IR 05000213/1989003
| ML20245D442 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/16/1989 |
| From: | Briggs L, Eaton R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20245D401 | List: |
| References | |
| 50-213-89-03OL, 50-213-89-3OL, NUDOCS 8906270112 | |
| Download: ML20245D442 (106) | |
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l i l i U.S. 110 CLEAR TORY COMMISSION I OPERATOR LICENSIllG EXAMINATION REPORT l i
J EXAMIllATION REPORT N G-213/89-03(OL) FACILITY DOCKET N FACILITY LICENSE N DPR-61 LICENSEE: Connecticut Yankee Atomic Power Company P. O. Box 270 ) Hartford, Connecticut 06101 FACILITY: Connecticut Yankee 1 l EXAlilNATION DATES: April 3 through 7, 1989 ) l J CHIEF EXAMINER: g#f/[ w h #[gf Lhrfy py Briggs ' Date SeniorOperationsEn// gineer i, APPROVED BY: M ERohild B. Eaton, Chief
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'Dat'e 4 PWR Section, Operations Branch, DRS- i
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l SUMMARY: Written and operating examinations were administered to eight Reactor Operator (RO) and two Senior Reactor Operator (SRO) candidates. All
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candidates successfully completed both the written and operating parts of their respective examinations, with.the exception of one (1) R0 applicant wh failed the operating portion of his examination. Seven R0 licenses and two SRO licenses were issue ' i
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l 8906270122 890616 GDR ADOCK 05000213 \ PDC ]
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i DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS: l RO l SRO I l l Pass / Fail l Pass / Fail i l I l I I I l Written l 8/0 l '2 / 0 l
l l I I . I l Operating l 7/1 l 2/0 l
i i l I I l Overall l 7/1 l 2/0 l
l CHIEF EXAMINER AT SITE: L. E. Briggs, USNRC OTHER EXAMINERS: B. S. Norris, USNRC F. P. Bonnett, USNRC E. L. Benjamin, PNL R. W. Vinther, PN K. Faris, PNL N. C. Jensen, INEL B. Picker, INEL 2.0 PRE-EXAMINATION REVIEW Prior to the administration of the Senior Reactor Operator (SRO) and the Reactor Operator (RO) written examinations, three (3) Connecticut Yankee staf f members, all under security agreement, reviewed the examinations at our office in King of Prussia, Pennsylvania on March 28, 1989. This review was performed to ensure that the examination to be administered was content valid and performance base All simulator scenarios were reviewed and exercised by the NRC on the Connecticut Yankee simulator prior to their use with the assistance of two (2) facility instructors, both of which were under security agreement .0 GENERIC DEFICIENCIES A generic deficiency is defined as: at least half of the candidates missed at least half of the credit for that are Two generic deficiencies were identified, one (1) during the facility walkthrough and one during the grading of the written tes _ _ _ _ - - _ _ _ - _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - . . _ _ . - _ -___
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. During the operating test walkthrough all candidates that attempted to use the Maintenance Tagging Clearance (MTC) system were' unable to obtain the~ requested tagging / clearance.informatio On the written-test, none.of the R0 candidates correctly answered a-question concerning the facility administrative quarterly exposure limi CHANGES MADE DURING GRADING There were several changes made during the grading of the written examination. Changes made were minor in nature and are identified on Attachments 1 and 2 of this. repor .0 EXIT MEETING (April 7,19891 NRC Personnel:
F. P. Bonnett - Operations Engineer, Region I L. E. Briggs - Senior Operations Engineer, Region I B. S. Norris - Senior Operations Engineer, Region I Facility Personnel: M. F. Bray - Assistant Supervisor Operator Training, CY R. Heidecker - CY Training Supervisor D. B. Miller Jr. - CY Station Superintendent B. W. Ruth - Manager, Operator Training SUMMARY OF COMMENTS MADE AT THE EXIT MEETING Operational Weakness The generic deficiency noted on the operating examination (paragraph 3.a.) was discussed with the licensee's representative Operational Strengths Communications between. crew members during simulator scenarios were very good, ' Almost all candidates displayed an excellent knowledge of equipment location and operation outside the control room and of the panels within the control room. The licensee noted that plant familiarity was probably due to the candidates' experience as non-licensed Equipment Operator _ _ __-_ _ __ ___ - --__ - _ -
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General Concerns l . The examiners noted du_ ring the control' room tours that Operator Aids were being used on the annunciator windows to identify alarm setpoints. The tags were.made from wire marker. tapes and did not appear to be controlled by procedure. .It was also noted that Dymo Tape was installed on switch handles.to identify control board switches. The.Dymo~ Tape identification duplicated the permanently-installed Bakelite. identification tags. The Dymo Tape had been use~d l prior to the permanent identification tag installation. The Station i Superintendent stated that this use of operator aids would be evaluated and correcte Several exsminers'noted.that housekeeping in some less frequented areas of the plant was not being maintained. Areas of concern were identified during the exit meetin The NRC noted that a considerable delay was experienced by several of the examiners on April 3 due to the' cumbersome security system in effect at the facility. All requested' clearance material had been sent to the facility prior to the examination by the chief examine In addition, the facility training supervisor had made extensive preparation with security personnel during the week prior to the arrival of the examination team and had been assured that there would not be any problem with site access. The access difficulties were somewhat mitigated by the facility on April 5 and 6 for the actual on-site examination by assigning a security guard to.each of the candidates being examine The NRC noted the following discrepancies in the examination material supplied for both the written and operating examination preparatio * Normal Operating Procedures were not sent in the original shipment of examination reference materia * Simulator.1/0 override was not provided (one is in preparation by the licensee).
- Simulator cause and effect manual in original shipment was a copy
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of such poor quality that it could not be rea * The ~ original shipment of reference material to PNL (the contractor writing.the test) in Washington State took.well over one (1) week to arriv Subsequent materials sent to address the above concerns were shipped via a more expeditious carrie ! The NRC stated that poor quality reference materials and long shipping - ! delays during future examinations may result in a delay of the scheduled examinatio ,
Attachments:
i' 1. R0 Master Written Examination and Answer Key 2. SRO Master Written Examination and Answer Key
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Mper - ]] . U. S. NUCLEAR REGULATORY COMISSION
' REACTOR OPERATOR LICENSE EXAMINATION I REGION 1 l FACILITY: Haddam Neck )
REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 89/04/03' INSTRUCTIONS TO CANDIDATE: Use separate paper.for the answers. Write ~ answers on one side onl Staple question sheet on top of the answer sheets. Points'for each question are indicated in parentheses after the question. The. passing-grade requires at least 70%.in each category and a final grade of a least 80%. Examination papers will be picked' up six (6) hours after the examination start I
% OF ;
CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 2 .00 4&M REACTOR PRINCfPLES (7%) THERM 0DYNAMIf.S (7%) AND , COMPONENTS (11%)-(FUNDAMENTALS EXAM) j 1 sc ' 27.IMr N EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%) H. ti 48.00 J&O& PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%) 10kO' % TOTALS FINAL GRADE All work done on this examination is my ow I have neither given nor received ai Candidate's Signature y pg h MM NN ' 8-ATTACHf1ENT 1
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' . l REACTOR PRINCIPLES (7%) THERMODYNAMICS Page -2 C (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
i QUESTION 1.01 (2.00) i STATE FIVE (5) factors which affect reactivity and are considered in an ECP (estimated critical position) calculatio (2.0) l
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1.01 i ANSWER (2.00) xenon . boron Tavg ' -
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g; ( T;.p A,, l} ./ n -f
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(n E 4t) i control rods : fuel burnup ' samarium 1 Any five (5) [+0.4] each; max. [+2.0]
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REFERENCE Conn Yankee: Engineering Procedure, ENG 1.7-5 ;
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192008K101 ..(KA's) )
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QUESTION 1.02 (1.00) During a reactor startup from an initial Keff of 0.88, the first reactivity addition caused count rate to increase from 10 counts per second to 15 counts per second. The second reactivity addition , caused count rate to increase from 15 counts per second to 30 counts per secon WHICH ONE (1) of the following statements BEST describe the relationship between the first and second reactivity additions? (1.0)
(a.) The first reactivity addition was the larger of the tw (b.) The second reactivity addition was the larger of the tw (c.) The first and second reactivity additions were equa (d.) There is not enough data to determine the relationship.
