ML19220B480

Examination Rept on Senior Operator License Issued for TMI-2.Written Examination Encl.Operating Test Administered 740213

ML19220B480
Person / Time
Site:	Crane
Issue date:	02/20/1974
From:	Collins P, Conner E Office of Nuclear Reactor Regulation
To:	METROPOLITAN EDISON CO.
References
NUDOCS 7904260305
Download: ML19220B480 (2)

Text

{{#Wiki_filter:- 9._ i \\ -I 1 -4 i. /N G ~ ~ U. S. ATCMIC ENERCY CCM.!SSION / EXAMINATICN RE? ORT _ Applicant License applied for: RO / / SRO IhALLY.Adl lA $f.tacd Location un k $ wA e. s b Reactor Currently a licensed operator here? Yes C No / / WRITTEN EXAMINATION: Operator (Section 35.21): Ad=inistered by E Z (~oe,- + Dated'Avaived/ / Gradad by k kl / Grada b,[ A A7 7%, 3@d I, CN, Df/ %, EP/%, FY, Gk%. Category Gradas: 'i Senior (5ection 55.22): Ad=inistered by /_N ( Date 7!/7/MWaived / / cra.2d by E4( Grada 77,7% Ca.egory Grades: HS9%, IT:,. WI,b7%) Lid. U OPERATING TEST:-(Section 55.23) Date 3 V Waived / / ~ - Adninistered bj 3.. Het Q Cold M ' EVALUATICN: Senior Operator - - PASSED N FAILED / / Operator - - - - - PASSED / / FAILED / / CCPJiENTS : RECCMMENDATION: N Approve for,(Senior) ({pargtpy) License / / Do not approve for (Senior) (Operator) License 2!/4!7 EXAMINER , #vy y _;.o DATO: ISSUE (SINICR) (C3&i9t~Fd LICENSE _[ k y[fd[7'[ Chief,CperatorLicensing3 rad-h, L NOTE: The operator and oral examination check sheet =ust be completed for each applicant. If he has failed the operating and oral test at the senior level, the check sheet should be ec=pleted to indicata his evaluation at the operator level. ,,0^1GQ d'. 7904 2 6 0 sos { S

a I._. 3 J -5 b_ I s = ~ 4 CPERATING AND OPAL EXAMINATION SU!O'.ARY REPORT

• PACE SRO RO NO.

1. Operating Demonstration k((((((((((((((//) 1.1 Pre-startup and Instrument Checks b l l l 1.2 Conao1e Operaeion k//[///((/(([/(((([/ 5 l l a. Manipulations 6 l } l b. Understanding k((((/(((((((((((([ 2. Faei1ity Equipment a. Major 5 l I b. Auxiliary 9 l l c. Engineered Safeguards Systems 6 l l //((/[/////[//(((([/A 3. Ins:rm.cneaeion a. Nuclear l l l b. Process 6 l 4 Reactor Protection l l l ((/((//((((((/((M 5. Procedures a. Normal M l 7 b. Abuurmal S c. Emergency M l l7 l 6. Reactivity Effects (Except Console Operation) l l 7. Administrative Requirements _M l l 7 l 8. Emergency Plan f l l l 9. Radiation Proccetion S l l l 10. Responsibilities 6 l If an SRO applicant is unsatisfactory at the SRO level, complete the RO column to evaluate his adequacy at the RO level.

• For each uns.itisfactory ("11") J i.s t the p: ige number (s) of the operating-oral ex iniination notes on which the unsatisf actory responses are explained.

