IR 05000322/1988012
| ML20235S276 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 02/17/1989 |
| From: | Conte R, Walker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20235S275 | List: |
| References | |
| 50-322-88-12OL, NUDOCS 8903070054 | |
| Download: ML20235S276 (102) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT
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EXAMINATION REPORT N (0L) FACILITY DOCKET N FACILITY LICENSE N NPF-36 4 - LICENSEE: Long Island Lighting Company Post Office Box 618 Wading River, New York 11792 FACILITY: Shoreham Nuclear Power Station EXAMINATION DATES: December 13 to December 15, 1988 l , CHIEF EXAMINER: M/ .. p g//7/(f7
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M acy E. Walk g Senior Operations Engineer Date-APPROVED BY: RichW d b chk Dste OperationsBranch,
[, Conte,Division Chief,BWRSection of Reactor Safety SUMMARY: Written examinations and/or operating tests were administered to three (3) senior reactor operator (SRO) candidates and two (2) reactor operator (RO) candidates. Two (2) SRO candidates and two (2) RO candidates passed these examinations. One SRO candidate failed both the written and operating test !
examinations.
I i 8903070054 890217 !" i PDR ADOCK 050003226 V PNV , L_______________
_ _ _ _ _ _ _ DETAILS TYPE OF EXAMINATIONS: Two (2) Initial and three (3) Retake EXAMINATION RESULTS: l R0 l SR0 l l Pass / Fail l Pass / Fail l l l l 1 I I l l Written l 1/0 l 1/1 l l l l l
! I I I l Operating l 1/0 l 2/1 l 1 l- 1 I I I I I l Overall l 2/0 l 2/1 l l l l l CHIEF EXAMINER AT SITE: Tracy E. Walker, Senior Operations Engineer OTHER EXAMINERS: D. Lange, Chief, BWR Section N. Conicella, Operations Engineer W. Cliff, PNL The following is a summary of generic strengths or deficiencies noted on operating tests. This information is provided to aid the licensee in upgrading license and requalification programs. No licensee response is require STRENGTHS A. General systems knowledge B. General administrative procedure knowledge C. Use of piping and instrumentation diagrams D. General knowledge of the Emergency Plan E. SR0 knowledge of refueling systems and procedures l
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l L & -3 .. ! ' DEFICIENCIES j A; Ability to explain the effect of operating HPCI.on various plant
' . parameters B. General _ knowledge of the ' components' and operation of an uninterruptible~
power supply (UPS) C. SRO knowledge of visitor exposure limits' , The following is a summary of generic strengths or deficiencies noted: from'. the' grading of written examinations. This information is being previded to aid the' licensee in upgrading-license and requalification training programs. No licensee response is require STRENGTHS A. Ability to explain plant response on'a complete loss of feedwater flo (Question 5.02) B. Knowledge of evolutions that place excessive stresses on the reactor
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vessel. (Question 5.03)- C.~ Ability to determine the required gain adjustment factor (RGAF) for nuclear instrumentation scram and rod block setpoints given a'proce s computer "P-1~ Edit." (Question 5.05) D. ResponLe of the. fuel zone level instruments while LPCI is injectin (Question 5.07) E.: Ability'to explain changes in peripheral control rod worth after core power reductions. (Question 5.11)L F. Knowledge of.how to place LPCI in service manually if it failed to initiate on a valid automatic signal. (Question.6.06) G. Ability to predict the response of the feed and condensate systern if
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the 'B' condensate pump tripped from 100% power. (Question 6.10) H. Knowledge of immediate operator actions and expected plant response
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for a complete loss of offsite power. (Question 7.10) I. Ability to utilize plant technical specifications for various plant conditions to determine required actions. (Questions 8.01,8.02,8.05)
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A.' Ability?to determine the' temperature-rise of feedwater through a l feedwater pump given all pertinent plant data. (Question ~5.01); i
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. B. Ability.to explain using numerical values ~the response;of the control- J Lyalves (CV's) and Intercept Valves'(IV's) to a mainiturbine overspeed 1 condition. (Question 6.01)l -j C. Knowledge-of actiens to be performed to ' verify the reactor l1s not ;
operating on a limiting control rod pattern. (Question 6.07). 1
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H D. Knowledge of the reasons why condenser air removal pumps are not placed' inLservice above 4% power. (Question 6~.08), E.: Knowledge of~the=fcct that: recirculation pamps'can be operated using individual loop flow control above 45% speed. (Question 7.03). .] F. Knowledge of the. requirements _of SP 12.012.01: Radiation Work Permit ,(Question 7.04)-
- Personnel Present at Pre-Examination Written Examination Review: .
NRC Personnel
. T. Walker, Chief. Examiner -
N. Conicella, Operations Engineer Facility Personnel
.s A. Burritt, Licensed Operator Instructor * E. Dean,. Plant Engineer, Operations - Personnel Present at Exit Interview:
NRC Personnel
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T. Walker, Chief Examiner N. Conicella, Operations Engineer F. Crescenzo, Senior Resident Inspector l.
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Facility Personnel r , ,
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W. Steiger, Plant Manager . _
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L.-Calone' Manager, Operations Training 1 Division
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H. Carter, Supervisor, Licensed Operator Training' _
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R. Francois, Lead.SR0 Upgrade. Instructor j R.> Reeves, Simulator . Instructor / Watch Superviso W. Keelty,' Compliance. Engineer-R
- E.. Dean,- Plant Engineer, Operations * Summary' of NRC Comments Made at Exit Interview:
The chief examiner'th'nked a the training and operations' staffs for their-cooper.ation during the examination The examiners felt that site access was smooth and that plant hou'sekeeping was adequat '
- Examination security for both the written and simulator portions were excellen ,
The written examination pre-examination review wss' discussed. The examiners felt this review was extremely beneficial. The facility staff was advised of the administrative requirements for sending the
- formal comnient Tne generic.stre'ngths and deficiencies noted on the operating examinations were discusse The chief examiner stated that every effort would be made to send the candidates' :results in approximately 30 working day Personnel Present at Examination Results Meeting:
NRC Personnel D. Lange, Chief, BWR 3ection, DRS T. Walker, Senior Operations Engineer N. Conicella, Operations Engineer R, Gallo, Chief, Operations Branch, DRS E. McCabe, Chief, Projects Section 18, DRP R. Conte, Chief, BWR Section, DRS Facility Personnel J. Scalice, Assistant Plant Manager L. Calone, Manager, Operations Training Division K. Rottkamp, Manager, Facility Services (Simulator) ' _ n
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6 Summary of Comments Made at the Examination Results Meeting: A raeting was held on January 27,1989 between the NRC and the facility to discuss the examination results. The meeting was held at the NRC Region I office. Several concerns were raised by the NRC over the faJ1ure of.one of the SR0 upgrade candidates. fhe concerns dealt with the facility's selection and certification process, the facility's pre-examination audit program and the candidate's fitness as a currently licensed RO on shif , The facility indicated that SRO upgrade candidates were chosen based L' on performance and supervisory ability and not solely on seniority.
l Both SR0 upgrade candidates were given the same training in preparation l for the NRC license examinatio ' e The facility indicated that both SRO upgrade candidates were given - an audit examination administered by the General Electric l Corporation and that both candidates passed the audit examinatio The facility indicated that they would review the competency of the SRO upgrade, who failed, with respect to R0 duties and corrective actions would be taken if neede , Attachments: 1. Written Examination and Answer Key (RO) 2. Written Examination and Answer Key (SRO) 3. Facility Formal Comments or Written Examinations 4. NRC Response to Facility Formal Comments
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5. Simulation Facility Fidelity Report ,
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fl TTA C H m EN T' ...%.... T % * U.1 5. NUCLEAR REGilLATORY COMMISSION 1- REACTOR OPERATOR LICENSE EXAMINATION
: 9 O, i, FACILITY: @HgBEHAM_________________
REACTOR TYPE: @WR-@E4__________________ E
DATE ADMINISTERED: 8 _8 _/ _1 2 _/ _ _ _ _1 3 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ EXAMINER: N_ R_ C _ R_ E G_ _I O_ _N_ _I _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ CANDIDATE _________________________ IN@IByCIIgN@_Ig_CBNpIDSIE Une separate paper for the answer Write answers on one side onl Staple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the questio The passing . grade requires at least 70% in each category and a final grade of'at 1 cast 80%. Examination papers will be picked up d" '6? hours after l. f the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY __Ye6UE_ _IQI@b ___gCgBE___ _y@ lye __ ______________C@lE@gBY_____________ _35c99__ _199t9 ___________ ______ PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL _25199__ ___________ ________% Totals g- Final Grade All work done on this examination is my ow I have neitker given nor received ai ___________________________________ Candidate's Signature i
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- _ _ _ _ _ _ _ ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ' .. = ** - - .NRC RULES AND GU.IDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the f ollowing rules apply:
l Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . .Restroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with anyone outside the examination room to avoid even the appearance or po'ssibility of cheatin . Use black ink or dark cencil only to facilitate legibl e reproducti on . i Print your name in the blank provided on the cover sneet of the j ex ami n at i o J Fill in the date on the cover sheet of the examination (i f necessary). Use only the paper provided f or answers.
L '7 . Print your name in the upper right-hand corner of the first page of each section of the answer shee . Consecutive y number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer shee . Number each answer as to category and number, for example, 1.4, . Skip at least three lines between each answe ; 11.. Separate answer sheets from pad and place -finished answer sheets face down on your desk or tabl . Use abbreviations only if they are coinmonly used in facility literatur . The point value f or each question is indicated in parentheses after the question and can be used as a guide for the depth of answer require . Show all c al c ul at i on s, cethods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no . Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE ' i DUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner onl . You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been complete ,
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(;j!:1'9[ WhenEyou complete your) examination, you shall;: l
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a. s C Assemble your examination as ' f ollows: J , (1) . Exam. questions on top.- '
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(2)- Exam iaids Jfigures, tables, etc.- (3).
' Answer pages including figures.which are-part of the. answe ' Turn'in your copy:of the examination..and all pages used;to: answer the. examination' question c.: Turn'in all scrap paper and the balance of the paper thatryou did not use for answering the question ' Leave the examination area,'as defined by.the examiner.- Iflafter leaving, you are f ound in this area while the . examination . is .still in progress,.your license'may be denied or revoke s [E
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i i I QUESTION 4.01 (3.00) Concerning SP 61.012.01, PERSONNEL DOSE LIMITS AND GUIDES: (3.0) l MATCH Column- A wi th the appropri ate 'value (s) from Column COLUMN A COLUMN B i j Whole body dose guide during fN-18) R outage mR/wk B. Dose limit to extremities mR/qt C. Whole body dose. guide (non-outage) .75 R/qtr
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D. Your whole body dose limit mR/*4#' 9 Dose guide to individuals who cannot disclose nature and amount mR/wk of dose received during current
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QUESTION'. 4.02- (3.00) I' ' LIST ALL entry conditions for SP 29.023.02, SECONDARY CONTAINMENT (3.OV
' CONTROL EMERGENCY PROCEDURE. INCLUDE setpoints where applicabl >
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QUESTION 4.03 (1.00) Concerning SP 23.202.01, HIGH PRESSURE COOLANT INJECTION (1.0) SYSTEM OPERATING PROCEDURE: If the HPCI turbine is manually started, the procedure directs the operator to simultaneously OPEN the steam to turbine valve (MOV-043) and START the auxiliary oil pump. BRIEFLY EXPLAIN WHY these steps must be perf ormed simultaneously.
