ML032480959
| ML032480959 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/26/2002 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-390/02-301, 50-391/02-301 | |
| Download: ML032480959 (149) | |
Text
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Administrative Documents WATTS BAR EXAM 2002-301 50-390 NOVEMBER 26 &
DECEMBER 9 13,2002 -
- 1. Exam Preparation Checklist ..................... ES-201-1
- 2. 4 x a m Outline Quality Checklist . . . . . . . . . . . . . . . . . . ES-201-2
- 3. J Exam Security Agreement ...................... ES-201-3 J
- 4. /Administrative Topics Outline (Final) . . . . . . . . . . . . . . ES-301-1J
- 5. J Control Room Systems and Facility Walk-through Test Outline (Final) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ES-301-2 f l
- 6. 'Operating Test Quality Check Sheet . . . . . . . . . . . . . .ES-301-3 J
- 7. /Simulator Scenario Quality Check Sheet . . . . . . . . . . . ES-301-44
- 8. /Transient and Event Checklist . . . . . . . . . . . . . . . . . . .ES-301-5 J
- 9. /Competencies Checklist . . . . . . . . . . . . . . . . . . . . . . . . ES-301-6 I O . /Written Exam Quality Check Sheet . . . . . . . . . . . . . . .ES-401-7 J
- 11. $JVrittenExam Review Workshe$. . . . . . . . . . . . . . . . .ES-401-9
- 12. 'Written Exam Grading Quality Checklist . . . . . . . . . . . ES-403-1
ES-201 Examination Preoaration Checklist Form ES-201-1 (R8,Sll Facility: Date of Examination:
Target 1 Chief Date* Task DescriptionI Reference
~
-180 1. Examinationadministration date confirmed (C.1.a; C.2.a & b) LM
-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e) LM
-120 3. Facility contact briefed on security & other requirements (C.2.c) LM
-120 4. Corporate notification letter sent (C.2.d) I LM
[-go1 [5. Reference material due (C.1.e; C.3.c)l I LM
-75
~
- 6. Integrated examination outline(s) due (C.1.e & f; C.3.d)
~~
I LM
-70 7. Examination outline s reviewed by NRC and feedback provided to facilitv licensee (6.A.h: C.3.e) I LM
-45 8. Proposed examinations, supporting documentation, and reference materials due (C.l.e, f, g & h; C.3.d) I LM
-30 9. Preliminary license applications due (C.l .I; C.2.g; ES-202) I LM
-14 I O . Final license a plications due and assignment sheet prepared LM (C.1.l; c.2.g; 2s-202)
-14 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f) I LM
-14 12. Examinations reviewed with facility licensee (C.1.j; C.2.f & h; C.3.g) I LM
-7 13. Written examinations and o erating tests approved by NRC suoervisor (C.2.i: C.3. t: I LM
-7 14. Final applications reviewed; assignment sheet updated; waiver letters sent (C.2.g, ES-204) I LM
- 15. Proctoring/written exam administration guidelines reviewed with LM
-7 facility licensee and authorizationgranted to give written exams (if applicable) (C.3.k)
-7 16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i) I LM They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.
1] Applies only to examinations prepared by the NRC.
ES-201 Examination Outline Form ES-201-2 (R8,Sl)
Quality Checklist
-aciliP Date of Examinati Item Task Description
- -a
- 1. a. Verify that the outline(s) fit@)the appropriate model per ES-401. RLM w - I R b. Assess whether the outline was systematically and randomly prepared in accordance with RLM I
T Section D.l of ES-401 and whether all KIA categories are appropriately sampled. -
T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. RLM E -
N d. Assess whether the justifications for deselected or rejected KIA statements are appropriate. RLM
- 2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of RLM s
normal evolutions, instrument and component failures, and major transients. -
i b. Assess whether there are enough scenario sets (and spares) to test the projected number RLM M and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity; ensure each applicant can be tested using at least one' new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s)-, and scenarios will not be repeated over successive days. -
- c. To the extent possible, assess whether the outline(s) confon(s) with the qualitative and RLM
- quantitative criteria specified on Form ES-301-4 and described in Appendix D. -
- 3. a. Verify that: RLM (1) the outiine(s) contain@)the required number of control room and in-piant tasks, w (2) no more than 30% of the test material is repeated from the last NRC examination,
/ (3sno tasks are duplicated from the applicants' audit test@), and T (4) no more than 80% of any operating test is taken directly from the licensee's exam banks. -
- b. Verify that: RLM (1) the tasks are distnbuted among the safety function groupings as specified in ES-301, (2) one task is conducted in a low-power or shutdown condition, (3) 40% of the tasks require the applicant to implement an alternate path procedure, (4) one in-piant task tests the applicant's response to an emergency or abnormal condition, and (5) the in-piant walk-through requires the applicant to enter the RCA. -
- c. Verlfy that the required administrative topics are covered, with emphasis on peiformance- RLM based activities. -
- d. Determine if there are enough different outlines to test the projected number and mix of RLM
- applicants and ensure that no items are duplicated on successive days. -
- 4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the RLM G
appropriate exam section. -
E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. -
RLM N
E
- c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. -
RLM R
A
- d. Check for duplication and overlap among exam sections. -
RLM L e. Check the entire exam for balance of coverage. -
RLM
- f. Assess whether the exam fits the appropriate job level (RO or SRO). -
RLM
- 3. Author
- 3. Facility Reviewer r)
- , NRC Chief Examiner (#)
- 3. NRC Supervisor
ES-301 Administrative Topics Outline Form ES-301-1 (R8, SI Facility: WATTS BAR Date of Examination: 11-9-13102 Examination Level (circle one): RO / SRO Operating Test Number 1 Administrative Describe method of evaluation:
Topic/Su bject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A. 1 Conduct of a. Calculate Shutdown Margin (NEW)
ODerations
- b. Complete Shift Turnover Checklist (NEW)
A.2 Equipment Control Complete Shift Daily Surveillance Log Mode One and Evaluate Surveillance Log (NEW)
A.3 Radiation Access a High Radiation Area (New)
Control
~
A.4 Emeraency Classify the Event per the REP (Security Event) - SRO ProcedureslPlan (NRC-JPM-NEW)
Emergency Plan implementation Medical Emergency Response (RO)
NUREG-I021 Interim Rev. 8, January 1997
ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Watts Bar Date of Examination: 12/9-13/02 Exam Level (circle one): RO / SRO(I) / SROW) Operating Test No.: 1 1 B.l Control Room Systems I System / JPM Title Code*
Safety Function
- d. Respond t o High Containment Pressure DS 5 JPMRl25A
- e. Transfer Steam Dumps to Tavg Mode (NRC-JPM-New)
NS I 45
- f. Retrieve a Dropped Rod per AOI-2 (JPM #95A)
JPMR095A R e m G S R M N G from Service (NRC-JPM-New)
DAS NLS II 7 1
B.2 Facility Walk-Through
JPMA048
/(Perform LOCAL =art of Control and Service Air 1 Compressors per AOI-10 (3-OT-JPMAOOIC) 3-OT-JPMAOOIC
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA Note: Bold items designate SROU JPMs.
ES-301 Operating Test Quality Checklist Form ES-301-3 (R8, SI 1 fir44 L.
iI Facility: Watts Bar Date of Examination: 12/09-13 Operating t Number: 1
- 1. GENERAL CRITERIA
-nitii
- b' a The operating test conforms with me previously approved out ne; changes are consistent uitn NIA sampling reqirements (e.g.. 10 CFR 55.45. operational :mporiance. safety Lnclon a str.oAon) -
- b. There is no day-to-day repetition between this and other operating NIA tests to be administered during this examination. -
- c. The operating test shall not duplicate items from the applicants' audit NIA test(s)(see Section D.l .a). -
- d. Overlap with the written examination and between operating test categories is within acceptable limits. -
- e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level. -
- 2. WALK-THROUGH (CATEGORY A & B) CRITERIA -
a Each .PM 'nchdes the fo lowing. as appl cab e: NIA M a condotions mating c-es references and tools, nclLd;ng assoc'ated procedures reasonaole and validated t.me limits (average time alloweo for comp et on) and specif c oesignat on ifoeemeo l o be time cr iical oy tne facility licensee spec;l!c performance criter'a tnat nclJde.
. deta (ed expected actions w th exact criter'a ana nomenc aidre
- system response and other exam ner cues
. statements descr.0 ng #mporlantooservations Io be made oy the applicant
- cr:ter a lor sxcesslLI completion of tne task loem lcat'on of cr tical steps ana their assoc ate0 performance stanaards
. restrict on5 on the seq-ence of steps 'Iappl'cab e -
The prescripted questions in Category A are predominantly open NIA b.
reference and meet the criter;a in Attachment 1 of ES-301. -
NIA C. Repetition from operating tests used during the previous licensing examination is within acceptable limits (30% for the walk-through) and do not compromise test integrity. -
- d. At least 20 percent of the JPMs on each test are new or significantly modified. -
- 3. SIMULATOR (CATEGORY C) CRITERIA -
a Tne assoc.ated simdlator operalsng tests (scenar 0 sets) nave oeen rev ewed in accordance Yusn NIA Fnrm FS.V U .d ah
-e m -
Printed Name I Signature Date
- a. Author L.R.Miller & i r k 11/25/02
- b. Facility Reviewer(*) NIA
- c. NRC Chief Examiner (#) .T-&YO~.r L 11/25/02
- d. NRC Supervisor Mlkt.7 CR.4.r Tt-6 ?%.& & ///Z(/*&
NOTE:
- The facility signature is not applicable for NRC-developed tests.
- Independent NRC reviewer initial items in Column c;I chief examiner concurrence required.
ES-301 Operating Test Quality Checklist Form ES-301-3 (R8,S1)
Facility: Watts Bar Date ot Examination: 12/09-13 Operating 1 t Number: 1
- 1. GENERAL CRITERIA
- a. The operating test conforms with the previouslyapproved outline; changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance. safety function distribution).
- b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.
C. The operating test shall not duplicate items from the applicants' audit test(s)(see Section D.l .a).
- d. Overlap with the written examination and between operating test categories is within acceptable limits.
- e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.
- 2. WALK-THROUGH (CATEGORY A & B) CRITERIA
- a. Each JPM includes the following, as applicable:
. initial conditions
. initiating cues
. references and tools, including associated procedures
. reasonable and validated time limits (average time allowed tor completion) and specific designation i f deemed to be time critical by the facility licensee
. specific performance criteria that include:
- detailed expected actions with exact criteria and nomenclature
- svstem resmnse and other examiner cues
. siatementiaescr Ding imponant ObSeNat ons to oe made DY tne applicant
. cr teria for successfulcompletion of me task
- identit cabon of crit cal steps and the r associated periormance standards
- restrictionson the sequence of steps, if applicable
- b. The prescripted questions in Category A are predominantly open reference and meet the criteria in Attachment 1 of ES-301.
C. Repetitionfrom operating tests used during the previous licensing examination is Within acceptable limits (30% for the walk-through) and do not compromise test integrity.
- d. At least 20 percent of the JPMs on each test are new or signiticantly modified.
- 3. SIMULATOR (CATEGORY C) CRITERIA
- a. The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.
Date
- a. Author
- b. Facility Reviewerr)
- c. NRC Chief Examiner (#)
- d. NRC Supervisor NOTE ' Tne facility signalure 6 no1 app cable lor hRC-oevelopeo tests R noepenaent NRC revsewer.nit a, items in Column 'c," chael exam ner concurrence WJired
ES-301 Simulator Scenario Quality Checklist Form ES-301-4(R8, SI)
Facility: Watt Bar Date of Exam: 12/09/02 Scenario Numbers: 1 12 1 3 erating Test NO.:^ I QUALITATIVE ATTRIBUTES Initials I The initial conditions are realistic, in that some equipment andlor instrumentation may be out of Sewice, but it does not cue the operators into expected events.
The scenarios consist mostly of related events. RLM
- 3. Each event description consists of RLM the point in the scenario when it is to be initiated ou 1$
the malfunction(s) that are entered to initiate the event the symptomslcues that will be visible to the crew the expected operator actions (by shifl position) the event termination point (if applicable)
- 4. No more than one non-mechanisticfailure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
RLM I IL~II The events are valid with regard to physics and thermodynamics.
Sequencing ana 1.m ng of events IS reasonable. ana a.lows tne examination team lo obtain complete evaluation resu i s commensLrate w th tne scenar o ob.ec1ives RLM I I MhII
- 7. If time compression techniques are used, the scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
- 8. The simulator modeling is not altered.
I The scenarios have been va date0 Any open s mulator performance defc encies have been eva Jateo to ensure mat f.nct.onal fidelity s mainta ne0 wnile running tne planned scenarios RLM RLM RLM RLM iLRH TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO SEE SECTION D.4.D) Actual Attributes
- 1. Total maifunctions (5-8) 4f4
- 2. Malfunctions after EOP entry (1-2) 212
- 3. Abnormal events (2-4) 212
- 4. Major transients (1-2) 111
- 5. EOPs enteredlrequiring substantive actions (1-2) 1I1
- 6. EOP contingencies requiring substantive actions (0-2) 011
- 7. Critical tasks (2-3) 1I 3
ES-301 Simulator Scenario Quality Checklist Form ES-301-4 (R8, S I )
D Rep?
Facility: Watt Bar Date of Exam: 12/09/02 Scenario Numbers: 1 / 2 /3 Operating Test No.:
QUALITATIVE ATTRIBUTES
- 1. The initial conditions are realistic, in that some equipment andlor instrumentation may be out of service, but it does not cue the operators into expected events.
- 2. The scenarios consist mostly of related events.
- 3. Each event description consists of the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shifl position) the event termination point (if applicable)
- 4. No more than one non-mechanistic failure (e.9.. pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
- 5. The events are valid with regard to physics and thermodynamics.
- 6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
- 7. If time compression techniques are used, the scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are
- 8. The simulator modelina is not altered.
- 1. Total malfunctions (5-8) 4/414(4)
- 2. Malfunctions after EOP entry (1-2) 2/1/1(2)
- 3. Abnormal events (2-4) 1/4/1(2)
- 4. Major transients (1-2) l/l/l(l)
- 5. EOPs enteredhequiring substantive actions (1-2) l/l/l(l)
- 6. EOP contingencies requiring substantive actions (0-2) O/I/O(O)
- 7. Critical tasks (2-3) 1/1/2(2)
ES-301 Transient and Event Checklist Form ES-301-5 (R8, S I )
Watts Bar Nuclear Plant OPERATING TEST NO.: 1 F,AJ/tL Ap licant QW RO As RO SRO-I As SRO Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution (2) #&tivity manipulations ma be conducted under normal or controlled abnormal conditions (refer to Section 8.4.d) but must be significant per Section C.2.a of Appendix D.
(3) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.
Author: Robert L. Monk, #&I#2 NRC Reviewer: Lee R. Miller,
ES-301 Transient and Event Checklist Form ES-301-5 (R8, S I )
Watts Bar Nuclear Plant OPERATING TEST NO.: 1 fia fT R1 R2 R2 R1 U U Instructions: (1)
I ,
Enter the operating test number and Form ES-D-1 event numbers for each I evolution ty'pe. -
(2) Reactivity manipulations ma be conducted under normal or contro//ed abnormal conditions (refer to Section J.4.d) but must be significant per Section C.2.a of Appendix D.
I (3) Whenever practical, both instrument and component malfunctions, should be included; only those that require verifiable actlons that provide insight to the applicant's competence count toward the minimum requirement. I Author: Robert L. Monk, # I , #2 & #3 NRC Reviewer: Lee R. Miller
ES-301 Competencies Checklist Form ES-301-6 (R8, S I )
Watts Bar Nuclear Plant December 2002 6,AL Applicant 11,3 Applicant 12,4 Competencies SCENARK C
- ENARK
$ 1 2 3 Understand and Interpret Annunciators and Alarms Diagnose Events and Conditions Understand Plant and System Response Comply With and Use Procedures (1)
Operate Control Boards (2)
Communicate and Interact With the Crew Demonstrate Supervisory Ability (3)
Comply With and Use Tech. Specs. (3)
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
Circle the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
Author: Robert L. Monk NRC Reviewer: Lee R. Miller
ES-301 Competencies Checklist Form ES-301-6 (R8, S I )
Watts Bar Nuclear Plant I
December 2002 Applicant R, I
F/hL4L I
Applicant R, 1 ROISRO-IISRO-U ROISRO-IISRO-U ROISRO-IISRO-U I
Applicant U Competencies Understand and Interpret Annunciators and Alarms Diagnose Events and Conditions Understand Plant and System Response Comply With and Use Procedures (1)
Operate Control Boards (2)
Communicate and Interact With the Crew Demonstrate Supervisory Ability (3)
Comply With and Use Tech. Specs. (3)
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
Circle the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
Author: Robert L. Monk NRC Reviewer: Lee R. Miller
ES-301 Competencies Checklist Form ES-301-6 (R8,S I )
Watts Bar Nuclear Plant December 2002 Daw Competencies 2ENARIC x
SRO 1
8.7.8 2.4.5 Understand and Interpret 1,2,6 Annunciators and Alarms 124 1.6.7 2.4.5 Diagnose Events .5.6 and Conditions Understand Plant 1.2.4
.5.6 1_
1.7.8
.lo 1 2.3.4
.5.6.
and System Response 7.8 Comply With and Operate Control 1.3.6 2.3.4 Communicate and ,7.8. .5.6.
Interact With the Crew 10 7.8 t
1.2.3 Demonstrate Supervisory .4.5.
Notes:
(1) Includes Technical Specification compliance for an RO (2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
Circle the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
Author: Robert L. Monk NRC Reviewer: Lee R. Miller
ES-301 Competencies Checklist Form ES-301-6 (R8, S I )
Watts Bar Nuclear Plant December 2002 Daw Competencies :ENARIO Annunciators and Alarms Diagnose Events 1.4.6 and Conditions Understand Plant Demonstrate Supervisory Comply With and Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
Circle the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
Author: Robert L. Monk NRC Reviewer: Lee R. Miller
ES-401 Written Examination Form ES-401-7 (R8, S i )
Quality Checklist Final Facility: Watts Bar Date of Exam: 11/26/02 tam Level: RO/SR(
tnitia -
Item Description - C"
- 1. Questions and answers technically accurate and applicable to facility -
- 2. a. NRC WAS referenced for all questions LRM
- b. Facility learning objectives referencedas available -
- 3. RO/SRO overlap is no more than 75 percent, and SRO questions are appropriate LRM per Section D.2.d of ES-401 -
- 1. Question selection and duplication from the last two NRC licensing exams LRM appears consistent with a systematic sampling process -
- 6. Bank use meets limits (no more than 75 Bank Modif.ed New percent from the bank at least 10 percent new, -
and the rest modhed): enter the actual question 56152 12/10 32/38 LRM distr'but on at right -
- 7. Between 50 and 60 percent of the questions on Memory CIA the exam (includhg 10 new questions) are -
written at the comprenension/analysis level; 45/43 55/57 LRM enter the actual quest:on distribJt on at right -
- Date
- a. Author -R.L.Monk Y l ML.4 "/"~/O"
- b. Facility Reviewer r) -N/A "
- c. NRC Chief Examiner (#) -L. R. Miller 8. k jk.A?L- .
- d. NRC Regional Supervisor -M.E. Ernstes fl-F. f d Note:
- The facility reviewer's in tials/signatLre are not applicable for NRC-developedexaminations.
- Independent NRC reviewer initia. items in Column "c;" chief examiner concurrence required.
ES-401 Written Examination Form ES-401-7 (R8, S1)
Quality Checklist PPSk Facility: Watts Ear Date of Exam: 11/26/02 Exam Level: RO/SRa
- Initial Item Description a
- 1. Questions and answers technically accurate and applicable to facility e
- 2. a. NRC WAS referenced for all questions
- b. Facility learning objectives referenced as available 8
- 3. ROISRO overlap is no more than 75 percent, and SRO questions are appropriate @
per Section D.2.d of ES-401
+M R I i U
- 6. Bank use meets limits (no more than 75 Bank Modified New 7.
percent from the bank at least 10 percent new, and the rest modified); enter the actual question 36 distribution at right Between 50 and 60 percent of the questions on I
~ B $ ! ~ ~ /8~ , ~
Memory I
13+s.
CIA 1
the exam (including 10 new questions) are written at the comprehension/analysislevel; enter the actual question distribution at right 4s-/Y3 4 5 - 7 ha
- 8. Referenceslhandoutsprovided do not give away answers ci;?,
- 9. Question content conforms with specific WA statements in the previously approved examination outline and is appropriate for the Tier to which they are assigned; deviations are justified n
- 10. Question psychometric quality and format meet ES, Appendix 8, guidelines @l
- 11. The exam contains 100, one-point, multiple choice items; the total is correct and agrees with value on cover sheet 8 Date
- a. Author di w g H
- b. Facility Reviewer (*) n -, .ta..
- c. NRC Chief Examiner (#) -L
- d. NRC Regional Supervisor %3f /e&/ 67. _..
