd 007' c: 008. b

i. 009 c

a ,010-

c 011:

a 012-c a: 013 b. .014 c .[015 b 016 a ..017-a' 4

018"

.d i 019 d 020'

b 021' a

022' c-- q 023; b t i 024 c 1 025 a: J, mL

i i

. SE3fIO,R REACTOR OPERATOR-

r. -

'P g)' 2 -l .1 ANS-WER KEY

\\

l (! l 026 ,a i 027 c i 028. c i 029 c 1030 d- .031 b J 032 d 1 -033 b q 034-b i 1

4..

035 b ( ) 036 d 037 b 038 a 039 a .j . 040' a P 041 c 042 a 043 d l 044 c t .045 a-l046'.

a I

i 047,' match with selected number in the blank l, a 8 b 5 c 3 I i 1, ' ?

a i, ec ' 'e .SENIO,R RFACTOR ' OPERATOR ~ PCg3 '3 l 'A N S'W E R' K E Y' E 1 d-7 '048 b '049-c 050 d. .051 a 052 g h-053' match with selected number in the blank a 4 b 1 c 3-d. 6 054 b .055 c '056

c 057.-

c -- ,"058 a 059 d 060 b' 061 a 062. d 063-a 064' c' I 065 b. 066: d 067 match with selected ~1mber in the blank l

e- - t s o p: p o - m-AENIO.R REACTOR OPERATOR P;g3 4. ,i, A N S W T. R KEY ,a. o l'. t F a 3 b 6 e c 5 l d 2 l -4 068 c l-L 069' a r s 070' b

1

,-L 071 c 072 c r ? ,1 i i - 073 b 4 i s 074 b' L 075 'c 076 d 077 'c 078 c' = 079 d l 080-c '081 a 082 b. 083 d t ( -',000 'u 085 c-086 a 087 d t 088 'b ? l i y

Yi; l'.! ;g,r. ; w o 3;g r.m " ~ n F -f j; ' .f q-t Dhhi[htEACTOR OPERATOR-L -P ge 5 I

-..r 6,7lrp

~p .o r A N S W>E R X E~ Y ' E .n ,,,i,y, i ,. J [; h: 1 t 1 s. ~. i,E r\\. I r I a' f' 5 f V 089: -a 090-c -1. ; i.'. !! j o91 l -c 'i l092' 'b n h '093 b i k I, ., b,. l-;v. - 09 4 I, 095 g .a, i, 096' Lc- ,:097 a P m). ,I e l h', g i l!i 5 -4 2 i, - ,;f(. g . c. r e. I e 1 l (********** END OF EXAMINATION **********)' l. i 11 5 r + 4 f, i I j ' )' -f U.') j iv ' 3,. i l

, p:

1 p 3 p C y ,~ n -,m a

,ks_In' -.. n >L m c LCi l ',.,, g t. o 1, g? ' - P 93 43 l 4 y .SENIC)R: REACTOR OPERATOR ~ um t-21 .y, i ANSWER. 001-l (1.00) _i iJ i ' 0 4...

REFERENCE:

i L' r AOP-001, Rev. O, p.,12-l .RDCNT-TP-3.1,.LO 4-r.[

000001A205

..(KA's) i V y, ANSWER:, 002 -(1.00) u t &+ d.!

REFERENCE:

o A7P-001, Rev. 3, p. 15

{

q000003K304 ..(KA's)

1 t

'l ' ~ ANSWER 1 003; (1.00) b.i 3

REFERENCE:

l ! FOLDOUT,B, Rev. 6, P. 5 'LO"- Not Available 7 000011K312 ...(KA's) tt t ANSWER: 004 (1.00)- 'C,.. 'i ;

REFERENCE:

ca ' ,JAOP-018, Rev. 1, p.'14 4 LO - Not Available o ', l ' 000015A208 ..(KA's) i uANSWERt. 005 (1.00) ) i l Y' ic L-1 I i. l 1 al j y .~

onq7+ i i + . io 3 6 ' e. l - l AENIqR REACTOR-CPERATOR ' P;g3 44 i H q',~ i s ^ 1

REFERENCE:

1 fl i R 1AOP-018i Rev. 1, p.113 ', ' JLO - Not Available i '000015A122- ..(KA's) s ANSWER: 006 (1.00) [h a d.' ) i

REFERENCES:

l ' AOP-002, Rev. 2,.p. 4 l 000024K104 ..(KA's) j L i

ANSWER',L 007 (1.00)-

O.. ',REFERENCEt AOP-014, Rev. O

p. 4 & 5

'LO - Not Available-000026K303 ..(KA's) .i ANSWERt. 008 (1.00). f + 1 b. S = REF' AENCE: t Rev. 3, p. 3 & 4 ' AOP-012, i 5 'LO-Not-Available ,000051G010 ..(KA's): 4 i ANSWERt.- 009 (1.00) ~ c.. a 1 i 1 + l t t I' ?~ l 5 1 4-s 4

w--

r - - ~

wa, ygyg. + !3,. ' hl b ( i 65 ,n y}M AEIC:qR REACTOR CPERATOR 'P ge 451 t -. p mf } ' fl pl}% 1 , \\ ' O REFEPENCE:. j ,'p. ^ t Technical Specifications 1.7 and 3;6.1 Lig'.LO'-'Not Avadlable i t i 0,00069G003 '..(KA's) 1 ANSWER: 010 (1.00) e - 0.- ?

REFERENCE:

- t

EOP-LP-16, p. 7 L EOP-LP-16,..:4 A. 3 1.

r ..000074K311 ..(KA's) y .t pjANSWER:' 011- (1.00) .1. t O.

