ML20235F008
| ML20235F008 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/14/1989 |
| From: | Burdick T, Hare S, Hopkins J, Lennartz J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20235F001 | List: |
| References | |
| 50-454-OL-89-01, 50-454-OL-89-1, NUDOCS 8902220361 | |
| Download: ML20235F008 (240) | |
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. i U.S. N'UCLEAR REGULATORY COMMISSION k
REGION III Report No. 50-454/0L-89-01 Docket Nos. 50-454; 50-455 Licenses No. NPF-37; NPF-66 I Licensee: Commonwealth Edison Byron Nuclear Station 4450 Gernian Church Rd. Byron, IL 61010 Facility Name: Byron Nuclear Station Examination Administered At: Byron Examination Conducted: Weeks of January 9 and 16, 1989 RIII Examiners: J. Hopkins h-/k-hf Date { S. Hare
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-lb/-@f/ i Chief Examiner: M J. Lennartz D 2-/6/-f> 7 I I
V .' te Approved By: f)A' T. Burdick, Chief h/hhf Date Operator Licensing Section 2 , Examination Summary Examination administered on January 9-17, 1989 (Report No. 50-454/0L-89-01) Areas Inspected: Written and operating examinations were administered to three Reactor Operator candidates and eleven Senior Reactor Operator candidates. Results: Three Reactor Operator and three Senior Reactor Cperator candidates ' passed the examinations. Eight Senior Rector Operator candidates failed the written examination with two of those candidates also failing the operating examination. l 8902220351 890214 4 DR ADOCK 0500(
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, - 1 37 g } ;)';l REPORT DETAILS
- 1. Examirars t
'*J.:Lennarti, NRC '
J.'Hopkins, NRC >
'S'. Hare,-NRC-n -*Chiif Examiner
- 2. Examiner Observation I
j During preparation of the written and eperating examinations the examiners found the reference material'phovided by the licensee: to be generally adequate. The! reference materials at times. however,' were lacking in plant-specific information in that it was written for the Braidwood' Plant, and the. system setpoints and parameters were not-always incorporated at the Byron Plart. There were also a couple'of;
. System Description Texts that were. totally missing from the provided material. -The following are a few specific examples of reference-material deficiencies:
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. Digital Rod Position Indication System lesson plan, Chapter 29, i indicates that to bypass the rod at bottom. alarm, all rods. in 1 that bank must be greater than'or equal to twelve (12) steps. ,
The actual setpoint at Byron is nine (9). steps. (See Byron ! comment on SRO examination Question 6 14 in Section 4Lof this report.) Braidwood plant specific material on .the Circulating Water System - and the Essential Service Water System were'provided. .In regards-to these two systems, the Byron Plant is designed very differently. and the provided material could not be'used. The Byron plant specific material was provided to the examiners upon request. Condensate and Feedwater System Description, Chapter 25, was missing from the provided reference material. The facility is encouraged to provide Byron plant specific material and to ensure that all of the reference material is updated and all inclusive. This would preclude technical errors and any delays involved with preparation and administration of future examinations. During the administration of the Operating Examinations, the examiners observed both deficiencies and strengths on the part of the Senior Reactor Operator and Reactor Operator candidates. In addition, two concerns were identifted by the examiners regarding: (1) labeling oi keys , for Emergency Diesel Generator (EDG) control panel, and (2) location of i. l jumpers required to execute 80A ELECT-3, " Local Emergency Start of a Diesel Generator." i 2 W
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.The following deficiencies in the candidates' performance'were observed in the majority of the candidates that were examined in'each particular knowledge or, ability:
The candidatas ability to successfully execute Byron Operating Procedure IP-2, " Transferring an Instrument Bus from the Inverter to the Constant Voltage Transformer" was generally unsatisfactory. The calididates overall~. knowledge of the Radiation Monitoring System capabilities in the Fuel. Flandling building,. including system components and indications was generally unsatisfactory. The candidates ability to' determine if the EDG jacking gear is disengaged during execution of Step 4 of Byron Abnormal Operating. Procedure' ELECT-3, " Local Emergency Start Op' A Diesel Generator" was generally unsatisfactory.
- The candidates ability to recogP.ize that an inadvertent Phase B isolation occurred was unsatisfactory.
The following strengths in the candidates' performance were observec' in the majority of the candidates that were examined .in each particular ability: 6 The candidates ability to. reference and utilize electrital and mechanical' system ficw diagrams was generally good.
- The candidates ability to perform immediate action steps of Byron Emergency Procedures was very good.
The Senior Reactor Operator candidates ability to prioritize events and address the most-important items regarding plant safety first was generally good. The candidates ability to co;nmunicate effectively and to operate with the "ceam concept" in mind was gererally good. The following concerns were identified by the examiners: In order to execute Byron Abnormal Operating Procedure ELECT-3, two (2) separate keys must be obtained from the Shift Engineers (SE) office. These two keys are not clearly lebeled as to the function each serves which could confuse the operator with a resultant unnecessary delay in completion of the procedure. 1 In order to cbmplete Step 9.d.3 of Byron Abnormal Operating Procedure E'.ECT-3, the operator muet obtain jumpers that have t'o be installed. These required jumpers do not have a dedicated stcrage ic:ker/locacien from which the operator weuld get these each time he needed them. Without _a dedicated storege locker / location, the operator may have to take time to find the jumpers with a resultant unnecessary delay in completion of the ;; vadure. 3 i-
I' . An additional comment is that the examiners felt that the " green board" concept for locked equipment key control was an excellent program in l that it demonstrated very precise and positive control of the keys. _,t
- 3. Ex i t_. Meeti ng An exit meeting was held to discuss the aforementioned observed deficiencies, strengths, concerns, and comments on January 17, 1983, with facility management and training staff representatives.
NRC representatives in attendance were: J. Lennartz, Examiner J. Hopkins, Examiner Facility representatives in attendance were: R. Pleniewicz, Station Manager R. Ward, Services Superintendent T. Tulon, Assistant Superintendent Operating j A. Chernick, Training Supervisor K. Gerling, PWR License Supervisor D. Popkins, Byron Simulator Supervisor L. Bunner, Byron Operations Lead Instructor l The facility managecicqt acknowledged the examiners observations discussed in Section 2 of this report. In addition, an exit meeting was held following the completion of the l si;nulator portion of the operating exatninations on January 16, 1989, This meeting was held with Production Training Ceriter management and 4 staff representatives to discuss the simulation facility report as ] contained in Section 5 of this report. NRC representatives in attendance were: ) i J. Lennartz, Examiner ] J. Hopkins, Examiner i i Production Training Center represer.tatives in attendance were: K. Ger?ing, PWR License Supervisor - T. Chasensky, Limulator Group Supervisor ) D. Burton, Simulator Instructor I 1 l The Production Training Cerster representatives. acknowledged the examiners i observations on simulation facility fidelity. ]
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- 4. Examination Review I I
Facility representatives were allowed to review the written examinations l prior to their administration, and ariy applicable comments from the review were incorporated into the examinations. 4
( + s Following the conclusion of the written examinations, the facility is given a copy of the Senior Reactor Operator and Reactor Operator examinations and answer keys, . The facility then had until-the end of the week Vf the examination administration to provide any additional comments in writing to the.NRC. The following paragraphs contain the facility comments concerning the
- f. examinations followed by the NRC resolutions.
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1 Senior Reactor Operator Exarnination 1 Byron Comment: Question 4.05 (R0 Questior, 1.05) l The primary effecis on Kef f by control rods are changes in (p) and (f). j (Aeswer c). (Pf) and (Pth) changes also have aa effect, although smaPer. I Byron proposes that Answer D. also ba accepted as a correct ansver since all ! the factors in answer D are affected by control rods, j References Attachments 1.a,1.b, Syron/Braidwood Nuclear Theory , Chapter 6 Lesson Plan, Pages 10 and 27. g ' NRC Resolution: Comment not accepted. The. quest $on >peciH eally asked for the DOMINATING EFFECTS on Kef' by the control rods and not the total effects. Control rods have a sinali effect on nor.-leakage probabilities (Pf and Pth) and a resulting small effect on Keff, but the domincting effects are due to changes in therma?
- utilization (F) and resonance escape probability and therefore, cholca C is the correct &nswer.
Pyron Concent: gy s,1; ion 4.13_(RD [klegtlan 1.13). Step 11 cf _BEP ES 0.1, " Reactor Trip Response" requires a verificatica of NATURAL CIRCULATION in accordance with Attachment B of t.he same precedure. Attachnent B list five conditions that support or indicate natural circulation flow as follow:
- 1. RCS subcooling acceptabla.
- 2. S/G pressure - stable or deci easing.
- 3. RCS hot ieg temperatures - stable ur decreasir.g.
4 Average of ten highest : ore evit thermocouple stable or decreasing.
- 5. RCS cid leg temperatures, at seteration temperature for S/G pressure.
Byron pC; poses that the cbove five conditions A sc be acceoted as correct answers, Referentes Attachmer,ts 2.a+2.e, _BF' ES 0.1, '% actor Trip iles;>onse," Pages is and 22, "Dyron/Braidwood Heat Transfer," Chapter 5, "Lesscn Plan," h.ges 28, 29 and 42. NRC Res_olution: Comment partially accepted. The question specti'ichily askt for FOL'R VER1FICATIONS that the operator uses to ensure teat h' eat Pemoval matches or
8 i exceeds heat generation. Proposed answers thres (3) "RCS Fot leg temperatures j stable - or vacreasing," and four (4) " Average of ten higMst core a't 1 thermocouple stable or decreasing" will be acceptad as they indicate heat removal. Alac, proposed answei 60. 5, "RCS cold leg temperatures at saturation trdnpereture for S/G pressure," will be accepted as an alternate to NRC answer No. 4, " verify cold leg temperature constant (or slightly aoove) the steam temper ture." The answer key has been modified to reflect these changes. Byron Comment: Question 4.18 (RC Question 1.18] The i4RC answer'is correct, but Byron feels the questian could be anntered adequately without the detail required in the answer key. Byrc'1 proposes that the following (or eNIValent) addresses the specif1c concern with the operation of the AR-3 relay, and de accepted for full credit: Holding the switch unt.il closed indice. tion is received precludes damage tc th: AR-3 relay contacts by ensuring the contacts are not opened under high currert. KR/l Resolut 3r,: Comment partially accepted. The proposed answer will be given partial ccadtt, and would be adequate to receive a passing score on this question. However, full credit will att be given for the proposed answer, as it ooes not fully explain the operation of the AR-3 relay. i Byrg Comment: Question 5.03 The 'OC answer 15 correct. however Tech. Spec. 'Lt0 5.9.8.1 requirn 1 RH loop nperable and in operation provided the water level above the tcp of the vest,el flange is > 23 feet. The bnis for Tech. Spec. 3/3.9.8 (RHR and Coolant Circulation) lists a level of 23 feet above aad flange with respsct to hest i sirsk capability. (see Attachments 12.z/12.b) The cardidate may pursue the basis for this 1.CO. j By7ca proposes the following be accepted as an optional answer: i Provides large heat sink in the event Gf loss of operating RH loap to provide 1 adequate time to initiate emergency procedures to ccol the core. 1
] Re_ferences Attachment 12a - Byron lech. Spec. LCO 3.9.8.1.
J Attachment 12b - Byron Tech. Spec. basis 3.9.6.1. NRC Resolut.iog: Comment accepted. The cnswer key has been modified to reflect this. 2
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{ l pyrpt omenti C Ouest1on 5.08 The NR0 answer is correct, howevar the candidate may co into a more in' depth discussion. Byron proposes the following be accepted as an optional answer: Independent and redundant systems designed to satisfy the single failure
-criterion, j Referenceu Attachment 13 - Byron /Braidwood System Description, Page 5, Section 1.c.
NRC Reso19tico: Comment partially . accepted. The proposed answer will be given half credit. In order for full credit to be received, the proposed answer must also int'.ude j "so that the loss of either system will not prevent the safe shutdown of the plant during sin.altaneous design bases loss of coolant accident and a loss of f offsite power," which is included in the provided referente along with the ' proposed answer. - Byron Comment: Question 5.09 Source Range Channel 32 control power (s supplied by Instrument Bus 112. Loss of Instrument Bus 112 would result i?i a loss of control power to SR Chapter 32. Byron propuses the fc110 wing be accepted as an optional answer: Loss of instrument Bus'112 References Attachmet;; 14 - ELEC-2, Page 4. NRC Re, solution: Comment accepted. The answer key has been modified to reflect this. Byron Comment: Question 5.11
'he NRC answer is correct, however, the Tech. Spec. basis lists a peak -
pressure of 44.4 psig assuming initial pressure of 1.0 psig due to a double. ; ended RCS cold leg break. } l Byron proposes the following be accepted as an optional answer. Limits containment pressure to a peak pressure af 44.4 psig assuming initial pressure of 1.0 psia due to a double ended RCS cold leg break l 3 ; i l i
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References Attachment 15 - Tech. Spec. bases, Pages 3/4 6-1. NRC Resolution: Comment accepted. The answer key has been modified to reflect this. Byron Conment: Question 5.17 Byron proposes the question be dc.leted from the exam based upon the following:
- 1. The question asks the candidate to interpret Tech. Specs. in a non-conservative manner which disagrees with Byron Station and PTC training philosophy. The candidates could interpret HAXIMUM power-level as the highest powar leval at which they would (conservatively) allow the plant to operate.
2 ine question states the rod is at 100 steps as indicated by DRPI. The DIRP lights only ' illuminate every 6 steps. In this case, DRPI would indicate the rod at 96 or 'i02 steps, not 100 steps. , 4
- 3. The accuracy of DRPI is i 4 steps of indicated position, which would I furthU expand the range of the answer. !
R_eferencec I Attachnient 16.a - System Description, Chapter 29, Page 1.i. Attachment 16.b - System Description, Chapter 29, Dage 18. Attachment IG.c - System Description, Cha e er 29, Page 19. NRC Resolution: ! Comment not accepted. The question specifically asks for MAXIHUM power level l that TECHNICAL SPECIFICATIONS would allow. Also, clarification of this question was asked for during administration of the written examination, and all SRO applicants were informed at this time that the question was specifically looking for maximum power level that technical specifications would allow. In addition, this question was asked of six PTC training i instructors for examination feedback, and five of these six instructors responded with the answer as written in the answer key. Due to the accuracy of ORPI, expanded answers will be accepted on a case by j case basis if the applicant states his assu;nptions as to where rods are located. However, if the assumption is made that rods are at 100 steps, as indicated in the question, or no assumptions are stated, then only the answer as written will be accepted. [ l 4 i, 4
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, Byron Comment: Question 6.0_5, l The D/G Air Start System supplies the ccntrol air system which in turn supplies tha Pnecmatic Protection System.
During a test modo start, the emergency fuel control valves remain open, thus allowing control air up to the fuel controi cylinder in the event'of any D/G t9st or emergency mode trip signal. During an emergency mode start the emergency fuel control valves will close thus blocking control air to the fuel control cy'linder in the event that any test anode trip is received.
,Re_fe rence s Attachment 17.a. b, c,-LCT LP PI-DG-XL-01, Pages 20, 21, 22. )
Attachment 17.d, e-LCT LP PI-DG-XL-01, Diagra:iis DG 17c-17d. J NRC Resolutio_n: Comment not accepted. The conment dcas not contain a concise facility recommendation and therefere will not be &ccep'ed in accordance wit.h Examiner Standard 403," grading of written examinations." In addition, clarification : was asked for during the administration of the examination, and all SRO ; applicants were informed that the question was specifically aski_ng about the Emergency Diesel Generator Air Start System Coaponents, and how they I- specifically responded to the different start signais. 8vron
, Con:.nent: Question 6.08 A Feedwater Isolation Signal directly causes FRVs and FRV bypasses as well as other valves to close.
Byron proposes a separate listing of "FRVs and FRV Bypasses close" is not required for full credit. Referenc_es f Attachment 18, Byron /Braldwood System Description, Chapter 25, Figure 25-6a. j I NRC Resolution: Cummein accepted. The answer key has been modified to reflect this. l i Byron Comment: Questio46 09 i l The question dces not provide the candidate with adequate information to l discern which portion of the controller failed; the reference or output, j The NRC answer is correct assu'ning the " controller output" failed low. j The candidate may assume the " reference" portion of the controller failed 1 l l
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, j low. . In.this case, the actual pressure is compars.1 to the failed reference.
(1700 psig), causing an output which lowers PZR pretoure to the new reference value. (this has the same end result as the controlling chanael failing high) Byron proposes the following be accepted as an additional, optional answer: j 90RV 4554 open 1 Both spray valves open i Actual RCS pressure decreases PORV 455A closes when actual pressure < 2185 psig Actual pressure centinues to decrease (sprays remain open) f!x trip at 1885 psig SI at 1829 psig j References Attach.?ents 19a, BGP 100-1A1, P&ge 3, ) Attachment lob, Byron /Braidwocd System Description, Chapter 14, Page 54. I. NRC Resolution: Comment partially accepted. The proposed answer will be accepted for full j credit if th2 applicant :tates the assumption that his answer is Dased on the j controller reference failing. low. The answer as written will be accepted for full credit withcut any asstimptions required, Byroq rpqmment: Ques _ tion 6.12 In this conditioro, De ince! switch in the DFF nr MAWUAL position will also generate an AF Pur.p Trouble and not causa a t, :p. Byron proposes the following te accepted as.an additional optional answer .
?ocal switch in the OFF or MANUAL position.
References Attachment 20 - Byron BAR 1-3-C6. NRC Resolution: Comment accepted. The answer key has been 2 dified to reflect this. Byron Comment: Question 6.14 Answer key states Rod at Bottom Annunciator would not annunciate until a rod m bank D reaches 12 steps. Byron croposes the following be accepted as the correct answer: 6 w-_".h___w-___- - - .---- - - - -----_d--- - - . - _ - - - "
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- Rod'at Bottom Annunicator would not annunicate until a rod in bank D reaches j l 9 steps.
References . i Attachment 21 - Byron BAR 1-10-E6. NRC Resolution: Comment accepted. The answer key has been nodified to reflect this. The incorrect setpoint came directly from the provided references (Systen Descriptions) that were utilized during preparation of the exam. The facility is encouraged to develop plant specific System Descriptions to , help alleviate this problem for future examinations. F I 1 i q I f l l i 1 1
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R_eactor Operator Examination Byron Comment: Question LOS See SR0 examination Question 4.05 for comment and NRC resolution. Byron Comment: Question 1.13 - See SR0 examination Question 4.13 for comment and NRC resolution.
, Byron Comm nt: Question 1.16 The Answer Key designates "0.5 poir,ts each" for each anst;er to part "A."
Since the question denctes Part 1 1s worth 0.5 points, each part should be wort'n 0.25 points. Byron proposes the point values for the answers be changed accordingly. i4RC Resolution: Comment accepted. The answer key has been mooiiled to reflect this. Byron Comment: Question 1.18 See SRO examination Question 4.18 for comment and NRC ruolution. f b Byron Comment: Question 1.20 , The information.for the answer comes from Column "B" of the lesson plan. t The information listed in Column B of a lesson plant.is intended to aid i the int,tructor with suggested transparencies, additional background material etc . .. Column "B" material is net considered required or testable , knowledge. Any required knowledge is to be placed in Column "A" of the 1 lesson plan. i Byron proposes this question be deleted from the exam.
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References Attachments 3.e and 3.b, Byron /Braidwood Lesson Plan, Chapter 23, Pages 16 and 17. ) NRC Resolution: Conment not accepted. The kno# edge and ability (K/A) rating from i NUREG 1122, " Knowledge and Abilities Catalog For Nuclear Plant Operators- l Pressurized Water Reactors," that this questien was written for (191001K101) { has an importance rating cf 3.3 for a reactor operater. The NRC feels this is J necetsary fundamental knowledge of component operations. ' l f I L_ __
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Byron Comment: Question 2,02 The term " parameter" does not provide adequate guidance to the ::andiSte. The candidates are taught the " indication" of containment' radiation icay alarm on a major sterm leak in containment while the " actual" radiation does not. Byron proposes that containment radiatiori level " INCREASE" on a steam break in containment is also an acceptable answer. Re f erenc e_s. Attachment .4, Major Accident Identification Chart (handout previded to candidates during day 25 of Simulator Training). l NRC Resolution: Comment partially accepted. The Contair. ment Radiation parameter will be deleted from the question. Accepting both answcrs does not successfully differentiate between a competent and less than competent operator. The answer key has been modified to reflect this. Additionally, the reference cited above was not provided to the examiners for use in preparing the examination. This would be a useful reference for future examinations, and the ' facility is urged to supply these type references to the IIRC. Byron Comment: Question 2.04 Part B does not specify which procedure is to be used. . Depending upon cooldown rate desired, SEp ES-0.3, Natural Circulation With Steam Void in Vessel (with RVLIS) may be used. In thiv, procedure, the operator is instructed to use RVLIS te monitor the growth of the void in the vessel plenura. Byron p:oposes RVLIS is also an acceptable answer. References Attachment Sa, BEP ES-0.3, Page 5, Step 6. Ati,'chment 5b, Byron /E>raidwood System Description Manual, Chapter 34, Fase 10. NRC Resolution: Comment partially accepted. One-half credit will be given for simply stating RVLIS, and the rem 61nder of the credit wiil be given for specifying the procedure. The answer key has been modified to reflect this. 3 Byron Comment: Question 2.18 The term " minimizes / mitigates inventory loss" does not adequately guide the candidate. While accumulator injection is a reason to deprecsurize the RCS, it has no effect on the actual loss of inventory. Byron proposes that accumulator injection not be required for fn11 credit. 1 l 2
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NRC Resol.ution: Commert accepted. The answer key has been modified to reflect this. l Also note that FS-201, Attachment 2, Enclosure 4, " Requirements for Facility Review of Written Examinations," recuires that the facility supply a referenca for each comment. No reference was provided. Additionally, the reference supplied by the examiner s,upports the original answer key. The NRC recommends that the facility revise the lesson plan. Byrot: Comment: Question 3.05.a The initial conditions provide erroneous indications to the candidate since SR High Flux Trip is set at 1.0 X 105 CPS. Byron proposes that an acceptahN answer should be " Manually trip the reactor and go to BEP-0." References Attachment 6, BEP-0 Reactor Trip or Safety Injection, Page 1 - Symptoms or Entry conditions. NRC eR'sciution: Comment accepted, The only acceptable answer will be to r.anually trip the reactor and go to BEP-0. The answer key has been modified to reflect this,
'Br on Comment: Question 3.06.c The wr-ding of Part c. of the question does not imply Technical S. calcification concerns. Blocking BDPS has no physical effect on Source Range Instrumentation.
Byron proposos that an acceptable answer to Part c. should be "No Effect". The Question could be interpreted to mean, "Is there an interlock between BDPS and the Source Range, when BDP5 is blocked? BDPS is blocked in BGP 100-2 prior to startup with no effect on the Source Range. References Attachment 6a, IBGP 100-2, Plant Startup. Page 6, Step 12. NRC Resolution: Comment accepted. Part c. deleted. The answer key has been modified to reflect this. 3
4 Additionally, the NRC recommends revising Chapter 31 of the $yste::' Description to prevent any future misunderstanding about how blocking BDPS effects the SR. Byron Comment: Question'E.07.a Byron proposes the VCT (iiot via relief valve) be added as an optional answer since manual valvc CV8482 can be opened to align seat return flow directly to the VCT. ; References Attachment 7, B0P CV-15, Pye 2. NRC Resolution: . Comment not accepted. The question asks specifically for FOUR places that PsCS water can go. The VCT will not be accepted twice. Byror Comment: Question 3.08 The reference used by the NRC is incorrect, This reference will be revised to indicate the correct answer. Byron proposes the correct answer as follows: l Prevent motor overload due to adverse containment conditions (LOCA or . Steam / Feed break). ; l References Attachment 8a, draidwood Systems,~ Chapter 20, Lesson Plan, Page 30. { Attachment Bb, WOG Background Document, Step Description, for FR-Z.1, Step 4. { NRC Resolution: Comment partially accepted. " Cooling capacity" of the RCFC will be changed to "the motor." Howeve,', to receive fuli credit, the candidate n1ust specify the Adverse Containment conditien, such as increased air density, excessive moisture, high humidity, or steam / moisture content. The answer key has been , modified to reflect this. ! l Byron Comment: Question 3.09 Part_a The NRC answer Key is incorrect. A lpH of 3.8 is a_eidic pH not bas 4: pH, , therefore Caustic Stress and Chloride Stress corrosions are not applicable, j 4 1 L_-_-_---_.--__
Byron proposes the following as correct answers: Part a.1 - With samp pH acidie (less than 7.0) iodine ... Part a.2 - Sump and associated ECCS components mere s.usceptible to corrosien. NRC Resolution: Comment accepted. The answer key has been modified to reflect this. j Part b i Byron proposes the following also be accepted as a correct answer: Containment Spray will restart on the EDG sequencer since the CS actuation signal has not been reset. (retentive memory logic statement not required for tull credit) Also see SRO License Exam question and answer key 6.16 References Attachment 9, Byron /Braidwood System Description Manual, Chapter 61, Page M. NRC Resolu_ tion: Comment accepted. Equivalent wording for the concept will ret.eive f.ull credit. The answer key has been modified to reflect this. Byron Ocament: Question S.14 l I Part I does not provide the candidate adequate guicance. He reay assume the { EDG remained running (not manually shutdown) when the SI wes reset, and " tnerefore not spec 1fy EDG startup. Byron proposas that Item 8, EDG Startup, not be required full full credit for Part 1. ; I NRC Resolution:
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Comment accepted. The candidate will not receive credit or be penalized for I selecting Item "B" in Part 1. The answer key has been modified to reflect this. l Byron Comment: Question 3.21 l 1 BAP 300-1 allows a system lineup in lieu of reverification of individual 1 outages: (See Attachment 10). - 1 6yron ' proposes the following be acceptable as an optional answer for Item 4., I Field Verification: ' i 5 i l
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- independent. verification of system lineup sheet, i 4
References i i I Attachment 10, BAP 300-1, Page 16, Stes C.3.v. (f). j
- 1. I NRC Resolution:
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Conmcrt accepted. The &nsw r has been modified to reflect this. < Byron Comment: Question 3.23 BAP 320-1 requires the SE, the SCRE, the NS0s and three EAs in the minimum i shift crew t.o' safely shytdown the unit. (See Attachment 11). Byron proposes that these thles be included as an acceptable answer. References Attachment .11, BAP 320-1, Page 2, Step C.2. . NRC Resolution: Comment partially accepted. The following answer will be added to the key.as. an acce). table substitute:
- 1. The Firc Brigade will not include the SE, NS0s, the SCRE, and three EAs in the minimur shift crew necessary fo* the safe shutdown of the unit. (0.5) 2_ Any personnel required for other essential functions during a fire i emergency. (0.5)
The answer key has been modified to reflect this. ( I I l 1 6
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- 5. SIMULATION FACILITY REPORT Facility Licensee: Byron Facility Licensee Docket No. 50-454/50-455 Operating Tests Administered At: Commonwealth Edison Production Training L
Center , 1 During the conduct of the simulator portion cf the operating tests, the foll~owing items were observed (if none, so state): l ITEM D_E_SCRIPTION
- 1. While feeding only "A" Steam Generator (5/G) during a loss of secondary heat sink scenario, "B" and "D" S/Gs showed level increasing at the same rate as "A" S/G even though they were (
isolated. *C" S/G which had a 150 gpd tube leak in it showed no level increase. ,
- 2. Steam jet air ejector radiation monitor 3 were the only monitors that alarmed during a Steam Generator Tube Rupture event.