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QUESTION 4.04 (2.00) Concerning SP 23.121.01, RESIDUAL HEAT REMOVAL (RHR) SYSTEM i I OPERATING PROCEDURE: A. In shutdown cooling and fuel pool cooling modes, RHR system (1.0) flowrate shall be maintained greater than 2800 gpm. STATE , I THE REASON :or this cautio B. In shutdown cooling, if RPV level is less than +43 inches, (1.0) two loops of RHR should be placed in service. STATE THE .li REASON for this cautio f T l
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I 10UESTION' ' 4. O5 ' (1.00)~
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' Concerning SP.22.OO4.01, DPERATION.BETWEEN 20%-AND.100% POWER:
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t ' A.:. Precauti on 4.7 warns : the operator- not to exceed the BOX (0.5) !
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rod line on the Power / Flow map unless core flow.is greater thaq 35 M1bm/hr. STATE THE REASON for this precautio 'I B. The recirculation pumps are transferred to master manual- (0.5) L' control at _______% pump speed. (FILL IN THE BLANK).
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.QUESTION-l - 4.06- - (2.00):
Chncerni ng T SP.-'- 29.023.03, PRIMARY. CONTAINMENT CONTROL EMERGENCY
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;A. StepL3.3.3 directs:the operator,to maintain RPV pressure-
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the;. significance ofsthe-HCT B.' STATE.the plant-paramaters available:from' Control Room .
(0.5) ' instrumentation required to determine.the HCTL'. g ..
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).', :a; 7 cc . ) QUESTION'- '4.07 ~ (2. 50) .
g Concerning'SP 29.020.01, ALTERNATE SHUTDOWN. COOLING EMERGENCY : L' PROCEDURE: il o
' . A. ' BRIEFLY DESCRIBE the basic flowpath f or cooling water to th (1.5)
reactor-~while in alternate-shutdown cooling. INCLUDE;in your? description HOW; core decay heat. is ultimately, remove D. : STATE the pref erred' pump for'use during alternate shutdow .
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cooling. ' EXPLAIN yourLanswe I
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I'?QOESTION'- '4.08L (3.00)' ,
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Thel reactor 11s at .100% power when . a complete : 1oss of' both_ normal' -
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:-and.stationireserve power occurs.-In accordance with SP 29.015.01,
{ LOSS OF OFFSITE POWER:
i J STATE ALL..'ths immediate operator' actions _' require (1.5)
' B. , BRIE FLY - STATE..the : response of each of the f allowing systems:
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~1 ~. 'Reac tor'. protec ti on .. system . (RPS)-
2._ Nuclear' steam' supply shutoff-system (NSSSS) 3.. Reactor building stan'dby ventilation system (RBSVS) .
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i QUESTION- 4.09 (1.50) { l STANDING ORDER NUMBER 30 provides specific guidance'concerning operation with the 5% low power license in effec A. STATE the maximum allowable average core power for any (0.5) transien B. DESCRIBE HOW core power is to be determined from available (0.5) plant. instrumentatio C. STATE the maximum allowable average power if the main (0.5) generator is synchronized to the gri !
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~ GUESTION 4.10- ( 3. 00 ) .~
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3Concerning SP.!21.'OO4.01, MAIN CONTROL RDOM-CONDUCT OF. PERSONNEL -- A. STATE WHEN,an RD can relieve the' Watch Engineer'of the control ( 1 ~. 0 ) -
. room command-function'. . B..: STATE WHO may. manipul ate reactivity control . (g,93 p
C. STATE.the' responsibilities'of the'first licensed control room (1.0) z operator.(NSO/NASD) during an.~ abnormal. plant condition. . INCLUDE s
[ . in your.dir,cussion the NSO/NASD's' primary concer !.
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QUESTION 4.11 (2.00) Concerning SP 12.006.01, STATION PROCEDURES-PREPARATIONS, REVIEW, APPROVAL, CHANGE REVIEW AND CANCELLATION: ANSWER TRUE OR FALSE: A. . Surveillance procedures are not required to be preformed (0.5) step-by-step as long as the intent of the surveillance is strictly adhered t B. Routine procedural actions that are f requently repeated do not (0.5) require the procedure to be presen C. Temporary procedure changes have a maximum life of 14 days (0.5) unless approved as a permanent procedure chang D. Temporary procedure changes may be initiated by ANY plant (0.5) staff member.
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QUESTION -4.12 (1.00) f
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;" Concerning SP 29.023.O1, RPV CONTROL EMERGENCY PROCEDURE: (1.0) j
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EXPLAIN WHY if boron injection is required, ADS must be inhibited from automatic initiatio !
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ANSWER 4.01 (3.00)
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A-6 B-4 C-2 D-1 i E-3 REFERENCE LP: SP 61.012.01 PERSONNEL DOSE LIMITS AND GUIDES OBJ: NONE FROM TRAINING MATERIAL KA: 294001 K1.04 (3.3/3.6) I 294001 K1.03 (3.3/3.8) 294001K103 294001K104 ..(KA's) ANSWER 4.02 (3.00) 1. reactor building differential pressure (0.5) at or above O inch'es I of water (0.5) reactor building exhaust radiation levels above the maximum normal operating radiation levels ( 0. 5) { g 3. reactor building floor drain sump level above maximum normal i operating value (0.5) 4. any secondary containment area temperature above the maximum normal operating value (0.5) 5. any secondary containment area radiation level above the maximum normal operating value (0.5) REFERENCE LP: SP 29.023.02 SECONDARY CONTAINMENT CONTROL OBJ: HL-944-SH1, B 3
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KA: 295032 G011 (4.1/4.2) 295033 G011 (4.0/4.5) 295035 G011 (3.9/4.2) 295036 GC',1 ( 3. 8 / 4.' 1 ) I 295036G011 295035G011 295033G011 295032G011 ..(KA's) 1
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dt__tBQCEQUBE@_;_NQBd@(t_@@NQBd@bt_EdE6@ENCY Psg9 15 BU9_509196gelC66_CgNIBQL ANSWER 4.03 (1.00) The TCV will f ully open once the auxiliary oil pump is started.(0.5) T. f the TCV was f ully opened and then the steam to turbine valve was f ull y opened, there is the possibility that the HPCI turbine might overspeed or develop excessively high discharge pressure. 00.5) REFERENCE LP: SP 23.202.01 HIGH PRESSURE CDDLLANT INJECTION HL-202-SH1 DBJ: HL-202-SH1, CD-2 KA: 294001 A1.02 (4.2/4.2) 206000 K4.11 (3.4/3.5) 206000 A1.07 (3.7/3.6) 206000 A1.09 (3.5/3.4) 206000 G010 (3.9/3.8) 206000G010 206000A109 206000A107 206000K411 294001A102
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ANSWER 4.04 (2.00) Flowrate greater than 2000 gpm prevents the min. flow valve from opening.(0.5) This could result in pumping the RPV j water or the fuel pool water to the suppression pool . (0.5) B. RPV level must be greater than +43 inches to assure a natural circulation flowpath (0.5) To provide a redundant method of decay heat removal at RPV levels that natural circulation is not possible, two loops of RHR are placed in shutdown cooling.(0.5) REFERENCE LP: SP 23.121.01 RESIDUAL HEAT REMOVAL SYSTEM pages 4,12 HL-121-SH1 OBJ: HL-121-SH1, CF-3,CF-7 KA: 294001 A1.02 (4.2/4.2) 205000 G010 (3.2/3.3) 205000 K1.02 (3.6/3.5) 205000 K3.03 (3.8/3.9) 205000K303 205000K102 205000G010 294001A102 ..(KA's)
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6, PRbCEDURES - NORMAL _1 ABNORMAL 1_EMER@ENgY Pcga 16 BNg_6@glgLg@lC@6_CgN16gL ANSWER 4.05 (1.00) Excessive neutron flux noise levels may occu (0.5) B. 45% pump speed (+/- 5%) (0.5) REFERENCE LP: SP 22.004.01 OPERA, TION BETWEEN 20% AND 100% POWER OBJ: NONE FROM TRAINING MATERIAL KA: 294001 A1.02 (4.2/4.2) 202001 AO.10 (3.5/3.7) 202002 K4.02 (3.0/3.0) 202OO?K402 202OO1A010 294001A102 ..(KA's)
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ANCWER 4.06 (2.00) A. The highest suppression pool temperature at which initiation of RPV depressurization will not result in exceeding, the suppression chamber design temperature (0.5) or the primary containment pressure limit (O.5), before the rate of energy transfer from the RPV to the containment is within the capacity of the containment vent. (0.5) " B. Suppression: pool temperature (0.25) RPV pressure (0.25) REFERENCE LP: SP 29.023.03 PRIMARY CONTAINMENT CONTROL HL-944-SH1 page 31 OBJ: HL-944-SH1, E,F KA: 295026 K1.02 (3.5/3.8) 295024'Kh.01 (4.1/4.2) 295026 GOO 7 (3 4/3.8) . 295024K101 295026 GOO 7 295026K102 ..(KA's)
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Page 17 BND'_66 dig 6ggIC6L_CgNIggL ANSWER 4.07 (2.50) One LPCI or CS pump takes suction f rom the suppression po31 (0.3) and discha ges through an open SRV back to the suppression pool . (0. 3) Heat is removed f rom the suppression pool by RHR in suppression pool cooling. (0.3) Heat is removed from the RHR heat exchanger by reactor building service water (0.3) and transferred to the LI Sound. (0.3)
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,, . ,, It is preferred to use one LPCI(0.5) for cooldown due to the internal RPV flowpath consideration.(0.5)
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REFERENCE LP: SP 29.020.01 ALTERNATE SHUTDOWN COOLING OBJ: NONE FROM TRAINING MATERLAL KA: 295021 A1.04 (3.7/3.7) 295021 GOO 7 (2.9/3.2) 295021 K3.05 (3.6/3.8) 295021K305 295021 GOO 7 295021A104 ..(KA's)
, ANSWER 4.08 (3.00) . verif y auto actions and manually initiate any that f ailed (0.5)
2. enter SP 29.010.01, EMERGENCY SHUTDOWN PROCEDURE (0.5) 3. notif y system operator and determine f rom him if the (0.5) Holtsville or the onsite 20MWe turbines have started B. 1. RPS deenergizes (0.25) causing a SCRAM (0.25) 2. NSSSS deenergizes (0.25) causing an isolation (0.25) 3. RBSVS initiates (&.-25) "%" nnwar ir c;;t erad by COG'm 'C. 25h (o.c ) { i REFERENCE . LP: SP 29.015.01 LOSS OF OFFSITE POWER HL-309-SH1 r ages 23,24 OBJ: HL-309-SH1, C,D-6 KA: 295003 G010 (3.9/4.1) 295003 A1.03 (4.4/4.4) 295003 A2.04 (3.5/3.7) 295003A204 295003A103 295003G010 ..(KA's)
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j4s *PkbCEDURES - NORMAL _ABNQRMAL t _tEMERGENCY 'Paga 18 L 'BNQ_B@QlgLQGlC@6_CQNIBQL ANSWER > 4.09 (1.50) A. 5% (0,5) B. average of all APRM readings (0.5)
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C. 4.75% (0.5) REFERENCE LP: STANDING DRDER NUMBER 30 DBJ: NONE FROM TRAINING MATERIAL KA: 294001 A1.02 (4.2/4.2) 294001 A1.03 (2.7/2.7) i 294001A103 294001A102 ..(KA's) ANSWER 4.10 (3.00) . OP CON 4 (0.5) OP CON 5 (0.5) b . holders of active RD or SRO (0.5) trainees in an established training program but on'ly under (0.5)
-the direct supervision of an RD or SRO and only when authorized by the watch engineer C. The NSO/NASD to panel 603 shall take immediate actins necessary for reactor safety (i . e. reactor' scram f ollowup. vessel level and pressure control, ECCS initiation) (O.5) He shall ensure auto actions take place or initiate these actions manually. (0.25)
His primary concern is to keep the core covered. (0.25) REFERENCE LP: SP 21.004.01 MAIN CONTROL RDOM-CONDUCT OF PERSONNEL ... , DBJ: NONE FROM TRAINING MATERIAL l KA: 294001'A1.03 (2.7/3.7) 294001 A1.09 (3.3/4.2) 294001A109 294001A103 ..(KA's) f (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) i= i b i 1
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A;I FALSE (0.5) i B. TRUE ( 0. 5) L ! C.-. FALSE (0.5) ? D. TRU (0.5) REFERENCE l C LP: SP-12.OO6.01, STATION' PROCEDURES-PREPARATIONS, REVIEW, APPROVAL,
. CHANGE REVIEW AND CANCELLATION DBJ: NONE FROM TRAINING MATERIAL' *
KA: 294001-A1.01 (2.9/3.4) 294001 A1.02 (4.2/4.2) 294001 A1.03 (2.7/3.7) 294001A103 294001A102 294001A101 ..(KA's)
,' ANSWER 4.12 (1.00)
ADS initiation may resul t in the injection of large amounts of-relatively cold, unborated water. (0.5)'The power excursion could r 1
. ccuse substantial fuel damage. (0.5)
( .. REFERENCE LP: SP 29.023.01, RPV CONTROL HL-944-SH1 page 13 - DBJ: HL-944-SH1, E'. KA: 295037 GOO 7 (3.7/3.9).