REFERENCE:

f I h-1: AOP-001, Rev. 3, p. 5 l LO - Not Available '000005G005 -..(KA's) . i ' ANSWER:. '012 (1.00) c.. 'l

REFERENCE:

ELEC-LP-28,'p. 8 ) 4 - ELEC-LP-28, LO?A.1 000057A215- ..(KA's). [

ANSWER

0131 -(1.00) Y-. b.. 6 1 A. _. ' .g 'l. J ( ..q ; lji: n 4r t 'L'. !< -i l

u-, 'I. 4 I'?ANIIqRhtEACTOROPERNTOR l l P g3:46

REFERENCE:

ELEC-LP-27, p. 3 ELEC-LP-27, LO A.2 000055A204- ..(KA's). (1.00f ' ANSWER 014 .c.' REFERENCE - DSP-001, Rev. 2,-;p. 3 LO - Not Available.. 000067K304 ...(KA's) ANSWER: 015 "(1.00)' b.

REFERENCE:

EPP-1~, Rev. 6',cp. 10L EOP-LP-5,--LO A.1' 000055A203 ..(KA's) ANSWERt 016 (1.00) c.

REFERENCE:

AOP-012, Rev.'3, p. 3-- 000051A202 ..(KA's) . ANSWER:- 017 (1.00) I 'c.- i e.,,,- w w.---

w-1: 1 y [4 '..,'. h. -' ~' #ENIOR REACTOR CPERATOR P;g3 47 NEFERENCE: i ' - M.E0P-LP-15,.p. 3 . BOP-LP-15, M A.2 000029K312 ...(KA's) i: 3 -ANSWER: 018 (1.00) 1 ~

6. :

REFERENCE:

WOG Basis for Transfer to' Hot Leg Recirculation 000011K313- ..(KA's) l -. v. ANSWER:' 019 - (1.00) d.

REFERENCE:

.EOP-LP-6, p.y7, EOP-LP-6, M c A. 4 -000015K307' ..(KA's)- ' ANSWER:- 020. (1.00) b.

REFERENCE:

'EOP-LP-2,.p. 6. -EOP-LP-2, LO A.2 000074G012 ..(KA's) ANSWER:- '021' - (1.00) O. D' 1 w:

u. n, g }( 'I.~ AENIqR REACTOR.CPERATOR, .Prg3 48

REFERENCE:

AOP-002, Rev. 2, p. 3 LO - Not'Available-000024K301 ..(KA's)< ANSWER: 022. (1.00).. c.

REFERENCE:

L ' A*;P-0 0 8, ' Rev.. O, p. 4,-8, 11 .-LO - Not Available-000059G011 '..(KA's) i ANSWER: 023 (1.00) -b.

REFERENCE:

EOP-LP-11, P. 3 EOP-LP-11, LC A.2 000040K304 ....' ( KA ' s ) / ANSWER: 024 (1.00)' 'c.

REFERENCE:

EOP-LP-11, P. 8 EOP-LP-11, LO A.3 .000040G012 ..(KA's) . ANSWER: .025 (1.00) a.. 1 I w

b w,y + l'[A, fi,; p ; F-,(l e - i,l'; I1, ,[., l n, a < t. ',.. 1, 2 j.SENIO,R. REACTOR OPERATOR P g3 49 D

gq

+

s;

REFERENCE:

- +: % 2.e klE OP-017, Rev.14,'p. 8 l A . LO 2. p% 'AIC,-TP-2.1, Rev. O, E' - 000065A208 ..(KA's) j m t i f ,h .] j,.p l'.'.... j. 5 I i diANSWER; 026 -(1.00) l n. h > ',,,, .! 'l ' - S'

.j i arc p

.W;: g a;

REFERENCE:

? I s O, '..f EOP-LP-4, p. 16 1EOP-LP-4, LO A.3. 9 '), m000038K306. ..(KA's) A p~ v e a,, h 9;L ANSWER: 027 '(1.00) w; a ,a. .c ; .w..- w o

REFERENCE:

m. r .:. Jic Stram tables ~c LO - None Available

. m., %,. 000008K101

..(KA's) N $ 3 4', i 93 y' ANSWER: 028 (1.00) s

Mc.,

t,. .,i V":,

REFERENCE:

thw. ~iX GP-003, Rev. 29,. p. 26 '",J T NI-TP-4.1', LO < 4. - i >.. W l00^032A204 og, ..(KA's). 'd1J. ws 't h;,p :,: q,: a. ANSWER: .029 (1.00)- sw q a c. ; c H.e 'o ' f ,n, _, l'i N N'\\ u im i l' iJ% =;' i i k i Yl. l yi i l i ?.a e f n. u:

, : m, 1

t) it - T,

N;fV y $0i D.m i n o gdg ~,. p/ j g EN14R REACTOR OPERATOR. x 4 i '.ly 0 4..: P gi 50-q,j 1 3 [pp ;,.p. vNWM 4

REFERENCE:

u 4. Z;,>,EPPL-Supplements, Rev.-5, p. 4 l ilhlp'RHR-LP, LO 1.A. i P.ij - 000025K101 ..(KA's).

' [,

I !(('~ l.j l-QANSWER, 030 (1.00) m4. '% ? d.. l J $n. {y/d

REFERENCE:

,j j" SD-001, Rev. 3, p.19, 21, 22 6 RPS-LP-5, LO 1., 2., 3. '000007A206 ..(KA's) Ik;l' { i 031 (1.00) ! JANSWER: J ib. j

REFERENCE:

'l L EOP-LP-3, p.5 i' L. ~EOP-LP-3, LO.A.4. .f. 000009K323 ..(KA's) q 'I' g. !? ANSWER' 032' (1.00) = i. >.i .t T u.I.