I I 3. During one. scenario charging fiaw controller, CV-121, would not ; operate in manual. 4 Any scenario which resulted in RCS pressure dacreasing to approximately 700 psig resulted in Safety Injection Accumulators pressure to spuriously peg high and give associcted accumulator high pressure alarm.
- 5. The RCS was instantaneously borated by 3000 ppm whenever charging pump suction supply automatically swapped from the Volume Control Tank (VCT) to the Refueling Water Sturage Tank (RWST).
- 6. The reactor would inadvertently trip on pressurizer high level, and numerous false signals / indications were received (i e., loss of all 4 C. power; loss of digital rod position indication; loss of turbine control panel indication; loss of turbine control panel indications: Emergency Core Cooling Pump motor amps fluctuated from high to low peg) whenevet the operator manually shut CV-1128 (VCT outlet isolation) after manually opening CV-112D (RWST to charging pump) to verify emergency boration capabilities.
This malfunction caused a significant delay and perturbation on the simulator exai;,inations that day. The malfunction, however, d was:ovrected by the Production Training Center staff she day it occurred. e i
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, . k. ' , 1 L a U. S. NUCLEAR REGULATORY.C W MISSION i 1- ' REAGTOB GPERATOR LICENSE EXAMINATION l( . FACILITY: Td/V ,_ I' REACTOR TYPE: PWR-WEC4 g_ i DATE ADMINISTERED: 09/01/09 __ , INSTRUCTIONS;TO CANDIDATFd h Us6- separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. E.xamination papers will be picked up six (6) hours after the examination starts.
% OF l CATEGORY % OF CANDIDATE'S CATEGORY V6LUE_ _ TOTAL SCORE VALUE CATEGORY _
24,J' N 1. DUO -e+4 E M4 REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
,pf kP+T AM
- 1. O& 44 r40- ,
- 2. EMERGENCT AND ABNORMAL PLANT EVOLUTIONS (27%)
97af C M YM 46-6& 47 EP 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC
/o 0.15- RESPONSIBILITIES (10%)
- m. ra 10;;L. % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
h 00/O V Candidate's Signatu'r/
. -~ . - . . - - - . . . .
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS
'During the administration of this examination the following rules apply-l 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
l ! 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Uce black ink or dark pencil only to facilitate legible reproductions.
~<. Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination {if necessary).
- 6. Use cnly the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category __" as appropriate., start each category on a new page, write only on one side of the peper, and write "Last Page" on the last answer sheet. 3
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Segarate answer cheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be ueed es a guide for the depth of answer required.
- 14. Show all calculations, methods, er assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial. credit may be given. Therefore, ANSWER ALL PARTS OF THE 1 QUESTION AND DO NOT LEhVE ANY ANSWER BLANK.
- 16. Lf parts of the examination are not clear as to intent, ask questions of the examiner only.
- 17. You must sign the statement on the cover shset that indicates that the work is your own and ycu have not received or been given assistance in j completing the examination. This must be done after the examination has been completed.
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- 18. When you complete your examination, you shall:
I
- a. Assemble your examination as follows:
(1) Exam questions on top. (2) Exam aids - figures, tables, etc. (3) Answer.pages including figures which are part of the answer,
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the ba?,nce of the paper that you did not use for answering the questions-
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
l __j
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. touATIon' SHEET ,
t = ma ,. s/t cycle efficiaacy = (Network out)/(Energy.in) z w = ag s'= v ,t + 1/2 et , t g = ec . Erain =' e=(v,-v.1/t A = nn A=A[* { PE = asa Vf = V, + et w = ett a = am2/t g = 0.693/t1/2
,= , ,.
A = , ,,2 *in'" " [:(('m)(*J3 g )+(t,)] aE = 931 am .
-p
, a = V,,As I,Ieg i
q = aCpat 6 = UAa7 I = I,e~"* Pwe = Wyah I = 1, 10~"" TVL = 1.3/s s P = P,10 sw(t) 'HVL 5 -0.593/s t P = P ,e /T SUR = 26.06/T SCR=5/(1-Kgf) l CR ,= $/(1 - Kgf,) SUR=26p/a*+(s-e)T CR j (1 - Kgfj)=CRII~Idf2)2 1 l T = (a*/s) + [(s - syIs] M =.1/(1 - Kgg)=CR/CR, j T = s/(p - s) M ='(1 - Egf,)/(1-K,ffj) T=(4-e)/(Is) , SOM = ( -Kgg)/Kgf - e.=(Kgg-1)/Kg f = aKg,/Kgf s' = 10 seconds I = 0.1 seconds" l e = [(s*/(T Kgf)] + [Tgf /(1 +IT))- I ldy = 1 d2 Id y gd ,2 2
)
P = ( 4V)/(3 a 1010) t2 R/hr = (0.5 CE)/dtg ,g,,,)-
= en R/hr = 6 CE/d2 (feet) !
I Water Parameters - siiscellaneous Conversions ) I al. = 8.345 les. 1 curie = 3.7 x 1010dps 1 1 . = 3.78 liters L kg = 2.21 the 1 hp = 2.54 x 10 Stu/hr 3 l 1 = 7.48 Density = 62.4 gal. lbs/ft3 1 aw = 3.41 x 106 Stu/hr Deasity = 1 ge/cm3 lin = 2.54 cm - Heat of vaportration = 970 Stu/lom *F = 9/5'C + 32 Heat of fusion = 144 Stu/1ba *C = 5/9 ('F-32)
\ Ag Q 4.7g g 29 fin.Hg. 1 STU = 778 ft-lbf
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- 1. REACTOR PRINCIPLES (7%)-THERMODYNAMIC y .. >
Page 4' *
-(7%) AND p,QJMPONENTS (11%) -(FUNDAMENTALS EXAM)- ..
/i
. QUESTION 1.01 (1.00) l Which.ONE of the following statements is NOT true concerning the Moderator
. Temperature Coefficient:
A. If the Resonance Escape Probability changes faster than the Thermal ; Utilization Factor with a given change in the moderator temperature,.then 4 the Moderator Temperature Coefficient is negative. B. Moderator Temperature Coefficient becomes more negative over-core life due to. decreasing boron concentration and increase in neutron leakage. C. For a given moderator teinperature change, more negative reactivity is inserted when control rods are in the core, versus control rods out of Core.
<D. Moderator Temperature Coefficient becomes less negative as moderator temperature is increased since the Thermal Utilization Factor increases while the Resonance Escape Probability decreases.
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-1. REACTOR PRINCIPLES (7%) THERMQDYNAMILS f Pago 5' d
-(7%) AND COMPONENTS (11%)-(FUNDAMENTALS-F M 1 '
- f. ...
4 1 QUESTION -1.02 (1.00) l 1 Dofine Fuel Temperature Coefficient (FTC) of reactivity. -(A mathematical
~
Gxpression can be used. Indicate Units if a mathematical expression.is-
,y e
utilized). ll: h .!, q L
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- 1. REACTOR PRINCIPLES (7%)-THERMODYNAMICS 'Pags 6 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
QUESTION 1.03 (1.00) Dalayed neutrons play a major role in the operation of-the core because they..
...-(Choose the ONE correct answer) (1.0)
A. are born at_(thermal) slow energy levels (less than 1 ev) and therefore are more apt to cause a fission as compared to being absorbed by a
' poison.
B. are considered as thermal neutrons and therefore they will not travel far enough to leak out of the core. C. are born so much-later than the prompt neutrons and provide controllability during steady state operations and power transients. D. provide 70 percent of the fission neutron inventory and have higher importance factors associated with them as compared to prompt neutrons. l l l r J
)
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- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Peso 7-(7%) AND COMPONENTS (11%)-(FUNDAMENTALS EXAM)
QUESTION 1.04 (1.00) Which ONE of the following descriptions best tupports the reason why Xenon reactivity increases sharply after a trip from 1000 hrs. at 100 percent power? A. Xenon decays less rapidly'due to a reduction in the neutron flux. B. Iodine half-life is much shorter than Xenon half-life. C. Iodine production is greatly reduced and Xenon production is greatly increased due to the reduction in neutron flux. D. Due to reduced neutron absorption Iodine concentration increases, and Xenon decays directly from Iodine, thus Xenon increases. l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
- 1. Page 8 REACIQB PRIN01ELEE_(7%) THERMODYNA_tiLCE L7%) AND COMPONEILTS (11%) (FUNDAMENTALS EXAM)
QUESTION 1.05 (1.00) The DOMINATING EFFECTS on Keff by the control rods are the changes in: (Choose the ONE correct response) A. Resonance escape probability (p) and non-leakage probabilities (Pf and Pth) B. Thermal utilization (f) and non-leakage probabilities (Pf and Pth) C. Resonance escape probability (p) and thermal utilization (f) D. Resonance escape probability (p), thermal utilization (f) and non-leakage probabilities (pf and Pth). (***** CATEGORY l CONTINUED ON NEXT PAGE *****)
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(1. REACTOR PRINCIPLES-(70 THERMODYNAMICS Page '9 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) a QUESTION 1.06 (1.00) Which ONE of the following statements is correct concerning the relationship between the Effective Multiplication Factor and the condition of the reactor. A Suberitical is the condition of the reactor when the Effective Multiplication Factor is greater than one. Bi A reactor with the Effective Multiplication Factor exactly equal to-one is considered critical with an increasing fission rate, C. A supercritical reactor has an Effective Multiplication factor greater 'l than one and a constant fission rate. i D. In a reactor with negative reactivity, the Effective Multipliestion Factor is less than one and this is considered to be suberitical. l l L
)
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l1. 'REAQIQB_2BIEIPLFS (7%) T11ERMODYNatilgE .
.Page 10' (7%) AND_qQMPONENTS (11%) (FUNDAMENTALS EXAM) c QUESTION 1.07 (1.00)
! ^Which ONE of the following statements concerning decay heat is NOT correct: l l . A. The less time a reactor is operated prior to shutdown, less decayLheat is produced since thera .is not as much time to acewnulate long-lived fission products. B. The longer time at power, the more decay heat will be produced.following shutdovn due to increased number of fission products. C. Immediately after shutdown, the decay heat decreases rapidly since.most of the energy is being produced by decay of short lived nuclides. D. Yhe gamma decay of fission productu leads to the release of delayed neutrons and produces decay heat. l l 1
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N b ' REACTOR PRI CIPLES 17%) THEPEODYNAIRGE .. Pego'11' (7%) AND COMPONENTS (11%) f FUNDM4ENTALS EXAM) QUESTION _ 1.06 (1.50)
% at THREE canditions must be.present in' order for Brittle Fracture of the reactora pressure vessel to occur? (Setpoints.not' required).
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-- 1 . ' REACTOR:PRINfdPJES (7%) THERM 0pXNAlfICS -
Page ?.2 c-
-l (7%) AMD COMPONENTSJ11%) (FUNDA M B LS EXAM) '-
r' QUESTION 'i.09 (1'.00) A. . While performing a plant cooldown utilizing the RHR system,'the'1A RRR ! pump becomes air bound. What would be TWO symptoms of an air bound pump, ' AND what would be a symptom.of a pump that'is cavitating that is NOT j aerociated with an air bound pump? { B. What action (s) can be taken to correct the problem of the air bound pump , to restore.RHR cooling, (Assume RHR pump 1B is inoperable) i i i s I 1 i l J 1 (***** CATEGORY 1 CONTINUED ON NEXT FAGE *****) 1 l 1 _ - - - - - _ - - _A
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. 1. - REACTOR PRINCIPLES'-(7%) ' TFiERMOQkN6tq9fG ~ , Page 13' <
w f7%)4AND COMPOFENTS Cli%) 'tTUNIWENTALS EXa$1)'
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' QL'ESTICN. f. ,10 (0.50')..
;Wh$t is the definition of' Nil-Ductility-Transition Temperature (NDTi?-
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A; ' REACTOR _EBINCTPLES l7%) THERMODYNAMICS s Page 14 flX) ANIL COMPONENTS ( 11% LQUEDAMENTALS ~ EK6M.). . = 3 QUESTION 1.11 (1.00) i d
.WHY and HOW (more restrictive or less restrictive) are the RCS operating limit 1
.curven for temperature and pressure during heatup and cGoldown transients i changed over the life'of the plantt
[ F ( * * * * *- C ATEGORY 1 CONTINUED ON NEXT PAGE *****)
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- c. 4LEEACTOR PRIlipNPLES' (IM;THERMODJNAM1CS - Page 15
~
q; H){J AND COMPONENTS (11%) (FUNDAMENTALS FK6dl . l i QUEET1011 1.12 (1.00) ] i Given the following information, CALCULATE the recctor core thermal output in l HEGAWATTS (MW). (Disregald any losses due te SG hlowdown and~RCP heat input, ! Ghow all calculations, round answer to nearest.MW). g Op c 1,3 BTU /1bm - deg'ees
.C/G Pressure : 1050 psig r F
' Steam flowrate.= 12 E6 lbm/hr Tavg 680.5 degreea F T - hot : S03 degrees T Feedwbter temperature 410 degrees F Condenser Pressure 27 inches Hg vacuum E
4 (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
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0,1 REACTOR'PRIN.pIPLES-(7%) THERMODYNAMICS . Pasa.16' (7%~) AND: COMPONEtLTS (11%) f Fll@jMENTAlf EXAM 1
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\ QUESTION 1.13 (1.03) 'I One of'the actions that an operator can take to enhance NATURAL CIRCULATION flow, is to ensure that heat removal matches or exceeds heat'.. generation. State !
FOUR. verifications th6 operator can use to ensure that heat removal matches or l exceeds. heat generation, j o 1
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f.' REACTOR EBlHQIPLES-(7%):? THERMODYNAMICS ~ 0. Page.17 - (
/?%) AND COMPONENTS'(11%)'(FUNDAMENTALS EXAM) l i
L: ,
'e QUESTION 1.14 (1.00) {
i Explain WHY and HOW the Steam Generator Water Level. Control systera uses a j density compensated. signal.as an input.for steam flow. 'j i l 1 1 i a y l
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' REACTOR PRINQIELES_(70 ' THXBtf0 DYNAMIC 5 i
-Page-18 L7%) AND - COfff0EENTS (11%) - (FUNDAMENTALS EXAM 1 -
QUESTION 1.15 (1.50) I Byron Unit 2 'is' doing an RCS heatup using three RCP's. If a fourth RCP in j!
~ mtarted to increare RCS ~ heatup rate, would the motor amps for the running RCPs INGREACE or DECREASE after the RCP is started? (Explain'the reason for this:, '
' change).
)
( i 1 i i (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) 1
15 REACTOR FRINQ1ELES.(7%) THERMODYNAMICS .
~Fago'19 1 I7%) AND COMP 2N.JHIS (113) (FUNDAMENTAL EXAM) 4: , q f, )
l l l l QUESTION 1.16- .(1.00)
' Answer cach of the following questions'concerning operation of centrifugal
. pumps, l A' . - 'In relation to pump discharge pressure, and - systen flowrkh, whai. ydid - f
'be the indications that 1A RHR. pump was operating ih e RUNOUT' condition?. ,
(0,5). i B. What is the major concern with operating a centrifugal pump at SHUTOFF HEAD conditions for an extended length of time? (0,5) i i l l l i I l l l b l l l 1
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- 1. RE&CTOR ?Jfif5HELES (2_U THERMQDYNAtiL9E Page 20- 1
- l (' f7X) AN1 COMPONENTS,(11'4)- (FUNDAMENT $LS'EXAtu i n: ,
l- ,
+ l QUESTION- ' 1.17f (il00).
p Answer the following questiona concerning operation of the-c6ntrifugel ) churging pumps in the CVCS. A. Draw a simplified pump curve representing.two centrifugal-charging pumps j
. operating. Indicate system operating points on the system characterist'ic i curve for'1 pump operating and for 2 pumps operating. (Labels on axis of -(
qurve required, but not specific values). (0.5)' B. Indicate by using a simplified pump curve, how the system operating point changes when the reactor operator shuts FCV-121 slightly with one centrifugal charging pump running. (Labels on axis of curve required,- but not specific values). (0,5) l }z i l 3 i (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
.L REACTOR'PRItiC_1PIjS (7%) THERMODYNAMICS- Page 21 ;
(741 Ai4D- COMPONElfTS (11%) (FUNDAMENTALS E2AM1 1 j QUESTION 1,18 (1.50) J A Special Operating Order was written fer closing of breakers in cafety-related equipment which utilize AR-3 relays. The Special Operating
. Order directs th6 operator to ensure that he/she holds the control switch to ;
CLOSE until the CLOSED indication is received. EXPLAIN WIiY the operator must l do this. (Specific concern with operation of AR-3 relay must be addressed). i l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
'- Paga'22 i 1 ~. ' REACTOR PRINCIPLES (7%) THERMODYNAMICS --
{ 74).:lHU_COMPOH&NTS . (11%) { FUNDAMENTALS EXAM) f
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QUESTION- 1.19 '(1.00) The MSIV discs rotate a few degrees in the plane of the seat during esch clesing stroke. Explain the purpcse of rotating the discs on each closing stroke. (1.0) i I l l s (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) l
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.l rf QUESTION 1021, '
( 1, 50 ) .- 13
* ,- 'thh Main ~Feedwater. System uses a: venturi type restrictor to meceure systen
'l lflowrte. 'WhateTWOl basic principles are ' involved to measure flowrato using a -
J 3r9 venturi' type flok restrictor? 3
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l ' .j ; . ; , . i d; REACTO}t PRINCIPLES iT4_)__I]g@MQJYNAMICS Page-25
,-(7%) AHp_QQMPONENTS (11%F (FUNDAMENTALS EXAM 1 o ,
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- QUESTION -1.22- (1.60) ,
While starting a RCP, you observe motor amps to be' verr highLimmediately foilowing the start, and-then decrease to'a significantly. lower value short,1y ' lafter starting the pump. EXPLAIN WHY motor amps respond like this.
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E d.' REAQIQB FRINCIPLW(7%i TH$RMODYNAMIQS. . a Pago 26. fl%) AND COMPONENTS (11?O -(FUNDAMENTALS' SXAM) , l ..A. /. 1
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- QUESTION' 1.25 '(1.00)
, i Periodically Chemistry will' analyze a sample on the inlet and. outlet-of the, f: . mixed bed; ion exchanger in the letdown system. EXPLAIN the reason Chemi.stry would.need to,cample both the inlet and outlet of the ion exchanger, k
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- 2. EMERGENCY ARD ABliQRMAL PLANT EVOLUTIQEi Pega 2B' f27%) ,3 I
1
- QUESTION- 2 01
. ( 1.00) 1 Sufficient' Shutdown Margin (SDM) is required to control the reactivity' I transient associated with a postulated steam line break.
- a. STATE the Einimum required SDM for normal power operations. j (0.5) .{
; b. How does the operator verifb that this requirement is met during normal j power operation? (0.5) ,
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I
- 2. 'EMERGENCYANDABNORMAL^Pb6HTEVOLUTIONS 'Pago 29 (270 i
I,ro QUESTION 2.02 '2.00) 1 Assume ~that there is a Design Basis High Energy.Line Break inside Containment.
, For the parameters listed below, indicate how each would change.for a Steam ',
Break and LOCA. (Assume all systems in automatic, no automatic trip, no operator action.) (Limit answer to INCREASE, DECREASE, REMAIN THE SAME.)
\
STEAM BREAK LOCA j Rx Power
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L;LQUESTION- ' L 03 (1.00). ,., State the Technical; Specification Safety Limit'and DNB Limitifor RCS Pressure. .
- (1. 0 );
L le t L L l-l- (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i j
__ -.. . _ . _ _ , , _ __ _ _ . . ~ - - . g s.
'2. EMERGENCY'AND ABNORMAL PLANT EVOLUTIONS zPaca-31'
( 274 ),
-QUESTION 2.04' (1.50) o L a. State the TWO primary means of Rx Vessel Head heat removal during l " Natural Circulation Cooldown", ES-0.2. (l'.0)
- b. During Natural Circulation Cooldown, STATE the principal indication of void formation in the Rx vessel head. (0.5)
.i
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) _ _ - - - - _ _ - _ _ _ - _ _ _ _ . _ _ _ _ _ 1
- 2. EMERGENCY AND AB.EORMAL PLANT- EVOLUTIONS Pcgs. 32 i (2781 I
i QUESTION 2.05 -(2.50) ! l
- a. Describe how Main Control Board (MCB) operation of the 1A Essential i Service Water (SX) pump is effected (if at all) if the Local / Remote l switch on the Remote Shutdown Panel (RSDP) is taken to LOCAL. ( 1, 6 )'-
{
- b. Describe how LOCAL control from the RSDP of the 1A SX pump is effected f (if at all) if the control switch on the MCB is in Pull-to-Lock. (0.5)
- c. Assuming that there is a major fire which destroys.the Auxiliary Electric j '
Equipment Room (AEER), describe how vital reactor parameters are monitored. (0.5) - f i
)
1 I 4 (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) f _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ ]
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Pega 33 2, EMERGENCY AND ABNORMAL- PLANT EVOLUTIONS ! s (270 { 1 li l- ,
-QUESTION 2.06 (2.00) ]
State FOUR signals (such as Safety Injection and Phase A)used to l) automatically shut Containment Isolation Valves. (Do NOT. include initiating l conditions such as Low Pressure, High Flow, or High Radiation as part of yvur cnswer.) (SI and Phase A will not be accepted as answers.)- (2.0) I e i- (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i L-_____-_________--____-.
ic .
, 2. ' EMERGENCY- AND ABNORMAL PL@T EVOLUTIONS .-
Paco 34 ; (27%); I l l[ QUESTION. 2.07 ('1.00) u= (1.0) j k'Explainhowalossof'120VACInstrument' Bus 111effectstheESFsystem.
.j 1
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~2. EMERGENCY-ANDABNORMALPLANT" EVOLUTIONS- . Paco 35 127%.1 , ; QUESTION. 2.08 (1.00).
In general, EXPLAIN how the LCO_ Action: statements' differ for one inoperable control rod that is'trippable versus one control rod that is untrippable. (1.0) P .
}
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) )
2, EMFRGENCY AND ABNORMAL PLANT EVOLUTIONS- Page 36-121M QUESTION 2.09 (2.00) { l
- a. Explain why a ruptured SG PORV controller is left in. Automatic when !
isolating flow from the ruptured SG. (0.5) l
- b. Describe THREE methods available to isolate flow from e ruptured SG if the SG PORV will not close using the Manual / Automatic (M/A) control station on the Main Control Board (MCB). (Failing electrical power or Remote Shutdown Panel operations are not acceptable answers.) (1.5)
I 1 l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
> 2. EMERGENCY AND' ABNORMAL'PT, ANT EVOLUT QG Paga'37 (27%)-
i-QUESTION 2.10 12.50)
- a. State TWO reasons for depressuriring the RCS'in BEP-3, " Steam Generator
. Tube Rupture." (1.0)
- b. Describe THREE methods and the order of preferred use.for reducing RCS pressure during BEP-3~, Steam Generator Tube Rupture. (1.5)
{ 1 i (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
- e+ t. ]
'2: EfERG2NCY-AND' ABNORMAL PLANT EVOLUTIQ g -Pero 38 12151:- ?i <
QUESTION 2.11 (1.50)
- a. Explain why. reactor power must be less than or equal to?70 percent when recovering a dropped rod while at power. ( 0.5)
- b. LState which alarm (s) may actuate while zeroing the P/A converter when preparing to recover a control bank dropped rod. (1.0)
[. I i i (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ 1
- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Pcga 39 (27%1 QUESTION 2.12 (2.00)
.a. Briefly EXPLAIN why the DEHC Reference Demand is set at 559 MWe and Load Rate Demand is set at 2000 MW/ min when the reactor is stable at full power. (Step 64 of BGP 100-3, " Power Ascension 5-100 percent.) (1.0)
- b. Refer to attached procedure, " Loss of Heat Sink," BFR-H.1, Briefly EXPLAIN why tha operator goes to BEP-1 if RCS. pressure is less than SG pressure. (Include in your answer how core decay heat 4.s removed with RCS pressure less than SG pressure.) (1.0) l I
4 i i i l'.
- l
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
W - - - - - - ._....: . . _ . . . . . . . . - . - . - . , ,. ( ,. n >. ..
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Que sIiw 3. I1. . La REV. 2A -RESPONSE TO LOSS OF SECONDARY HEAT. SINK -; 1BFR-H.1 ; 1 WOG-l' UNIT 1 STEP ACTION / EXPECTED RESDONSE ~ RESPONSE NOT OSTAlhiED ! I
-l I CAT 7rION If total feed flow is LESS THAN 500 GPM due to operator. action, but total feed flow CAPABILITY.of 500__GM is available, then~this procedure should NE be performed, QUTION
,If wide range level Tn any 3 SGs du LESS THAN 25% ,(60%.FOR ADVERSE CNMT),
or PZR pressure is GREATER 'tHAN OR
- EQUAL TO 2335 PSIG, while performing Steps 1 thru 10, then the RCPs should be tripped and ' Steps 11 thru 16
~) '
should be immediately initiated for bleed and feed. r' CAUTION 3 Feed flow should NOT be reestablished 3 to any faulted SG, if an. intact SG fh2 d is available. O e h: ca...... 4............................... C
- O i: NOTE
- t [d fj With this procedure in effect, CJ
- notify the Station Director who wili *
- evaluate for GSEP conditions per
- BZP 200-A1, BYRON EMERGENCY ACTION d
- LEVELS.
e...a***********.........***.wa ....***** . 1 NECK IT SECONDARY HEAT SINK IS HQUIRE]: .
- a. RCS pressure - GREATER THAN a. GO TO IDEP-1, LOSS OF ANY INTACT SG PRESSURE REACTOR OR SECONDARY COOLAWt, Step 1.
Step continued on next page Page 2 of 31 (0128E/0013E)
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/E. EMERGl'N_E][.jAND_ ABNORMAL PLANT EVOLUTIONS :-
? Pcco 40; ; ,a, (27%)-
- c. l .
t. i.'
-i
., QUESTION .2.15' (2.50) , . ,
- t .
R < e. .Defino the following Technical Specification terms: -(1,0) . 4
, w
,a 1. Controlled Leakage.
F ' 2'. Pressure Boundary Leakage.