o 295037 GOO 7 ..(KA's) I
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U. S. NUCLEAR REGULATORY COMMISSION
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i<'*"' r SENIOR REACTOR OPERATOR LICENSE EXAMINATION
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. FACILITY: , SHQREH@M________,,________ ? .
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.gWR-gE4__________________
. W REACTOR TYPE: DATE ADMINISTERED: _8_9_/_12__/_13_________________ _ EXAMINER: NRg_REgIgN_I___,,_________ CANDIDATE __________._______________ 1NglgggIlgNg_lg_g@NQlg@lEl
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U2e separate. paper for.the answer Write answers.on one side onl _ Staple question sheet on-top of the answer sheets.- Points 1for 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 Examination papers will be picked up six (6) hours after
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laast 80%. the examination start % OF CATEGORY % OF CANDIDATE'S. CATEGORY __YekgE_ _191@6 ___Sgg5E___. _y@6gE__ ______________g@IEgg6y_____________ 24.30 _EE 99__ _2Et99 ___________. ______ . THEORY.OF NUCLEAR POWER PLANT OPERATION, FLUIDS,AND THERMODYNAMICS _2E299__ _25199 ___________ ________ PLANT SYSTEMS DESIGN, CONTROL, ( AND INSTRUMENTATION _2E199__ _29199 ___________ ________ PROCEDURES - NORMAL, ABNORMAL',. EMERGENCY AND RADIOLOGICAL CONTROL _NEA99__ _25199 ___________ ________ ADMINISTRATIVE'FROCEDURES, CONDITIONS, AND LIMITATIONS 99.s-
, _t99r9 _ ___________ ________% Totals i Final Grade
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All work done on this examination is my ow I have neither gi ven
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nor received ai ___________________________________ Candidate's Signature
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; .3 ', 'NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS s.
k Duri'h g tde administration of this examination the f ollowing rules. apply:
) Cheating on-the examination means an automatic denial of your application and could result in.more severe penaltie Restroom trips .are to be limited and only one candidate at a' time may leav You must avoid all contacts with delyone outside the examination room to avoid even the appearance or possibility of cheatin [ Use black ink or dark pencil only to facilitate legible reproduction .[ ) Print your name examinatio in the blank provided on the cover sheet of the . Fill in the date on the cover sheet of the examination (i f. necessary) . ( ) Use only the paper provided f or answers.
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. Print your name in the upper right-hand corner of the first page of each ' : nection of the answer shee Consecutively number each answer sheet, write "End of Category __" as ( appropriate, start each category on a new page, write only,on one side-of the' paper, and write "Last Page" on the last answer shee .4, ( ) Number each answer as to category and number, for example, ffSkip at least three lines between each answe ()downonSeparate answer your desk or sheets table. f rom pad and place Jfinished answer sheets f ace g
Q % Use abbreviations only if they are commonly used in facility literatur f)Thepointvaluefor each question is indicated in parentheses after the question and can be used as a guide for the depth of answer require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical probleins whether indicated in the question or no Partial credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN , If parts of the examination are not clear as to intent, ask questions of ~ the examiner onl You must sign the statement on the cover sheet that ,noicates that the
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work is your own and you have not received or been given assi stance in compl eting the examination. This must be done after the examination has been complete }
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4 ' 7) e, 18) Whbn you complete your ex ami nati on , you shall: )
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e Assemble your examination as follows: l (1) Exam questions on to ;
'! (2) Exam a2ds - figures, tables, et (3) Answer pages including figures which are part of the answe Turn in your copy of the examination and all pages used to answer ,/ the examination question Turn in all scrap paper and the balance of the paper that you did '
s not use for answering the question Leave the examination area, as defined by the examine If after _
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leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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u ETHEORY'OFhNUCLEAR' POWER' PLANT' OPERATIONz Page '2
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-QUESTIO .01 '(3.00)
At'SNPS'the typical operating paramaters:for a reactor '( 3. 0 ) ' L . f eedwater pump are: ' sucti on precsure 650_ psi g, discharge
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QUESTIOW 5.02 (3.00) The reactor is at 1007. power when a feedwater controller failure (3.0) occurs resulting in a complete loss of feedwater flow to the reactor vessel. During the time period JUST PRIOR TO THE SCRAM, do you expect reactor power to INCREASE, DECREASE OR REMAIN.THE SAME. STATE TWO(2) REASONS to justify your answer.
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.Certain .planty evolutions; couldL subject the reactor vessel : to!
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- excessiveJstresses.if operational' li mi ts. were. not _ observed.g LIST'
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J THREE - (3) -' evol uti ons - that.. are controll ed by.- operati onal:: limits
,or,! procedures ~that could subject the reactor vessel-to excessive; ' thermal' " str esse .,
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., ' DUESTION 152 04 :
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gj - A reactorfstartup.is.in.' progress.:The reactor'is critical and- .(2.0)-
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on;aE60 second: period.yTRUE,OR FALSE: If' power.-increased by a - f' actor.?ofj.4 over'.the..next % seconds) the; point ' of adding ' heat l, .h'as been reached. EXPLAIN your answer? based on'the period change.:
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QUESTION' 5.03 (3.00) The following information was obtained from the latest P-1 EDIT: l PCT PWR 48.0 ' LHGH APRM GAF O.99 CMWT 1169 A. DETERMINE the required gain adjustment factor (RGAF). (2.0) l (SHOW ALL WORK) B. Based on the information above, is the reactor operating (1.0) on a limiting control rod pattern? EXPLAIN your answer.
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'QUESTIDM 5.06' (3.00) {
i The reactor is operating at 100% power when one(1) SRV opens and remains open. STATE HOW each of the f ollowing paramaters would change ! THROUGHOUT THE TRANSIENT until a steady-state condition is reache BRIEFLY EXPLAIN your answers. (assume the reactor does not scram) A. Reactor pressure (1.0) INDICATED steam flow (1.0) C. Reactor water level (1.0) W
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if e.Sf" , 2, QUESTIOh! 5 . 0 7'- - ( 1A) o . . . .
(0 W)
-44,4b
! Answer the fallowing 1TRUE.OR FALSE.,Concerning<the Fuel Zone l level f instruments: J . A' tocA occ us Fr. , roop,' r,A ,g,, p ,-
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. Ori n;; 2 LOC ^ L'i t h-t-he-r-eac-t-ori -at-1-50-psLgAemdtcated 4 1svs1 will be 44CliEP ther ':ctual -l evel -
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B. ' If LPCI . was_ 'inj ecting, the -indicated l evel would be HIGHER l, than actual leve l
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:- l QUESTION 5.09 (2.50)
Concerning reactor thermal limits: A. DEFINE Critical Power Rati (1.0) B. Operators have control over several parameters that affect (1.5) critical power l evel . WHICH of the f ollowing would INCREASE the critical power level assuming all other variables remained constant? EXPLAIN your answer (s).
1. Local peaking factor is INCREASE . Reactor pressure is DECREASE . Recirculation flowrate is DECREASED.
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-- QUESTIO '5.09 .( 2.00)
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Concerning the-subcritical eactor: A.'BRIEFLY: EXPLAIN:how a constant natutron flux. level is possible ( 1. 0 ) -
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. During.a reactor startup, WHY do SNPS procedures employ a slow (1.0) deliberate approach...to criticality? . i
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QUESTIOff -5.10 ' ( 2. 00 ) ' TRUE OR: FALSE:'Itiis_'possible.for.-reactor power.to INCREASE:a ~
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ESTI'ON' 5.11 ! ( 2. 00) . , g . Reactor power was' decreased;from 100% to 75% by reducing., -
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' ' recirculation flow. HOW does'this power' change affect periphera control: rod' worth-(INCREASE, DECREASE OR REMAIN-THE SAME).four (4)
: hours after. reaching 75% power compared to'the periphera control rod-worth p-ic- te the power decrease?' EXPLAIN your answe y
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QUESTION 6.01 (3.00) Concerning the Electro-Hydraulic Control System (EHC):
(see attached FIG 18 of HL-657-SH1)
A. WHICH component (s) of the EHC logic diagram is/are used to (1.0) adjust generator frequency prior to synchronizing to the grid? B. EXPLAIN the response of the CV's and IV's to a turbine (1.5) overspeed condition if the EHC controls are set for normal 100% power operation. (show all workteca - .'*J vIw h re IJc vues &ms 4 %% st*cd) TRUE OR FALSE: If the reactor is at 100% power and pressure (0.5) set is 920 psig, the actual reactor steam dome pressure will be.950 psi l f
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,,'; ..- ? , -- , ' - QUESTIO!4 6.02 (3.00)
Co:icerning the Emergency Diesel Generators (EDG's) and the Emergency Electrical Distrib'ution System: STATE TWO (2) 4KV loads on DIV II Bus.102.that DO NOT trip if (1.0) a slow =. transfer occurre 'B.-EDG 101 has' started on.a valid bus'undervoltage and its. output (2.0) breaker'has shut. BRIEFLY DISCUSS the sequence of events #with respect ' toithe EDG's and loads powered f rom the emergency busses / if an operator now depresses the Core Spray ynter 1 manual initiation push-butto . Divis/u w' s m 4 *
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L -QUESTIOh! 6.0 ' (2. 00) .
Answer.(TRUE OR. FALSE for each:of'the: fallowing concerning.th Remote Shutdown Panel f(RSP): - If the remote shutdown transfer switch (RSTS) for ( 0. 5 ) ' the RHR system is in EMERGENCY, the-RHR pump WILL-
- NOT auto start when a valid low reactor water level signal is generate *
B. When the RSTS.for the RCIC system is in EMERGENCY, (0.5)
. ALL.the RCIC system' interlocks and trips'are bypassed ~.