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_(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) l l l ANSWER 1.02 (1.00) J R , Jo [ [+1.0] REFERENCE Conn Yankee: CY-0P-RXTH-L35003, p. K104 ..(KA's) i QUESTION 1.03 (1.00) In the event of a rod ejection a
REGION I l
. FACILITY: Haddam Neck
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REACTORLTYPE: PWR-WEC4 ;
DATE ADMINISTERED: 89/04/03 1 INSTRUCTIONS TO CANDIDATE: . Use separate ' paper for the answers. Write answers on one side onl Staple question sheet on top of the answer sheets.- Points for each question are indicated in parentheses af ter the question. 'The passing grade requires at least 70% in each category and a final . grade of at least 80%. Examination papers will be picked up six (6) hours after the examination start I
% OF CATEGORY % OF CANDIDATE'S CATEGORY SCORE VALUE CATEGORY VALUE- TOTAL 24.00 24.00 4. REACTORPRINCIPLES'(7%) -^
THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 33.00 33.00 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%) 43.00 43.00 PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%) 10 % TOTALS FlfiAL GRADE I All work done on this examination is my. ow I have neither given -
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' ATTACHMENT 2- ! REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 2 , (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
. QUESTION 4.01 (2.00) A reactor trip was initiated due to a feedline ruptur Feedwater loss is occurring at greater amounts than the feedwater pumps can replace. Isolation of the feedline is not possibl At WHAT point will the feedwater rupture eventually become a steam rupture?- (1.0) HOW and WHY will this affect core reactivity? (1.0) ANSWER 4.01 (2.00) When the steam generator level drops below the feed ring (steam escapes through the feedline and out the feedline rupture). [+1.0] The excessive steam flow will result in a positive reactivity addition [+0.5] due to the cooldown of the primary coolant. system (s) [+0.5]. REFERENCE Conn Yankee: Heat Transfer Thermodynamics and Fluid Flow Fundamentals, p. 18 . Conn Yankee: Reactor Plant Information Book, Chapter 2.3,
" Steam Generators," pp. 8- K121 191006K107 ..(KA's)
QUESTION 4.02 (2.00) WHAT is the definition of SHUT 00WN MARGIN per Technical Specification 1.13? (1.0) If the reactor Keff is .9823, WHAT is the shutdown margin? ,1.0)
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(7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
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ANSWER 4.02 (2.00) 4
; Instantaneous amount of reactivity by which the reactor i either is suberitical, or would be subcritical from its present condition [+0.5] assuming all rods are fully inserted [+0.25], except the most reactive rod which is 1 i
assumed to be fully <c
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' SDM =' 1 - Keff)/Keff !
SDM = I .9823)/.9823 i SDM = 1800 PCM (+/- 5 PCM) [+1.0) REFERENCE i Cor.n Yankee: Reactor Theory Lesson Plan, CY-0P-RXTH-L35011, p. ]
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192002K110 ..(KA's) . l i QUESTION 4.03 (1.00) As Keff approaches 1.0, for the same increase in Keff, a greater length of time is required to reach the new equilibrium leve This is characteristic of WHICH ONE (1) of the following? (1.0)
(a.) moderator effects on neutron leakage ] (b.) decreasing population of' delayed neutrons (c.) reactivity change on power increases (d.) the effects of suberitical multiplication i
ANSWER s3 (1.00)
(d.) L+1.0] i L i
! REFERENCE ! 4 Conn Yankee: Reacthity and Reactor Control Training l Manual, Module B, Chapter 2, p. K101 ..(KA's) ! (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) _ _ _ _ -
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QUESTION 4.04 (1.00)
WHICH ONE (1). of the following will make the moderator temperature i coefficient (MTC) LESS NEGATIVE? (1.0) .l (a.) INCREASED moderator density
'(b.) INCREASED control rod insertion (c.) INCREASED reactor power -{
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I ANSWER 4.04 (1.00) !
(d.) [+1.0]
REFERENCE Conn Yankee: Reactor Theory Study Guide, OP-LO-RXTH-4A, l pp. 2 and K101 ..(KA's)
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QUESTION 4.05 (2.50) WHAT are the THREE (3) purposes for using rod insertion ) limits (RILs) as stated in Technical Specification 3.10.2? (1.5) HOW and WHY do RIls vary with an-increase.in re' actor power?. (1.0) l
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REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) f .
ANSWER 4.05 (2.50) I Ensures: accep] l
[t0.5 table power distribution limits are maintained minimum shutdown margin is maintained [+0.5] potential effects of rod misalignment on associated j accident analysis are limited [+0.5] RILs increase with increasing reactor power [+0.5:1 because the power defect increases with increasing power ':+0.5].
REFERENCE Conn Yankee: Technical Specifications Bases, p. 3-17 ! Conn Yankee: Module B, Reactivity and Reactor Control, Chapter 4, " Controlled Reactivity Effects," pp. 44-4 K115 ..(KA's) QUESTION 4.06 (1.50) ASSUME that the RCS pressure is 2000 psig and CVCS letdown flow through the orifice (s) is 80 gpm. CVCS backpressure is 200 psi WHAT will be the letdown flow if RCS pressure drops to 1800 psig?
(SHOW all work) (1.5)
ANSWER 4.06 (1.50) Flow proportional to square root of delta-P [+0.5] (basic formula) 80 gpm proportional to square root 1800 psid x/80 gpm : square root 1600/ square root'1800 x= (80 gpm x square root 1600/ square root 1800 x= 3200/ square root 1800 [+0.5] (work) x=75 [+0.5] (answer)
(accept 74-76gpm) (***** CATEGORY 4 CONTINUE 0 ON NEXT PAGE *****)
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REFERENCE Conn Yankee: Thermodynamics and Heat Transfer (CY-0P-LO-HTFF-L650012) p. 5 193006K105 ..(KA's) QUESTION '4.07 (2.00) WHICH ONE (1) of the following parameters would cause a decrease in the Departure from Nucleate Boiling Ratio? (1.0)
(1.) INCREASE in RCS temperature (2.) INCREASE in RCS letdown (3.) INCREASE in RCS pressure (4.) INCREASE in RCS flow WHAT is the basis for the minimum allowable value for DNBR? (1.0)
ANSWER 4.07 (2.00) (1.) [+1.0] Corresponds to a 95% probability at a 95% confidence level that DNB will not occur. [+1.0] REFERENCE Conn Yankee: Technical Specification, p. 3-31 K110 ..(KA's) QUESTION 4.08 (1.50) The heat flux at a specific point in the reactor is'4'x 10*5 , l BTV/hr-ft*2. The Departure from Nuclear Boiling Ratio (DNBR) is ! WHAT would be the critical heat flux at this location? '
(SHOW all work used to arrive at the answer.) (1.5)
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i ANSWER 4.08 (1.50) ; i DNBR = CH Flux / Actual Flux [+0.5] _ (formula) CHF = (DNBR)(Actual Heat Flux) [+0.5] (work) ' i CHF = (3.0)(4 x 10*5 BTU /hr-ft*2) l CHF = 1.2 x 10*6 BTU /hr-ft*2 [+0.5] (answer) REFERENCE Conn Yankee: Heat Transfer Thermodynamics ano' Fluid Flow Fundamentals, p. 23 K106 ..(KA's) ) l l QUESTION 4.09 (1.50) WHY will Axial Offset (AO) change if reactor power is l reduced from 100% to 50% by borating (no rod motion)? ASSUME ! the reactor is operating at ibm power with all rods out, early in cycle life at equilibrium Xenon conditions when power is ; reduced to 50%. Neglect changes due to Xeno (1.5)
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i ANSWER 4.09 (1.50) Due to the greater decrease in the outlet temperature relative to the decrease of the inlet temperature [+0.75], more positive reactivity will be added in the upper core regions, resulting in a more positive (less negative) A0 [+0.75] REFERENCE Conn Yankee: Reactor Theory Lesson Plan, CY-0P-LO-RXTH-L35010, ; p. 3 ! 193009K107 192008K120 ..(KA's)
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, REACTOR' PRINCIPLES (7%) THERMODYNAMICS Page 8 . (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) .