- b. -State the following TS' leakage limits: (1.5)
- 1. Pressure: Boundary Leakage. , a
- 2. Unidentified Leakage. . -
3., Reactor-to-secondary Leakage. (No SG isolated)'
- 4. Identified L'eakage.
1 4
- 5. Controlled Leakage. !
o
)
1 I
\
i (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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I'I21 " EMERGENCY AND ADNORMAL PLANQV_OLU"'IOllE 4 Pege 41'
' ' n. , RJ_O. ,
.)
1
. QUESTION 2.14 (1.50) i I
- Exhlain why EACH of the l'ollowing statetaents are correct for_ a ' loss of 'a 125 i VDC ESF Dais:{ Bus.111 or 112). (Consider each case separately.) -(2.'5)
L 1. The reactor must be immediately silut down or tripped. { le j
.2. Only one_ train of ESF equipment will' actuate on a ESF alsneal. ;
i
- 3. Only one kDG will start on an ESF signal. l l
'l
_1* t l (***** CATEGORi 2 CONTINUED ON NEXT PAGE *****)
, = - - _ _ -
3,_ , , , 77 -- 7, , > , : , . , .
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' . LPIgo42
- 2. EMERGENCY AND ABNORMAL PLANT'EVOLUTIQNJSl
.i l 3.121%1 ,
((,;.
;Y. :l; i
..e i
' QUESTION 2.15 .(1'.50) .
Describe the THREE alternate metho's'of d cooling the RCS with'a. loss of-'all.RHR .1 l cooling'in-Mode 4. (Assure Tave-equals 300 degrees Fahrenheit)-(Include- 3 specific flow paths.as applicable) ( 'i . 5 ) . 1 I
.1 1 .~
l: L t. I 1 i T
! 4 fi 1
,i (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
- J
'; 2. EFERGENGL&HD ABNOPMAL PkbMT EVOLUTIONS Page 43 l (27%)
f: QUESTION 2.16 (1.00) l Explain why Rod Control is left in automatic ff the reactor will not manually trip in BFR-S.1, " Response to Nuclear Power Generation /ATWS." (Include in
~
your ancaer the setpoint for switching rod control to manual. ) (1.0) i i (***** CATEGORY 2 CONTINUED ON NEXT PAGE .*****)
2 '. EMERGENCY AND' ABNORMAL PLfET EVOLUTIOMS Pago . 44
'(2720 '
)
.l
' QUESTION' 2.17 (1.00) ,
j A Large Break LOCA or Steamline break inside containment may cadse PZR Level to indicate a Higher Level than.actually exists. Briefly' describe TWO causes for.this false high level indication with a LOCA or steamline break inside {
' containment. .(1.0)
.i 1
.i 1
i
)
4
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l i t I i l l l 1 (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i I
BNORMAL' PLANT.EVOLliTION3 IPage:45
'2 .
EMERQENCY'AND
- c. ,
L27%) :, t
- t. e
- QUESTION 2.18 44,IM4 Aesume that the Unit has experienced a sustained loss of ALL AC. (all othar l- syst. ems sre operating ns designed) Briefly EXPLAIN how reducing RCS temperature and pressure minimizeo/ mitigates RCS inventory loss. (Consider temperature and pressure sepa2:atelir. ) (W O.*)
[ (***** END OF CATEGORY 2 *****)
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;w iPLANTLSYSTEMF_Laghi AND PLANT-WIDE' GENERIC;n ' '
, . Pega .;46 ; ,
;.'lik j, TESPONSIBILITIEjl L191). . ,
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- _ _ . _ . _ . _ _ _ _ . _ _ _ _ _ _ _ . _ . . . _ . _ _ l
_ _ . _ _m...-~._ . _ . . _ . . a, . . . . Page 47-LPLANT SYSTEf1S i33%) AND PLINT-WIDE GENEBlf ~
. RESPONSIBILITIES (10%) !
< l 9
- QUESTION 3.01 (2.50) I l
During a surveillance on the Solid State Protection System (SSPS) Train A, BOTH reactor. trip Bypass Breakers are mistakenly rached-in. '
- a. State TWO control room indications that the NSO has that BOTH trip bypass breakers are racked in. (1.0) i b .. Briefly explain why BOTH trip bypass breakers can NOT be closed from the control room. (Administratively restricted is not an acceptable answer.) ,
(0.5)
- c. .Regarding BOTH trip bypass breakers, describe how the SSPS General !
Warning Circuit generates a reactor trip. (Include in your answer the specific mechanism for opening the trip breakers.) (1.0) f l i L i l l l l l I 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l i
-~~; , - ,. - . _ . . _ _ . . __ 1
~!
, '3; Page'48 PLANT SYSTEMS-(384) AND' PLANT-WIDE GENERIC i' 4
- BESfQJ4SIBILITIES (1041-IQUESTION- 3.02 (1.75)
; Assume the unit is operating at'100 percent power with all control systems in c utomatic. Aissume . BOTH operating Main ' Feedwater Pumps trip off the - line. -(All' 1 'other systems operate ai designed). ,Briefly describe how the following-systems / components ,are effected (if 'at all) by this casualty. Include in
, .your answer the SPECIF.C source of the signal. (1.75) k.' Reactor
- 2. Main Turbine
- 3. AFW Pumps
- 4. SG Blowdown Isolation Valves :
1 1 i i (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
- _ - _ _ _ - _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ - _ _ ___ _ _ _ h
-)
PLANT SYSTEMS (38%) AND PLANT-WIDE GENEFIC Page 49~
, 3 ,~
]!
-RESPONSIBILITIES (10%)
- 4. . -. f 3.03.
' QUESTION ( 3. '50 )
Assume the Unit is in Mode 3 at NO LOAD Tave and experiences trloss of 7 i feedwater to the SGs. (The Startup Feedwater pump tripped). (ITHOUT ANY ; OPERATOR ACTION, describo the events which automatically restore feedwater flow to the SGn. Include in yoitr answer TWO flowpaths which can be used and the' SPECIFIC initiating signals which align / realign the flowpaths. (Consider LONG TERM effects.) (Assume NOsaakeup to CST.) (All other equipmenit operates ao designed.) i 4 I' I (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l'
Ip..;. , - - I' .
- i
.. Pegs 50 t
' 3. . PLANT SYSTEMS'(38%)-ANQ PLANT-WIDE GENERI,G RESPONSIBILITIES (1050 QUESTION 3,04 -(2.00)
In BCA INST-1, " Nuclear Instrumentation Malfunction: . Power Range' Channel. Failure," .(see: attached. procedure) the' operator is directed -to bypass the-
- associated function on the NIS Miscellaneous Control and Indication Panel:
1- Power Mismatch
-, Rod Stop Upper / Lower. Current Comparator
- ' Channel Current Comparator
.Briefly explain the purpose of bypassing each function.
- (2.0)
I I i I (***** CATEGORY 3 CONTIHUED ON NEXT PAGE *****) I 1 - - - _- - __ ___ _ __ - _ __ __ _ _ _ _ _ _ _ , _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___
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REY.-52 NUCLEAR INSTRUMENTATION MALFUNCTION - UNIT 1 PR CHANNEL FAILURE- . INST-1 rE ATTACHMENT A (PG 2 0F 6)
, STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l 1
emene********esene*meneeneaemone*ene*****
- e.
NOTE
~
- If Instrument Bus 114 is rieenergized,*
- then the N1s Miscellaneous Control *
+
- and Indication Panel will be *
- inoperable. Therefore, the following*
- functions will be inoperable: -*
*
- Power mismatch + *
*
- Rod Stop i .
* -
- Upper Current Comphrator .
*
- Lower Current Comparator
*
- Channel Current Comparator
*****semamenemmeeneenmaamme**sema****eene 5 CIEC4 NUM ER 0: POWER RANGE m .,
C 4 ANNE 1S -:AILM );
- a. IF two.PR channels fall.
~
~
- a. IF.one PR channel failed,
) ~THEN bypass the associated functions on the NIS E d the Reactor trips, THEN GO TO 1BEP-0, Miscellaneous Control and . REACTOR TRIP OR SAFETY Indication Panal: INJECTION, htsp 1,.
- Power mismatch IF two PR channsjs fail e Red Stop Ed a Reactor trip is NOT 1
- required, j Upper current comparator
- Lower current comparator THEN refer to Technical
- Channel current ccmparator specifications 3 < 3.1, Table 3.3-1.
- b. Refer to Technical Specification l 3.3.1, Table 3.3-1
- j
?
I I J J l l l I, . - - . - 4 Page 4 of 18 APPROVED (0069E/0006E/042188) M i 01988 B. O. S. R.
~ _ . - , . . .. .
,. . 77.: , , 4 3
' i.1 PLANT SYSTEMS (38%)' AND' liANT-WIDE GENERIC 3'P age l51 )
i; BESZ9NSIBILITIES (10%) ] 1
,-QUESTION 3.05 -(2.25) a ., During a normal reactor stlartup, DESCRIBE the action (s)ithe NSO takes when the following conditions exist and EXPLAIN why this/these action (s)
J is/are taken: N31 1.2 ES CPS . N32 1.3 E5 CPS l
.M35 8 E-10 AMPS i N36 7 E-10 AMPS (Limit your answer to the Nuclear Instrumentation system) (1.,0)
~
,,.b.- :Briefly EXPLAIN how the Source Range. instrumentation system is
. interconnected with the Power Range instrumentation system. (Include, coincidences and setpoints as applicable.). (1.25) l l
l 1 (***** CAT 3 GORY 3 CONTINUED ON NEXT PAGE *****)
-!- j
.i
--_-___.--_:-_-_-c._---____ .__ . - _ .
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- 3. PLANT: @YSIEtfS' (38%) AND PLANT-WIDE GENERIC: ' Phqa 52 ' L RESPONSIBILITIES-(104),
{ a l
. . i ,ro u QUESTION 3.06 @ r00t Assume the Unit is in Mode 5 with all'syst. ems operating as designed. 'l 'Concerning the Boron Dilution Prevention System (BDPS) and using the attached i figure as a guide: ,
- a. STATE'the TIME that automatic actuation of the BDPS occurs. (0.5) l
- b. DESCRIBE- the events that occur erhen automatic actuation initiates.
(Alarms do not need to be-included.) (1.0)
.c._ EXPLAIN hve biwAl w DDP0 c"IcvLo Lhe Svui ce P.cni;;c Lw Li umou bativu . (0.5) i l
I i (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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- 3. Pago 53 l 1)LANT SVJTEMS (38%) AND PLANT-WIDE GENERIC l RESPONSIBILITIES (10%) -
i ! l
-QUESTION 3.07 (2.00)
- a. State FOUR places where RCS water can end up-as it passes through the Excess Letdown line. (Include relief valves as-appropriate in your answer) (1.0) > 1
-b. Briefly 'IXPLAIN why the following pansmeters are effected (as indicated) ,.
by long-term operation of the Excess Letdown system. (Consider Mode 1 ' operation only.) (Consider each case separately.) (1.0)
- 1. RCS activity increases:
1
- 2. Hydrogen in RCS remains constant:
1 l l l (***** CATEGORY 3 COi4TINUED ON NEX.T PAGE ***** ) ;
m a- . . . . . _ . , ._ .. ., , _ _ _ _
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?n.fL S TLANT E STEMS (38%)'AND PLANT-WIDE GENERICi < }j!y > n ),4.. :. h RESPONSIBILITIES _!LLQ11 r ' I-. l
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~
l QUESTION - 3.08 (1.00). .
. fExplcin thelbasis for:the Reactor Containment Fan' Cooler'(RCFC) automatically -
ss hifting to SLOW speed with an ESF actuation signal, (1.0) c ;,
+7 i.
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. . . . . _ _ . _ . _ _ . _ _ . _ _ _ _ ...._.--__.__m_-_--._--_-.. - . . -
Paga 55 1 3; PLANT SISTEMS'(38%) AND FLANT-WIDE GENERIC BESPONSJAlklTIES (1Q%.,1-I
-QUESTION S,09 (2.50) .a. Describe TWO major. hazards associated with Containmeist Recire. Sump pH equal to 3.8 after a large break LOCA (1.0') , j 1
b,- ' Assume the Containment Spray (CS) system has actuated and is operating as 'I designed. Given the following plant conditions' DESCRIBE HOW and WHY the CS system is effected. (No operator action.) (1.5) i Containment Pressure: '12 psig. -] l
- EDGs starting up after a loss of all off-site power. l
-}
l i / 1 i s i i l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
2., ._ _ . . .
)
)
Pago: 56 l 1, PLANT SYSTEMS (38%) AND PLANT-WIDE GENERI_Q RESPONSIBILITIES (10%) ) I h RUESTION 3.10 (1.50) I l Assume that a Normal Containment Purge is in progress. The Containment Purge oystem then receives an ESF signal. EXPLAIN IN DETAIL how(Include the ESF signal in your ) affects the operation of the NORMAL PURGE EXHAUST system. l cnswer ALL cause and effect relationships.) l (1.5) l l i i i
)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Paga 57 ;
BESf0NSIBILITIES S (10%) . QUESTION 3.11 (3.25) Using the attached PZR Level Control Logic diagram, EXPLAIN IN DETAIL the cequence of events which occur when PZR Level Channel I fails HIGH from 100 psrcent power. (Assume no operator action, all control systems in automatic, and the level control switch is selected to the channel indicated in the figure.) (Include setpoints; alarms are not required.) (Continue with j explanation until PZR is stable or a reactor trip occurs.) (3.25) { l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
--c- - - - - - - .
Q ye.;s tY ' 3. l . e;
. AUCT10NttRED Tag .
I M E 8 e 1 .I , fe0 LOA 0 04 6 ave ,._ y%_____.6_______..ph _ _gjg,F CHAASING PUMP STATION
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j _________,_i_,____________s, Livn f a o o o
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*'y/a,'"u, g, L 3 ,g,,3 s .. __________... .
iuva CNA a Satemi .1, , pg _4______q 7_ __ , e u___i___________ ,s____.i_____i,_____________ p_ _ _ _ __q -l8 l ; 1
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8 h 1 [ 1 1 ALL ORlFICE I ISOLATION 8 I A h VALVES CLOSCO l ar-- > 8 , ,, j s a m , I
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l 4 6 <r LETOOWN ISOLATION LETDOW88 UNE ISOLATION
, AUTO MA88UAL CLOSE A4 k M ' $0 g g g0gC0N] y C0erTROL STATICN MIEICE CLeet OPEN CLOS 6 g **"' 0 tes IS T N
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- 3 NEATERS
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LOCAL CO*lT20L OVERRiott ' ' ALL OTMER SISMALS. INTERLOCM LOCAL OvtRftlet ACTUATES (SLOCM ALL ALAAM ist C006 TROL ROOM EXCEPT LOCA.L """ *"""' - =>=="' CONTRCL) i,ct no$tN < , et- oorgy LETDOWit LINE LETDOWN LINE ISCLATION V6LVE ISOLATION VALVE.. LCV-4SS LCV.480 J VALVE VALVE FULL OPEN PULL OPEN , SIS N A L SIGNAL i I l L. . 1 1 FIGURE 14-15 PRESSURIZER LEVEL CONTROL ( REV. O) 1
I'J. 3' PLANT-SYSTEMS (38%) AND PLANT-WIDE GENERIC' Pcga 58.. EgSPONSIBILITIES (10%)- i
, QUESTION .3.12 (0.50)
'To operate a component from the Main. Control Board (MCB), the Local-Remote switch on the Remote Shutdown Panel (RSDP) must be in Remote. Explain the cdditional requirement (s) needed to operate the controller for CV-121, "PZR l level control," from the HCB. '(Limit your' answer to RSDP) '(0.5) l l
l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l
JL_ PLANT ' SYSTEMS ( 38%) ANN PLANT-WIDE GEMEBlf Paso 59 RESPONSIBILITIES (10%) QUESTION 3.13 (1.50) Assuming a normal at-power lineup for 100 - e nt power, DESCRIBE the flow of power to the 125 VDC ESF Bus 111 from it4 dmate power source (i.e., Main
'Gonerator er Ring Bus). List all major components. (Component identification numbers and breakers are not required;.however, bus / component description is required, e.g., 120 VAC Instrument bus.) (A labeled drawing is sufficient.)
R ) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ - _ _ _ _ _
- 3. -PLANT SYSTEMS (38%) AND PLANT-WIDE _ GENERIC Paco 60 RESPONSIBILITIES (10%) ,
%1r QUESTION 3.14 ( ? _50 )-
.For the unit conditions listed below (Left Column), MATCH the automatic action (s) (Right Column) which wi.11 occur for a given condition. (Consider
'ecch case separately). -(More than one answer may be required in Left Column.
Answers may be used more thaa once.)(Assume all equipment operates as docigred.) 41.5-) t' 3,2 r) UNIT CONDITION AUTOMATIC ACTIONS
- 1. UV on 4 KV ESF Bus after A. 4 KV ESF~ bus stripped.
SI is reset. B. EDG start-up.
- 2. UV on 4 KV ESF Bus with SI signal still present. C. EDG close onto 4 KV ESF bus.
- 3. SI after UV on 4 KV ESF D. SI sequential bus loading.
(DG sequencer has timed out.) E. Safe Shutdown (Blackout) sequential loading.
- 4. SI coincident with UV
- on 4 KV ESF bus. F ., SI sequencer reset.
- 5. SI while UV on 4 KV ESF bus G. " Blackout" sequencer reset.
(sequence is in progress.) H. Only RHR and SI pumps start on sequencer. (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
3
- 3. PLANT SYSTEMS (38%) AND PLANT-WTDE GEEEBIQ . Pcge: 61 RESPONSIBILITIES (10%)
-QUESTION 3.15 ~(1.00)
- a. Briefly EXPLAIN why PZR spray flow is reduced'when D-RCP is stopped. .,
(0.5) I
- b. BGP 100-5, " Plant Shutdown and Cooldown," states that if D-RCP is off while depressurizing the RCS, the operator should place the PZR spray valve ~(455B) controller in manual with-zero demand. Explain the basis for shutting the PZR spray valve.(0.5)
I l i l
?
l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) I
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I 3 '. PLANT SYSTEtLQ_(=38%) AND PLANT-WIDE GENERIQ 4
=
F2ga 62 RESPONSIBILITIES (10%) i QUESTION 3.16 (2.25) l (R,pn For the following ECCS pumps, LIST the Shutoff Head, Maximum *Flowrate,.and Dasign Flowrate. (2.25) l
-( Rw+ ) r,, :
Shutoff Head Max Flowrate Design Flowrate (psis) (gpm) (gpm) Osntrifugal ,
' Charging Pump SI Pump RHR Pump 1
l i l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
9 ~ . .,
..~....~.-.--
- 3. PLANT SYSIEMS (363)'AND PLANT-WIDE GENE 81Q POge 63 l
'BKSEQNElalLITIES (10%1 RUESTION 3.17 (2400)
A recent LER Describes a situation where the RER pumps' began cavitating while
" pumping down" the refueling cavity. The reactor head had been . removed with the vessel internals still installed. Cavity water level was being locally !
monitored and remained chove the vessel flange throughout the " pump-down." { EXPLAIN in detail why cavity level was not a good indicator of reactor vessel' water level in this situation. (2.0)
~
l i i i l
)
o (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) i
+.. - - - -
.. f# . D . .' l ', . , Pag 6.64 f
^)J3. ' PLANT SYSTEMS =f30%)-AND PLANT-PIDE GENERLQ. ,
. RESPONSIBILITIES J1041 -:
..o$ , !
1 i
. .j
-QUESTION 3.18- ( 1.50) 1 1
List the sources of' makeup water.to the Essentlul Service Water (SX) Cooling '.
-Towar Basin AND any' automatic and/or control function associated with this.
- source. (1.5) l 1
'l
- 1 1
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7.. ,. . _ . . . _ . . , - . - _ . . . _ ( f. ^. N 3 '[ PLANT SYSTIMS (38hi M g PLANT-WIDE' GENERIC I Foss 65 EESZONSIBILITIES f10%1 i I
'1,
. c .- 1 1
' QUESTION 3.10 (2 06) . , '
. l State.FOUR different Main Control Room indications of s PZR Code' Safety Valve.
J
' that is leaking by. (DO NOT include RCS Makeup or leak 6etection.) (2.0) j l
1 j l 1
- i. .<
1 I ( j i {: 1
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PLANT tiXSTRii8 (380 AND. PLANT-WIDE GENERIC Pace 66 ') RESFQNSIBI_LITIEG f10%J-' , ; j l QUESTION 3.20- (1.00): , 1 1 Orang 6 Dots'are used'.in the Main Control Room to identify unique conditions'. l L 'For an Orange Dot placed'at the discretion of the.NSO, STATE the HAXIMUM time it can be used and what action must be taken.if this tine frame is exceeded. 1 (1.0) ] i 4
. i l
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. I
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- h. PLANT SYSTEMSIf 38%) AND PLANT-WIDE GENERIC Pagn 567' {
j
'{((._m . JQ'b'gDNSI.BILQIES (16pl.
3 l
)
, _ QUESTION- 3.21 (2.00) for BAP 300-1, " Conduct of Operations," the preferred method Of Independent l
_.. Veri'ficationLof proper mystem alignment for safety related components-is by'a-s. 3 sscond qualified individual. L3ST FOUR methods the individual ~ may use to { 1 accomplish independent verification (2.0) :
.]
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l I (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l
- t. .
- 3. ~ Page 66 PLANT SYSTEM 'l380 ANULANT-WIDE GENERIC FISPONSIBILITIES (100 i l
l ]-: l QUESTION 3.20 (1.00) ; Orange Dots are used in the Mnin Control Room to identify unique conditions. For an Orange Det placed at the discretion of the NSG, STATE the MAXIMUM time
$t can be used and what action must be taken if this time frrane is exceeded.
(1.0) Ci B-bb s 1 i 1 I E (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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4 - L-3! -PLANT' SYSTEMS (38%) AND PLANT-WIDE GENERIC' ' Paco 69 11 BEEPONSIBILITIES-- (10%) ,, , 7; , i ' l QUESTION -3.23 (1.00) _
.Per BAP 300-1,-" Shift Operation," describe TWO restrictions on personnel who
.shall:NOT.be included on the Fire Brigade --(1.0) n ,
' t. \
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i I l j 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) t g ...
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7 - - - _ w, - J
. p 3. PLAN.7 SY TEMS ' ( 38% F AND.]&MTrWIDX;RfdiKBlG" . , Para.70'
]
. ll a. BEgfRHSlSILITIES~(10%f ., j G. ,
, ,o.. <
iff,f: e:! . , f , .,) . 7 fl. QUESTION.' 3.24: .(2.50) ' '
; g Ca, State.the power level khen the " Green Board" concept"for ythe Main Control' I
' Room is 'cypl:icable- '(0.5)
- 1 b.' . Describe.tbemeaningof.thefollowinglampcolorsas!they'appi.ytothe
" Green Board":concebt. (2.0) n 1. Green -
l
,/-
- 2. Red -
.y ,
- 3. Blue -
- 4. Amber -
- s. !
I !
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13 '. = PLANT" SYSTEM 6j 384i-AND PLA)TT-WIDE GEN,EE1C- 1-cga 71 l 3 ., - RESPONSIBILITIES (104): 1., , 7;. l o ;l ! i
-QUESTION 3.25 -(2.00) ar . Containment entry in Mode 1 is rcstricted-to a Minimum of _ or . a-Maximum of. _____ personnel. (1,0)
.' b . Explain the basis for the MAXIMUM numbar of personnel,. (1.0). j k
i (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION **********) j heh- a.----_--a. _ . _ , _ _ , . _ _ _ _ _ _ _ . . , _ _ _ , . _ _- _ . _ _
+- = = - = = =
4, p , w a " - -~ a- -~ m..; .*r+:~~ "- " --~ ~ " 9+ -" w +- -- v NM iREACTOR PRINCIPLES (74)1 THERMODYNAMICS Pago. ;7 2...
;i wf7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
#1
;.. ANSWER 1.01- (1.00)-
lD ( 1. 0 ') REFERENCE- - Braidwood Reactor Theory, Chapter 3, Revision'2,.pgs. 13-24; O .Te.rminal Performance Objectives 4-10. 192004K106 :..(KA's) ANSWER i.02 (1.00) .
.9 u
FTC is the change .in reactivity-(0.5) per degree change in effective' fuel'
. temperature. (0,5)'
OR delta rho (in pem) (0.5) 1> 'FTC.= ----------------------------------- i delta fuel temperature (degrees F.) (0.5) I y.
' ' REFERENCE
.. '1 Braidwood Reactor Theory, Chapter 2, Revision 2, pg. 26; Reactor Physics, Chapter 6, Revision'1, pg. 37, Terminal Learning Obj. 11.
192004K102 ..(KA's) ANSWER 1,03 (1.00) C (1.0)
'!REKERENCE I 4 j Braidwood Nuclear Theory, Chapter 7, ' Revision 2, pgs. 20-36. l 192003K107 ..(KA's) .
J
'f i-ANSWER 1.04 (1.00) j
.B (1.0) 4 f
, 1 a
'l
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) i;
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S.gikEACTbR:_ PRINCIPLES (7%) THEBtf0 DIN 62ilGEC . ..
.i. ! Pcca 73 *
-(7%)'AND COMPONENTS 1(11%)' f FUNDAMENTALS EXAM). ~
L REFERENCE
.Braidwood' Reactor Theory, Chapter 4, Revision 2, pgs; 24-28.
'192000h112 ..(KA's)-
" ANSWER. 1.'05 (1.00)- .
'C (1,0)
REFERENCE
'Braidwood Reactor. Theory, Chapter 6, Revision 2, pg. 11, Terminal
-Performance Objective 4.
19200SK107 ..(KA's)' c, ANSWER 1.06 (1.00) D (1.0) J REFERENCE-
.Braidwood Nuclear Theory, Chapter 5,-Revision 2, Pgs. 23-29, j Terminal'-Performance Objective 2. .l 192002K107- ..(KA*s) l u
ANSWER 1.07 (1.00)' D (1.0) [ REFERENCE Braidwood Nuclear Theory, Chapter 3, Revision 2, pgs. 51-54, L. Torrainal Performance Objective 7. 1 192008K127 ..(KA's) (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
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- Poco?74' U
I:e
- (,]f. ) AD COMPONENTS'(114) (FUNDAMENTALS _ EXAM)
N;
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s 1
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i ~. 9' (l'.50) jXANSWERT 1.08 ,, I'
;g i
;(0; 5 each) .s
.j , j
; l '.
- Pre-existing flaw (flaw initiated) .
1 if 3h,; Tensile stress; q
,J y
- 3 . .- Iow temperature j i
' iREFERENCE 6< Braidwood Heat Transfer,l Chapter 6f Revision i', pg. 13,.' Terminal l
.T
. Performance. Objective:2. ;
193010K101 ..-(KA's) g ] .g . a 1 3NSWE'R: .1.09 '(i.00) ~ 4 1
.Sytsptoms:of. air-bound pump'are:
n'. J A . '
- 11. - ~ Reduced-(fluctuating) discharge pressure .