C'.'When the RSTS for t'he'RHR system is in EMERGENCY, (0.5).
the RHR pump CANNOT be manually started or stopped f rom the control roo RSP instrumentation.will provide accurate indication of (0.5) all monitored parameters regardless of the position of the RSTS' *
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QUESTION * 6.04 (2.00) A reactor startup is in progress in accordance with (2.0) SP-22.OO1.01 (Start up - Cold Shutdown to 20 Percent).
Reactor pressure is 350 psig and preparations are in progress for starting a reactor feedpump. STATE FOUR (4) reactor protection system trip signals that are AUTOMATICALLY BYPASSED in this condition and BRIEFLY EXPLAIN HOW they are bypassed. (Note: the shorting links are removed)
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:-QUESTIOf4 6.05 (3. 00) .
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';TheLplant.is. operating'at.85% power when an operator-l inadvertently' inj ects ' HPCI - during a- surveillance tes ' ~ Assume the' reactor.DOES NOT' scram and.ND operator: action:
is taken'after'the HPCI injectio (see attached FIG 2 of HL-656-SH1)- i If. the f eedwater level control' system (FWLCS) was in ( 2. 0 ) . l I 3-element control, . DESCRIBE the' response of;the FWLCS-l
until a stable condition .is reached with HPCI-l . injecting atLrated flow.: INCLUDE in your description the effect on water level,-feedpump' speed.and feed-
' flow.- . BRIEFLY DESCRIBE how-the, response and final condition ( 1. Oi I would be-different i f.. the FWLCS was in . single-element; ,
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- mutomatica11 y i ni ti ate. ^ STATE , the major steps. required..to
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'(see' attached FIG 1A of HL-204-SH1)~
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. Theireactor'_is operating-at 100%. power. LIST FOL'P r .
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QUESTION 6.08 (3.00) Concerning the Condenser Air Removal System: A. STATE TWO (2) concerns with using auxiliary boiler (1.0) steam to operate the steam jet air ejector B. STATE TWO (2) purposes for the steam jet air ej ector (1.0) discharge radiation monito C. SRIEFLY EXPLAIN why the condenser air removal pumps should (1.0) NOT be operated when reactor power is greater than 4 */. .
(2 reuscas)
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L CUEST.I ON' 6.00- (2.50) g IFor- each of. the following, INDICATE whether~ the statement
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j' applies;to the Rod Worth Minimizer: (RWM), the Rod p Sequence Control System :(RSCS),- BOTH or NEITHE f- Low power alarm point is 30% as. sensed.by. steam. flow.- _
(0. 5) - Purpose. is to limit reactivity worth of control rods (0.5) .,. and reduce. severity of airod drop. acciden .
C. Start up may continue with system ' inoperabl (0.5) .g D. Alarm light'on panel-illuminates when a select. error . ( 04 5 )
'is'mad ' Inf ormation is stored and run by the process compute (0. 5) ~ ,
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k -QUESTIOhl 6.10 , '(3.00) jA Concerning"the Condensate [ Systems:-
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A.._TRUE OR FALSE: . If the plant was at~100% power when ( O. 5)~
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,. , a complete loss of station . air occurred,, there would be NO EFFECT on the condensate system's' ability to maintain'200% system flow., bJ r Jw +-
, B. ;The reactor. is at 100% power when' condensate pump B .(2.5)
trips.due-to a motor fault. EXPLAIN the expected
'
response of the plant with FJD operator action. .. INCLUDE
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in your' discussion'the response of'the' condensate-
' booster pumps,-the feedpumps, reactor level, feed < flow and .
reactor power. (assumeLthe reactor does not. scram) H~ l'! '
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~ , .p DUEST' ION'. . 7. 01 '- (1.00)
Concerning SP 23.202.01, HIGH PRESSURE COOLANT' INJECTIO (1.0) SYSTEM OPERATING PROCEDURE: If the HPCI turbine i s manuall y. started, the procedure directs the operator to simultaneously OPEN the' steam to turbine valve (MOV-043).and START the auxiliary oil pump. BRIEFLY' EXPLAIN WHY these steps must - be perf ormed ' simultaneousl h. --
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QUES I'ON 7.02' (2.00) Concerning-SP 23.121.Ol', RESIDUAL HEAT' REMOVAL.,(RHR) SYSTEM
' 'DPERATING PROCEDURE: ' 'A.cIn shutdown cooling and fuel pool cooling. modes, RHR system (1.0) ' '
flowrate shall be' maintained greater.than'2800 gpm. STATE
.--THE. REASON for this cautio B..In shutdown' cooling, if RPV level is less.than +43. inches,- ( 1. 0 ) =
two loops of RHR should lbe placed in service. ~ STATE THE
< REASON-for this cautio I (
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-DUESTIO .03- .. (1.00) . Concerning SP 22.O'04.01, OPERATION BETWEEN 20% AND'100% POWER:- .
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h Precaution-4.7 warns the operator not to exceed the 80%_ (0.5) ; rod' line. on. the Power / Flow map unless core flow is greater . than 35 M1bm/hr.- STATE THE REASON for-this precautio ' B. The recirculation pumps are transferred'to master manual- (0.5) control'at--45 % pump speed. If the master. speed controller is
: inoperable,is power ascension permissible using individual loop. flow control? ANSWER YES OR N ,
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. ' DUEST I Old . '04 ; .(3.00) .,
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%, Concerning SP 12.012.01' RADIATION WORK PERMITS-(RWP): ]
A.--. STATE the-significance of the Watch Engineer's signaturef ,(1.0) ! in'the RWP Approval'section'of.an RW .l
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F , B.. STATE the types of tasks that'an Extended RWP is used fo ' (0. 5) C. WHO IS/ARE authorized to allow a worker.to deviate from the ( 1. 0 ) - requirements of.an RWP..(answer by title) 4 u --
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L- - TRUE DR FALSE: For entries into areas' where exposures are (0.5)
'in excess of.100'mR/hr, stay-times'are required:to be specifie .
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QUESTIOhi- '7.05 -(2.00) Concerning SP. 29.023.03,- PRIMARY CONTAINMENT CONTROL EMERGENCY _ PROCEDURE: A. Step 3.3.'3 directs the-operator to' maintain RPV pressure ' ( 1. 5 ) . below the heat capaci ty temperature limi t - (HCTL) . . EXPLAIN the significance of the HCT ' B. TRUE ORTFALSE The primary containment SHALL be vented if- (0. 5 ) - suppression' chamber' pressure reaches 60 psig regardless of the
- radioactive release to the. general publi i i l
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; Concern'ing SP' 29.023.07, LEVEL / POWER: CONTROL EMERGENCY. PROCEDURE: ' (1.5)
EXPLAIN' whh, the ' reactor water level decrease can be terminated-
- iw hen'all-SRV's remain closed and drywell pressure remains below f_ 1.69 psig;even.if power is still greater than 5%.
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QUESTION 7.07 (3.00) Concerning SP 29.023.01, RPV CONTROL EMERGENCY PROCEDURE: A. EXPLAIN WHY drywell pressure above 1.69 psig is an entry (1.0) condition for the RPV control procedur If boron injection i s required, it can be terminated when all (1.0) control rods are inserted to or beyond position O2. EXPLAIN the significance of position 0 C. EXPLAIN WHY if boron injection is required, ADS must be (1.0) inhibite , l lI I
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y]j;; H _ '* * : WjQUESTIDhl 7.OS (3.00) For' each . of! the f oll owing. pl ant : condi tions,- STATE WHICH. Emergency (3.0)
. Procedure must be entered.. (If -NONE state ,.so and if more than one . state ALL procedures.that are applicable.) Consider each-condition-
sep ar atel y. -
~ RCIC: initiated on;a valid-initiation signa LB.:RWCU'heattexchanger room temperature is^100 deg C. ' RBSVS 'ini tiated- on a valid initiation' signa D. ' All MSIV's close. due to a valid main steam line high radiatio E. Suppression pool temperature reaches.95 degF. during a HPCI'
full' flow-test surveillanc . Jh N' ! \ L
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4 ; P .GUESTION.:
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7.0 ( 2. 50 ) - Concerning SP'29.020.01,-ALTERNATE SHUTDOWN-COOLING EMERGENC l; : PROCEDURE:-' BRIEFLY DESCRIBE the basic flowpath f or cooling water : to the ~ -(1.5)
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reactor- while. in -alternate shutdown cooling. INCLUDE in your-
. description.HOW core decay heat is ul timatel y remove ' B. STATE the preferred; pump:for use during' alternate shutdown- .(1.0) ' cooling. EXPLAIN your answer.'
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DUESTIONY ';7510' .(3.00) ."
, =The.reactorLis at: 100% power when a complete-loss'of'both normal- 'd - and station'. reserve' power occurs. In accordance;with SP 29.015.01,. *
LOSS,OF OFFSITE POWER:
;. JA.; STATE ALL the immediate operator (actions. require (1.5)
B.. BRIEFLY. STATE the. response of each:of the fallowing systems:. (1;5) P.
I 1.fReactor protection. system (RPS)
'l2.: Nuclear _ steam' supply shutoff system.(NSSSS)- : 3.- Reactor building standby ventilation system :(RBSVS)
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LdbESTIO .7'. 1 1 -(3.00)
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The; reactor?is operating at 100% power when a crack develops'on the main condenser expansion joint _ causing a rapid decrease in
. condenser vacuum. In (accordance with SP. 29.012.01, LOSS OF j CONDENSER ~ VACUUM EMERGENCY PROCEDURE: STATE"FOUR(4) aut'omatic actions that directly occur due to .the (2.0)
loss: of. vacuum.11NCLUDE setpoint If'the cause of the vacuum loss had been . a loss of - sealing -(1.0) steam,-~ subsequent actions of.SP 29.012.01- direct the operator-
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to open.the main condenser vacuum breakers. EXPLAIN THE
' REASON for this ste y P
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,--; - : .. 8 ADMINISTRATIVE PROCEDURES,,_CgNgillgNS z Paga 34
: .. AND LIMITATIONS < .
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QUESTION B.01 (3.00) The reactor is at 100% power with the "C" RHR pump motor (3.0) disassembled for an upper motor bearing replacement. A surveillance test was just completed which revealed the HPCI-pump suction automatic transfer from the CST to the suppression pool on CST low level to be inoperabl . STATE ALL ACTIONS required by plant technical specification INCLUDE ALL LCO's that are applicable to the present plant status, e l l [ ;
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a-I QUESTIDA: 8.0 (3.00)
e The' reactor is' operating at 100% power whenithe electrical i _ supervisor / reports that the specific gravi ty. f or the Division 2 l :125. vol t B1' battery pilot cell is 1.19 ,A.' . STATE ALL ACTIONS required by plant technical specification (1.5)
. INCLUDE all applicable LCD' '
B. STATE-ALL'! ACTIONS required if-the electrical. supervisor _als ( 1. 5 L
' reported that the Division 3"125_ volt C1 battery'had a terminal voltage'of 128 volts while on float charge. INCLUDE all -)
applicabl e LCD' ; I i l l i j
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-QUESTION 'B.03 -(i.50)
STANDING' DRDER NUMBER 30 provides specific ' guidance: concerning'- operation: withi the 5% -law power license-in effec A. STATE the maximum allowable average. core' power f or- any (0.5) transien (0. 5)
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LB. DESCRIBE HOW core' power 11s to be determined from availabl . plant instrumentation.