QUESTION 4.10 (2.00) WHAT THREE (3) general conditions must be present for a brittle fracture to occur? (1.0) HOW do heatup and cooldown rate limits on the reactor coolant system reduce the probability of brittle fracture? (0.5) WHY does the concern about brittle fracture,of the Reactor Pressure Vessel increase as the plant ages?- (0.5) ANSWER 4.10 (2.00) . sufficient stress temperature less than[+0.33] NDT [+0.34] presence of flaw [+0.33] Reduces the thermal stress. (Reduced delta-T across the RV wall reduces thermal / tensile stress.) [+0.5] Accumulative neutron exposure makes the material more brittle. [+0.5] (NDT increases with N exposure) REFERENCE Conn Yankee: Technical Specifications, p. 3- K104 193010K105 ..(KA's) QUESTION 4.11 (1.00) A Centrifugal Charging Pump (CCP) is running with the discharge flow control valve in mid-positio If the discharge valve fails fully open, INDICATE WHICH ONE (1) of the following parameters will decreas (1.0)
(a.) CCP discharge flow (b.) motor amps on CCP (c.) non-regenerative heat exchanger outlet temperature
l (d.) seal injection flow (assume seal injection flow control l valvedoesnotchangeposition)
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(d.) [+1.0]
REFERENCE Conn Yankee: CY PIB, "CVCS," Chapter 4, pp. 71-7 K103 ..(KA's) QUESTION 4.12 (1.00) The RTD on the RCS hot leg fails, sending an erroneous low temperature signal to the T-average circui EXPLAIN what type of RTD failure has occurred and WHY it sends a low temperature signa (1.0) ANSWER 4.12 (1.00) RTD failure due to short circuit [+0.5] will cause a low resistance signal (and a resultant low temperature signal to the T-avg circuit) [+0.5] . REFERENCE Conn Yankee: CY Plant Information Book, Chapter 2.6, "PZR Level", p. . Conn Yankee: Core Mitigation Lesson Plan, " Post Accident Instrumentation," CY-0P-LO-MITCOR-L75004, p.1 K113 ..(KA's) QUESTION 4.13 (1.00) EXPLAIN the difference (s) between a regenerative heat exchanger and a non-regenerative heat exchange (1.0)
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ANSWER 4.13 (1.00) Regenerative heat exchanger uses the same fluid as the cooling fluid and the cooled fluid. [+0.5) In a Non-regenerative heat exchanger, hot fluid is cooled by a cooler fluid supplied by another_ system (where heat is eventually transferred to a sink).
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REFERENCE "f ~ Conn Yankee: Heat Transfer Thermodynamics and Fluid flow Fundamentals, p. 164-16 K107 ..(KA's) QUESTION 4.14 (1.00) WHAT is the principle behind the operation of a Bourdon tube? (1.0) ANSWER 4.14 (1.00) A curved tube used as a pressure sensor [+0.5], it works by deflecting when subjected to a pressure due to the difference in areas between the inside and outside radii [+0.5]. REFERENCE Conn Yankee: Haddam Neck, " Post Accident Instrumentation," Lesson Plan CY-0P-LO-MITCOR-L75004, p. 2 K110 ..(KA's) QUESTION 4.15 (2.00) EXPLAIN HOW and WHY the following occurrences would affect net positive suction head (NPSH) available to the reactor coolant pumps, grid frequency decrease (1.0) pressurizer temperature increase (1.0)
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.. . . REACTOR PRINCIPLES (7%). THERMODYNAMICS- Page 11 . (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) , l ANSWER 4.15 (2.00)
i Increases NPSH [+0.5], because slower pump speed will- J decrease flow / friction / losses [+0.5]. f Increases NPSH [+0.5] due to RCS pressure increase [+0.5]. l l REFERENCE { Conn Yankee: Heat Transfer Thermodynamics and Fluid Flow Fundamentals Manual, p. 32 I 191004K106 191004K115 ..(KA's) l I l QUESTION 4.16 (1.00) , Concerning CVCS demineralizers: WHY is letdown flow limited to approximately 160 gpm? (0.5) HOW are demineralized resins protected from high temperatures in the CVCS? (INCLUDEsetpoint) -(0.5) . y l ANSWER 4.16 (1.00) '! To prevent excessive flow through demineralizers that could .. incur damage. [+0.5] a' 1 .
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If temperature of CVCS letdown increases to 140 degrees"F, then LO-TCV-113A diverts letdown around the demineralizer [+0.5] { REFERENCE Conn Yankee: Plant Information Book, "CVCS," Chapter 4, ' pp. 15, 19, and 3 K109 ..(KA's)
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. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 12 , (33%) -QUESTION 5.01 (1.50) WHICH ONE (1) of the following would be a correct symptom of a feedwater regulating valve failing closed? (1.0) (1) decrease in plant RCS loop Tavg (2) feed flow / steam flow mismatch alarm on affected S/G and low level alarm (3) Alarm for low feedwater pump suction pressure (4) Overpower rod stop occurs If the valve fails to respond properly in either automatic or manual, WHAT operator action (s) should be taken? (0.5)
ANSWER 5.01 (1.50) (2.) [+1.0] trip reactor (and turbine) [+0.5] j REFERENCE Conn Yankee: .T 3.2-18, p. 1- K304 000054A205 ..(KA's) QUESTION 5.02 (1.00) Per E-0, Reactor Trip or Safety Injection, WHICH ONE (1) of the following is a symptom that requires a Safety Injection / Containment Isolation actuation? (1.0)
(a.) pressurizer pressure equal to or less than 1850 psig (b.) containment pressure greater than or equal to 4 psig (c.) pressurizer pressure equal to or less than 1750 psig (d.) containment pressure greater than or equal to 5 psig (***** CATEGORY 5 CONTINUE 0 DN NEXT PAGE *****) -_ _ - - - _____ -_. _ _ _ _ -
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ANSWER 5.02 (1.00) l (d.) [+1.0] REFERENCE Conn Yankee: .E-0, Reactor Trip or Safety injection, A107 ..(KA's) l QUESTIO .03 (2.50) Per E0P 3.1-12, " Emergency Boration", WHAT' are the symptoms i; AND their indications that would necessitate an emergency l boration? (1.5) WHAT are TWO (2) sources from which boric acid could be supplied to the Charging Pump suction on an emergency boration? (1.0) ANSWER 5.03 (2.50) ' . unexplained or uncontrolled positive reactivity insertion [+0.5] as indicated by increasing nuclear flux or startup rate [+0.25'l uncontrolled cooldown ]:+0 5.l as indicated by a decreasingTavg[+0.2 . boric acid mix tank (BAMT) [+0.5] the RWST [+0.5] n,
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t .w ,,:. + s .. MD'd% fr(Cli'Th REFERENCE Conn Yankee: E0P 3.1-12, p. G011 006000K601 ..(KA's)
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QUESTION 5.04 (2.00) ! I WHAT are THREE (3) permissive functions that the turbine first j i stage pressure transmitter (PT 1204).affects in addition . to various meters and recorders? (1.0) -l
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At 85% reactor power, PT 1204 fails causing Tref to indicate
+10 deg F higher: WHAT automatic system response (s)-would occur? (0.5) WHAT operator action (s) should be taken-to control the l system upset?' (0.5)
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I ANSWER 5.04 (2.00) 1 '
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input to P-7 (10%) i f '/ h Au c 0' *" "GM . input to P-2 f,-__p , in
[+0.34]put to P-8 (74%)for one, [+0.33] each for other two rod withdrawal as Tave-Tref is mismatched [+0.5] place rod control in manual [+0.5]