1 i 2. Reduced (fluctuating) capacity .{ 4<- '3. . reduced (fluctuating) amps l
.(any 2,at .25 Sach)' , ,
.j
< Air bound ~ pump does'not have ths noise associated with a"cavitating pump.
j
. ( .25) . , ,
BL Vent (or prime) the' pump (system). (.25) p REFERENCE 1 h Braidwood Fluid Flow Chapter 3, pg. 57. l 193006K108; ,193006K111 ..(KA's) 10 i . ANSWER 1.10 (0.50)
> (0. 5 ) - .
3 ., The temperature of a metal at=which no appreciable deformation occurs prior.to. L failure.
'(Notes' Also accept . . . temperature at which yield stress equals the l H fracture stress . . ., for full credit) ?
y ., , 1 (***** CATEGORY 1 CONTINUED ON NEXT PAGE ****~*) f
yg. =.a. = :a: - y;a y.
, - i g-, .. a- - w.c.: a .x::. ..- .a.::....- :-
;ll .~ . . . .
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h i,BEAQ1QR PRINCIPLES (7%D TJIERHODYNAMICE . .Pego,75. i 121),AND1 COMPONENTS (11%? (FUNDAMENTALS.EXAHF <, 1 REFERENCE Praidwood Heat Transfer, Chapter 6, Revision 2, pg. ~16, 33. 'j
~193010K102 ..(KA's) 1 f
' ANSWER 1.11 (1.00) .
-Buildup of radiation damage in the reactor vessel wall (neutron-induced j embrittlement) (.375) causes the Nil-Ductility Reference Temperature-(RT-NDT) J to increase over core life (causes the reactor precsure vessel to become more brittle).(.375) resulting in the operating limit curves becoming more restrictive (.25)
REFERENCE i Braidwood Heat Transfer, Chapter 6, Revision 2, pg. 29,-Terminal l Performance Objective 5. i 193010K104 ..(KA's) ANSWER 1.12 .(1.00)
~
I (0.5) Q (S/0) = m (delta h) = Q (reactor)
! Q (S/G) = 1.2 E7 lbm/hr (delta h)
.de.lta h = h (steam) - h (feedwater) delta h = 1100.4 BTU /lbm - 385.9 BTU /lbm delta h = 804.5 BTU /1bm (.25) ;
Q-(S/G) = (1.2E7 Ilm/hr) (804.5 BTU /lbm)
= 9.65 E9 BTU /hr in MW = (9.65 E9 BTU /hr)(1 hr/60 min)(.01756 KW/ BTU / min)(1MW/1000KW) t
= 2827 MW (will accept 2813 MW - 2842 MW) (0.25) 1 i
REFERENCE l'
' Steam Tables; Braidwood Heat Transfer, Chapter 7, Revision 3. ;
193007K108 ..(KA's) l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) - _ _ _ _ _ _ _ _ _ _ _ . _ __. O
g , ,o "?.._C..,.,..-..__.a.m_._--._...-_, m 7 W .r ;- , E1 REACTOBJ2INCIPUES (7%) THERMODYNAMICS Pagtt;76 !
' .CUfrL6HD_.QQdEONENTS (11%) (FUNDAMENTALS EXAM) 1 c
I-
' ANSWER 1.13 (1.00) ~j (0.25 each) t
- 1. Verifying use of available heat removal paths..
- 2. Verifying S/G water level is normal.
- 3. Verify a positive temperature difference exists between theLeoro and the i S/G. {
4 !. Verify cold leg temperature constant.(or slightly above) the ctaam temperature. (41s* ace <piklje : RC S ce/J fey f es.p esa fur as . ,y f u Q fg. REFERENCE
* * ## ' *M""'"-
Braidwood Heat Transfer, Chapter 5, Revision 2,'pg. 40. 193008K123 ..(KA's) )
. ANSWER 1.14 (1.00) ;
Since steam density. varies with changing power levels (0.5), the steam' flow-t: oignal also utilizes steam pressure as an input (.25) since density is i proportional to pressure in a saturated systea (.20) j OR Volumetric flowrate is proportional to D/P across flow restrictor (.25) and case flow is proportional to (square root D/P)x(density) (.25). Density is proportional to pressure in saturated system (.25). Therefore, mass flowrate is proportional to (square root D/P)x(Pressure) (.~25) REFERENCE I Braidwood SGWLC System Description, pgs. 18, 21, Terminal i
. Performance' Objective 6. ,'
193006K112 ..(KA's)
.i f
ANSWER 1.15 (1.50) Dscrease (05)
.(The running RCPs are now drawing less. .crent) because they are pumping at less capacity (0.5) since total RCS head increased (0.5) (when the fourth RCP d was started).
I 1 l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
, i
;' l
\
1
. - = . - =m (g; + ,9 3 y. . . u ;7 _ ; w -
i Pcga 77 kh 4 h h 0 R P R I} LQ I E L E S ' ( i %.1: THbRMODYNAMIES i
-(74) AND COMPONENTO Q1%) (FUNDAMENTALS EXAM)- .
7.:4, , , y-
, REFERENCE- '
t :Brcidwood Fluid Flow Chapter 2, Revision 3, pg.-28. 191003K104- ..(KA's) ., t -
- ANSWER 1.16. (1.00.)
9' A. Low discharge pressure . c.ar High flowrrte (flowrate beyond design)- -(0 4 each)- B. Overheating the pump (0.5) REFERENCE Braidwood Fluid Flow, Chapter 2, Revision 3, pgs. 63-69, Terminal Performance Objectives 7, 8. 191004K112 191004K104 ..(KA's) i i AiiSWER 1 17 (1.00) A. d Hoed' 3 Point 1 = operating point for.'1 pump running (0.25) Point 2 = cperating point for 2. pumps 3' running- (O.25) l a Volumetric flowrate l B. % Point 2 indicates system operating point gg after FCV-121 is shut slightly (O.5)
'_I -..___._- _ _ ,
i Volumetric flowrste l l REFERENCE l Braidwood Fluid Flow, Chapter 2, Revision 3, Terminal Performance Objectives 5, 6. 192004K114 ..(KA's) (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) 1 [
. . ; .u,. . . = +. a , .. =. , --- - - -
9ai e .
- 1. REACTOR PRINCIPLES 17k) Tf58tiQDYNAMICE ' Pago 78 L7%) AND COMPQNEN_IS_L1,1%) WUNJAMENTALS E7JW)
ANSWER. 1.18 (1.50) ! i E , , (If.the opergtcor teleases the control switch from the close position to the ! uf ter close p,osition prior to receiving i,he breaker cloud indicatien), then . the AR-3 relay, which carries a high current, {-5) will de-energize (.25). l The-AR-3 relay contacts will then have to break this high current (.5) which j tends to destroy the. contacts. (.25) REFERENCE Byron Special Operating Order S0-ST-0019. 191008K107- 19100GK104 ..(KA's) l ANSWER 1.19 (1.00) The disc will seat in a different position on each closing stroke (0.5) to prevent small imperfections from developing into major problems (0.5). REFERENCE 1 e Sys. Description, Chapter 23, Revision 4, Page 15. 191001K108 ..(KA's) ANSWER 1.20 n so( % ff,, 1/.,-/MY b' n n.,A ao
#ek! dutle La#*t 4(A i
6 ., LOWDOWN-is thm differcuvo Lotwcca Oct=1 popning open era--ur: of the ::fety 3 #/ lyc aiid ovLual tumuoLing prc ure. -tfML) REFERENCE Sye. Dcactivtivu bessvu l'len, Chapter 23, Revision !., P;ge 17. [# -101001"101 . . ( K!. ' : ) p., . , sj _ j_ /,, f. ,/ l ANSWER 1.21 (1.50)
- 1. When the fluid flows through the venturi (restriction) a drop in pressure and a simultaneous increase in velocity will occur. (0.75)
- 2. The change in pressure created by the restriction is proportional to flow (squared). (0.75)
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
.,w .. . . . .....w....a:m-.~..a .+. w .--...+ ,
g - - - - - - - - - - - at e i< j
,s ,
I l 1 ^/1' . REACTOR PRINCIPLES'(7%) THERMQDYNAMIOS- ' ' Pega 79' b J7%) AND COMPONENTS (114) f FUNDA%ERT&f; EXAMi i i
? REFERENCE !
Brcidwood I&C, Chapter 1, pcs, 22, 23, Terminai Performance' ! tObjrctive 12. :i 191002K105 ...(KA's) { ANSWER 1.22 ( 1~. 50 ) - a { l Ths RCP requires a starting current (0.5) to start the pump and its motor' rotating'(overcome rotational inertia of rotating assembly) (0.5)'which is additional to the rinfrent required for actually pumping the fluid (0.5). 1 I REFERENCE Braidwood Fluid Flow, Chapter 2, Revision 3, pg. 63, Terminal Performance Objective 9. 191005K105 ..(KA's) !
)
ANSWER 1.23 (1.00). To determine activity levels of-both inlet and outlet of the ion exchanger
'(.125) in order to determine the decontamination factor (DF) of the ion q exchanger (.125) which in used in determining the ion exchanger j officiency (0.75). 4 REFERENCE Braidwood Chemistry, Chapter 6, Revision 4, pgs. 29-33.
191007K103 ..(KA's) j l (***** END OF CATEGORY 1 *****)
, , _. - ~ . , - - - .. -, - - - - - --- --
,7 1 -c y l .. .
, . .-4 ' ! ..
4
- 2. EMERGENCY-AND' ABNORMAL PLANT EVOLUTIONS T :Paga.805 f ..
(27%) , E
'm ,
p L
.l. ,[
' ]
ANSWER 2,01 (1.00) l a .- Greater than or equal to '1.'S percent dK/K. (0,5) l
' b'. - Control rods are above Insertion Limits. _
(0.5)- ,
' REFERENCE
.l lTS:3;1.1.1, 3.1.3.6, 000040K105 ,,.(KA"s) ;
i ANSWER. 2.02 42,001- /, fo
, , 4
'.'d i o.
STEld BREAM LOCA Rx. Power Increase Ssas M r.trinreat-Raatr.t4.on - 'c~~ _-
. J,n ca.e u e - p + l.;,d oc[
'] 1 Stocm Line Pressure Decrease' Same l
. ircadwater Flow Increase -Same
..(0 25) each REFERENCE .
BEP-0, Revision 2A. BEP-2, Revision 2. 000040A203 ..(KA's)
< ANSWER t. 0 3 (1.00) l 0 Safety Limit: not to exceed 2735 psig (2750 psia). (0.5) .f DNB Limit: greater than or equal to 2219 psig (2234 psia). (0.5) ]
' REFERENCE TS 2.1,2, 3.2.5.a.
000027A204 ..(KA's) i (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i 3 _ _ . _ - - - . _ l
C- y 7, , . .. , , -~. y q; , z u, a Pago 81 QM EMEFXiENCY! AND ABNOBtMh,_ PLANT Ey.QLD.IlQHE
,(f,1 n .
t , y 'i" . l ANSWER l2.04- f 1.' 50 ) : k[ a, (1) CRDM fans. ' (0. 5 )' ll :(2) Lossee.Lto ambient. .(0.5) ~, b; Large PZR level variations (level indication becc'.nes erratic) . (0.5)
- o u 4l *AL : Av115 (.>vTif c.uuaw 12 Ja,e in accorbses witf AE/ gg
" M* L e-/ c ;ra.. / fa, w;;ftpa,y,,j;,,y,g,j(y9,gyggyel -
=BEP ES-0.2, Revision 2, Step 14.
'BEP ES-0.2 Lesson Plan, Section VI, Chapter 1-(Page.11.of 225).
000055A202 000015K101 - . . ( KA ' s ) ' q l'fL LANSWER- 2.05 (2.50) a .' 'All control (0.5)-and indication (0.E) from the MCB is lost. (0,5)
-b. Operation f rom time RSDP is not effected (0,5) (provided the component still har., power).
e 'e. :Belected parameters are monitored from the Fire Hazards Control Panel. (FHCP) (0.5)
' REFEREtiCE -
.Brai'dwood Sys Description, Chapter 62, Revision 2, Pages 9, 17.
000068A121 ..(KA's)
- ANSWER 2.06 -(2.00)
Phase B Containment Ventilation Isolation
. Main Steamline Isolation Feodwater Isolation (0.5) each j REFEREhCE TS 3.6.3, Table 3.6-1 000069A2C1 ..(KA's)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
y.. . . _ . .__. __~._,_ . . _ - L, i
- 2. EMERGENCY AND ABNORMAL PLANT 4 EVOLUTIONS P:ga:82-L27%)
.i ANSWER 2.07 (1.00)
~ Loss of Instrument Bus ill will disable (0.5) automatic actuation'(of Train A) of ESF equipment. (0,5)
REFERENCE BOA-ELEC-2, Revision 54, Notes, Step 1. Sys. Description, Revision 3, Chapter 61, Page 48. 000057A219 .e (KA's) i ANSWER 2.08 (1.00) The trippable rod Action statement allows continued power operation (0.5) while the untrippable rod Action statement requires a shutdown (0.5.). REFERENCE TS 3.1.3.1 000005G003 . . (KA's) ANSWER 2.09 (2.00)
- m. Prevent lifting SG code safety valves (which are unisclable.) (0.5)
- b. 1. (Fast) close the SG PORV using the Auto-Close' switch on the HCB.
(0.5)
- 2. Locally close the SG PORV isolation valve (MS-19). (0.5)
- 3. Remote Manual Operation of the SG PORV with hand pump. (0.5)
-REFERENCE Sys. Description, Chapter 23,. Revision 4, Pages 13, 32-34.
BEP-3, Revision 2B, Step 3. BEP-3 Lesson Plan, Revision 7, Section III, Page 19 of 153. 000038K302 . . (KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i.-
cn wg
- 2 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS PacaJ83 1- (270' ,,
' ANSWER 2.10 (2.50)
- c. 1. -Reduce Leak rate. (0.5)
- 2. Refill the PZR. '(10.5)
- b. First -
Normal PZR spray (0.4)
-Second -
PORV. (0.4) Third -
. Aux spray (0.4)
(0.3 for order of preference) REFERENCE BEP-3, Revision 2B,. Steps 16, 17. 000038K301 ..(KA's) ANSWER 2.11 (1.50) l
- s. To prevent reactor power from exceeding 90 percent while recovering the
; rod. (0.5) ,
- b. Rod Bank Lo Insertion Limit. (0.5)
Rod Bank Lo-Lo Insertion Limit (0.5)
. REFERENCE 1
. BOA ROD-4 Lesson Plan, Revision 4, Page 7 of 17, 11 of 17. l 000003K304 ..(KA's)
ANSWER H2.12 (2.00) j e. To establish appropriate plant conditions (0.5) for response to a' loss of ! MFP. -(10,5)
- b. SG no longer acts as a heat sink (At is a heat source).(0.5)
Core decay heat is removed by RCS break flow. (0.5) REFERENCE. ! l BGP 100-3, Revision 53B, Step 64 i BFR-H.1, Revision 2A, Step 1. i L BwFR-H.1 Lesson Plan, Revision 0, Page 11 of 109. 000054K304 ..(KA's) i
.i
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l \
- _ _ _ _ - _ - _ i
.. n _._.__._.____._a. . = = _ . . _ = = .
l 2. EHERGENCi~AND ABNORMAL' PLANT EVOLUTIONS Paso:84 (27%) f i- . ANSWER 2.13 (2.50)
- n. 1. Controlled Leakage shall be that seal water flow to the.RCP seals.
(0,5)
- 2. Pressure Boundary Leakage shall be leakage through a nonisolable fault in a RCS component body, pipe wall, cur vessel wall (except SG tube leakage). (0.5)
- b. 1. None. (0.25) ,
- 2. 1 gpm. (0.25) 3, 1 gpm total to eill SGs (0.25) AND 500 gal / day through any one SG.
(0.25)
- 4. 10 gpm. (0.25)
- 5. 40 gpm. (0.25) l REFERENCE j l
TS 1.8, 1.22, 3.4.6.2. 000009K320 ..(KA's) l ANSWER 2.14 (1.50)
- 1. SG FRV fail shut. (0.5)
- 2. Control power is lost to circuit breakers for ESF equipment. (0,5)
- 3. Control power for EDG is lost. (No power to starting air solenoids.)
(0.5) ! REFERENCE 5'n . Desa,; p isk., faa.3,ct.p/*4$py.48. Sys. Description, Revision 2, Chapter 8a, Page 22. 0000b8A203 ..(KA's) 1 (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
r -r i2. EMEBQKtLQY AND ABNORMAL.JLANT EVOLUTIONS Paco 85 j (27%)
; ANSWER 2.15 (1.50)
- 1. Steaming intact /nonisolated SG(s). (0.5) 2 '. Bleed and Feed of RCS using Excess Letdown (through Loop Draina) and charging. (0.5)
- 3. Bleed and Feed of RCS using PZR PORV(s) and charging. (0.5)-
REFERENCE i I BOA-PRI-10, Revision 52, Step 5. l 000025K101 ..(KA's) ANSWER 2.16 (1.00) In automatic, rods may insert faster (up to 72 SPM based on temperature aisnal) than manual control. (0.5) Rods are shifted to manual when the temperature error signal is less than 48 SPM. (0.5) REFERENCE BFR-5.1, Revision 2, Step 1. 000029K310 ..(KA's) i ANSWER 2.17 (1.00)
- 1. Reference Leg heating (0.5)
- 2. Secondary transducer (strain gauge) will heatup. (0.5)-
REFERENCE Sys. Description, Revision 6, Chapter 14, Page 67. 000028A202 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
^
' 2.
-EMERGENCY AN'D' ABNORMAL PLANT EVOLUTIONS PasaL86 -
'(27%) -t- -
I 1 l.co' ANSWER 2.18 (1.50) j f Temperature - minimizes RCP seal degradation. (0.5) Prassure - reduce RCP seal leakage. (0.5) injcct CI ::cr uliters. 10. 5 ): pt/e fe.d REFERENCE BCA-0.0 Lesson Plan, Revision 0, Page 9 of 205. 000056K302 ..(KA's) i (***** END OF CATEGORY 2 *****) l
]
i.,d.
' PLANT SYSTENS (38%) Mp PLANT-WIDE GENERIC Pega 67 RESPONSIBILITIES (104)
ANSWER 3.101 (2.50)
- a. 1. Reactor Trip Bypass Breaker indicating lights. j; z(0.5)
- 2. Bypass Breaker Racked-in annunciator to alarm. (0.5)
- b. Switch on control board prevents closing both breakers at once. (0.5)
- c. Both bypass Dreakers being closed (0.5) will deenergize the U? coils.
(0.S) REFERENCE Sys. Description, Revision 1, Chapter 60a, Page 15. Chapter 60a Leacon Plan, Revision 0, Page 18 of 22. 001000K603 ..(KA's) ANSWER 3.02 (1.75)
- 1. Reactor: tripped (.25) on Lo-Lo SG 1evel. (.25)
- 2. Main Turbine: tripped (.25) on reactor trip / turbine trip (P-4). ( 25)
- 3. AFW pumps: both automatically started (.25) on Lo-Lo SG 1evel. (.25)
- 4. Blowdown Isolation Valves: no effect (.25)
REFERENCE Sys. Descript. ion, Revision 4, Chapter 26, Page 53; - Chapter 27, Page 40; Chapter 60b, Page 22 059000K302 059000K303 059000K304 ..(KA's) l t 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
Lh *
- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 88 RESPONSIBILITIES (10%) .
ANSWER 3.03 (3.50)
'Lo-Lo SG 1evel (.5) will' auto start both AFW pumps. (0.5)
Feedwaterwillbesupplied'fromCST(0.5)throughtheAFWfumpstotheSGs. Without a source of makeup water, the CST will eventually lose level'and-the AFW pumps will develop low suction pressure. (0.5) AFW SX suction valve will automatically open (0.5) ns low AFW pump suction-pressure (14.1 psig/1.22 in. Hg. VAC) (0.25) coincicent with Lo-Lo SG 1evel (2/4 on.1 SG) (.25) and supply SGs from ESW. (0.5)
-REFERENCE Sys. Description, Revision 4, Chapter 26, Pages 39, 41. . 061000K402 ..(KA's) s ANSWER 3.04 (2.00)
Power Mismatch: removes failed power range chtunel from auctioneered circuit. (0.5) Rod.Stop: removes failed channel from Overpower Rod Stop. (0.5) Upper / Lower Current Comparator: removes failed detector'from comparator circuit alarm (QPTR). (0.5) Channel Current Comparator: removes failed channel from comparator circuit alarm. (0.5) REFERENCE Sys. Description, Revision 2, Chapter 33, Pages 18, 23, 24. BOA INST-1, Revision 52, Step 5. BOA INST-1 Lesson Plan, Revision 4, Page 9 of 35. 015000A201 ..(KA's) l' l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) . l n - - _ _ - - a
~
- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC 'Page 89 RESPONSIBILITIES (10%)
ANSWER 3.05 (2.25)
- a. Wh-n av-=+-* ther P-A /1/? TP rectcr then 1 2 10 --yo) (.25) the MSO
-ble:ks (.25) CR Ili "cits eud SR "i Fla. .mectcr trip. (.203 Thio im dvue to prevent pessibic dcacg; (octuratien) te the 3R Jotccta=
(.25) { &c < sA is e t.as & SK Hoy4 G'luv Y;,) .,/ M i es- c.M) tap %
/94.. A t o.r ) ./ ,, r, #E /-a . (a,r)
- b. When 2/4 PR (.25) are greater than 10 percent (.25) (P-10) SR Hi Volts
(.25) and SR Hi Flux reactor trip (.25) are automatically deenergized. (blocked) (.25) REFERENCE Sys. Description, Revision 3, Chapter 31, Pages 46, 48, 53. 7 015000K407 015000G001 ..(KA's) ANSFER 3.G6 ( ? . 00 ) -(1, s u )
, n. T = 14 (0.5)
- b. RWST supply valves to charging pump suction open.(LCV 112D and E) (0.5)
VCT supply valves to charging pummp suction shuts. (LCV 112B and C) (0.5)
-c. SP bccc;cs incicrctic. --( 0. 5 L REFERENCE a Sys. Description, Revision 3, Chapter 31, Page 47.
015000A107 015000G004 ..(KA's) ANSWER 3.07 (2.00)
- a. 1. PRT (via relief path)
- 2. RCDT
- 3. VCT-(via relief path)
- 4. Charging pump suction (.25 each)
- b. 1. RCS activity increases: CVCS demineralizers are bypassed. (0.5)
- 2. H2 remains the same: RCP seal water return is shifted to top of VCT. (0.5)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
..x . _ , . , . - . . -
e 2
- 3. PLANT SYSTEMS'(38%i AND P5 ANT-WIDE GENERIC Page 90
. RESPONSIBILITIES (191).
, REFERENCE
?Sys. Description, Revision 7, Chapter 15a, Pages 43, 74.
004000G007 ..(KA's) ANSWER 3.08 (l'.00) Proventoverloadingthe-coobaher- e carecity-of the RCFC (0.5) due to increased
; containment' air density following a LOCA. (0,5) j REFERENCE
- O* ##" ""/ U '""1 Iyj ar Sb/rs/sbra ca d h Sys. Description, Revision 2, Chapter 42, Page 39.
022000G007. ..(KA's) ANSWER 3.09 (2.50)
- a. 1.
aejfe With sump pH bes_c (less'than 7.0), iodine is less water soluble and will come out of solution'(0.5) (Iodine may leak to outside environment.)
- 2. Sump and associated ECCS component more susceptible to ~- 4'-
-::urtle et see- corrosion (0. 5) (Component may fail due to corrosion.)
- b. The containment spray system will restart t#.5) on the EDG sequencer.
(0.5)- TheCSactuationsignalisthrougharetentivememorylog(ccircuit(0.5) (and is not effected by a loss of power). (CS actuation signal must be manually reset.) og c n /,; ,,,,y g , ,,, ,,; ,, , s, y (, g) ,, pg,, ,pg ,,p _ ,,, (,7 y REFERENCE ske.e. 4 e, jj, f j TS 3.6.2.2. . Sys. Description, Revision 3, Chapter 59, Pages 5, 38, and Figure 59-2;. Chapter 61, Page 59. 026000K402 026000A301 ..(KA's) I ANSWER 3.10 (1.50) ESF signal trips shut (.25) the Containment Isolation Valves. (.25) Purge Exhaust Fan trips (.25) when Containment Isolation Valves (VQ002A/B) shut. (.25) Purge Exhaust Fan damper (VQ04Y) trips shut (.25) when fan trips. (.25) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l l.
. . ...__....__.c.. _._.-.-._._2. _ _ . . 1 . 3;' PLANT SYSTEMS (38%)'AND PLANT-WIDE GENERIC Paga.91 EEEPONSIBILITIES (10%) REFERENCE
'Sya. Description, Revision 2, Chapter 42, Pages 45, 46. 1 029000K103 ..(KA's)
ANSWER 3.11 (3.25) Charging flow to minimum. (.25) All~PZR heaters on (.25) from + 5 percent high deviation. (.25) PZR level actually lower. (.25) At 17 percent (.25): all orifice isolation valves shut. (.25) letdown isolation valve 460 shut. (.25) turn off.all PZR heaters. (.25) PZR leve1' increases due to letdown isolation. (.25) At 17 percent (.25) PZR-tackup heater re-energizes. (.25)
. At 92 percent (.25) reactor trip. (.25)
REFERENCE Sya. Description,. Revision 6, Chapter 14, Page 61 and Figure 14-15. 011000A210 011000K405 ..(KA's) ANSWER 3.12 (0.50)
.The Auto-Manual switch on the RSDP must be in Auto. (0.5)
REFERENCE l Syo. Description, Revision 2, Chapter 62, Page 25. 011000A401 ..(KA's) i ANSWER 3.13 (1.50) 345 KV ring bus. (.25) SAT 345 KV/4 KV x-former (.25) 4 KV ESF bus (.25) 4 KV/480 VAC x-former (.25) 480 VAC ESF bus (.25) Battery Charger (to 125 VDC ESF Bus 111) (.25) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
. .....--.--..-.--:w:- ----,-u - - - -- - - , = - - --:--- - - - - - - - - -
[ PLANT SYSTEMS 138%) AND PLANT-WIDE GENERIQ.' Pcco-92? ,0[3i EgSPONSIBILITIES-(10%) l REFERENCE
.Syo. Description, Revision 4, Chapter 4, Pages 50, 89, and Fi;gure 4-2..
062000K103 ..(KA's)
- 3. 2 F fANSWER. 3.14 FS-60-)
.1 . . A, Y C, E. ( T4 r. en.);,4i& w;// J r e e e Ne- cr*A* ar Af " $6d $
$<. le.adi7 a '%l 2.- A, C,-D.;
- 3. H.
4.- A, B, C, D.
' 5.. G, D. (.25 pts. each)
-REFERENCE Syn. Description, Revision 4, Chapter 4, Page'42.