" C. ; STATE' the maximum allowable average power if the main (0. 5 ) : generator is synchronized to the gri , l
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QUESTION -- ; 8.04' .(1.00)~ 1 _ l
- It'ls discovered-.today, December'13 day shift--(O800-1600), that- (1.O) .
a monthly surveillance test due on Tuesday, December 6 mid shift- i (0000-0800),' was'not performed. The surveillance test had been perf ormed on- time- f or the past 5 months. If' the surveillance test is performed today on day. shift,- WILL'the time interval for'this _ test have been vi ol ated? (YES OR'NO). EXPLAIN your. answer.
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QUESTION 8.05 (2.00) During a HPCI surveillance test the NSO neglected to monitor (2.0) suppression pool water temperature and allowed it to rise to 112 degF. In accordance with plant technical specifications, the mode switch was placed in the shutdown position, the HPCI surveillance secured and suppression pool cooling commence The reactor is now in hot shutdown with the suppression pool at 104 deg WOULD it be a violation of technical specifications to now commence a reactor startup (YES OR NO)? EXPLAIN your answe Ref erence all applicable LCO's.
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I j QUESTIDW- 8.06- (2.00)
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'all . operational conditions as follows:
P; OP CON CHLORIDE LIMIT 1 <= 0.2' ppm-2,3 <=~O.1 ppm all other times .<= 0.5 ppm A.! EXPLAIN'WHY.the chlorice limit for cold shutdown is higher (1,0)
- ' than for power operation EXPLAIN WHY the chloride limit for startup is lower than . (1.0)
for power operations.. s ,
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QUESTIDA B.07 (3.00) Concerning the EMERGENCY PLAN IMPLEMENTING PROCEDURES (EPIP): CLASSIFY.the following events. INCLUDE the event category in (2.0) your classification. (use only the inf ormation provided) 1. ATWS condition, reactor power 30%, main turbine on-line, SLCS failed to initiat . Unauthorized person has occupied the remote shutdown panel roo . Reactor scram on low level due to both feed pumps trippin Reactor level reached -50 inches and was restored to normal level band with HPCI and RCI B. STATE TWO(2) conditions that require station evacuation in (1.0) accordance'with EPIP 1-6, EVACUATIONS.
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-QUESTIDS 8.08- (2.00)
l Concerning.SP. 12.035.01, CONTROL OF LIFTED LEADS AND JUMPERS: i' A.. STATE WHEN a. lifted lead must_have a station equipment' (O.5)
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cl earance . permi t' (SECP) . affixe STATE WHICH' on-duty personnel can' grant permission for (0.5) . approval or lifting of an LL& . , C. A permit is not required if a jumper is installed or a lead (0.5) l is lifted momentarily. DEFINE " momentarily" as used cin l :- reference to an LL& D.. STATE HOW LONG a lead can remain lifted before a permit must ( 0. 5) ~ be issued if the-lead was lifted as a sign-off step in an
' approved station procedur . ?
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QUESTION B.09 (3.00) Concerning SP 21.004.01, MAIN CONTROL ROOM-CONDUCT OF PERSONNEL: A. STATE WHO can relieve the Watch Engineer of the control room (1.0) command funtion during operational conditions 1,2,3 and during operational conditions 4, B. STATE WHO may manipulate reactivity control (1.0) C. STATE the responsibilities of the first licensed control room (1.0) operator (NSO/ NASO) during an abnormal plant condition. INCLUDE in your di scussion the NSO/NASD's primary concer .
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LQUESTIO = 8.1 (2.00) For each ~of' the_ f ollowing scenarios, INDICATE _.(YES-DR NO) -i f : a- (2.0)
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1. hour noti fication ' to .the NRC is required . in accordance wi th'
.SP 12.009503, REPORT'OF ABNDRMAL'CONDITIDNS-'(RAC):AND LIMITING CONDITIONS.0F DPERATIONS'(LCO).
. The. reactor'is at 100% power _when both control: room ~ air
- conditioning systems become inoperable..
l:I 'B.1The reactor scrammed.due'to operator error _fwhile ranging the'IRM's during.a reactor startup..: C. The Watch Engineer declares an unusual' even D. Drywell pressure,is 2.0 psi , t'
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DUESTIDA- 8.11 (2.50) Concerning SP: 12.006.01,~ STATION PROCEDURES-PREPARATIONS, REVIEW, APPROVAL, CHANGE REVIEW AND CANCELLATION: ANSWER 1TRUE OR FALSE for each of the following statements: Surveillance procedures are not required _to be preformed (0.3) , step-by-step as long as the intent of' the surveillance is
.
strictly adhered to.
l B. Routine procedural actions that are f requently repeated do not (0.5) require the procedure to be presen C. A temporary procedure change niay be valid with er4 7- a verbal . ( O'. 5 ) approval f rom the pl ant management staf f us'th J we-iff*- Jacum/=4*, . D. Temporary procedure changes have a maximum lif e- of 14 days (0.5) unless approved as a permanent procedure chang E. Temporary procedure changes may be initiated by ANY plant (0.5) staff membe ,
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O e EQUATION SHEET 1
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l ' I f a ma , y = s/t Cycle efficiency = (Net work out)/(Energy in)
w = ag s = V ,t 4 1/2 at t E = me , , KE = 1/2 my a = (Vf - V,)/t A = AN A = A,e"**
,
PE = agn
.
Vf = V, + at w = e/t , A = an2/t.1/2 =.0.693/t1/2
'
W = v A ~ 2 *1/2'## * EI*1 M}I*bIl '. A= s0, , [(t 1/23 * I*b)3 AE = 931 am -
""Y avA ' -
t=ge* , o Q = mCpat . , _ . _ _
~= =
k=UAAT' i * Pwr = Wfah , I*Ih~"**/M
! = I,10~
-
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P s'P*10 "#I*) , HVL = -0.693/u .
'
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. SUR = 26.06/T s SCR = S/(1 - K,ff,)
'
, CR x = S/(1 - Keffx)
SUR = 26c/t* + (s ,o)T CRj (1. - K ,ffj) = CR2( ~ eff2}
.
T = ( t*/o) + [(8 - o V Io 3 ~ M = 1/(1 - K,ff) = Gj M, T = s/(o - s) . M = (1 - K ,ff,)/(1 - K,ffj)
'
T = (s - o)/(Io) SOM = ( - K,7f)/K,ff a = (K ,ff-1)/Keff = def/K,ff L* = 10 seconds . I = 0.1 seconds-I o = [(L*/(T Keff)3 + [8,ff/(1 + IT)] - Id l1*Id P = (t4V)/(3 x 1010) Id 2 ,2gd2 -
~
jj 22 I = aN R/hr' = (0.5 CE)/d2 (,,g,73)
.
l R/hr = 6 CE/d2 (feet) ,
'
Water Parameters l
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Miscellaneous Conversions 1 gal. = 8.345 lb . 1 curie = 3.7 x 1010dps
..= 3.78 liters
'
i kg = 2.21 lbm 1 ga 1 ft ' = 7.48 ga hp = 2.54 x 103 Stu/hr Oensity = 62.4 lbrIi/ft3 1 mw = 3.41 x 106 Stu/hr Density = .1 gm/cm3 lin = 2.54 cm : Heat of va'porization = 970 Stu/lem *F = 9/5'C + 32
~
k Heat of fusion = 144 8tu/lbm *C = 5/9'(*F-32) 1 Atm = 14.7 psi = 29.9 in.' H BTU = 778 f t-lbf 1 ft. H 2O = 0.4335 lbf/in. ' i -
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EgulgS teNQ_IdEgdggyNgdlCS
,- .
i l- -j i ANSWER 5.01 (3.00) .
;
CONSTANTS: density of fluid = 62.4 lbm/ft3 1 BTU = 778 ft-lbf Cp = 1 BTU /lbm-degF Hp = Pout-Pin ; a. Pump Head-Hp'= (Pout-Pin)/6 (0.5)
= (1050-650)x144/62.4 = 923 ft (0.1)
I Ideal Work- ! Wp, ideal = Hp x flowrate (0.5)
= 923 x (5.8 x 10E6) = 5.4 x 10E9 ft-lb/hr (0.1)
I Input Power-Wp, actual = Wp, ideal / efficiency (0.5)
= (5.4 x 10E9)/O.80 = 6.8 x 10E9 ft-lb/hr (0.1) Power converted to heat-Q = Wp, actual - Wp, ideal (0.5) = (6.8-5.4) x 10E9 = 1.4 x 10E9 ft-lb/hr (0.1)
Convert to BTU:
= (1.4 x 10E9)/778 = 1.8 x 10E6 BTU /hr Delta T across pump- - delta T = Q/ (flowrate x Cp) (0.5)
g
= (1.8 x 10E6)/((5.8 x 10E6) x 1.0) = 0.31 degF (0.1)
REFERENCE LP: HL-901-SH1 Lesson 3 pages 4-58 to 4-61 OBJ: HL-901-SH1 Lesson 3, CB-5 KA: 293OO3 K1.23 (2.8/3.1) 291004 K1.05 (2.8/2.9) 291004 K1.13 (2.6/2.7) 291004K113' 291004K105 293OO3K123 ..(KA's)
: (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) - - - - -
_- -
. ~ . ' Ei__IHEgBy_gE_NgCLE88_EQWEB_EL@NI_gEEB911gNg Pag 2. 46 ff; EM91pSt eyp_IgEggggyyeg1CS * , ,. , . ANSWERJ 5.02 .(3.00) (
DECREASE (0.5) L; ( 2: required at ch) h 1..Immediately-,the' loss of feedwater flow causes a~ decrease in moderator.subcooling (which introduces negative dk/k into the core.)
2. When f eedwater flow dropu bel ow 20%, the recirc. pumps will auto runback to 30%. (The decrease in core flow causes an. increase in voiding which also adds negative dk/k into core. ) Decreasing level in the downcomer will reduce the available head for core circulation and will result in decreased core flow, (and thus resctor power will decrease.)
- REFERENCE LP: HL-900-SH1 Lesson 12 pages 7-187 to 7-192 HL-658-SH1 pages 11,15 DBJ a ' Hl.-900-SH1 Lesson 12, CG HL-658-SH1, ED-CC KA '259001 K3.12 (3.8/3.9) ' 293008 K1.34 (2.9/3.1) g 292000 K1.20.(3.3/3.4) 259001.K3.06'(3.1/3.1) 259001K306 293OOBK134 292OOBK120 259001K312 ..(KA's)
: ANSWER 5.03 (1.50)
k ( any 3 0 0.5 each ) L 1.. Vessel heatup
^
u Vessel cooldown Recirculation pump start
" Hydrostatic testing Tensioning reactor head bolts li a .
!]- f e
(***** CATEGDRY 5 CONTINUED ON NEXT PAGE *****)
m !>
:q., . - , . wz -
-
.
.
, . . _ .
J3 .1
.
55I -THEOR','OF'NUCl', EAR POWER PLANT OPERATION ' Pcga 47 c' FEUIDS 1ANp_TfERMQDYNAMICS-t.
-
, ,,s- ,
I ' REFERENCE , LP: HL-908-SH1 Lesson 8.pages.B-160-to 8-168 Technical; specifications 3.4.1.4, 3.4. ,OBJ:' HL-708-SH1 Lesson B, 1, 3 - KA: 293010 K1.04 (2.9/3.2)
- '293010K104 ..(KA's) ' ANSWER 5.04 (2.00).