REFERENCE:

p , DC-TP-2'.7, p.-13 'l DC-LP-2, LO A.1. 000058A203 ..(KA's) a i i. ) i L 033' (1.00) , ANSWER: e s M ii i ' ll,y .i M' ' /,. Lf w}ii g p; , \\ 'l, y k i' *^ Jt 'I tf' 1. }* i( i; 4 f.i

- i .k.... 1 ' AEblIOR= REACTOR,OPERATOM P;g3 51' i

REFERENCE:

.AOP-010, Rev.4, P. ' 4 " 'PLS-1, P. 24 25 "LO;- Not Ava11able o. 000054A205 ...(KA's) t i k ' ANSWER: 034. (1.00).

bs

+ in

REFERENCE:

ttf ACP-019, Rev. O, p. 5 l-I4 --Not Available 000027G011 ..(KA's) ,t - ANSWER: 035 (1.00). b. l 1,. u

REFERENCE:

-I t EOP-LP-17, p., 13 l 'EOP-LP-17, LO A.1. 000054G011 ..(KA's) i I i-ANSWER: 036 (1.00). i d. i

REFERENCE:

EOP-LP-4, p.25 - EOP-IG-4, LO A. 3. 000038K309 ..(KA's) } i i ANSWER: 037 (1.00) b. i l. l 1. i. l L .i 1 s +. . =.

W gr - y16 g, t ([ jfic, lipSMIOKREACTOR. OPERATOR-P2g3 52' hk. ] m

REFERENCE:

$!F.

($iAOP-016, Rev.

3, p. 3,.4 l ,= fiLO;- None Available ! 'tw 000009G011 ..(KA's) ' lf,! x h ?,y J ANSWER: 038 (1.00) C. l n

REFERENCE:

~ AOP-003,-Rev. O, p. 3 4 , g LO1-None Available-000022G005- ..(KA's) c. f L(ANSWER 039 (1.00)

.

0.

REFERENCE:

!Q((cSDr019, Rev.8, p. 35 'f![;RM-TP-3.1, iu Rev. 1, LO 3. i 00J'61A101, ..(KA's) h[l((p I !f ANSWER: 040 (1.00) i . t;,..; o vi, c,

REFERENCE:

[li ;;., f TAOP-017,,Rev. 4, P..6 i {F ; :. AIR-TP-2.1, LO 2; /t . 000065A206 ..(KA's) o .s UANSWER: 041 (1.00) ~i Q\\ 'I 1 + L ? i i i L....

,1 a. 1ENIOf REACTOR CPERATOR-P;g3 53 l 1

REFERENCE:

4, ' SD-059, : Rev. 2, p. 11 JRCS-TP-4.1, LO 1.' o' - 000028G011 ..(KA's) 1o Il ! ANSWER: 042 (1.00) 'l( ..w c.

REFERENCE:

1 -s i: PLR-LP-53, p. 6 V: ; PLR-LP-53, LO A. 2. - 000036K201 ..(KA's) n.. i,. $ ', 'l[. p 'f I r f l tANSWER:'- 043 (1.00) e. .1: 's $? t sx,

REFERENCE:

l 4 Z ELEC-LP-26,.p. 10 st ?ELEC-LP-26,'.LO A.1. Q 000056A247 ..(KA's) .I 4 i ANSWER:- 044 (1.00) . w ' c.u ' . i

REFERENCE:

j .M, /,

iSD-027, Rev. 9, p. 30

[ si FWrTP-3.1, LO 2. i pf", [061000K402 .-(KA's) 'r .i o g... - (' l l LANSWER:- '045 (1.00) 1 Jin :a. 1'g'3 i {f a w j ; ' 'y .) lf 4. )J,. n

d. I f :

,p- ] Q; '- g;. ,u' ' u m* ' n Eik' T f.

,\\ \\

7. '

,v w 4 i 7SENIOE REACTOR OPERATOR POg3 54 c,,. ,'Yl'l. i l 1

REFERENCE:

f.# 1 a ?N,'- E{u!SD-027, Rev.<9.' p. 15 ', FW-TP-2.1, LO 1'. 7059000K416 ..(KA's)- l W@ l

.o W

l 'i

(4 : ANSWER: 046 (1.00)

U: m > y:o. i ql REFERENCES. W h: Technical Specification 3.3.2.1 i '@ >ESF-TP-4.1, LO 7. W 026000G005 ..(KA's) l,, "r t l4.. ';$ ANSWER: ' 047 f;y yiv - (2.00). i lM fo. 8 l '".b. 5. f; ? c. 3 ' y d, L7-(0.5 each)- j'

REFERENCE:

I V SD-021,-Rev. 12, p. 22 F CVC-TP-3.1, LO 1.'-& 2.. 'g q 004020A305 004020A104 ..(KA's) w, y .p' JQ(ANSWER' 048 (1.00) w if b.~

REFERENCE:

4 .SD-023, Rev. 1, p. 18 -LRW-TP-2.1, LO-1. 068000K401' ..(KA's) ,pw ? . (k' h y-b -ANSWER: 049 (1.00) c.= a ? A I'> i r iv h L, t +-. .i w

y L'%,'l.