4 I
Note:
- The facility reviewer's initials/signature are not applicable for NRC-developedexaminations.
- Independent NRC reviewer initial items in Column '"c: chief examiner concurrence required.
Written Exam Review Worksheet Attached are the facilitie's marked exam questions. All comments were incorporated into the final exam.
QUESTIONS REPORT for WBfindraft
- 1. 001AK3.01 00 liTl G2iTlGl//C/A (3.2/3.6)lBIWB02301/C/EL Given the following plant conditions:
-- Plant at 65% power. #lQ tl Impulse pressure transmitter, 1-PT-1-73, fails !xjlcausing rods to step at 72 steps per minute.
- Rods were placed in MANUAL causing rod motion to stop 14 steps from their original position.
Which ONE of the following describes the appropriate course of action?
A. Ensure turbine load remains constant and dilute to restore original rod position.
B. Reduce turbine load to compensate for the rise in reactor power.
C. Withdraw rods manually to restore Tavg to program.
DI Insert rods manually to drop Tavg to program.
I The correct answer is I
- a. Incorrect - Diluting would further increase the difference between Tavg and Tref if turbine load were held constant.
- b. Incorrect - Turbine load would need to be increased to offset the increase in T-avg due to rods stepping out from the NI failure.
- c. Incorrect - withdrawing rods would further increase the difference between Tavg and Tref.
- d. Correct - Tavg would be elevated due to the rods stepping out on the PT failure.
Inserting rods manually to decrease Tavg to program is appropriate.
Thursday, October 31.2002 06:0548PM 1
QUESTIONS REPORT for WBfindraft
- 2. OOlKl.05 001/T2GI/T2Gl/NI FAILURE/C/AINANB02301/CIKFO Given the following:
- Unit power is 66%
- Control Rods are in Automatic .
- No operator actions Which ONE of the following would cause rods move in , then remain at the new position with a reduced T-avg. A A. Loop A Th fails low B. PT 1- 73 fails high C. Loop A Tc fails low DY 99 channel M-41fails high New, REF: 3-OT-SYS85A
- a. incorrect - rod control circuit uses auct High Tave - failing low does not make this the auct hi
- b. incorrect -this channel of turbine pressure inputs the control rod logic and the Tref program is topped out at 588.2
- c. incorrect - rod control circuit uses auct High Tave failing low does not make this the auct hi
- d. correct - Rods move in until the power mismatch rate signal decays, then remain at the new position with a reduced T-avg.
Thursday, October 31,2002 06:05:48PM 2
QUESTIONS REPORT for WBfindraft
- 3. 002K5.10 001/T2G2/TZG2/TEMPERTURE MISMATCWCIA 3.6/4.lN/WB020301ICAU.M
&,E G/i8W&3*,
.Unit 1 is at &I o power and ramping up.2jL
-Rods are in automatic with Bank D at M s t e p s
-The operator has met all requirements to i w s e turbine load and has pressed the turbine control GO button Pds1 r&Lq
--Turbine control valves are opening and megawatts are i n d i n g Tavg isHprogram ou 1rq Which ONE of the folloying describes Tavg behavior assuming no dilution by the operatorTas
& +uzb,; l r o p 1 3 raised t u b r , i g u ~ i t 7 0t u o b j u ?
rrse . .
B. Tref will , ut Tavg will remain constant.
C. Tavg and Tref will remain constant 1 S&iRg.
risd DY Tref will iRsFea4e .and. Tavg will
.g-Ref: WB lesson plant 3-OT-SYS085A, obj 7 & 21 Distactor analysis:
D is correct because Bank D hits the C11 rod stop at 220 steps. As the governor valves continue to open, turbine power continues to rise along with Pimp (Tref). However, no more positive reactivity is added (no dilution per stem) and no rods due to C11, but power defect adds negative reactivity which drives Tavg down until Moderator temp coefficient balances at a lower Tavg.
A, B, and C are incorrect they have Tavg either rising or remaining constant.
Thursday, October 31, 2002 06:05:48PM 3
b.
QUESTIONS REPORT for WBfindraft
- 4. 004KS.OBIIP$iT2Gl/T2GI/OXYGEN~ (2.8/3.2)/B/WB023Ol/C/KFO Which-of the following is the primary reason for maintaining a hydrogen cover gas in the VCT during normal at power operations?
A. to assure N-16 concentrations are ALARA B. to maintain RCS pH within TRM limits C. to maintain conductivity below ,017 micro Mhos D I to maintain oxygen concentration below the TRM upper limit Ref: NA 2002 -validated to WB Lesson plan 3-OT-SYS062A, TRM 3.4.4 Chemistry
- b. incorrect RCS pH is controlled by primary chemistry not with cover gases
- c. incorrect conductivity is controlled by water quality efforts not cover gases
- d. correct Hydrogen cover gases "scavenge" oxygen, thus lowering the oxygen concentration Thursday, October 31,2002 06:05:49PM 4
QUESTIONS REPORT for WBfindraft
- 5. 006Al.11 001iT2GZ/T2G2//M (3.1/3.4)/J3/WB02301/CELIKFO Given the following plant conditions:
- A SGTR has occurred on SG #I.
- ES-3.1, "Post SGTR Cooldown Using Backfill", is in progress.
- Ruptured SG level is 25%.
- RCS is at 390°F.
- RCS is at 400 psig.
- Cooling down using steam dumps to condenser.
- RCP ##4in service.
ES-3.1 step 13 requires a return to step 3 if RCS temperature is greater than 200°F.
Step 3 requires the operator to ensure adequate shutdown margin.
Why is it necessary to reverify adequate shutdown margin at this point in the procedure?
A. The RCS temperature change during cooldown will cause significant boron concentration changes due to PZR outsurge.
B. Charging to maintain PZR level during cooldown will cause significant boron concentration changes.
C:' The secondary fluid in the ruptured SG will cause significant boron concentration changes.
D. The auxiliary spray will cause significant boron concentration changes.
The correct answer is C Thursday, October 31,2002 06:05:49 PM 5
\.
QUESTIONS REPORT for WBfindraft 6 . 006K1.07 001~2G2/T2G2//C/A(2.6/2.9)lsiWBO23Ol/C/ELfl(FO Given the following conditions:
- The plant is operating at 100% power.
- Inadvertent Safety Injection occurred
- #I SG level transmitter that controls MDAFW pump LCV failed low.
- #4 SG PORV opened momentarily after the reactor trip and developed a large packing leak.
Which ONE of the following would cause the initial main feedwater isolation during this transient?
A. The #I SG level reached 83%.
BY The safety injection actuation signal.
C. Tavg dropping to 564°F following the reactor trip.
D. When the south valve vault level had risen to 4 inches due to the PORV packing leak.
The correct answer is B.
- a. Incorrect - level may reach 83% but FWI would already have been actuated by the SI.
- b. Correct - SI causes immediate FWI.
- c. Incorrect - would normally actuate FWI following a reactor trip however the SI initiated the FWI immediately.
- d. lncorrecty - PORV leak would cause increase in level in the vault room however FWI would have already been actuated by the SI.
Thursday, October 31,2002 06:05:49PM 6
QUESTIONS REPORT for WBfindraft
- 7. O08AK 1.O 1 00 1/T 1 G2/T I G2//C/A (3.2/3.7)iSIWB0230l/C/KFO Given the following:
- Unit 1 is stable at 100% power
- A pressurizer safety valve opens and fails to reseat and the Unit trips Ye Which of the following indications would the operator expect to see as a result of this event over the next 30 min?
A. Safety tailpipe temperature would increase to greater than 600 F and then slowly decrease.
B. Safety tailpipe temperature would increase to greater than 600 F and then slowly increase.
C:' Safety tailpipe temperature would increase to between 220 F and decrease and sta$ze.
gotand then slowly D. Safety tailpipe temperature would increase to between 220 F and ,F and then slowly increase and stat#ze. 330 Ref- Farley 2000, validated for WB -
- a. incorrect - the temperature is correct for pressures of 2240
- b. incorrect -the temperature is correct for pressures of 2240
- c. correct - since it relieves to the PRT, the pressure will increase until the rupture disc relieves (Ish psig) and then the pressure (and temperature ) will decrease and eventually stablize
- d. incorrect - will not continue to increase once the PRT rupture disc relieves.
85 Thursday, October 31,2002 06:0550PM 7
QUESTIONS REPORT for WBfindraft
- 8. 0 1OK3.O1 00 liT2G2iT2G2PRESS CONTROLICIA 3.8/3.9/B/WB020301ICIRLM Given the following:
- Pressurizer pressure is 2230 psig and rising.
- The variable heaters are energized.
- The spray valves are closed.
- The Master Pressure Controller, I-PIC-68-340A, fails to a co@tant output-2230 psig.
Which ONE of the following describes the response of the pressure control system if the operator takes no further action?
I-A. Pressure will rise until PORVs PCV-68-334 andkV-68-340A open to control pressure.
1 BY Pressure will rise until relief valve PCV-68-334 opens to control pressure.
C. Pressure will rise until the spray valves open to control pressure.
D. Pressure will cycle on the variable heaters at a higher setpoint.
Ref: WB lesson plan 3-OT-SYS068C Distractor analysis:
A is incorrect because PORV continues to receive a constant input and therefore remains closed.
B is correct because PORV 334 receives input from PT 323 which is seeing the actual pressure rise.
C is incorrect because the spray valves remain closed because there input is not changing from the master controller and is spray open setpoint.
D is incorrect because the input to the variable heaters is constant at a value less than their shutoff point.
Thursday, October 31, 2002 06:05:50 PM 8
QUESTIONS REPORT for WBfindraft
- 9. 01 IA3.03 001/T2G2/TZGZ/PZRLEVEL/C/A 3.2/3.3/B/WB020301/C/ELRLM Given the following:
a,-
Unit is at 50% power.
- All automatic control system are in their normal lineup.
- .Ge&&w+#ressurizer rogram eve ails to an output corresponding to 50% load. level p
- Assume no operator action is taken.
OM WhicHof the following describes the effect on charging flow and PZR level as the plant load is in-gd to 1OO%?
ra I OCY
+*f i & . h t -
A. Charging flow i&&es-& actual PZR level FBR7aiR4 constant.
B. Charging flow d&&i%es and actual PZR level .c--d---s.
Pro s CY Charging flow h ami L. N # actual
- b h PZR level d. eucjJbn+
CtSCJ D. Charging flow remains constant and actual PZR level -.i
Reference:
WB Lesson Plan 3-OT-SYS068C Obj. # I 4 Distractor analysis:
A is incorrect because Tav increases as power increases which will make PZR actual level increase.
B is incorrect, same reason as A C is correct because as PZR level rises with coolant expansion due to Tav increase, with
-L output at 50%, an error is generated that PZR level is too high, causing charging flow to decrease.
D is incorrect, same as A for PZR level, charging flow increases, see C.
Note, WB exam bank had answer C as "Charging flow rises and actual PZR level rises." Need to check this with them.
Thursday, October 31,2002 06:05:50PM 9
QUESTIONS REPORT for WBfindraft
- 10. 0 11EA 1.04 00 liT 1G2iT 1G 1//CIA (4.4/4.4)iBiWB02301ICEL Given the following plant conditions:
- Unit 1 tripped due to a Large Break LOCA.
- Containment pressure = I 2 5 psid.
- RWST level = 20%.
- Containment Emergency Sump level = 15%.
- RHR Swapover to the Containment Sump could not be performed.
- The operating crew has transitioned to ECA - 1.I, "Loss of RHR Sump Recirculation."
- The crew is performing step 3 of ECA - 1.I, "Loss of RHR Sump Recirculation", to determine the proper Containment Spray pump alignment and operation.
Which ONE of the following actions will result in the Containment Spray pumps being in the proper alignment under the existing plant conditions?
A. Leave both Containment Spray pumps running until RWST level drops to 8%.
B. Stop both Containment Spray pumps and place handswitches in "pull-to-lock.
CY Stop one Containment Spray pump and allow the remaining pump to take suction from the RWST.
D. Stop both Containment Spray pumps, until suction can be aligned to the Containment Sump, then restart one pump.
Thursday, October 31,2002 0605:51 PM 10
QUESTIONS REPORT for WBfindraft
- 11. 01 1EK2.02 001/TlG2fTlGl//C/A (2.6/2.7)/BnVBO23Ol/C/EL Given the following conditions:
- A large break LOCA occurred
- Operators have just completed swapover to Containment Sump
- A loss of offsite power occurs Which ONE of the following describes the actions required for this condition?
A. Pull to lock SI pumps and CCPs until the RHR pumps have been restarted after the shutdown boards are reenergized.
B.* Pull to lock the CCPs until the RHR pumps are restarted after the shutdown boards are reenergized.
C. Ensure both RHR pumps are started by the blackout sequencer after the diesel generators reenergize the shutdown boards then restart the SI pumps.
D. Ensure all ECCS pumps are started by the blackout sequencer when the diesel generators reenergize the shutdown boards.
The correct answer is B Thursday, October 31, 2002 06:05:51 PM 11
QUESTIONS REPORT for WBfindraft 12.0 12K6.1000liT2G2iT2T2P-7iM3.3/3.5/NiWB020301/CiRLM
&c., 7ne *.)lJPw3*6:
Unit 1 is at 100% power
-Permissive 70-D, P-7 LO POWER TRIPS BLOCKED illuminates Which ONE of the following describes the effects on RPS?
A. The reactor will not trip on Pressurizer High Pressure.
B. The reactor will not trip on Pressurizer Low Water Level.
CY The reactor will not trip on Pressurizer Low Pressure.
D. The reactor will not trip on Loss of Flow in one loop.
Ref: WB Lesson Plan 3-OT-SYS099A, obj. 17 Distractor analysis:
A is incorrect because P-7 is not an input to the trip.
B is incorrect because PZR Lo Water Level is not a trip.
C is correct, because P-7 blocks it when P-7 is off (light on).
D is incorrect because P-8 is unaffected and trips Rx on 114 logic.
Thursday, October 31,2002 06:05:52PM 12
QUESTIONS REPORT for WBfindraft
- 13. 013K2.01 0011f2Gl/T2Gl/PUMPTRIP LOGICM (3.6/3.8)/B/WB02301/C/KFO Given the following:
- 1A-A and 1B-B SI pump breakers are "racked in"
- A fuse blows in the NORMAL DC Trip Circuit for the 1A-A SI pump
- A safety injection (SI) acutation occurs ow Whichvof the following describes the response of the SI pumps to the SI signal?
A. 18-B SI pump will start, but 1A-A SI pump will not auto start until the control power supply is transferred.
B. 1B-B SI pump will start, but 1A-A SI pump will not auto start and must be started from MCR handswitch.
CY Both SI pumps will auto start, but the 1A-A SI pump can not be stopped from the MCR.
D. Both SI pumps will auto start, but the 1A-A SI pump can not be stopped #fef&Iw mechanically at the breaker.
Watts Bar exam bank - NEED CONFIRMATION ON BREAKER LOGIC Thursday, October 31,2002 06:05:52PM 13
QUESTIONS REPORT for WBfindraft
- 14. 014A4.01 00l/T2GZ/T2GI/STARTUP/C/A ( 3.3/3.4)/8/WB023Ol/C/KFO Given the following:
- Operators are preparing for a reactor startup fid BeIct shutdown banks were withdrawn
- All control banks are $iffully inserted
- The rod control startup reset switch is manipulated in error WC WhichYof the following describes the required actions to proceed with the startup?
A. Restore the P/A converter to 230 steps BY Restore the shutdown group step counters to 230 steps C. Restore the bank overlap unit to 230 steps D. Reinsert all shutdown banks INPO bank -validated for WB lesson plan 3-OT-SYS85A
- a. incorrect - P/A converter does not need to be reset because the control banks are fully inserted
- b. correct - all group step counters are reset to 0 by the reset switch
- c. incorrect - bank overlap counters are at 0 because the control rods are fully inserted
- d. the shutdown group counters can be manually reset - reinsertion is not required Thursday, October 31,2002 06:05:52PM 14
QUESTIONS REPORT for WBfindraft 15.01 5K4.06 001/T2G1/T2G1//M/B/WB023Ol/CiKFO While operating at 90% power, one power range channel of nuclear instrumentation Power
. . .ha6 bucl V c
- r t O M r ( Ct+u*\
Range f06U) p 16 &di.
c b y Ped5 . 8irth/lb& Wh*&
What is the coincidence for a NIS reactor trip?
4 OT67 A. 2 o u t o f 4 2
BY Pout of 3 I
C . ?Out Of 4 D. 1 out of 3 INPO bank
- a. incorrect - coincidence changes to Iout of three when in bypass
- b. correct - coincidence changes to%out of 3
- c. incorrect - wrong logic and bypass limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- d. incorrect - bypass status limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Thursday, October 31.2002 06:0553 PM 15
QUESTIONS REPORT for WBfindraft 1 6.017AK1.0400IIT1 G1IT1G1/LOSS OF FLOW/C/A(3.7/4.1)lBiWB02301/C/RLM Given the following plant conditions:
- Unit is operating at 30% power.
- All control systems are in AUTO.
- Loop 3 Reactor Coolant Pump has just tripped.
Which ONE of the following is the overall plant response?
A. Reactor trips on HIGH steam generator level when the #3 steam generator level "swells".
B.* Unit power remains the same with steam flow rising on the other steam generators.
C. Unit power is reduced to approximately 22% power (3/4of original power level).
D. The reactor trips on a Low RCS Flow condition.
WB bank Thursday, October 31,2002 06:05:53PM 16
QUESTIONS REPORT for WBfindraft 17.017K3.01001iT2GliT2GllFAILEDCORE EXITIMIBIWB02301/C/KFO If all core-exit thermocouples are inoperable during an event in which the RCPs were tripped, what indication(s) may be used to verify that natural circulation cooling is occurring?
A. RCS hot leg temperatures only B. RCS cold leg temperatures only CY Both RCS cold leg and hot leg temperatures D. There are no direct indications to verify natural circulation for this condition Bank (NA'02) - validated for Watts Bar, ES-01, "Reactor Trip Response
- a. incorrect - insufficient information
- b. incorrect - insufficient information
- c. correct -the difference in temperatures will be adequate to determine of natural circulation has been established
- d. incorrect, using both hot and cold legs is adequate Thursday, October 31,2002 0130553PM 17
QUESTIONS REPORT for WBfindraft 18.022AG2.1.32 00In1G I R l G l/LOW PRESSURE LETDOWNM 3.4/3.8/N/WB020301/C/RLM I-During water Solid operations with letdown from RHR, Sol-62.01 requires that FCV-62-83, RHR LETDOWN FLOW CONTROL be full open.
Which ONE of the following describes the basis for this precaution?
A. To ensure maximum letdown flow rate for purification.
B. To ensure VCT level can be maintained under all charging flow conditions.
I-C:' To ensure PCV-62-81, Letdown Pressure Control can control pressure transients.
SUtlZl?* *I D. To ensure RCS to RHR Sup&Lme Relief Valve (74-505) isn't challenged.
r-RFU* 74-505 No specific learning objective found.
Distractor analysis:
Answer A is incorrect because charging flow controls letdown flow.
Answer B is incorrect because balancing charging and letdown controls VCT level.
Answer C is correct because with FCV-62-83 less than full open, it can in effect limit flow and prevent pressure reduction when PCV-62-81 fully opens in response to a high pressure transient.
Answer D is incorrect because the suction relief can be challenged by other factors (eg. pump starts) even with FCV-62-83 full open.
Thursday, October 31,2002 06:0554PM 18
QUESTIONS REPORT for WBfindraft
- 19. 02262.1.10001/T2Gl/T2Gl/CTMT AIR TEMP/M 2.7/3.9/MIWB020301/C/RLM Which ONE of the following correctly identifies the minimum and maximum allowable temperatures per Tech Spec for the Containment upper compartment temperature in Mode 2.
A. Between 85°F and 120°F.
BY Between 60°F and 110°F.
C. Between 60°F and 120°F.
D. Between 85°F and 110°F.
Ref: WB lesson plan 3-OT-SYS030C, obj 3 WB TS 3.6.5 Modified from WB exam bank which asked MODE 1 limits.
Distractor analysis:
See attached TS Thursday, October 31,200206:05:54PM 19
QUESTIONS REPORT for WBfindraft
- 20. 024AK2.01 001iT1GliT1G1/lM(2.7/2.7)iBIWB02301/C/EL A condition has occurred which warrants entry into AOI-34, "ImmediaterBoration". While attempting to borate 1 , the aligned boric acid pump-Which ONE of the following Immediate Boration flowpaths should be used in this condition?
A. To the suction of the CCPs through Emergency Borate valve 1-FCV-62-138 after re-aligning the boric acid pump on tank recirc.
B. To the suction of the CCPs through Manual Boration valve 1-ISV-62-929 after re-aligning the boric acid pump on tank recirc.
CY To the suction of the CCPs through 1-FCV-62-135 and 136 using the RWST as the boration source.