1. TRUE ( 0. 5) : Using P=Poe(t/T) yt ..
-
sq (0.5) JT=t/ (I n (P/Po) ) = 9%vi n (4) = 65sec (0.1 ) . The peri od dE!*P$2:r . was : caused /by negati ve . reacti vi ty (0.9).
added from the temperature increase of the coolan REFERENCE'
:LP: HL-9007 SH1 Lesson'15'pages 7-231 to 7-232 *
OBJ: HL-900-SH1 Lesson'15, CA-1 KA: 292008 K1.13 (3.8/3.9)
.292008 K1.12 (3.6/3.7)
..
4: 292OOOK112 292OOOK113 ..(KA's) ANSWER 5.05 -(3.00) RGAF = FRTP/MFLPD (1.0) MFLPD = 6.7/13.4 = 0.50 - (0.5) RGAF =~(48.Q/100)/O.50 = 0.96 40.5).
.B. N (0.5) The reactor is not at a thermal limit value of'LHGR (0,5)
' (13.4 kw/ft is thermal limit for LHGR)
i s 4e (***** CATEGCRY 5 CONT)NUED ON NEXT PAGE *****)
' ;
t-
9 __IHEggy_pE_NUgLE@B_EgdEB_EL@@l_9EEB811gN 1 Page 48
'
ELulpptegp_IHEgdggyN@Digg
- .
REFERENCE , LP: HL-904-SH1 Lesson 1 pages 10-9
HL-904-SH1 Lesson 3 pages 10-28 to 10-32 OBJ: HL-904-SH1 Lesson 1, CA-3 HL-904-SHL Lesson 3, CD KA: 293009 K1.07 (3.1/3.7)
>
294001 A1.15 (3.2/3.4) 294001K115 293OO9K109 ..(KA's) ANSWER 5.06 (3.00) DECREASE INITIALLY then returns to ORIGINAL PRESSURE (0.5) EHC will compensate by throttling TCV's (0.5)
(accept slight decrease due to less steam flow theref ore less pressure drop in steam lines) DECREASE (0.5)
SRV flow f rom the steam lines is upstream of the flow (0.5) venturis therefore the flow indicator will see less-flow through the steam lines
- INCREASE INITIALLY thp#cd Nv 4 Wn returns to slightly below ORIGINAL (0.5)
LEVEL A 40 3 b N "I Level would initially " Swell" due to the pressure "'drop then (0.5) it would " Shrink" on the repreusurization.- ' "-
^"'a
-
,
*
(accept return to orighnal level) D -
A-REFERENCE LP: HL-201-SH1 page 12 HL-902-SH1 Lesson 3 pages 3-54 Lo 3-57 OBJ: HL-201-SH1, E
.HL-902-SH1 Lessan 3, practice probl em 3 KA: 291002 K1 07 (3.2/3.2)
29?OOB'K1.22 (3.5/3.6)
'z39001 A1.07 (3.7/3.7)
239001 A1 08 13.8/3.8) 23*?OO1 A1.09 (3.5/3.4) 293OO1A109 293OO1A100 293OO1K107 292OOBK122 291002K107
' ..(KA's) .
e (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
- - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ ___ ______
4 5:__IHEgBy_QE_UgC6E88_EgWEB_EL@NI_gEEB@llgN1 Pcgp 49 EbM19S1 0Ng_IHEgdggyN8dlCS (
. , : ( ANSWER 5.07 (JA10)
d olch; A. FALSE F -4&rSt-
<mren t is calibrated at O psig, higher *"' (Since the in press ould give indication of a level that was lower r n actual.)
B. TRUE (0.5)
(Since the instrument is calibrated with no jet pump flow, with LPCI injecting the indicated level would be pegged high.)- ,
l REFERENCE LPs HL-9BO-SH1 Lesson 7 page 7-16 OBJ: HL-980-SH1 Lesson 7, CF KA: 291002 K1.09 (3.3/3.3) 295031 A2.01 (4.6/4.6) 293001 K1.03 (2.5/2.7) 293001K103 295031A201 291002K109 ..(KA's) 2' ANSWER 5.08 (2.50) s A. CPR = CP/ actual bundle power (0.5) CP = the bundle power that would cause DNB (or transition (0.5) boiling) somewhere in the bundle B. Reactor pressure is DECREASED (0.5) As pressure is decreased, the enthalpy required to cause (1.0) vaporization increases due to the point of operation on the Mollier diagram. Since more power is requireed to cause vaporization, the critical power level increases, i l
.- (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
L____ _ _
L Si__IHggSY_gE_ NUCLE 98_EgWEB_EL9NI_QEEB911gN z Pcg5 50 )
"
ELuiggteND_IHE6dQgYN@dlC@ 11
* , e l : REFERENCE LP: HL-904-SH1 Lesson 1 pages 10-15 to 10-20 OBJ HL-904-SH1 Lesson 1, CA-4,CF-3 KA: 293009 K1.18 (3.2/3.7)
293009 K1.23 (2.8/3.2) 293009 K1.24 (2.7/3.2) 293009 K1.25 (2.7/3.2) 293OO9K125 293OO9K124 293OO9K123 293OO9K118 ..(KA's) ANSWER 5.09 (2.00) A constant flur is possible due to source neutrons (1.0)
(intrinsic, photo-neutron, or installed sources) It allows neutron level to rise high enough to make the (1.0)
effects of source neutrons less pronounced on the rate of power increase. (accept: by letting counts stabilize it is possible to see if the 3 conditions for criticality are present) REFERENCE LP HL-900-SH1 Lesson 16 pages 7-258 to 7-262, 7-273 to 7-274 y DBJ: HL-900-SH1 Lesson 16, CA,CG KA: 292003 K1.01 (2.9/3.0) 292008 K1.04 (3.3/3.4) 292008 K1.05 (4.3/4.3) 292OO8K105 292OO8K104 292OO3K101 ..(KA's) ANSWER 5.10 (2.00) (' ' TRUE (0.5) If at high power and shallew rods were inserted, (0,5) the positive - reactivity f rom void collapse (0.5) could more than offset the negati've reactivity from inserting low worth control rods.(0.5)
,
.*
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
I
-
-. -- :s - . - - ,,
l 5- ' THEORY OF NUCLEAR POWER PLANT OPERATION 1 Pago 51 , 7- FLUIDS AND t THERMODYNAMICS .j
> . . .
l
'
I REFERENCE i LP: HL-900-SH1 Lesson _13 page 7-206 OBJ: HL-900-SH1 Lesson 13, CB-1,CB-2,-practice problem 13 '
.HL-900-SH1 Lesson-12,.CG' HL-900-SH1 Lesson-15, CG-3 "
KA: 292008 K1.20 (3.3/3.4) y 292005 K1.04-(3.5/3.5) 1 292OO5K104 292OO8K120 ..(KA's) h
<
ANSWER 5.11 (2.00) h INCREASE (0.5) The highest; xenon l concentration will be.in the center of th , core where the highest neutron flux previously existed.(0.75) This will1 now suppress the flux in the center of the core and increase
'the flux in the area of periphery rods, thereby increasing their worth. (0.75).
l' L REFERENCE
'
LP:-HL-900-SH1 Lesson 11 pages 7-153 to 7-154 HL-900-SH1' Lesson 13 page 7-209 / s ' OBJi HL-900-SH1-Lesson'11, CB-1,CB-2
- - HL-900-SH1 Lesson'13, practice problem 6 KA: 292005 K1.09-(2.5/2.6)
292006 K1.OB (2.8/3.2) 292OO5K109 292OO6K108 ..(KA's) ! q
'
h.
n
:
.
e k
,
L-6 (***** END OF CATEGORY b *****) i l.: 1 l' L ' c_ _ _ _ - _ _ _ . _ _ . _ _ - _ - - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ -
- _ - _ _
_ _ _ - - _ _ - _ _ _ - _ _ ---. .
.
,
;6i__PL9NI_g @lEdg_QEglGN _CQG16QL t t_@NQ_lNEIBUdENI@IlgN: P gr 52 h:
t
... ..- . . , ' ,. 'A N S' W E R 6.01 (3.00)
A.'The load selector increase / decrease PB's (0.5)'are used to generate a control valve demand (0.5) (this' changes turbine
. speed which changes generator output frequency) ~
B. CV's throttle and. are f ully closed at 105%. speed (0.5) 90 RPM X 1.11 = -100%- (0.25) IV's' throttle between 105 and 107% speed and are f ully closed at 107% speed (0.5) 126 RPM X 2.77 = -350 (0.25) C. FALSE (920+3O+55 = 1005'psig steam dome) (0.5)
-REFERENCE LP: HL-657-SH1 pages 9,10,11,13,14,22,23 OBJ: HL-657-SH1, B-2,B-6,D-2,E KA:241000 K1.08 (3.6/3.7) 241000 K1.09 (3.1/3.4)-
241000 K5.04 (3.3/3.3) 241000 K1.24 (2.7/2.8) 241000 A1.13 (2.7/2.7) 241000A113 241000K124 241000K504 241000K109 241000K108
..(KA's)
y P ANSWER 6.02 (3.00)
' . CRO pump B (0.5)
2. Feeder to.480 V bus 112 (0.5) B. The core spray initiation logic will provide a LOCA signal to EDG 101 and EDG 103. (0.5) EDG 101 will continue to operate and EDG 103 will start but EDG 103 will not load. (0.5) Load shedding occurs on bus 103. (0.5)' Bus loading sequence will commence on but, 101 and 103. (0.5)
(,EDGtol .,of*Ik M ) .
W
.
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
. _ . _ _ _ - - - - _ - - _ _ _ - _ _ _ _ - _ _ _ -
6,3 ,_P ANT _@Y@Iqd@_Qggl@@t_ggNI6pL t _@@Q_ly@l6Udgyl@IlgN Page 53
, , < .' ,
REFERENCE LP: HL-307-SH1 pages 18,21,22 HL-309-SH1 page 24 OBJ: HL-307-SH1, B-1 s: HL-309-SH1, B-1 KA: 264000 K1.07 (3.9/4.1) 264000 K3.03 (4.1/4.2) 264000 A3.05 (3.3/3.5) h ~ 262001 K3.01 (3.5/3.7) 264000A305 264000K303 264000K107 262OO1K301 ..(KA's) ANSWER 6.03 (2.00)
(0.5 each)
A. TRUE B. FALSE C. TRUE D. FALSE REFERENCE LP: HL-133-SH1 pages 4,7,8,10,14 OBJ: HL-133-SH1, B,C,E KA: 295016 K2.01 (4.4/4.5) 295016 GOO 5 (3.4/3.5)
,
295016 GOO 7 (3.1/3.4) 295016 GOO 7 295016 GOO 5 295016K201 ..(KA's) ANSWER 6.04 (2.00)
(4 9 0.5 each)
1. MSIV closure not in RUN 2. TSV closure < 307. power 3. TCV fast closure < 30% power 4. APRM C/S with IRM U/S net in RUN 5. APRM 119% fixed not in RUN
.-
i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
--_ _ _ - _ _ _ _ _ - _ - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ ___ _ _ _ _____ _ ______ _ _ __ _
__ _ _ _ - _ _ _ - a
'i61__P(@NI_Sy@IEM@_DESlGN ...
t _CgNIB06t_@yD_IN@lBUMENI@llgN1 Pcg2.54~
,
s-
* ' ,, ,-
L REFERENCE' LPs HL-611-SH1.page 36 HL-603-SH1 page-23' OBJ: HL-611-SH1, C,D HL-603-SH1, B-2 KA: 212000 K4.12-(3.9/4.1)
:212OOOK412: ..(KA's)
ANSWE .05 (3.00)
~A.' Reactor: level would' INCREASE initially (due to HPCI injecting) (0.5).