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2 s > ] '(NRC FCRM 157 U.S. NUCLEAR REGULATO RY CCMMISSICN LICENSE APPLIEO FCR: 7 (10 75) d rh RC SRQ f URRENTLY A L:CENSEO CPERATOR *E2E? EXAMINATION REPORT vEsp NO C i APPLICANT'3 NAME REACTCR OCATICN e. ./ / / WPITTEN EXM ACMINISTERED BY QATE i WAeVED I CPERATCR GRACEOSY GRACE EV A LV ATICN e (SECTICN 55.21) g PASSED C CATEGORY GRACES j A % 3 %C %0 %E %F G F AILED C ACMINISTER EO SY: CATE () e b[ M /4 - 5 - / W AIV ED C SENICR CPERATCR GRACE 0 y: GRACE,, EV ALU ATION tSECTICN 55.22) /. ' - 'Y 2 M 'k' N-DASSED 'E CATEGCRY GR ACES .V. I '/ f F2. +;' - 'J s i L .s ,A,LE0 CPERATING TEST ACMINISTERED SY: CATE WAlvEO k PASSEO C (SECTICN 55.20) ' AEU C NOT C CCLD C COMM ENTS ~ I f A E FOR SIGN ATU R E f* hm 4 LICENSE M CPERATCR LICENSE C f /' R ECCMMENCATICU ib dN- [Y / CC NCT APARovE FCR A '. v / E X A MI N E R { ATE '/ i, SF.NIOR LICENSE C C9TR ATC A LICENSE SC SIGN ATU R E \\ / ICUE SENIC A LICENSE C PE R A TO R Lt CE *4",E C / 3 t [ ,.4 k,/ [/'(( LJCENSE c. t def. Ccerator L. censing Brancn / /

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3 /~N q O i '3 U. S. NUCLEAR REGULATORY CC:'.1ISSION i SENIORRkACTOROPERATORLICENSEEXAMINATION L Three Mile Island rf Facility: B/M PWR Reactor Type: i .Date Administered: 8/15/78 Examiner:_J.J. Holman Applicant: INSTRUCTIONS TO APPLICANT: Use separate paper for the answers. Staple question sheet on top of the answer sheets. Points for each question are indicated in parenthesis after the question. Category % of Applicant's % of Value Total Score Cat. Value CATEGORY i /2.Ff IIf H. Reactor Theory is pn /f i

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Radioactive Materials on E Handling, Disposai ar.c Hazards /1 #/ f3 7 J. Specific Operating 15 - 20 Characteristics /I2 Ph57 K. Fuel Handling & Core 15 20 Parameters 15 20 /76 4#, 7 L. Administrative Procedro Conditions and Limica;i: 75 100 d8.Y f#, I' Totals Final Grade: f# 8 79-1S3

j l O n A 4 i H. REACTOP. THECRY (15) H.1 If 1", excess reactivity is added to a reactor that is critical, the resulting startup rate is very high. Explain in detail why the addition of 1." negative reactivit y to a critical reactor results in a low negative startup rate. (2.0) H.2 The Doppler coefficient is the result of reactor fuel absorbing neutrons and causing a negativa reactivity effect. a. Explain why the absorption of a neutron by the fuel is a negative reactivity effect rather than a neutron induced fission of the nucleus. (1.0) b. What eventually becomes of the nucleus that absorbs t' e neutron in Ocppler capture? (1.0) H.3 The control rods at TMI are operated in an overlapped sequence. a. Why is operation with overlap desirable? (1.0) b. What characteristic of the rods and/or core makes overlap desirable? {1.0) H.4 A reactor has a count rate of 30 CPS when it has a, Keff of 0.95. What is the expected count rate when Kef f is 0.98?__Shcw how.you _ _... _.. arrived at this answer. (2.0) H.5 Attached Figure H.5 is a pcwer history of a reactor like yours. (NOTE: Ignore any procedural violations). Assume neither the SAXON nor the ROBAL program is available for your use. You desire to know how much Xenon will be in the core at criticality. a. Show, on the Figure, how you would divide the pcwer history into power blocks for a hand calculation. (1.0) 6. Fill in the necessary information in the following tabb: (1.5) t5 LOCK " POWER TIME AT POWER (hrs) DECAY TI"E (hr-) c. Discuss the factors which must be considered in coming up with an answer and describe hcw the information in 5 b above is used in the solution to your problem. (2.0) H.6 Explain the affect the selection of the omper moderator / fuel ratio has on the reactivity coefficients of your reactor. (2. 5 )