Sya. Description. Revision 4 3 Chapter 9, Page 63. Sys. Description, Revision 3,. Chapter 61, Pages 43-47. 064000K410 064000K411 '..(KA's) l ANSWER 3.15 (1.00)
- a. With D-RCP stopped, there is less D/P across the reactor vessel. -
(0.5) ~ h esu (0.5)
- b. This is done to prevent backflow the idle sprey line.
REFERENCE ! Sys. Description, Revision 6, Chapter 14, Page 64. BGP 100-5, rev.5, step 28..b j 010000K103 ..(KA's) i 1 l 1 l i, (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) ) i i
, ..._m . . - _ . . _ - - . . ; i
- 3 . PLANT SYSTEMS (38%) AND PLANT-WIDE' GENERIC Paga'93' RESPQHEIBILITIES (10%) ,
m '! i
< ANSWER 3.16- (2.25) }
? Shutoff. Head. Max Flowrate Design Flowrate (psig) (gPm) (gym) -
' Centrifugal-Charging Pump 2600 550 150 SI~Pcmp 1500 650 400 RHR. Pump. 200 5000 3000
(.25 each) REFERENCE Sys. Description, Revision 8, Chapter 58, Page 88. 006030K603 . .'( KA' s ) i ANSWER 3.17 (2.00)' In this situation, the only flow path to drain the cavity ^1s through the l by-pass flow holes in the upper core barrel flange. (1.0)
.Vossel? level was not hydraulically coupled with the cavity and-could not be determined by observing cavity level (1.0) i 1
REFERENCE Sys. Description, Revision 3, Chapter 20, Page 21 and Figure 101-10. syn. Description, Revision 5, Chapter 11, Page<8. LER 50-454/88-007. 1 005000K307 ..(KA's) i ANSWER- 3.18 (1.50) Circulating' Water System Makeup (.25). Basin level control (.25). l SX Makeup Pumps (.25). Automatic startup on Lo Lo SX Basin level (.25). Deep Well Pumps (.25). Basin level control (.25). l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
., u.- . _ . . . . _ . . . _ _ . _ . . . _ .... _ . .. _-
)
{ t
% PIANT SYSTI@_(.33#1 A@LELANT WID]LGENERIG Paga 94' f
, RESPONSIBILITIES (10%).
REEERENCE l UFSAR, Revision 6/88, Section 9.2.5. BOP SX-12, Revision 2, SX-T2, Revision 1. LER 50-454/86003, 50-455/87003. . 076000K125 ..(KA's) ANSWER 3.19 (2.00) v. O e c re. as in fcspressw o (defeuddy ou l canis <)
- 1. PRT Level High.
- 2. PRT Temperature High. j
- 3. PRT Pressure High.
- 4. PZR Safety Valve Discharge high temperature (0.5 each)Meagr /,wr. I REFERENCE Bys. Description, Revision 6, Chapter 14, Pages 35-38.
007000A410 ..(KA's) 14 l t 3
. ANSWER 3.20 (1.00) j i
Maximum time is 1 day. (0.5) Rapiece dot with Caution Card (if condition is expected to exist for more than 1 day). (0.5) REFERENCE BAP 300-1, Revision 1, Step C.2.b.17. ' 194001K102 ..(KA's) 1 ' l ANSWER 3.21 (2.00) 1 J
- 1. Observation of control room indicators.
- 2. Observation of ESD Panel indications. ,
- 3. Observation of position indicators or status lights. l
- 4. Field verification of equipment alignment. 3 of l (0.5 cach) %dpda.) ycrifka bku a f rysfea lin.e y s A <= W j i )
i i 4 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) i e
~ ' '
% My * ' 4 :V >
$% Y c ' '
^'
n.
^
f3P? PLANT SY!i1E19.(38%)-AND PLANT-WIDE GENERIO < Page 95-4 RESPONSIBILITIES (10%l: 1- . g .
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? I
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REFERENCE J r,, x j j (' J BAP 300-1, Revision 1, Step C.3.v. s' 194001K101: ..'(KA's) , ') l , b
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. ANSWER 3.22 (1.50)l 1 i
Maximum of 5 starts (.5) within 1 minute (.5) followed by a minimum 3D minute
, cooling off time (.5). '
~!
1 REFERENCE , 3
.BAP 300-1, Revision 1, Step C.3 a.
- 194001K107 ..(KA's)
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-ANSWER 3.23 ('1. 00 ) , , , s
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. 1. Personnel required in control room. M', Sfff--=' /36#,(0.5)
- z. Personnel necessary for the safe shutdown of the unit. (0.5) og REFERENCE j,.T h f,'<< Driy & wgdwJh & f .
I BAP 300-1, Revision 1, Step 3.C.q. +4* Sc#E w.. / 3 % i ff, j,4. ,/H/ eru 1 0 K1 . 's) e
~Y ' " N"N**" *b N *"Y L A*y ps wa./ <<su,*,ac/ 6, Aw agu.);u / I "AN5WER. 3.24 (2.50) N ' * "' NE '
- a. Greater than or equal to 30 percent. (0.5) 1
- b. 1. Green -
normal configuration. (0. 5 )'
- 2. Red -
abnormal configuration. (0,5)
- 3. Blue - rotating equipment is not running and is a backup.(0,5)
- 4. Amber -
tripped condition. (0.5) i REFERENCE BAP 380-1, Revision 5. 194001K101 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) 1 i A__.-.__.______..._
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- n. Minimum ~of 2. '(0.5) r Maximum.of,30. < (O.5)
- b. To ensure thsi, 615 personn61 wili ^be 'able to leave containment in one.
. cycling of the air-lock if required.
-( 1. 0 ) -
l REFERENCE f BAP 1450-1, Rev'ision 11. 194001K105 ..-(KA's)- 9.7 e i f
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(*****.END OF CATEGORY 3 *****) ' (********** END OF EXAMINATION **********) P l' O. w _ ____ __ - _- _ _ ._ _
pp 4 ,:!,, . - ~
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; U..S.JNUCLEAR REGULATORY' COMMISSION SENIOR REACTOR OPERATOR ' LICENSE EXAMINATION MRON '
FACILITY: REACTOR TYPE: EHB-EEC4 1 DATE ADMINISTERED: 822B1409 ___ w
.dh 7 e s.gJ n e.-
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Write answers on one side only. Stople questi .e sheet cn top of the E.n sw e r shosts.- Points f or --ach k qucetaca cre indicated in parenthe.ses after the queci. ion. The paa. ring { ctade requirve at Ietst 70% in eacb cat,egory and a final grade of at lene: 80% Exceniaatica papen, will be picked up aix (0) hours after . J the examination stars.
% CF
, CATEGokY % OF CANDIDATE'S CATEGORY ;
J VbLUE_ .lOI6L .___Sp@ E _VALUE -06IfELOBX_ _ H o' 6 _.a3 0n a": 4 . 0 0 4. F.EACTOR PRINCIPLES (7%) - i
, THERMCD7NAMIC2 (7%) AND l COMPONENTS (10%) (FUNDAMENTALS EXAld) ;
i I k; __3 5_ ._0 0 33.00 5. EMERC3NCY AND AENORMAL PLANT ; I J[ EVOLUTIONS (33%) f . 43.02___ 43 00 ___ _ 6. PLANT SYSTEMS (30%) AND FLANT-WTDE GENER]C RESFONL 3ILITIES (13%) 100 9_ __
% TOTALS FINAL GEADE l
.o All wcrL done on this examinsticn is my own. I have neither given nor rer. 31vc 3 ai J . i' \ i ___ ._ ______ h; Candidate' c Signature i I a
'f I
1 l l I l I __ - _ _ - _ - - - _ _ -- _ E
_ _ . . _ , m . ._ _ ___ _ ._- -- 1 i NRC. RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this exay.ination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination 1 room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
l
- 4. Print your name in the blank provided on the cover sheet of the j
) examination. i f
- 5. Fill in the date on the cover sheet of the examination (if necessary). {
i
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet. o
- 6. Consecutively number each answer sheet, write "End of Ce.tegory __" as appropriate, start each category on a new page, write only on one side of the papor, and write '"Last Page" on the last answer sheet.
9,. Number each answer as to category and number, for example, 1.4, 6. 3,
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer ats face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
i
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required. i
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PAP.TS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
17 You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in complet3ng the examination. This must be done after the examination has been completed. 1
.38. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top. (2) Exam aids - figures, tables, etc. l (3) Answer pages including figures which are part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the exaruination questions.
Turn in all scrap paper and the balance of the paper that you did i c. not use for answering the questions. l
- d. Leave the examination area, as defined by the examiner. If after !
leaving, you are found in this area while the examination is still i in progress, your license may be denied or revoked. l l 4 l 1 l l 1
)
I l I i i l I _ _ _ _ _ _ _ _ _ _ _ . _ __ __ a
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. __-______ ____ o ____ ;
yp T T W supp1ted 'l 2. Eo pAV pAVg =pAv 222 3 A = KA J SP p 5 = KA Q M = KA ST M = KA op J 6P x nc AT (ir.) - oT (out) th AT- - < - - - - - - - - - - - - - - - - - m G = -f ------- 9 AT (in) 8.Bx10 In (----~~-<-> 3 AT (out) { Gr" , kAoT T -T = --- Q = ----- i cl ps ox 4k
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/ SGD18Il0N_GdQ_GUEdlSI6X EQBdukeS:-
R/hr = 6CE/d Iy = IO' 1 {=C22 n -Gt-rG .G
- Qll.WilQQ_dat2 I = 1 "
O Volume 0'10
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A=A O e A = AN
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CONME831QUS'
.1 gm/cm = 62.4 lbm/ft Density of water (20 C) = 62.4 lbm/ft 1 gal = 0.345 8bm 23 1: ft = 7.48 cal ' Avogadro's Number = 6.023 x 10 1 gal = 3.78 litars Heat of Vapor (H O)'= 970 Btu /lbm 2
i lbm.= 454 grams Heat of Fusion (ICE) = 144 Btu /lbm-
~
e = 2.72 1 AMU = 1.66 x 10 . grams n is 3.14159 Mass of Neutron = 1.000665 AMU 1 KW = 738.ft-lbf/sec Mass of Proton = 1.007277 AMU I 1 KW =.3413 *Jtu/hr. Mass'of Electron = 0.000549 AMU n 1 HP = 560-ft-lbf/sec One atmosphere e 14.7 psia = 29.92-in. Hg 1 HP = .746 KW
- F = 9/5 *C + 32 1 HP = 2545 Btu /hr *C = 5/9 (*F - 32) i 1 Btu = 778 ft-lbf ' R =
- F + 460 6 'K = 'C + 273 1 MEV.= 1.54 x 10 Stu h = 4.13 x 10~ M-sec L 10 1 W = 3.12 x 10 fissions /sec
'i g n 32.2 lbm-ft/lbf-sec c = 931 MEV/.4MU C
1 inch = 2.54 cm C=3x 10 m/sec ) r = 0.1714 n 10-B Btu /hr ft 2 P 4 i e __--_-___.m__3. . _ _ _ _ .
= =
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.Mrple or Oak-Wood. .O.096 l
- Building' Brick. -0. 4 Window: Glass i O.45 Concrete 0.79
-1% Carbon Steel 25.00 1% Chrome Steel- 35.00
' Aluminum 118.00
; . Copper 223.00
-Silver 235.00.
' Water (20 psia, 200 degrees F) 'O.392 Steam (1000 psia, 550 degrees F) O.046-Uranium Dioxide 1.15 H211 um .O.135 Zircaloy 10.0 dlSCELLONEQUS_1NEQBd8I1ON:
E = mc KE'= 1/2 mv
~
PE = mgh V:=V f O
+ at' Geometric Object Area Volume Triangle A= 1/2 bh /////////////////
2 ///////////////// Square A=S Rectangle A=LM M lllllllllllllllll 2 ///////////////// Circle A = nr Rectangular Solid A ' 2(LxW + LxH + WxH) V=LxWxH 2 Right' Circular Cylinder A= (2 nr2)h + 2(wr2) V = wr h-Sphere A = 4 wr 2 V = 4/3 (wr2) Cube ///////////////////////////// V=S l l-1
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Page 9 of 5 09IO_SdEEI C15CELLGUEQu5_10EQ800Il00_1coctiewedt: 10 CFR 20 Appendix B t __, Table I Table II l Gamma j l Energy Col I Col Il Col I Col II l MEV per Air Water Air Water Material Half-Life disintegration uc/mi uc/mi uc/ml uc/mi I
-6 ~0 Ar-41 1.84 h 1.3 Sub 2x10 -----
4a10 ------
-3 Co-60 5.27 y 2.5 S 3x10
~7 1x10 1x10 ~0 5x10~ 1
~# ~
~10 ~#
1-131 8.04 6 0.36 S 9x10 6x10 1x10 3x10
~#
Kr-85 10.72 y 0.04 Sub lx10~ ----- 3x10 ------
~# ~3 ~0 ~
Ni-65 2.52 h O.59 S 9x10 4x10 3x10 1x10 " ;
-12 ~I# -6 Pu-239 2.41x10" y 0.008 S 2x10 1 10~ 6x10 5x10
~Il ~#
Sr-90 29 y ----- S 1x10~ 1xiO~ 3x10 3x10
-6 ~#
Xe-135 9.09 h O.25 Sub 4x10 ----- 1x10 - - - - ~ ~ ' Any single radionuclides with T which does not decay by alpha or/2 > 2 hr 1 3x10
-9 9x10-5 1x10
-10 3x10
-6 spontaneous fission 2
Neutron Energy (MEV) Neutrons per cm Average flux to deliver equivalent to I rem 100 mrem in 40 hours thermal 970x10 6 670 0.02 4GOx10 280 (neutrons) 6 39 0.5 43x10 ________ _ 6 - 37 g,2 10 24x10 ,ec Linear Absorption Coefficients p (cm~l) Energy (MEV)' Water Concrete Iron Lead O.S 0.090 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77
- 1. 3 0.057 0.13 0.40 0.57 2.0 0.048 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.038 0.CR9 0.30 0.47
.......m
j DYNAMICS _Page 4
- i. REACTOR PRINCIPLES (7%) THEBt0 l (7%) - AND COMPONENTS _L101) (FUNDAMENTALS EXAM)
... q 1
9 QUESTION 4.01 (1.00) , Which ONE of the following statenients is NOT true concerning the ' Moderator , Temperature Coefficient: [ A. If the Resonance Escape Probability changes faster than the Thermal. Utilization Factor with a given change in the moderator temperature, then the Moderator Temperature Coefficient is negative. B. Moderator Temperature Coefficient becomes more negative over core life due to decreasing boron concentration and increase in neutron leakage, C. For a given moderator temperature change, mere negative reactivity is inserted when control rods are in the core, versus control rods out of cote. D. Moderator Temperature Coefficient becomes less negative as moderator temperature is increased since the Thermal Utilization Factor increases while the Resonance Escape Probability decreases. f 1 l l 1 i (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) s l
)
1
4.
'Page' 5 REACI98 PRIHQIfLES'(7 Q_IBEEMQDINAMICD 1731_AND COMPONESIS,_L10%) (FUNDAMENTALS EE/El i
QUESTION 4.02 (1.00) e Defirie Fuel Temperature Coef ficient (FTC) of reactivity. (A mathematical expression can be used. Ir.dicate units if a mathematical expression is i utili::ed ) . i 4 d l li t - p i l l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) I
4, RESQTOR ERJNCIELES (7%) THERMgDYMAdlqS- Page 6 17%) AND_COMPONEt!IS_(10%P (FUNDAMENTALS EX8til qui:STION 4.03 (1.00) Delayed neutrons play a major role in the operation of the core because they .
. . (Choose the ONE correct answer) (1.0)
A. are born at (therma]) slow energy levels (less than 1 ev') and therefore are more apt to cause a fission as compared to being absorbed by a poison. B. are considered as thermal neutrons and therefore they will not travel far enough to leak out of the core. C. are born .so much later than the prompt neutrons and provide controllability during steady state operations and power transients. D. Provide 70% of the fission neutron inventory and have higher importance factors associated with them as compared to prompt neutrons. l l l I l l l l l l 1 1 l l l (****4 CATEGORY 4 CONTINUED ON NEXT PAGE *****) l l l
--___m_ _ _ _ _ _ _
- _ = _ _ , - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
Page 7 4; RE8G1981 BIEGIELES (7%) THEBMODYEAMIGS (7%) Atip COMPONENTS (10%) (EUEDAMEETALS EXAM) QUESTION 4.04 (1.00) Which ONE of the following descriptions best supports the reason why Xenon reactivity increases sharply after a trip from 1000. hrs. at 100% power? A. . Xenon decays less rapidly due to a reduction in the neutron flux. B. Iodine half-life is much shorter than Xenon half-life. C. Iodine production is greatly reduced and Xenon production is greatly increased due to the reduction in neutron flux. D. Due to reduced neutron absorption Iodine concentration increases, and Xenon decays directly from Iodine, thus Xenon increases. l 1 a I t [ i (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) _ _ _ _ _ _ _ _ _ _ _ _ _ ____._ ____ . - - _ a
- . .. ~ . . .
Page 8 4, READIQB_EBlHCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENIS (10%) (FUNDAMENTALS EXAM) l QUESTION 4.05 (1.00) ! l The DOMINATING EFFECTS on Keff by the control rods are the changes in: (Choose the ONE correct response) A. Resonance escape probability (p) and non-leakage probabilities (Pf and Pth) i B. Thermal utilization (f) and non-leakage probabilities (Pf and Pth) C. Resonance escape probability (p) and thermal utilization (f) D. Resonance escape probability (p), thermal utilization (f) and non-leakage probabilities (pf and Pth). e I (***** CATEGORY 4 CONTINUED ON NEXT PAGE **'***) l 1
.Page 9 4, FEARIQB PRINGIELES (7%) THEREODYN6MICS 17*4) AND CQMPONEETS (10%) (FUNDAMENI6LS-eke l l QUESTION 4.06 (1.00)
Which ONE of the following statements is correct concerning the relationship between the Effective Multiplication Factor and the condition of the reactor. A. Suboritical is the condition of the reactor when the Effective Multiplication Factor is greater than one. B. A reactor with the Effective Multiplication Factor exactly equal to one is considered critical with an increasing fission rate. C. A supercritical reactor has an Effective Multiplication factor greater than one and a constant fission rate. D. In a reactor with negative reactivity, the Effective Multiplication Factor is less than one and this is considered to be suberitical. l l i
)
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
Page 10 11 . RESCTOR PRINCIPLES (7%) THERMODYNAMICS 17%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM 1 QUESTION- 4.07 (1.00) Which ONE of the following statements concerning decay heat is NOT correct: A. The less time a reactor is operated prior to shutdown, less-decay heat is produced since there is not as :nuch time to accumulate long-lived fission products. B. The longer time at power, the more decay heat will be produced fo11cwing shutdown due to increased number of fission products. C. Immediately after shutdown, the decay heat decreases rapidly since most of the energy is being produced by decay of short lived nuclides. D. The gamma decay of fission products leads to the release of delayed neutrons and produces decay heat. i i I (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) l 1
- c. ;
ly - l
.Page 11 4,. REACTUR PBINCIPLES (7%)'THElsMQDYNAMICS
-(7A) AND COMPONENIS (10%) (FUNDAMENTALS EXAM).
l i QUESTION 4.08 (1.50) What THREE conditions must be present in order for Brittle Fracture of the l reactors pressure vessel to occur? (Setpoints not required) l l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
Page 12 4, REAGIQB_EBINGIELES (7%) THEBdODYNAMICE (7%) AND CQMPONENTS (10%) (FUNDAMENTALS EXAd1 QUESTION 4.09 (1.00) A. While performing a plant cooldown utilizing the RHR system, the 1A RHR pump becomes air bound. What would be TWO symptoms of an air bound pump, AND what would be a symptom of a pump that is cavitating that is not associated with an air bound pump? (0.75) B. What action (s) can be taken to correct the problem of the air bound pump to restore RHR cooling. (Assume RHR pump 1B is inoperable) (0.25) (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) I a_ _ __
j i Page 13 ;! 1 REACTOR PR11LQ1ELES (7%) TIIEEMODYNAtiTCS (7%) AND COMPONENTS (10%) FUNDAMENTALS EXAM) { i QUESTION 4.10 (0,50) What is the definition of Nil-Ductility Transition Temperature (NDT)?
\
I i (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
.e_. _._.___._;.. .
t ,
- , y Page-Id I /3 S REACTOR PRINCIPLES (7%) THERMODYNAMICS'
~
l' (7%) AND COMEONENTS (10%)'(FUNDAMENTALS' EXAM) QUESTION 4.11- (1.00) WHY and HOW.(more restrictive or less restrictive) are the RCS operating' limit curves for temperature and pressure.during heatup and cooldown transients
' changed over the life of the plant?
l .. ii' i: l1 - .i. I ,t l l l 4 (***** CATEGORY 4 CONTINUED'ON NEXT PAGE *****) L
Page 15 A. REAGIOR PRINCIPLES (7%) IEEEMODYBAMICS 17%) AND COMPOREEIS (10%) (FUNDAMEEIALS EXAM) QUESTION 4.12 (1.00)
.Given the following information, calculate the reactor core thermal output in MEGAWATTS (MW). (Disregard any losses due to SG tlowdown and RCP heat input.
Show all. calculations, round answer to nearest MW). Cp = 1.3 BTU /lbm - degrees F S/G Pressure : 1050 psig Steam flowrate : 12 E6 lbm/hr Tavs = F80.5 degree:; F T - hot : 603 degrees F Feedwater temperatu.9 = 410 degrees F Condenser Pressure : 27 inches Hg vacuum r l l l l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *444+)
- 4. Page 16 REAGIDE_EBIHCIPLES (7%) THERMODYNAdlGS
( 'f % ) AND CQUEQFlHTS (10%) (FUNDAMENTALS EXAM) QUESTION 4.13 (1.00) One of the actions that an operator can take to enhance NATURAL CIRCULATION flow, is to ensure that heat removal matches or exceeds heat generation. State FOUR VERIFICATIONS the operator-can use to ensure that heat removal matches or i exceeds heat generation. l i -l l l l (***** CATEGORY 4 CONTINUED ON NEXT PAGE **4**)
- g . ,
Page 17
$ JBEACT(>R PRINCIPLES.[V%)-THERMODYNAMIC _
L7%) AED_02MEGEEFLS (10%J tFUNDAMENIALS CXatil
. QUESTION 4.14 ( 1, 0'J )
Explain WHY and HOW the Stean Generator Water Level Control system uses a
. density compensated signal as an inpat for steam flow.
I 1 i l 1 4 (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
c ; L, - i Page 18 L_B3A910B PR$NCIPLES (7%.lEERMOD'dMTCS ! .L7 % ) 6ND COMP 0biEEIS (10%) (f,JIMMENIALS EXAM) ; l i QUESTION 4.15 (1.50) ] i Byron Unit 2 is doing an RCS heatup using three RCP's. If a fourth RCP is j started to increase RCS heatup rate, would the motor amps for the running RCPs 1NCREASE or DECREASE ofter the RCP is started? (Explain the reason for this change). . I l 1 i l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *444*)
Page 19 i, REAGIQR PRDIGHLES-(7%) THERMODE 6MXCS (7% LAND COMPONENTS (10%) (FUNDAMENTALS EXAM) i
. QUESTION 4.16 (1,00)
Answer each of the following questions concerning operation of centrifugal - pumps. A. In relation to pump discharge pressure, and system'flowrate, what would be the indications that 1A RHR pump was operating in a RUNOUT condition? (0.5) B. What is the major concern with operating a centrifugal pump at SHUTOFF HEAD conditions for an extended length of time? (0,5) 4 i I t (***** CATEGORY 4 CONTIN 0ED ON NEXT PAGE *****) l
.. ~ . . .
I 1,1= REACTOR EBil!GlPLEC (I%i THEBdQPlM6 MIGS Page 20' l (7%) AND COMEQt!ENTS (10%LJf,qNDAMENTALS EXAM 1 l J l l l l QUESTION 4.17 (1.00) I Answer the following questions concerning operation of the centrifugal charging pumps in the CVCS A. Draw a simplified pump curve representing two centrifugal charging pumps operating. Indicate system operating points on the system characteristic t curve for 1 pump operating and for 2 pumps operating. (Labels on axis of curve required., but not specific values). (0.5) B. Indicate by using a simplified pump curve, how the system operating point changes when the reactor operator shuts FCV-121.slightly with one centrifugal charging pump running. (Labels on axis of curve required, ; but not specific valuec). (0.5) 4 i l l I i 2 { i r (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
Page 21 ALBElifLGB_ERIEIELES (7%) THEEd0 DYNAMICS
, IJ11_6ND COMEONENTS (10%1 (FUNDAMENTALS EXAtO QUEST?Ci4 4.18 (1.50)
A special operating order was written for closing of breakers in safety-related equipment which utilize AR-3 relays. The special operating order directs the operator to ensare that he/she holds the contro1' switch to CLOSE until the Cl,0 SED indication is received. EXPLAIN WHY the operator must. do this< (Specific concern with operation of AR-3 relay must'be addressed). (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) ) l l
. . . r m..
Page 22
- 4. REACTOR PRllLCIPLES (7%) THEBMODYH6MICS (1%L.6BD.. COMFj2NENTS (10%) HJ)NDAMEUT ALS EXAM) l I
i: l-( QUESTION 4.19 (1.00) l An administrative limit of a ma::imum five (5) starts within one (1) minute follored by a minimum of 30 minutes cooling off time is~ applicable for operation of all limit torque motor operated valves. What is the reason for this limit?
'i i
1 (*"** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
I RE&CTOR; PRINCIPLES (7%) THERMODYNAMICS Page'23
'4.
(7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) QUESTION 4.20 .50) The Main Feedwater System uses a venturi type restrictor to measure systen flowrate. What TWO basic principalc are involved to measure flowrate using a venturi type flow restrictor? 1 (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
1
- 4. Pege 24
! REACTOR PRINCIELES (7%) THEBMODYMAMLCH ( 7*4 ) AND COMPlQUENTS-(10%) (FUtgDAMENTA145 EXAt11 1 I i QUESTION 4.21 (.1. 50 ) i While starting a RCP, you observe motor amps to be very high .immediately j following the start, and then decrease to a significantly lower value shortly I
'after starting the pump. EXPLAIN WHY motor amps respond like this.
i i. I 'l s l ' l l - 1 l I ! i (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) I i
1 J EA970R PRIHgIPLES (7%) THERMODYNAMlgS . Page 25 (7%) AND COMEQUENTS (10V) (FUNDAMENTALS EXhM) QUESTION 4,22 (1.00) Periodically chemistry will analyze a sample on the inlet and outlet of the mixed be4 J on excitanger in the letdown system. EXPLAIN the reason chemistry would need to sample both the inlet and outlet of the ion exchanger. t l [ (***v* END OF CATEGORY 4 *****)
77;- s '. , , . _ . . ._. . - -
- 1 7? age l46 51- EBEBGEHQL.AND ABNORMAL PLANT EVOLUTIONS l
' - 12.3%,,2 j
I (4**** CATEGORY 5 CONTINUED ON NEXT PAGE *****) Y -
Page_27 E. EMEBGENCYLAND ABNORMAL PL6EI_E.VOLUI1ONS (33%1 QUESTION' 5.01 (1.00) The previous shift experienced a PZR Level Master Controller Failure which was repaired by I&C and was returned to service in automatic 2 hours ago. Given the following plant parameters, EXPLAIN WHY you believe that the PZR Level Master Controller is/is not working properly. , Tavg = 578 des F and stab)e Reactor Power 67% and stable PZR level = 53% and stable (read LT 459/460) PZR pressure = 2230 psig containment temperature = 95 degrees F containment pressure = 0.5 psig f i Y I k 1
)
)
l (**4t* CATEGORY 5 CONTINUED ON NEXT PAGE **St4') l L_____- __ l
l
- 5. Page 28 EMEBGENQ1_AHD ADNORMAL_fLANT_ EVOLUTIONS LM%_1 1
l l j l
-QUESTION 5.02 (3.00).