. ' ' opi$ :.h, y;g I s v a/ n; .e

4, m

SENIOR.REACTJR OPERATOR' P ga 55 i:' N

REFERENCE:

i i 4 '- i SD-007, Rev.l1, p. 29- '.AC-TP-3.1, LO:1.C.; 001000K202 ..(KA's) ANSWER t -050l,(1.00) d.:

REFERENCE:

SD-Obl, Rev.15',!p.'10-RDCNT-TP-3 ; 1, 14 1,. 014000A103' ..(KA's) ANSWER: i051 (1.' 0 0 )

Osl

REFERENCE:

.u SD-006,-Rev. 10, p. 13 & 14 ~ CCW-LP-2','LO 2. 003000K404' 003000K602 (KA's) ANSWER: ' 0 5 2 '. (1.00) W;

REFERENCE:

[SD-010j Ref. 3,-p. 10 & 13 sNI-TP-1.1, LO 4. 015000K407 015000A202 (KA's) 5 ) j -; s -'If .I . I, {, tt m 1

b....

l c .e. ~h SENIOR. REACTOR CPERATOR P g3 56; 'l f ANSWER:' 053 (2.00) t G.i4 . b.~.1 ht.. c.'3 i d.16.(.5 each) 3 l REFERENCEi- 'SD-007,<Rev.1 1,Ep. 5f&26 RDCNT-TP-1.1,:LO 3.A. i 001010K404 ..(KA's) i ANSWER: 054 -(1.00) L U b. j fe.

REFERENCE:

K ISD-007, Rev.11, p. 25 - RDCNT-TP-1.1, LO 3.A. 001000K408 ..(KA's) q

ANSWER

055- (1.00) ~' ' c.'

REFERENCE:

OP-101, Rev. 12, p. 11 LO~

None Available

003000G010

..(KA's) a -ANSWER: 056 (1.00)- c.- 1: I i l H + Ur m j

k. d .i I t .p-k 3 e i ~i 6c ENIOJL REACTOR. CPERATOR FCg3. 57

REFERENCE:

SD-006,-Rev. 7,.p; 16

ESF-TP-5.1; LO 2.

013000A301 ..(KA's) 1

( -

, ANSWER:

057, (1.00).

c. '.

REFERENCE:

~ 'SD-012, Rev. 2,' p.;20 .LO - None Available- ~ 017020K403- ..(KA's)~ a ANSWER: 058 ^(1.00). l

c. <

1

REFERENCE:

I i'

DC-10-1,' Session.2, p. 5 DC-TP-2.1, LO 2.

063000K302 ..(KA's) 1 ) ANSWER: =059 (1. 00). 1 'd ; 1

i

REFERENCE:

l 'SD-006) Rev.-10, p.-7 1 4 ESF-TP-5.1, LO.2. .013000K101, ..(KA's) - ) l i ANSWER: 060 (1.00) ' b. l ?.t. t (! 1: o e i W_ t

gi; h/SENIOJt REACTOR OPERATOR - j Paga 58l -o

REFERENCE:

1-

Technical Specificr. tion 3.10.3 and Basis

,NI-TP-5.1, LO 5. i '015020G006 ...(KA's) ,v ,-1 - ' ANSWER:, . 0 61 '.. (1.00) . l u 'O.' -REFERENCFs-SD-059, Rev. 2, p.'ll ~ RCS-T' -3.1, LO 4. / G' 011000K404 ..(KA's) 'M4SWER:' _062 (l'. 00 ) ,d.~ J,:

REFERENCE:

j OP-992, rev. 6, p.1 6 CSS-TP-8.1, LO 1.

028000A101-

..(KA's) 'An5WER: '063 (1.00) O.

REFERENCE:

SD-059, Rev.:2,-P. 16 ^RCS-TP-4.1, LO l'. .010000A107 ..(KA's) < ' ANSWER::- 064' (1.00) c'. - l i s I } l' i l-

f. 1-w/

. a

~ .0f bq ';- gh10Jt' RFACTOR CPERATOR :' P g3.59' ?

REFERENCE:

j + 11, p. 19,&.20 SD-005, ReV. DG-TP-2.1, LO 2. a ~064000K4024 ,..(KA's) u ~ ANSWER: 065 -(1.00) b8 ,1 o

REFERENCE:

n ( l: SD-008,~Rev. 1, p., 9, 10j 11 ' FH-TP-1.1', LO ' 3. : 034000K601 '..(KA's) ANSWER:. 066.e.(1.00) ii -d.? o

REFERENCE:

.SD-011,-Rev. 5,.p. 18 RPS-TP-4.1. 012000K611'- ..(KA's)-

ANSWER:

. 067.~ (2. 00) .Q. 3-

b. ' 6

.c. 5.

d. ' 2' (0. 5 each)-

.i

REFERENCE:

SD-011, Rev. 5,.'p. 15 - 21 RPS-TP-4.'1, LO 2. & 3. 012000G004' .=.(KA's) l u 4 ANSWER:

068 (1.00) 5 h

'c.- L r ~ I l l.. b lI t m

t 1 .1 ', SENIOJt, REACTOR OPERATOR.' P;g3 60

REFERENCE:

SD-027, REV. 9, p. 18 - 20' .SGLCS-TP-2.1, LO 1. 1035010A203 ..(KA's)' r ANSWER: 069 (1.00) . a.: REFERENCES. SD-044, Rev. 2, p. 5 & 19 FP-TP-7.1', LO 3. 086000K405 ..(KA's) . ANSWER:- 070.(1.00). b. j

REFERENCE:

d SD-001,.Rev. 3, p.~15 RCS-TP-11.1, LO 4. 002000K107 ..(KA's). ) 4 ANSWER: 071 (1.00) c.