REFERENCE j i Conn Yankee: Malfunction Cause and Effect Malfunction l Rx 1 l Conn Yankee: Annunciator Response Procedure 4.6-23, p. l
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000001K206 '000001A205 ..(KA's) ]
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1 QUESTION 5.05 (3.00). 1 I During reactor operation in Mode 1, component cooling water flow to the RCP bearing oil coolers is lost.' Per A0P 3.2-10, " Loss
.of Component Cooling Water", l l
. WHAT. is .the time limit to restore flow before additional l action is required? (1.0) If that time limit is exceeded, WHAT are the operator actions that must be taken as specified-by AOP 3.2-107 .(2.0)
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ANSWER 5.05 (3.00) i 1 two minutes [+1.0] . trip reactor (refer ic E-0) [+0.5] stop all RCPs [+0.5] isolate letdown and reduce charging to minimum required [+0.5] maintain RCP seal water injection flow [+0.5] l REFERENCE Conn Yankee: AOP 3.2-10, p. K303 000026A206 ..(KA's)
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QUESTION 5.05 (1.50) i A. reactor trip should have occurred but did not. FR-S.1, " Response i to Nuclear Power Generation," reesires the operator to manually trip the reactor. The operator has p:.thed the reactor trip button, bu still no trip has occurred. Per FR-S.1, WHAT actions should be taken at this point? (1.5) ;
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i l ANSWER 5.06 (1.50) i manually insert control rods [+0.5] de-energize 480V buses 4 and 7 [+1.0] (by performing the following:
- de-energize 480V bus supply breakers 4841 and 4971 - check open 480V tie breakers 4TS and 6T7)
REFERENCE Conn Yankee: FR-S.1, pp. I and A112 000029A111 ..(KA's)
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QUESTION 5.07 (2.00) There are four criteria to terminate safety injection flow per E-0, " Reactor Trip or Safety Injection". STATE these FOUR (4) criteri Include applicable setpoints/ trend (2.0) ANSWER 5.07 (2.00) ,
\ RCS subcooling [+0.3] greater than 32 deg F [+0.2] secondary heatsink - total aux feed flow [+0.15] greater than 320 gpm [+0.1] i OR - WR level in at least one SG [+0.15] greater than 63% [40.1] RCS pressure [+0.3] stable or increasing [+0.2] pzr level [+0.3] greater than 10% [+0.2]
REFERENCE Conn Yankee: E-0, Reactor Trip or SI, p. 1 K324 00000BK305 ..(KA's)
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QUESTION 5.08 (1.00) WHICH'ONE (1) of the following describes the correct action to be - I taken if during power. operation more than one rod has dropped
'into the reactor? (1.0) .I (a.) if reactor did not trip, reduce power to less than 50%
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(b.) manually trip the reactor and go to E-0, Reactor Trip or Safety Injection (c.) stabilize Tavg at the present Tref with rod motion f
(d.) check the power range nuclear instruments for quadrant tilts
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ANSWER' 5.08 (1.00)
(b.) [+1.0]
REFERENCE Conn Yankee: AOP 3.2-23, p. K304 ..(KA's) QUESTION 5.09 (1.00) WHAT is the principle reason for verifying that the main turbine governor valve and stop valves are closed after a reactor trip? (1.0) ANSWER 5.09 (1.00) to prevent excessive cooldown of the reactor [+1.0] (by discontinuing a large steam load) REFERENCE
. Conn Yankee: OP-LO-E0P-L30, LO # K103 ..(KA's) ,
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QUESTION 5.10 (0.50) Ouring an emergency situation, WHAT plant procedure is entered based on SR0 judgement to determine or confirm the most appropriate post-accident recovery guideline? (0.5)
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' ANSWER 5.10 (0.50) l ES-0.0, "Rediagnosis" [+0.5] j REFERENCE Conn Yankee: Emergency Response Procedure, ES-0.0,
"Rediagnosi G012 ..(KA's)
QUESTION 5.11 (3.00) a4 WHAT TWO (2) criteria contained in E-2, " Faulted Steam Generator Isolation," are used to identify a faulted steam generator? (1.0) WHAT FOUR (4) criteria contained in E-3, " Steam Generator Tube Rupture," are used to identify a ruptured steam generator? (2.0)
ANSWER 5.11 (3.00) . any SG pressure decreasing in an uncontrolled manner [+0.5] any SG completely depressurized [+0.5] , i unexpected increase in any SG wide range level
- . ;+0.5; high activity from any SG blowdown line sample + 0.5J high radiation from any SG steamline [+0.5] high radiation from any SG blowdown line [+0.5] ;
REFERENCE Conn Yankee: E-2, Faulted SG Isolation, p. . Conn Yankee: E-3, SG Tube Rupture,' p. G010 000038A111 000038A112 ..(KA's)
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QUESTION 5.12 (1.50) . With the fuel transfer gate open and. irradiated fuel out of the reactor vessel, WHAT are FIVE (5) indications that would confirm ] a refueling cavity seal failure has occurred? ..(1.5) ; i I, . ANSWER- 5.12 (1.50) i " Spent Fuel Pit Low Level" alarm "Rx Containment Sump HI-LO Level" alarm rapid increase on containment sump level. recorder "Incore Instrument Sump HI Level" alarm rapid increase on wide range level recorders . decreasing cavity level as indicated on refueling cavity level indicator possible RMS area monitor alarm from containmenthd >' > d. "N
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and/or spent fuel building /: . - '
., "s/^r ,ntv s7n c,>' f f u ;) decreasing cavity level as observed on staff fauge :cf (/< ~
attached to the cavity wall Any five (5) [+0.3] each, +1.5 maximu REFERENCE
' Conn Yankee: E0P-3.1-48, Cavity Seal Failure, G005 ..(KA's)
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t QUESTION 5.13 (2.00) While conducting ES-0.1, " Reactor Trip Response," the RCPs are not running and attempts to start them fail. The procedure instructs-you to open the loop Tc isolation valve, close the loop bypass valve, and verify natural circulation. WHAT are FOUR (4) conditions that .
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i i ANSWER 5.13 (2.00) RCS subcooling based on core exit thermocouple [+0.3] is greater than 32 deg F [+0.2] SG pressures [+0.3] are stable or decreasing [+0.2] i RCS temperature based on core exit thermocouple and averagetemperatureindications[+0.3]isstableor decreasing [+0.2] ' RCS cold leg temperatures [+0.3] are at saturation f ! temperature for SG pressures [+0.2] REFERENCE Conn Yankee: ES-0.1, " Reactor Trip Response," p. 14.
( 000017A121 ..(KA's) , QUESTION 5.14 (2.00) in the event of a complete loss of condenser vacuum a turbine trip and reactor trip occurs. In E0P 3.1-8, " Complete Loss of Condenser i Vacuum", one of the subsequent actions requests you to verify Tave i is reduced to approximately 535 deg f WHAT are THREE (3) methods of reducing Tavg in this situation? (1.5) WHY are steam dumps not an available method? (0.5) , i
ANSWER 5.14 (2.00) , Reduce Tave by: L - opening steam supply to hog jets [+0.5] I - opening atmospheric vents [+0.5:i i
- aux feed pumps to control Tave L+0.5] loss of condenser vacuum blocks the steam dump actuation signal, so steam dumps not available [+0.5]
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. (3 38s) . -REFERENCE . Conn Yankee: E0P 3.1-8, Rev. 6, .