Fprm D. ;Fo the discharge of the CCPs through l-FCV-63-$25 and $6 using the BIT as the boration source.
The correct answer is C Thursday, October 31,2002 06:05:54PM 20
QUESTIONS REPORT for WBfindraft 2 1. 025A3.02 001/T2G1/T2G1NCIAIB/WB023OllC~~
Given the following:
- Large Break LOCA has occurred causing a Reactor Trip and Safety Injection
- OAC observes annunciator "Glycol Exp Tank Level HI/HI-Hi" is lit a,u&
Whichvof the following describes the most likely reason the annunciator is illuminated?
A. Phase A closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the auxilary building side of the isolation valves relieve glycol into the glycol expansion tank.
BY Phase A closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tank.
C. Phase B closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the auxilary building side of the isolation valves relieve glycol into the glycol expansion tank.
D. Phase B closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tank.
Bank, lesson plan OT-SYSOGIA, drawing 1-47-814-2 In the event of a LOCA, the glycol heats up from approximately -5 F to the containment accident temperature and expands harmlessly into the expansion tank. The liquid trapped between a pair of isolation valves is relieved around the inner isolatin valve through a bypass line via a small check valve. The bypass line also contains test connections for periodic leak testing of the isolation valves and check valve.
- a. incorrect - no relief valves feedback to the expansion tank
- b. correct
- c. incorrect - no relief valves feedback to the expansion tank
- d. incorrect - phase B does not close the these valves Thursday, October 31,2002 06:05:55PM 21
QUESTIONS REPORT for WBfindraft
- 22. 025AA2.07 00l/T1G2fT1G2/MIDLOOP/C/A (3.2/3.2)/B/WB02301/C/KFO Given the following:
- RCS temperature is 118 F
- Reactor Vessel head is removed
- Reactor Upper lnternals are installed in the reactor vessel
- Refueling Level is W f t . 718'6
- RCS draining is in process at 10 gpm
- RHR pump A is running with indicated flow ofS g p m
- RHR pump A begins to exhibit indications of cavitation The cavitation and subsequent loss of RHR heat removal is occurring due to ......
A. draining with the upper internals in place, which reduced the RHR suction pressure.
B. steam binding of the RHR pump, caused by low recirculation flow.
C:' air entrapment at the RHR suction inlet, caused by the high flow conditions D. draining with the upper internals in place, which reduced the RHR discharge pressure.
Ref. Bank - WB verification: Sol-74.01, AOI-14, GO.10
- a. incorrect, upper internal installation will not effect RHR suction pressure.
- b. incorrect, recirculation flow valve shuts at 1400ggpm
- c. correct, air entrapment occurs at higher flow rates, normal midloop flow rate is 2000
- d. incorrect, upper internals installed will not effect RHR discharge pressure to this extent Thursday, October 31,2002 06:05:55 PM 22
WBN Sol-74.01 1 RESIDUAL HEAT REMOVAL SYSTEM Revision 37 Page 112 of 123 4000 Mode 6 with
.23 ft above 3000 2500 t Mode 6 with R H R Pump <23 ftabove flow rate GPM 2000 Per Pump Minimize Operation in this Range 1400 750 I I I I 0 I I I Mini flow Reduced FCV-74-1 &-2 FCV-74-1 & 2 Operation Inventory1 Flow path Flow path (One midloop (2 pumps pump only)
(One pump only) ____OR ____
running)
FCV-74-8 & 9 Flowpath (One pump only)
QUESTIONS REPORT for WBfindraft 23.02562.1.27 001/T2GliT261/PURPOSEOF ICE CONDM 2.8/2.9/M/WB020301/CRLM Which ONE of the following is a purpose of the Ice Condenser System?
A. Helps limit peak clad temperature of the fuel by maintaining a minimum back pressure on the RCS during blowdown phase.
B. Uses sodium tetraborate to remove elemental hydrogen from the containment atmosphere.
C.' Absorbs (thermal) energy released during LOCA to control the peak pressure in containment.
D. Uses sodium hydroxide to remove elemental iodine from the containment atmosphere.
Ref WB lesson plan 3-OT-SYS061A, obj 2 Distractor analysis:
Thursday, October 31,2002 06:05:55 PM 23
QUESTIONS REPORT b,"* fA FJ8,; for WBfindraft
- 24. 026A 1.O 1 00 lfl'2G2/T2GlIDESIGNICIAIM/WBO2301IC/RLM Jar ber*L 4 d & & r + SA&$ j*j4Jim h a ore&:&
3 4494 p
- Containment Pressure is 1.6 psig and rising
- One High Containment Pressure bistable has illuminated Which ONE of the following describes the correct operator response to prevent Containment Pressure from exceeding design limits?
,/A. Continue to closely monitor Containment Pressure and the High Containment Pressure bistable status.
B. Manually actuate HS-30-64A, Phase B Actuation Switch on M-6, and HS-30-68A, Phase B Actuation Switch on M-5, simultaneously.
C. Manually start and align Train A and Train B Containment Spray Systems.
@A anually actuate HS-30-64A, Phase B Actuation Switch on M-6, and HS-30-64B, Phase B Actuation Switch on M-6, simultaneously.
WB bank-modified Thursday, October 31,2002 06:0556 PM 24
QUESTIONS REPORT for WBfindraft
- 25. 026AK3.03 00 1/T 1 G 1/T1 G 1/A01 1 5ICIA (4.0/4.2)IBIWB0230l/C/RLM Given the following:
- Unit is at 100% power.
- " A Train CCS Surge tank level is dropping due to a leak.
- US has entered AOI-15, Loss of Component Cooling Water.
Which ONE of the following describes required actions in the event " A Train CCS surge tank level cannot be maintained.
A. Transfer "A" Train CCS suction to the " B Train side of the surge tank, isolate non ESF header.
B. Shift Thermal Barrier Booster pump suction to " B train, shutdown affected "A" Train components, start "B" Train components as necessary.
CY Stop the thermal barrier booster pumps, trip the Reactor and stop all RCPs.
D. Shutdown running " A Train components and place in auto, start "B" Train components as necessary.
WB Bank Thursday, October 31,2002 06:05:56 PM 25
QUESTIONS REPORT G W O
- I A m&.$: for WBfindraft
- 26. 027AK3.03 OOllTlGVTlG2RORVICIA 3.7/4.1iNIWB020301/C/RLM
-- Unit 1 is at 100% power.
Annunciator 89A, PZR PORV LINE TEMP HI, illuminates.
- Both PORV's indicate closed.
Pressurizer pressure is normal.
6 , 5 m ~ i lR o a a b r &*I&+&dh( L4.k In accordance with A O I - 1, which ONE of the following is the correct action and reason?
A. Close the associated block valve because a vapor-space leak causes PZR level to increase.
B. Close both block valves because a vapor-space leak causes PZR level to increase.
CY Close the associated block valve because the PRT will rupture.
D. Close both block valves and remove power because the PRT will rupture.
Ref: WB lesson plan 3-OT-A011800, obj. 1 & 5 WB procedures AOI-18, AOI-6, ARI 89-A Disaster analysis:
Answer A and B are incorrect because PZR level rise is only associated with large leaks that affect PZR pressure.
Answer C is correct because it follows the ARI guidance and small leaks can raise PRT pressure to the rupture disc setpoint.
Answer D is incorrect because power should not be removed.
Thursday, October 31,2002 060556 PM 26
QUESTIONS REPORT for WBfindraft
- 27. 029EA1.13 OOl/T1G2/TlGl/TURBINETRIP/M 4.1/3.9/B/WB020301/C/RLM Which ONE of the following is the NEXT action the operator is required to take if the main turbine does NOT trip automatically and CANNOT be tripped from the MCR: per FR-S.l, "RESPONSE TO NUCLEAR POWER GENERATIONIATWS?
A. Place both EHC pumps control switches in P-T-L.
B. Trip the turbine locally at the front standard.
CY Manually RUNBACK the turbine.
D. Shut the MSIV's.
WB lesson plan 3-OT-FRS-0001, Obj. 3 WB exam bank Distractor analysis:
A is incorrect because it is a followup action later in the procedure, step 9 RNO.
B is incorrect because it is a local action if MCR actions fail, step 9 RNO.
C is correct per RNO step 2 D is also in RNO step 2, but only occurs if runback doesn't work.
Thursday, October 31,200206:05:57PM 27
QUESTIONS REPORT for WBfindraft
- 28. 029K1.02 O O I I T ~ G ~ / T ~ G ~ / R MONITOWM AD 3.313.6/NlWB020301/M Which ONE of the following describes the sample path of RE-90-130, Cntmt Purge Exhaust, and effect of the alarm exceeding the alarm setpoint?
fG&Sd44,A A. RE-90-130 samples the Cntmt Purge Exhaust discharge and initiates a Containment kip upon alarm.
BY RE-90-130 samples the Cntmt Purge Exhaust suction and initiates a Containment Vent Isolation upon alarm.
C. RE-90-130 samples the Cntmt Purge Exhaust discharge and initiates a Containment Vent Isolation upon alarm.
PA l d J &
D. RE-90-130 samples the Cntmt Purge Exhaust suction and initiates a Containment hfge
&ip upon alarm.
Ref: WB Lesson Plan 3-OT-SYS030C, obj. 10 WB Lesson Plan 3-OT-SYS090A, pp. 63 SO1 88.1, Checklist #3 Dwg. 1-47W866-1 Thursday, October 31,2002 06:05:57PM 28
QUESTIONS REPORT for WBfindraft
- 29. 032AK1.01 001iTlG2/TlG2/POWER FAILURE/C/A/M/WB02301/C/KFO Given the following conditions:
- Reactor Startup in progress
- Shutdown Banks withdrawn
- Control Bank withdrawal is i m d n e n t
- SRM N132 indicates approximately 1000 cps
- SRM N131 is in bypass Which ONE of the following will occur if the control power fuse for SRM N131 blows?
A. Lose indication for SRM N131 on Main Control Board and NIS cabinets B. Both SRM drawers deenergizes and "non-operate" alarm acuates C? Reactor Trips D. Rod withdrawal is blocked Modified from WB bank - rewrote question stem and changed distractor. Validated in Lesson Plan SYSO92A
- a. incorrect-not all indicatipon lost since instrument power is available
- b. incorrect-SRM N132 unaffected by loss of control power to SRM N131
- c. correct- loss of control power deenergizes bistables and initiates trip signal (1/2 logic)
- d. incorrect - Source range low does not initiate rod stop Thursday, October 31,2002 06:05:58PM 29
QUESTIONS REPORT for WBfindraft
- 30. 034K4.01 001/T2G3/T2G2iLOSS OF A I M (2.6/3.4)/B/WB02301/C/KFO DUE Which- of the following describes a feature of the Refueling Machine designed to prevent the accidental release of a fuel assembly?
A. The Gripper is mechanically engaged and disengaged by a remote operating handle on the bridge and requires no power or air to operate.
B:' The gripper requires air to disengage, however, a mechanical latch prevents gripper release under load even if air is supplied.
C. The gripper disengages upon loss of air, however, a mechanical latch prevents gripper release under load even if air is removed.
D. When the gripper is engaged, operators mechanically lock gripper in place with extension shaft which must be unlocked before the gripper can release.
Ref: lesson 3-OT-SYS079 (LO11)
- a. incorrect - air required to disengage
- b. correct - mechanical latch on gripper works under load
- c. incorrect - engages on loss of air
- d. incorrect - no operator action required for gripper mechanical latch to operate Thursday, October 31.2002 06:05:58PM 30
QUESTIONS REPORT for WBfindraft 3 1. 035K1.09001/T2G2/T2G2iTRANSIENTRESPONSEICIA 3.8/4.O/B/WB020301/C/EL/RLM Given the following plant conditions:
- The reactor is operating at 50% power.
- Rod control is in MANUAL.
- Turbine control is in IMP-IN.
- #3 S/G PORV fails OPEN.
Which ONE of the following describes the resulting steady-state conditions?
(Assume no reactor trip or operator action and turbine power remains constant)
AY Final Tavg < initial Tavg and final power > initial power.
B. Final Tavg < initial Tavg and final power = initial power.
C. Final Tavg = initial Tavg and final power > initial power.
D. Final Tavg = initial Tavg and final power = initial power.
Reference:
TAAOI 1, General theory section Distractor analysis:
A is correct steam loss through PORV causes Tav decrease which adds positive reactivitiy which causes power to rise. Tav will remain less than initial Tav because some of the reactivity is used to overcome power defect associated with power rise.
B, C, and D are incorrect because they conflict with the above correct answer.
Note: Since IMP-IN is given, do we need to tell them that turbine power remains constant?
Thursday, October 31,2002 06:05:58PM 31
QUESTIONS REPORT for WBfindraft
- 32. 037AK3.07 001iTlG2/TlG2/TTSBE LEAWM 4.2/4.4/B/WB020301/C/RL,M Given the following:
- A SG tube leak of approximately 30 gpm has been identified on SG #3.
- The operating crew has entered AOI-33, Steam Generator Tube Leak.
- Operators have completed Step 21 of the AOI and have isolated feed flow to PSG #3 after verifying level greater than 10%.
Which ONE of the following is a basis for ensuring the affected SG level greater than IO%?
A. To ensure that the pressure and temperature limits of the SG shell are maintained.
B! To prevent the RCS cooldown from causing depressurization of the affected SG C. To prevent SG overfill.
D. To prevent thermal shock to the tubes during RCS cooldown.
Ref: WB Lesson Plan 3-OT-A013300, obj. 8 A is incorrect in that these limits apply to CSD conditions B is correct because the insulating layer of water above the tubesheet helps trap pressure in the SIG and minimize tube dlp during cooldown.
C is incorrect because level control is not an issue.
D is incorrect because there is no sudden introduction of cold water after the level is attained.
Thursday, October 31,2002 06:05:59 PM 32
QUESTIONS REPORT for WBfindraft
- 33. 039A1.03 001/T2G2/T2G2/MS WARMUP/C/A 2.6/2.7/B/WB020301/C/ELIRLM Given the following plant conditions:
- Startup in progress.
- Operators are warming the main steam lines using the MSlV bypasses.
- The OAC observes that the RCS has cooled down 108°F in the past hour.
- The CRO observes that the main steam lines have heated up 102°F in the past hour.
Which ONE of the following indicates the actions that should be taken by the operators and why?
A? Close the MSlV bypass valves; RCS cooldown limit was exceeded B. Close the MSlV bypass valves: main steam line heat-up limit was exceeded C. Close the MSlV bypass valves; both RCS and main steam line limits were exceeded.
D. Leave MSlV bypass valves open; NO RCS or main steam line limits were exceeded.
Ref WB Exam Bank WB Lesson Plan 3-OT-SYS001A1 obj 24
- a. Correct - RCS cooldown limit of 100"F/hr was exceeded; main steam line limit of 200"Flhr was NOT exceeded. Closing the bypass valves would terminate the cooldown
- b. Incorrect - main steam line limit was not exceeded. Examinee could confuse the RCS and main steam line limits.
- c. Incorrect - only the RCS cooldown limit was exceeded. Examinee may believe the limits were the same. Closing the bypass valve would terminate the cooldown.
- d. Incorrect - examinee could confuse the limits and believe that neither limit was exceeded, however the RCS cooldown limit was exceeded and closing the bypass valve would terminate the cooldown.
Thursday, October 31, 2002 06:05:59PM 33
QUESTIONS REPORT for WBfindraft
- 34. 040AG2.4.6 001/TlGl/TlGl//C/A (4.0/4.3)/B/WBO2301/C/EL Given the following plant conditions:
- Unit was at 100% power.
- A main steam line break occurred in the Turbine Building.
- Operators were unable to close the MSlVs and transitioned to ECA-2.1, Uncontrolled Depressurization of All Steam Generators.
- SI termination steps are in progress.
- Loop 3 MSlV is closed locally.
- The CRO observes the #3 SG pressure rising slowly.
Which ONE of the following actions should be performed?
A. Transition to E-2, "Faulted SG Isolation".
B. Transition to ES-1.1, "SI Termination".
C. Remain in ECA-2.1 until RHR is in service.
D.* Remain in ECA-2.1 until SI is terminated.
The correct answer is D Thursday, October 31,2002 06:05:59PM 34
QUESTIONS REPORT for WBfindraft
- 35. 041K3.04 O O ~ I T ~ G ~ / T ~ G ~ / S TDUMP E A MRX POWERICIA3.5/3.4iB/WB020301/CELRLM Given the following conditions:
- Unit at 100% power, EOL conditions.
- Turbine operating in IMP OUT.
- A steam dump valve inadvertently comes full open.
- All other control systems normal.
Which ONE of the following correctly describes the plant conditions, when plant stabilizes, and assuming NO operator action?
A. Megawatts electrical same as initial; reactor power rises.
B. Megawatts electrical same as initial; reactor power drops.
CY Megawatts electrical drops; reactor power rises.
D. Megawatts electrical drops; reactor power drops.
Ref: WB Exam Bank WB Lesson Plan 3-OT-SYS001B, obj 27 WB Lesson Plan 3-OT-SYSOOIB, pp. 24 lursday, October 31,2002 06:06:00 PM 35
QUESTIONS REPORT for WBfindraft 36.045A3.05001/T2G3/T2G3/GOVERNOR VALVE/C/A3.5/3.6/B/WB020301/CIELIRLM Given the following plant conditions:
- Plant operating at 100% power.
- All systems aligned normal.
- Turbine EHC control is in IMP OUT.
Which ONE of the following describes turbine governor valve operation while in IMP OUT mode?
A. Governor valve position is adjusted to maintain generator load constant and will NOT respond to changes in system frequency.
B. Governor valve position is adjusted to maintain generator load constant and will respond to changes in system frequency.
C. Maintains governor valves at a set reference position and will NOT respond to changes in system frequency.
DI Maintains governor valves at a set reference position but will respond to changes in system frequency.
Ref WB Exam Bank WB Lesson Plan OT SYS047A Obj. 2 Lesson plan pp. 12 and 18 Info on pp. 12 and 18 seem to conflict, need to follow up w/ site.
- a. Incorrect - in the IMP OUT mode governor valves adjust to maintain load and system frequency.
- b. Incorrect - in the IMP OUT mode governor valves adjust to maintain load and system frequency.
- c. Incorrect - governor valves are set at a reference set in by the operator, but WILL change in response to system frequency changes
- d. Correct - governor valves are set at a reference set in by the operator and WILL change in response to system frequency changes.
Thursday, October 31,2002 06:06:00 PM 36
QUESTIONS REPORT for WBfindraft
- 37. 054AG2.4.48 001/T1Gm1GZSG LEVELICIA 3.5/3.8MiWB020301/C/RLM d i u e f i i-b FoilowiIq:
+Unit 1 is at 100% power.
-Annunciator 63-F, SG LEVEL DEVIATION, alarms and the operator notices S/G # I level rising along with MFP speed and the remaining SIG levels constant.
tY Which ONE of the follovt'describes the (1) cause, (2) required action and (3) consequence of no operator action?
A. (1) # I S/G FRV is opening, (2) return # I SIG level to program, (3) Auto Turbine Runback initiated BY (1) # I SIG FRV is opening, (2) return # I S/G level to program, (3) Feedwater Isolation initiated C. (1) MFP master contoller failing high, (2) control MFP speed using manual, (3) Auto Turbine Trip initiated D. (1) MFP master contoller failing high, (2) manually trip turbine, (3) Feedwater Isolation initiated Ref WB 3-AOI-1600 Note: electronic copy of A01 16 corrupt Distractor analysis:
A is incorrect because the consequence is a P-14, Hi-Hi SG level which initaties a FW isolation.
B is correct because only one SG is rising, hence a FRV is the cause, action is from AOI-16 for FRV failure and FW isolation occurs with no operator action at P-14.
C is incorrect because a problem with the MFP controller would affect all SG's the same.
D is incorrect same as C.
Thursday, October 31,2002 06:06:00 PM 37
QUESTIONS REPORT for WBfindraft
- 38. 055EK3.02 OOl/TlGliTlGl/iM (4.3/4.6)iBnVB02301/UELKFO Which ONE of the following is a purpose for depressurizing all intact SGs to 300 psig during the performance of ECA-0.0, "Loss of Shutdown Power"?
A. Reduces DP across SG U-tubes to minimize possibility of tube rupture.
BY Reduces DP across RCP seals to minimize leakage and loss of RCS inventory.
C. Maximizes Natural Circulation flow before Reflux cooling begins as the RCS becomes saturated.
D. Maximizes Natural Circulation flow to allow reactor vessel head to cool since CRDM are unavailable.
WB bank, validated with ECA-0.0 Thursday, October 31,2002 06:06:01 PM 38
QUESTIONS REPORT for WBfindraft 39.055K3.01001iT2G2iT2G2NACUUM PUMP/C/A 2.512.7/BIWB02030l/C/RLM Given the following conditions:
- Reactor power is steady-state at 100%.
- Rod control is in automatic.
- Condenser Vacuum Pumps 1A and 1B are running with I C pump out of service for maintenance.
