ML20248B164
| ML20248B164 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 06/02/1989 |
| From: | Burdick T, Damon D, Hopkins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20248B152 | List: |
| References | |
| 50-305-OL-89-02, 50-305-OL-89-2, NUDOCS 8906080282 | |
| Download: ML20248B164 (116) | |
Text
{{#Wiki_filter:_ - _ , _ _ . ._- _ _ - - -. ._ - . . - _ .-- . . _ - _ _ _ y" g 6 ' U.S.' NUCLEAR REGOLATORY COINISSION
.c REG' ION ~III W Report No,'. 50-305/0L-89-02 Docket"No. 50-305- ' License No. DPR-3 l .
Licensee: Wisconsin Public Servict Corporation w 700 North Adams Post Office Box 19002 Green Bay, WI 54307-9002 Facility Name: Kewaunee Nuclear Power Plant f7 e Examination Administered At: .Kewaunee Nuclear Power Plant . Examination Conducted: May.1-5, 1989' '
,RIII Examiner -
lohk Ddte' t .- ) Chief Examiner: D.,J. Damon [/2[81 '
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Dhte' MM
- Approv'ed_By:- . Thomas M. Burdick, Chief [/74 Operator Licensing Section 2 '
Date b kxaminationSummcry Examination administered on May 1-5, 1989 (Report No. 50-305/0L-89-02)) to three reactor operators and nine senior reactor operators (one SRO was evaluated as an R0 only).
, 'Results: '.0ne senior. reactor operator failed the examination. All other operators l passed the examinations..
I u 89060B02B2 890602 l PDR-V ADOCK 0 % 3 5 - 4
- _ _ _ - _ - - _ _ _ - _ . - _ _ . - ~
r i g REPORT DETAILS-i .
,1. Examiners-L J. A. Hopkins-D. J. Damon-
-T. P. Guilfoil-L G. O. Weale 1
- 2. Exit Meeting On May 5, 1989, an exit meeting was held between the NRC examiners and
. members of the facility staff. The following persons attended the meeting: .
K. Evers, Plant Manager,;WPSC /
.C.'A..Schrock, Assistant Manager Plant Operations, WPSC _
D. T. Braun,. Superintendent Plant Operations, WPSC J. R. Mueller, Superintendent Nuclear Training, WPSC ' R. F. Zube, Assistant Superintendent Nuclear Training, WPSC J. Brown, Nuclear Training Supervisor, WPSC-P. C. Craig,, Instructor, WPSC R. L. Nelson, Senior Resident Inspector, NRC J. S. Stewart, Resident Inspector, NRC l T. Burdick, Chief, Operator I.icensing Section, NRC D. Damon, Chief Examiner, NRC L LJ. Hopkins, Examiner, NRC-G. Weale, Examiner,- NRC' The following comment's were made by the Chief Examiner during the. meeting:
- a. ~ES-601 specifies'that a minimum of 350 questions'per section must be submitted for the written examinations. An agreement with NUMARC specified that questions should be generated at a rate of 30 ner' month from. August 1988 - a total of 210 questions by the March 1,-
1989 submittal: date. The facility submitted 143 questions for Part A and 105 questions for Part B. The NRC was able to construct the Part A and B written examinations entirely from facility supplied questions. j b. Initial review of facility questions by the NRC showed a high l- percentage of " lookup" type questions. This was identified to the facility staff prior.to administration of the examinations. Subsequent revisions by the facility staff reduced the percentage of lookup questions to essentially zero. At the same time, the level and quality of the questions were substantially improved. L L 2 [ , E:_____---_____-_.---__ - - _ -
- c. NRC monitoring of the facility evaluators during conduct of the examinations showed that generally, facility evaluators are doing an excellent job. With minor exception, there was no cueing or prompting of the examinees. The facility evaluators conducted themselves in a very professional manner.
- d. The limited number of sets of reference materials and facility staff evaluators led to scheduling difficulties during the JPM and written portions of the examinations. Initially, all JPM's were scheduled for performance on a single day. Because of diminishing effectiveness of evaluators during the second set of JPM's, the schedule was changed to allow performance of the last JPM set on a second day. The zone evaluation method used encumbered the flow of evaluation due to the number of zones. Such a process requires more zones and more flexibility in scheduling. s._
n The written examinations were also encumbered by the lack'of materials. Enough material and staff must be available to conduct both portions _ of the exam at the same time. - Increased sets of reference materials and increased numbers cf facility staff evaluators would lead to more flexibility in the exam Lchedule.
- e. During the JPM walkthrough portion of the examination, approximately 50% of the personnel observed in the Auxiliary Building by NRC l evaluators did not have security badges in plain sight, as required i by the facility security plan. The security badges were located either under a lab coat, or in a pocket.
- d. Examinee strengths noted during the simulator examinat~ ions:
(1) All operators referred to appropriate procedures in a timely manner. (2) Annunicators were always verified before they were acknowledged. (3) Bistable tripping as a result of instrument failures was a very controlled evolution.
- g. Preliminary results of the evaluations were:
(1) All crews passed the simulator examinations. (2) There was one individual failure on the simulator examinations. (3) All operators passed the JPM walkthroughs. (4) All operators passed the JPM questions.
- 3. Program Evaluation There was one individual failure during the simulator exams, documented by the NRC exam team, that was not identified by the facility evaluators.
3 (
The reason for the failure was that the individual failed to perform
.two individus1. critical tasks. In this circumstance, failure of the individual.is mandated by ES-601.D.l.C(2)(b)(2). The facility contended '
that the individual in question did not fail to perform the two tasks identified by the NRC. In one case, the facility submitted a modification to the scenario,.after the evaluation was performed, changing the individual critical task to a team critical task. This was not accepted by the NRC. In the second case,.the facility argues that the individual did indeed perform the task, even though there was no formal evidence that the individual took actions required by the scenario. Both the NRC evaluators and the facility evaluators agreed that no formal evidence exists to show that the individual performed the critical task in accordance with the scenario. The NRC rejects the contention that the task be considered acceptably completed without evidence to conclusively show that the task was performed. , e, Wherepartialcreditonamulti-partanswerwasnotassignedbhthefacility on the written exams, the NRC made a determination and so annotated on the
-exam key. The facility also accepted answers that were not acceptable to the NRC. In addition, the facility used a different method from the NRC in '
determining overall grades which also contributed to the discrepancy between facility and NRC grading. This did not affect the facility's pass / fail decision. Facility evaluations, in conversation with region management during the followups by NRC, indicated certain grading policies after-the-fact regarding required information for full credit on written exam questions. Taking these practices into account also served to reduce the difference between NRC and facility grade results. Such techniques or practices regarding parameter values or setpoints'must be established prior to grading to be considered acceptable. Also, facility evaluations indicated that interpretations of answers were made in some cases. The NRC does not interpret unclear answers. This also appears to reduce the objectivity of facility evaluation grading. The facility grading passed all operators on all parts of the examination. NRC grading resulted in a total of one failure on all parts of the examina-tion. This resulted in a pass / fail agreement of 91.7%. ES-601.C.3.b(1)(a) specifies that there must be at least a 90% pass / fail agreement between NRC and facility grading; thus the requalification program is considered satisfactory. 4
os L L I' REQUALIFICATION PROGRAM EVALUATION REPORT c . . .
. Facility:- Kewaunee Nuclear Power Plant
' Examiner:- Damon, Hopkins, Guilfoil,.Weale Dates of Evaluation: May 1-5, 1989
-Areas Evaluated: x Written x . Oral 'x Simulator-Examination Results:
R0 SR0 Total Evaluation-Pass / Fail Pass / Fail Pass / Fail (S,sM, or U) Written Examination. 3/0 9/0 12/0- S Operating Examination , Oral 3/1 9/0 12/0 S Simulator
- 4/0 7/1 11/1 S Evaluation of faci 11ty written examination grading S
*0ne operator with an SR0 license was evaluated as an RO only during the simulator examinations.
Overall Program Evaluation Satisfactory X Marginal Unsatisfactory (List major deficiency areas with brief' descriptive comments)-
^
-ES-601.C.3.b(1)(a).- The facility grading passed all operators on all parts of the examination. NRC grading resulted.in a total of one failure for all~
parts of.the exam. The pass / fail agreement was thus 91.7%. c b tted: .ar rded* , A roved: Ama ic /Wrig h- . O k 5
l 9 i' KNPP REQUALIFICATION EXAMINATION PARTA STATIC SCENARIO 1 QUESTION
SUMMARY
SHEET OPERATORS NAME: EXAM ID#: NA1 DATE ADMINISTERED: STATIC SCENARIO ID#: b PART A: PIANT OPERATIONS SCENARIO 1 -. QUESTION POINT POINTS NUMBER VALUE SCORED - 91 M 92 M 91 M (, 9h 2.3 m u Dh 1.3 91 L1 98 U 91 2.3 12 M TOTAL QUESTIONS: 19 TOTAL POINTS: 18.3 TOTAL SCORE: SCENARIO l' CATEGORY SCORE: % ALL WORK DONE ON THIS EXAMINATION IS MY OWN. I HAVE NEITHER GIVEN NOR RECEIVED AID. OPERATOR'S SIGNATURE: GRADERS NAME (PRINT): GRADERS SIGNATURE: j
KNPP REQUALIFICATION EXAMINATION PART "A". GUIDELINES
- 1. Use black ink or dark pencil ONLY to facilitate legible reproductions.
- 2. Print your name in the blank provided on the cover sheet of the examination.
- 3. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTEP.
the examination has been completed.
- 4. Fill in the date on the cover sheet of the examination, if necessary.
e?
- 5. Answer ear.h question on the examination. If additional paper,is required, use only the lined paper provided by the examiner. '
- 6. Use abbreviations only if they are commonly used in facility literature. s
- 7. The point value for each question is indicated above each question.
- 8. Show all calculations, methods or assumptions used to obtain an answer to a mathematical problem, whether asked for in the question or not.
- 9. Unless solicited, the location of references need not be stated.
('""
- 10. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BIAh%.
- 11. If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.
- 12. Rest room trips are to be limited and only one examinee at a time may leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise.
- 13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
- 14. This Part 'A" section is designed to take approximately 45 minutes to complete. You will be given one hour to complete this section.
j - 15. Due to the existence of questions that may aquire all examinees to refer l to the same indications or references, particular care mu.st be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating.
- 16. When you are finished and have turned in your completed examination, leave the examination area.
l 1
NA1.001 0-LRQ-EXAM-STAT-001 Rev.'A ATTACHMENT 1 SCENARIO
SUMMARY
OPERATOR HANDOUT Prior to the event,'the plant was operating at steady state equilibrium 100% power for 140 days. RCS boron concentration was 464 ppm with burn-up at 5000 MWD /MTV. No major equipment was out of service. When the event started, annunciator 47020-14, Reac Cint Lp A Temp Bypass Flow Low, alarmed. Approximately three minutes later the reactor was manually tripped and safety injection was manually initiated. l= Presently exiting E-0 at step 24 prior to entering E-1 at step 1. z7-i
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NA1.001A- 89A.002A Rev. A i l
-QUESTION #: 01 POINTS: 2.0 NOTE: This. question is not directly related to the given plant conditions.
1 IF control rod H8.had stuck, as well as G7, following the reactor trip, what i E uld be the readings on the following indicators at the completion of boration? Assume SI DID NOT initiate. Consider each indicator used separately. NOTE: Record Present readings from the current board indications as a. reference. a) Emergency BA Flow Integrator Present gal Final ga) r. b) Boric Acid Storage Tank 1B Present % . Final %
NA1.001B 89A.002B Rev. A-QUESTION #: 01 POINTS: 2.0 1 ANSWER: a) Emergency BA Flow Integrator: Final > present + 600 gal
~
(50%) b). Boric Acid Storage Tank 1B: Final < present - 20% - (50%) ANSWER REF: 1) E-CVC-35, Emergency Boration, Rev. H, step 4.3 TIME ELEMENT: '4 minutes LEVEL OF LRN/ TYPE: Application / Problem Solving r. KNPP OBJ: 000 005 EA2.03J Given multiple stuck control rods while at power, deterrr.ine the appropriate required actions. << ASSOC. TASK: 0000050501 K/A CAT. REF: 000 005 EA2.03 Ability to detennine or. interpret: Required actions if more than z one rod is stuck or inoperable 4.2/4.7 g- STATIC SIMULATOR CONDITIONS: STAT 001
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'89A.009A'! Rev. A:' <
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. QUESTION#: 02! POINTS: 1. 0.:
I' ' Assess' existing plant conditions and EXPLAIN.if initiation of containment spray. is or-is.not' required. al [ +- r jI ib , e ed r< 4 I sn ns .. l l' p a . t.s
NA1.002B 89A.009B Rev. A l QUESTION #: 02 POINTS: 1.0 ANSWER: Initiation of containment spray is not required because contain-ment pressure has remained below 23 psig. ANSWER REF: 1) E-0, Rev C, Reactor Trip or Safety Injection, step 4.14
- 2) Simulator Control Room Indications TIME ELEMENT: 3 Minutes LEVEL OF LRN/ TYPE: Application / Essay KNPP OBJ: 000009EA2.11J Given a small break LOCA, determine whether containme.nt spray
~
initiation is required. f' ASSOC. TASK: 0000820501 . K/A CAT. REF: 000009EA2.11 Ability to determine or interpret: Containment temperature, pressure, and humidity. 3.6/3.8 STATIC SIMULATOR CONDITIONS: STAT 001
_ _ = . , NA1.003A.. 89A.061A Rev. A.