)
BOA PRI-4, "High Reactor Coolant Activity," Step 6 directs you to perform Technical Specification 3.4.8 action statement if RCS gross radioactivity is greater than 100/E bar microcur3es per gram. The action statement requires
-that the plant be placed in at least hot standby with Tave less than 500 deg F within 6 hours.
A. What is the basis for reducing Tave to le.es than 500 dec F (1.5) B. What is the basis for limiting RCS gross radioactivity to less than 100/E bar microcuries per gram? (1.5) I l (***** CAT 2 GORY 5 CONTINUED ON NEXT PAGE *****) A- _-- _ - _ - _
Page 29
'.EL EMERGEH9X_AHD_AHH9BMAL PLANT EVOLUIlOMS _
(33%) QUESTION 5.03 (1.00) During refueling operations, Technical Specifications require that a minimum-of 23 feet of water shall be maintained over the top of the reactor vessel flange. What is the basis for this minimum level requirement? 1 l l l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
.. t Page 30
- 5. EMERGENCY AND ABNORMAL PLANT NVOLUfIONS-L225.1 I
i I QUESTION 5.04 (1.50) { i DEP-0, " Reactor Trip or Safety Injection," immediate action Step 5, states l
" VERIFY FW ISOLATION." What is the basis for this step? /
l l 1 I J I f; 4 l I 1 k 1 (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l
\
4 l
Page 31
'5' J!jgBgI'p0Y AND ABNORMAL-PLANT EVOLET20Ns 12.3Al QUESTION 5.05 (1 50)
What is the reascn that the air operated control valves for the Containment
' Spray System eductors have mechanical ecops to prevent failure in the ,-. comp 3etely open position?
i l' i I y I' (***** CATEGORY 5 CONTINUED ON NEXT FAGE *****) a_
4
}
Page 32 (
- 5. EMERGENCY ARID ABNORMAL PLANT EVOLUTIONS LGD QUESTION 5.06 (2 00) ,
BOA Sec-4, " SAC Startup During Abnormal Cenditions," requires a nitrogen bottle to be hooked up to the compressors to supply control air if instrument-air header pressure is less than 80 psig. EXPLAIN WHY this must be done. (Explanation chould include problem associated with starting the SAC without control air). i (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
Page 33 l J
.5. EtiEB@NCY_6HD_.hBHQBMAL PLANT._ EVOLUTIONS L !
12.322 1 1 1
,j l
QUES?'. TON 5.07 (1.50) 1 BEP E-3, "SGTR," Step.20 states, "Stop FCCS Pumps and Place in Standby." Step ! 20 would be performed if ECCS termination criteria are met,- What is the bcsi.s (
?or performing this step? )
i J 1 i i 1 l 1 l l 1 l i I li I (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) j
"Yj E
( ,.,.
'faiEMEB2EllqylND ABNORMAL PLANT' EVOLUTIONS 'Page 34 -
f33%1 '! 1 i i l l 5.08 (1.00) f
-QUESTION-Technical Specifications require that both safety-re. lated 125 volt D.C. buses ar< operable and fed ~from'their associated buttery and full capacity charger.
What is the basis for this?- l 1 i i I i
)
i 4 i f l (***** CATEGORY 5 CONTINUED ON NEXT PAGE '*****) __ - - - l
- 5. Page 35 EMEBGENCY AND ABNORM &L PLANT EVOLUTIONS LitBIzl QUESTION 5.09 (1.00)
Mhile performing a startup, a reactor trip occurred due to the failure of k Source Range instrument N32. Using the following given information, determine what specifically caused the failure of N32 to cause the reactor to trip? Highest SR reading at time of trip was 8" E3 Highest IR reading at time of trip was E11 cp g! a.. L{ s -li amps Level trip switch on N32 was in the bypass position High flux at shutdown on N32 blocked 1 (***** CATEGORY 5 CONTINUED ON NEXT FAGE *****) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . )
I Page 36 faddEMEli.CY At!D AS@BMAL ELANT EVOLUTIONS (33%1 QUESTION 5.10 (3.50) Byron Unit 1 tripped from steady state 100% power at 1225. The unit had been at 100% power for 60 days, and all systems were operating properly. It is now 1310 and you are monitoring the Critical Safety Function Status Trees (CSFSTs). Using the attached CSFSTs and the followinc information, determine the condition (red, orange, yellow, green) of ALL critical safety functions, AND list in order of priority (highest to lowest) the procedures that would be performed. (ASSUME any procedure (s) that is(are) identified by the CSFSTs will be performed.) RCS W.R. Pressure (430A/405) at 1070 psig PZR Pressure at 1075 psig PZR Level at 42% Source Range NI's energized with 0 SUR Containment Pressure at 21 psig Containment Radiation is Normal Average of ten highest thermocouple is 515 deg. F A, B, and D S/G Levels (N.R.) at 42% C S/G 1evel (N.R.) at 6% A, B, and D S/G Pressures at 1080 psig C S/G Pressure at 200 psig A, B, and D RCS loop cold leg temperature at 480 Dog. F C RCS loop cold leg temperature at 260 deg. F Containment Floor water level at 10 inches RVLIS and Plenum Regions at 100% < A e e Head
)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE **t**)
lp L.t \\ ?! REV. 2 'SUBCRITICALITY 1BST-l' WOG-1 UNIT 1 4 [ o To 18FR.S.1 Go To T- M M MB M ,,,,,,,, Fower range LESS THAN 88
- r Ss g, Go To Yee g 18FRI S.2 5-- intermediate
~
range SUR
'Intersnediate range SUR
"* MORE _
~( . EERO or NE8ATilli YMAN Yes NEGAT8Vg Yes -0.8 DPM
- cSe N. V*
Source range EnEReizEn 99 Go To vee g isFM.S.:
. O_
Source range suR zEnO ., _ NEGATIVE l "\ CSF SAT APPROVED rage A or A .- (0262E/0030E) JUL 301987
"" B. O. S. R.
_.L:,xss.'s.3..'.a s.. . . . . .. REV. 2 CORE COOLING 1BST-2 ? ( WOG-1 UNIT 1 i 1 Go To
.4
.41
- 1 B F R.C.1
. ; .m +:. 6'. -
Core exit TCs No LESS THAN - - ison., Go To se I B F R.C.2
. j
...; -W .
v
~
.; , Core exit TCs No
..+ ..
F ' LESS THAN 70S*F
. ?:
Yee
*^
,,'.;- ,! y-l, > .
e E29@; .. e. 77 RCS subcoolJng
- e ACCEPTABLE. No OOOO
*. VALUE 1 BF R.C.3
- g. Per sconic Display _
',- -aN l' or Attachment "A"
' "if and Figure' sBSva.1- Y" l
e.. *
, CSF
( I APPROVED SAT rose i vi a , (0263E/0030E) JUL 3 01987 B.O.S.R. f
'.4:A .. c.d.- . . . .c . , . , .
- i. 1 L
e.1- , REV. 2 CORE COOLING 1BST-2 'f 'f; (. WOG-1 UNIT 1 I
- c. a.,
- *
- ATTACHMENT A A. Determination of Post-Accident RCS Subcooling:
i-' 1. Check Cnmt f6r ADVERSE conditions; o Cnmt pressure greater than 5 PSIG
- ~
- OR -
o Cnmt radiation greater than 10 5R/hr
> 2. Check RCS pressure on wide range pressure instruments .' '
.~' (1PI-403A/405).
a.i. : n w . , e. . .
.. 9 3. Determine temperature for RCS pressure using NORMAL or ADVERSE 5t Cnmt curves per Figure 1BST 2-1. ,l
( O'. .
- 4. Check average of ten highest core exit TCs from MCB indicators s'".:',7]_-
.y (1TI-1T001/1T002) . % '
~,. .
7 'is 5. If average of ten highest core exit'TCs less than temperature for RCS pressure, then acceptable subcooling exists.
,q W .. ; . N s,.
I
?.. .
{baw. p y. n; .
. (' APPROVED l
(0263E/0030E) JUL 3 01987 B. C. S. R.
. . + . . ya:d :.Cc :.sa . . . . . . . . .- REV.-2 CORE COOLING 1BST-2 ,f ( WOG UNIT 1
~
1 200 800 400 500 600 '700 1 E, 2000
@:,.~ ,
. e. ! l . f;EE 200b
, 2500 ii
- a- :
!" 2500 ,, 2400 e % --
l l-T~ 2400 \ 2800 . l-{gf-- 2300
. 2200 :
-! :E , 2200 -l 2100 -! ! ! 2100 2000 l ! l 2000
~
1900 /j j 1900 i
*1600 0 :/ i: 1800 h
a 1700 9 ACCEPTABLE f f 1700
' ' +'f i " a.1600
// /
1600
?i.. g 1500 E
j Q'. 1500 l(. 9 D 1400 / / / 1400
.A 'e 1800 I
. / [ 1800 m 1200 =/,
.r ,t / / 1200 ADVERSE'~ - ' ' ~
[1100 TC'NMT' '
~/ / 1100 e 1000 ./ I _/, 1000 u o 900 /i / 900 e a -
- N OT .-
800 f,.f j ACCEPTABLEg 800 ~ 4 700 _f,f .. 700
#1- 600 .j-;/ _/. 600 fl.:'n 500 ff './ 500 400 /-' 400
./
800 / - 300 200 :ttmMORMAL J !8 ATURATION
'C N MT ; ,
200
,i 100 #
100 200 800 400 500 600 700 t TEMPERATURE (*F) FIGURE 1BST 2-1 g RCS SUBC00 LING MARGIN
\ APPROVED 1 Page 3 01 4 JUL 3 01987 (0263E/0030E)
FINAL B.O.S.R. , l
_ . . . . - - ~ - . - . . - - - -
= Lla.' :. .. .n . -. -. . .
I REV. 2 HEAT SINK 1BST-3 ;i ( WOG-1 UNIT 1
, , EF N.1 4.a Total feedwater flow Me
, to SCs
.~- 'j GREATER _
rnan soo
) .I ..
OPM 'y,, AVAILABLE' Co To 99999999998 isrR.N.s karrow range ! O level in at Me Wessure in all least one SC SCs . 4 Ne k e**_ATER f _ LESS THAN ' s ts.: r THAN 4%f S4% 1:33 paso _ FOR ADVERSE I'*
. CNMT) y,,
3;{ ""'
, g*****e @ U..... ]
Narrow range if:(N 4 + "! level in all5Cs No LESS THAN . , 5/CL 82% -
.~ (g . -
' ~ '
Tee
. , g. ...@Co To ,.,R.... ,
Pressure in all )
- .qkW * **
LEss TuAn
~
1175 Pelo-s Yes Co.To OO{ 18FR.H.5 I
- l <- w%- Narrow range level in all 5Cs N o-
?. andATER THAN4% (34%
POR ADVERSE CSF CNMT) V** Q ISAT APFROVED Page 1 of 1 JUL 3 01987 (0264E/0030E) RNAL B. O. S. R. 1 -
Sul2..: :: : .. - REV. 2 INTEGRITY 1BST-4 ; ( WOG-1 UNIT 1 l y ( BFR P.1 All RQ
".",~, ."'c'.i7',3 N. Go To temperature 1SFR.P.1 /J' . d === values . FO - ': -- T 4E nedW. W
[a 'n ,' ' Yes All RG cold l 1115741 les temperature - l h "* Go To b ORIATI" O 1sFR.P.2 THAN 248'F
, G i Y** All RG cold 3J., l Temperature I'8 No decrease in s temperature all RG cold No L,,,, values , _
; legs OREATER
.ESS THAN -
[" .(. THAN 270'F yes 00'F IN THa ( o
- ,. i AST SO -
WINUTES Yes
? ,.
5 ~ l CSF li:
- AT
's . s E sFR e.i All RO cold leg No
'! temperature j;.;
-(- .
RQ pressure r- ,, i o ,, GREATER l LESS THAN No COLO OVER. TNAN 340*F RESSuRE F *LlutT per 0 gg Co To gg Mg e - 18FR.P.2 1BST4 2eand Yes temperature IBST4 2b OREATER - THAN 880*F CSF Yee SAT lI ' CSF SAT ( . APPROVED page 1 of 4 JUL 3 01987 (0265E/0030E) B. O. S. R.
~- _ _ _ _ . _ _ . _ . _ _ _ _ . . . _
n..,. . ,...~,.~....u...x..-. , n...c.-.-.. . REV. 2' INTEGRITY 1BST-4 .f WOG UNIT 1 . I l l Y 100
............................ soo . . . . .. . .. . .. . .. . .. . .. . .. . .. . .. . . . . . . . . ...
. soo w.u. -
.a h,s. t , ..
. .r . . s .,
...... .... ..........................s.
s.., . ..
. . t. ,s n.s .. ._ .. ..................................... ..................................................
- w. . .,;m..~.
n.
..?,, ,.
<.v..
2..................................
.r. . .s.. , .. ....................................................
. 4.,. . ...............................
.;. , . n
,, . 3 c. .s. .
s 18@...........................................................,.......................
..........................................................................Im m
1,,: 1. m. v
........................1........................................................................
s, .. ,. .... . .. . . .....................................................................................t........ 3... 5 M, ...... . . . . ........................................... _. s ... . . . . . . . . . . . . .. .,. .. m. ... .
.. m ...............................................
m _,.,.,
, . . . , , W U U. .. ..............
aa .......
.ss, . .a. .y2. ,,,. m .............................................................................................1 v.,,.,,,
c. m ...........
...r.......................................................................... , . . , ~ . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .s. a. m o .... . . . . .... . . . . ..............................
sm........................................ u .. . w.
..m. . .......................
.........................................................................................m
. ... ... ...c........................
- y. . p.'.p . ,,2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... ..... ............................................
i 400 ................... . . . . . . . . . . . . . . . . . . . . ...............
....................................s....
...............................t.
n,.................................... 1.o . # . ....................................z.......................................................... O .. . ............................................ ..... .................. ..... ..... ... . . . . y , R08 COLD LEG TEMPERATURE ('P) FIGURE 1BST 4-1 v PLANT OPERATIONAL LIMITS l APPROVED Page 2 of 4 JUL 3 01987 , (026SE/0030E) B.O.S.R. ! 1 l l l
s
.a.w.. 21:: ,;
REV. 2 INTEGRITY 1BST-4 : UNIT 1 ,( WOG-1
.;p >:.- .. t
#N ~" t O 100 200 800 400 500 j
~
y summum a a sps e am m a a s p m mm y usepse m y misum a ma p s a m a m m mamm um
- -s 2400"'
, , , , 2400 .,
- ' PORY 455A' '
l l 1 i
.o m 2000"5 I . . l 2000 jf 7 E I I
I i i I 8 I i! ' X_ f- i. I 5 1600.. . l / 1600
*- = , i , , , i i y! i .
Y W I I 1200- , , . l 1200 n = , , ii , , n I a , ,. g ' ' '
. . 1.4. .. - 800 . . ... . . . , 800
[ .
@ 700 700 v o
.1: 4
.,;f.w. T. F 3s g wl
- A o- 700 700 2..
.n. A v F.. -
i em w .s. . . .iii M CD m r i i
..syc .
mm :- !
- w. .. ..,. m -
ri t - ii
, = 'y t.
5% g%g eOO " ; > . , 600 l
- +
- A> E I I 3
, i
[
- .,i i! t i mo I, ', ' ..
AA "; i j l:,: , , ,; w -n
-o o - , ,
v , . , , 500". '
. s00 !
HA
= i i i i i .
I 4 m
. , . ,' i -- -
,r i . i N = i +
ACCEPTABLEZ li;, i REGION FOR -
='
i < OPE. R. A,T,IO,N, C a . , . . . .. 4gg 4gg I 0 100 200 300 400 500 RCS TEMPERATURE (*F) FIGURE 1BST 4-2A BYRON COLD OVERPRESSURE PROTECTION SETPOIN1S {' APPROVED Page 3 of 4 JUL 3 01987 l
, . (0265E/0030E)
B.O.S.R.
L i2 '
. . . :. . .. M_ . . . .. : . . . . .
r
. i REV. 2 INTEGRITY 1BST-4 g
(- WOG-1 UNIT 1 : 1
. l i
?
s .- . k' 0 100 SOO 500 fh3-- y ....... ,,,, ,. y ,, ,800. - , ,400__ 4 ' 2400 - 2400
- q. .. , . _ , ,
f ;r * - PORY 456 l 7 4 4 2000: 5
! l .
, ./-
!E i i 2000
[, ' E l s E. 4 e i s 1600 2 1600 E t !.F i 1 , I
- E I IE I i !
1200.E . , , . , , . 1200 l A I I E I i i i
.F
- g E t ! i I .
' , m Q 800"' . . .. , . . .. , , , , 800
- p.{p.- e to
d ' '
700 o 700 .
. v.fr y .
w ' b.k. E* gy I (y*,E;. - - 7%j , ,
< o 'v* 700.M 1 i
E I 700 ,
- q. ca.i-E4 m = ,',' ;
.y$- .. '
pg m . i mM s: '
=
fi. .' M l, w > n. . i A ', 600 fM.
- w. I. o M 600' ., ,2 i 7; p, ): -
E X e i t M 4 / p h4
, a- -
E 1
-ap" t i N o = ' '
+w - m o 500 " 500 H A -
E
. i i 4 I I I 3 - i ACOEPTABLE -
REGION FOR
=
- . OPE. RATIO. N.
, . . . . .. 400 "
'400
.I O.[ ' O -
100 200 300 400 SOO ROS T3MPERATURE (*F) FIGURE 1BST 4-2B BYRON COLD OVERPRESSURE PROTECTION SETPOINTS ( APPROVED Page 4 of 4 JUL 3 01987
~
(0265E/0030E) RNAL B.O.S.R.
z..u ....*~%:
-- ^ *. ' d.' e %>r , + 4 s . . s e .as ~ -%.
- e. f . REV. 2 CONTAINMENT 1BST-5 j i WOG-1 ,
UNIT 1 E I' E'. - gyg,g,9 Containment
'fPressure No LESS TNAM
~
80 PSIG ve. ga _ Go To E ' 1 BFR Z.1 i E Containment . pressurg No LESS THAN 20 PSIG y o .' g Co To 1 BFR=Z.2 I E Containment
-[ floor water No 7 'g,y,g LESS THAN SolNCHES Yo. o To
' *si MOO 1 B F R-Z.3 O
I O Containment radiation No LESS THAN """ A ). A F M ' S ET PM NT: e1RT.AR011 Ys
! 1 RT- A R012 AT . (~ . APPROVED v
i Page 1 of 1 JUL 3 01987 (0266E/0030E) FINAL- B. O. S. R.
~ ~ -
= = - = - - - - -
~1 2 % .15 L :a.:.i. -. .. .:~.~~ . _
1 INV ORY 1BST-6 j ( ki i
'g g , Go To ,
j 1BFR.I.3
< a'.i g
9-RVLIS head and plenum N* regions _ i Indicate 1 ico% Yes j
? -
e e Go To i 99el 1 B F R.I .1 r
' ~
T Pressurizer level No h l , '"*" Co To 99990000e39e h~ ,,c ap 111 g i BFM.I.2 Yes 9
' Pressurizer j ; No level GREATER g THAW 17% Go To
- q Yes 8 8 #I iBrR.I.:
G e
- w. .
O RVLIS head
, [
and plenum No regions [ indicate 100% Yes i ' CSF aaPRoveo V~
$sl-W Page 1 of 1 jg[ 3 01987 (0267E/0030E) ME B.O.S.R.
AN -----_
Page 37
.5. 'EMEEGENCY AND ABNORNAL PLANT EVOLUTTONS j
(33%1 - 8 i a 1
. QUESTION 5.11 (1.50)
Technical Specifications require that primary containment internal pressure be maintained between negative 0.1 and positive 1.0 psig. What is the basis for the positive 1.0 psig limitation? i I l i i
.{
l I i j ( l t l f f (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) 1
e %
- 5. EMERGENCY AND ABNORMAL PLANT ~ EVOLUTIONS Page 38
.(33%) ,-
QUESTION 5.12' (1.00) Answer each of the following questions concerning the IR NI's. A. What is the power supply for IR NI-35 Instrument Power? B. What is the power supply for IR NI-36 Control Power? i (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
- 5. EggLAND ABEDBMAL PLANT EVOLUTIONS Poge 39 QUESTION 5.13 (1.00)
What are FOUR SYMPTOMS of a reactor trip as addressed in BEP-0, " Reactor Trip or Safety Injection"? (Redundant type symptoms will be credited only once). t (***** CATEGORY 5 CONTINUZD ON NEXT PAGE *****) _ _ _ _ _ _ _ _ _ . _ _ _ _ _ l
a Pago,40
'5' . ' EMERGENCY'AND' ABNORMAL PLA$T EVOLUTIbtlE LDM
- QU$STION _5.14- (1.50)
BOA ROD-4, " Dropped. Rod Recovery," Step 3a-directs the operator to check Tave-greater than 550 deg.F. What is the basis for checking.Tave greater than 550 deg.F AND what must be done.if Tavo is less than 550 deg.F7 3(Include any. applicable time limits). ( 'd 9 I (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) __m____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ . . _ _ _ . _ _ _ . _ _ _ . _
Page 41 E. EMERGENCY AND_ ABNORMAL PLANT EVOLUTIONS (33%1 QUESTION 5.15 (1.50) BEP E-3, "SGTR," Step 1 gives specific criteria on when to trip a RCP. However, RCP RCP trip is required to ensure core cooling for small break LOCA's. trip during SGTR's is not necessary to ensure core cooling but is still : required if the specified criteria are met. What are the bases for tripping a RCP during a SGTR event when the tripping criteria are met? I (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
- 5. Pege 42 EMEBGENCY AND ABNORMAL PLbNT EVOLUTIONG
( 333Q QUESTION 5.16 (1.00) If an uncontrolled rod insertion is not stopped when the operator places the Rod Bank Selector switch in the manual position, what should the operator do in accordance with BOA-ROD-1, " Uncontrolled Rod Motion"7 i I 1 i i I 1 ( l l I (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) 1
- 5. Page 43 EMERGEB9X_AED_ABHORMAL PLANT EVOLUTIONS '
L11%1 i 1 QUESTION 5.17 -(1.00) One rod in control bank D group 2 is known to be trippable but inoperable due ! to an electrical failure. The rod is presently positioned at 100 steps as indicated by DRPI. Using the attached technical specifications, what would be the MAXIMUM power level that TECHNICAL SPECIFICATIONS would allow you.to l continue to operate at? (Assume all other technical specification ] ' requirements to support this are met.) i i l 1 l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) i
.- = : = --- :.u-- -- --
-==------===z==---- : -- --
REACTIVITY CONTROL SYSTEMS .( 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full-length shutdown and control rods shall be OPERABLE and positioned within i 12 steps-(indicated position) of their group step counter demand position.
. APPLICABILITY: MODES 1* and 2*.
ACTION: l
- a. With one or more full-length rods inoperable due-to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require- !
ment of Specification 3.1.1.1 is satisfied within 1 hour and be in - i HOT STANOBY within 6 hours. .l
- b. With more than one ful_1-length rod inoperable or misaligned from the group step counter demand position by more than i 12 steps (indicated position), be in HOT STANDBY within 6 hours.
. c. With one full-length rod trippable but inoperable due to causes other than addressed by ACTION a. above, or misaligreed from its l- group step counter demand height by more than i 12 steps-(indicated position), POWER OPERATION may continue provided that within 1
- hour: .
- 1. The rod is restored to OPERABLE status within the above alignment requirements, or
- 2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod while maintaining the rod j sequence and insertion limits of Figure 3.1-1. The THERMAL POWER l level shall be restricted pursuant to Specification 3.1.3.6
- j during subsequent operation, or
- 3. . The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:
a) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and l within the following 4 ho~urs the High Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED a THERMAL POWER.
~
b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours; l
*See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
( BYRON - UNITS 1 & 2 3/4 1-14
j / E
' REACTIVITY CONTROI. SYSTEMS LIMITING CONDITION FOR OPERATION l 3 ACTION (Contin ~ued) -
c) A power distribution map is obtained from the movable incore detectors and q F (Z) and Fh are verified to be within their limits within 72 hours; and .j d) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm. that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; j h SURVEILLANCE REQUIREMENTS - 4.1.3.1.1 The position of each full-length rod shall be determined to be within the group de,iand limit by verifying +,he individual rod positions at least once per 12 hours except during time intervals when the rod position ; deviation monitor is inoperable, then verify the group positions at least once i per 4 hours. j 4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined OPERABLE by movement of at least 10 steps in any one direction at j least once per 31 days. j I 9 e BYRON - UNITS 1 & 2 3/4 1-15
r, , 4 . . . . . _ _ _ 7 _ 5 , REACTIVITY CONTROL SYSTEMS b CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as shown in Figure 3.1-1. , APPLICABILITY: MODES'1* and 2*f. ACTION: . With the control banks inserted beyond the above insertion ,1imits, except for surveillance testing pursuant to. Specification 4.1.3.1.2:
- a. Restore the control banks to within the lioits within 2 hours, or .
- b. Reduce THERMAL POWER within 2 hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank position -
using the above figure, or
- c. Be in at least HOT STANDBY .within 6 hours.
( . C . SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion liuits at least once per 12 hours except, during time intervals when the Rod Insertion Limit Alarm is inoperable, then verify the individual , rod positions. at least once per 4 hours.
. t "See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
#With K,ff greater than or equal to 1. i k, ,
BYRON - UNIT'S 1 & 2 3/4 1-21 l
5 . .,i J i 228 t 220 --
. : (29%,228) .I : . / (79%,228)i 1
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- /-
__. .p_ 200 --
': ' .l.-
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. j. .
. I"t '
. . BANK B l 8 - 3
- _': 3 :'~'
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- j .g. .
- g. . .