Which ONE of the following conditions could result if NO operator action is taken in response to a COND VACUUM PUMP 1B SEAL WTR PRESS LOW alarm?
A. Rising megawatt output and rising steam seal header pressure.
B. Rising megawatt output and rising condenser hotwell level.
C. Dropping megawatt output and dropping condensate temperature.
DI Dropping megawatt output and rising condensate temperature.
WB Lesson plan 3-OT-SYSI 100, obj 4 Distractor analysis:
Degraded vacuum causes megawatt output to decrease due to reduce delta H. Therefore, A and B are incorrect.
Condenser is a saturated system, so higher Psat means higher Tsat. Therefore D is correct and C is incorrect.
Thursday, October 31,2002 06:06:01 PM 39
QUESTIONS REPORT for WBfindraft
- 40. 56K1.03 001/'T2Gl/T2Gl/FEED PUMP TRIP/C/A 2.6/2.6/N/WB020301/CIRLM
&vpu r#L Cotjouu,;): ' 2-Unit 1 is at 72% power. A control problem causespFCV-210, Condensate Inlet to 1A MFPT Condense! to close.
Which ONE of the following describes the effect on continued plant operation?
A. ' , the Standby MFP starts and Rx power BY lAUWJ%p ' , the Standby MFP starts and Rx power can remain 72%.
- c. -1 ' , the Standby MFP does not start and Rx power must be reduced.
D. , the Standby MFP does not start and Rx powe Ref: 3-OT-SYS002A, obj. 15 3-OT-SYS003A, obj. 5 & 7 Distractor analysis:
A and D are incorrect, because the 1A MFP trips on low condenser vacuum C is incorrect because the standby feed pump auto starts B is correct, because the standby feed pump starts and is able to carry -15% turbine power and the 1B MFP can carry 67%, the sum of which is above 72%.
Thursday, October 31,2002 06:06:02 PM 40
QUESTIONS REPORT C $ v e p 77th &lIWr; for WBfindraft
- 41. 059AA1.01 OOliTlG2/Tldl/RADFLUID LEAKAGE/M 3.5/3.5/N/CVB020301/C/RLM
-Unit 1 is operating at 50% power
-Annunciator 178-A, SG BLDN 1-RM-120/121 LIQ RAD HI alarms Which ONE of the following correctly describes plant response and the actions of the control room operators?
A. No automatic action and operators verify alarm validity.
B! Operators verify SG Blowdown is isolated to Cooling Tower Blowdown and aligned to Condensate Demin.
C. Operators verify Auxiliary Bldg Rad Waste discharge header is isolated from the blowdown line.
D. Operators verify Cooling Tower blowdown flow is bypassed to the 35 acre pond.
Ref: WB Lesson Plan 3-OT-A0131000, obj. 2 & 3 ARI 178-A Distractor analysis:
A is incorrect because RM 120/121 have auto actions B is correct base on ARI 178-A C is incorrect the Aux Bldg in not involved in SGBD stream D is incorrect because this action would not prevent an offsite release.
Thursday, October 31,2002 06:06:02 PM 41
QUESTIONS REPORT for WBfindraft
- 42. 059K6.09 OOlK2Gl/T2GllSPEED CONTROLICIA 2.4/2.6R*TIWB020301/Cl~M Unit 1 is at 60% power with both 1A and 1B MFP's operating in AUTO.
/;PT-1-33, Steam Header Pressure, output begins to slowly drift-Assume no operator action.
Which ONE of the following describes the effect on the Main Feed Water System?
A. Fe-e,d Water Reg valves begin to close and then both MFP's discharge pressure begins to i$BZse.L f poae rt 5e B. Both MFP's ischarge pressure begins to i n m s e and all @tfFeed Water Reg valves begin to open.
drq C:' Both MFP's discharge pressure begins to dty& se and a l l w F e e d Water Reg valves begin to open.
D. Fejd Water Reg valves begin to close and then both MFP's discharge pressure begins to de&%e.
Ref WB Lesson Plan 3-OT-SYS0003A, obj. 6 WB Dwg. 47W611-03-02 Distractor analysis:
C is correct because input from d/p program remains constant because steam flow remains contant. However, PT-1-33 failing low, causes the dlp actual (as sensed) to increase above program. This in turn causes the speed summer to decrease its output to the speed control station which will reduce feedpump speed and it's discharge pressure. Flow rate will decrease and the FRV's will open to increase flow to the S/G's.
All other answer's are incorrect because they are variations of the answer with one parameter going in the wrong direction.
Thursday, October 31,2002 06:06:02PM 42
QUESTIONS REPORT for WBfindraft
- 43. 061A1.04 00 I/T2Gl/T2G l/CST/CIAiMIWB0230 l/C/KFO Which ONE of the following describes the base assumptions for minimum CST volume for a Loss of Offsite Power?
A. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in Mode 3 followed by 50 "F/hr cooldown rate to Mode 5.
B. Immediately cooldown at 50 "Flhr cooldown rate to Mode 4 .
C.' 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in Mode 3 followed by a 50 'Flhr cooldown rate to Mode 4.
D. immediately cooldown at 50 "Flhr cooldown rate to Mode 5.
Modified from Byron - validated from WB AFW System description N3-38-4002
- a. incorrect - capacity is for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> hold then cool to mode 4
- b. incorrect - capacity for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and then cool to mode 4
- c. correct - stand pipe in CST ensures 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> hold and then 50 Flhr cooldown to mode 4
- d. incorrect - capacity to hold for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with 50 Flhr cooldown to mode 4 Thursday, October 31,2002 06:06:03 PM 43
QUESTIONS REPORT for WBfindraft 44.061AAl.01 00 l a 1 G2/TlG2/iM/N/WB02301/CKFO 1
Which ONE of the following area radiation monitors intiate a Containment Ven@tion Isolation?
A. Waste Disposal System Gas Effluent Monitor, 0-RM-90-118 13@n-9a-r 3 0 BY Containment Purge Rad Monitor, I'RM-90-130 C. Fuel Pool Area Monitor, 0-RM-90-102 I-D. Personnel Access Area Monitor, RM-90-2 New - Lesson plan SYS9OA -
- a. incorrect - hi rad closes the vent header isol
- b. correct
- c. incorrect - isolates the aux building, does not generate an AB1
- d. incorrect - no auto actions Thursday, October 31,2002 06:06:03PM 44
QUESTIONS REPORT for WBfindraft
- 45. 062A3.05 001/T2G2/r2G2/LOSP LOOPICIA 3.5/3.6/81WB020301/C/RLM Given that the following occurred in sequence:
- A small break LOCA occurred which resulted in a reactor trip and SI.
- The SI signal was reset during the performance of E-I, "Loss of Reactor or Secondary Coolant."
- A loss of offsite power (LOOP) occurred and the diesel generators loaded as designed.
Assuming no operator actions, which ONE of the following would be the status of the loads on the 6.9kV SD boards?
A. All equipment powered from the SD boards with the control board switch in automatic will be restarted.
B. No 6.9kV SD board loads are automatically restarted.
CY Equipment normally started during a L O j P will be automatically restarted; SI and RHR pumps remain OFF.
0 D. All equipment that was operating prior to the LOSP will be automatically restarted; All running ESF equipment will be reenergized
Reference:
WB Exam Bank (inadequate info to verify, missing lesson plans on EDG loading.
Thursday, October 31,2002 06:06:03 PM 45
QUESTIONS REPORT for WBfindraft 46.062AG2.Eg 0 l / T l G l i T lG 1/lMiB/WB02301/CiELIO Which of the following correctly identifies the emergency cooling water supply to the control and station service air compressors, per AOI-13 "Loss of ERCW", if normal ERCW supply is lost?
A.
?Raw Cooling Water header B.J Raw Service Water header C. Unit 1 Primary Water header D. Demin Water header Ref - AOI-13, 47~850-1,47~845-5
- a. incorrect - RCW does not support the compressers
- c. incorrect - no ERCW connection to support compressers
- d. incorrect -
Thursday, October 31,2002 06:06:04PM 46
QUESTIONS REPORT for WBfindraft
- 47. 063K3.02 001/T2G2/T2G1/CONTROL POWEWCIA 3.5/3.7IIWB020301lCC/RLM VI3D
. G M w a s running para114 to the 6.9kV Shutdown Board for surveillance.
In additon to the expected post trip annuciators, the operator notes annunciators:
17-A 125 DC VITAL CHGWBATT I ABNORMAL 6 125 DC VITAL BATT BD I ABNORMAL CKTS ISOLATED 10-/2 Which ONE of the following describes the response to this event by6GM?
/e**
A. %G;lPCtrips and its output breaker opens 14-fi B. D G l P continues to run and its output breaker opens r.4-A C. D G M trips and its output breaker remains closed 1R.P DI D G M continues to run and its output breaker remains closed Ref: WB lesson plan 3-OT-A012100, obj. 1 & 2 3-OT-SYS057P, obj. 8 WB Dwgs 1-45W724-1 1-45W727 1-45W760-82-2 1-45W760-211-4 Distractor analysis:
A is incorrect because the DG can run using its own DC control power, but the output breaker has not control power to trip.
B is incorrect because the output breaker has no control power to trip.
C is incorrect because the DG does no trip D is correct because the DG has its own control power and the output breaker remains closed due to no control power.
Thursday, October 31,2002 06:06:04PM 47
QUESTIONS REPORT for WBfindraft
- 48. 064K2.03 00 ~ I T ~ G ~ / T ~ G ~CONTROL
/ D / G POWERIM 3.213.6iNiWB02030 1ICIRLM Unit 1 is at 100% power All Diesel Generators are in standby jn-fi Annunciator 281-A, DG CONTROL POWER FAILURE fofDG.#f Which ONE of the following describes the status of the Diesel GeneratoGAFTER the annunciator alarms?
1P'sf A. vDGM starts and is operable.
1 P#
B y ' b G M does not start and is inoperable.
C. All four diesel generators start and are operable.
D. All four diesel generators do not start and are inoperable Ref: WB lesson plan 3-OT-SYS082B, obj. 10 ARI 281-A Dwg 1-45W727 1-45W760-82-2 1-45W760-82-4 1-45W760-82-6 Distractor analysis:
A is incorrect because the starting air solenoids need power from the Diesel 125V DC Distribution Panel 1-DPL-82-A-A which is deenergized as evidenced by the annunciator 281-A.
B is correct because the starting air solenoids have no power and cannot respond to an auto start signal C and D are incorrect because they continue to have control power and all 125V vital battery boards are still energized.
Thursday. October 31, 2002 06:06:04 PM
QUESTIONS REPORT
& "eu T H E F O I I uw : for WBfindraft
- 49. 065.4.41.01 001/T1G3/TlG2/lCIAiNN/WB0230llClRLM
-Unit 1 is at 100% power
- Annuciator 42.6, C&SS AIR COMPR SEQUENCER UNDERVOLTAGE
- Control Air pressure is slowly decreasing Which ONE of the following describes actions for locally controlling air pressure?
A. Take manual control of the Foxboro 43AP pneumatic controller B. Shift AC control power C. Start and stop Control Air Compressors D1 Take manual control at the local control station using the solenoid manual valve New - ref: Watts Bar ARI 42-E and lesson plan 3-OT-SYS032A, obj 11 Distractor analysis:
A incorrect because controller has no power B incorrect because control power is DC,but shifting control power takes precedence over taking manual control of unloader C is incorrect due to no procedural guidance and undesirable from equipment standpoint D is correct IAW ARI Thursday, October 31,200206:06:05 PM 49
50.067AK1.02 001/T1GliTlGI/FIRE ON&
Which me of the followin QUESTIONS REPORT for WBfindraft Room?
Q d G h N A A.
B. og system c.' am system D. 0 2 system REF: Modified from Watts Bar Exam Bank SYS026A.21 Thursday, October 31,2002 06:06:05 PM 50
QUESTIONS REPORT for WBfindraft 5 1.068AK3.18 00 1 f I 1Gl/r 1G 1/EVACUATION/M/N/WB0230 1/C/KFO Evacuation of the Control Room is reauired due to a control room fire. The actions of AOI-30.2, " ' ' ' ' ", prior to evacuating the control room include which of-eht QIfk BY Deenergizing the RCP start bussespxl'Electrical Control Board J"
C. Initiating 4 - m D. T' Ref: AOI-30.2 Fire Safe Shutdown, appendix C steps 1 - 8,
- a. incorrect, feedwater pump status is not addressed prior to evacuation
- c. incorrect, ensure the MSlVs are closed but does not direst initiating a main steam isolation signal
- d. incorrect, addresses ensuring the 6.9 bus energized but does not address tripping any unnecessary DGs Thursday, October 31,2002 06:06:05PM 51
QUESTIONS REPORT for WBfindraft
- 52. 068K1.07001/T2Gl/T2GI/RAD WASTE/M 2.7/2.9/NiWB020301/C/RLM ob Which we of the following describe how lncore lntrumentation Seal Table leakage enters the Liquid Radwaste System?
A. Drains to the Reactor Coolant Drain Tank apid pumped to the Tritiated Drain Collector Tank.
B:' Drains to the
&e 3 C. Drains to the Eauioment
,
- Drain SumD.to the Flow Drain Collector Tank.
+ O ! r-4 D. Drains to the Reactor Building - Floor and Equipment Drain Sump $3 pumped to the Floor Drain Collector Tank.
Ref: WB lesson plan 3-OT-SYS077A, obj.
Dwg. 1-47W851-1 Distractor analysis:
See attached drawing Note: From the drawing, it appears that the Reactor Building Floor and Equipment Drain Pocket Sump has its own pumps, but can overflow into the Reactor Building Floor and Equipment Drain Sump. If this becomes and issue, we can substitute the Passive Sump for distractor D.
Thursday, October 31,2002 06:06:06 PM 52
QUESTIONS REPORT for WBfindraft 53 069AK2.03 00 l G l ~ l G l / C T M TINTEGRITY/C/A 2.8/2.9/N/WB020301/C/RLM 4 , v t h dU e/(LN4!8*{**
Unit 1 is at 100% power.
Annuciator 158-A, UPR CNTMT AIRLOCK INNEWOUTER alarmed for no apparent reason on the previous shift. Maintenance personnel have been dispatched to investigate the alarm.
They report that they have opened the outer door and found the inner door ajar.
Which ONE of the following describes the correct actions required by A01 12, "Loss of Containment Integrity?"
A. Verify the outer door closed within one hour and restore the air lock to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. Repair the inner door within one hour and lock the outer door within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
CY Close the outer door within one hour and lock the outer door within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. Commence plant shutdown within one hour and be in Mode 5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Ref: WB 3-OT-A011200, obj. 4 WB 3-OT-AO11200, pp. 5 WB Tech Specs Distractor analysis:
A is incorrect because the air lock is not inoperable because the outer door is operable. These actions are for an inoperable air lock.
B is incorrect because there is no requirement to repair the inner door within one hour.
C is correct per Tech Specs 6.2 condition A.
D is incorrect because there is no requirement per A01 12 to commence shutdown within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Thursday, October 31.200206:06:06PM 53
QUESTIONS REPORT for WBfindraft
- 54. 071K3.05 001/T2Gl/T2Gl/ARM PRM/C/A3.2/3.2/M/WB020301/C/RLM Given the following plant conditions:
- A Gas Decay Tank is being released to the atmosphere using the normal release path.
- The tank being released has HIGH gaseous activity.
@'PCV-77-117, Plant Vent Pressure Control Valve fails toward the open position.
Which ONE of the following radiation monitor pairs will alarm to alert the operators and secure the release, respectively?
I-A. Shield Building Ventilation Monitor [RE-90-4001 and Aux Building Vent Monitor
[O-RE-gO-I011.
0-B. Auxiliary Building Ventilation Monitor [RE-90-1OIA] and Shield Building Ventilation Monitor
[RE-90-4001.
l-1-
C:' Shield Building Ventilation Monitor [RE-90-4001 and WDS Gas Effluent Monitor
[O-RE-gO-I 181.
0-D. Auxiliary Building Ventilation Monitor [RE-90-101A] and WDS Gas Effluent Monitor [O-RE-gO-I 181.
Ref: WB lesson plan 3-OT-SYS077B, obj. 9 and 3-OT-SYSOSOA, obj. 7 r analysis Distract0 A is incorrect because the AB monitor is unrelated to WDS release B is incorrect same as A C is correct because the Shield Blda monitor will upscale and the WDS effluent monitor will trip FCV-77-119 shut and secure release.
D is incorect same as B Thursday, October 31,2002 06:06:06 PM 54
QUESTIONS REPORT
&,"ep Tnth F ~ I I W ; ~ for WBfindraft
- 55. 07262.4.3 1 001/T2GliT2Gl/ARI RESPONSEM 3.3/3.4/"8020301/C/RLM
-Unit 1 is in Mode 6 9 0 - 13s
-Fuel Movement is in progress annuciator 186-8 MCR AREA O-RM- Q ldf D HI alarms Which ONE of the following correctly describes the actions of the control room operators?
A. Verify Control Building Isolation occurs.
B. Notify fuel handling crew to stop all fuel movement.
CY Notify RADCON to investigate the alarm.
D. Verify emergency control building air cleanup and pressurizing fans RUNNING.
Ref: WB Lesson Plan 3-0T-O90A, obj. 9 ARI 186-6 Distractor analysis:
A and D are incorrect because they are auto actions which occur if the MCR Intake rad monitors 125 or 126 alarm B is incorrect because there would be no relation between Control Room area rad monitor and refueling operations (and no other rad monitor alarms are in)
C is correct per ARI guidance Thursday, October 31,2002 06:06:07PM 55
QUESTIONS REPORT for WBfindraft
- 56. 07SA4.01 001/T2G2/T2G2//M (3.2/3.2)/s~O2301/C/KFO Given the following:
- Reactor trip and Safety Injection occurred while the plant was operating at 100% power
- Four ERCW pumps were running in their normal alignment before the =occurred.
Which of the following identifies ERCW pump status after the SI and the effect it has on the Condenser Circulating Water (CCW) system make-up?
A. Four ERCW pumps running; CCW make-up is provided only from ERCW since RCW bypass strainer is isolated.4~tlr 62 & y d .
B. Four ERCW pumps running; CCW make-up is provided only from ERCW since RCW bypass strainer is routed through the overflow structure.
CY Four ERCW pumps running; CCW make-up is provided from both ERCW and RCW D. Four ERCW pumps running; CCW make-up is not required since the Unit is tripped.
has a bypass that ensures continuous make-up to CCWREF: lesson plans 3-OT-SYS027A (LO 2) and 067A (LO 13)
- a. incorrect - RCW has a bypass that ensures continuous make-up to CCW
- b. incorrect - RCW has a bypass that ensures continuous make-upto CCW
- c. correct - 2 pumps per train start on SI and RCW has a bypass that ensures continuous make-up to CCW
QUESTIONS REPORT for WBfindraft
- 57. 076K2.08001/T2G3/T2G3/POWER SUPPLYiM 3.1/3.3iN/WB020301/CRLM Which ONE of the following describes the power supply for I-FCV-67-92$, Lower Containment IC Cooler ~ u p p ~? y ? ~
A? 480 V Reactor MOV Board 182-8 B. 480 V Shutdown Board 182-8 C. 480 V Reactor MOV Board 281-8 D. 480 V Shutdown Board 1B1-B Ref WB Lesson Plan 3-OT-SYS067A, no specific learning objective DwgS: 1-45W760-67-5 1-45W751-11 1-45w749-4 1-45-W724-2 Distractor Analysis:
A is correct based on attached dwg's.
B and D are incorrect because the 480 V shutdown board does not directly feed any MOV's C is incorrect because they have unit 2 designators.
Thursday, October 31, 2002 06:06:08 PM 57
QUESTIONS REPORT for WBfindraft
- 58. 079K4.01001/T2G2iT2G2/SAS CROSS CONNECT/M 2.9/3.2/B/WB020301/C/ELiRLM If Station Control and Service Air System air pressure is dropping, the Service Air System automatically isolates from the Control Air System when pressure drops below which ONE of the following?
A l 80 psig.
B. 79.5 psig.
C. 78 psig.
D. 70 psig.
Ref: WB Exam Bank WB Lesson Plan 3-OT-SYS032A, obj. 16 Distractor analysis:
A is correct, see lesson plan pp. 33 (attached)
B is incorrect, corresponds to isolation setpoint of Aux Air C is incorrect, doesn't correspond to any auto event D is incorrect, corresponds to essential and non-essential air to the Rx Bldg isolatation Thursday, October 31,2002 06:06:08PM 58
QUESTIONS REPORT for WBfindraft
- 59. G2.1.2 001/r3/T3/PROCEDURE COMPLIANCEM 3.0/4.O/"B020301/C/RLM A! n the event of a national security emergency and no action consistent with the license
-condition or TS that can meet the national security objectives is immediately apparent an A is correct, see attached B is incorrect, lacks SRO approval statement C is incorrect, lacks national command authority requirement D is incorrect, refers to risk significant equipment
\
Thursday, October 31,2002 06:06:08 PM 59
QUESTIONS REPORT for WBfindraft 60.G2.1.3 001iT3/T3/SHIFT TURNOVEFUM 3.7/3.8/BiWB020301/C/RLM A Unit 1 UO is preparing to relieve the on-shift UO for a lunch break during a normal shift.