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~ OVESTION#: 03- POINTS: 1.0 Explain'how the given pressurizer. level trend would have been affected 1'lthe f 18!
' Si pump had NOT failed.
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NA1.0038 89A.061B Rev. A
. QUESTION #: 03 POINTS: 1.0 l-ANSWER: ;PRZR level would hav.e decreased at a slower rate until SI flow exceeded the leak flow and then it would have refilled at a faster rate.
ANSWER REF: 1) Control room indications
- 2) System Design Description 33, Rev. O, Safety Injection System, p. 33-5.
- 3) KNPP IPEOP Background Document for'E-1, Section 2.1.2
. TIME ELEMENT: 3 minutes LEVEL OF LRN/ TYPE: Analysis / Essay 7 KliPP OBJ: 013000A1.11J <'
~
i- Given a failure of an SI pump on an SI actuation, determine the effects of this condition on RCS inventory. ASSOC. TASK: 0000800501 K/A CAT. REF: 013000A1.11
- Ability to predict and/or monitor changes in parameters (to pre-( '-
vent exceeding design limits) associated with operating the ESFAS controls including: Pressurizer level, steam space temperature, and liquid temperature. 3.3, 3.7 STATIC SIMULATOR CONDITIONS: STAT 001 NOTE: Questions 89A.008, 89A.061, 89A.010 and 89A.062 are closely related. 1 1-t --__ _ -_ -
g - - - - 3 h[. ' 'NA1;G04A)' ' 89A.062A .. Rev.-- A. K QUESTION #: ' POINTS: 2.5: h :' Based'on.the present plant conditions, list three' indications that'. verify , failure of-required ESF. equipment-to actuate and provide the-step (s) in the
- appropriate E0P at which.it was identified. 't A
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L NA1.004B 89A.0628- Rev. A l i QUESTION #: 04' POINTS: 2.5 ANSWER: Any three (3) of the following: (50%) (.'in ea)
- a. SI Pump IB Switch position in AUT0/ Breaker Overcurrent Trip Light - LIT
- b. Status Light 44910-0205 on SI Active Status Panel - DIM
- c. SI Pump 1B Amps - 0 amps j d
- d. SI Pump 1B.Disch Pressure gauge P923 - O psig -
- e. Annunciator 47032-35 BUS 1-6 FEEDER BREAKER OVERCURRENT TRIP
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and associated SER point 703
- f. Reduced flow indication on flow meter F-925 f 7-
- j. ' SE . g .f g re l'eht e W red I6h+ 4/
AND E-0 Step 4.4, Check if SI-is Actuated OR Step 4.8, Verify ESF equipment Running (50%) ANSWER REF: (1) Control room indications
... (2) Emergency Operating- Procedure E-0, Rev. C, Reactor Trip or F Safety Injection, Steps 4.4.b., 4.8.a., 4.8.c.
TIME ELEMENT: 6 minutes LEVEL.0F LRN/ TYPE: Analysis / Essay KNPP OBJ: 013000A4.01J Given initiation of an ESF system (s), determine the indications. 1 of the failure of a given component to actuate.
-ASSOC. TASK: 0130010101 0000800501 K/A CAT. REF: 013000A4.01 Ability to manually operate and/or monitor in the Control Room:
ESF initiated equipment which fails to actuate 4.2, 4.5 i STAT 001 l STATIC SIMULATOR CONDITIONS: NOTE: Questions.89A.008, 89A.061, B9A.010 and 89A.062 are closely related. . 1 _ _ _ _o
;NA1.005A" 89A.097A Rev. A- .
- QUESTION #: ;05: POINTS: 2.0 4
For-the' existing plant conditions,' describe the-change in RCS subcooling.if-1A SI pump.-is stopped? Include the reason for the change. Assume RCS pressure has E stabilized at:its present value.. .l l f)
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l NA1.005B 89A.0978 Rev. A ) i QUESTION #: 05 POINTS: 2.0 ANSWER: RCS subcooling will. decrease when SI pump is stopped. .(50%) Since RCS pressure is less than shutoff head of the SI pumps, RCS pressure will decrease when SI flow is 'j' stopped and, therefore,.subcooling decreases. (50%) ANSWER REF: 1) KNPP IPEOP Background Document, ECA-3.2, Rev. 10-30-87, J Section 2, page 15 TIME ELEMENT: 5 minutes LEVEL OF LRN/ TYPE: Analysis / Essay KNPP OBJ: 006050A1.02J g GivenaninitiationofSI,predicttheeffectsofr5CCScomponent operation on RCS subcooling. _ ASSOC. TASK: 0000810501 K/A CAT. REF: 006 050 A1.02 Ability to predict and/or monitor changes in parameters (to pre-vent exceeding design limits) associated with operating the ECCS controls including: Subcooling 4.0/4.2 STATIC SIMULATOR CONDITIONS: STAT 001 4
- - - - __-.m_ _ . _ . _ _ . _ _ _ _ _ _ _ _ _ _ , . . _ . _ _ _ _ . _ _
- f
.NA1.006A 89A.139AR.Rev;1A QUESTION #: 06' -POINTS: 1.5
.The STA has just. completed monitoring the critical safety function status trees.
'He informs.the Shift Supervisor ~of the.need to enter FR-H.1, Response'to Loss of Secondary Heat Sink, Explain why you agree or disagree with the STA's diagnosis.
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m .. NA1.006B' 89A.1398R Rev. A L t
, QUESTION #: 06. POINTS: 1.5-ANSWER: Disagree because FR-H.1 is entered only if both steam generators are less than 2% narrow range level. and total feed flow is less than 200 gpm. Aux feed flow is greater than 200 gpm.
ANSWER REF: 1) Control Romn Indications
- 2) Critical Safety Function Status Tree F-0.3, Heat Sink TM-I E ELEMENT: 4 minutes LEVEL OF LRN/ TYPE: Analysis / Essay l
KNPP'0BJ: Given the control board indications, determine if ayToss of heat sink' condition is occurring. ,f ASSOC. TASK: 000 K/A CAT. REF: 000054G12 Ability to utilize symptom based procedures. 3.2/3.9 STATIC SIMULATOR CONDITIONS: STAT 001 4
- -- - - - - - - - - _ _ __A ___.__.__..__.___.___w
NA1.007A 89A.143A Rev. A
'0VESTION#: 07 POINTS: 1.5 Based upon design operation and current plant conditions, explain why flow meter F-925 is indicating flow.
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l ', NA1.007B 89A.143B Rev. A i QUESTION #: 07 POINTS: 1.5 ANSWER: RCS pressure is less than 2000 psig (or RCS pressure is less than shutoff head of the SI pumps). ANSWER REF: .1) E-0, Rev.-C, Reactor Trip or Safety Injection, Step 4.16
- 2) System Design Description',' Chapter 33, Rev. O, Section 2.0,
- p. 33-4
- 3) Simulator Control Room Indications q TIME ELEMENT: 4 minutes LEVEL OF LRN/ TYPE: Analysis /$ssay KNPP OBJ: 000009G7J N Given a small break LOCA,.specify the criterion used to determine -
whether SI flow is required. ASSOC. TASK: 0000820501 K/A CAT. REF: 000009G7 Ability'to explain and apply all system limits and precautions 3.5/3.9 I STATIC SIMULATOR CONDITIONS: STAT 001 aga gag m,g ~s- : sr -sa a sz-sa = a.s4 m'% a ad injede , y o u a i, sea-liwe is Add % 6-Ms M - INid L. h h. 8, row assd infA flo.a. a c. nsem n%k usa na aue,4a. % uw 4,y, 4 4tc,w 15 ho hou edivb (w P- 92g d hf3 hof Al/ress A cap 4 pA.
? , , . . . , . , i l+e ..NA16008A' 89A.157A Rev. A y .
- sl POINTS:. 2.0 U '
QUESTION #i.'08f c; For.the existing plant conditions,,-explain why SI can or cannot be terminated.- f 5 4/ q$ : f s z-ya. . . . 6 2 9
NA1.0088U 89A.1578 Rev. A QUESTION #i 08 ' POINTS: 2.0 ANSWER: - SI cannot be terminated because SI termination criteria of: 1 RCS pressure - greater _than 2000 psig and stable or
, . increasing AND.
Pressurizer level - greater than 2% is not met. ANSWER REF: 1) Control Room Indications
- 2) Emergency Operating Procedure E-1, Rev. C, Step 4.11
- 3) E-1 QRF, Rev. B c" #
e
- TIME ELEMENT: 4 minutes _
LEVEL OF LRN/ TYPE: Analysis / Essay KNPP'0BJ: 006050A1.01J Given a small break LOCA, evaluate _SI termination criteria. ASSOC. TASK: 0060180101
;(( .
K/A CAT. REF: 006050A1.01, Ability to predict and/or mon
- tor changes in parameters (to pre-
- vent exceeding design limits) associated with operating the ECCS controls including: PRZR level and pressure 4.2, 4.7 STATIC SIMULATOR CONDITIONS: STAT 001 1
l l _m_______.-__m____._______.__.__ _ . . _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _ _ ____-___-_._-..._.m_ _ _ . _ - _ . _ - _ _ _ . _ - _ _ _ - . _ _ . _ _ _.-__m. _ _ . _ . _ _ _ _ _ _ . . _ _ . . , _ . , - . _ _ . _ . _ _ - . ._____.___.___-_______..-_____.._______w
s NA1.009A 89A.158A Rev. A.
- QUESTION #:~'09 POINTS: 2.5 During the recovery actions'for this event, the operating crew is performing.
step 9 of' ES-1.2, Post LOCA Cooldown and Depressurization. If normal spray were not available, what control board operations would be required'to make the PRZR
. PORVs and auxiliary spray available. Use.the current control board. con-figuration as a starting point for your answer.
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n :;a u* ,'.NA1 009Bs ' 89A,1588' Rev. A QUESTION (: POINTS: 2.5 ANSWER: .No actions needed for the PORV's. lIA-101 must be opened and a charging pump must be started for aux. spray. , ANSWER REF: 1)' Control Room Indications g 2)' IPEOP Background Document E-1,-Step 9 .P. 44 and 45, " Rev. A "* , , 3) IPEOP Background Document ES-1.2, Step 9, P. 41, Rev. B TIME ELEMENT: 6 minutes
' LEVEL OF LRN/ TYPE: Analysis / Essay KNPP OBJ: 000b09EA1.01J ~ e3-
- r. ..- ,l' Given a small break LOCA, determine the actions necessary to depressurize the RCS if nornal spray is not available. '.
ASSOC. TASK: 0000820501-K/A CAT. REF: 000009EA1.01 Ability to operate and monitor the following: RCS pressure and
. r; .
temperature. 4.0/4.3 k STATIC SIMULATOR CONDITIONS: STAT 001 l
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iNA1.010A4 .89A.159A Rev..A /; .; 9 :. I ~' POINTS: 2.0
-QUESTION #: 10 1;; ' Based on the existing conditions,'what. recovery procedure should be used after l:: ~ .the completion ofl-the applicable steps in E-17. Include the appropriate-tran-
_sition step.'in_your. answer.- l l
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NA1.010B 89A.159B Rev. A QUESTION #: 110 -POINTS: 2.0-
.. ANSWER: ES-1.2, Post LOCA Cooldown and Depressurization from E-1 step 17.
ANSWER REF: '1). Control Room Indications
; '2) Emergency Operating Procedure E-1, Rev. C, Step 4.17 TIME ELEMENT:- 5 minutes
. LEVEL OF LRN/ TYPE: -Analysis / Essay.
1
-KNPP OBJ: 006000G13J Given a'small break LOCA, determine the correct procedural guidance. . ._
ASSOC. TASK: 0000820501 /
~
K/A CAT. REF:. 006000G13 .< Ability to perform specific system and integrated plant proce-
-dures during all modes.of operation 4.3, 4.2 STATIC SIMULATOR' CONDITIONS: STAT 001
(. 6
ELOR6.1 WISCONSIN PUBLIC SERVICE CORPORATION NO. 0-LRQ-EXAM STAT 001 EV A V TITLE: SMALL BREAK LOCA KEWAUNEE NUCLEAR POWER PLANT L PRESENTATION TIME: 1 HOUR EXAMINATION OUTLINE DATE: 4 2.8 %1 PAGE 1 , REVIEWED BY: b A bNo APPROVED BY: 64h 0 G (Ill 1 l- SCENARIO EVENT NO:
- 1. Stuck rod.