2., 000051K301 ..(KA's) s-QUESTION 5.15 (1.00) WHICH ONE (1) of the following'would be a symptom of' losing . the "A" battery bus"during reactor operation? . (1.0);
; (a.) reactor trip and turbine trip with a loss of secondary side annunciation , (b.) loss of C and D vital inverters (two power range drawers faillow) -(c.) MSIV's close due to loss of power to solenoid valves 1 & 3 (d.) auto auxiliary feed initiates to S/Gs 3 and 4 ANSWER 5.15 (1.00) (c.) [+1.0)
a REFERENCE Conn Yankee: E0P 3.1-49, " Partial Loss of DC," pp. 2 and .
' 000058A203 ..(KA's)
QUESTION 5.16 (2.00) ' If estimated critical position (ECP) predicts criticality ~ below the rod insertion limits, WHAT actions must be'taken? .(1.0)-
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l WHY are these actions necessary? (1.0)'
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l ANSWER 5.16 (2.00) borate _ [+0.5] and calculate new ECP [+0.5] reactor may not be brought critical with rods below RILs [+0.5] to ensure adequate SD margin [+0.5] REFERENCE
! Conn. Yankee: Reactivity Balances and ECP's (CY-0P-LO-RXTH-L35012),
p. 14 of 22 (Lesson Plan).
000024A205 000024K301 ..(KA's)
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QUESTION 5.17 (1.50) l l The following is a list of Emergency Procedures used at ! Connecticut Yankee. COMPLETE the following by indicating the proper order of priority (#1 being the highest priority).
Assume that conditions exist which require use of all procedure (1.5) ECA-0.0, Station Blackout ECA-1.1, Loss of Emergency Recirculation ; FR-C.2, Response to Degraded Core Cooling ; FR-H.1, Response to Loss of Secondary Heat Sink
, FR-Z.1, Response to High Containment Pressure ANSWER 5.17 (1.50)
, '+0.3' ! '+0.3' '+0.3'l '+0.3' '+0.3'.
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REFERENCE Conn Yankee: F-0, Critical Safety Function Status Tree . Conn Yankee: Chapter 3, User _'s. Guide, p.1 G012 000007G012 000055G012 ..(KA's) QUESTION 5.18 .(2.50) Per AOP 3.2-12, " Loss of. Residual Heat Removal (RHR) System," WHAT are FOUR-(4) indications and/or alarms on the Main Control Board which would indicate that the RHR system is not functioning properly? (1.0) Briefly DESCRIBE the flowpath used for decay heat removal given a loss of RHR with the Refueling Cavity full. Assume RHR piping and pumps'are intac (1.5).
ANSWER 5.18 (2.50) . RHR 480V motor trip alarm [' e N/^ loss of amperage indication for the RHR pumps , loss of RHR pump discharge pressure indication r i /m 1' high temperature of RHR return fluctuating amps and discharge pressure indicating :r s ,c,./: M ri pump cavitation " RESIDUAL HEAT REMOVAL LOW FLOW" alarm Any four (4) [+0.25] each, +1.0 maximu open RH-MOV-874 to establish gravity flow from refueling cavity [+0.5) to RWST [+0.25] via the RHR pump and heat exchangers [+0.25'l align LPSI pumps .+0.25] to return RWST water to cavity [+0.25]
(valve #notrequired)
REFERENCE
. Conn Yankee: A0P 3.2-12, Rev. 3, p. 2-3.
( 000025K301 ..(KA's)
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l QUESTION 5.19 (1.50) A fire in the control room necessitates a rapid evacuation. Per AOP 3.2-8, " Plant Operation Outside Control Room," HOW AND WHERE would the reactor and main turbine be tripped? LIST all locations and/or methods. Assume the main control board is not functiona (1.5) ANSWER 5.19 (1.50) Rx trip / turbine trip can be accomplished manually at' head end (front standard) of turbine [+0.5] Reactor can be tripped in switchgear room by manually openin trip breakers [+0.25] or opening breakers on MG sets [+0.25] . 480V bus 4 and 7 rod drive MG set supply breakers [+0.25], open switches on three vital bus inverters [+0.25] REFERENCE Conn Yankee: AOP 3.2-6, p. . Conn Yankee: ADP 3.2-8, p. 1 000068K202 ..(KA's) J i l
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QUESTION 6.01 (1.50) Given the following data concerning the' power-nuclear instruments:- NIS 32 NIS 34 NIS 311 NIS 33
. lower current' reading 53mA 55mA -56mA 54mA lower reference current 106mA' 110mA 112mA 108mA upper current reading 52mA 56mA 58mA 57mA upper reference current 104mA 112mA 112m mA WHAT is the quadrant power tilt ratio (QPTR)? Use attached data sheet if desire (1.5)
I ANSWER- 6.01 (1.50) normalized currents NIS 32 NIS 34 NIS 31 NIS 33 Av upper .5 0.518 0.528 0.511 , lower .5 .5- 0.5' l max upper / avg upper = 1.03 max lower / avg lower = ) QPTR = 1.03
'+0.75' for normalized currents and average current ! '+0.75 for QPTR determination REFERENCE Conn Yankee: SUR 5.3-40 Rev. 7, QPTR Calculation, p. 6. - Conn Yankee: Technical Specifications, 3.17.4, " Quadrant !
Power Tilt Ratio Limits." Conn Yankee: CY-0P-LO-RXTH-L35010, Power tilstribution, L.O. f A104 ..(KA's) -
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I QUESTION 6.02 (1.00)'. COMPLETE the following.~ statement:. 1 The reactor coolant' pump must be idle for minutes before startin '(0.5) ; WHAT is the reason for that limit? (0.5) l
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ANSWER 6.02 (1.00) ] minutes. [+0.5]
. RCPs are not designed for jogging operations. Too frequent' ;
starting may lead to damage of motor winding.. [+0.5]- REFERENCE ]
'i Conn Yankee: Plant Inton stion Book, " Reactor Coolant 1 Pumps," Chapter 2.2, p. 5 . Conn-Yankee: CY-0P-LO-PRISYS-LOO 220, L.0. # J 003000K614 ..(KA's)
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l , QUESTION 6.03 (1.50) On a DECREASING Volume Control Tank (VCT) level, MATCH the percent of level setpoints in. column 1 to the appropriate system responses in column (1.5) ) Column 1 Column 2 % Hi Level Alarm , % Hi Level Alarm reset I
! % Stop Auto Makeup % Start Auto Makeup- % Stop Letdown Diversion WOS Low Level Alarm Auto Shift of Charging Pump Suction to RWST Manual Reset to RWST l
ANSWER 6.03 (1.50) 1 s 4 [+0.3] each .