( As level increases a level error signal will develop) which causesLRFP speed to DECREASE (0.5). This will c'ause level to DECREASE #ar.d stabilize at a point 2 -' rc-s,h?(Where'W 4*" *I
'
the level error signal compensates f or the HPCI -injection flow) (0.5) .
. ' Total'feedwater flow will. DECREASE by the amount of HPCI. injection (0. 5) . -
B. Single-element control does not-take into account the steam flow and' feed flow error signals. It controls on' level error only.. (0.5) Final level will remain-the same. (0.5)
. % o<l3 :. I w REFERENCE LP: HL.-656-SH 1 pages.23,24,28 P 3 .OBJ: HL-656-SH1, C-2,C-3
'
'KA: 259002 K1.16 (3.4/3.5) 259002 K4.10-(3.4/3.4)
259002 K1.03 (3.8/3.9) 259002'K1.04 (3.5/3.6) 259002 K4.09 (3.1/3.1) 259002.A3.02 (3.4/3.4) 295002K104 295002K103 295002K410 295002K116 ..(KA's) ANSWER 6.06 (1.50) 1. Open nin. flow valve MOV-045(A) (0.25) 2. Start RHR pum (0.25) 3. ~ Verif y reactor pressure is ;330 psig or less (0.25)
~
4. Open LPCI inbd isolation valve MOV-037(A) (0.25) 5. When RHR flow is 2400 GPM, ciose min. flow valve MOV-045(A) ( O'. 25 ) ,
'l
-
:
1
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
l i l I
~ , . . . . . x .m . = = - - = =
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"
REFERENCED , a, y J LP J HL -704-SH1 .pages"32,33; , . 7' e' , 'OBJ:1HL-204-SH1,.CE-12
" *
KA::203000LA2.14 (3.8/3.9).
<
W.~_203OOOA214 ..(KA's) ( '
,
'
_
'
ANSWERi 6.07s l (2. 00)1 , , W '- (0.5' each) E
'1.' Verify proper rod sequence p -.2._ Verify proper. rod 1 position- .
_ .
,
3.1 Verify: rod blockLmonitor operabl . Use ' P-1. printout to(verif y thermal L 11mits
, ,
p ' REFERENCE ., , LP: HL-606-SH11 .page 21 E 20BJ:lHL-606'SH1,-CE - [ ' LKA:"215002 K4.01-(3.4/3.5)' 4 4
. ;215002 GOO 5?(3.1/4.0) , . -215002 GOO 5" :215002K401 ..(KA's)
Lq
'
, - ANSWER'
, '6.0 . ( 3. 00 )
O A. : 1. . phosphatesL can. destroy recombiner catylists ,
( 0. 5) ,
12. auxiliary boiler may - become contaminated (with
'
(0.5)
reactor pressure > 125 psig.)
B.11. - provides early detection of f uel leaks '
' ( 0. 5) -
12. . when . retreatment ~ radi ation - level s 'are compared to .(0 S) system discharge radiation levels, the efficiency ~of the'offgas: system _can be determined y . . I C.. -The - condenserc air: ; removal pumps bypass'the offgas. system .
. ;.
W ,
. theref ore the exhaust does not: have any H2 rer.ombination -(0.5? :
and the activi ty level Hof the ' exhaust is not reduced prior J to its release. ( 0. 5)
..) + '#
$ g
.-
h (***** CATEGORY 6 CDNTINUED DN NEXT PAGE *****)
<
l, . T 1Em.___'.m f
-_.___il__E___'.___ . _ _ . . _ _ . _ _ __
. _ . _ - ._ - - - _
,
m n, 5 ,
!6? PLANT-SYSTEMS DESIGN _CgNTRQL i _AND t INSTRUMENTATION' . Pag 2356' ,- :,. ..= ,
v f-
{
'
:
. .,: .;
REFERENCE g :LP:JHL-701/714-SH11 pages 11,26,31' E OBJ: HL-701/714-SH1, A,B, practice problem C KA:-271000 A1.12 (3.1/3.5).- j
' .'271000 kl.01*(3.1/3.1)- )
271000 A1.13 (3.2/3.7) - {
.271000 A1.02 (3.0/3.6)
271000 G010 (3.1/3.2) Y
'271000A102 -271000G010 271000A113 271000K101 271000A112 . . . ( KA ' s) -
n Ec . . .
' ANSWER' 6.09 (2.50)
, < (0.5 each)
1F RWM h
, B..BOTH C. RWM -
D. RWM E. RWM I REFERENCE
'LP: HL-607-SH1 pages 3,6,8,18 HL-609-SH1 page 3 OBJ:.HL-607-SH1, A,B,C,E-6 >
g-l .
,HL-609-SH1, A e KA: 201004 GOO 4.(3.7/3.7) 201006' GOO 5 (3.2/4.0)
201006 A3.01-(3.2/3.1) 201006 K1.07 (2.8/2.9) 201006 K1.OB (3.2/3.3) 201006A301 201006 GOO 5 201004GO04 . . (KA's) ANSWER 6.10 (3.00) '
. FALSE . (fee.l pm ~%. . Peu <sle Talegen} . A. IRiE 4tml y :ci rwsicti ::p;bi1.. ty ::- l e:t ? (0.U)
'B) Feedwater flow drops (to about 80%)(with all other pumps i n varying degrees of cavitation). (0.5) CBP P-072A and .RFP P-OO6A trip on low suction pressure. (1.0) RPV water level decreates and will initiate a recirculation 3p runback to 45% speed at 33.5 in. (0.5) Reactor power L/L decreases and water level is restored with the plant u stabilized at abnut 67% power. 10.5)
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REFERENCE , LP:/.HL.-103-SH1 -pages'26,27,32,33
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256000iK3.04-(3.6/3.7) 256000 K3.11 '(3.9/3. 9) 256000K311- 256000K304:: -295019K20 ..(KA's)-
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;AND RADIOLOGICAL CONTROL-.
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: ANSWER: 7.0 .(1.00)
~
-The TCV.will fully open once the auxiliary oil pump is started.(0.5)
-Iff the .TCV was f ully opened and then the steam to- turbine valve was ifully opened, there is the possibility that the HPCI turbine might
' overspeed or develop excessively high discharge- pressure. (0.5)
REFERENCE LP: SP 23.202.01 HIGH PRESSURE COOLLANT INJECTION HL-202-SH1 OBJ: HL-202-SH1, CD-2 KA: 294001 A1.02 (4.2/4.2) 206000 K4.11 (3.4/3.5) 206000~A1.07 (3.7/3.6) 206000 A1.09 (3.5/3.4) 206000'G010 (3.9/3.8) 206000G010 206000A109 206000A107 206000K411 294001A102
..(KA's) .
ANSWER 7.02 (2.00) Flowrate greaterethan 2000 gpm prevents the min. flow valve from opening.(0.5) This could result in pumping the RPV j, water or the fuel pool water to the suppression pool . (0.5) RPV level must be greater than +43 inches to assure a natural circulation flowpath (0.5) To provide a redundant method of decay heat removal at RPV levels that natural circulation is not possible, two loops of.RHR are placed-
, in shutdown cooling.(0.5) -REFERENCE l
LPt SP 23.121.01 RESIDUAL HEAT REMOVAL SYSTEM pages 4,12 HL-121-SH1 OBJ: HL-121-SH1, CF-3,CF-7
-
KA: '294001 A1.02 (4.2/4.2) 205000 G010 (3.2/3.3) 205000 K1.02 (3.6/3.6) 205000 K3.03 (3.8/3.9) 205000K303 205000K102 205000GO10 294001A102 ..(KA'c) )
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- _ _ _ _ _ - _ _ _ _ PROCEDURES - NORMAL _t ABNORMAL _g EMERGENCY
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Page 59 AND RADIOLOGICAL CONTROL
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ANSWER 7.03 (1.00) Excessive neutron flux noise levels may occu (0.5) B. YES (0.5) REFERENCE LP: SP 22.004.01 OPERATION BETWEEN 20% AND 100% POWER OBJ: NONE FROM TRAll4ING MATERI AL KA: 294001 A1.02 (4.2/4.2) 202001 AO.10 (3.5/3.7) 202002 K4.02 (3.0/3.0) 202OO2K402 202OO1A010 294001A102 ..(KA's) ANSWER 7.04 (3.00) The SRO is satisfied that the work can be performed with adequate safety for stetion personnel (0.5) and equipment (0.5) B. Jo'os/ tasks that are routine or repetative (0.5) . Health physics ssection (0,5) 2. Watch engineer (0.5) .., D. FALSE (,requi red when exposure i s > 1000mR/hr) (0.5) REFERENCE LP: SP 12.012.01 RADIATION WORK PERMITS OBJ: NONE FROM TRAINING MATERIAL KA: 294001 K1.03 (3.3/3.8) 294001 K1.04 (3.3/3.6)
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ANSWER 7.05 (2.00) The highest suppression pool temperature at which initiation ) of RPV depressurization will not result in exceeding, the {
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suppression chamber design temperature (0.5) or the primary containment pressure limit (0.5), before the rate of energy transfer from the RPV to the containment is within the capacity of the containment vent. (0.5) B. TRUE (0. 5) REFERENCE LP: SP 29.023.03 PRIMARY CONTAINMENT CONTROL HL-944-SH1 page 31 - OBJ: HL-944-SH1, E,F KA: 295026 K1.02 (3.5/3.8) 295024 K1.01 (4.1/4.2) 295026 GOO 7 (3.4/3.8) 295024K101 295026 GOO 7 295026K102 ..(KA's) ANSWER 7.06 (1.50) n When all SRV's are closed and D/W pressure below 1.69 psig energy is no longer being transferred to the primary containment thereby challenging its integrity. (1.0) Power has been reduced enough at this state therefore a further reduction in l evel is not required. (0.5) REFERENCE LP: SP 29.023.07 LEVEL / POWER CONTROL OBJ: NONE FROM TRAINING MATERIAL KA: 295037 G012 (3.9/4.6) 295037 K2.09 (4.O/4.2) I 295037 K1.02 (4.1/4.3) 795037K102 29503?K209 295037G012 ..(KA's) i
,
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ANSWER 7.07 (3.00) A.'High drywell pressure is indicative of a line break (0.5) and requires RPV water level control . (0.5) B. With all control rods at or beyond position 02, the reactor will remain shutdown under all conditions irrespective of coolant temperature (0.5) and any baron that may have been injected. (0.5) C '. ADS initiation may result in the injection of large amounts of relatively cold, unborated water.(0.5) The power excursion f rom the reactivity addition could cause substantial fuel damage.(0.5) REFERENCE LP: SP 29.023.01 RPV CONTROL HL-944-SH1 pages 4,6,13 OBJ: HL-944-SH1, A,D,E KA: 295024 GOO 7 (3.6/3.9) 295024 GOli (4.3/4.5) 295037 GOO 7 (3.7/3.9) 296037 K3.02 (4.3/4.5) 295037K302 295037 GOO 7 295024G011 295024 GOO 7 ..(KA's) +' ANSWER 7.08 (3.00) SP 29.023.01 RPV CONTROL (0.5) B. NONE (0.5) o.22) ,sP x q . op . o 1 P2: c,our cour20 4 (0 3d C. SP 29.023.01 RPV CONTROL orNSP 29.023.O2 SEC CONT CONTROL (Gr5+g g D. SP 29.023.01 RPV CONTROL ( 0. 5 ) film (o.22) E. SP 29.023.03 PRI CONT CONTROL (0.5) REFERENCE LP: SP 29.023.02 SECONDARY CONTAINMENT CONTROL SP 29.023.01 RPV CONTROL SP 29.023.03 PRIMARY CONTAINMENT CONTROL OBJ HL-944-SH1, B KA: 295032 G011 (4.1/4.2) 295033 GOli (4.0/4.5) 295035 G011 (3.9/4.2) 295031 G011 (4.2/4.6) 295025 G011 (4.2/4.3) 295026 G011 (4.3/4.7) 295031G011 295035GO11 295033G011 295032G011 ..(KA's)