6U E Which m P '
f the following describes their required minium actions when this occurs?
A. A review of the Operating Log since last held shift or 3 days, whichever is less, Standing Orders, LCO(s) in actions B. A review of the Rounds sheets/Abnormal readings , Standing Orders, any SllTest in progress/planned C:' Abnormal or unusual plant conditions existing, any evolutions in progress, actions anticipated D. Radiological changes in plant during shift, a walkdown of the MCR control boards, SllTest in progresslplanned Ref: Surry exam 2002 OPDP-1, pp. 24 and Shift Turnover Checklist A, B, and D are items from the Shift Turnover Checklist which is NOT required for a temporary relief per page 24 of OPDP-1, pp.24 and are therefore incorrect.
C are the items listed on pp. 24 as required for temporary turnover.
Thursday, October 31,2002 06:06:09 PM 60
s QUESTIONS REPORT for WBfindraft
- 61. G2.1.32 001iT3/T3/COMPONENT COOLING W A N 3.4/3.8MiWB020301/C/M Flowrates in the Component Cooling Water System is limited to 12000 gpm shell side flow.
Which ONE of the following explains the basis for this precaution?
A. It limits tube dlp and Heat Exchanger loading.
B. It limits pump runout and tube vibration.
C! It limits tube vibration and Heat Exchanger loading.
D. It limits pump runout and tube erosion.
Ref: WB lesson plan 3-OT-SYS070A, obj. 1 Sol-70.01, section 3, P&L's Distractor analysis:
C is correct, see P&L A,B, and D are incorrect due to either erosion or pump runout which are not mentioned but is plausible at high flowrates.
Thursday, October 31,2002 06:06:09 PM 61
QUESTIONS REPORT
&ygN rpfi / - u / / v m , ~ for WBfindraft
- 62. G2.2.12001/T3/T3/INVENTORY BALANCEICIA 3.0/3.4/N/WB020301/C/RLM
- Unit 1 is at 100%
- p SI-68-32, Reactor Coolant System Water Inventory Balance is in progress
-- 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since commencing data collection Final readings from the RCSWIB indicate that the total RCS leakage rate is -0.08 gpm Which ONE of the,following describes the correct action to be taken?
Ql A. Sign the surviellance as satisfactory B.J Continue data collection for an additional hour C. Void the surveillance and perform at a later time D. Investigate to determine the source of inleakage to the RCS Ref WB procedure SI-68-32, pp. 16 & 17 A is incorrect because data must be collected for at least an additional hour before the surveillance can be termed complete B is correct, see SI-68-32, pp. 16 & 17 C is incorrect because it is contrary to procedure guidance D is incorrect unless the leakage continues to be negative by more than -0.10 gpm after the second data collection Thursday, October 31,2002 06:06:09 PM 62
QUESTIONS REPORT for WBfindraft
- 63. G2.2.13 001/T3/T3/TAGGING/M 3.6/3.8/NIWB020301lC/RLM ouE Which -of the following is NOT a reason to tag a device, component, or piece of equipment per SSP-10.2, Clearance Program?
A! Design deficiency B. DCN C. Test activity D. Open Work Orders WB procedure SPP-10.2, pp. 9 Distractor analysis:
See attached Thursday, October 31,2002 06:06:10 PM 63
QUESTIONS REPORT for WBfindraft
- 64. G2.2.22 001/T3/T3/SAFETY LIMITSM 3.4/4.l/M/WB020301/C/RLM Which one of the following sets of conditions represents a violation of a technical specification safety limit and required action?
A. Power = IO%, Pressure = 2400 psig, Tavg = 655"F, be in Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> BY Power = 80%, Pressure = 2250 psig, Tavg = 640°F, be in Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Power = IO%, Pressure = 2400 psig, Tavg = 655"F, restore to within limits in% 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. Power = 80%, Pressure = 2250 psig, Tavg = 640°F, restore to within limits in {2 hours Ref: Modified from TP 2000 by adding required action to pick up LCO part of KA.
WB TS Section 2, Safety limits Distractor analysis:
A and C are incorrect because they are within limits and no action required D is incorrect, because even though it is out of limits, it must be restore within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is the DNB parameter spec.
B is correct because it is both out of limits and has the correct required action per TS Thursday, October 31, 2002 06:06:10 P M 64
QUESTIONS REPORT for WBfindraft
- 65. (32.3.1 001iT3iT3iDOSE EQUIVILENTSM 2.6/3.O/B/WB020301/CRLM Which we of the following dose components are included in a Radiation Worker's Occupational Dose?
A. Total Effective Dose Equivalent and Planned Special Exposures.
B. Planned Special Exposures and Committed Effective Dose Equivalent.
C. Deep Dose Equivalent and Planned Special Exposure D: Deep Dose Equivalent and Committed Effective Dose Equivalent.
Ref Surry exam 2002 WB Rad con procedure SPPd.1, section 5, pp. 32 WB lesson plan 3-OT-RAD0003, pp.10 Thursday, October 31,200206:06:10 P M 65
QUESTIONS REPORT for WBfindraft 66.G2.3.4001/T3/T3/EXPOSURELIMITS/M 2.5/3.l/B/WB020301/C/RLM Given the following plant conditions:
- A LOCA has occurred and a SAE has been declared.
- The TSC and OSC have been activated.
- To prevent core damage it is recommended that entry be made into Safety Injection Pump Room I A .
- Projected dose rate in the pump room is 1 . 1 6 ~ 1 0 mr/hr
~
- Duration of the exposure is expected to be 3 minutes.
Which ONE of the following must authorize this exposure?
A. Site Vice President B. Plant Manager C! Site Emergency Director D. Radcon Manager
REFERENCES:
EPIP-15 p.3, SPP-5.1 p.10 WBN Exam Bank
- d. incorrect - per EPIP-15 of the Radiological Emergency plan the Site Emergency Director must authorize emergency dose limits in excess of TVA admin limits and 10 CFR 20. Examinee may select since the Radcon Manager is responsible for completing the paperwork and he must authorize exceeding the limit during non-emergency conditions.
- c. correct - With a projected dose of 1.16E+5 mr/hr, the total dose to respond to this emergency condition is 5.8 Rem.(I.l6E+5 mWhr / 60 minutes x 3 minutes). Per EPIP-15 of the Radiological Emergency plan the Site Emergency Director must authorize emergency dose limits in excess of TVA admin limits and 40 CFR 20.
- b. incorrect - per EPIP-15 of the Radiological Emergency plan the Site Emergency Director must authorize emergency dose limits in excess of TVA admin limits and 10 CFR 20. Examinee may select since Plant Manager must authorize exceeding 5 R during non-emergency conditions.
- a. incorrect - per EPIP-15 of the Radiological Emergency plan the Site Emergency Director must authorize emergency dose limits in excess of TVA admin limits and 10 CFR 20. Examinee may select since Plant Manager must authorize exceeding 5 R during non-emergency conditions.
Thursday, October 31,2002 06:06:11 PM 66
QUESTIONS REPORT for WBfindraft
- 67. G2, 3.4NWBO2030l/CiRLM
-Unit 1 is in Mode 3 following a refueling outage
-Both Containment Purge Systems are in operation
-The Shifl Manager has directed that the Containment Purge System be secured in accordance 01-30.02, CONTAINMENT PURGE SYSTEM.
q h i c h ONE of the following should be considered prior to securing Containment Purge?
A. Outside air temperature B. Outside atmospheric pressure CY Radiological implications D. Containment Purge HEPA and Charcoal filter DP Ref: WB lesson plan 3-OT-SYS30C, obj. 12 WB procedure Sol-30.02 Distractor analysis:
A and D are incorrect because they only apply while the system is in service B is incorrect, because it only applies when placing the system in service C is correct because changes in ventillation, particularly reduction in ventillation can have adverse affects on radiation levels. This is also a precaution in the procedure related to securing CTMT purge. (see below)
CAUTION Radiological implications (e.g.: causing an area to become airborne or raising the humidity in contaminated areas) should be considered any time Containment Purge is secured.
Thursday, October 31,2002 06:06:11 PM 67
QUESTIONS REPORT for WBfindraft
- 68. (32.4.I 001/T3/T3/IMMEDIATE OP ACTION/C/A 4.3/4.6/N/WB020301/C/RLM
& Y E N THE ItolLlnA9&
-The Unit is at 100% power.
e -A Loss of Shutdown Power occurs Which ONE of the following describes the correct procedure and immediate operator action.
A. E-0, Rx Trip 01 Safety Injection, ensure Rx is tripped by Rod all bottom lights lit BY ECA-0.0, Loss of Shutdown Power, ensure Rx tripped by neutron flux dropping C. FR-S.l, Nuclear Power Generation/ATWS, ensure Rx is tripped by neutron flux dropping D. ECA-0.0, Loss of Shutdown Power, ensure Rx tripped by rod bottom lights lit Ref: WE lesson plan 3-OT-PA11204, obj 1 WE procedures PAI-1204 E-0 ECA-0.0 iignts have
- nu p Distractor analysis:
A is incorrect because rod bottom lits will not have power E is correct because emergency procedures can be entered directly from a Loss of Shutdown i/ power and Nl's will still be powered from battery via inverter.
C is incorrect because FR-S.l is not an allowable procedure to enter EOP's D is incorrect because rod bottom lits will not have power
\v Thursday, October 31,200206:06:11 PM 68
QUESTIONS REPORT for WBfindraft
- 69. G2.4.11 001/"3/T3/SG LEAWCIA 3.4/3.6/M/WB020301/C/RLM Unit 1 is at 100% power with known leakage in SG 2 of 0.05 gprn The Chem Lab reports that today's leakage is 0.06, up from yesterday's reading of 0.05 gprn Which ONE of the following should be performed?
Reference provided A l Be in Mode 3 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. Reduce load to hot standby in accordance with AOI-39, then cooldown and depressurize the RCS.
C. Trip the reactor; enter E-0, then transition to E-3.
D. Convene PORC to evaluate continued operation.
WB lesson plan 3-OT-A01300, obj. 8 Procedure AOI-33, appendix B and C Distractor analysis:
A is correct per table in App. B B is incorrect because it the action for greater than 600 per day thru all or 150 per day thru one C is incorrect because 0.6 is well within charging capability which is the decision point for E-0 D is incorrect because it is the action for leaks less than 0.05 per day Thursday, October 31, 2002 06:06:12 PM 69
QUESTIONS REPORT for WBfindraft
- 70. G2.4.16 001/T3/T3/GO TOiM 3.0/3.9iBIWB020301/C/RL,M While in the Emer ency Response procedures the team is directed to "Go To" another procedure, which .& of the following is the correct implementation of this action?
A. The "GO T O implies the procedure in use is no longer applicable, and any tasks in progress need not be completed.
B. Tasks still in progress must be completed prior to the transition directed by the "GO T O step.
CY The "GO T O implies the procedure in use is no longer applicable, but any tasks in progress should be completed.
D. Tasks still in progress need not be completed prior to the transition directed by the "GO TO" step, unless preceded by a double asterisk.
WB lesson plan 3-OT-PAI-1204, obj. 13 & 19 WB procedure PAI-1204 Bank: From Surry 2002 Distractor analysis:
Answer C is correct, see below paragraph from PAL1204 Answer A and B are incorrect due to timing or required completion Answer D is incorrect because double astericks relates to high and low level steps vice transitions.
From PAL1204:
Transition to another step or instruction may be completed before completion of the task in progress, provided that completion of the task is verified at a later time.
Transitions which are not high level action steps are identified with a double asterisk preceding the words GO TO and are in bold face type.
Thursday, October 31,2002 06:06:12 PM 70
QUESTIONS REPORT for WBfindraft 71.G2.4.8001fT3/T3/PROCEDURE TRANSITIONiCiA 3.0/3.7/BiWB020301/C/RLM Given the following condition:
- The crew has entered ECA-0.0 due to a loss of both SD Bds.
- The Load Dispatcher has recovered one 161KV line from Watts Bar Hydro.
- The crew has implemented AOI-35.
Which ONE of the following actions should the crew take?
A. Immediately transition to ECA-0.1, Recovery from Loss of Shutdown Power without SI required.
B. Immediately transition to ECA-0.2, Recovery from Loss of Shutdown Power with SI required.
C. Manually actuate SI and return to E-0, Rx Trip or Safety Injection.
DI Continue with ECA-0.0, Loss of Shutdown Power while concurrently performing AOI-35, Loss of Offsite Power.
Ref: WB procedure ECA-0.0 and AOI-35 WB bank question, changed two obviously incorrect distractors Thursday, October 31,2002 06:06:12 PM 71
QUESTIONS REPORT for WBfindraft
- 72. WE03EK2.2 OOl/TlG2iTlG2/HEAT REMOVALICIA 3.7/4.01B/WB020301ICIRLM Given the following plant conditions:
- A small break LOCA has occurred.
- RCPs have been tripped.
- Appropriate actions in accordance with E-0 and E-I have been
- completed. /47s RCS pressure is stable at I'S9psig.
- ECCS is operating in cold leg injection mode.
Which ONE of the following statements describes the primary method of decay heat removal at this time?
A! Heat transfer between the RCS and the S/Gs due to natural circulation flow.
B. Heat transfer between the RCS and CCS via the RHR Heat Exchangers.
C. Heat transfer from the injection of water from the RWST and the removal of steadwater out of the break.
D. Heat transfer from Reflux boiling in the SIGs.
Ref WB Lesson Plan 3-OT-EOP0100, no specific learning objective found WB lesson plan 3-OT-SYS063A, no specific learning objective found WB exam bank Distractor Analysis:
A is correct because due to the thermodynamic ? H between the primary and secondary and resultant heat transfer rate will exceed the heat transfer into the injection flow water.
B is incorrect because CCS flow is isolated from the RHR Hx's at this point in the accident.
C is incorrect same as A D is incorrect because at this point in the accident the SIG U-tubes are still filled with water.
Thursday, October 31,2002 06:06:13PM 72
QUESTIONS REPORT for WBfindraft
- 73. WE05EA 1.3 001/TIG2/TlG2/FEED AND BLEEDICIA 3.8/4.2iBIWB020301/C/RLM Given the following plant conditions:
- Unit is operating at 100% power at EOL.
- Total loss of feedwater occurs and operators implement FR-H.l, "Loss of Secondary Heat Sink".
of eed te addition is available and the operators have
- No initiate m
%n e
d
?
i!
- Manual Safety Injection was initiated and when the operator attempted to open the pressurizer PORVs, PCV-68-340 failed to open.
Which ONE of the following describes the correct operator mitigation strategy to respond to this problem?
A. Stop one Centrifugal Charging Pump to reduce loss of inventory through PORVs.
B. Close any open Pzr PORV to conserve RCS inventory and return to the steps to re-establish Main Feedwater.
Cy Open the reactor head vents to reduce RCS pressure since one pressurizer PORV may not provide sufficient heat removal capacity.
D. Verify PORV, 1-PCV-68-334, and it's block valve open to reduce RCS pressure since 1 Pzr PORV provides adequate heat removal capacity for a loss of heat sink.
Ref WB lesson plan 3-OT-FRH0001, obj. 9 & 10 Distractor analysis:
- a. Incorrect - one PORV is not sufficient to provide adequate heat removal.
- b. Correct - increases the bleed path capability and reduce pressure to ensure the core remains cooled.
- c. Incorrect - procedure directs bleed and feed not depressurizing a SG which would be a less effective cooling method.
- d. Incorrect - more bleed path capacity is needed to ensure pressure reduction and cooling capability, not less injection.
Thursday, October 31,2002 06:06:13 PM 73
/
I QUESTIONS REPORT for WBfindraft
- 74. WE10EA2.2 OOllTl GIlT1G1//CIA (3.4/3.8)1B/WB0230 I/C/EL Given the following plant conditions:
- Reactor trip occurred with subsequent loss of RCPs.
- Operators have implemented ES-0.2, "Natural Circulation Cooldown".
- A cooldown rate of 25"F/hour has been established.
- RCS depressurization has been initiated while maintaining subcooling
> 165°F.
- Operators are monitoring PZR level and RVLIS for void formation.
- The OAC observes that loss of inventory in the Condensate Storage Tank is imminent.
Which ONE of the following describes the appropriate procedural actions?
A. Stop the cooldown and remain in ES-0.2.
B. Raise the cooldown rate and remain in ES-0.2.
C. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and lower the cooldown rate.
D.* Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and raise the cooldown rate.
The correct answer is D.
- a. Incorrect - loss of CST inventory should cue the examinee that transition to ES-0.3 is appropriate. Examinee may believe stopping cooldown is appropriate to conserve inventory.
- b. Incorrect - loss of CST inventory should cue the examinee that transition to ES-0.3 is appropriate. Examinee may believe raising cooldown rate would be appropriate in order to reach RHR conditions sooner however ES-0.2 does not provide instruction to do this.
- c. Incorrect - loss of CST inventory is an appropriate condition to require transition to ES-0.3 since more rapid cooldown rate is allowed while addressing voids in the RCS. Examinee may believe it is necessary to lower cooldown rate to conserve inventory.
- d. Correct - loss of CST inventory is an appropriate condition to require transition to ES-0.3 since more rapid cooldown rate is allowed while addressing voids in the RCS.
Thursday, October 31, 2002 06:06:14 PM 74
QUESTIONS REPORT for WBfindraft 75.WE1 lEAl.3 001iT1G2IT 1G2/RECIRCULATION/C/A 3.7/4.2/BIWB020301/CiRLM Given the following plant conditions:
- Reactor trip and SI occurred on Unit 1 due to a small break LOCA.
- Crew has transitioned from ES-1.3, "Transfer to RHR Containment Sump", to ECA-1.1, "Loss of RHR Sump Recirculation", due to the failure of both RHR sump suction valves pI J a /.b6t!*U&\
d Crew has reduced ECCS flow to 1 CCe c w
- Crew is performing Step 23 of ECA-1.1 to check makeup flow adequate and observes the following indications:
- Loop 2 RCP running
- RVLIS = 60% and slowly dropping OM-W h i c h m f the following lists the correct operator action for this condition?
A. Ensure additional makeup source to RWST has been aligned.
BY Control charging to raise makeup flow C. Place RHR shutdown cooling in service.
D. Slowly depressurize RCS to inject CLAs.
Ref: WB lesson plan 3-OT-ECAO101, obj. 1 W5 procedure ECA-1.1 Distractor analysis:
A is incorrect because this is a continuing action from earlier in the procedure, not a hold point.
B is correct per step 23 RNO because RVLIS ~ 6 3 % w/ RCP running.
C is incorrect because stem does not indicate D is incorrect because the depressurization subcooling and PZR level which are not In original bank question the following was a distractor:
"Place at least one train of ECCS pumps inservice until RVLIS > 65%.". It has been replaced because step 23 RNO also has "OR restart ECCS pumps as necessary".
Thursday, October 31,200206:06:14PM 75
QUESTIONS REPORT for WBfindraft
- 1. 001A4.03001~G1/T2Gl/BORATION/C/A4,1/3.9/BlWB020301RiRLM During a plant heatup, the control rods were withdrawn 5 steps in the BANK-SELECT position to prevent "thermal lock-up of the rods during the heatup.
Which ONE of the following would result if the control rods were NOT fully inserted using BANK-SELECT prior to withdrawing rods using MANUAL?
A. Rod upper limit stop malfunction.
BY Rod bank overlap malfunction.
C. Rod bottom lights malfunction.
D. Rod Position Indication malfunction.
Ref: WB exam bank Thursday, October 31, 2002 05:42:38 PM 1
QUESTIONS REPORT for WBfindraft 2.003 2.02 001/TUG1/TZ/Gl/RCPIC/A 3.7/3.9/N/WB02301/R/RLM p I Ttw Follow,*\
- Unit 1 is at 39% power
- Annunciator 100D, RCP Seal Leak Off Flow Hi has alarmed, due to #4 RCP.
- #1 RCP Lower is at 220°F and increasing.
S;//*u+#ad@rwr-describes the correct actions for the control room crew?
A. 1 %p the Rx and go to E-0, Rx Trip or Safety Injection.
$ . B 40to GO-5,UNIT SHUTDOWN FROM 30% REACTOR POWER TO HOT STANDBY.
CY T i p - t b # ; K?, P$0 to AOI-5, Unscheduled Removal of One RCP Below P-8 D. fo to AOI-39, Rapid Load Reduction to remove the Unit from service.
Ref: WB lesson plan 3-OT-A012400, obj. 10 WB AOI-24, section 3.2, step 2 Distractor analysis:
A is incorrect because AOI 24, section 3.2, step 2 says to trip Rx IF power >48%, otherwise, trip the RCP 6 is incorrect (same as A) and because once Rx is tripped in AOI 24, then E-0 becomes controlling procedure.