- 2. Failed SI pump. A' i
- 3. Small break LOCA. ,
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Reference:
1.. 0-LRQ-SEP 2.2.3 (C7/Y2) (( l-
- 2. 0-LRQ-SEP 2.1.3 (C8/Y1)
EVALUATION METHOD: Static simulator open reference written exam. L____. _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. m
ELOR6.2 WISCONSIN PUBLIC SERVICE CORPORATION NO. 0-LRO-EXAM STAT 001 REV A TITLE: SMALL BREAK LOCA KEWAUNEE NUCLEAR POWER PLANT EXAMINATION OUTLINE DATE: A R 2 E 1989 PAGE 2 1.0 Scenario Summary A. Power History: The plant has been operating at 100% power for 140 days. Currently at steady state, equilibrium conditions. Burn-up is 5000 MWD /MTU. B. Current Baron Concentration: ,-?
/
464 ppm _ C. Status of Inoperable Equipment / Applicable T.S. LCO's: -
- 1. Before event:
None
-- 2. During event:
- a. IB SI pump - overcurrent trip - LCO TS 3.3.b.1.B.
- b. Stuck rod - stuck at time of trip - LCO TS 3.10.e, 3.10.g
- c. Small break LOCA D. First-Out Annunciator:
47020:0104, Reac Cint Lp A Temp Bypass Flow Low. E. Control Board Manipulations and Procedure Steps Necessary to Conduct Transient:
- 1. Increase charging flow to maximum per A-RC-36D, Step 3.2.2.
- 2. Place turbine driven aux feedwater pump in pullout per E-0, Step 7.
F. Applicable Procedures in Progress and Step In Effect:
- 1. Exiting E-0 at step 24.
- 2. Entering E-1 at step 1.
G. Actions Necessary to Overcome Simulator Deficiencies: None ,
l' ELOR6.3 i WISCONSIN PUBLIC SERVICE CORPORATION NO. 0-LRO-EXAM STAT 001 REV A TITLE: SMALL BREAK LOCA KEWAUNEE NUCLEAR POWER PLANT EXAMINATION OUTLINE ApR 2 61989 l DATE: PAGE 3 2.0 Simulator Setup Instructions Sequence Setup Action (s) Required Reference / Time
- 1. Verify or perform DORT.
A
- 2. Initialize to IC-12, 100% power, MOL. ,/'
- 3. Complete a control room shift turnover checklist. ACD 4.5 ..
- 4. Rotate recorders.
.. 5. . Take simulator out of freeze. Time 0
- 6. Insert malfunction RD0616 to provide mechanical Time 1 min binding of rod G7 in CBC.
0-LRQ-SEP 2.1.3 (C8/Y1)
- 7. Insert malfunction SIO3B to cause IB SI pump to Time 4 min trip on overcurrent after starting in Step 12 below. 0-LRQ-SEP 2.2.3 (C7/Y2)
- 8. Insert malfunction RC06A at 50% :averity to Time 5 min initiate a 360 gpm break in the IA RTD bypass manifold. 0-LRQ-SEP 2.2.3
~
(C7/Y2)
- 9. Increase charging flow to maximum. Time 6 min A-RC-360, Step 3.2.2
- 10. Automatic letdown isolation occurs. Time 7 min i
- 11. Trip manually at 2000 psig. Enter E-0. Time 8 min A-RC-360, Step, 1.1 j
r, a ELOR6.4
- l. WISCONSIN PLMLIC_ SERVICE CORPORATION-' NO. 0-LRO-EXAM' STAT 001 'REV A l
L TITLE: SMALL BREAK LOCA l-- KEWAUNEE NUCLEAR-POWER PLANT EXAMINATION OUTLINE- APR 2 81989 DATE: PAGE 4 2.0 Simulator. Setup Instructions (Continued) l l Sequence Setup Action (s) Required Reference / Time
- 12. Manually initiate SI. Enter E-0. Time 8.1 min A-RC-36D.
Step 1.1 E-0 ' .7
,[
- 13. Pullout TDAFP. Time 10 min E-0 Step 7 .
- 14. Exit E-0 at Step 24 and enter E-1 at Step 1. Time 13.5 min
- 15. Acknowledge and reset all annunciators.. Time 13.5 min I
- 16. . Place simulator.in freeze. Time 13.5 min
- 17. Secure chart drive.
- 18. Verify simulator indications support the exam questions and Attachment 1.
t
- - - - - - - - - - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ w
levs l.. L 1 KNPP 1 REQUALIFICATION EXAMINATION PART A STATIC SCENARIO 2
' QUESTION
SUMMARY
SHEET OPERATORS NAME: EXAM ID#: NA2 DATE ADMINISTERED: STATIC SCENARIO ID#: b 1 ! PART A* PIANT OPERATIONS SCENARIO 2 )- QUESTION. POINT POINTS NUMBER VALUE SCORED . 9.1 2.0 92 L1 M L1
.T -
g y 91 1.a E M . t ._
/2 D TOTAL SCORE:
TOTAL QUESTIONS: 91 TOTAL POINTS: -ift:2' SCENARIO 2 CATEGORY SCORE: % ALL WORK DONE ON THIS EXAMINATION IS MY OWN. I HAVE NEITHER GIVEN NOR RECEIVED AID. OPERATOR'S SIGNATURE: j GRADERS NAME (PRINT): ) GRADERS SIGNATURE:
o KNPP REQUALIFICATION EXAMINATION PART "A" . GUIDELINES
- 1. Use black ink or dark pencil ONLY to facilitate legible reproductions.
- 2. Print your name in the blank provided on the cover sheet of the examination.
- 3. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed.
- 4. Fill in the date on the cover sheet of the examination, if necessary.
0
- 5. Answer each question on the examination. If additional paper,is required, use only the lined paper provided by the examiner. _
- 6. Use abbreviations only if they are commonly used in facility literature. .,
- 7. The point value.for each question is indicated above each question.
- 8. Show all calculations, methods or assumptions used to obtain an answer to a mathematical problem, whether' asked for in the question or not.
- 9. Un1Ess solicited, the location of references need not be stated.
.{
- 10. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.
- 11. If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.
- 12. Rest room trips are to be limited and only one examinee at a time may leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise.
- 13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
- 14. This Part "A" section is designed.to.take approximately 45 minutes to complete. You will be given one hour to complete this section.
- 15. Due to the existence of questions that may require all examinees to refer to the same indications or references, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating.
- 16. When you are finished and have turned in your completed examination, leave the examination area.
1-l' ,
-NA2.001-LRQ-EXAM-STAT-011
^
REV A L , ATTACHMENT 1 SCENARIO
SUMMARY
OPERATOR HAND 0UT Prior to the event, the plant was operating at steady state equilibrium 100% ' power for 140 days. RCS baron concentration was 464 ppm with burn-up at 5000 MWD /MTV. RCS wide range pressure channel PT-419 is failed. l During the event, the component cooling water surge tank level started increasing slowly. Investigation was in progress when annunciators 47001-22, Mois.Sprtr Stop Check Valve Closed and 47001-23, Htr Drn Tnk Cdsr Dump Valve Open alarmed. ' The B0P noticed that number four turbine control valve was closed. Procedure A-CC-318 is in progress at step 3.2.1.
~
9 (.. I e t
NA2.001A 89A.kOSA Rev. A LQUESTION#: LO1- : POINTS: 2.0 W
-Explain what effect the failure of.RCS wide range pressure transmitter (PT-419);
?will have on the RHR system during RCS cooldown to cold shutdown.
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NA2.001B 89A.105B. Rev. A QUESTION #: 01 POINTS: 2.0 ANSWER: The failed high PT-419 would maintain the RHRS high pressure interlock in effect and would NOT allow the RHRS hot-leg suction valves, RHR-2A and 2B, to open.
= ANSWER REF: (1) Control Room Indications (2) System Design Description 34, Rev. O, Residual Heat Removal System, p. 34-9, 10 (3) E2036, Integrated Logic Diagram - Residual Heat Removal System, Rev. V
-TIME ELEMENT: 7 minutes ,7 LEVEL OF LRN/ TYPE: Analysis / Essay /
KNPP OBJ: 005000K4.07J Given a failure of a RCS wide range pressure transmitter, deter-mine the effect on the RHRS system. ASSOC. TASK: 0050010101 ('" , K/A CAT. REF: 005000K4.07 Knowledge of the RHRS' design feature (s) and or interlock (s) which provide for the following: system protection-logics, including high-pressure interlock, reset controls, and valve interlocks. 3.0,.3.3 STATIC SIMULATOR CONDITIONS: STAT 011 NOTE: This question is closely related to question numbers 89A.126 and 89A.140 l 1 r
g7 . ... , < 4 .
;89A.106A Rev. AD l'[ t LNA2.002Ai 1.,
l.
.' 00EST!0N#:J 02 POINTS: 2.5 L
~
Explain what.: two (2): indications (non-annunciator) in the control room verify that the inleakage to the Component Cooling Water System is NOT from a RxCP
-thermal barrier.
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4
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9 I
b NA2.0028 89A.106B Rev. A E- QUESTION #: 02 POINTS: 2.5 l( ANSWER: RxCP thermal barrier discharge isolation valves are open and RxCP CCW return water temperatures are nonnal.. p . 3 ANSWER REF: (1) Control Room Indications
- (2) Operating Procedure A-CC-318, Rev. E, Leakage into the Component Cooling System, Step 3.2.1.b u TIME ELEMENT: 8 minutes LEVEL OF LRN/ TYPE: Analysis / Essay KNPP OBJ: 008000A2.04J ,
~
.n i Given a R-17 radiation monitor alarm, state the ac.t1ons to be taken to determine the leaking component in the Component Cooling ,
Water system. ASSOC. TASK: 008000A2.04J Given A R-17 radiation monitor alarm, state the actions to be taken to determine the leaking component in the Component Cooling Water system. K/A CAT'. REF: 008000A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Radiation Monitoring System (R-17) Alarm. 3.4, 3.0 STATIC SIMULATOR CONDITIONS: STAT 011
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S.Le ink.M h a melev vae IgRc osf e . wo+ acar M. -}Ai3 a c4A rewdr -the h no hih uaMie 6n 3 c
- k en si d d e 40 syd -ik Sub did delk pas re LJ r& 6c- e4 A Ayd.
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;NA2.003A *- '
89A.124A Rev. A. - Q, < % - n' o QUESTION #i 03 . POINTS: 1.5 g. a f. s.: .
'With;the one. turbine control valve shut, how wil1~the! Steam' Dump System. control
.Tavg.if the turbine were to trip.under the' existing conditions?:-
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i NA2.003B 89A.124B Rev.'A i I
~
QUESTION #: 03 POINTS: 1.5
-- ANSWER: On a turbine trip signal the steam dump controller compares Tavg to a no-load-Tavg value of 547'F and generates an error signal for steam dump operation. (Failure of a Turbine control valve 1 has no.effect on Steam Dump System Operation.)
ANSWER REF: 1) Control Room Indications .
-2) System Design Description 6. Rev. O, Main Steam System and Steam Dumps (MS), p. 6-28, 29
- 3) OP-XK100-153, Rev. 4
- 4) E1626, Rev. M g TIME ELEMENT: 5 minutes f LEVEL OF LRN/ TYPE: Analysis / Essay ,
KNPP OBJ: 041020K4.11J Given a failure of a turbine control valve, determine the effect on Steam Dump Operation. ASSOC.. TASK: 041 K/A CAT. REF: 041020K4.11 Knowledge of Steam Dump System design feature (s) and/or interlocks which provide for the following: Tavg/ Tref program. 3.0/3.0 STATIC SIMULATOR CONDITIONS: STAT 011 I O 6
'~'
b' (i; j 7_J NA2.004A:.:
; . 89Ae130A '.Rev. A--
, QUESTION #i :04: .
. POINTS: - 1.5: -
'Wh'atisithereasonadeviationexistsbetweenTrefand'auctioneeredTavg?
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- -_ _ . _ - - - __ .____^___.m_ m_.i_. _ _ _'_ _ . _ ___m_____ _ . _ _ _ _ ___ _ _m- . _ m__ _ _ _ _ _ _ -_ _
. NA2.004Bl '89A.130B- Rev. A l
QUESTION #: 04 POINTS: 1.5
~
ANSWER: Failure of the turbine control valve in the shut position has lowered turbine 1st stage impulse pressure, which lowers the Tref t signal for Tavg - Tref deviation. ANSWER REF:. 1)' Control Room Indications
- 2) Alarm Response Sheet 47014-15, Rev. 6-14-85
- 3) System Design Description 49, Rev. O. Rod Control System and.
Rod Position Indication System, p. 49-12 TIME ELEMENT.: 5 minutes LEVEL OF-LRN/ TYPE: Analysis / Essay j? ,p m. , 8., ,,
;, KNPP OBJ: 001000A1.02J , "j?[\ Given an auctioneered Tavg - Tref deviation alann, determine the -
g) t; , cause of the alarm. il ASSOC. TASK: . 0010090101 I .!{ K/A CAT. REF: 001000A1.02 Y ! .k . . l l)- l i; Ability to predict and/or monitor changes in parameters (to pre-vent exceeding design limits) associated with operating the CROS: controls including: T-ref 3.3, 3.4 yWp .pp'! STATIC SIMULATOR CONDITIONS: STAT 011 .;Mi " .: , ;. t
- "' ' ' 9 NOTE: This question is closely related to question number 89A.134 i i
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. CA2.005A'. L ~89A.136A Rev.iA!.