REFERENCE:

I SD-001, Rev. 5,.p. 10 <RCS-TP-8.1, LO 1. 1002020K509 ...(KA's) - ANSWER:- 072 -(1.00) + .C. t l i - i L 1 l CL' )

,~ .y; ., w y. v. . c y x, 1,..e . y' '. , W' f Q,..ips s c.. .:u w i.Et c i ,, j - stili 9:: 7. +

y -. -. c.s. -

o 3 r 7-. m '~ SENIOR REACTOR OPERATOR = -@ I. i * ' Pag 3 61' + '.q;g + c, ...m 'i * ' g 5 + o#

REFERENCE:

1 ~b t x. I ,,,j )GPh005f Rev. 29? p.:23 o J9 i GEN-TP-1.1,: LO : 2. i 062000A403'- ..(KA's) a cm $v ANSWER:' 073:..'(1.00): +, 4 [. I cy b.

REFERENCE:

AC-HO-li Session 1,.p. 7= LO - None AvailableJ 1062000K301'

.. ( KA ' s ),.,

,4 I Q{J i l' 074. J (1. 00)'- 3]1 ),T ANSWERt - 1 b. : ,N ' 4 VlREFERENCN:. 'L j.0 tm m 3 JSD-025, Rev. 4, p. 6 , p'; i M S - T P - l'. 1,* L O ' 2. d , W6,l i 1039000K102 ..(KA's) 'q

ij s.

~+ v y 3 e EANSWER: 075.. (1. 00)-- ,.M x1 ~ fi i .Q ei J

REFERENCE:

.- j 'i 289-021, Rev.:12, p;-81 SFPC-TP-1.1,- LO 2. .1.(KA's) l033000A203 I k y ;- i ' 'l ANSWER:- 07.6 (l'. 00 ) 3 l Idi; ' d e 'fg n s b i m I cjal y I 3 ]p ii 'h ) u

w

m.'

q. ' ',. 9.p m ;q ~> 1: .i ? { e, i ,,x e [

r-

~ ;. P O + ' L, .v.. : NOSENIOR REACTOR OPERATOR. a l0. l' Pegs;62 Q3

u c,

<.+

REFERENCE:

E!- i

t

,e. ( SD-011,1Rev. 2,- p. 19. 6 l RPS-TP-3.1, :. LO ' 1. - 'i-lt':; " RPS-TP-5.1,'. LO 1. - e i, ? ' 012000K406 (KA's): .. s . ANSWER: 077 (1;00) [ ". e M c.: p (o s s. ? j :

REFERENCE:

y.g.. yp' RHR-TP-1.1, LO 5.-SD-003, Rev.'4',' p.:5'& 12) .c, (KA's) . 005000K407- .: ANSWER:- 078 (1.00). Y c. O i

REFERENCE:

.j ' SD-013, Rev.:3,^p. 8-CCW-TP-1.1,--LO 3.- 008000K401. (KA's)- 1 +' ANSWER:- 079 (1 LOO) .1 mN' _ g.

REFERENCE:

?j 'SD-059',)Rev. 2, p.110 l

RCS-TP-3.1",. LO ' 3.:

Jl r - 007000K301'. (KA's) .j 7 a-i g ' ANSWER:: 3 ja 080 (1.00)- ' c. . f s \\'.. ~ 8 l 'd + 4 '\\N j 'l - I I k

? O s i r n

y

,r.a, w, x (;'t.. :(SENIOpt; REACTOR CPERATOR'- 1 z . ; >s .1 6 P2gaj63 Ud.~ /- di ^ i v"; REFERENCE : s 4 SDiO25,' Revd 5,'p. 8-W. ' M S - T P - l'. 1',.- L O 1. - <) [l, # 7041000G004 ,..(KA's)' ~ .:n .^i.' 't ANSWER:< . 081 (1.00); ..j e

' O. ?

r 1,

REFERENCE:

4 uAOP-LP-01, p..7 AOP-LP-01, LO A.3. -[ '194001A103 ..(KA's)- j { w f,ANSWE M . 082.. (1. 00) ' ,. f e 3 ,~ _yp. e . 1 l

REFERENCE:

c -1 L-tA'OP-LP-01, p.;8 oI ' AOP-LP-01, : LO A. 4~.- 1189001A103 ..(KA's). { t 083 (1;00):

lANSWER

d.

REFERENCE:

1 ,'g l..' A O P L P - 2 / - p.< 8 -

t

-J ; AOP-LP-2, ' LO 'A'. 3 ' - 7 194001A113 ...(KA's) nn: m t 1 00)'

t J,q. ANSWER: J A

t w: - y $U I .s3 i b ';, ' s, L r I I ll' t.[ I ' 4 gg s [. i ( l ,E k f *' lh e I [ l q' ,4 oL;, W :-

C t' c/ ;.,

b,

'r=.l'., i n. j:. L ~ " } ;;fp,fis - e ; : !y, -; s,-- t !MdO 'f REACTOR PERATORl* . Pag 3 645 c y,p, s. '/

REFERENCE:

nl

9,4 lAOP-LP-6,;p. ~ & c 6.