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REFERENCE
. Conn Yankee: Plant Information Book, Chapter 4, "CVCS," pp. 166-16 K106 006020A304 ..(KA's) ! (***** CATEGORY 6CONTINUEDONNEXTPAGE*****)
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QUESTION 6.04 (1.00) l Per Technical . Specification 3.10.2, all shutdown and control rods shall be operable and positioned within a set number of steps indicated position (RPI) of their bank position. WHICH ONE (1) of the following specifies that limit? (1.0)
(a.) +/- 20 steps from bank position (b.) +/- 22 steps from bank position l (c.) +/-'24 steps from bank position (d.) +/- 26 steps from bank position l
)
ANSWER 6.04 (1.00) f (c.) [+1.0] REFERENCE * i Conn Yankee: Plant Information Book, " Rod Position," Chapter 79, p. 1 . Conn Yankee: Technical Specifications, 3.10.2.1, p. 3-17 A204 ..(KA's) QUESTION 6.05 (1.00) HOW AND by WHAT s
::;echanisms (CRDM)ystem accomplished?is cooling of the control rod drive (1.0)
ANSWER 6.05 (1.00) CRDM cooling fans draw cooled air from the discharge of the CAR ' units cooling [+0.5]
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REFERENCE ! . Conn Yankee: Plant Information Book, Containment Vent," J Chapter 56, p. 2 l
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022000K404 ..(KA's) QUESTION 6.06 (1.50)
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i WHAT automatic actions would occur if, during reactor operation, one of the Bank B control rods drops below 50 steps? (0.5) WHICH ONE (1) of the following is the setpoint for a Tavg-Tref rod stop? (1.0)
(1.) deviation is +/- 10 degrees F or greater (2.) deviation is +/- 15 degrees F or greater j (3.) deviation is +/- 20 degrees F or greater ) (4.) deviation is +/- 25 degrees F or greater
ANSWER 6.06 (1.50)
: Turbine load runback (90%) [+0.5] (2.) [+1.0]
REFERENCE Conn Yankee: Plant Information Book, " Rod Control," p. K407 ..(KA's) , i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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QUESTION 6.07 (3.25)
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The plant is operating at 100% power with all control systems in ' automatic. Feedwater flow channel for #1 steam generator fails high. ASSUME.no operator action.is take EXPLAIN HOW each of the following is INITIALLY affected and WHY that effect occurs.
l feed flow (0.75) S/G 1evel (0.75) l steam flow (0.75) EXPLAIN why the reactor will or will not tri (1.0) l J i ANSWER 6.07 (3.25) .! j . actual feed flow decreases [+0.25] due to main feedwater regulating valve closing in response to the false high ! feed flow signal [+0.5] S/G 1evel decreases [+0.25] due to decreased feedflow
[+0.5] no change [+0.25] due to steam demand at 100Ss power [+0.5] (up until trip) Steam flow / feed flow mismatch does not exist [+1.0] (and S/G 1evel is dominant)
w it t Nor TR ) }7 REFERENCE Conn Yankee: Malfunction Cause and Effect, "RXO9 Feedflow Failure." Conn Yankee: Plant Information Book, "RPS," Chapter 75, p. 5 C.304 039000K108 ..(KA's) QUESTION 6.08 (1.50) WHAT are THREE (3) different signals, other ti'an manual, that will automatically trip a main feedwater pump? Setpoints NOT necessary for full credi (1.5) j
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RESPONSIBILITIES (13%) ANSWER- 6.08 (1.50) low suction pressure bus UV bus overcurrent bus high differential current condensate pump trips Any three [+0.5] each; [+1.5] maximum . REFERENCE Conn Yankee: Plant Information Book, "Feedwater," Chapter 19, pp. 11 & 1 K416 ..(KA's)
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QUESTION _6.09 (1.75) WHAT is the source of suction to the auxiliary feedwater pumps? (0.5) HOW MANY auxiliary feedwater pumps are available and WHAT TYPE of pumps are they? (0.5) To be considered OPERABLE, each AFW pump must attain a minimum rated flow. WHAT is that flow and WHAT is the basis for the minimum flow rate? (0.75) ANSWER 6.09 (1.75) WST (demineralized water storage tank) [+0.5] [+0.25], two (2) turbine driven and one.,(1) motor driven
[+0.25] gpm [+0.25]. 450 gpm is sufficient to prevent the steam generators from boiling dry [+0.25] during a period of coincident loss of offsite power and maximum decay heat-requirements-[+0.25].
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REFERENCE Conn Yankee: CY-0P-R0-SECSYS-LO2100, L.0. #1 & # . Conn Yankee:- Plant Information Book, " Auxiliary Feed," j Chapter 21, pp. 2- ; Conn Yankee: Technical Specifications, 4.8, " Auxiliary Feedwater," p. 4-1 ; i 061000K602 061000K401 061000A301 .. W s) l
QUESTION 6.10 (1.50) WHAT are THREE (3) signals that will automatically initiate auxiliary feedwater flow? Do not include any loss of AC or DC power supplie (1.5) I
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j ANSWER 6.10 (1.50) ]. both MFW pump breakers open [+0.5] ,,MccgM hr bsIis ] <"' ' S/G low level (45% on W.R. 2/4) [+0.5] ' e s loss of control air system pressure [+0.5] j f,
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l' t' v REFERENCE Conn Yankee: Plant Information Book, " Auxiliary Feed," i Chapter 21, p. . Conn Yankee: CY-0P-R0-SECSYS-LO2100, L.O. # j
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061000K402 ..(KA's) QUESTION 6.11 (1.00) WHAT are TWO (2) subcomponents of the reactor coolant pumps that are cooled by the Component Cooling Water System? (1.0)
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ANSWER 6.11 (1.00) RCP motor bearing oil coolers [+ . RCP thermal barrier coolers [+0.5]]
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REFERENCE
' Conn Yankee: Plant Information Book, "CCW," Chapter 44, pp. 46 & 4 . Conn Yankee: ODI #133 Rev. 1, p. 1. . , Conn Yankee: CY-0P-R0-PRISYS-LO4400, l. 0. #2 & #9,
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008000K301 ..(KA's) l i
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QUESTION 6.12 (2.50) WHAT automatic action (s) occur, besides alarms, for EACH of the following Radiation Monitoring System monitors: Service Water System Effluent Monitor (R-18)? (0.5) Component Cooling Water System Monitor (R-17)? (0.5) VentStackEffluentMonitor(R-14A)? (0.5) WHICH ONE (1) of the following radiation monitors can be used to initially detect primary to secondary leakage? (1.0)
(1.) Wide Range Gas Monitor (R-14B) l (2.) Reactor Coolant System Letdown Monitor (R-20)
(3.) Waste Test Tank Effluent Monitor (R-22) j (4.) Air Ejector Effluent Monitor (R-15)
ANSWER 6.12 (2.50) . At alarm point it terminates any liquid discharge in i progres (TripsFRCV-1003) [+0.5] At alarm point causes vent isolation valve on CCW surge tank (CC-TV-605)'toshut(isolatingthesurgetankfrom the environment). [+0.5] Alarm point causes automatic closure of Waste Gas Decay Tank release valve (WO-TV-2221). [+0.5]
(Valve numbers not required) , (4.) ' [+1.0] (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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REFERENCE Conn Yankee: Plant Information Book, " Radiation Monitor," Chapter 82, pp. 39, 57, 70, & 7 . Conn Yankee: CY-0P-FUNHP-L25010, pp. 2-4, 7, & K401 ..(KA's) QUESTION 6.13 (1.50)- MATCH the RCS Pressurizer pressure conditions in Column I with the associated values in Column 2 (1.5) Column 1 Column 2 PORV Opens psig High Pressure Reactor Trip psig Normal Operating Pressure psig Low Pressure SI Trip psig Energize Backup Heaters psig Trip Backup Heaters psig psig psig psig (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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ANSWER 6.13 (1.50)-
'a. 2' '+0 . 25'-
. b. 3' '+0.251 l c.-5 '+0 . 25' d. 9 '+0.25' e. 6 '+0 . 25 f.4l+0.25l REFERENCE' Conn Yankee: Plant Information Book, Pressurizer ' Pressure," Chapter 2.5, pp. 61 & 6 . Conn Yankee; CY-0P-LO-PRISYS-LOO 250,'L.0. f3, f4,_#6, and # A302 ..(KA's) QUESTION 6.14 (2.00) WHAT are FIVE (5) trips that will be blocked when power is -
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less than 10% (P-7)? (1.5) Besides turbine impulse pressure, WHAT input (s) is (are) utilized to determine when power is less than 10% (P-7)? (0.5) ANSWER 6.14 (2.00)- Variable low pre' .ure trip x 2 Low auto stop oil pressure trip
4 Turbine stop valve closed Steam line isolation valve closed trip e M%/ C /j ~'1%~ )
"
5 Reactor Coolant Low Flow Trip '~ l'" (~( S//
'"
,, 'j,)
e
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7 Reactor coolant pump bus UV trip Reactor coolant pump breaker open trip g fy Lp) Any five (5) trips [+0.3], max.+ /4 PRNI, <10% (coincident not required) [+0.5].