- j , n ..
QUESTION #: 05f POINTS: 1.0
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. ~
f . Have the appropriate' automatic act. ions for high component cooling; system acti-vity occurred?-- Explain your. answer.
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. NA2.0058 89A.136B Rev. A QUESTION #: 05 POINTS: 1.0 ANSWER: Yes.
The Component Cooling Water surge tank vent valve, CC-104, has closed. ANSWER REF: (1) Control Room Indications (2) Operating Procedure A-CC-31B, Rev. E Leakage into the Component Cooling System, Step 3.1.1 (3) OP-XK100-19, Rev. R (4) E2045, Rev. K-1 l (5) OperatingProcedureA-RM-45,Rev.U,HighRadiakion Monitoring System, Step 3.17.1.a.1 TIME ELEMENT: 4 minutes , LEVEL OF LRN/ TYPE: Analysis / Essay
.KNPP OBJ: 008000K1.03J Given a R-17 radiation monitor alarm, determine the effect on the Component Cooling Water System.
{ ASSOC. TASK: 0080090101 K/A CAT. REF: 008000K1.03 Knowledge of the physical connections and/or cause-effect rela-tionships between the CCS and the following systems: R-17 radiation monitor 3.2, 3.0 STATIC SIMULATOR CONDITIONS: STAT 011 l l 1 J 1 I l l l _. ._. _ _ _ _ _ _0
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2.0-LQUESTION#: 06 POINTS: Given the current plant conditions: (1): Briefly explain why the CRD system-is or is not responding properly? (2) If.Tava decreases to 550*F with ro'ds continuing to insert, what fnunedtate action {s)'should the operator take? J,
/
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.: NA2.006B 89A.1388 .Rev. A
-OVESTION#: 06 POINTS: 2.0 ANSWER: (1) The CR0 system.is responding as required by the greater _than l~
5'F Tavg/ Tref deviation.
'(2) Inrnediately transfer to manual rod control ANSWER REF: (1). Control Room' Indications L
(2)- Operating Procedure E-CRO-49A, Rev. C, Continuous Rod' l' Insertion, Steps 3.2.1 and 3.2.2 TIME ELEMENT: 5 minutes LEVEL OF LRN/ TYPE: Analysis / Essay T. KNPP OBJ: 001050G13J fr
/
Given symptoms of a continuous rod insertion, determine the , corrective procedural action to be taken. - ASSOC. TASK: 0000060501 K/A CAT. REF: 001050G13 Ability to perform specific system and integrated plant proce-
- n. dures during all modes of plant operation. 4.2, 4.3 STATIC SIMULATOR CONDITIONS: STAT 011
/ 9
A.,... _. _
- NA2.007A 89A.140A' Rev. A.-
1 . (h0EST10N#: 07- -
' POINTS: 2.5
~
What -two. (2)::: technical specification related systems' are affected by the failure
- of RCS wide range pressure transmitter PT-4197--
/
' ~
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NA2.0078 89A.140B Rev. A 4 QUESTION #: 07 POINTS: 2.5 ANSWER: ICCMS system OR Subcooled Margin Monitor (50%) and RHR system (valves RHR-2A and RHR-28) (50%) ANSWER REF: (1) Control Room Indications (2) System Design Description 36, Rev. O, Reactor Coolant System, p. 36-52 (3) Technical. Specifications, Section 3.5, Table 3.5-6 (4) E2036, Rev V TIME ELEMENT: 6 minuteu / LEVEL OF LRN/ TYPE: Analysis / Essay KNPP OBJ: 002020G5J Given a failure of a RCS wide range pressure instrument, state 1 the technical specification related equipment that is affected. ASSOC. TASK: 0020090101 K/A CAT. REF: 002020G5 Knowledge of limiting conditions for operations and safety limits. 3.5, 4.2 STATIC SIMULATOR CONDITIONS: STAT 011 NOTE: This question is closely related to question numbers 89A.105 and 89A.126. I
. NA2dOO8kl 89A.163k'Rev'.-A r
. : . .13-1 QUESTION #: 08. POINTS: 2.5
( -.
'The..STA has:just informed you that.he has diagnosed.a 20 gpm leak from the 'let-down heat' exchanger'to the CC system.' Diagnose and explain whether or not'you F- .-agree with him.
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NA2.008B 89A.163B Rev. A j l
. I OVESTION#: 08' POINTS: 2.5 I l
ANSWERi If the leak were 20 gpm, letdown flo would indicate approxima-tely 20 gpm. At present, letdown fl w is indicating approxima- -l tely 35 gpm. .Therefore, disagree. 1 f I
/
ANSWER REF: ] ) Simulatpr Control Room Indic ions TIME ELEMENT: ( minutes LEVEL OF LRN/TYP.: Ana ysis/ ssay KNPP OBJ: 0 020G1BJ
^
N
. i Re yntz e in tions of a leak rom the letdown hea,t exchanger.
.,4 f ASSOC. TASK: - 004 50 1 /
K/A CAT. REF: 004 G15 111ty to recognize abnormal indications for system operating-parameters which are entry-level conditions for emergency and abnormal operating procedures 4.2/4.3 STATIC SIMULATOR CONDITIONS: STAT 011 l l ', I-
cm . .-
.ELOR22.1 -__
' WISCONSIN PUBLIC SERVICE CORPORATION NO. 0-LRQ-EXAM STAT 011 REV A TITLE: TURBINE CONTROL VALVE FAILURE KEWAUNEE NUCLEAR POWER PLANT PRESENTATION TIME: 1 HOUR EXAMINATION OUTLINE
~ REVIEWED BY: b A b l /r 6 7 APPROVED BY: O4h f W ()
SCENARIO EVENT NO:
- 1. RCS wide range pressure failure.
Letdown heat exchanger tube leak. "7 2. 3._ Turbine control valve failure. . (
Reference:
- 1. 0-LRQ-SEP 2.1.4 (07/Y2)
- 2. '0-LRQ-SEP 2.1.4 (C8/Y1)
- 3. 0-LRQ-SEP 2.1.5 (C8/Y1) l~
EVALUATION METHOD: Static simulator open reference written exam. l
ELOR22.2 l
' WISCONSIN PUBLIC. SERVICE CORPORATION NO. 0-LRQ-EXAM STAT 011 REV A l
.l TITLE: TURBINE CONTROL. VALVE KEWAUNEE NUCLEAR POWER PLANT FAILURE I
~
t. EXAMINATION OUTLINE i DATE: APR 2 8 1989 PAGE 2 1 1.0 Scenario Summary A. Power History: The plant has been operating at 100% power for 140 days. Currently at steady state, equilibrium conditions. Burn-up is 5000 MWD /MTV. B. Current Boron Concentration: 7 464 ppm _/ C. Status of Inoperable Equipment / Applicable T.S. LCO's: ,
- 1. Before event:
- a. Wide range RCS pressure PT-419 failed high.
- 2. During event:
. e: .
- a. . Letdown Hx tube leak.
Turbine control valve failure. b. D. First-Out Annunciator:
- 1. 47001:0202 Mois. Sprtr. Stop Check Valve-Closed.
- 2. 47001:0203 Htr. Drn. Tnk. Cdsr. Dump-Valve Open.
E. Control Board Manipulations and Procedure Steps Necessary to Conduct Transient: ,
- 1. None F. Applicable Procedures in Progress and Step In Effect:
, 1. A-CC-31B, Step 3.2.1 G. Actions Necessary to Overcome Simulator Deficiencies:
.1. None
l ELOR22.3' l WISCONSIN PUBLIC SERVICE CORPORATION NO. 0-LRQ-EXAM STAT 011 REV A TITLE: TURBINE CONTROL VALVE KEWAUNEE NUCLEAR POWER PLANT FAILURE EXAMINATION OUTLINE DATE: APR 2 81989 PAGE 3 2.0 Simulator Setup Instructions Sequence Setup Action (s) Required Reference / Time
- 1. Verify or perform.00RT.
- 2. Initialize to IC-12, 100% power, MOL. f2
/
- 3. Insert system override RC207 (S02, Line 1) Time 0 min at 2500 psig. to fail PT-419 high. 0-LRQ-SEP 2.1.4 (C7/Y2)
- 4. Take simulator out of freeze. Time 0 min 5.. Place simulator in freeze. Time 0.1 min
- 6. Complete a control room shift turnover checklist. ACD 4.5
- 7. Rotate recorders.
- 8. Take simulator out of freeze. Time 0.1 min
- 9. Insert malfunction CV04 at 5% to provide a 5 gpm Time 2 min letdown heat exchanger tube leak. 0-LRQ-SEP 2.1.5 (C8/Y1)
, 10. Insert malfunction TC01D at 1% to fail turbine Time 5 min control valve #4 closed. 0-LRQ-SEP 2.1.4 (C8/Y1)
- 11. Acknowledge and reset all annunciators. Time 6 min
- 12. Place simulator in freeze. Time S min l
- -- _ --- -_A
ELOR22.4 WISCONSIN PUBLIC SERVICE CORPORATION NO. 0-LRO-EXAM STAT 011 REV A TITLE: TURBINE CONTROL VALVE KEWAUNEE NUCLEAR POWER PLANT FAILURE EXAMINATION OUTLINE DATE: APR 2 E 1989 PAGE 4 2.0 Simulator Setup Instructions (Continued) Sequence Setup Action (s) Required Reference / Time
- 13. Secure chart drive.
Verify simulator indications support the exam ,? 14. questions and Attachment 1. / I l i
NRC1.3- Page 1 of 3 i i J
-JOB PERFORMANCE MEASURE EXAMINATION OPERATOR / EXAMINER ROTATION (FIRST GROUP)
STATION #1 - SIMULATOR PHIL CRAIG STAFF GR(UP NRC EXAMINER JPM NUMBERS
- 1. .STERNITZKY -------------- 1. GUILF0ll ---------- K 8 , G , R
- 2. RISTE ------------------- 2. HOPKINS ----------- $, 5 , 9 , 8
- 3. RUITER ------------------ 3. D AMON ------------- $1 #3
- 4. MASARIK ----------------- 4. WEALE ------------- d, A , D
_. ?
/
STATION #2 - AUXILIARY BLDG GORDIE KROGH STAFF GROUP NRC EXAMINER JPM NUMBERS
- 1. MASARIK ----------------- 1. WEALE ------------- @ , B , @
- 2. STERNITZKY -------------- 2. GUI LF0ll ---------- @ , O
-o
~ '
- 3. RISTE ------------------- 3. HOPKINS ----------- Q , B , @
s 4. RUITER ------------------ 4. D AMON ------------ -(6, p, ,F STATION #3 - CONTROL ROOM / TURBINE BLOG JOHN SHAEFFER STAFF GROUP NRC EXAMINER JPM NUMBER:
- 1. RUITER ------------------ 1. DAMON ------------- g, g , #
- 2. MASARIK ----------------- 2. WEALE-------------g
- 3. STERNITZKY -------------- 3. GUILF0ll ---------- Q, E
- 4. RISTE ------------------- 4. HOPKINS ----------- e, 95 STATION #4 - SAFEGUARDS ALLEY / DIESEL GENERATOR ROOM MIKE BURACZEWSKI STAFF GROUP NRC EXAMINER JPM NUMBERS l 1. RISTE - ----------------- 1. HOPKINS ----------- @, y
- j. 2. RUITER ------------------ 2. D AMON ------------- R, m l 3. MASARIK ----------------- 3. WE ALE ------------- 8, B ,10
- 4. STERNI TZKY -------------- 4. GUI L F0Il ---------- W , @
l b . . _ _ _ ________.._.___m_
~ << ~ ,
7 l KNPP REACTOR OPERATOR REQUALIFICATION EXAMINATION. PART B QUESTION
SUMMARY
SHEET OPERATORS NAME: DATE ADMINISTERED: PART B EXAM ID#: NBR PART B: LIMITS AND CONTROLS ,; l t QUESTION POINT POINTS QUESTION POINT POINTS . NUMBER VALUE SCORED NUMBER VALUE SCORED
~
n u n .u n u u u. a u n u (. . m u n u n u - M M - a M M u L n u 1 m u l TOTAL QUESTIONS: M TOTAL POINTS: J2 TOTAL SCORED:
^
CATEGORY SCORE: % ALL WORK DONE ON THIS EXAMINATION IS MY OWN. I HAVE NEITHER GIVEN NOR RECEIVED AID. OPERATORS SIGNATURE: GRADERS NAME-(PRINT): GRADERS SIGNATURE:
l' 1 l: KNPP i 1 REQUALIFICATION EXAMINATION o u PART "B" GUIDELINES
- 1. Use black in' or acrk pencil ONLY to facilitate legible reproductions. l
- 2. Print your name in the blank provided on the cover sheet of the examination.
I l 3. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examinatic,n. This must be signed AFTER i the examination has been completed.
- 4. Fill in the date on the cover sheet of the examination, if necessary.
- 5. Answer each question on the examination. If additional paper [s required,.
use only the lined paper provided by the examiner. .
- 6. Use abbreviations only if they are commonly used in facility literature.
-7. The point value for each question is indicated above each question.