180 . . '. j, - ;_ _.:_ _J _ . ._p . . . . . : . _ .: . . .. j .. . :{ .! - i
- .(100%,161)~'
160 (0%,162). E o : _j .. _ _ _ _ - :: _. } . : ;
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i' 's; ;
- i. ':
i - ii:
. 140 ..
a '
- BANK C S
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. l . :: - -
.: i. i. : 1. : : . .. : -
m O 100 .":- . ' n. if .: - 1- -
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.1 2
. . . ...: . ;! .: .B. .AN. . .K.D. .iii.i.:.i.;;..;. i. : ..
c: 60 ---
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j, . - .;j; .j. ;;;: __ _(30%,0)l . l: j: :
; i 0
0 20 40 60 80 100 l RELATIVE POWER (Percent) f
. 1 1
1 l 1 FIGURE 3.1-1 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER FOUR LOOP OPERATION ( ] 1 l BYRON - UNITS 1 & 2 3/4 1-22
7,_- ;- _ . . _ _ - _ - - _ , - _ ,
# i 5 ;. ' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS' 4 Page 4'4_
(33%)
-QUESTION 1 5.18 (1.00)
A NOTE in BOA PRI-6, " Component Cooling Malfunction," states that the CC
' temperature limit is 105 deg.F-and can be 120 deg.F for 3' hours if RBR is in l' 1 operation. WHY is the temperature limit allowed to be-120 deg.F if RHR is.in operation?
l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
-- . - - - . - . ------ _ ___j
Page!45
- 5. EtEBGENCY_6ND ABNORMAL PLANI _EVOLLIIIONS (33%1 f
I QUESTION 5.19 (1.50) While performing a plant cooldown from the Remote Shutdown Panel, you observe that the S/G wide range (WR) levels have been increasing. EXPLAIN WHY S/G 1evels would respond in this manner. (Assume that steam flow and feed flow have been continually matched, S/G WR level indicators are operable, and no other plant accident / transient exist). (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
9
- 5. Page 46 EMERGENCY _AND AB_HQBMAL' PLANT' EVOLUTIONS (33%1 QUESTION 5.20 (2.00)
During execution of BOA PRI-5, " Control Room Inaccessibility," EXPLAIN WHY the normal required entry requirements into emergency procedures do/do not apply. 1 (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
Fage 47 5 '. EMEEGENCY AND ABNORMAL PLANT EVOLUTIONS (33%1 QUESTION 5.21 (3.00) Byron Unit edOs operating at 98% power with power range NI-43 inoperable and placed in the tripped condition. All other systems / components are operable and in their normal at power lineup. Electrical maintenance wants to supply power to the 120 VAC ESF instrument bus 111 from the Conste.at Voltage Transformer in orderEXPLAIN to do a surveillance on the 7.5not WHY you would/would kvallow inverter for this evolution to instrument bus 111. take place. (Assume all technical specification requirements are met). l (***** END OF CATEGORY 5 *****) l
PLANT SYSTEMS (30%) AND PLANT-WIDE GENEBig Pcge 48 6 '~. RESPONSIBILITIES (13%) j l l { (**4** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
- 6. Page 49-PLANT SYSTEMS (30%) AND PLANT-WIDE _GENEBlQ BESPONSIBILIIIES (13%)
QUESTION 6.01 (1.50) In order for isolation valve 8811A (suction isolation from containment sump A) to AUTOMATICALLY OPEN, what TWO conditions are needed? (Coincidences and setpo.ints not necessary, do not include MCB switch positions) 1 l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) t
f" 3 o 1 f.; - ,
- Page.-50 f6. PLANT SYSTEMS'(Sd%i AND:PL' ANT-WIDE' GENERIC--
I" RESPONSIBILITIES ~.(13%) ;; y .. t QUESTION 6.02- (1,;50) Concerning the Main Turbine, what-are the THREE functions of the Overspeed Protection Controller..(OPC)? I-4 l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
. ___ . _ - _ _ _ _ _ _ _ _ ~_-. - -_ . .. __ _ _ _ _. - Page 52 6 '. "?LANT SYSIEMS (300 AND PL&NT-WIDE'5ENEBLG - 3EEPONS::BILITIES -(13%) i
. QUESTION 6.03 (2.00)
Answer each of the following questions concerning the Rod Control-System': ')
-A, .EXPLAI'N how the Rod Control system responds upon receiving an urgent-failure in the LOGIC cabinet, and the resulting rod motion capabilities.
(1.0) B. Which ONE of the following DOES NOT get an input signal from the Pulse-to-Analog (PA) converter. (1.0)
- 1. Rod insertion limit computer
- 2. Step counters on the MCB'
- 3. 8 pen recorder
- 4. Bank D rod stop (C-11)
L 1 l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
- 6,- PLANT SYSTEMS (30%) AND PLANT-WIDE GF.,tuu Pege.52 c RESPONSIBILITIES-(13%) ,
r. t QUESTION '6.04 (2.00)
' Answer ~each of the following questions'concerning the Spent Fuel Pool'(SFP) cooling system:
- A. 'What'are FOUR design features that would prevent the inadvertent draining.
'of the SFP. (Do not include features that alert _the operator of level
-loss). (1.5)
B.- -What tre the two NORMAL sources of make up water to the SFP7 (0.5) 2. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
, 6 .' PLANT SYSTEljs-(30%) 5ND PLAMT-WIDE GENERIC Page 53
. .RESPONSI31L2 TIES (13%) .
i QUESTION 6.05 (2.50) i A. EXPLAIN =how the Emergency Diesel Generator Air Start System operates to-maintain air pressure for starting and control air during an EMERGENCY , START of the Diesel Generator, AND how would its operation be different' during a. TEST START of the Diesel Generator? (Include any applicable l setroints) { } Q L } . 1 i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i____________.__._____.__.__._
c;. w .
- 6. PLANT SYSTEMS (30%)^AND PLANT-WIDE GENERIC Page 54-RESPONSIBILITIES (13%)-
QUESTION 6.06 (1.00) ,
~ Byron Unit 1 is at 18% power following a startup. The reactor. operator reports that the Main Turbine bearing oil pressure is dropping steadily and that he is going to manually trip the turbine. Will tripping the turbine result in a reactor trip? EXPLAIN why/why not. (Include in your answer any applicable setpoints and coincidences)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) ____ _ _ _ _ _ _ _ _ _ _____________ ____ _ _______________j
8.- -. _ Pogo~55
- 6. PLANT SYSTEMS L30%) AND PLANT-WIDE GENEBIC RESPONSIBILITIES (13%) 1 j
i i i 1 QUESTION 6.07 (2.00) One of the recctor trips designed to protect the core from a DNB accident is RCP bus underfrequency. EXPLAIN how an underfrequency condition on a RCP BUS could lead to a DNB accident. i i i i 4 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
Paga 56 i 6. PLANT SYSLEMS ( 30%) AND PLANT-WIDE GENERIC-RESPONSIBILITIES (13%) QUESTION 6.08 (1.50) A. The reactor operator on Byron Unit 2 reports that B S/G 1evel is at 73% narrow range and rising rapidly. If no operator action is taken, what would mitigate this event? (List only those mitigating actions that are a direct result of S/G level and include any applicable setpoints). (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) - -_ _ ______ _ _ ___- _ __ _ _ _ b
Page'57 l
- 6. PLANT SYSTEMS _ LEO %) AND PLANT-WIDE GENEBIG 1 RESPONSIBILITIES (13%)
I J J l
.1 QUESTION 6.09 (2.00)
! EXPLAIN how the Pressurizer System would respond if the Pressurizer Pressure Master Controller failed low while at 100% power? (Terminate answer when a ESFAS actuation occurs or at a controlling pressure band, whichever occurs first. Include any applicable setpoints. Assume system in normal at power lineup). (***** CATEGORY 6 CONTINUED ON NEXT PAGE ***'**)
~ ~
Page 58 S. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%) QUESTION 6.10 (2.00) The personnel airlock allows access to containment during Mode 1 operations. EXPLAIN the two interlocks associated with the operation of the personnel airlock which assure that containment integrity is maintained during a containment entry at power.
. i
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l l- ._ - _ _ _ _ - _ _ _ - _ - _ _ _ _ - _ _ - _ _ _ ____ _ _
n- - , - . - - . - - - - - - - - _ - - - - _ - _ - - _ - _ - - _ _ - - - - - - - _ - - - _ - _ - - - _
?LANT SYSTEMS (30%)-AND PLANT-WIDE GENERIC Page 59 6.
3 RESPONSIBILITIES (13%) QUESTION 6.11 (2.50) A. With Byron Unit 1 operating at 75% power, indicate the normal _ lineup, OPEN or CLOSED, for each of the following Main Feedwater valves. (1.0)
- 1. FW 009 (FW Isolation Valve)
- 2. FW 043 (FW Isolation Bypass Isolation Valve)
- 3. FW 035 (FW Tempering. Isolation Valve)
- 4. FW 034 (FW Tempering Control Valve)
B .- What are two reasons that FW 039 (Preheater Bypass Valve) is OPEN when power is greater than 80%? (1.5) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
Page 60
- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENEBIC RESPONSIBILITIES (13%) -
QUESTION 6.12 (2.50.) Answer each of the following questions concerning the Auxiliary Feedwater System (AFW); A. What are FIVE conditions that will cause the "AF Pump Diesel Trouble," alarm to annunciate in the Main Control Room and not cause the engine to trip? (Setpoints not required) (1.25) B. What conditions are necessary to provide Emergency Service Water (SX) to the AFW pumps AUTOMATICALLY? Assume that the MCB switches are in , automatic. (List all possible conditions; coincidences required; setpoints not required). (1.25) k (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) I / l
- a. . ,
..=; == - - - - - - - - - - - - - - - - -
E_LANT' SYSTEMS _laQ%)'AND PLANT-WIDE GEHEBig Page 61' 6. RESPONSIBILITIES (13%) QUESTION 6'.13 (2.50) .y
' Answer each of the following questions concerning the Reactor' Coolant Pumps (RCPs):
A. What' interlocks must be satisfied in order to close a RCP breaker? (1.0) B. Why.must component cooling water be supplied to a RCP that is not running. while in Mode 3. (Assume seal injection is not being supplied). (1.5) , i i i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) I. - - _ _ . . - - - _ . _ _ _ - . - - - _ _ _ _ _ - _ _ _ - _ _ _ _ _
.--____w. -
D o
- 6. ~ PLANT SYSTEMS (30%)'AND PLANT-WIDE' GENERIC Page 62 BEEEQBg1HILITIES (13%)
I L X (QUESTION 6.14 (2.00) l Answer each of the following questions concerning the Rod Position Indication System: A. 'If one Control Bank D rod dropped to the bottom duringLa reactor startup,
,would the " Rod At Bottom" alarm annunciate if the remaining Control Bank D rods were at 8 steps? EXPLAIN why/why not. (Include any applicable setpoints, assume proper bank overlap). (1.0)
B. EXPLAIN how it is possible.to have a rod indicated on the bottom by the Digital Rod Position Indication system while the step counters indicate-that.the rod'is'at 138 steps. (1.0) f (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
- 6. PLANT SYSTEMS (30%) .AtLD PLANT' WIDE GENEBIC - Page 63 RESPONSIBILITIES (13%1
)
QUESTION 6.15 (1.00) Answer each of the following questions concerning the Inadequate Core Cooling System: r. A. What is the range of temperature that can be monitored on the digital LED readout on the MCB for the core exit thermocouple? (0.5) B. What would be the indications, on the MCB display, that a thermocouple was in an alarm condition? (0.5) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
m- .
. .. ,. _.. ,__ ;~., - _ --- _-------- -
y N , ;; . PL6HI_ETSTEMS (30%) ANJ)._PL ANT-WIpg__ GENERIC L Pege.64; i 16'i " BESPONSIBlklTIES (13%1 , r, QUESTION 6.16 (1,5d)
' Answer each of the following questions concerning the Engineered Safety.
Features' System: A. Containment' spray (CS) has actuated, and has: reduced containment pressure to 12 psig when a loss of offsite power occurs. What. condition will-the CS. pumps be in (running or secured) after the sequencer has timed'out AND: WHY? (Assume no operater actions have been'taken since.CS initially actuated). B. If the Reactor Containment Fan Coolers (RCFC) are running in fast speed, what condition would.they be in'(FAST-SPEED, SLOW SPEED OR SECURED), following'a safety injection? (Choose one) m 4 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
a.<. . j;
- -.~...,, .:,.., . . .y: .;.. . . - ,. n _ . a. . n . . _
p )[ -[ : 2. / 4 .... '
'Page 65, PLANT SYSTEMS-(30%)'AND' PLANT-WIDE GENERIC r 16 ; '
RESPONSIBILITIES (13%)
~
.' QUESTION 6.'17 (1.00)
- Which ONE.of the followingTis~the. correct' classification of the Turbine.-.
Building Area? l-
.A. Unrestricted'd' area B. Uncontrolled area '
C. Controlled area
'D. Radiation area 1
- g.
i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
. . ...... - - - . . .. .. - .:..;.. - - .. :,12; = ; =.;; - .. .,,, , . .
Pege 66
..6. PLANTSYSTEMS(30%FAhDPLANT-WIDEGENERIC
= RESPONSIBILITIES-(13%.).
P QUESTION 6 ~.18 (2.00) ,
-What is the definition of a HIGH RADIATION AREA? -'( 1 .' 5 ) -
A. B. Who (title) shall authorize entry into a High.Radiahion Area? (0.5). 1 u 1
)
J l l' l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l
~ --- - ' - '-~~ ~
E,-
,.w .. _ .. .... - -'1~-~~~~ ~T~ ~~ 3
,- , e 1 f J
. P a g e 6 7 ...
1 61 ?SANT SYS"3MS-(30%)'AND PLANT-WIDE: GENERIC MSEQNS::B:: s1 TIES-(13%) '
, .c QUESTION: 6.19 (1.00)
!What is the significance of posting a controlled area with a radiological.-
DANGER sign as. compared to posting a controlled area with a radiological. CAUTION sign? (*:**** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
;p ..
. ,- - - w .-. ,.. g .. .-..,, ... . . . . . - __ _ - - - ____- ___ _ _ -
~ ~
6 '. PLANT' SYSTEMS ~-(30%')'kNDPLANT-WIDEGENERIC~ > 'Page 68
--RESPONSIBILITIES (13%)
-QUESTION -6.20'. ! '( 0 .- 50 ) .. ,
i During.what EMERGENCY CLASSIFICATION (S) should the Station Director ~ initiate an evacuation for non-essential personnel? l l .l.. i r a l-i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i L :
y-
.,., .n Pege'69 6. ! ? d4T S"SIEMS_(30%) AND PLANT-WIDE GENERIC
( ES?ONS".BILITIES (13%) [.
. QUESTION 6.21' '(1.00)
Lf In accordance-with BAP 1450-7, " Confined Spaces Entry," WHO'(title) maintains the. Confined' Spaces Entry. Permit Log, AND-how often should he/she review active Confined Spaces Entry Permits? (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1
, . s .. ;y
- 6. 'PLANTSYSTEMS(30%)A51DPLANT-WIDEGENERIC' ,
'Pege'70 RESPONS1HILITIES (13%)-
-)
1e I; l LQUESTION- -6.22 (1.50) - j Li EXPLAIN how' access'to the reactor cavity incore area is1 controlled in order to prevent-unauthorized / inadvertent entry? (Assume all administrative' paperwork-l end: radiological-requirements have been met) l l I (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
Page 71
- 6. PLANT' SYSTEMS (30%) AND PLANT-WIDE GENEELQ RESE9ESlHlkITIES (13%)
I i
~
QUESTION 6.23 (1.50) . i One of the Shift Engineers actions following a reactor trip is to ensure that the plant is placed in-a' safe condition by observing that the necessary operations are performed in accordance with approved procedures. What are THREE other actions that the Shift Engineer SHALL take following a reactor trip? (Assume a reactor trip is the only event that took place and~that no GSEP emergency actions level exist.) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) _._m__.m. _ . _ _ . _ _ _ _ _ . _ _ _ _ . _ _ _ _ . _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ = _ _ _ _ _ _ . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ = _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _
Page'72'
. 6 '. PLANT-SYSTEMS (30%) AtQ PLANT-WIDE' GENERIC -
RESPONSIBILITIES-(13%1-
-QUESTION 6.24 (1.00) -
Answer each of the following questions concerning BAP 1101-11,." Implementing Procedure for Fire; Fire Chief."
.A. Who (title) normally will function as the Fire Chief? (0.5)
. B .' .If the Fire Chief cannot get to the primary fire equipment cage on the
'401 foot elevation of the Turbine Building due to the location of the fire making.it hazardous, WHERE would he.go upon notification of the fire? (Be specific) (0.5)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) I, I J
- 6 '. PLANT SYSTEMS (30%)'AND PLANT-WIDE GENERIC 'Page 73 RESPONSIBILITIES (13%)
l ' - QUESTION 6.25 (1.00) . , l The'NSO reports to.the SE that he believes the procedure he'is using to test
.the Emergency Diesel Generator is inadequate'. What are TWO mechanisms that the SE can utilize to resolve the' suspected discrepancy in the procedure?
i ?, - (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
- 6. PLANT SYSTEMS (30%)'AND PLANT-WIDE GENERIC 'Fage 74
)7 l -RESPONSIBILITIES (13%) , l
-QUESTION 6.26 (1.00)
L Which'ONE of the following statements is NOT correct concerning out-of-service (005). general requirements: l A. If two or more groups are working on a. Job under the responsibility of I one supervisor, only one master OOS card is required. B. If any part of a job will be cleared at a given time, it will be l considered as two or more jobs with'two or more 005 requests and master OOS cards. Blanket 00S requests cannot be used for work on safety-related C. systems / components. D. Master 00S cards are hung first and removed last. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i
- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC
- Page 75
-RESPONSIBILITIES (13%)
1 4 QUESTION 6.27 (1.50) e , BZP 400-4, " Emergency Response Centers Inoperability," describes contingency actions to be taken in the event that the Technical Support Center (TSC) is declared inoperable for a period of greater than 2 hours for other than routine maintenance. What are THREE conditions that would render the TSC inoperable? l
+
V (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********) i _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ l
_ , , , . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ -z- ___ _ - _ - _ _ Pege'76'
..L_ EI6CCR PRISCIELEE (7%1 IjigggnDYNad193' .
G.IU_atp COMFONENTS_(10%) !Ji1@AMENTALS ..EXAd1'.
. ATUWF;t 4.01 (1.00) l
- j. 'D- (1.0) 3ETE?ENCE
! Eraldsc.c d .'.teactor' Theory , Chapter 3, Revie, ion C. pgs. 13-04;
'T+rninal Eerfc.rmance Ob 'ectivec 4-10.
192004M106 ..;KA's) AS2WER '4.02 (1.00) FTC lo the . change in reactivity.(0'5) per degree change in:eff+ctive fuel
- . entre rat u re . (0.5)
CR delta rho (in pcm) (0.0) y;; = ______.___________________.________ delta fuel temperature (degrees.F.) .(0.5) REFERENCE Braidwood Reactor Theory, Chapter 2, Revision 2, pg. 26; Reactor ~ Physics, Chapter 6. Revision 1, pg. 37, Terminal Learnir.g Obj. 11. 102004K100 ..(KA's)
' ANSWER 4.03 (1.00)
C (1.0) REFEEENCE Braidwoud Naclear Theory, Chapter 7, Revisien 2, psc. 00-s6. 100003K107' . (KA's) ANSXER 4.04 (1.00) 3 (1.0) ( utte .;ATEGORY 4 CONTINUED ON NEXT FAGE ++***)
Psge 77 4 MEAGIQE_iBIEGIELES (751_IliESMQ2 631 2 . ("^4matiD COMPCNE*CG f 10%) (FE2&dENI6LS EXAM)
; REFERENCE
~
.braidwood Reactor Theory, Chapter 4, Revision 2, pgs. 24-28.
100006K112 ..(KA's)
-(1.00)
ANCWER 4'.05 C (1.0) I?FERENCE Fraidwood Reactor Theory, Chapter 6 Revision 2, pg. 11, Terminal Performance Objective 4. 130C 0bK107 ..(KA's) ANSWER 4.06 (1.00) D (1.0) EEFERENCE Braidwood Nuclear Theory, Chapter 5, Revision 2, Pgs. 23-29. Terminal Performance Objective 2. 192002K107 ..(KA's) . AN'3WER 4.07 (1.00) D (1.0) REFERENCE Eraidwood Nuclear Theory, Chapter 3, Revisic.n 2,_pgs. 51-54, Terminal Performance Objective 7 100000K127 ..(KA's) J l
.i
(***4* CATEGORY 4 CONTINUED ON NEXT PAGE +++++) i
.f1.,
' )
n Fage 70-i _ilMIC 3_ZS;t'CIPLE3 ' ( 7%) THE'.3d E M102 . 12L._MI.L.CXtGEEMI5 (10%) (E!iE2MENTALS EK6dl AU.9W::R 4.08 (1.50) , (0.5 er.ch) 1, Pre-existing flaw (flaw initiated)
- 2. Tenelle stress. ,
- c. .Lvw-temperature ~
REFERENCE Braldwood Heat Transfer, Chapter 6, Revision 1, pg. 13, Terminal Perf >rmance Objective 2. 193010K101 ..(KA's) ANGWER 4.09 (1.00) (any two at .25 each) A. Symptoms of air bound pump are:
. 1. Reduced (fluctuating) discharge pressure '
- 2. Redaced (fluctuating) capacity
- 3. Reduced (fluctu.ating) motor amps Air bound pump does not have the noise associated with a cavitating pump. -
(.25) E. Vent (:r prime) the pump ( syste.n) . (.25) REFERENCE Braids >od Fluid Flow Chapter 3, pg. 57. 193000K108 193006K111 ..(KA's) ANCWER 4.10 (0.50) (0,5) The temperature of a metal at which nu appreciable deformo* ion occurc E ric r t-failure. temperature at which yield Stret s eq.:3 3 z- the (Ucte: Alao accept . . . fract.tre stress . . . for full credit) Ut**** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
w=y - - w - . . - - -w-..~- - Pege 79.
$ _$3asT,2B_131NCI?LES ('m THERM 22YH6MLGi
. 7u:AUD R E0iiEEIS '100 (ECHRt.MENIEL3 EXAMf t
'REFEE2NCE 16, 33.
.Orai .'.w6cd Heat Transf er, - Chapter 6, Sovision 2,-pg.
190010K100 ..(KA's) ANSWER 4;11 (1.00) Suildap ;f radiatic.n damage in the reactor vessel wall (neutron-induced embrittlement) (.075) causes the Nil-Ductility Reference Temperature (RT-NDT)
- e increase c.ver core life (:auses the reactor pressure vessel to beerme mere brittle)-(.375) resulting in the operating limit curves becoming more restrictive (.25)
.RUERENCE Oraidwood Heat Transfer, Chapter 6, Revisivn 2, pg. 09, Terminal Performance Objective 5.
193010K104 ..(KA's) AN5WER 4.12 (1.00) Q (S/G) : m.(delta h) : . Q (reactor) (0.5) Q (S/G) = 1.0E7 lbm/hr (de1t.a h) delta h = h'(steam) - h (feedwater) delta h : 1190.4 BTU /lbm - 385.9 BTU /1bm delta h : 804.5 BTU /lbm (.25) QL(3/G) : (1.2E7 lbm/hr) (804.5 BTU /lbm)
= 9.65E9 BTU /hr in MW = (9.65E9 BTU /hr)(1 hr/60 min)(.01758 KW/ BTU / min)(1MW/100PKW)
= 2827 MW (will accept 2813 MW - 0842 MW) (0.25)
REFERENCE i Steam Tables; Eraidwood Heit Transfer, Chapter 7 Rev131cn 3. ) l'J 3007K108 ..(KA's) I l
)
(***** CATEGORY 4 CONTINUED ON NEXT FAGE ++++*)
EGGI+23_EEEGIELES ( 72;) 2E30021E6 MIG Page 80 4. GB.1 AND cod 20NENTS (10%) /FUNDAMENI& E_EXbM1 ANNEh 4.13 (1.00) (0.25 each)
- 1. Verifying use of available heat removal paths.
- 2. Verifying 5/G water levei is normal.
- 3. Vcrify a positive temperature dif f erence exists between the ce.re er.! the C/G.
- 4. (or slightly above) the ateam.
Verify ecid 1(+gKC5 temperature. temperature cold leg WA+m constants O sa.6% gem fe x6 pnas.ee) 4 afgnfjj "+ 'g ware ~*o 2 we ,- m .x.d.,,
- b. A w e. y el 4ea ngoV ccre. e4 .tlemeewple h,orole de.ac.es .
Braldwood float Trancfer, Chapter 5, Revision 2, pg. 40 193008K123 ..(KA's) ANSWER 4.14 (1.00) Since steam density varies with changing power levels (0.5), the steam flow
. signal also utilices steam pressure as an inin.t (.25) since density is proportional to pressure in a saturat+d system (.25)
OR Volumetric flowrate is proportional to D/P across flow restrictor Density ( .25) and - mass flow is proportional to (square root D/P)x(density) (.25). is proportional to pressure in saturated system (.25). Therefore, mass flowrate is proportional to (square root D/P)x(Pressure) (.25) REFERENCE Eraidwood SGWLC System Description, pgs. 18, 21. Terminal Performance Oi>jective 6. 193006K112 .(KA's) ANEWER 4.15 (1.50) Decrease (05) (The ranning RCPs are now drawing less current) b+;cause they are p'.urping at les.e capacity (0.5) since total P.CF head increased to.5) (when the fourth RrP waz stu_ted). (***** CATEGORY 4 CONTINUED ON NEXT PAGE
- r"t)
L_--______-_-___-_______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Page'81 '
-Am_SEACTOR FRI G ELES (7ft,I THERMQ2H A E S -
-(?x1_6DD COML2EEEIg '10%) rFUNEbMENTALS EXAM)
' RE?EF EN'.1E Frailw.ed Fluid Flow Chapter 2, Revision 3, pg. 28, 131::Or K104 ..(KA's)
' ANSWER 4.16 (1.00)
Low discharge pressure air A. High flowrate (flowrate beyor.d design) Mggteach) B. Overhe ting the pump (0.5)
.REFERENCZ Braidwood Fluid Flow, Chapter 2, Revision 3, pgs. 63-69. Terminal Performance Objectives 7, 8.
191004K112 191004K104 ..(KA's) ANCRER 4.17 (1.00) A. Head Point 1 = operating point for 1 pump (0.25) running a operating point for 2 pumps Point 2 running- (0.25) Volumetric flowrate
- 3. Point 2 indleates system operating point 1 after FCV-121 is shut slightly (0.5)
Eead i Volurnetric flowrate EEFEREN0Z Braidwood Fluid Flow, Chapter 2, Revision 3. Terminal Feriormance { Objectives 5, 6, 191004K114 ..(KA's) (***** CATEGORY 4 CONTINUED ON NEXT FAGE ***tt) ) l l
s. Psge 82 iu _[laEIQ5_fE2dCIPLES (7%) THEhdQLEMIGS in1 AND COMEQt!ENTS_f12M_LE!RiE6dEUIbkS_EZM1 9 i AtidG 4.18 (1.50) (If :-).e .perator releases the control swit,ch from the close positicn to the after elc u position prior to ruceiving the breaker closed indicativn), th+/n the AR-3 relay, which carries'a high current, (0.5) will de energi:9 (.25). { The AR-3 relay contacts will then have to break this high current (0.5).which a j tenda t:, Sestroy the contacts. (.05) 1 I EEFERENCE Eyran Special Operating Order S0-S7-0019. 19:009K137 191008K104 ..(KA's) ANSWER 4.19 (1.00) Frevent :nctor thermal insulation degradation. (1.0) J REFERENCE
.EAP 300-1, Revision 1, pg. 20.