C is correct based on AOI 24, section 3.2, step 2 RNO for rising bearing temp directs tripping pump, closing seal leakoff and going to AOI-5 D is incorrect because power is less than P-8, 48% and AOI 24 directs transition to AOI- 5, which after several other actions can direct to AOI-39 or other power reduction procedures.
Thursday, October 31, 2002 05:42:39PM 2
QUESTIONS REPORT for WBfindraft 3.p4K4.04 001/T2Gl/T2GK O N T R O L TRANSFEWCIA 3.2/3.1/iWWB020301/R/RLM G : , v e
- f h J U / / O r u l ~ j:
-Unit 1 is recovering from a Main Control Room evacuation in accordance with AOI-27, Main
-Control Room lnaccesibility and control has been formally transferred from the Auxiliary
- Control Room.
u h d h e UO attempted to perform a blended makeup to the V C J M anngator 112-E, PW to Blender Flow Deviation alarmed.
Which ONE of the following describes the cause of the alarm?
A. Transfer switch for Primary Water Pumps left in Aux position j-BY Transfer switch for FCV-62-143, Blender Primary Water Flow Control Valve left in Aux position Leroawo V/US*~ +O "u'y ,
C. Transfer switch for 1-LCV-62-118 left in Aux position I-D. Transfer switch for FCV-62-144, Makeup to CCP Suction Flow Control Valve left in Aux position Ref: WB procedure AOI-27 No learning objective found Distractor analysis:
A is incorrect, switch does not exist B is correct, in Aux position at the Auxiliary Control Room, FCV-143 remains closed regardless of activities on the Main Control Board C is incorrect because level is not an input when performing a manual makeup D is incorrect because this switch does not exist Thursday, October 31,200205:42:39 PM 3
QUESTIONS REPORT for WBfindraft
- 4. 005AK3.02 001fT1GVTlC1//C/A(2.5/2.6)/B/WB02301/REL Given the following plant conditions:
- Reactor power is at 75% with a power rise in progress using control rods.
- The OAC determines that Control Bank D rod H-12 is immovable and is 14 steps below the other rods in Bank D.
- Crew is performing AOI-2, "Malfunction of Reactor Control System" Which ONE of the following describes how control rod H-12 will be realigned to control bank D and how control bank insertion limit will change following the realignment?
A. Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be higher.
B.' Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be lower C. Control rod H-12 will be realigned to Control Bank D and control bank D insertion limit will be lower.
D. Control rod H-12 will be realigned to Control Bank D and control bank D insertion limit will be higher.
The correct answer is B
- a. incorrect - the method of realignment is correct but the change in insertion limit is in the wrong direction since the bank will be inserted to match H-12 position.
- b. correct - control bank D will be inserted to match rod H-12 position and since the bank in being inserted the insertion limit for control bank D will be lower after the bank is aligned with rod H-12.
- c. incorrect - the method of realignment is incorrect and the change in insertion limit is wrong since the bank will not move the insertion limit will not change.
- d. incorrect - the method of realignment is incorrect and the change in insertion limit is wrong since the bank will not move the insertion limit will not change.
REFERENCE:
AOI-2, section 3.4 p. 23. Lesson plan 3-OT-SYS085A pp. 36-37 10CFR55.41.5, 10 RO-1 SRO - 1 Thursday, October 31, 2002 05:42:39PM 4
QUESTIONS REPORT for WBfindraft 5,005K5.03 001/T2G3K2G3/BORATION/C/A 2.9/3.1/B/WB020301/R/RLM
&er pri G*L4wW&:
=Unit 1 is in Mode 4 with #1 Reactor Coolant Pump running. ."A train RHR has JUST been placed in service when the Reactor Operator notes source range counts suddenly itweaehg.
rls,ua.
Which ONE of the following describes the correct action?
A l Commence a maxkwmboration per AOI-34 Immediate Boration to add negative reactivity.
B. Start the #2 Reactor Coolant Pum and secure the #1 Reactor Coolant Pump to ensure through mixing of the RCS volumIf .
C. Start " B Train RHR and secure " A train RHR to reestablish pre-event conditions.
D.
Ref: TP Exam Bank, no specific learning objective found Need copy of AOI 34 to verify this question.
Distractor Analysis:
A is correct because AOI provides guidance to immediatly borate when uncontrolled +reativity is inserted.
B is incorrect because swapping RCP's will not add negative reactivity to the core.
C is incorrect same as answer B.
D is incorrect because there is no guidance for a normal boration.
Thursday, October 31,2002 054240 PM 5
QUESTIONS REPORT for WBfindraft 6 . 008K1.02 001/T2G3/nG3/CCW LOADSlM 3.3/3.4/B/WB020301/LM Which ONE of the following correctly describes the uses of CCS in the Reactor Building?
A. RCP oil coolers, Seal Water Htx. and RCP thermal barriers.
B. RCP oil coolers, RCP thermal barriers and Regen Htx.
C. RCP oil coolers, RCP thermal barriers and Non-Regen Htx.
DI RCP oil coolers, RCP thermal barriers and Excess Letdown Htx.
Ref: WB Lesson Plan 3-OT-SYS070A, obj. 2&15 Dwg. 47W859-2 Distractor analysis:
See attached dwg. Note dwg says Containment, and question call it Rx bldg?
Thursday, October 31, 2002 05:42:40PM 6
QUESTIONS REPORT for WBfindraft 7.009EA2.39 00l/TlG2/TlGURCP TRIP CRITE.RJA/M 4.3/4.7/B/WB020301RRLM Which ONE of the following explains why it is preferable to leave the RCPs running during a small break LOCA if the RCS pressure RCP trip criteria on the foldout page are met but there is no SI flow?
A? To provide heat removal through the break and the S/Gs.
B. To maintain two phase mixture level above the break longer.
C. To limit single phase inventory loss out of the break.
D. To prevent boron stratification in the core.
Ref: WB Lesson Plan 3-OT-0100, obj. 3 WB Lesson Plan 3-OT-0100, pp. 14 DC Cook exam bank A is correct because the pumps will pump two phase (or steam) flow and cool by reflux in S/Gs B is incorrect because the two phase mixture will continue to exit the vessel.
C is incorrect same as B.
D is incorrect because there will be boron stratification in the core due to severe inventory depletion.
Thursday, October 31,2002 05:42:40 PM 7
QUESTIONS REPORT for WBfindraft
- 8. 013K6.01 O O l / T 2 G l ~ G l / C H A ~FAILURE/C/A L 2.7/3.I/B/WB020301/R/RLM Given the following plant conditions:
- Reactor power is 100%
- Pressurizer pressure channel I , 1-PT-68-340, has been removed from service for surveillance testing with its associated bistables tripped.
- Pressurizer pressure channel IV, 1-PT-68-322,fails law ua Which ONE of the following describes the result of these conditions?
A l Reactor trip, but NO Safety Injection Pzr PORV, 1-PCV-68-340 remains closed B. Reactor trip and Safety Injection Pzr PORV, 1-PCV-68-340 remains closed.
C. Reactor trip but NO Safety Injection Pzr PORV, 1-PCV-68-340 opens.
D. Reactor trip and Safety Injection Pzr PORV, 1-PCV-68-340opens.
Ref: WB Lesson Plan 3-OT-SYS099A 47W611-63-1 Did not find specific lesson plan on ESFAS.
Thursday, October 31,2002 05:42:41 PM 8
QUESTIONS REPORT
-)-UT F . I l t w l
- j : for WBfindraft
- 9. 01 562.2.12 001 /T2GI/T2G l/SURVEILLANCWC/A 3.0/3.4/N/WB020301/R/RLM Unit 1 has been ramping up in power in accordance with GO-4, Normal Power Operation and has stablized at 53% power to perform I-SI-92-1, NIS daily comparison.
Results of the surveillance are as follows:
Calorimetric Power - 49%
N-41 indication - 54%
N-42 indication - 52%
N-43 indication - 52%
N-44 indication - 53%
Which ONE of the following describes the required action?
,@?A? Shall obtain concurrence from the Svstem 92 Svstem Engineer - and adiust all Nls to 49%.
u7 B. Make no adjustments C. Shall obtain concurrence from the Svstem 92 System Engineer . and adjust all Nls to 51%.
D. Adjust N-41 to 51%
Ref: WB procedure I-SI-92-1 No specific learning objective This is a daily surveillance, but may want to provide precautions and limitations.
Distractor analysis:
A is correct in that it is permissible to downward adjust Nls to equal calorimetric, but N-41 requires concurrence from the engineer because its adjustment will exceed 4%
B is incorrect because T/S requires Nls to be + or - 2% or less C is incorrect because no NI will be adjusted more than 4%
D is incorrect because the other Nls will still be out more than 2%.
Thursday, October 31,2002 05:42:41 PM 9
QUESTIONS REPORT n,
- Y- tl, F o / l
- w : q : for WBfindraft 10.016K3.02 OOITT2GjTZG2IPZR LEVEL TRANSWTTWCIA 3.43.5 WB0203011RIRLM
~ ~
With Pressurizer Level Control Channel Select switch 1-XS-68-339E selected to Ll-68-339 & 335, the following SEQUENTIAL plant events occur due to a failure without operator action.
rr $6
- Charging flow inp&es to maximum
- Pressurizer level begins to rise
- Letdown isolates and heaters turn off
- Pressurizer level eventually rises to the high level reactor trip Which ONE of the following failures occurred?
A. Level channel 1-LT-68-339 failed high.
B. Level channel 1-LT-68-335failed high.
CY Level channel 1-LT-68-339 failed low.
D. Level channel 1-LT-68-335failed low.
Ref: WB lesson plan 3-OT-SYS068C, Obj. 12 Distractor analysis:
A is incorrect because charging "see" the level as high, throttles to minimum. Actual level decreases and channel LT 335 shut letdown valve 62-69 and isolates heaters. With no letdown, even an minimum charging, actual level rises to the high level trip setpoint.
8 is incorrect because LT-68-335 can't be selected for level control C is correct because failing low makes charging increase and level would initially go up rapidly due to letdown also isolating and cause a trip the Rx D is incorrect same as B Thursday, October 31, 2002 05:42:41 PM 10
QUESTIONS REPORT for WBfindraft 11.022K4.03 001/T2Gl/T2Gl/ESF ACTUATION/M 3.6/4.O/B/WB020301/M Given the following plant conditions:
- Reactor trip & Safety Injection occurred due to Large Break LOCA.
- Containment OB isolation has occurred.
- All systems responded normally.
Which ONE of the following describes the response of the Lower Compartment Coolers when OB is reset?
A. Fans in A-P-AUTO remain off.
Cooler ERCW isolation valves remain closed.
B. Fans in A-P-AUTO remain off.
Cooler ERCW isolation valves open.
CY Fans in A-P-AUTO start.
Cooler ERCW isolation valves remain closed.
D. Fans in A-P-AUTO start .
Cooler ERCW isolation valves open.
Ref: WB Lesson Plan 3-OT-SYS030C, obj. 5 WB Exam Bank Need licensee to verify this question. Lesson plan a bit vague on this point.
Thursday, October 31, 2002 05:42:42 PM 11
QUESTIONS REPORT for WBfindraft
- 12. 051AA 02 001KlG TIC - 43.5/45./B/wB0230llRlELKF0 (3.9/4.1) 7 Which ONE of the following combinations requires ONLY the turbine (NOT the reactor) to be tripped per AOI-11, " Loss of Condenser Vacuum"?
A. Generator load 700 MWe; condenser pressure 5.3 Hga.
B. Generator load 400 MWe; condenser pressure 5.0" Hga.
C.*Generator load 300 MWe; condenser pressure 4.0" Hga.
D. Generator load 200 MWe; condenser pressure 3.0 Hga.
I REF WB bank, validated in AOI-11 A. incorrect - per back pressure limit table in AOI-11 B. incorrect - per back pressure limit table in AOI-11
- c. correct
- d. incorrect - per back pressure limit table in AOI-11 Thursday, October 31,2002 05:42:42PM 12
QUESTIONS REPORT for WBfindraft
- 13. 056AK1.01 001/T1G3/TlG3/ES-O.UA 3.7/4.2/N/WB02301/TURLM CIVC* SI/lowv,6\:
-Unit 1 has experienced a Loss of Offsite Power P
-the operating crew is currently performing a cooldown, in accordance with ES-0.2, Natural Circulation Cooldown
-c rior to initiating the cooldown, two CRDM fans trip Which ONE of the following describes the maximum allowable cooldown rate?
A. <IOO"F in any one hour B. <50"F in any one hour CY <25"F in any one hour D. 4 0°F in any one hour Ref: Watts Bar Lesson Plan 3-OT-EOP0000, obj. 15 Watts Bar Lesson Plan 3-OT-EOP0000, pp. 44 of 95 Distractor analysis:
Answer A is incorrect, but is normal max cooldown with forced RCS flow Answer B is incorrect, but is correct for 3 or more CRDM fans operating (total of 4)
Answer C is correct per ES-0.2, step 7 RNO Answer D just rounds out the 4 Thursday, October 31,2002 05:42:42PM 13
QUESTIONS REPORT for WBfindraft 14.057AA2.18 001/T1G1/T1G1NITAL BUS/M 3.1/3.l/BiWB020301m/RLM Given the following:
- Unit 1 at 100% power
- Alarms received indicate a failed electrical board
- Other indications are:
nr
- W,P - ~ f s t o S PW~ ~I r-X*>-b6 (YIJIb+d.rC
- Low seal flow to RCP's due to FCV-62-89 failing open
- High charging flow due to FCV-62-93failing open Which ONE of the following identifies which electrical board that was lost?
A. 125 V DC Vital Battery Board I BY 120 VAC Vital Instrument Power Board 1-1.
C. 125 V DC Vital Battery Board II D. 120 VAC Vital Instrument Power Board 1-11.
Ref: WB Lesson Plan 3-OT-A012500, obj. 1 WB procedures AOI-25.1,.2 and 21 .1,.2 WB exam bank Distractor analysis:
See attached procedures which show loads from each of the above boards.
Thursday, October 31,2002 05:42:43PM 14
QUESTIONS REPORT a,,,= for WBfindraft
- 15. 059K4.I I 0 0 1 ~ 6 l l I T G IIFEEDWATER ISOLATIONICIA 3.1/3.31M/WB020301/M a*q After whichmeof the followina events can the feedwater isolation be reset bv feedwater isolation reset performing any other actions?
~.ooeratina the T I O A. A spray valve fails o er pressure to drop to 1725 psig. The spray valve is closed and pressure returns to 2235.
BY From 10% Rx power, the operator overfeeds a single steam generator to the High-High Level setpoint and subsequently clears the High-High Level by reducing level.
-4c. A turbine trip from 65% Rx power, causing a reactor trip. Steam dumps open to control Tavg at 557°F.
D. A high steam line flow causes a low Tavg and an SI. Main Steam isolation terminates high flow condition and allows Tavg to return to 557°F.
I 1 Ref: WB Lesson Plan 3-OT-SYS003A. obj. 13 WB dwg. 1-47W611-3-2 Distractor analysis:
Answers A and D are incorrect because the SI input must also be reset.
Answer C is incorrect because both the FWI switches AND pushbuttons must reset.
Answer B is correct because when only a Hi-Hi S/G level input is present, when it clears, only the pushbutton needs depressing to break the seal-in. See attached logic drawing.
Note: This needs to be discussed with the licensee carefully in that the logic diagram seems to conflict with a statement from the startup procedure (also attached).
Need to verify that HS 3-99A2on the dwg is the button mentioned in the lesson plan. If it is a switch, the stem will need to be changed.
Thursday, October 31,200205:42:43PM 15
QUESTIONS REPORT for WBfindraft
- 16. 061K5.01R 0 0 1 ~ G 1 ~ G 1 / / C / A / M / W B 0 2 3 0 1 / R / K O Given the following:
- The Unit 1 reactor tripped from 1 0 0 % p w r W w ~ r
- All systems responded as designed The heat transfer rate between RCS and the steam generators will .....
rlic f6+5 2ISb 5 AY i w e a 3 e as RCS temperature i n w e s and AFW flow i m s .
B. i n w s e as RCS temperature stabhizes and AFW flow i dr 1 e5 t s .
flwi r13-r C. i n w s e as AFW temperature i n m e s and AFW flow in&es.
rrws D. d & s s e as AFW temperature stabhlizes and AFW flow irpesses.
Modified from INPO bank -
- a. correct - as the temperature differential increases the heat transfer rate increases
- b. incorrect - as the temperature differential stabalizes the heat transfer rate stabalizes
- c. incorrect - as the temperature differential decreases the heat transfer rate decreases
- d. incorrect - as the temperature differential stabalizes the heat transfer rate stabalizes Lee< b d / d .;Ls ~ A sL-, or Thursday, October 31,2002 05:42:43 PM 16
QUESTIONS REPORT for WBfindraft
- 17. 072A1.01 001~2Gl/T2Gl/SFP/M3.4/3.6n\I/WB020301/M Th,e following cm&meAs t:
-Unit 1 is defueled
-Fuel movement activites in progress in the Fuel Pool
-Radiation readings on 0-RM-90-102and 103, Spent Fuel Pit Area Monitors have been steadily rising.
If the radiation levels continue to rise, which ONE of the following should occur?
A! Aux Building General Supply and Exhaust Fans and the Fuel Handling Area Exhaust Fans STOP and the ABGTS Fans START B. Aux Building General Supply and Exhaust Fans STOP and the Fuel Handling Area Exhaust Fans START C. Aux Building General Supply Fans and ABGTS Fans STOP and the Fuel Handling Area Exhaust Fans START STOP D. Aux Building General Supply Fangand the Fuel Handling Area Exhaust Fans STOP and ABGTS Fans START Ref: WB Lesson Plan 3-OT-SYS030B, Obj.13 3-OT-SYS090A, Obj.7 ARI 184-8 Distractor Analysis:
B, C, and D are incorrect because they should occur when the high radiation alarms actuate (See attached ARI-B)
A is correct because it should NOT occur (See attached ARI-B) 0 I S + m i os urrcUch.
//3, 4uu BlJ] t,t,J 5 4 f C U A w . ~ P s~ t u p Fuel / - ) d l , i s BpAhmS+ Fau S?oP
@ B & T s p h s 57r4kr 8 eJt L,.l SwI, )~&-,j F W W ~ ~ O ~ T Fuel ,&,.&/tiit c 2 h d ~ s fF4*5 S t A I f t 3 6 & t ~F k s 3709 4, $ut RtA, &~~&514fftjlF E h d h r $Fl)rp p*ar c u r l &LfG & % n b t dF h a 9 4 t T t$@ra F- S A P ~
D. dwy&l& &d SupPI9 <kXAclua7 Fad GurI N&t.rd,$ &&A&,$+ 57oP h e 0 7 5 FA*@ STpf Thursday, October 31, 2002 0 5 4 2 4 4 PM 17
QUESTIONS REPORT for WBfindraft 18.073A2.O1001/T2GUT2GUWASTE RELEASEA4 3.1/3.5/N/WB020301/LM Given the following:
-Unit 1 is at 100% power
-A liquid waste release is in progress 4-
-Annuciator 18 -A, WDS RELEASE LINE 0-RM-122 LIQ RAD HI alarms.
-The reading o RM-90-122 has decreased to less than background Which ONE of the following describes the W r e q u i r e d actions by the control room operators? ikrneL A. Have the detector assembly cleaned.
B. Notify RADCON to take radiation readings -*
in the detector area.
&Qcd - 17 CY Verify liquid rad waste release vavl- shut.
Q-D. Initiate a Maintenance Work Order to repair RM-90-122.
Ref: WB lesson plan 3-OT-SYS090A, obj. 7 ARI 181-A Distractor analysis:
A is incorrect because there is no guidance to clean the detector although low readings could be the result of fouling.
B is incorrect due to no guidance to confirm that areas readings are suddenly less than typical background D is correct based on the guidance in the ARI and the philosophy to secure releases to the environment when process monitors fail.
D is incorrect as an initial action although ultimately the detector will need repair at a later time.
- Need to verify term that WB uses for Maintenance Work Order.
Thursday, October 31,2002 0542:44 PM 18
QUESTIONS REPORT for WBfindraft 19.074EA2.01001fI'IGlfI'l 'SUBCOOLING/C/AIB/WB023Ol/R/KFO~RM Given the following:
- The Unit has tripped from 100% power with a LOCA in progress
- Pzr pressure is 900 psig
- RCPs are tripped
- Core Exit thermocouples indicate 720 degrees F
- RVLlS indicates 36%
- Thotfor all loops range between 512 O F and 525 O F Which of the following describes the conditions existing in the core as applicable to the EOPs?
A. Subcooled conditions, which present no challenge to the fuel matrix and fuel cladding as long as the hot leg temperatures remain below saturated conditions.
B. Saturated conditions, which does not present a challenge to the fuel matrix and fuel cladding as long as the cold leg temperatures remain at saturated conditions.