- 8. Show all calculations, methods or assumptions used to obtain an answer to a mathematical problem, whether asked for in the question or not. i
- 9. Unlesi, solicited, the location of references need not be stated.
{
- 10. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.
- 11. If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.
- 12. Rest room trips are to be limited and only one examinee at a time may leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise.
- 13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
- 14. This Part "B" examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete this examination.
- 15. Due to the existence of questions that may require all examinees to refer to the same references, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating.
- 16. When you are finished and have turned in your completed examination, leave the examination area.
_ - _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ - _ - _ - _ _ _ _ 1
r - ~ ' ' = =- ~ ~ - - - - - ~ ~ - - - - - - - - ~ - - - - - - - - - - - - - - --
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(. -+ NBR.001A. 898.001A Rev. A-I' QUESTION #: 01 POINTS: 1.0 n: Initial Plant Operating Conditions: 98% Power, Nonnal Operating Pressure, Normal Operating Temperature. I
'ICS Pump 1A~has been tagged out of service since 0800 this morning. The f electrical maintenance department requests de-energizing and tagging out 480 VAC bus 1-61 for bus maintenance. State whether the tagout should be allowed / disallowed and explain your reasoning.
' ,7
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' NBR.001B' 89B.001B Rev.~A l 00ESTION#': 01, ' POINTS: 1.0 ANSWER: (1) The'tagout should not be allowed. (20%)
L (2) De-energizing 480 VAC bus 1-61 de-energizes ICS pump 18 and Containment fan coil units 1C and 10. (40%) Because.IA ICS pump is out of. service, de-energizing bus 1-61 violates the. Tech. Spec. requirement for two operable containment. cooling trains'during power operation. (40%). ANSWER REF: (1)' E240, Circuit Diagram - 4160V and 480V Power Sources-(2) Technical Specifications 3.3.c.2, Containment Cooling Systems TIME' ELEMENT: 4 minutes 7)- LEVEL OF LRN/ TYPE: Evaluation / Essay , KNPP OBJ: 026000K3.03J Given a loss of the ICS system, determine the resulting effects on the: requirements for operation of the containment fan coil units. ASSOC.. TASK: 0260010101 K/A CAT. REF: 026000A3.03 Knowledge of the effect that a loss cf the.ICS system will have on the fo~ dog: Containment fan coil units 3.2, 3.0 4
.es.. _ . _ _ . _ . _ . . - - _ _ _ . _ . - _ , . _ . _ . . _ _ _ _ _ . _ _ - . . _ _ _
..y ,,,
NBR.002A. 89B.005A~~Rev. A QUESTION #: 02 POINTS: 2.0-L. ,. During power operations at 80% power with.the control rods in AUTO, a control rod'in' Control Bank-D dropped. The reactor'did NOT trip. I: What. is the innediate~ operator action (s) and what is the basis for the action (s)? - o V
,s.-
t. Y
~
y$ 7 L
n J . NBR.002B 898.005B' Rev. A 1: QUESTION #:- 02 , POINTS: 2.0
. ANSWER: Reduce reactor power to less than 50% power. (25%)
, Reducing power below 50% increases the margin to core peaking factors (37.5%) and insures adequate shutdown margin. (37.5%).
. ANSWER REF: 1) Technical Specification 3.10.e.2
- 2) .E-CRD-49C, Dropped Rod, Rev F, step 3.2.3 TIME ELEMENT: 5 minutes LEVEL OF LRN/ TYPE: Evaluation / Essay-KNPP OBJ: 000003EK3.04J- j?
e
/
Given a dropped control rod event, evaluate the effectiveness of ., the innediate actions stated in Operating Procedure E-CRD-49C:' . DROPPED ROD. ASSOC. TASK: 0000030501 K/A CAT. REF: 000003EK3.04-Knowledge of the bases or reasons for the following: Actions
.(9 contained in E0P for dropped control rod 3.4, 3.8 4
NBR.003A 89B.085A Rev. A QUESTION #: 03 POINIS: 2.0
~
Plant Operating Conditions: Plant Startup in progress at step 4.6 of procedure N-0-01. Maintenance department wants to tag out 480 VAC bus 1-32 for 24 hours to perform maintenance. Explain why this should not be done at this time.
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i 9
NBR.003B- 898.085B Rev.-A QUESTION #: 03 POINTS: 2.0 ANSWER: De-energizing. bus 1-37)willde-energizeMCC -3 which is the power supply for RxCP 1A oil lift pump. The RxCP cannot be started without the oil lift pump running. (50%) QQ
%ctM fM 14 ad ItHe "I8 , ced k geW (14)
ANSWER REF:. 1) Operating Procedure N-RC-36A, Reactor Coolant Pump Operation, Step 3.4
- 2) Operating Procedure.N-0-01, Plant Startup from Cold Shutdown
-Condition to Hot Shutdown Condition, Step 4.6
- 3) Electrical Cross Reference, Rev. 10-17-88,480VJCC
- 4) Motor List, Rev. 8-31-84 f[
~
- 5) un M -
TIME ELEMENT: 6 minutes LEVEL OF LRN/ TYPE: Evaluation / Essay ( KNPP 0'BJ: 003000K2.01J Given a plant electrical lineup, determine the ability to operate the Reactor Coolant Pumps. ASSOC. TASK: 0030010101 0030020101 0000160501 K/A CAT. REF: 003000K2.01 Knowledge of bus power supplies to the following: RxCP. 3.4, 3.3 h _____m._.-____.- _ _ _ _
'NBR;004A: 898.096A' y -
F
- 1 .
L ; QUESTION #: 04 POINTS: 2.0
-The plant is at 100% power, Normal. Operating Pressure and Temperature.
A' reactor coolantDieak, located on the RCS piping, of 10 gpm has been iden-- l tified. Prior to identification, there had been no change in PRZR level. L- . Explain how this RCS. leak could occur without affecting PRZR level?- I-i, 0 $
[' D ' L -NBR.0048- 898.0968 r QUESTION: 04 POINTS: 2.0 ANSWER: During normal operation with letdown' flow at 40 GPM, one charging pump will be in manual and one charging pump would be in auto.' (50%) The leak of 10 gpm would not show up as a decreasing pressurizer level because the charging pump in auto would increase speed to nake up for the leak. (50%) ANSWER REF: 1) A-RC-350, Rev. O, Reactor Coolant Leak, Various~ steps
- 2) System Description 36, Rev. O, Reactor Coolant System.
.pp. 36-48, 49
- 3) System Description 35, Rev. O, Chemical and Volume Control' System, p. 35-26 ,,
.r ?
TIME ELEMENT: 5 minutes e
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LEVEL OF LRN/ TYPE: Application / Essay KNPP OBJ: 000028EK1.01J Given an RCS leak,' evaluate the effect of the-leak on the PRZR level control system. 0000280501
.(,
~
ASSOC.. TASK: K/A CAT. REF: 000028EK1.01 Knowledge of the following theoretical concepts as they apply to the PRZR level malfunction emergency task: RCS leak abnormalities 3.5, 3.5
)
L I NBR.005A 89B.036A Rev. A QUESTION #: 05 POINTS: 3.0 The plant is cooling down following a LOCA. The RCS is at 300'F.and 100 psig. You are directed to perform A-RHR-34B, Residual Heat Removal Split-Train Mode, to continue cooldown. Explain why the annunciators listed below are in the indicated state during the performance of A-RHR-34B: a) RHR. IMPROPER LINEUP-(47023-31) -- extinguished b) RHR PUMP 1A' PRESSURE HIGH (47023-43) -- illuminated c) RHR PUMP IB PRESSURE HIGH (47023-44) -- extinguished d) RHR LOOP RC FLOW LOW (47023-45) -- extinguished , 9 4 0 4 9
'NBR.005B' 89B.036B Rev. A QUESTION #:- 05 POINTS: 3.0
' ANSWER: a) RHR IMPROPER LINEUP (47023-31) -- this alarm cleared with RCS.
pressure lest than 450 psig because RHR 1A, 1B, 23 and 28 - are opened-(for split train operation). (25%) G/S) b) RHR PUMP 1A PRESSURE HIGH (47023 .When this pump is aligned to the RCS and restarted, its discharge pressure p will be greater than 210 psig to illuminate the alarm (25%) (,7 c) RHRPUMPIBPR)$5UREHIGH(47023-44)-- This pump discharge pressure will stay below 210 psig because s suction is from the RWST to extinguish the alarm (25%) ,7 7) d) RHR LOOP RC FLOW LOW (47023-45)
- 1) Depending on the size of the break, the injection flow rate :nay be less than 1250, so the alarm may be initiated during the injection phase. ,
- 2) This alarm will reset when pump 1A is started and flow is' '
established through RHR-101/CV-31116
-- either answer (25%) ,7.5~). .
ANSWER.REF:- 1) A-RHR-342 Residual Heat Removal Split-Train Mode
^- 2) -N-RHR-34-CL Rev R Residual Heat Removal Prestartup Checklist
- 3) 47023-31, 43, 44, 45, Alarm Response Sheets 1
- 4) E2036, Integrated Logic Diagram - Residual Heat Removal System
- 5) E2032, Integrated Logic Diagram - Safety Injection System TIME ELEMENT: 8 minutes LEVEL'0F LRN/ TYPE: Analysis / Essay KNPP OBJ: 005000K1.06J J
Given a cooldown in progress following LOCA, compare decay heat removal flow path to the low head safety injection flow path. ASSOC. TASK: 0050030101 1 K/A CAT. REF: 005000K1.06 Knowledgeofthephysica1Iconnectionsand/orcause-effectrela- ; tionships between the RHRS and the following systems: ECCS l (SI/RHR) 3.8, 4.3 ; 4
]
i __--_ .--_-__--_-_-___..-_____----Q
NBR.006A 898.040A Rev. A
' 0VESTION#: 06 POINTS: 3.0 Plant Operating Conditions: 1007, power, Normal Operating Pressure and Temperature. The following valves are DANGER tagged under various tagouts:
SA 2D, Air Compressor 10 Air Receiver Outlet ~- SHUT SW 18510, Air Compressor 10 Service Water Inlet - SHUT FW 100 A,-FW Recirc to Condenser 1A - SHUT-SW 4A, Turbine Building SW Supply and Is016'. ion Valve - SHUT SD 2A, Main Steam Controlled Relief Valve Isolation - SHUT The Maintenance.l.ead Man requests that SW pump 182 be secured for mai6tenance. Evaluate the request based on procedural compliance, identify whether the 1B2 SW pump should or should not be secured for maintenance, and explain your reasoning.
. 9 i
d 4
._--_-__-______.-____--_.--.m
NBR.006B 89B.040B Rev. A QUESTION #: 06 POINTS: 3.0 ANSWER: SW pump IB2 cannot be secured because it would render train "B" inoperable due to the fact that train "A" service water supply valve is danger tagged shut. ANSWER REF: 1) N-SW-02, Service Water System, Step 2.4.2
- 2) Tech Spec 3.3.e.2, Service Water System
- 3) Operations-M202, Rev. BE, Flow Diagram Service Water System, Sheet 1 , , ,
yv
- 4) Operations-M210, Rev. T, Flow Diagram Turbinejdil Purification .
- 5) Operations-M208, Rev. AS, Flow Diagram Fire Protection System '
i
- 6) Operations-M204, Rev. GM, Flow Diagram Condensate and Gland Seal System
.. TIME El.EMENT: 8 minutes l'.
LEVEL OF LRN/ TYPE: Evaluation / Essay KNPP OBJ: 076000G13J For a given SW system evolution, apply the appropriate plant procedure (s) to ensure the evolution complies with procedural guidelines. ASSOC. TASK: 0760010101 07600S0101 K/A CAT. REF: 076000G13 Ability to perform (use) specific system and integrated plant j procedures during all modes of operation 4.3, 3.7 I 1
i - . ~ NBR.007A 898.041A Rev. A, i QUESTION #: 07 POINTS: -3.0 Initial Plant Conditions: 100% power, Normal Operating Pressure and Temperature L SW header pressure: 84 psig, PI-41503 and PI-41506
~SW Preferred Selector Switch ES-46523 in 1A position SW pumps.1A1 and 1A2 running SW pumps 1B1 and 182 in AUTO and not running Annunciator 47002-15, SW PUMP BEARING SEAL WTR FLOW LOW, is actuated. {
Investigation identifies the source of the alarm as FS-16809. !. i 2 Shortly after, SW header pressure decreases from 84 psig to 80 psig due to increased cooling demand. i Which SW pumps should be running following the SW header pressure ~' tt;ansient? , Explain, c
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6 1 O
..) , ,, lO NBR.0078' 898.041B Rev. A f3 . QUESTION #: 07. POINTS: 3.0 fg (a [
l- 7
- ANSWER
- 1) SW pumps.IA1 and 1A2 shouid'be runnihg. U(40% .
p
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- 2) SW heade.r pressure of 80 psig will provide a' start signal to SW pump 181 at 82 psig.' -(30%) w The auto start of SW pump 1B1 will be blocked by the "BRG Seal Water Flow Low" start permissive'on SW. pump 181. (30%)
I ANSWER REF: 1) Operating Procedure E-SW-02, Low Service Water Pressure, Step 3.1.1 t 2). Alarm Response Sheet 47002-15, SW PUNP BRG SEAL,WTR , FLOW LOW
- 3) E-1630. Integrated Logic Diagram, Service Wate'r System
. 4) Operating i'rocedure N-SW-02, Rev. H, Service Water System. ,,T '
TIME ELEMENT: 9 minutes
- g". LEVEL OF LRN/ TYPE: Evaluation / Essay 4
KNPP OBJ: 076000K4.02J . Given a set of SW system initial conditions, predict the L resulting SW system status. ASSOC. TASK: 0760040101 0760050101 K/A CAT. REF: .076000K4.02 .j Knowledge of the SWS design feature and/or interlock which provi- ) des for the auto start features of the SW Pumps- 3.2, 3.3 4 _._.m. ._ . _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
89B.043A:--Rev.'A.