1 a.f.AOP-LP-6, J A.' 2. -

.b, 1 01A10'2 c i..(KA's): ll 4 w. s n .. ANSWER l 085- (1.00) t c.; l 4 !s :.-

REFERENCE:

.m i

AOP-LP-9,1 p.: 10,& 11.

l , AOl'-LP-9,. LO A. 2. A 194001K116'. ..(KA's) j .g. s q ! ANSWER: LO86 L(14 00), s c.- n n J

REFERENCE:

i I, J. W' tAVT-L'P-1A, p.,11 &'12 'o sAVT-LP-1A,-LO A.8. ~ 194001A114 ..(KA's) en i /! ANSWER: 087 (1.00) y ~

,

6.y

-i

REFERENCE:

f ,i l o a-J: EOP-LP-1,ip.'10'. i 1 4LEOP-LP-1,:LOcA.4. n x , sis.194001A102 '..(KA's) .l j;. 3 a> 1;, i i lANSWER: 1088; (1.00)

b..

li) 0--s ~ { ..{- l l: l'.ih' I fs 5 is h' . ;j l,. L A C3 .;e:

jlW@ [ [ .k j ?. ' 4,fjQ li!y p,a J, "^ "g} 3 ShIO)t,n oREACTOREOPERATOR= J ; y pig 3: 65 ' x, !

ig.

, 'N ' i t t i 4 i:_ q,* i

REFERENCE:

'S e w ni, v, > - i i i b. iPROCMLP 2,$p $6:. + L

b.. i PROC-LP-1,0 I,A A.1.-.

W n 7 4 .) l D ,t194001K103' ..(KA's). t v g y ;; 1 . g ~. i, i ? sp? - '.Y : 'R. : I . / ,. ' i' y . ANSWERI;, 4089:. (1.00) 4

it ze Q(

..i[ O g' y pt: q. c

REFERENCE:

? D' 'l +

i,.: n.. a, y l PROC-LP-1L p.i 11'

~ .. g % PROC-LP-ly.LO.A.27

f

ib M...

T.. jy

194001K103-

..(KA's)- l :;1 m' A H-1w ~ n ..ai,'3'k,, g i

' ;1. 'i
)
; ANSWER: '. 090 '(1.00) o,m.

c.h 1;

w w

r..

REFERENCE:

. ~ m, Tl[~ PROC-LP-1,,p.c14 & 15 ' PROC -LP.-1,.1LO A.1. j

1194001K103'

..(KA's) e 1,. '091:. (1.00)'. 3 ANSWER:= .c,. 6 ,. }, ~

REFERENCE:

l 4 J i AOP-LP-7,.< p. J 5-7 4 LAOP-LP-7,ELO'A.2. & A.3. t .194001K102; ..(KA's) s .3 (ANSWER:' 092 ~ (1. 00) s,. t 4 1 I F ? s l v ^ 4 m.; m ~r-v w

y, W \\,, m y. y4 x } 'f I {-}..' . O ShIO[ REACTOR CPERATOR!: .) f i' 4

Pag 3L66

', + c ,hy, .-a> ( ,_n .c +, r + 1 $REFERENCEi' t l: v:;+.. L' x + '!;4 f AOP-LP-7, p. ';19 / &' 2 0 !.. J !? :./ AOP-LP-7, i LO.. A. 8. J & ; A. 92 Wf% L, f..(KA's):.. a. b. .,n . 194001K102' ^ ,.g h,) -t a _ $_ e r 'n Y[. g }{, c' 4 1 g -t E' 4 ANSWER:-- 093- (1. 00); .l-u o 'b.- w

REFERENCE:

+ y. EOP-LP.-1, p. 15 ~ .EOP-LP-1,+LO'A.4.' ':lI"4001A102 -i..(KA's)

n 4

5 . _ sg IANSWER:- (1~. 0 0 ) 3 ,.-:b. 3

REFERENCE:

e 1EP-LP-1, p. 5-tEP-LP-1, LO A.2.a., i 1194001A116 ..(KA's) S: d ANSWER:. l095. '(1. 00) ; r D.. ~ .i.

1

REFERENCE:

EP-LP-3,' p. 4.& 5 I:P-LP-3,' LO A.1'. '194001A116- ..(KA's) 1 iANSWER:- 096 (1.' 0 0 ) I, .C,. -i ) 4 i s 'f3 ', I. 1 I e

- ~ ' ~ , -lja + y",'s.r ;., m;: s< N fi g 7 1.- , 1 s, g s s ..O a ' I n ', } ;I ;. E i' C I y

f3 i

, -{ g J;, s y",., t W. v,, . gi

pcv

-.y ,v s@ i s.:.qe, y ~ ENIOS REACTOR,CPERATOR? M' i P0g167 0, ,t s i ...J g ')I ' s.,, q',s 7 y ")ey- .) w. f . 2 et.

REFERENCE:

i s 1, '.' PROC-LP-3 0, p. :- 8-10':

PROC-LP-30,:LO'A.2.' &.A.'3k

.W:n! 3- .e. p , (KA 's)i... ., ' 194 001A114 '- "E6 ,m

c

,l,. RANSWER::- ,097 -(1. 00)) 1 c,. I

REFERENCE:

OMM-013, Rev. 1, p. 63J- ' LO

None Jvailable -

' 194 001A3 02: (KA's)- 4 .t-

3.,

s g _d 1 0 i ' l. 5 c' '. 1 y

2
j

.~i 1 i i ,,. I s 1 1 -w ~1 .(**********;END OF EXAMINATION **********). 1 i I 'f. t {,

i, y ,,m r;. % ~ ,,.j.,j s 5$ , ;,' r,v -m. e - e,....~, r,,

j c s

.",, s l

f fu_ f, gggg 1,

.q Carolina Power & Light Compahy ? l.f u E H.'B. ROBINSON SEG PLANTJ h -POST OFFICE BOX 790 + HARTSVILLE, SOUTH CAROLINA-J29550l July 12, 1990 +- File:.NTS-4208(F)' Serial: NO-90R141 . Regional' Administrator. f U.=:S. Nuclear Regulatory. Commission. _ Region 11- -Suite 2900 =t* ?101 Marietta' Street, N.Wh Atlanta, Georgia 30323 a .ATTENTIONi.Mr. John _F.Munro:-