a J, I. RADI0 ACTIVE MATERIALS HANDLING, DISPOSAL AND HAZARDS (15) I.1 List the Tech. Spec. limits on Specific Activity for the primary and secondary systems. a. For each of the limits, describe the bases for the values. ( 1. 5 ) b. Explain 5 and how it is detamined. (1.0) I.2 After several years of operation, 'it beccmes necessary to replace a pump seal water filter. During the removal, the filter falls to the floor. The area is immediately evacuated. A subsequent survey indicates a 2 REM /hr dose rate 3 feet from the filter. You are in charge of the recovery operation. Explain how you would perform the salvage operation. Include precautions to minimize personnel exposure, educe the spread of contamination and clean up after the salvage is ccepleted. (3.0) I.3 a. A smear is taken on a calibrated pressure guage which was used in the waste disposal area. Determine if the guage may be I returned to the instrument shop. (1.5) Smear area 100 cm2 Background 18 CPM S minute count 300 Scaler efficiency 17% b. Explain how you would take smears on such a guage. (1.0) I.4 Assume a reactor coolant leak develop s in the reactor building. a. What are the limits on reactor coolant system leakage as a function of ldcation or identity of the leakage. ( 1. 0) b. Assuming the leakage collects in the reactor building sump, describe in sequence what happens to the water frcm the sump to its ultimate disposal. (2.0) c. Prior to entering the reactor building to search for the leak, what installed monitoring system (s) can be used by the inspection team to evaluate the radiation levels? (1.0) I.5 According to the Environmental Tech Specs, what conditions apply to purging of the reactor building? (2.0) 1.6 An operator asks you if it's true that a curie of any material, if a point source, will read 1 R/hr at one meter. What is ycur answer? (1.2) I e v./ scr ( .sd

.~ ~ j n m J. SPECIFIC CPEPATING CHARACTERISTICS (15) J.1 Assume the plant is at full newer, all ICS stations are in automatic mcde and one of the feedaater pumps trios. Sketch and explain the behavior of the parameters shown on Figure J.1. (3.0) J.2 During a routine reactor startup, the reactor power level reaches 15% and T avg is seen to deviate from its progranted value of 581.F. What is this indicative of (consider for both above and below SBl* F) and what could you do about it? (2.0) J.3 Assume the reactor is brought critical at 10-8 amps for a reactor startup. a. Se. Figure J.3. Shcw where, for a Xenon free com, the nomal critical rod position would be. Justify your choice. (1.0) b. What must be done if an insertion limit is violated? (1.0) c. The insertion limits in Figure J.3 are based on three criteria, one of whicn is to maintain the minimum shutdown margin. What are the other two? (1.0) snes fa % e d. What PE-_'- -. ~..t is the, shutdown margin specification. bar:d ::? (1.0) J.4 Overpressurization of the primary system while the plant is in a cold shutdavn condition is-a serious incident. a. What overpressure protection is provided at TMI to prevent or lessen the ccnsequences of an overpressurization incident? (1.0) b. What administrative precautions are also taken for this type of incident? (2.0) c. What problem could a pressure spike cause if it occurred later in og life? (1.0) J.5 When accelerating the turbine to 1800 RPM, the amplitude of mechanical vibration changes, a. What. causes the high amplitude vibrations? (0.5) b. How can the operator tell if the vibraticns experienced are normal or 2bnomal? (0.5) c. How does the coerator cope with the normal high amplitude vibrations? (0,5) d. A reder of the s taff suggests stcpcing at one of the hich 2nlitude vibraticn points to take data. As shift suce mis'r, ..ili you allow this? Explain your reasoning. ,4