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M n NBR 008A' '
. [i' '
R QUESTION #: 08- POINTS: 2.0
.a
/f LA reactor trip and SI have occurred.' When Step 22 of- E-0, Reactor. Trip or Safety Injection is performed,- it.is discovered that.1A S/G pressure isl .
'? decreasing-.in an uncontrolled manner. Subsequent' actions ~ require. verifying shut-
.f/' or' shutting-theLMSIV(s).- .
/[ State two;(2) reasons or basis for verifying shut or. shutting'the MSIV(s)? y
.N t
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)
w i__.1.______ _ _ _ _ _ . . _ _ _ _ _ _
898.043B Rev. A
- N8R.008B: _
-QUESTION #: 08 POINTS: 2.0 ANSWER: 1) An. attempt to 1solate the-leak (50%)
- 2) To isolate the S/Gs from each other (50%) i ANSWER _REF: 1) IPEOP Background Documents, Vol. I, E-2, Faulted Steam Generator Isolation, Rev. 7-31-88 ,
.f i
TIME ELEMENT: 6 minutes
, LEVEL OF LRN/ TYPE: Analysis / Essay KNPP OBJ: 000011EK3.01J /
Given plant conditions involving a faulted steam generator (s),. determine the reasons for verifying shut / shutting the MSIVs. - p ASSOC. TASK:- 0000110501 K/A-CAT. REF: 000011EK3.01 Knowledge of the bases or reasons for the following: Verifying ((.. the main steam isolation valve position 3.2, 3.8
NBR 009A 898.044A Rev. A QUESTION #: 09 POINTS: 2.5 Plant Operating Conditions: 100'/. ' power, Normal Operating Pressure and Temperature A "SW PUMP BRG SEAL WTR FLOW LOW" 47002-15 alann is received, followed by a reactor trip and SI actuation.
- 1) What service water pumps should be operating and why?
- 2) What should be the resulting status of the cross-connection between SW trains "A" and "B"? Explain.
e?' f F
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. NBR.0098 898.044B Rev. A -
, QUESTION #: - 09 POINTS: 2.5 ANSWER:' '1) All four SW pumps.should be running due' to auto start signal from the SI. 'The bearing water low fl w SW ump start inhi-bit is bypassed by an SI actuation. ,
2) SWtrains"A"and"B"shouldnolongerbecross-connecteddue) to the SI auto closure of the SW cross-connect valves.(l,25
- ANSWER ~REF: 1) E-1630,. Integrated Logic Diagram, Service Water System, '
Rev. J 1 TIME ELEMENT: 7. minutes. [ LEVEL OF LRN/ TYPE: Application / Essay _ KNPP OBJ: 076000A3.02J Given plant conditions resulting in an automatic signal to the service water (SW) system, predict the final SW system lineup. ASSOC.. TASK: 0760040101 g . 0760070101 K/A CAT. REF: 076000A3.02 Ability to monitor automatic operation of the SW with respect to emergency heat loads 3.6, 3.7 4
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NBR.010A 898.058A Rev. A QUESTION #: 10 POINTS: 2.5 Plant Conditions: Plant cooldown to cold shutdown in progress Tave = 380'F RCS Pressure = 1800 psig SI actuation manually blocked in the control room Annunciator 47024-13, CONTAINMENT HI PRESS SI CHANNEL ALERT, is received. Containment pressure is verified to be 4.5 psig. What will be the response of the Safety Injection System? Explain, y? I i l p l L_____._.____.__ _ _ _ _ .
898.058B Rev. A-NBR.010B QUESTION #: 10 POINTS: 2.5 ANSWER: SI will actuate. } SI actuation upon containment' pressure channels greater than the actuation setpoint is NOT blocked by the SI nanual block swi h. Under the given conditions, SI will have already actuated. ANSWER REF: 1) Operator Training Manual Rev 8403, p. IV-11.13, IV-12.19 and IV-12.20
- 2) Syste... Design Description 33, Rev. O, Safety Injection System, p. 33-16
;?
- 3) X-K100-150, Rev. 5, Logic Diagrams - Safeguards Actuation Signals -
TIME ELEMENT: 6 minutes LEVEL OF LRN/ TYPE: Evaluation / Essay ,(- KNPP OBJ: 013000K4.01J Given plant conditions requiring SI, determine the necessity for actuation / reset of SI. ASSOC. TASK: 0130030101 K/A CAT. REF: 013000K4.01 Knowledge of ESFAS design feature (s) and/or interlock (s) which provide for the following: SI reset / actuation 3.8, 4.5 ; 4
'O _ _ . _ . - . _ _ - . _ - . _ _ . _ _ - _ _ _ _ . - _ _ _ - . . - - . - - . - .
f'... 898.062A. Rev. A-iN8R.011A-
- QUESTION #: 11' POINTS: 2.5
. Plant.0perating Conditions: 100% Power, Normal Operating Pressure and i
, . Temperature.
~
Plant power is lowered to 50% at a normal _ rate. What, if any, are the CVCS charging'and letdown flow' automatic responses to the resulting PRZR level change. Explain.
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y - r ' a ij ' k
7, NBR.0118- 898.062B Rev. A' o QUESTION #: 11 POINTS: 2.5 i l ;' ANSWER: 1) chan l ThereShouldnot.beany(/,0)gestoCVCSchargingor, ficw rates. .(40%) letdown i
- 2) The PRZR level-control system is dert gned with a program-levelsetpointbasedonTave.(30%@SlThedecreaseinPRZR ,
level would be compensated for by the .Tave peerease and no level error signal would be. generated.(30%pf)In this case, charging and letdown flow would remain constant by design.- ANSWER REF: 1)) System Design Description number 36, Reactor. Coolant System,
- p. 36-45, WPS-RC21, 22
- 2) SystemDesignDescriptionnumber35,Chemicalanddolume Control System, p. 35-28 f?
l t
- 3) Operating Procedure N-CVC-35B, Charging and Volume Control _
- 4) Operator Training Manual, Rev. 8403, PRZR Level Control System, p. IV-7.5 TIME ELEMENT: 6 minutes' LEVELbFLRN/ TYPE: Application / Essay KNPP OBJ: 004000r!.01J Given a change in PRZR level, predict the response of the CVCS.
ASSOC. TASK: 0040010101 K/A CAT.'REF: 004000K1.01 Knowledge of the physical connections and/or cause-effect rela-tionships between the CYCS and the following systems: PRZR level control. 4.2, 4.3 U [ k M Tag h 08d w N pre n - m ie kM E.II h $l% kye, A pm , s, cH,'m u,ll k rad (24). A3 lul
-p beks p% ci m J.tl k meusa (14). E41% re b I+l A0 Akt,n ,A g% led , Ar4 c% dlJ 43 g edp.Ivdwe. (M) 1
i ' NBR.012A 89B.063A Rev. A POINTS: 2.5 Yy QUESTION #: 12 Plant Operating Conditions: 100*/. Power, Normal Operat'ing Pressure and Temperature. An RC PHP.lA N0 l' SEAL DIFF PRESS LOW, 47019-14, alarm has occurred with the following 1A RxCP conditions:
#1 seal water. outlet temp - 180*F
#1 seal differential press 0 psid
#1 seal water leak-off flow - 2.3 gpm
#2 seal water leak-off flow - 1.4 gph
-#3 seal water leak-off flow - 80 cc/hr Seal Injection water flow - 8 gpm Seal Injection water inlet press - 2265 psig ,
Seal Injection water temperature - 130'F f?' !
'/
Explain your diagnosis of the above indications. , r 49W 4 _ . . - - . . _ _ _ . - _ _ _ - - - _ . - - - - - . - - - - _ - - _ _ _ _ - _ - - - - - _ . - _ - - - - - - - - w
4, .: NBR.0128. 898.0638. Rev. A QUESTION #:. ' 12 POINTS: 2.5
' ANSWERS - 1) Irce::tig:te iha naceihi'it; cf e Teil u//'- - b #1. ;;l diffsientisi
= press"re M:t A nt. ' 5 C ) '-
, Q thJ f
- 2) 3~
. pressure, the diagnosis is a failed. instrument.Sincealli Q. ) 02s).
-ANSWER REF: 1) Operating Procedure A-RC-36C,'Ma1' function of' Reactor Coolant Pump
- 2) System Design Description'. number 36, Reactor Coolant System,
- p. 36-26 '
- 3) Operating. Procedure N-RC-36A, Reactor Coolant PtNp Operation
/
- 4) Alarm Response Sheet 47019-14, RC PMP 1A N0 l' SEAL DIFF PRESS- .
LOW, Rev. 1-11-89 , TIME ELEMENT: 7. minutes LEVEL OF LRN/ TYPE: Evaluation / Essay KNPP OBJ: 003000A3.01J Given an alarm on an RxCP seal parameter, verify adequate seal injection flow to operating RxCPs. l 4 ASSOC. TASK: 0030020101 0000160501 K/A CAT. REF: 003000A3.01 Ability to monitor automatic operation of the RxCP,- including: seal injection flow. 3.8, 3.0 1 l
.NBR.013A1 898.068A Rev. A QUESTION #:- 13 POINTS: 2.5
(' F
. The plant.is at' 100% power, normal' operating' temperature and_ pressure. PRZR Relief Tank Pressure is being maintained at 7 psig by cooldown of the PRT. If-this pressure is caused by leaking PRZR code safety valve PR-3B; 1). What temperature. indicator would be used to verify the leaking valve?
-2) .What temperature value would be expected?
-?~
j' a 9 i
.; v:
. NBR.013Bl 898.0688 Rev. A
- QUESTION #: 13 POINTS: 2.5 ANSWER: ort the plant--
1). computer Temperature and T-437 indicator on ConsoleTIA-437 "C"). (40%) (which (/, reads gu)0)
- 2) Temperature value = 230 + 5'F. (60%) /.h
- ANSWER REF: 1)- N-RC-368, Rev. J, Pressurizer Relief Tank Operatio'n, Step 4.5
- 2) Operations XK100-10, FLOW DIAGRAM REACTOR COOLANT SYSTEM, Rev. AJ1
- 3) ASME Steam Tables g
/
TIME ELEMENT: 8 minutes .
- LEVEL OF LRN/ TYPE: Analysis / Essay KNPP OBJ: ,002000K6.12J Given symptoms of a leaking RCS code safety valve, verify indica-tion of the leaking valve condition.
- ASSOC.' TASK: 0020110101' l
K/A CAT. REF: 002000K6.12 Knowledge of the applicable performance and design attributes of the following RCS' components: RCS code safety valves. 3.0, 3.8 4' e 4 L-
/
NBR.014A 898.009A Rev. A QUESTION #: 14 POINTS: 1.5 At 0900, the plant is operating at e5% Power, Normal Operating Pressure and Normal Operating Temperature. 1 The following plant conditions exist:
- Delta temperature across the main condenser is 27*F
- Both CW pumps are running
- Lake temperature is 65*F and daily average has been steady or increasing over i the last week j
- Outside temperature is 90*F with temperatures of 97 to 99"F predicted for the {
day A maintenance request has been submitted requiring CW pump 1A to be secured and tagged out of service for routine maintenance. ,
~
State whether or not the 1A CW pump should be secured. Explain your reasoning. 1 1 I J l 1
- - ----- a
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' NBR.014B 898.0098 Rev. A L QUESTION #: 14 POINTS: 1.5 ANSWER: a) No.(25%). .
b) . Based on stated conditions, if-1A CW pump is secured, ' con-denser delta temperature will increase.to above 28'F. (75%) ANSWER REF: 1) N-CW-04 rev L, Circulating Water. System, step 4.2.2-TIME ELEMENT: 5 minutes LEVEL OF LRN/ TYPE: Application / Essay KNPP OBJ: 056000K5.07J GivenasetofCWsystemparameters,determinetheChpumplineup. necessary to support power operations.. i'
~
ASSOC. TASK: 0560010101 4 K/A CAT. REF: 056000K5.07 Knowledge of the following theoretical concepts as they apply to the condensate system: Relationship between condenser cir-culating water flow, condenser temperature, and condenser vacuum e - 3.0, 2.8 e I
ps- . ,. \ r-
.)