C. Saturated conditions, which present a potential challenge to the fuel matrix and fuel cladding.
DI Super heated conditions, which present a imminent challenge to the fuel matrix and fuel cladding.
WB bank - validated on steam tables
- a. incorrect - not saturated conditions
- b. incorrect - is super heated but does challenge the fuel matrix and fuel cladding
- c. incorrect - not saturated conditions
- d. correct - superheated conditions that present a challenge to fuel matrix and cladding Thursday, October 31,200205:4244PM 19
QUESTIONS REPORT for WBfindraft
- 20. 078G2.4.11001/T2G3/T2G3/LOSS OF AITUCIA 3.4/3.6/B/WB020301/M Given the following conditions:
- Plant in Mode 5.
- Total Loss of Control Air has occurred.
- Train " A RHR in Shutdown Cooling mode.
- The OAC reports that Pressurizer level is 92% and slowly'rising.
- CCS is inservice with flow to the RCP thermal barriers.
Which ONE of the following actions should be taken to control Pressurizer level per AOI-10, "Loss of Control Air"?
A. Locally isolate charging and letdown and place excess letdown in service.
B. Stop CCPs until PZR level is less than 70% then cycle a CCP on and off to maintain PZR level between 65 and 70%.
C. Locally Isolate charging until PZR level is less than 70% then adjust then locally operate 1-FCV-62-93 to control charging flow.
DI Stop CCPs until PZR level is less than 70% then start a CCP to establish seal injection flow.
Ref: WB lesson Plan 3-OT-AOI1000, obj 7 AOI-10 Distractor Analysis:
A is incorrect, the procedure does not direct isolation of charging, but stopping.
B is incorrect, no procedural guidance to cycle charging between 65% and 70 %O C is incorrect, no procedural guidance to locally operatE FCV D is correct per AOI IO, section 3,4 Thursday, October 31, 2002 05:42:45PM 20
QUESTIONS REPORT for WBfindraft 2 1. 086G2.4.25 O O l / " ? . G ~ G 2 / P R O C E DTRANSITIONM
~ 2.9/3.4/B/WB020301/FURLM Given the following:
- The Unit is at 100% RTP and at steady state conditions.
- A fire is detected in the Auxiliary Building.
- The SM has determined the fire has the potential to affect equipment necessary to achievehaintain safe shutdown.
- The US has transitioned to AOI-30.2, Fire Safe Shutdown.
- A Spurious Safety Injection occurs.
Which ONE of the following identifies the required procedure transition for the given conditions?
A. Perform AOI-30.1, Plant Fires, concurrently with AOI-30.2, Fire Safe Shutdown.
B. Perform AOI-30.2, Fire Safe Shutdown, while referring to ES-1.1 for SI termination actions.
C. Perform E-0, Reactor Trip or Safety Injection, then AOI-30.2, Fire Safe Shutdown, when SI termination criteria is met.
D I Perform AOI-30.2, Fire Safe Shutdown, while referring to other instructions as directed by AOI-30.2 Ref. WB lesson plan 3-OT-A013000 AOI 30.2 Distractor analysis:
A is incorrect because AOI-30.1 is a non-Appendix R fire procedure and the SM has determined it to be an Appendix R fire.
E is incorrect because AOI 30.2 takes precedence over EOP's.
C is incorrect same as B D is correct because it is permissible to run AOI-30.2 concurrently with normal plant instructions.
Thursday, October 31, 2002 05:42:45 PM 21
QUESTIONS REPORT
&ver+A, r&w+: for WBfindraft
- 22. 103A2.03 001/T2G3/T2G2/"ASE B/M 3.5/3.8/NIWB020301/M I - Unit 1 has Safety Injected
~~
Phase A isolation has occurred
- The crew is performing step 11 of E-0,Rx p i p or Safety lnjectim when the UO notes that
- Containment Pressure iS 3.2 psig and Phase B has not actuated.
m s m k or; 'OPW Which ONE of the following describes the action@) required?
A. Manually actuate either Phase B manual'handswitches and manually start the Containment Spray pumps.
B. Manually actuate both Train A and B Phase B manual handswitches and manually start the Containment Spray pumps.
C. Manually actuate either Phase B manual handswitches and manually shut the MSIV's and vw2 bypasses.
I Manuallv actuate both Train A and B Phase B manual handswitches and manually shut the MSIV's and bypasses.
Ref: WB lesson plan 3-OT-SYS088A, obi. 9 WB dwg. 1-47W1611-88-1 Distractor analysis:
A and C are incorrect because Phase B manual actuation required BOTH switches actuated simultaineously.
B is incorrect because spray pumps start as a result of manual actuation (see logic dwg)
D is correct because both switches are actuated and MSIV's only isolate as a result of input from Containment Pressure instruments.
Thursday, October 31,2002 05:42:45 PM 22
QUESTIONS REPORT for WBfindraft
- 23. WE02EA1.2 001/TlG2/TlGl//C/A (3,4/4,0)/B/%'B02301/%3L Given the following conditions:
- Plant is recovering from a reactor trip and safety injection due to a faulted SG.
- Faulted SG has completely blown down and as been isolated in accordance with the appropriate EOP.
- RCS pressure is 1900 psig andrising.
When terminating safety injection which ONE of the following identifies actions that result in a drop in the ECCS flow to the RCS?
- 1) Stopping the 1st charging pump.
- 2) Stopping both safety injection pumps.
- 3) Establishing normal charging and isolating BIT.
- 4) Stopping RHR pumps.
A l 1 and 3.
B. 3and4.
C. 1 and 2.
D. 2and4.
The correct answer is A.
- a. Correct - both these actions would result in reducing flow to the core since at this pressure only CCPs would inject.
- b. Incorrect - 3 would reduce flow, however RHR pumps are not injecting at this pressure.
- c. Incorrect - 1 would reduce flow, however the SI pumps are not injecting at this pressure.
- d. Incorrect - neither would reduce flow at this pressure.
Reference:
SYS063A; EOP0000.18 WA E02 EK1.l [3.2/3.8]
Thursday, October 31,200205:42:46PM 23
QUESTIONS REPORT for WBfindraft
- 24. WE08G2.4.18 O O l ~ l G l ~ l G l m T S l3.4/4.2/B/WB020301/M M
Step 1 of FR-P.1, "Pressurized Thermal Shock", has the operator check that RCS pressure is greater than 150 psig.
This step is based on:
A? Preventing implementation of actions in FR-P.l if a large break LOCA has occurred.
B. Ensuring adequate low head safety injection cooling prior to isolating CLAs.
C. Preventing core exit temperatures from exceeding the required temperature to place RHR inservice.
D. Ensuring RHR system is in service to provide adequate mixing in the cold leg downcomer region.
Ref: WE3 Lesson Plan 3-01-FRP0001, obj. 9 WB exam bank Answer A is correct, see attached lesson plan.
Thursday, October 31,2002 05:42:46 PM 24
QUESTIONS REPORT for WBfindraft
- 25. WE13EK3.2 001IT1G3n1G3/OVERPRESSuRE/cIA2.9/3.3B/WB020301fRJRLM During the performance of FR-H.2, "Steam Generator Overpressure", operators are directed to verify T-hot less than 545°F if initial attempts to depressurize the SG(s) is unsuccessful.
Which ONE of the following is bases for this verification?
A. Ensures that the SG level instruments (WR) will be within the required accuracy during the depressurization.
C. Ensures RCS saturation pressure is below shutoff head of SIPS in the event SGs become a heat SOURCE instead of a heat SINK.
DI Ensures excessive heat transfer from the RCS is NOT the cause for the SG overpressure.
Ref: WB Lesson Plan 3-OT-FRH0001 obj 13 WB Lesson Plan 3-OT-FRH0001 pp 44 of 56 Source WB exam bank Distractor analysis:
Answer D is correct based on lesson plan page 44 Thursday, October 31.2002 05:4246 PM 25
QUESTIONS REPORT for WBfindraft
- 1. 003A2.02S001/T2Gl/T2GIIRCP/C/A 3.7/3.9M/WB023OI/S/RL.M U n i t 1 Reactor Dower has been reduced to remove LOOD3 RCP in accordance with AOI-5.
Unscheduled Removal of One RCP Below P-8.
Which ONE of the following describes the initial plant response when the RCP is tripped and action required.
)CIS@
A. Tavg in loop 3 inpxrS?s to Thot of the other 3 loops and MFW flow must be reduced.
44 BY Tavg in loop 3 d d l t t o less than Tcold of the other 3 loops and MFW flow must be reduced.
D. Tavg in loop 3 de
- C. Tavg in loop 3 i s e s to Thot of the other 3 loops and loop 3 PZR spray valve must be closed.
valve must be closed.
ases to less than Tcold of the other 3 loops and loop 3 PZR spray Ref: WB Lesson Plan 3-OT-A010500, obj. 6 WB AOI-5, pp. 10 A & C are incorrect because loop 3 Tavg decreases (see quote from AOI 5 below)
D is incorrect because loop 3 has no spray valve B is correct based on based on quote from AOI 5 below and step 1, section 3.3 of 01 5.
"When a RCP is removed from service, a reverse flow occurs in the affected loop. The result is a significant reduction in the RCS hot leg temperature and reduction in steam generation from the affected SG. Previous experience in losing a RCP "at power" at WBN showed that Tavg in the affected loop went below Tcold in the active loops until feedwater was isolated and a thermal equilibrium was reached. In this instance, Tavg for the affected loop went below the minimum temperature for criticality. Tavg returned to greater than 551°F in approximately 6 minutes following isolation of feedwater to the idle S/G. "
Thursday, October 31,200205:43:39 PM 1
QUESTIONS REPORT for WBfindraft
- 2. 005AK2.02 001/T 1Gl/TlG l/DISCONNECT/C/A 2.5/2.6/N/wB02030 l/S/RLM Unit 1 was at 25% power and ramping up when the RO noticed that one of the Bank C control rods is 13 steps below the other rods in Bank C which at 215 steps.
At 0900, immediately after discovery, power assension was halted.
At 0945, the rod was determined to have an electrical problem which was repaired.
At 1015, the management staff has concurred with realignment of the misaligned rod in accordance with AOI-2, Malfunction of the Reactor Control System.
Which ONE of the following outlines the method of realigment?
A. Record information from Bank Overlap Unit, step counters, and P/A converter. Disconnect lift coil for the affected rod, reset step counters, select Bank C and insert Bank C control rods.
B. Disconnect lift coil of the affected rod, select Bank C and insert Bank C.
CY Record information from Bank Overlap Unit, step counters, and P/A converter. Disconnect all lift coils in Bank C except the affected rod, reset step counters, select Bank C and withdraw affected control rod.
D. Disconnect all lift coils in Bank C except the affected rod, select Bank C and withdraw the affected rod.
Ref: WB lesson plan 3-OT-AOI-0200, Obj. 8 WB procedure AOI-2 Distractor analysis:
A is incorrect the procedure for aligning a rod misaligned for >I hr (ie. move the rod to the bank, not the bank to the rod)
B is incorrect same as A, also missing some steps. However, this is the method at step 13 for recovery prior to repair IF it were a Bank D rod.
C is correct per AOI 2 steps 33 through 37 D is incorrect because information from BOU, P/A and step counters must be recorded prior to realignment.
43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
Thursday, October 31,200205:43:40PM 2
QUESTIONS REPORT for WBfindraft 3.005K5.03S 001/TZG3/T22G3/EMERGENCY BORATION/C/A 2.9/3.1/M/WB020301/S/RLM Given the following plant conditions:
- The unit is in MODE 6, refuelindactivities in progress inside
- containment. I
_.. " A train RHR in service for core cooling and letdown to CVCS.
- Chemistry reports RCS boron concentration is 1925 ppm.
Which ONE of the following describes the correct actions and the reason?
A. Isolate Refueling Cavity from the Spent Fuel Pit by closing the transfer tube wafer valve to prevent dilution of the Spent Fuel Pit.
B. Place train"B" RHR in service, remove " Atrain to isolate dilution paths connected to " Atrain RHR.
raise CY Initiate boration using AOI-34, "Immediate Boration" to kwease boron concentration to minimum required limits.
D. Evacuate containment and verify contaiment integrity intact to ensure Technical Specfication 3.9.4, Contaiment Penetrations is met.
Ref: WB Exam bank, modified to add reason for SRO level question.
Need references GO-6, AOI-34 Distractor analysis:
A is incorrect in that closing the transfer tube valve will not help the regain SDM.
B is incorrect because swapping trains will not increase SDM C is correct because AOI provides guidance immediately increase c b = 2100 ppm.
D is incorrect due to no procedural guidance to do so and it does not increase SDM.
43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
Thursday, October 31,2002054341 PM 3
QUESTIONS REPORT for WBfindraft 4.007EA 1.0300 1/T1Gm1G2//C/A/B/WB0230l/S/KFO An RCS cooldown is in progress per ES-0.2, "Natural Circulation Cooldown". The plant is being depressurized using auxiliary spray. As pressure drops through 1300 psig, a rapid rise in pressurizer level is observed. Charging and Letdown are in manual and are matched.
ONE Which%f the following describes the expected operator actions and the reason?
A. Isolate charging flow and raise the cooldown rate to 50 degrees F/hr to help shrink RCS inventory.
B. Isolate charging flow and place additional letdown orfice(s) in service to remove the excess RCS inventory.
C. Isolate the Cold Leg Acculmulators to prevent further introduction of nitrogen to the RCS.
D? Isolate the auxiliary spray and energize pressurizer B/U heaters to collapse the bubble in the Rx head.
I W 0 Bank -
- a. incorrect - increasing the cooldown rate will further decrease RCS pressure
- b. incorrect - this will decrease the inventory but not address the pressure drop
- c. incorrect - isolating the cold leg accumulators will not effect the level or ppressure at this time
- d. correct - stopping the aux spray flow will stop the depressurization and truning the B/U htrs on will help recover the pressure.
43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
Thursday, October 31, 2002 05:43:41PM 4
QUESTIONS REPORT for WBfindraft
- 5. 009EA2.34 00l/TlGUTlGZ/PROCEDU~/C/A(3.6 /4.2)/BNBO23Ol/S/KFO Given the following conditions on Unit 1:
- Reactor trip and safety injectio h ve occurred
- c, MSlVs have just closed due to ontalnment pressure,?(, pdr&m,'~, E-0 S ~ ID P
- RCS pressure is 1700 psig and stable
- CETCs indicate 570 F
- Total AFW flow is 700 gpm
- PZR level is M%
2s Based on these known conditions, the operators should .........
BP Terminate Safety Injection.
@ a 69 6 r O f VC. .verify"all RCPs mwbpped.
Ref: bank from Byron '00, validated for WB in E-0, ES-1.1
- a. incorrect - Phase B actuated if containment pressure >2.8psig,
- b. correct SI termination criteria met
- d. incorrect - if required the containment spray pumps would have auto started, containment presure only high enough to close MSlVs Thursday, October 31, 2002 054341 PM 5
QUESTIONS REPORT for WBfindraft 6.028AA2.12 001/TlG3/TlG3PZR LEVEL/C/A 3.3/3.4/N/WB020301/S/XLM Given the following:
-Unit 1 is at 100% powerd p; I -LIE-CB-333
-Pressurizer level is dep&nTslowly 2 3 ? ?. ,
-The output of the Pressuriz~Jp@&p troller IS in
-The Charging Flow Controller% inc sing hsC1 .
H,Q 2 -93 A
-Charging flow dec@ing.d**to;*$
-Annuciator 92C, PZR LEVEL LO-HTRS OFF & LTDN CLOSED is illuminated Which ONE of the following is the cause of the Pressurizer level decrease?
I-A. FCV 93, charging flow control valve has developed a diaphrarn leak.
Is i-U+b1-93?& rpuf B.Y The Charging Flow Controlleris failing high.
I-LIO- b.6339 C. The PZR Level Controllefis failing high.
r D. The Ta input to the PZR is failing high.
Ref: Watts Bar lesson plan 3-OT-SYS068C, obj. 15 Watts Bar lesson plan 3-OT-SYS062A Distractor analysis:
Answer A is incorrect because FCV-62-93fails open, hence a diaphram leak would tend to make the valve open (higher flow). Note: If the leak is small enough, the flow controller would handle it with increased output, but flow would stay on program until the controller rnaxed out and then flow would increase.
Answer B is correct because the Charging Flow Controller failing, in this case high, causes FCV-62-93 to close thus decreasing flow and hence PZR level.
Answer C is incorrect because the PZR Level Contoller failing high would call for more charging flow thus causing Charging flow and PZR level to increase.
Answer D is incorrect because the auctioneeried high controlling Tav would call for a level increase until it maxed out the program. This would cause charging flow to either increase or remain the same.
Thursday, October 31, 2002 05:43:42 PM 6
QUESTIONS REPORT for WBfindraft
- 7. 03_8EA1.04 001/T1G m J GUPRESSURE REDUCTION/C/A 4.5/4.8fl\l/WB02030 l/S/RLM G I W P .tk be I J B u ~ ~ '
- Unit 1 was at 100% and experienced a failed opet?PORV for which the block valve only partially closed.
- After the actions of*-0, Reactor Trip or Safety Injection, it has been SG is ruptured.
- The operating crew has isolated the ruptured SG and transitioned tofcECA-3.1, SGTR and LOCA - Subcooled Recovery ..
- RCS pressuresi- 1750 psig and ni &%%&
- Pressurizer level is 100%
a3- SRCS te erature is 530" F r&*w r . eawn g e level is & and irlcrecrsi&
S G Wa R
- All automafic systems have functioned properly and RCP's are running Which ONE of the following describes the actions required to stabilize SG break flow?
A. Cooldown by dumping steam from the non-ruptured SG's followed by depressurization of the RCS with Pressurizer Spray Valves.
B. Cooldown with RHR followed by depressurization of the RCS with Pressurizer Spray valves.
CY Cooldown by dumping steam from the non-rupture SG's followed b depressurization of the RCS a 2 b r b 9 u a L $ r c m o v d 04 ccs prrnpa, D. Cooldown with RHR followed by depressurization of the RCS 0 f- E C C S PLL"P3 Ref: WB EOP E-3,Stm Gen Tube Rupture, pg 16 and 17 Distractor analysis:
Answer A is incorrect because PZR spray is not effective in a PZR with level at 100%
Answer B is incorrect because RCS pressure is too high for RHR and spray ineffective Answer C is correct because PORV's are by procedure the next preferred depressurization method after PZR sprays and the SG's are the preferred heat removal method Answer D is incorrect because RCS pressure is too high for RHR ECA-3.J d # b~d & ~ ~ U I& Uf~c$~wj~.GfL d ,j P04v;Of $Pys ;4 P?R &ud i s 229"/0 Thursday, October 31, 2002 05:43:42 PM 7
QUESTIONS REPORT for WBfindraft 8.051AA2.02S001/T1G1/T1GlNACWMICIA 3.9/4.1/B/WB020301/S/RLM Given the following:
- Condenser pressure rising; operators dropping turbine load in attempt to maintain vacuum.
D Condenser backpressure is 5. H a.
Main turbine load is 43%.
Which ONE of the following would be the FIRST to automatically occur or be procedurally required if condenser pressure continues to rise?
A. Auto main turbine trip on low vacuum.
B. Manual reactor trip.
C. Loss of steam dump capability.
DI Manual turbine trip.
Ref: WB Lesson Plan 3-OT-AOlll00, obj. 2 AOI-11, Sec. 2.3; Sec. 3.0 steps 6-8 WB Exam bank Distractor analysis:
A is incorrect because auto trip does not occur until vacuum >7.0 Hga B is incorrect because the procedure directs turbine trip first.
C is incorrect because are capable unit1 vacuum reaches >6.5Hga D is correct per guidance in AOI 11 Thursday, October 31,2002 05:43:42PM
QUESTIONS REPORT for WBfindraft 9,056AKl.OlS 001/TlG3/TlG3/ES-0.2/C/A 3.7/4.2/NAVB02301/SIM 6' ( U E Y THt ~o/~owlvq:
-Unit 1 has experienced a Loss of Offsite Power
-The operating crew is currently performing a cooldown, in accordance with ES-0.2, Natural Circulation Cooldown
-Prior to initiating the cooldown, two CRDM fans trip Which ONE of the following describe the implications of the loss of the two CRDM fans?
r AY The time to achieve RHR conditions is i n u d , requiring additional CST makeup.
B. Steam voiding in the RCS vessel will occur unless ERCW is supplied to the AFW suctions.
C. Loss of RCS subcooling will occur as the RCS is being depressuized.
D. At least one of the tripped fans must be restarted (total of 3 running) prior to commencing cooldown.
Ref: WB Lesson Plan 3-OT-EOP0000, obj. 15 WB Lesson Plan 3-OT-EOP0000 pp. 41 & 42 Distractor analysis:
A is correct because with less than three CRDM's, the max cooldown rate is reduced from 50"F/hr to 25"F/hr which challenges the CST makeup capability (see basis for step in lesson Plan)
B is incorrect because voiding in the vessel is related to depressurization which in not related to the choice of filling the CST from ERCW.