SUBJECT:

. Senior Reactor _ Operator Written Examination. .H ./

Dear l Mr. Munro:

_ On July 19,fl990, Mr. Curt Rapp'of the USNRC administered written Senior Reactor! -Operator'E9aminations at.H. B. Robinson. Enclosed, please find coments for the . examination. Instructors from=the.H. B.'_ Robinson Training Unit reviewed.the examinations,for > comments. TheyLincluded: R..S. Allen. T. R.~ Byron H. L. Carter s R. H. Shane s

If you have any questions, please contact me or Mr.- C. A.'Bethea.

j Very truly yours, t k Of 1 / i C. R. Die z Manager Robinson Nuclear Project b 'T .TRB:1sj-l 4 IL cc:' L..H. Martin

Enclosures (4)

JUL 161990 aa

o,

/ ,,.5 4.M:, 1 }.

. i%', ' ' ~ ^~ ~^ ^- ^ n; p, !n y;,7 e-lil-In' l 's' l L';,W j Enclosure 1:To Sertalsc -90R141-j f Page!.-ofl1; 1 7

f a.

4 ., i l 1 i NRC EXMINATION CO MENTS' s + w H. 8. ROBINSON SRO CLASS 89-1 (Upgrade) and 90-1 EXMINATION DATE -- duly. 9.11990- .[ l ,n l1.== Question 005 f i Recommend accepting answer "a" or "b". Since the symptoms indicate a failure of.a RCP fli seal and both "a" and "b" are innediate actions stated in A0P-018 Section 4.3.1, then answers "a" and "b" are both correct.. =i g

Reference:

'A0P-018, page 12 of.'15 (Rev. 1)

L' l u 2.- Question 052 3 Recommend changing-answer key from "a" to "b". -Both Intermediate Range < Channels must clear P-6 to automatically-reenergize source ranges. 'i

Reference:

NI-LP-3, page 11 of 28 3. . Question 084' Recommend.deletir.g question. No answer is correct.. Portions of the Main: . Steam System require.0WP!s. 6 I I of 5 (Rev. 1)

Reference:

. 0WP-024, page 4 s t 1 I A e j i i

by3QML .' W W7:' ^ , j'Q LEnc1gstfre! 2jTo?SeHal l = N0s90R141,3 [PageR1&ofils W ' Q=- I)' y,, i' Wll ' %%;d[m yiS, - ' - C gg.a.*n y,p, 7 N 3 'j o ith,sg.47 g i 1 o... R($, : Q4jdf e- .FAILUkE OF REACTOR: COOLANT PUMP SEAL- (Continued)L -:V C, # g nk i n r y,, 'W i H, j }Ui y

@;ll! b 4,1.3

~High standpipe level.- 1

w. g.

g s ;, i4'.1.4 RC PUMPS SHAFT SEAL WTR LO DELTA =P-alarm.= 4 kb $e 4.1. 5 :

RC PUMPS LABYRTH SEAL LO DELTA P' alarm.-

[p@; u l ;[4 1.6 z 1 3 f RC PUMPS SHAFT #1 SEAL LEAK HICH TEMP.; alarm. ]

w..

[ l [.". / 4k 1'. 7J .High Pump' bearing temperature. L a m. 9 Qfl. 4j i'. 8. High No. 1 Seal leak-off temperature.- 1 GW l 4 gp @N{->t(Y,4lwl! f 4.2., ' ' Automatic Actions ~ w ; [; ;. N:hw, None Applicable j r pg 9 p 4 ] kn x,,

S

-4.3 Operator Actions -!W , m; i 4. 3.15l .Immediate' Actions N' 4.3.1.1 .Using available plant indication and if necessary local inspection,' I ep-DETERMIllE which React.or Coolant Pump seal is failed.-

l

[vi .4.3.1.2. IF No. l' Seal has failed, THEN:

1. -

SHUT the No. 1 Seal Leak-off Isolation Valve. J CVC-303A l

-l CVC-303B

'CVC-303C 2.- REDUCE Reactor Power to less than-40% AND.STOP the affected Reactor Coolant Pump within 36 m nutes. j -3. Do NOT restart the affected RCP. J W 4$ 3'.1.3 : ~IF_ No. 2 Seal has failed, THEN:. + q y' 1. MONITOR Pump bearing, temperatures AND Seal leak-off p, temperatures and flows. 2. MONITDR Reactor Coolant Pump vibration levels'AND REFER to. P Section 5.0, "High Reactor Coolant Pump Vibration," if levels are excessive. 1 L p 4.3.2 Subsequent Actions 4.3.2.1 REFER to Technical Specification 3.0 AND 3.1.1. l: LAOP-018' Rev. 1 Page 12 of 15 l w

' i ei J. "\\* ~ l ~ ~ ~ r Enclosu& SM& L C f, ,4 7 re 3hTo(Serial: W - <PagejBof.1pfg/r 1 NO-90R141).- .( NI-LP-3 -. } 'h.. T 'g/dM/Q Mit J + UTLINE: KEY AIDS-E O b-J R Ok O,' A-jgjm:ne ;

m

? '%J,gd@ d, e2 .w NOTE:- LIf ~ reactor. L power 21stabove the' Source.