KNPP SENIOR REACTOR OPERATOR 1(QUALIFICATION EXAMINATION PARTB QUESTION-
SUMMARY
SHEET OPERATORS NAME: DATE ADMINISTERED: PART B EXAM ID#: NBS PART B: LIMITS AND CONTROLS _ / c' QUESTION POINT POINTS QUESTION POINT Pb1NTS . NUMBER VALUE SCORED NUMBER VALUE SCORED
, 1 91 1Q 11- 2d 92 M 12 2J D 2.& 11 21
( 9h 2.& H 13 l l U ' 1.& . Di M 91 M M M l 92 2d 19 23 TOTAL QUESTIONS: M TOTAL POINTS: 22 TOTAL SCORED: CATEGORY SCORE: % ' ALL WORK DONE ON THIS EXAMINATION IS MY OWN. I HAVE NEITHER GIVEN NOR RECEIVED AID. i OPERATORS SIGNATURE: GRADERS NAME (PRINT): GRADERS SIGNATURE:
)
1 k
KNPP REQUALIFICATION EXAMINATION PART "B" ^ GUIDELINES
- 1. -Use bisek ink or dark pencil ONLY to facilitate legible reproductions.
- 2. Print your name in the blank provided on the cover sheet of the examination.
- 3. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed.
- 4. ' Fill in the date on the cover sheet of the examination, if necessary.
- 5. Answer each question on the examination. If additional paperfis required, use only the lined paper provided by the examiner. .
- 6. Use abbreviations'enly if they are commonly used in facility literature.
- 7. The point value for each question is indicated above each question.
- 8. Show all calculations, methods or assumptions used to obtain an answer to a mathematical problem, whether asked for in the question or not.
{ 9. Unless solicited, the location of references need not be stated.
- 10. Nrtial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION r.ND DO NOT LEAVE ANY ANSWERS BLANK.
}1. If parts of the examination are not clear ;ith respect to their intent, ask questions of the examiner only. 1
- 12. Rest room trips are to be limited and only one examinee at a time may leave. You must avoid all contact with anyone outside the examination room to avoid even the uppearance or possibility of examination compromise.
j~
- 13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
- 14. This Part "B" examination is designed to take approximately 90 mi.nutes to complete. You will be given two hours to complete this examination.
- 15. Due to the existence of questions that may require all examinees to refer ,
to the same references, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating. I l 16. When you are finished and have turned in your completed examination, leave the' examination area. I
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.NBS.001A 898.001A Rev. A D . .
.: QUESTION #: 01 POINTS: 1.0 Initial Plant Operating Conditions: 98% Power, Normal Operating Pressure, Normal Operating Temperature.-
I
-ICS Pump 1A has been tagged out of service since 0800'this morning. The electrical. maintenance department requests de-energizing and tagging out 480 VAC bus 1-61 for bus maintenance. State whether the tagout should be.
allowed / disallowed.> Explain the basis for your decision. l 0 i 0 4..
FL NBS.001B -- 898.001B Rev. A l
. QUESTION #:. 01- POINTS: 1.0 ANSWER: (1) The tagout should not be' allowed. (20%)
(2) _De-energizing 480 VAC bus 1-61 de-energizes ICS pump 1B and Containment fan coil units IC and 10. (40%) Because 1A ICS pump is out of service, de-energizing bus 1-61 violates the Tech. Spec.~ requirement for two operable containment cooling trains during power operation. (40%)
. ANSWER REF: (1) E240, Circuit Diagram - 4160V and 480V Power Sources (2) Technical Specifications 3.3.c.2, Containment Cooling Systems TIME ELEMENT: 4 minutes t
[ LEVEL OF LRN/ TYPE: Evaluation / Essay , KNPP. OBJ: 026000K3.03J . Given a loss of the ICS system, determine the resulting effects on the requirements for operation of,the containment fan coil units. ASSOC.. TASK: 0260010101 K/A CAT. REF: 026000K3.03. Knowledge of the effect that a loss of the ICS system will have on the following: Containment fan coil units 3.2, 3.0
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,NBS.002A 898.005A Rev. A I
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? : QUESTION #: 02 POINTS: 2.0 During power operations at 801, power with the~ control rods in AUTO, a control
.- , rod in Control' Bank D dropped. The reactor did NOT trip. -
l.. What is- the'imediate operator action (s) and what is the.. basis for the action (s)? p a r f 0$
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i N85.0028 898.005B Rev. A r QUESTION #: 02' POINTS: 2.0
' ANSWER: Reduce ' reactor power- to less than 50% power. (25%)
Reducing power below 50% increases the margin to core peaking factors (37.5%) and insures adequate shutdown margin. (37.5%)
' ANSWER REF: 1) . Technical Specification 3.10.e.2
- 2) E-CRD-49C, Dropped Rod, Rev F, step 3.2.3 TIME ELEMENT: 5 minutes LEVEL OF LRN/ TYPE: . Evaluation / Essay 000003EK3.04J .;
KNPP OBJ:
/
Given a' dropped control rod event, evaluate the effectiveness of . the imediate actions stated in Operating Procedure E-CRD-49C: ' DROPPED ROD. ASSOC. TASK: 0000030501
'K/A CAT. REF: 000003EK3.04 9- - Knowledge of the bases or reasons for.the following: Actions .(. contained in E0P for dropped control rod 3.4, 3.8' e
e
NBS.003A 898.085A Rev. A-J .. QUESTION #: 03-. POINTS: 2.0
. Plant Operating. Conditions: Plant Startup in progress at step 4.6.of procedure .i N-0-01.
Maintenance department wants to tag out 480 VAC bus 1-32 for 24 hours to perform maintenance. Explain why this should not be done at this time, i
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,j '- 'I NBS.003B 89B.0858. Rev. A QUESTION #: 03 POINTS: 2.0 (5)
ANSWER: De-energizing bus 1-32 will de-energize MCC 1-32E^which is thepowersupplyforRxCP1Aoilliftpump.(50%)(.9TheRxCP-(l. cannot be started without the oil lift pump running. (SE) Iktyd : C Hf '2. A AJ f.w.18 h m,t-IE PM<d b .0)
. ANSWER;REF: 1) Operating Procedure N-RC-36A, Reactor Coolant Pump Operation, Step 3.4
- 2) Operating Proc'edure N-0-01, Plant Startup from Cold Shutdown Condition to Hot Shutdown Condition, Step 4.6
~
- 3) Electrical Cross Reference, Rev. 10-17-88, 480V,MCC-
- 4) Motor List, Rev. 8-31-84 /
- 5) Mcc %K ,[
TIME ELEMENT: 6 minutes LEVEL OF LRN/ TYPE: Evaluation / Essay- [ KNPP OBJ: 003000K2.01J Given a plant electrical lineup, determine the ability to operate the Reactor Coolant Pumps. ASSOC. TASK: 0030010101 0030020101 0000160501 l K/A CAT. REF: 003000K2.01 Knowledge of bus power supplies to the following: RxCP. 3.4. 3.3 4
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N85.004A- ..898,030A1 Rev. A
"' POINTS:. 2.0
- 1. QUESTION #5-04
.o
.With<the plant in' cold shutdown, electrical power is lostIto both'DC buses,-
BRA-102 and BRB-102;;for approximately 30 seconds.
. Explain why personnel assembly is or is'not required.. = .
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' NBS.004B 89B.0308 Rev. A l'
l- . QUESTION #: -04 POINTS: 2.0 i- ANSWER: Loss of both DC buses for less than 15 minutes is classified H as an Alert:- (75%) Therefore, assembly is required..(25%) ANSWER REF: 1) EP-AD-2, Emergency Class Determination-l l
- 2) EP-AD-4, Alert, Site Emergency, and General Dnergency TIME ELEMENT: 5 minutes
- LEVEL OF LRN/ TYPE: Application / Essay ,).
KNPP OBJ: 000058G1J / Given a loss of DC power, determino plant personnel notification- ', and assembly requirements.
. ASSOC. TASK: 0000580501 K/A CAf. REF: 000058G1
( Knowledge of system criteria which require notification of plant personnel 4.0/3.7 4
. - _ . ._ ._____-____---_____-_a
'NBS.005A- B9B.036A Rev. A-QUESTION #: 05 POINTS: 3.0
-The plant is cooling down following a LOCA. The RCS is at 300*F and 100 psig.
You are directed to perform A-RHR-348. Residual Heat Removal Split-Train Mode, to continue cooldown. Explain why the annunciators listed below are in the indicated state during the performance of A-RHR-34B: a) RHR IMPROPER LINEUP (47023-31) -- extinguished b)_ RHR PUNP 1A PRESSURE HIGH (47023-4.?) -- illuminated c) RHR PUMP IB PRESSURE HIGH (47023-44) -- extinguished d) RHR LOOP RC FLOW LOW-(47023 45) -- extinguished , F u o i l ' i, I
NBS.0058- -89B.036B- Rev. A J QUESTION #: .0'5 POINTS: 3.0
.IANSWERi ' a) .RHR IMPROPER LINEUP (47023-31) -- this alarm cleared with RCS pressu less than 450 psig because RHR 1A, 1B, 2A and 2B are og i (for split train operation). (25%).
b)' RHR PUMP 1A PRESSURE HIGH (47023-43 -- When this pump is aligned to the RCS and restarted, its discharge pressure
< will be greater than 210 psig to illuminate the alarm (25%)
c) RHR PUMP IB PRESSURE HIGH (47023-44).-- This pump discharge pressure will stay below 210 psig because its suction is from the RWST to extinguish the alarm (25%) d) RHR LOOP RC FLOW LOW (47023-45)
- 1) Depending.on the size of the break, the injiction flow rate may be less than 1250, so the alann may be initiated during the injection phase. ..
- 2) This alarm will reset when pump 1A is started and flow is established through RHR-101/CV-31116
-- either answer (25%)
e ' ANSWER.REF: 1) A-RHR-348, Residual Heat Removal Split-Train Mode 2). N-RHR-34-CL Rev R,, Residual Heat Removal Prestartup' Checklist
- 3) 47023-31, 43, 44, 45, Alarm Response Sheets
- 4) E2036, Integrated Logic Diagram - Residual Heat Removal System
- 5) E2032, Integrated Logic Diagram - Safety Injection System TIME ELEMENT: 8 minutes LEVEL OF LRN/ TYPE: Analysis / Essay KNPP OBJ: 005000K1.06J -
Given a cooldown in progress following LOCA, compare decay heat removal flow path to the low' head safety injection flow path. ASSOC. TASK: 0050030101 K/A CAT. REF: 005000K1.06 { Knowledge of the physical connections and/or cause-effect rela- ! [ tionships between the RHRS and the following systems: ECCS (SI/RHR) 3.0, 4.3
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. NBS.006A 898.040A Rev. A 1
~ QUESTION #: 06 POINTS: '3.0 Plant Operating Conditions: 100% power, Normal Operating Pressure and Temperature. The following valves are DANGER tagged under-various tagouts:.
SA 2D,' Air Compressor ID Air Receiver Outlet - SHUT SW 18510, Air Compressor 10 Service Water Inlet - SHUT FW 100 A, FW Recirc to Condenser 1A - SHUT SW 4A,-Turbine Building SW Supply and Isolation' Valve - SHUT SD 2A, Main Steam Controlled Relief Valve Isolation - SHUT The Maintenance Lead Man requests that SW pump 182 be secured for reintenance. Evaluate the request based on procedural. compliance, identify whether the 182 SW pump should or should not be secured for maintenance, and explain your reasoning, r0-oO a k l
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,. - NSS.006B 898.040B Rev. A
.;3 ,
u QUESTION #: -06 POINTS: 3.0
. L-
! ANSWER:' 'SW pump 182 cannot be secured because it would render train "B" ! -inoperable due to the fact that train "A" service water supply valve ~is danger tagged shut. ANSWER REF: 1) N-SW-02, Service Water System, Step 2.4.2
- 2) . Tech Spec 3.3.e.2, Service Water System
- 3) Operations-M202, Rev. BE, Flow Diagram Service Water System, Sheet 1 _7
- 4) Operations-M210, Rev. T, Flow Diagram Turbine 'bil Purification ,
- 5) Operations-M208, Rev. AS, Flow Diagram Fire Protection System
- 6) Operations-M204, Rev. GM, How Diagram Condensate and Gland Seal System TIME ELEMENT: 8 minutes LEVEL OF LRN/ TYPE: Evaluation / Essay
. KNPP OBJ: 076000G13J For a given.SW system evolution, apply the appropriate plant procedure (s) to' ensure the evolution complies with procedural guidelines.
ASSOC. TASK: 0760010101 0760050101 K/A CAT. REF: 076000G13 Ability to perform (use) specific system and integrated plant procedures during all modes of operation 4.3, 3.7 4
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. NBS.007A_ 898.041A Rev. A QUESTION #: 07 POINTS: 3.0'
~
Initial Plant Conditions: 100% power, Normal Operating Pressure and Temperature
~SW header pressure: 84 psig, PI-41503 and PI-41506 SW Preferred Selector Switch ES-46523 in 1A position SW pumps ~1A1 and 1A2 running N SW pumps 181 and 1B2 in AUTO and not running Annunciator 47002-15, SW PUMP BEARING SEAL WTR FLOW LOW, is actuated.