C is incorrect because the procedure contols subcooling margin during depressurization D is incorrect because the procedure does not require 3 or more CRDM fans prior to start of cooldown.
(5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.
Thursday, October 31,200205:43:43PM 9
QUESTIONS REPORT for WBfindraft
- 10. 057AA2.19OOl/TlGl/TlGlNITAL BUS/C/A 4.0/4.3/NIWB020301/SlRLM I Unit 1 is shuttina down due to a failure of 120 VAC Vital Instrument Power Board 1-1. When Rxj power is approimately 10%. the unit trips.
Which ONE of the following decribes the reason for the trip?
A. SRM High Flux Trip BY IRM High Flux Trip C. Low Setpoint of PRM High Flux Trip D. High Setpoint of PRM High Flux Trip WB lesson plan 3-OT-A012500, Obj. 1 and 2 WB procedure AOI-25, pp. 8 Distractor analysis:
A is incorrect because the plant is above P-6 B is correct because 1 of 2 IRMs high flux trip is in when the plant goes below P-10 which reinstates the IRM High Flux Trip function.
C is incorrect because coincidence for PRM trip not met D is incorrect because coincidence for PRM trip not met and power less than trip setpoint.
Thursday, October 31,200205:43:43PM 10
QUESTIONS REPORT for WBfindraft 11.060AA2.04 OOl/TlG2/TlG2/GAS TANK LEAWMIBNB02301/S/KFO Given the following plant condtions:
- Gas Decay Tank release in progress with ABGTS running for dilution air flow
- A leak occurs on the waste gas compressor which results in a gas release to the Auxiliary building
- 0-RE-90-101, Auxiliary Building Vent Monitor, is in alarm
- Assume no operator action W E WhicWof the following indicates the effect this leak will have on the plant?
A. Gas Decay Tank release will be terminated; ABGTS will be stopped B. Gas Decay Tank release will be terminated; ABGTS will continue to run C. Gas Decay Tank release will continue; ABGTS will be stopped DY Gas Decay Tank release will continue: ABGTS will continue to run R E F WB ' 01 - verbatim question SRO Only (43.4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.
Thursday, October 31,20020543:43 PM 11
QUESTIONS REPORT for WBfindraft 12.073A2.01S OOI/T2GZfIZG2/PURGUC/A 3.1/3.5/N/WB020301/S/RLM The following conditions exist for Unit 1:
-Mode 6
-Fuel movement in Containment in progress
-Contaiment Purge operating
-Annunciator 174-D, CNTMT PURGE EXH 1-RM-I30/131INSTR MALF alarmed Which ONE of the following describes the required actions by the control room operators?
A. Restore the rad monitor to service within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend fuel movement.
BY lmmediatley shutdown containment purge when the annunciator alarms.
C. Verify that containment purge automatically tripped.
D. Suspend fuel movement until the rad monitor is restored to service.
Ref: WB lesson plan OT-SYSOSOA, obj 7 ARI 174-D TS 3.6.6 Distractor analysis:
A is incorrect because neither the TS nor the ARI direct stopping fuel movement.
B is correct because the ARI directs shutting down purge if it is running C purge does not automatically trip on RM 130/131 low flow (instrument count rate will decrease).
D is incorrect because again there is no guidance in TS or the ARI to suspend movement and there are specific actions required within specified timeframes (ie secure purge).
Thursday, October 31,2002 05:43:44PM 12
.)
QUESTIONS REPORT for WBfindraft
- 13. 076AA2.02S 001/TI G1/T1Gl/lC/AINA?rB0230l/S/KFO/RLM I
Given the following:
- Unit is at 100%
- Chem - Lab reported Reactor Coolant Dose Equivalent Iodine-I31 Specific Activity is -6.3 p C i / g m . p Based on these conditions, which ONE of the following operator actions are now required?
- Reference provided
&A InrvcLbrP A. PlaceAl CVCSYdemins in service at maximum flow rate and continue power operations.
UB. Monitor Dose Equivalent 1-131 within acceptable region of Appendix A once per 4 hr and reduce power as necessary to maintain within acceptable region of Appendix A.
C. Place unit in Mode 3 at less than or equal to 500 O F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
M D? Continue power operations. wt>Auidd&u/ f c s ~ ~ ~ l ' ~
WB Bank - validated per AOI-28 and lesson plan 3-OT-A0112800
- a. incorrect - CVCS demins not required
- b. incorrect - c. incorrect - monitoring not requiredThis action causes the plant to be unnecessarily reduce power.
- c. This action causes the plant to be unnecessarily reduce power.
- d. correct - The Reactor Coolant Dose Equivalent Iodine-131 Specific Activity per Appendix A of AOI 28 is less than the limit of 10 pCilgm. No information is given about Dose Equivalent Iodine-131. Therefore, no action is required.
Note: This procedure, AOI 28, poorly distinguishes between the Specific Activity Spec and the Dose Equivalent Iodine Spec.
Thursday, October 31,200205:43:44PM 13
QUESTIONS REPORT for WBfindraft 14.086G2.4.25S001/T.G2/nG2/APPENDIX R FIRWC/A2.9/3.4/N/WB020301/S/RLM G l e t i u t*& C U L L O W ~ L 7:
Unit 1 is currently at 100 /D A fire has been reported in the Auxiliary Building The Turbine Driven AFW pump is disassembled for maintenance All other equipment is functional In accordance with AOI 30.2, Fire Safe Shutdown procedure, which ONE of the following functions, if lost, would prevent meeting the Steam Generator Inventory Control Function?
A. 1A Motor Driven Auxiliary Feedwater Pump B. One channel of Steam Generator Level Control C? Suction from the Condensate Storage Tank D. Suction flow from one train of Essential Raw Cooling Water Ref: WB lesson plan 3-OT-AOI 3000, obj 12 AOI-30.2 Distractor Analysis:
According to the attached logic diagram, a loss of suction from the CST will prevent fulfillment of the SG Inventory Control Function. (see attached) This is not intuitive since one train of
- should suffice for supplying flow to AFW motor driven.-
ERCW Need to provide AOI 3Q.2 as reference
--y 0 7 ' f * , a Y r M Provi
?
Thursday, October 31,2002 05:43:44PM 14
QUESTIONS REPORT
&,yew T H E (CULuWlfi~: for WBfindraft
- 15. 103A2.03S 001/T2G3/TZG2PHASE B/M 3.5/3.X/N/WB020301/S/RLM
-Unit 1 has Safety Injected
-Phase A actuated
-Phase B just actuated
-A review of the Main Control Board indicates that the Air Return Fans are not running Which ONE of the following describes the correct action and reason?
A. Immediately start the Air Return Fans because they should have started on a Phase B Isolation Signal.
BY Start Air Return fans when 10 minutes have elapsed to prevent Hydrogen gas pockets from forming in Containment.
C. Immediately start the Air Return Fans to prevent Hydrogen gas pockets from forming in Containment.
D. Start Air Return fans when 10 minutes have elapsed to prevent overloading safety related electrical busses during initial transient.
WB lesson plan 3-OT-SYS030D, obj 3 WB procedure E-0, step 11, RNO Distractor analysis:
A and C are incorrect because E-0 requires waiting 10 min.
D is incorrect because there are no reference in FSAR, or lesson plans to electrical loading issues.
B is correct based on guidance in E-0 and secondary purpose of system Thursday, October 31, 2002 05:43:45PM 15
QUESTIONS REPORT for WBfindraft
- 16. (32.1.14 001/T3/T3/NOTIFICATION/M 2.5/3.3/NIWB020301/S/RLM is r r p r r d k Which ONE of the followingawfsrbe notified when a Temporary Alteration installation has been completed orreturned to normal?
A. Unit Operator aPYcJrors 5 k , d l & J B. ht+www+
CY Shift Manager D. Unit Manager Ref: WB procedure SPP-9.5, Temporary Alterations No lesson pian provided Distractor analysis:
Seeattached Thursday, October 31,2002054345 PM 16
QUESTIONS REPORT for WBfindraft
- 17. (32.2.29OOl/T3/T3/FUEL HANDLINGN 1.6/3.8/B/WB020301/S/RLM The following plant condition exists:
You are SRO for refueling into the reactor vessel when the US informs you that one source range channel has failed its surveillance.
Which ONE of the following is the required action?
A! Suspend core alterations until the failed source range channel is operable.
B. Continue fuel reload as one channel is operable.
C. Continue fuel reload for = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in any 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period until two source range channels operable.
D. Suspend core alterations until boron sampling has been completed.
Ref: San Onofre Bank 2000 WB Tech Specs, section 3.9.3 B and C are incorrect because they violate TS D is incorrect because it is part of the actions for loss of two source ranges Don't have GO-7 Refueling procedure Thursday, October 31,200205:43:45PM 17
QUESTIONS REPORT for WBfindraft
- 18. G2.2.8 OOl/T3/T3/50.59/C/A 1.8/3.3/B/WB020301/SIRLM -
Changes to which ONE of the following will require a 10CFR50.59 review?
A. Change to the Physical Security Plan that requires moving a section of the perimeter fence.
B. Revision to the Radiological Emergency Plan that changes the designated assembly areas for accountability.
CY System modification that adds a full flow recirculation test line to the discharge of the Safety Injection pumps.
D. Changes to the Nuclear Quality Assurance Plan.
Reference:
WB procedure SPP-9.4 WB failed to provide SSP-9.4, will need if distractor analysis to be done.
(43.3) Facility licensee procedures required to obtain authority for design and operating changes in the facility Thursday, October 31,2002 05:43:46 PM 18
QUESTIONS REPORT for WBfindraft
- 19. G2.3.8 001/"T3/"T3/WASTEGAS RELEASE/M 2.3/3.2NiWB020301/S/RLM a
Unit 1 is preparing to release Waste Gas Decay Tank E, which was remove from service 32 days ago, in accordance with Sol-77.02. WASTE GAS DISPOSAL SYSTEM.
Which ONE of the following decribes the minimum approval authority for the release?
1 OS6WmR A. UNIT WPEWSWi and CHEMISTRY DUTY MANAGER I 0PPP4rolt B. SHIFT MANAGER and UNIT S W E W B # l CY SRO and CHEMISTRY DUTY MANAGER D. SHIFT MANAGER and another SRO Ref: WB procedure 501-77.02 No learning objective found Distractor analysis:
A is incorrect because the Unit Supervisor is not listed in the procedure as an approval authority.
B and D are incorrect because the Chemistry Duty Manager must approve release of tanks less than 60 days old.
C is correct per attached procedure Thursday, October 31, 2002 05:43:46PM 19
QUESTIONS REPORT for WBfindraft
- 20. WE02EK1.2 001/TlG2/TlGl/SI TERMINATIONM 3.4/3.9/B/WB020301/S/M Given the following conditions:
- Main steam line break has occurred outside containment, resulting in a reactor tripkafety injection (SI).
- MSlV closure stopped the steam release.
- SI termination criteria was met and the crew is currently terminating the SI per ES-1.I, "SI Termination."
Which ONE of the following combinations of parameters would require an immediate reinitiation of safety injection?
Maximum RCS RCS PZR CNTMT Press Subcooling Pressure Level A. 1 psig 75°F Stable 18%
B. 2 psig 72°F dropping 20%
C. 3 psig 87°F dropping 34%
DI 4 psig 60°F Stable 24%
Ref: WB lesson plan 3-OT-EOP-0000,Obj. 8 Distractor analysis:
- a. Incorrect - with containment conditions below the adverse setpoint of 2.8 psig the reinitiation criteria is PZR level 4 5 % and subcooling < 65°F.
- b. Incorrect - both PZR level and subcooling are above the minimum for conditions below adverse setpoints.
- c. Incorrect - both PZR level and RCS subcooling are above the minimum for adverse containment conditions.
- d. Correct - with adverse containment conditions (>2.8psig) the reinitiation criteria is PZR level <33% or RCS subcooling ~ 8 5 ° F .
Thursday, October 31,200205:43:46PM 20
QUESTIONS REPORT for WBfindraft 2 1.WE04EA2.1 001/TlG2fIlG1/PROCEDURE TRANSITION/C/A 3.4/4.3/B020301/S/RLM grvew TH6 F O i L O W I ~
f dmpp)y~
Unit 1 was at 100% and was manually Safety Injected due to dweasTi pressurizer level.
Plant status is:
-The Operating Crew is performing E-0, Reactor Trip or Safety Injection
- All automatic actions occurred
-RCS pressure is stable at 1600 psig, c cyr 5 6 0 0 , ~
-Pressuizer level is slowly risinp&l;/%
-Steam Generator pressures%* evels are
-Steam Generator were tre ding no mal prior to isolation and Condenser exhaust rad monitor is normal % ~ OW& 1 1
~ wRe Y M u ~ i f v r ~
-Containment conditions are pre-event
-Area monitor recorder 1-RR-90-1 and 0-RR-90-12A have significantly upscaled
-Vent monitor recorder 0-RR-90-101 was trending up prior to isolation Which ONE of the following describes the correct procedure transition?
A.
B. Go to E-I, Loss of Reactor or Secondary Coolant.
C: Go to ECA-1.2, LOCA Outside Containment.
D. Go to ES-0.0, Rediagnosis.
Ref: WB Lesson Plan 3-OT-EOP0000, obj. 1 WB Lesson Plan 3-OT-ECA0101, obj. 8 Distractor analysis:
A is incorrect because Step 29 directs transition to ECA-1.2 due to abnormal Aux Bldg radiation levels.
B is incorrect because Containment conditions are pre-event.
C is correct because Step 29 directs transition to ECA-1.2 due to abnormal Aux Bldg radiation levels.
D is incorrect because it only applies after transition from E-0.
Thursday, October 31,2002 05:43:47 PM 21
. I QUESTIONS REPORT for WBfindraft
- 22. WE06EA2.1001/T1G1/T1GllFR-C.2/C/A/B/WE302301/SIRLM ctveu T H E F o L l b w r * \
A LOCA is in progress with all RCPs secured, and the control room operators are attempting to stabilize plant conditions. An operator who is monitoring plant parameters observes the following:
.. Core exit TCs: 780°F
. RCS Pressure RVLlS :
885 psig 50%
auc Which @of the following describes current core cooling conditions and operational requirements?
A. Subcooled. Operator action is not required because core cooling is satisfactory.
B. Saturated. At their discretion, the operators can take action to restore subcooled core cooling per FR-C.3, "Response to Saturated Core Cooling."
C? Degraded. Prompt action must be taken per FR-C.2, "Response to Degraded Core Cooling," or conditions could degrade.
D. Inadequate. Prompt action must be taken per FR-C.l "Response to Inadequate Core Cooling, or core uncovery and fuel damage could occur.
Modified from a Surry Bank Question # 425.
Lesson Plan 3-OT-FRC0001 FR-C.1,C.2,C.3, objective # 1 A. Incorrect, the conditions given indicate that the RCS is in a superheat condition.
B. Incorrect, the conditions given indicate that the RCS is in a superheat condition.
C. Correct, the conditions given indicate that the RCS is in a degraded core cooling condition, and this is the correct remedial action to take.
D. Incorrect, the conditions given indicate a degraded core cooling condition.
Thursday, October 31,2002 05:43:47 PM 22
QUESTIONS REPORT for WBfindraft
- 23. WE08EA2.1S 0 0 1 / T 1 G 1 / T 1 G l ~ S N3.4/4.2/BIWB020301/S/M Given the following plant conditions:
- Crew is responding to a large-break LOCA
- FR-P.1 currently being performed in response to a PTS ORANGE path
- Containment status tree is ORANGE Which ONE of the following is the correct crew response if the PTS status tree turns YELLOW prior to the completion of the Function Restoration Instruction?
A. Crew should stop performance of all Function Restoration Instructions, then evaluate all Critical Safety Functions to determine the appropriate procedure to implement.
B. Crew must complete FR-P.1 since it is equivalent to the PTS RED path Function Restoration Instruction, unless it is superceded by a higher priority RED path.
CY Crew should continue with FR-P.l until transitioned out or the procedure is completed. Status trees will be evaluated at that time to determine the appropriate procedure.
D. Crew should stop performing FR-P.1 and implement the Containment ORANGE path Function Restoration Instruction since it is now the highest priority.
. Ref: WB Lesson Plans 3-OT-FRP0001, obj. 10 and 3-OT-PA11204, obj. 5 Procedure PAI-1204, pp. 26 WB exam bank A is incorrect because while in FRPs, CSF status trees are monitored continuously B is incorrect because the plant conditions, not the procedure number determines implimentation priority.
C is correct based on reference PAL1204 D is incorrect because it conflicts with guidance in PAL1204 Thursday, October 31,2002 05:43:47 PM 23
QUESTIONS REPORT for WBfindraft
- 24. W13EA2.1S OOlfJ?G3/TlG3/OVERPRESSWC/A 2.9/3.3/B/WB02301/S/LM
& u w rCth E ~ / I o ~ w ~ :
The Unit 1 operating crew is currently executing E-I, "Loss of Reactor or Secondary Coolant".
Plant conditions are as follows: 1.5' Containment pressure i s k f p s i g and slowly RCS temperature is 570°F.
a S/G Pressures: S/G #I = 1200 psig; S/G#2 = 1190 psig; S/G#3 = 1230 psig; 1 -
S/G#4 = 1205 psig.
SG NR Levels: S/G #I = 25%: S/G#2 = 30%: S/G#3 =&T 7 h,
~ ~
FR-H.2, "Steam Generator Overpressure", has been entered.
0 . S/G#4 = 35%.
For the existing plant conditions, the Unit Supervisor should:
AI Direct the operators to NOT release steam from S/G#3 and transition to FR-H.3, "Steam Generator High Level" to control and lower S/G#3's level.
spaat$ Direct the operators to NOT release steam from S/G#3 and continue with FR-H.2 to reduce S/G pressure.
C. Direct the operator to open the PORV on S/G#3 to drop pressure below 1220 psig then transition to FR-H.3, "Steam Generator High Level" to control and lower S/G#3's level.
D. Direct the operator to open the PORV on S/G#3 to drop pressure below 1220 psig and continue with FR-H.2 to reduce S/G pressure.
Ref: WB Lesson Plan 3-OT-FRH0001 obj 6 WB Lesson Plan 3-OT-FRH0001 pp 41 & 42 of 56 10CFR43.5 Source WB exam bank last used in '98 SRO audit Distractor analysis:
Answer A is correct based on FR-H.2 procedure step 3 RNO Answers B, C, & D are incorrect based on inappropriate actions and branching directions Thursday, October 31,200205:43:48PM 24
QUESTIONS REPORT for WBfindraft
- 25. WE 1662.3.10 001TTlG2/TlGUEXPOSURE REDUCTIONM 2.9/3.3/BIWB02030 l/S/EL/XLM Given the following:
- A Small Break LOCA occurred 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.
- Containment pressure is 1.7 psig.
- Containment temperature is 220°F.
- Lower containment radiation indicated level is 25 Whr.
- FR-Z.3, "High Containment Radiation", is entered.
Which ONE of the following actions is required in accordance with FR-Z.3?
A. Peform a manual Phase B isolation.
BY Ensure control room isolation.
C. Sample containment atmosphere using PASF.
D. Ensure that all lower compartment coolers are in setvice.
Ref: WB Exam Bank WB Lesson Plan 3-OT-FRZ0001, no specific learning objective WB Lesson Plan 3-OT-FRZ0001, pp. 15 Distactor analysis:
B correct because of step 4 in FR-Z.3.
A, C, D,are incorrect because they are not required by the procedure.
Is this part of the sample?
Thursday, October 31, 2002 05:43:48PM 25
ES-403 Written Examination Grading Form ES-403-1 (R8, S I )
Quality Checklist
-Initials Item Description a
- 1. Clean answer sheets copied before grading RLM NIA I LM
- 2. Answer key changes and question deletions justified and documented RLM I LM
- 3. Applicants' scores checked for addition errors RLM (reviewers spot check > 25% of examinations)
- 4. Grading for all borderline cases (80% +I- 2%) reviewed in RLM detail
- 5. All other failing examinations checked to ensure that grades RLM T
are justified
- 6. Performance on missed questions checked for training RLM NIA LM deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants
- b. Facility Reviewerr) -NIA
- c. NRC Chief Examiner (*) -L. R. Miller
- d. NRC Supervisor (*) -.
irr) ~ The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.
ES-501 Post-Examination Check Sheet Form ES-501-1 (R8, S I )
Task Description Date Complete
- 1. Facility written exam comments or graded exams received and 11/26/02 verified complete
- 2. Facility written exam comments reviewed and incorporated and 12/16/02 NRC aradina completed, if necessary
- 3. Operating tests graded by NRC examiners 12116/02
- 4. NRC Chief examiner review of written exam and operating test 12116/02 aradina completed
- 5. Responsible supervisor review completed 12118/02
- 6. Management (licensing official) review completed 12118/02 I 7. License and denial letters mailed I 1/9/03 I1
- 8. Facility notified of results 12/18/02