' Q /m[i Range ~ high flux 1 rip setpoint.: clearing t

g, y s<p V O this function willi cause ' a. reactor trip : 4i .m m, - and; may-damage ~ Lthe, Source Range < ' f.e,e. w "r m

.?

r detectors j

W Q g<

+ e 4,, f,h ' 7. ; ; Power. escalation pemissives ( t 1 - + s 'n :- a.- One out of two Intermediate Range permissive: P-6 setpoint isgj W. f/F . signals (P-6):1srequiredbefore'theSourceRange -10, ~... gg .{1gF( level trip; can be blocked l 'and detector hi gh.. 10-famps j . voltage cut off ' N: ,m :., n m b. Source ; Range level trips are automatically

qmy, e

A reactivated -and high. voltage ' restored when both~ yA .f Intermediate Range channels'- lare; below ' the ' = n

m...

4 permissive P-6 level'

l v.f!1-I

[v;f 9 B.-l Interconnections With Other Systems L

1., Reactor: Protection System - high' flux level trip
r s.

W j' -2. ' Plant computer-u

3.. 'AC' electrical power

.u f:, a. Instrument bus #1 - NIS cabinet A k' I i b. Instrument bus #2'- NIS cabinet B r-c.: Instrument bus #3.- NIS cabinet C l1 l-+ d. Instrument-bus #4 - NIS cabinet 0 li a ( '. i -r

l i
\\~

e 11 of 28 g l'S I 9: t..

p -r 3} c 2 p ' i [ Enclosure 4)TolSerialt NO.-90R141-iPagel1 pf 1 'h. ' h TOWP Titlos ~~MS-1 1

g. " ' O g Pega:

1 of-2 4% f n g g;g~ R 11, This: revision is the latest revision available and.has been-verified-fh[ against the'R'evision Status List. W (Print): ( ,Name Signature Date g -2.. System -- MS ~ Work Request Not '3. Component: Main Steam Isolation Valve "B" 4. Scope'of Work: Replace coil on MSIV "B" opening solenoid valve (s)~ 5.- Testing required on redundant equipment prior to rendering component L inoperable: ' 'N/A =1 4 4 - 6.- Precautions-1) Manual bypass valve must be held in'the bypass position-- during the' entire time that work is being performed otr' opening solenoid valve. Marual' bypass has spring return to normal position.

2) Solenoid valves will remain eneraised durina repairs on these valves.

3) Ensure opening solenoid valve (s):are energized and not' venting to atmosphere prior to releas'ing manual bypass.

1 -7.' Valve'/ Breaker / Switch lineup / .rt has been completed. . Signature Date- ) '('

8. 'LCTR Issued (If applicable)

LCTR Not !i 1 n -9. Testf g: required on' redundant equipment while-component is' inoperable. i -1 N/A- ] ,i 10. I&C Maintenance lineup completed. N/A /- Signature -Date 11. LCTR removed and Valve / Breaker / Switch ~/ ) -lineup restored to normal. Sigur tre Date H 12.;. Post Maintenance Testing. l a. Verify opening Solenoid valve is energized and not v'enting to atmosphere. / Signature Date. 'j 1 l: l h L-OWP-024 Rev.

Page 4 of 5 h

L 3

--qr &p;; ', u ax m+ ~ @fb" \\, Jm 0$rb,'ISE'O. l w s, o ~. " s Oir9 Y'\\ D l * \\ bc l m -. ENCLOSURE 4-t -< T NRC RESOLUTION OF FACILITY COMMENTS. 9' e .fSR0 Examination-i t m ~

Question 005: - ' Facility comment accepted. The answer key ~will' be' changed?to; accept a. or b.- for fulle cre'dit.

it 4, Facilit, comment 1 accepted. The' answer key will beichanged.to; j

Question'052:

require b.'as the full credit answer.-- w J~ cQuestion.084: Facility comment accepted. :The question'will be deleted'from L the. examination'and the pointsvalue' adjusted. L i r \\ .i L. I r i 1 0 L k i i k 1 t-l' t-I l

g g.- ] ~ + ,w %? Joj Q } w e l .J .j ENCLOSURE 5 j O ~' SIMULATIOE FACILITY FIDELITY REPORT o i Facility Licensee: H..B.' Robinson Steam Electric Plant a 'Facil.ity' Licensee Docket'No.:- 50-261 r-y Operating Tests. Administered on: July 10-12, 1990-- This form is to; be. used only to report observations. - These observations do 1 'not' consititueiaudit or ~ inspection-findings and ara. not, Lwithout further i verification and review, indicative of non-compliance with'.10 CFR 55.45(b). 1 4 These -observations do not affect NRC certification or-approval of the-- simulation facility other than -to' provide information:which may be used-in i 9 future-evaluations. No licensee action is' required in-' response. to these r ~ bservations. o During the conduct'of the simulator portioi, of the-operating examination, the -following items were observed:. p i 11)L -Malfunction for clogged. boric acid filter only effects boric' acid flow a't 100' percent severity. 2) Failure closed of LCV-115C'causes LCV-115B' to open but no flowpath from 'the RWST is established. 'This has been identified by the-facility.

3) Ther'e[isnoeffectonpeakcontainmentpressureforvariousratesofsteam

. generator blowdown'and number of containment coolers in operation.- .i

4) There is no effect'on feedwater pump.' suction pressure if a condensate pump i

bypass is failed open and the heater drain pump is tripped.

5) ERFIS,subcricality'CSF incorrectly indicated..a red path at power.

I i j o !}}

ML20064A574

Text

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