Investigation. identifies the source of the alarm as FS-16809. Shortly after, SW header pressure decreases from 84 psig to 80 psig due to increased cooling demand. W;iich SW pumps should be running following the SW header pressure transient? s~ Explain. fr f 9 4
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NBS.0078 89B.041B Rev. A QUESTION #: 07' POINTS: 3.0 ANSWER: 1) SW pumps 1A1 and 1A2 should be running. (40%) i
- 2) SW header pressure of 80 psig will provide a start signal to SW pump 181 at 82 psig. (30%)
The auto start of SW pump 181 will be blocked by the "BRG Seal Water Flow Low" start permissive on SW pump 1B1. (30%) ANSWER REF: 1) Operating Procedure E-SW-02, Low Service Water Pressure, Step 3.1.1
- 2) Alarm Response Sheet 47002-1S, SW PUMP BRG SEAL RTR FLOW LOW
- 3) E-1630, Integrated Logic Diagram, Service Water System
~
- 4) Operating Procedure N-SW-02, Rev. H, Service Water System TIME ELEMENT: 9 minutes LEVEL OF LRN/ TYPE: Evaluation / Essay
(. KNPP OBJ: 076000K4.02J Given a set of SW system initial conditions, predict the resulting SW system status. ASSOC. TASK: 0760040101 0760050101 K/A CAT. REF: 076000K4.02 Knowledge of the SWS design feature and/or interlock which provi-des for the auto start features of the SW Pumps 3.2, 3.3 .. . - - _ . . _ - _ _ _ _ . _ - - - - - . _ _ _ . - - . - . - _ - _ _ - - - - - - . - - - _ - A
'NBS.008A 898.043A Rev. A.
QUESTION #: '. 08 POINTS: 2.0 A reactor trip and SI have occurred. When Step 22 of E-0, Reactor Trip or Safety injection is performed, it is discovered that IA S/G pressure is
. decreasing in an uncontrolled manner. Subsequent actions require verifying shut or. shutting the MSIV(s).
State two (2) reasons or basis for verifying shut or shutting the HSIV(s)? y? ed
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NBS.008B 898.0438 Rev. A I QUESTION #: 08 POINTS: 2.0 ANSWER: 1)L An attempt to isolate the leak. (50%)
- 2) To isolate the S/Gs from each other: (50%) l l
.j ANSWER REF: 1) IPEOP' Background Documents. Vol. I, E'-2, Faulted Steam- -{
Generator Isolation, Rev. 7-31 ] t i TIME ELEMENT: 6 minutes LEVEL OF LRN/ TYPE: Analysis / Essay jp .- KNPP OBJ: 000011EK3.01J / Given plant conditions involving a faulted' steam generator (s), ,, determine the reasons for-verifying shut / shutting the MSIVs. ASSOC. TASK: 0000110501 K/A CAT. REF: 000011EK3.01 f Knowledge of the bases or reasons for the following: Verifying
-i the main steam isolation valve position 3.2, 3.8 I e.
n' j i ? ( _. _ _ . _ _ _ _ . . . . _ _ _ . . . _ _ _ _ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ J
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NBS.009A' 89B.044A Rev. A'
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- QUESTION #:. 09 POINTS: 2.5-
-j.
- 6 Plant Operating. Conditions: 100%' power, Normal Operating Pressure and
. Temperature-
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A "SW PUMP BRG SEAL WTR FLOW LOW" 47002-15 ' alarm is ' received,--followed by a' reactor trip and SI actuat. ion.
--1). What service water pumps should be operating and why?
2): What'sNoul'dbetheresultingstatusofthecross-connectionbetween'SW . . trains "A" and "B"? Explain.- f . T
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NBS.009B: 898.044B Rev. A c
~ QUESTION #:. 09 POINTS: 2.S
. ANSWER: 1) 'All four SW pumps should be running due to auto start signal from the SI.. The bearing. water low flow SW pump' start inhi-o bit is bypassed by an SI actuation.
'2) SW trains "A" and "B" should no longer be cross-connected due to the SI auto closure of the SW cross-connect valves.
ANSWER REF: 1) E-1630. Integrated Logic Diagram, Service Water System, Rev.'J TIME ELEMENT: 7 minutes g" # e LEVEL-0F:LRN/ TYPE: Application / Essay ; q KNPP OBJ: 076000A3.02J Given plant _ conditions resulting in an automatic signal to the service water (SW) system, predict the final SW system lineup. ASSOC. TASK: 0760040101
, 0760070101
(-~ K/A CAT.'REF: 076000A3.02 Ability to monitor automatic operation of the SW with respect to emergency heat' loads 3.6, 3.7
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NBS.010A 898.058A Rev. A QUESTION #: 10 POINTS: 2.5 Plant Conditions: Plant cooldown to cold shutdown in progress Tave = 380'F RCS Presscre = 1800 psig-SI actuation manually blocked in the control room Annunciator 47024-13, CONTAINMD4T HI PRESS SI CHANNEL ALERT, is received. Containment pressure is verif d to be 4.5 psig. What will be the response of the Safety Injection System? Explain.
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NBO.0108- 898.058B Rev. A QUESTICN#: 10 POINTS: 2.5 g ANSWER: SI w111' actuate. . SI actuation upon containment pressure channels greater than the actuation setpoint-is NOT blocked by the SI manual block switch. Under the given conditions, SI will have already acteated. p ANSWER REF: 1) Operator Training Manual, Rev 8403, p. IV-11.13, IV-12.19 and IV-12.20-
- 2) System Design Description 33, Rev. O, Safety Injection '
System, p. 33-16 7
- 3) X-K100-150, Rev. 5, Logic Diagrams - Safeguards Actuation Signals _
TIME ELEMENT:. 6 minutes IFYCL OF LRN/ TYPE: Evaluation / Essay l (m KNPP OBJ: 013000K4.01J Given plant conditions requiring SI, determine the necessity for actuation / reset of SI. ASSOC. TASK: 0130030101 K/A CAT. REF: 013000K4.01 Knowledge of ESFAS design feature (s) and/or interlock (s) which provide for the following: SI reset / actuation 3.8, 4.5 i l l w \
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. 898.062A' Rev. A
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# l NBS.011A.L:
QUESTION #: 11' POINTS: 2.5 l; ' ; Plant. Operating Conditions: 100% Power, Normal Operating Pressure and M Temperature. Plant power is lowered to 50% at a nonnal rate. What, if any, are the CVCS-
' charging:and letdown flow automatic responses to the resulting PRZR level change'._ Explain.-
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' NBS.0I' 1B . 898.062B' Rev.'A' QUESTION #: 11= POINTS: 2.5
. ANSWER: 1) 'There should' not be any cha'nges to CVCS charging or letdown flow rates. (40%)
- 2) The PRZR level control system is designed with a prcgram level setpoint based on Tave.(30%) The decrease in'PRZR.
level would be compensated for by the Tave decrease ano no level error signal would be generated.(30%) .In this case, charging'and letdown flow would remain constant by design. ANSWER REF: .1) System Design Description number 36, Reactor Coolant System,
- p. 36-45..WPS-RC21, 22
- 2) System Design Description number 35. Chemical and,, Volume
. Control System, p. 35-28 # '
3)~ Operating Procedure N-CVC-35B, Charging and Volume Control .
- 4) Operator Training Manual, Rev. 8403, PRZR Level Control System, p. IV-7.5 TIME ELEMENT: 6 minutes
. (~ -LEVEL OF LRN/ TYPE: Application / Essay KNPP OBJ'. 004000K1.01J Given a change in PRZR level, predict the response of the CVCS.
ASSOC. TASK: 0040010101 K/A CAT. REF: 004000K1.01 Knowledge of the physical connections and/or cause-effect rela-tionships between the CVCS and the following systems: PRZR level control. 4.2, 4.3 Old O uk k vir suthh h ' 4 Tag is relud, cmsunts Iu l E li be sl4db @c km3 so cluap3 E(l k olwd (24 ). As jul 4 Ses kb tm;* , CL*fiS dill h hm64 (2o9.) . 6pL/( l le4( .40 54&l 6 <d poo;% lal, S/ cyg ~;l/ refer,- is ib or'vpM vdwt bcM 4 V'--_________.--_.____
NBS.012A -89B.063A Rev. A
. QUESTION #: 12 POINTS: 2.5 Plant Operating Conditions: 100% Power, Normal Operating Pressure and Temperature.-
An RC PHP 1A NO 1 SEAL DIFF PRESS LOW, 47019-14, alarm has occurred with the
.following 1A RxCP conditions:
#1 seal water outlet temp - 180'F
#1 seal differential press - O psid
#1 seal water-leak-off flow - 2.3 gpm
#2 seal water leak-off flow - 1.4 gph l #3 seal water leak-cfi flow - 80 cc/hr Seai Injection water flow - 8 gpm Seal Injection water inlet press - 2265 psig A Seal Injection water temperature - 130*F
/
Explain your diagnosis of the above indications. -
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~ N85.0128 898.063B Rev. A J
QUESTION #: 12 POINTS: 2.5 4 ANSWER: 1) In ativoie th; p;;;ibility cf a fciled #13Ea1 dif fereniiai ~ j pr;;;;r; ir,stra ,;nt. '50%) ]
- 2) Since a11' indications are normal except #1 seal differential l '
pressure,4the diagnosis is a failed instrument.4 (%'4)- O,2% , 039 ANSWER REF: 1) Operating Procedure A-RC-36C, Malfunction of Reactor Coolant Pump
- 2) System Design Description number 36, Reactor Coolant System,
- p. 36-26
~
- 3) Operating Procedure N-RC-36A, Reactor Coolant P.dmp 0peration
/
- 4) Alarm Response Sheet 47019-14 RC'PMP 1A N0 l' SEAL OIFF PRESS _
LOW, Rev. 1-11-89 - TIME ELEMENT: 7 minutes LEVEL OF LRN/ TYPE: Evaluation / Essay j ( KNPP OBJ: 003000A3.01J Given an alarm on an RxCP seal parameter, verify adequate seal injection flow to operating RxCPs. ASSOC. TASK: 0030020101 0000160S01 K/A CAT. REF: 003000A3.01 Ability to monitor automatic operation of the RxCP, including: seal injection flow. 3.8, 3.0 1 W :_ _ -_ - . _ _ _ _ _
- NBS.013A 898.068A Rev. A POINTS: 2.5 QUESTION #: -13 The plant is at 100% power, normal operating temperature and pressure. PRZR Relief Tank Pressure is being maintained at 7 psig by cooldown of the PRT. If this pressure is caused by leaking PRZR code safety valve PR-3B;
- 1). What temperature indicator kJuid D* used to verify the leaking Valve?
- 2) What temperatur. value would be expecte??
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l . .1,4 g NBS.0138 898.068B Rev. A 1 y i ~ QUESTION #: 13 POINTS: 2.S l, ANSWER: 1) Temperature indicator TIA-437 (which reads out on the plant ~ computer and T-437 on Console "C"). (40%)
- 2) Temperature value = 230 1 5'F. (60%)
ANSWER REF: 1) N-RC-36B, Rev. J, Pressurizer Relief Tank Operation, Step 4.5
- 2) Operations XK100-10, FLOW DIAGRAM REACTOR COOLANT SYSTEM, Rev. AJ1
- 3) ASME Steam Tables s.
f-l TIME ELEMENT: 8 minutes. . LEVEL OF LRN/ TYPE: Analysis / Essay KNPP.0BJ: 002000K6.12J Given symptoms of a leaking RCS code safety valve, verify indica-tion of the leaking valve condition. l-( ASSOC. TASK: 0020110101 K/A CAT. REF: 002000K6.12 Knowledge of the applicable perfonnance and design attributes of the following RCS components: RCS code safety valves. 3.0, 3.8 I
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. NBS.014A- 898.009A Rev. A
' QUESTION #: 14- POINTS: 1.5 At 0900,: the plant is operating.at -85% Power, Nonnal Operating Pressure and Nonnal Operating Temperature.
' The following plant conditions exist:
L-Delta temperature across the main condenser is 27'F
- Both'CW pumps ate running
- Lake temperature is 65'F and daily average has been steady or increasing over
'the last week
- Outside temperature is 90*F with temperatures of 97 to 99*F predicted for the day A maintenance request has been submitted requir'ng CW pump 1A to be secured and tagged out of service for routine maintenance. ,, ;.
Should you allow CW pump-1A to be secured? Explain. r e
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~NBS.0148 89B.009B Rev. A i
!- 14 POINTS: 1.5 QUESTION #: ANSWER: a) No (25%) b)' Based on stated conditions, if IA CW pump is secured, con-denser delta temperature will increase to above 28'F. (75%) ANSWER REF: 1) N-CW-04 rey L Circulating Water System, step 4.2.2 TIME ELEMENT: 5 minutes LEVEL OF LRN/ TYPE: Application / Essay KNPP OBJ: 056000K5.07J GivenasetofCWsystemparameters,determinetheCNpumplineup necessary to support power operations. / ASSOC. TASK: 0560010101 , K/A CAT. REF: 056000K5.07 Knowlerige of the following theoretical concepts as they apply to the condensate system: Relationship between condenser cir-culating water flow, condenser temperature, and condenser vacuum 3.0', 2.8 4 f iI
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