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' . ,; < ANSWER 7.09 (2.50)
A. One LPCI or CS pump takes suction from the suppression pool (0.3) and discharges through an open SRV back to the suppression pool . (0.3) Heat is removed f rom the suppression pool by RHR in suppression pool cooli ng. (0.3) Heat is removed from the RHR heat exchanger by reactor building service water (0.3) and transferred to the LI Sound. (0.3) It is preferred to use one LPCI(0.5) for cooldown due to the internal RPV flowpath consideration.(0.5) REFERENCE LP: SP 29.020.01 ALTERNATE SHUTDOWN COOLING OBJ: NONE FROM TRAINING MATERIAL KA: 295021 A1.04 (3.7/3.7) 295021 GOO 7 (2.9/3.2) 295021 K3.05 (3.6/3.0) 295021K305 295021 GOO 7 295021A104 ..(KA's)
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ANSWER 7.10 (3.00) . verif y auto actions and manually initiate any that f ailed (0.5) enter SP 29.010.01, EMERGENCY SHUTDOWN PROCEDURE (0.5) notify system operator and determine from him if the (0.5) Holtsville or the onsite 20MWe turbines have started . RPS deenergizes (0.25) causing a SCRAM (0.25) NSSSS deenergizes (0.25) causing an isolation (0.25) RBSVS initiates 'O.25) uhan oower i_s rac+c-cd ty the EO9' 'O. 254-(o 5) REFERENCE LP: SP 29.015.01 LQ3S OF OFFSITE POWER HL-309-SH1 pages 23,24 OBJ: HL-309-SH1, C,D-6 KA: 295003 G010 (3.9/4.1) 295003 A1.03 (4.4/4.4) 295003 A2.04 (3.5/3.7) 295003A204 295003A103 295003G010 ..(KA's)
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AND RADIOLOGICAL CONTROL o s' ANSWER 7.11 (3.00) l . main turoine trip (0.25) 22.5" HgVAC (0.25) RFPT trip (0.25) 20.0" HgVAC (0.25) MSIV's (and MSL drains) isolate (0.25) 8.5" HgVAC (0.25) bypass valves close or remain closed (0.25) 7" HgVAC (0.25) B. vacuum is broken as quickly as possible to prevent excessive ccoling of the turbine shaft and seal (1.0) ' REFERENCE LPr SP 29.012.01 LOSS OF VACUUM HL-124-SH1 pages 14,15 HL-701/714-SH1 page 23 OBJ: HL-124-SH1, CD HL-701/714-SH1, E-4 KA: 259002 GOO 7 (3.2/3.2) 259002 K2.02 (3.1/3.2) 259002 K2.03 (3.5/3.6) 259002 K2.04 (3.2/3.3) 259002 K2.05 (2.7/2.7) 259002K205 259002K204 259002K203 259002K202 259002 GOO 7
..(KA's)
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ANSWER 8.01 (3.00) 1. LPCI T/S 3. action (1.5) Restore INOP pump to operable status within 7 days or be in hot shutdown within the next 12 hours and cold shutdown within the following 24 hour . HPCI T/S 3.3.3 action b (1.5) Table 3.3.3-1 3.c action 36 Place the INOP channel in the tripped condition within 1 hour (HPCI will remain operable if the suction in manually aligned to the suppression pool within i hour.)
I REFERENCE LP: TECH SPECS 3/4.5.1 ECCS TECH SPECS 3/4.3.3 ECCS ACTUATION INSTRUMENTATION OBJ: HL-202-SH1, CJ
.KA: 294001 A1.08 (3.1/3.6)' 294001 A1.03 (2.7/3.7)
206000 GOO 5 (3.6/4.3) 206000 G011 (3.7/4.4) 206000G011 206000 GOO 5 294001A103 294001A108 ..(KA's) E l ANSWER 8.02 (3.00)
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' A. T/S Table 4.8.2.1-1 (0.5) The battery may be considered operable provided that within (1.0) 24 hours, all category B measurements are taken and found to be within their allowable values and that all A and B parameters are restored to within limits within the next 6 day B. T/S 3.8.2.1 c (0.5) T/S 4.8.2.1 Declare 125 volt C1 INOP (0.5) Restore'the inop battery and/or charger to operable status (0.5) L within 2 hours or be in hot shutdown within the next 12 hours L and cold shutdowr within the f oll owing 24 hours.'
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~ KA E294001 A1.OB'(3.1/3.6)' 294001 A1.02-(4.2/4.2) I L294001 A1.03 (2.7/2.7) -263000.0005 (3.1/3.8)
263000 G011 (3.2/3.7)' 1263OOOG011~ 263OOOGOO5 294001A10 A102 294001A108
..(KA's)
T
! ANSWER 8.03 '(1.50) %- '(0.5)
B. average of all APRM readings (0. 5) L .75% (0.5)
-REFERENC 'LP: STANDING ORDER. NUMBER'.30 OBJ: NONE FROM TRAINING MATERIAL :KA: 294001 A1.02-(4.2/4.2)
294001 A1.03 (2.7/2.7)~ 294001A103 '294001A102 ..(KA's) L ANSWER 8.04 (1.00) NO . ( 0. 5 ) T/S 4.0.2 allows 25% extension .O.25(31 days)=7.75 days '(0.5) REFERENCE' -
.
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LP: TECH SPECS 4.0.2 SURVEILLANCE REQUIREMENTS
.DBJ: NONE FROM. TRAINING MATERIAL'
KAs 294001 A1.02 (4.2/4.2) 294001 A1.03 (2.7/3.7) 294001 A1.OB (3.1/3.6) 294001A108 .294001A103 294001A102 ..(KA's) ' l .- l (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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2:__0DdlN1 SIB @llyE_PBQCEQUBE@t_CQNQlllgNgt Pcg2 66 L T 6NQ_Lidll@llgNS L . . i ANSWER 8.05 (2.00) YES (1.0) T/S 3.0.4 is applicable which states that entry into an OP CON (0.5) shall not be made unless conditions are met for LCO without reliance on the action statemen T/S 3.6.2.1 a.2 requires <=90 degF for Op Con.1,2 (0.5) REFERENCE LP: TECH SPEC 3/4.6.2 DEPRESSURIZATION SYSTEMS OBJ: HL-402-SH1, D KA: 294001 A1.OB (3.1/3.6) 223001 GOO 5 (3.3/4.1) 223001 G011 (3.3/4.2) 223OO1GO11 223OO1 GOO 5 294001A108 ..(KA's) ANSWER 8.06 (2.00) Chloride stress corrosion increases as temperature ince.?ases (1.0) During startup, the condensate and feedwater returning to the (1.0)
- vessel has a higher O2 concentration. Higher O2 promotes
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stress corrosio REFERENCE LP: TECH SPECS 3.4.4 CHEMISTRY HL-908-SH1 LESSON 2 page 8-26 OBJ: HL-908-SH1 LESSON 2, 4,6 KA: 294001 A1.08 (3.1/3.6) 294001 A1.14 (2.9/3.4) 259001 G010 ( 3. 2/ 3. 3 )- H 259001G010 294001A114 294001A108 ..(KA's)
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' ' ' - .AND LIMITATIONS.-
b
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V ANSWE 'O.07 (3.00)
~
g . Site' area. emergency (No.9) Event categor (0.66)
" General emergency- (No.3) Event category 13 (0.66) Unusual even (No.1) Eventfcategory 4 '( 0. 66 ) , (any 2 @ 0.5.each)'
1.-general emergency 2. discretion of Emergency Director . safety hazard such as toxic gas, flammable gas.and/or fire. affect widespread. areas onsite 4. ~ actual ;or potential significant release of radioactive materials to the environment o REFERENCE' LP:-EMERGENCY PLAN IMPLEMENTING PROCEDURES SD-980-LP1-
- DBJ: SD-980-LP1, CM KA: '294001 A1.16 (2.9/4.7)
294001A116 ..(KA's)
F . ANSWER B.08 (2.00) a lead that is normally exposed to voltages above 130 (0.5) watch engineer or watch supervisor (provided the watch engineer (0.5) is kept fully informed) C. as long as the wire in question is intended to remain in the (0.5) worker's han D.-one(1) working shift (O 5) i' REFERENCE LP: SP 12.035.01 CONTROL OF LIFTED LEADS AND JUMPERS OBJ: NONE FROM TRAININcs MATERIAL KAs.294001:K1.02 (3.9/4.5) 294001 K1.07 (3.3/3.6) 294001 A1.02 (4.2/4.2) 294001 A1.03 (2.7/3.7)
'294001K102 '294001A103 294001A102 294001K107 ..(KA's)
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ANSWER 8.09 (3.00) A. OP CON 1,2,3 an i ndi vi dual (other than STA) with an active SRO (0.5) OP CON 4,5 an i ndi vi dual with an active SRO.or RO (0.5) . holders of active RO or SRO (0.5) trainees in an established training program but only under (0.5) the direct supervision of an RO or SRO and only when authorized by the watch engineer C. The NSO/ NASO to panel 603 shall take immediate acti'ns necessary for reactor safety (i . e. reactor scram followup, vessel level and pressure control, ECCS initiation) (0.5)-He shall ensure auto actions take place or initiate these actions manually. (0.25) His primary concern is to keep the core covered. (0.25) REFERENCE LP: SP 21.004.01 MAIN CONTROL ROOM-CONDUCT OF PERSONNEL OBJ: NONE FROM TRAINING MATERIAL KA: 294001 A1.03 (2.7/3.7) 294001 A1.09 (3.3/4.2) 294001A109 294001A103 ..(KA's)
ANSWER 8.10 (2.00) A. YES (0.5) 8. NO (0.5) C, YES (0.5) D. YE9 (0.5) R>IF'dRENCE LP: GP .12.009.03 REPORT OF ABNORMAL CONDITIONS (RAC) AND LIMITING CONDITIONS OF OPERATIONS (LCO) OBJ: NONE FROM TRAINING MATERIAL KA: 294001 A1.16 (2.9/4.7) 290003 GOO 3 (2.9/4.1) 206000 GOO 3 (3.1/4.4) 206000 GOO 3 290003 GOO 3 294001A116 ..(KA's) i
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- ( O. 5)'-
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, REFERENC . L P s-: S P J 12;006.'01- STATION PROCEDURES-PREPARATIONS,-REVIEW, APPROVAL,
CHANGE REVIEW:AND CANCELLATION OBJ:'NONE FROM TRAINING MATERIAL
, ' KA: 294001 - Al' 01 - (2. 9/3. 4) 294001 A1.02'(4.2/4.2) 294001 A1;03 (2.- 7 / 3. 7 ) ! 294001A103 -.294001A102 .294001A101 .' . ( K A ' s ) .
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