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:\ . . PLANT SYSTEMS (30%)L AND P'LANT-WIDE GENERIC- Page 36 1 RESPONSIBILITIES (13%) '
i REFERENCE Conn Yankee: Plant Information Book, "RPS," Chapter 75, pp. 75 & 7 <
' ' Conn Yankee: CY-0P-LO-ICSYS-LO7500, L'.0. #2 and # ..
012000K601 .012000K610 ..(KA's) 6.15 (2.50) j QUESTION l 1
) MATCH the RCS Pressurizer Relief tank conditions in l column I with the appropriate values in column (1.5)
COLUMN 1 COLUMN 2 l normal level (%) psi l Iow level- alarm- (%) < psig hi level alarm (%) > c. 150 psig normal pressure (psig) psig
' rupture disc. setting (psig) % %
1 %
, % % WHAT is the purpose of the Pressurizer Relief Tank? (1.0)
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ANSWER' '6.15 (2.50) a.- f '+0.3'
- g l+0.3l e + . b '+0.3' d l+0.3 Collect, condense, and cool discharge from the pressurizer safety and relief valves [+0.5] to. prevent release of radioactive fluid to the containment atmosphere [+0.5].
REFERENCE Conn Yankee: Plant Information Book, " Pressurizer Relief," Chapter 2.4, p. 3 . Conn Yankee: CY-0P-LO-PRISYS-t00240, L.0. #1, #3, and # A301 007000A202 007000K103 002000K105 ..(KA's) QUESTION 6.16 (3.00) WHAT are the requirements per Technical Specification 3.7- , for minimum water volume and boron concentration in the ! Refueling Water Storage Tank?' (1.0) WHAT is the Technical Specification basis for the minimum water volume requirement? (1.0)
: WHAT is used for ECCS pump suction after the RWST level s J
is reduced by 100,000 gallons? (1.0)
.
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3 - PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 38 , RESPONSIBILITIES (13%)
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j ANSWER 6.16 (3.00) l
> 230,000 gallons [+0.5] and i concentration as , .> 2450 ppm determined +/- 50 ppm[+0.5]
by engineering or refueling (tc e p1 .M OO r h( +" =itA aa s o n . .. - T b oA ; Requirements bound the maximum expected boration capability requirement conditions after [+0.5][ Xenon decay +0.25]based and on end oftocycle cooldown 140 degrees F. [+0.25] Containment sump (is used for recirculation phase of cooling) . [+1.0]
,
REFERENCE Conn Yankee: Technical Specifications, 3.7, p. 3-1 . Conn Yankee: Plant Information Book, "ECCS,", Chapter K601 ..(KA's) QUESTION 6.17 (1.00) MATCH the ECCS pumps in Column 1 to the shutoff head pressures in Column (1.0) Column 1 Column 2 charging pumps psig residual heat removal pumps psig
- high pressure SI pumps psig , low pressure SI pumps psig psig ' psig 7. 145 psig-(***** CATEGORY 6 CONTINUE 0 ON NEXT PAGE *****)
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I PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 39 1 l
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n ANSWER 6.17' (1.00) ] . '+0.25' . '+0.25' l . '+0.25' ; . l+ 0. 25.! j
REFERENCE Conn Yankee: Plant Information Book, "ECCS," Chapter 5,
<
p. . Conn Yankee: CY-0P-LO-PRISYS-L00500, L.O. # K613 ..(KA's)
!
QUESTION 6.18 (2.50) ;
'
ANSWER the following concerning fire brigade staffing: HOW MANY members of the fire brigade shall be maintained , on site at all times? (0.5) { Per Technical Specification 6.2.2, Facility Staffing, WHICH individuals may not be used to satisfy the fire j brigade manning requirements? (1.0) {, WHICH ONE (1) of the following is responsible for coordinating ) and/or directing fire fighting efforts to bring under control ' any fire fighting occurring within the plant? (1.0)
(1.) Station Superintendent / Unit Superintendent (2.) Operations Supervisor )
(3.) Shift Supervisor (4.) Fire Brigade Leader
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ANSWER 6.18 (2.50) members [+0.5] ] Exclude two (2) members of.the minimum shift complement , I necessary for safe shutdown of the plant [+0.5] and any personnel required for other essential functions during a fire emergency [+0.5]. (3.) [+1.0] ; I REFERENCE ) i' Conn Yankee: Technical Specifications, 6.2.1 . Conn Yankee: ACP 1.0-25 Rev. 4, p. 2- K116 ..(KA's) QUESTION 6.19 (1.00)
;
WHICH ONE (1) of the following statements applies to the proper ] use of the Critical Safety Function Status Trees? (1.0)
(a.) A Yellow terminus requires immediate operator attentio (b.) If any Red terminus is encountered, the operator is re uired to immediately stop any Emergency Operating Procedure E0P)
and perform the Function Restoration Procedure (FRP) required by the terminu (c.) If any Orange terminus is encountered, the operator is l expected to monitor all remaining trees. If a Red terminus ; is encountered in a lower priority condition, she/he will ! continue with the Orange tenninus of the higher priority j conditio l (d.) A Green tenninus will require continuous monitoring unti .; a Yellow terminus appears in a higher categor ANSWER 6.19 (1.00) j (b.) [+I.0]
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Page 41 PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC
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REFERENCE Conn Yankee: Haddam Neck ERG's, Chapter 3, User's Guide, p. 1 A115 ..(KA's) QUESTION 6.20 (1.00) WHO is initially responsible for evaluation, assessment, and. classification of plant events and/or incidents? (0.5)- Determination must be made if an event / incident can be classified as a reportable event or an emergency inciden HOW are these determinations made? (0.5) ANSWER 6.20 (1.00) Initially, the Operations Shift Supervisor assisted by the Outy Office [+0.5] An attachment (12.1A, Reportable Events) to the Emergency Assessment procedure will be used to determine the-classification. [+0.5] (Accept EPIP 1.5-1 as an answer) REFERENCE
I Conn Yankee: Emergency Plan Implementing Procedures, EPIP 1.5-1,'p. A116 ..(KA's) a l QUESTION 6.21 (2.00) i i l Northeast Utilities provides corporate guidelines for . I ' individual exposure to radiation. WHAT are the. QUARTERLY ! l and ANNUAL whole body exposure limits? (1.0) WHAT are FOUR (4) types of areas where Radiation Work Permits are required prior to entry? (1.0)
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ANSWER 6.21 (2.00) mrem / calendar quarter [+0. 5] 5000 mrem / year [+0.5]
.
'
- 4 ,b , :, rc .: n G . high radiation area / Meg , contaminated area m no,LE -
/ 'e . - t; < b a-
3. . airborne radioactivity area M0
.
4. neutron radiation area 1/' .M any other area posted with an ."RWP Required" sign Any four (4) [+0.25] each REFERENCE Conn Yankee: Radiation Worker Training Manual, pp. 23 & 7 . Conn Yankee: CY-0P-RO-FUNHP-L25009, RWP's, L.O. f K104 194001K103 ..(KA's) QUESTION 6.22 (1.50) A clearance is needed to allow maintenance work to be performed
. on an electrical breake WHO is responsible for reviewing' and authorizing the clearance? (0.5) WHAT color tag will be used? (0.5). WHEN may & clearance be cleared? (0.5)-
ANSWER 6.22 (1.50) Shift Supervisors /SCO's [+0.5]
.