191001K108 ..(KA's) ANSWER 4.20 (1.50) 1.. When the fluid flows through the venturi (restriction) a drop in pressure and a simultaneous increase in velocity will occur. ( 0. '/ 5 )
- 2. The change in pressure created by the restriction is proportional to flow
(;quared). (0.75) REFEhENCE Ersidwavd ISC, Chapter 1, pgs. 02, 23, Terminal Perf c rmance f Obj:etive 10. 19:002K105 ..(KA's) l J AN3WER 4.21 (1.50) I The FCP requires a starting current (0.5) to start the pump and its motor l l rotating (overcome rotational inertia of retating assembly) (0.5) which is. ! additional to the current required for actually pumping the finid (0.5) I r (t**** CATEGORY 4 CONTINUED ON MEXT PAGE *****)
.,-_. ~, - --
- 7. w Page 83 ,
, 1 4!aGIQE_ESIS9IILEQ f7t:) THERMcDYNAtilG
. ~*',y AND COrgG;ENTS (10%2_LET)dDAMENTALE EXMJ FIFFRENCE Drai N xd Fluid Flow, Chapter 2.-Revision ?., pg. 63. Terminal
_%rformar.ce Objective 9. 191305K105 ..(KA's)
'(1.90) i -
TEWER 4.22 To deter.nine activity lev +1s of both ' inlet and outlet of the'ian exchanger ( . ':.5) in order to det+rmine the decontamination f actor (DF) of'the icn-e.< changer .( .125 ) which is used in determining the ion excht.nger effi:lency.(0.75). REFERENCE
'Braidwood Chemistry, Chapter 6, Revision 4, pgs. 29-33.
131007K103 ..(KA's) (***** END OF CATEGORY 4 +++++) ; 4 a___--______ _ _ - _ _
g_ A rege 84 L _._ M EGENCY_AND ABNQ M LELANT EVOLUTIQtM
.LI2I.[1.1 l l 1
AN.;'4ER' 5.01 (1.00) Ja n/a ws.rking properly (0.5). The programa.ed PZR level at-the given power level ud ~'evg should be 48%. (0.5) T4EFET(ENCE Braidwood System Description, Chapter 14, Eevision 6, Figare 14'O. , C C C 0 2.2 A*.'0 0 ..(KA's) ANSWER 5.02 (3.00) A. Prevents the release of activity should a steam generator t,ube rupture
. (1.0) since saturation pressure of the reactor coolant (0.5) is below the lift pressure of the atmospheric steam relief valves.
B. Ensures (an appropriately small fraction of) 10 CFR 100 cite boundary
- dose limits are not exceeded (1.0) following a EGTh accident (0.5).
EEEE3Et:CE BOA PEI-4, Revision 52, pg. 4; Byron Technical Specification Bases pgs. 4-5, 4-6. 000076G004 000076K006 ..(KA's) . At!3WER 5.03 (1.00) Ensures that sufficient water depth is available to remove 39% (0.1) of the assaaed 10% (0,1) iodine gap activity (0.4) released from the rupture of an irradiated fuel assembly (0.4).
- 0 R.-
e; 6* er.ny' (Pre'. des lagegre htp+ 4e. e.ved luu sf k erv. ' RH a sseek uAs(..is)ak i+9 eme
~ ~ ~ ,n t. ,s , Vs freeed e s (. es-)
p p s.) t,,; Syron T+chn caI*Ipe b i N51:N '.s . 000006G004 ..(KA's) AN3WER 5.04 (1.50) 7:. prsver.t uncontrolled filling of any swam generater ( .75) and the associated excessive RCS cvoldown (.75). 1 (***** CATEGORY "; CONTr.40ED ON NEXT PAGE * * * ")
=. , . ;- - - - - - - - - - - - - -
j Fago 85 j
- h. 33E32ENCY AND 6E'3ORGL Pl A*JT EVOLIEIONE. J LEGI 1
REFERE: ICE - By r...n EE? -0 , pg. 6; MOG ERG Backgr..ntnd Documents. 000C07K301 ..(KA'a) ANCWEL 5.05 ( l' . 50 )
~Thl a sares that the proper pH values for containment 4, pray are maintair.ed (1.0) .<en with the'lves of instrument air (0.5).
I.EFERENCE - Braidwood Gystem Description, Chapter 53, pg. 46. 000065K303 . (KA's) ANEWER 5.06 (2.00) Wi:,hout control air, the compressor unloader valve fails open (0.5) and start,ing the compressor with the unloader valve epen will cetuse-the compressor-
-;to hunt for a pres mre (0.5) which could cauro damage to the compras.scr (1,0).
REFERENCE Braidwcod System Description, Chapter 53, Revision 3, pg. 45. - 000065G007 ..(KA's) AN3WER 5.07 (1.50) h*M Terminate SI to stop primary to secondary leakage 4--1.^'gand the "!. pumpc are placed in standby to ensare they ar+ available if needed -(? - REFERENCE WOG ERG 33ckground Document E-3, pg. 113. 000i08K309 .(KA's) ANOWER 5.08 (1.00) Ensure aafe shutdown of plant ( . 7 5) and the ;nitigati.n ( ar.d ce nt rol) .f ac:iden., conditions (.25). . (***** CATEGORY 5 CONTINUED ON NEXT PAGE ***tt)
Page 86' G. EMX"., Cit'Cvd8D ABNORUMNT .EynLUTTONG O lL%l I BEFEFINGE i Dyron Teclu.ical Specification Bases, pg. 3/4 8-1. 0000560004 ..(KA's)
, ASDCR 5.09 (1.00) ,
icas of c:ntr51 power. (1.0) hygsgins+rameMbus' ttL Braidwocd System Description, Chapter 31, Reviulon b. pgs. 54-55, Figure 31-1, Revision 0, Terminal Performance. Objective 8. 00003CK201 ..(KA's) A2:5' DER 5.10 (3.50) BET-1 green B3T-2 Yellow (BFR-C.3)
.DET-3 Yellow (BFR-H.5)
~BST-4 Yellow (BFR-P.2).
BST-5 Orange (BFR-Z.1) BST-6 Green (0.5 each condition) Prioritizing Procedures t,o be performed
- 1. BFR-Z.1
- 2. BFR-C.3
- 3. SFR-H.S
- 4. BFR-P.2 (0.1 each correct procedure, 0.1 correct order)
BEFERENCE Bryong CSFSTs Unit 1, Revision 2. 000040G012 ..(KA's) i I i l ANSWER 5.11 (1.50) f1.9) of no j Ensures containment peak pressure won't exceed design pressure psig M.?'" ( O. MOpduring steam line break conditions (c. 4)
-OD i s.o' L.k;b c.da;-eai grewsre 4. a peak presss.-e %) .f w.9 p;3 (o.,) l dse. 4. a deskte eMea Rts c old Ic3 break Cose)(c.9)e,
(***** CATEGORY 5 CONTIN *JED ON NEXT PAGE *****) 1 - _ _ - _ - - _ _ - _ _ . _ _ . . _ _ 1
L__ 3'"32151 4S_.Ay NCRM A dEdn._EEQ~i?T I Ob'S ?ase 87-L$11 6EFERENCE' Oyren Teeltnical Specificati>n Bases. pg. 3/4 6-1. 000340K006 ..(KA's)
~ AN04.ER 5.12 (1.00).
A. 100 VAC Instrument Bus 111. B. 1:0 VAC Instrument Bis 112. (0.5 each) REFEEENCE Sraidwsod Oystem Description, Chapter 32, Revision 1, pgs. 18, 19. 000033K001 ..(KA's) (1.00) ANSWER 5.13
.1. Any Rx Trip first out annunciator.
- 2. Rapid decrease in neutron level as indicated on NI's.
3 ^. All rods (shu-dewn and control) fully inserted (rod bottom lights lit). .
- 4. Rapid decrease in unit load to zero power. (.25 es.:h)
RE'ERENCE F Eyron IEF-0, Revision 2A, pgs. 1, 2. 000007G911 ..(KA's) I AN3WER 5.14 (1.50) 55B deg.F is the technical specification minimum temperature for critie.411ty (0,5) if Tave is less than 550 deg.F, then it must be reatored to with'n its li mi- 'O.5) within 15 minutes (0.5). FEFEEENCE E0A EOD-4, Revision 53, pg. 2, BOA-4 Lesson Plan, 7evision 54, pg. E. 0000030008 , 000000G003 ..(KA's) ("M** CATEGORY 5 CONTINUED CN NEXT PAGE rtv+*)
c, . , Fage 88 JL. EE.31!.XSGY._45D_ADUORMAL_2LABI E2QLUTIOUS' ,
.L:a ss.,
l^ . 1 A*l 9. CR .5.15 (1.50)- l'1. 5 5 ',: or Er.c ws nainst: possible opera ,or misdi., gnosis (0. F), opera t.or error .
' a r.iulti. le s . f ailure event scenariu . (0. 5 ) .
~
I-F EJEDENCE , W'G EEG ~ Bae4rcund E -3, Fg. 50. 00000EK003' ..(KA's) ANSWER- .5.16 (i.00) Manually trip the reactor. (1.0) EEFEEENCE E0A KCD-1 Lesson Plan, Revision 53, Pg. 5
- 000031G010 ..(KA's)
ANSWER 5.17. (1.00)
- 78% (will accept 77.5 - 78.5) (1.0) .
REFERENCE Byron Technical Specifications 3.1.3.1, 3.1.3.6. 0000000003 ..(KA's) AN.?WER 5.18 (1.00) The. limit is higher becauae the 305 is somewhat c..aler (1.0) . (Alevjeal.am l te:rp-n ature of cooling water to RCP-motor bearinge is 130 deg.F per ECF Toch. Manual will be accepted fcr half credit). FE7EFENCE 50A F3!-6 ~_esson Plan, Revisivn 53, jg. 21
- 0000260C 07 ..(KA's)
(**$1* CATEGORY 5 CONTINUED ON NEXT FAGE +++*r) , _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ ]
m.+..w ,um ,, ,
~ ~ ' ~ ' ' ' ~ ~ ~ ' ~ ' ' ' ' ~ - ~ - - - - - - - - - - - - . . - . - _ . _ , _ _ _ , _ _ _ _ _ __ - - - - - _
~
j d' Fago 89 L L__2, . E. Ea.s;lCI_6ED_6EKEMAL_ELaNI- EVOLUIlQNs
- =::.:u. .
W:0WFR 5.19 (1.50) The ?,/'l WR: level indicators are cold calibn t+d (0.5). As S/G temperatt.res d.;creare (due to plant'cooldown) (0.5; WR 1+ vel indication will increw.e f'or.a i;i . en 'e c. nant level (O.5). ( A1.se ..w.ept explanation of whter bec.: ming mre dense during cooldawn whis h. so. tid : ...c.e imlicat. d le .w l to incresce. ) EEFERE.'JCE E0A FEI-5,- Revision 50, pg. 10. C00069A201 ..(KA's) A!!5WER 5.20 (0.00) Do not apply (0.5) because activation of the Remote Shu*.dc.un as determined Pa.wl authorizes by the dircet entry into applicable emergency procedures (1,0) . SRO (0.5).
-REFERENCE BOA PRI-5, Revision 50, pg. 3.
000068GC12 ..(KA's) ANSWER 5.21 (3.00) Would not (0.5) because the Cc.nstant, Voltage Transf >rmer is mechanically interlocked with the invert r (1.0) (to prevent them from simultaneously supplying the instrument bu power s,. # 2f the transformer were pljeed in and a reactor ce rvi.;;e , a momentary loss o would occur to bus 111 !^ ' trip w:uld occur '
" (bistables fr r ancther chonn+1) areinthet.ripledfoun#sinceNI-43bistables dition (.05).
@ 74 (o.s)J EEFEF.ENCE pgs. 50 54; Eraidwwd System Description, Chapter 4, Fevision 4, PCF I N , Revision 52A, pgs. 1, 2.
00005'A220 000007G007 ..(F.A*s) i i l 0+++"; (tt*** END OF CATEGORY i
g :- - - -
=: , .
n .y Tage 90 l 1 __J:I.62I_E"3IEU M 50%) AND_fMSI_-W12E;GEEE31g.
- , TGiCGUEli;IIEU1El-At
- CWER 6.01 (1.50) 1 Safety injection signal pr+sent'
- 2. ~1o-lo level.'in RWST (.75 each)
M:!EREtCE Eraidsvod Cystem Description, Chapter 18-Lesson Plan, Rev'ision: 4 , - pg . 2 0 '. Of.5000K402 ..(KA's)
'hNSWER 6.02 (1.50) l '. Ov+rspeed
- 2. Load. Drop Anticipator p
- 0. Interceptor Valve Fast Valving (0.5 each)
.EEFERENCE .
'Braidwood System Description, Chapter 37A, Revision 2,.pg. 04;
. Terminal Performance Objective V.
045000K413 ..(KA's) AN5WER 6.03 (2.00) Al.
'Ecth stationary and movable grippers energine (0.4) on low current (0,1).
and all (auto, manual, bank select) rod motion is inhibited (0.5). B. 2-(1,0) i
- REFEREl'CE
~Draids.aod System D+scription, Chapter 28, Lesson Plan, Revisien 4, pgs 50, 76; Turminal Performance Objective 10.
001050K401 001000G007 ..(KA's) (**=** CATEGORY 6 CONTINUED CN NEXT ? AGE *** 6)
L.- j:.
?nge 91 lS . ELA3I_dY.IMD_.[DQt)-AND I ELANT-WIDE._ GENERIC GTsTIEIHLIIIER_L12U A9.'wFR ?. 0 4 (2.00)
?. . (..ny.4 at 0.375 each) 1, Duction ~to spent fuel pimps slightly (4 ft) below normal water'leve2, C. Anti-alphon hole on sper.t -fuel pumps discharge lines. .
~3. Gpent, fuel pump dischargs line stops (6 ft) above fuel.
- 4. 'No drains a the spent fuel pool
- 5. Open 31ulo gate with dry transfer canal would only drop SFP level (6'ft) elightly.
D. (.25 each)
- 1. RW5T.
- 2. Primary water REFERENCE
..Braidwood.3ystem Description, Chapter 51, Lesson Plan, Revision 3, pgs. 50 ti2; Knowledge Objectives 5, 6.
.033000K401 ..(KA's)
ANSWER 6.05 (2.50) During an emergency start, both the air compressor and air dryer start simult Anecusly (O'5) at 245 poig (0.1) in the air receiver (0.4), and then beth stop (0.4)' when air receiver pressure reaches 255 psig (0.1). During a test start the air dryer starts first (0,5), and then the air compressor starts after'a time delay (0.4) of about 30 seconds (0,1). REFERENCE Braidwood System Description, Chapter 9, Lesson Plan, Revision 4, pgs. 24, 25;
' Terminal Performance Objective 2 064000F.105 ..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
Pege 92
- {! . . ELMI_QUIEtG ' ( 300 AND PLMI.-HIDE _ GENERIC ggaroNo131;;Ilsg_LL10.
t l' . f L AN.NER 6.06 (1.00) R:ac ue Jill not trip (0.5) l Trir blocked by loop flow permissive (F-8)-since 2 out of 4 power range NI's ( . 2 5 ') are not greater then 30% p.iwar (.25) . EEFERE.CE N Praidwood Gystem Description, Ch3pter 60b, Revision 4. pg. 24; Terminal
.Perforn:ance Objective 4.
012000K610 ..(KA's) ANSWER 0.07 (2.00) i The underfrequency' condition would lower the RCP speed (0.5) with a rest'. ting I drop'in RCS flow (0,5) and shorter flow coast down period (0.5) which could result in exceeding minimum DNBR if the underfrequency cor.dition was severe" enough (0.5). REFERENCE Braidwood System Description, Chapter 60b, pg. 15; Terminal Performance Objective 5. ' 012000K402 ..(KA's)
. ANSWER 6.08 (1.50) on E The S/G. following 4 i . 2.5 i actions)will
(.375 occur at 78.1% narrow range (will accept 73
# -1. T ripa ZR',' (,25 :nd bypc.:-: =1; c 2'4-l /. Trips MFr?( . 25d) 37d 17 Trips 11ain Turbine ' Z T(37d -.
&4. "; .;;.: :
.d u.;.1+tscn ,alv(2--(-25; 37 7
- 5. C.w us KEFERENCE
{ees w4<r sSeta% pg. 10; Etaidwood Oystem Description, Chipter 22, Lesevn Flan, R+ vision 3, Byron PL5 pg. 17. 035010E112 ..(KA's) l ("*** CATEGORY 6 CONTINUED ON NEXT ? AGE *****)
Pags 93 du_ELduI ~YDTElf (305.) AND PLANTdlDE_GENEPlG EME2ESIEIL111EQ_L1 W1
/.N2WER 6.09 (2.00)
All heaters will-energize (0.5) and the. spray vialves will close (0.5; ( ti;. respond to censed low pressure condition). RCS pressure will continue to In ren.;e until PORV 456 opens at 1335 psig. ( 0. 5 ) RCS pressure will then ce.;i;1 ate between 2315 psig and 2335 psig as PORV 456 occillates (0,5) ' s t.A Nok! r4lsoc,o,4.xessept s.r. ped *n o m,,e seg k".pbee.xe"..,y 4.p. hk9 sf
,. ,. o. d,,, n f, C"Vulse'
,4., o w.
i;EFERENCE n,, ,
, g ne rttiue. b.nl eedit.(o.ar)p+s. .s M be. de4.,clu , og tso e.F s w.nr.a . , .
Eraldwood Eystem Descr'iption, Chapter 14 Revialon 6, y s. 55-59; esp m;o u . y Terminal Performance Objective 21. 010000K403 ..(KA's) AN3WER 6.10 (2.00)
- 1. Pressure equalizing valves are interlocked (0.5) so that only one valve can be opened at a time (.25), and only when the opposite door is closed
(.25).
- 2. The air lock doors are interlocked (0.5) to ensure that one door is completely closed before the oppr> site door can be opened (0.5).
REFERENCE Braidwood System Description Chapter 40, Revision 3, pgs. 21,22 103000K404 ..(KA's) I ANSWER 6.11 (2.50) A. 1. FW 009 - OPEN
- 2. FW 043 - CLOSED
- 3. FW 035 - OPEN
- 4. FW 034 - OPEN (0.25 each)
B. ' rnsures sufficient flow thr: ugh the aux feed noccle (.25) to maintain subcooling (prevent steam f ormation in aux feed li:w) f.0.5)
- 2. I.imit flow to the mein tocale (.25) to re: luce tube vibration problems (0.5).
1 i l I
*****1
(+**** CATEGORY 6 CONT:NUED ?N NEXT FAGE L i l
- - :._- . ~, - - - - - - - -
.Page 94 f;: EkaElRIEE3_L20!j) AND PLAN'"-WIDE GEMEElG tEEE20.IEILIIIE3
; (13%)
h2FE.~C CE Fr,ldw ed' ?ystem Descrip',1c n, Chapter 25, Lessen Plan, Revisic.n 7, prs. 06-40. n500ccAina .,(KA's) ASCWER 6.12 (2.50) A. 1. Restrict,cd lube oil filter i 2. Air box cripped
- 3. .High water temperature
- 4. Low cil pressure
- 5. Restricted fuel oil filter
- 6. High crankcase pressure (any five at 0.25 each)
- 7. Lom) r,slicA o.& in A A* (4 . cal w ; b in cFrerp)AA4ut.)g
- 3. Low AFW pump suction pressure coincident with any one of the following (0.5).
- 1. lo-lo S/G 1evel (0.15) on 2/4 channels in any.one S/G. (0.1)
- 2. RCP bus undervoltage (0.15) on 2/4 RCP busses. (0.1) -
-3. Any SI '(.25)
ItEFERENCE Braidwood System Description, Chapter 26, Revision 4, pgs. 26, 39. 061000G008 061000K401 ..(KA's) ANSWER 6.13 (2.50) A. 1. RCP oil lif t pump discharge pressure greater than 600 psig. (0.5)
- 2. Loop isolation valve interlock. (Hot leg and cold open, or cold leg shut and bypass open.) (0.5)
B. To pr+ vent overheating RCP seals (0.5) and ivw+r radial bearing (3.5) d u .:- to ho; RCS water flowing up FCP shaft (0.5). i REFEEENCE pgs. 30, Braidweed System Description, Chapter 13, Lesson Plan, Revision 5, 50. 003000K403 003000E404 ..(KA's) l l (H*** CATEGORY 6 CONTINUED ON NEXT PAGE "* *)
- i. :
Page.95 5; ELANT CISIEMG_12231_AEILELANT-WIDE GENEBlt L;sro:07?; LIT:Es (10s2 ; I .. 9.14- (2.00) I At:SWE3 M d at bottom alarm would not annunciate-(0.5) because-it is bypass +d-A.
.mtil e rod in bank D (0. 4 ) reaches M etepe.~(0.1).
9 B. :RP: .1:.dicates a:tual rod position (0.5) while-the step counters indicate d . mare.'ed rod position (by counting pulses f rom rod control system to. move ride) (0.5) REFERENCE Eraidwood System Description, Chapter 29, Lesson Plan, Revision 5,-pgs.'14-20;
. Terminal Performance Objective 5.
L 014000K403 014000K501 ..(KA's) ANGWER 6.15 (1.00) A. 35 deg. F to 2300 deg. F (0.5)
., B . LED display (0.25) and the acitnewledge pushbutton will start flashing.
(0.25) REFERENCE Braidwood Description, Chapter 34b, Revision 3, pgs. 20-21; Terminal Performance Objective 7. 017000K403 017000G008 ..(KA's) ANSWER 6.16 (1.50) A. Running (0.5) because the C3 signal stays in until it is roset (0.5) B. Clow speed (0,5) REFERENCE BrairJwood System Description, Chapter 61, Eevial.sn 3, pgs. 31, 59. 013000K103 013000K105 ..(KA's) ANSWER G.17 (1.00) B (1.0) ($4++* CATEGORY 6 CONTINUED ON NEXT PAGE **+**)
- - _ - - - _ _ _ _ _ . _ - . _ _ _ - - . _ _ - - _ - _ - - _ _ _ _ . - - . _ - _ - _ . _ _ - - - _ _ _ _ . _ _ ~ _ - _ - - - _ - _ _ _ . - -
Fa.;e 96 6 FLANT OYEEM.D 00%L632_EL&$1-MDE GENERIC . , SEE.FCuSIBILIIIES-(13E1 REFERENCE ERP 1000-Al Lesson Plan, Revision 1, pg. 5 Terminal Performance Obje.; t t . e 1. 13400:K103 ..(KA's) AN3WER 6.1d (2.00) A. Any area accessible to personnel (0.5) in whi:h there exists radla:1vu at. w:h levels that a .najor partino of the Lcdy could receive ( 0 f. '. .;*; cater than 100 millirem in any one hour (0.5) B, Shift Engineer-(5E) (0.5) IOp+ rating Department Chift Supervis,r). REFE.32NCE
-DRP 1000 Al Lesson Plan, Revision 1, pg. 5, Terminal Performance Objective 1; BEF '.000-A1, Revicion 3, pg. 7.
1?4001K105 ..(KA's) .
$N3WER 6.19 (1.00)
Danger is used on high radiation area signs only (0.5) while caution would be-used on all other radiological signs and labels (0.5). . REFERENCE b'RP1000-AlLessonPlan, Revision 1, pg. 8; Terminal Performance Objective 3. 134001K105 ..(KA's) ANSWER 6.20 (0.50) Gite emergency. General emergency. (0.25 each) REFERENCE BZP Lesson Plan, Revision 3. pg. 28; BZP 310-4 Reviaion 7 ;g. 1 194031A116 ..(KA's) i (uw** CATEGORY 6 CONTINUED ON MEXT FAGE **A'+) - = _ _ _ _ _
'Pago 97-O. -kk6EI_GYQIE01_122%) AND PLANT-WIDE CEMEBIG
- A ;5EGNS111LillE3 (13*Q I
l I ANGWER- 6.21 (1.00) Shift Siipervisor maintains log-(0.5) and should review active permits each shift. (0,5) REFERENCE 1 BAP 1450-7, Revision 4, pg. 5. 104001K114 ..(KA'a) ANSWER 6.22 (1.50) The reactor cavity incore area hatch cover is locked (0.5) with two padlocks (.25) and there are two keys, (.25) controlled by two separate people, that.
- are required for entry. (0.5)
REFERENCE .
~
19 ( 1K10 (Kk'sf' ANSWER 6.23 (1.50) . (any three at 0.5 each)
- 1. Notify the SCRE (call the SCRE to the control room),
- 2. Determine recovery actions to be taken.
- 3. Notify ASO (Assistant Superintendent Operating) or (duty Operating Engineer).
- 4. detify appropriate offsite agencies (notify NRC).
- 5. Ensure reactor trip documentation is completed (log reactor trip).
REFERENCE BAP 300-1 Revision 1 pg. 7 134001A109 ..(KA'c) AN5WER 6.24 (1.00) A. Designated Shift Foreman. (0.5) B. S:,ckup cage on the 451 foot elevation (.25) of the Turbine Building (-. 0 5 ) , (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
saw- -- .. __ u., ..-,.. v . __ . . _ _ _ . _ . ~ .
-Pag 2 98
- 6. PLMT SYSTEMS (30%)" AND PLAT!I .W_IDE_.GEMEEIC L .RESPON3IBILITIES (1341-V l
[ REFERENCE BAP- 1100 -11 ~, Revision 3, pg. 1.
'194001K116 .(KA's)
'AN5WER 6.25 (1.00)
- 1. Determine a way that the test can be performed by using the procedure as written. (0.5)
- 2. Submit a procedure change. (0.5)
REFERENCE BAP-300-1, Revision 1, pg. 22. 194001A103 ..(KA's) )' ANSWER 6.26 (1.00)
.D (1.0)
REFERENCE BAP-330-1, Revision 2, pgs. 5-7. - N 194001K102 ..(KA's) ANSWER 6.27 (1.50) ,
- 1. Loss of power.
- 2. Loss of most or all communications.
Loss of dose calculation capability (Model C)
'3.
- 4. Area becomes uninhabitable. (any three at 0.5 each)
REFERENCE BZP 400-4, Revision 2, pg. 1; BZP Lessen Plan, pg. 32; Terminal Knowledge Objective 6. 194001A116 ..(KA's) (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********) is
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