I Red. Tag (Electrical / Mechanical) [+0.5] (accept Blue tag if conditions are stipulated) Only after all Work Orders assigned to clearance have been completed. [+0.5]
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REFERENCE Conn Yankee: ACP 1.2-14.2 Rev. 9, " Equipment Control (Locking and Tagging)," pp. 2, 6, & 1 K107 194001K102 ..(KA's) QUESTION 6.23 (1.50) ACP 1.0-5, " Containment Access," is used to control personnel access into and out of containment. During normal and emergency situations when containment integrity is required: WHAT are the Operations Shift Supervisor's responsibilities concerning containment access? (1.0) WHAT is the MINIMUM number of people required to make a routine containment entry? (0.5) ANSWER 6.23 (1.50) . Maintains control of the operations key to the access hatch power supply breaker [+0f5],_and < o.25J ensuresthatcontainmentacc@esshatchtesting]is completedinaccordancewithSUR5.1-62[+Jr I (SUR number not required) b, >,.} _.. -
--
Ah
~-~~~~ 3 e c g~i - ~ three (3) [+0. 5]
-
) b≠ te fe rsonne) +a '
REFERENCE Eniu to A inrnu d Conn Yankee: ACP 1.0-5, Rev. 7, v. 2 ;f 1 aa 194001K105 ..(KA's) f'A AM M ! - Account
'
40 t4& 1s {:renac d yer5MnCIthey ' uho ufel (Lq ns., :e
, a + u 1N y t
~- Yllyrc r.82 %e.) c r,tja W C of /5. 9 ( c # shi',,%
' -
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Q , 'g Of u .>, p , Ctel. 2 CY lf' t
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p. . , ( Ain _
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QUESTION- 6.24 (1.50) Technical Specifications 3.2, Reactor Coolant System activity, states that the reactor shall not be critical unless the total specific activity of the reactor coolant, with half. lives more than 30 minutes, is less than 68/E uCi/ml of coolan WHAT is the concern for not exceeding this limit AO WHAT accident is this limit designed to protect against? (1.5) { i
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ANSWER 6.24 (1.50) Release of activity into the RCS could constitute a hazard if the RCS barrier is breached [+0.5] and then only if the coolant contains b :cepYIN' i I excessive amounts of activity that could be released to the #""'.c#*/#
>-
environment [+0.5]. The limit protects against unacceptable releases in the event of a SG Tube Rupture accident [+0.5] f*mec REFERENCE Conn Yankee: Haddam Neck Plant Technical Specifications, 3.2, " Reactor Coolant System Activity," p. 3- K103 ..(KA's) QUESTION 6.25 (2.00) WHAT is the minimum shift staffing requirements for full power operation as specified in ACP 1.0-23, " Operations Department Shift Staffing Requirements?" (1.0) One reliefof y(our licensed reactor operators found out that hislicensed reactor ope work by an hour. WOULD the on-duty licensed operator be pennitted to leave the position unmanned as long as you knew there would be relief within a two hour period? WHY or WHY NOT7 (1.0)
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l ANSWER 6.25 (2.00) licensed senior reactor operators (SRO) 2 licensed reactor operators (RO) ! 2 auxiliary operators (AO) 1 shift technical advisor (STA)*
*(May be filled by an on-shift STA qualified SRO) {
[+0.25] each No position may be unmanned upon shift change due to an oncoming shift crewman being late or absent. [+1.0]
REFERENCE Conn Yankee: ACP 1.0-23 Rev. 1, " Operations Department Shift Staffing Requirements," p. 4 of A103 ..(KA's) QUESTION 6.26 (1.00) The off-going shift supervisor has just signed her/his name and license number to the Control Room Log. WHICH ONE (1) of the following should have been the LAST entry she/he made prior to signing the log? (1.0)
(a.) load changes made during the shift (b.) any reactivity changes (other than startup or shutdown) (c.) reactor mode CHANGES made during shift (d.) number of hours the reactor was critical / shutdown during shift ANSWER 6.26 (1.00)
s (d.) [+1.0) I (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) _ _____ _ _ _ -
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REFERENCE Conn Yankee: ADM 1.1-5 Rev. 1, " Control Room Operating Log," p. A106 ..(KA's)
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(********** END OF EXAMINATION **********)
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~ .. Cycle' efficiency = ((iOSWN . ; * f s ma v = 5/:
out)/(Energy in) . J i
,
8
. , , .ng s = Vg : + 1/2 a:-
9 ' !
-^t E * *0~ '
A=Ae3 2 a = (V, - V3 )/: A = - Ari l KE = 1/2 mv l PE = mgn w = e/t 1 = InZ/t1/2 =.0.593/t1/2 l
+ at yf = y, j
_ t /28If * b(t')(t")). ))
W = v a (,~1/2) . 'b ,
'
E = 931 an ~ I=Ie". 1 I Q $ mcps: -ux I*Ieo j Q = UA n I = 1, 10-x/T/L Pwr = Wfan T/L = 1.3/u 3 HVL = -0.593/u f P = p 10 sur(:) t . P = Po e /T SCR = S/(1 - K,ff) SUR = 26.05/T CR x = 5/(1.- X,'ffx) SUR = 250/i* + (s - o)T CR)(1 - K ,fg) = CR2 (I ~ keff2)
.
T=(1"/o)'[(s-p)/So] M = 1/(1 - X,ff) = CR)/CR o T = 1/(o - s) M = (1 - X ,ffe)/(1 - Kefg) T = (8 - o)/(ao) SDM = (1 - X ,ff)/K ,ff a = (Ke..,,-1)/K...,,, = X ,,,/K i 10~5 seconds e,, e,
..
_' A= =0.1 seconds,) o=[(L'/(IKeff))~E ef#/(I~AI)3 I)d) = I d I d 2 ,2 y,t 2 g2: 2 l
!
P = (26/)/(3 x-1010) 11 2 , I = oN .R/hr m c (0.5 CE)/d (meters) 2 l
.R/hr..:5..CE/d
= g f,, ),
<
Wa.ee Parameters Miscellaneous Conversion ; 1~ curie i 3.7 x 1010 gps l 1 gal. = 8.345 le ' 1 kg = 2.21 lom 1ga].=3.78 liters ' 1 hp = 2.54 x 10 3 Stu/nr 1f. = 7 . 4 3 s al .- 1 w = 3.41 x 10 Stu/hr Density = 52.* 1 g/f-3
'Densi?y = i gm/ W lin = 2:54 cm Hea: of vaccrization = 970 Stu/lom ~
'F = 9/5'C + 32 ;
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hea of fusion = ila Stu/ lcm *C = 5/9 (*F-32) 1 Atm = 14.7 ;si = 29.9 in,'. H BTU = 778 ft-lbf 1 ft. H 2O = 0.4335 luf/in.- i
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SUR 5.3-40 Rev. 7 Major JUL 111988
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l' ADMIN % DATASHEET #1 Excore QMR Calculation Lower Detectors Upper Detectors
.
l Current Reference * Current Reference * ; Readine Current Ratiot Readmg Current Ratiol
{
NIS 32 I i NIS 34 NIS 31 - I NIS 33 ,
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Average Ratio: Average Ratio:
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:
) IAwer Tilt Ratios UonerTilt Rancs NIS 32 (Loop 2)
NIS 34 (Loop 4) NIS 31 (Loop 3)
'i NIS 33 (Loop 1)
1 Ratio = Omnt Readin '
"~
Refertnce Readmg
*
* Reference Currents were taken during INCORE # dated
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6 of7
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