.. 3 3 m q. j K. FUEL HANDLING AND CCRE PARAMETERS (15) K.1 A heat balance is used to calibrate the power range amolifier outputs. Sciefly describe hcw this heat balance is performed, including all of the necessary factors to be considered. (2.0) K.2 a. Frequent mention is made in the Tech Specs and elsewhere of the terms ONERand Power Peaking. Explain the meaning of these terms and why they are selected as liciting conditions. (2.0) b. The Reactor Protective System is designed to trip the reactor before CNBR falls to 1.30. Suppose the protective system malfunctions and dcesn't trip the reactor until a DNBR of 1.25 exists. Dces this mean all the fuel rods will fail? Explain. (1.0) c. How are Hot Channel Factors and DNSR related? ( 1.0) K.3 With regard to Tech Specs that are applicable during the refueling period: a. Is it permissible to continue Core Alterations without at least one CHR pump in operation? Explain. (1.0) b. Is it permissible to conduct a containment purge-while-re--- ------- fueling? Explain. (1.0) c. Is it permissible to move maintenance items through the equip-ment hatch during refueling? Explain. (1.0) K.4 Attached Figure K.4 shows Power Doppler Coefficient vs. Core Power. Why does the coefficient vary as shown, especially for EOC? (2.0) K.5 Initial fuel loading at most PWR's develcps as a " slab". Typically, the source is located in the center and the fuel is loaded cutward. Temporary chambers (A & B) are located in the vessel and subcritical multiplication clots are made for each section of the slab loading. For the loading shown in Figure K.3, a. sketch the expected plot of 1/M for each chamber, and (1.5) b. explain any difference between the two plots. (1.5) K.6 What acministrative recuirements are imcosed when handling heavy objects (> 15 tons) with the fuel handling crane? (1.0) - -~ [ e

~ 5 L. AC M ISTRATIVE PROCEDURES. CCNDITIONS AND LIMITATIONS (15) L.1 a. What must be done if the number of operable fire detectors is less than that required by Tech Specs? (1.0) l b. What must be done if the requ1md sprinkler system for a protected area is inoperable? (1.0) L.2 Describe the process by which all shift personnel are made awam of facility modifications. (1.0) For ew.o L.3 What are the responsibilities of the Shift SbpvWhar with regard to review, approval and clearing RUP's? (2.0) L.4 Assume the reactor trips due to a spurious signal. Af ter completing the immediate and subsequent actions of the trip procedure, what further administrative actions are required of the Shif t Supervisor? (2.0) L.5 10 CFR Part 55, Operator's Licenses, defines an operator as any individual who manipulates a control of a facility. a. Define " control" as it applies to this definition and give two examples. (1.0) I b. Is it necessary to be a licensed operator to manipulate a control? Explain. (0.5) i c. Assume an operator was injured during a motorcycle accident. He is disabled for 5 months. Under what conditions can he return to normal duties?. (1.0) L.6 Assume you are the senior operator in charge of your shift. For each situation listed below: i) prdvide your immediate action respcnse and fi) include the reason for your action. Assume rated pcwer operation unless specified. a. During a test of the containment isolation valves, one of the valves begins to leak at the packing gland when it is in the open position. The test engineer suggests he can "back seat" the valve by holding in the "open" relay at the motor control center. (2.0) b. Af ter repairs to one of the diesel generators, the unit is tested prior to returning it to service. One of the fuel injector lines ruptures and sprays fuel oil on the hot exhaust and is ignited. The auxiliary onerator leaves the area and notifies you. List the action of the control rocm personnel and you as the Shift F;renan. ICI I N L CCNTI'iUED Ctlll EXT PAgg 78-3bb

~ = ..z w..- 9 -3 1 L. ACMI!!ISTRATIVE PRCCEDURES, CC!!DITIC!1S A!!D LIMITATIC.'lS (15) CC.'tT I.';UE D Fov w L.7 As Sh i f t Sw= r" ': ", list the steps you are required to complete when relieving the off-going Shif t L;e..ime. (1.5) F.% e S 1 1 0 r o}..- d a i. .. u s b

j e3 -j Table 1. MISCELLANEm.5 10 CFR 20 App %ix E 3 l Table 1 11 Tsble II Energy Col 1 Col II Col 1 l C l II MEV per Air Vater l Air ! Water Xsterial Half-Life disinte rstien pc/ml sc/:11 4c/=1 I s e /r.1 -6 I -8 A-41 1.83 h 13 2x10 o l kx10 Co-60 53 y 25 3x10-I 1x10-3 1x10-0 5x10 '5 i l I-131 8.1 d 0 36 9x10 6x10-5 l lzl0-10 3x10-I r.r-85 10.8 y 0.04 lx'10-5 l 3x10-7 -7 i -8 -4 Ni-65 25 h 0 59 9x10 4x10-3 l 3x10 1x10 Pu-239 2.4x10" 0.co8 2x10-12 1,10 -4 -1"l5x10-l 6x10 y 1 o i 4 -3 3x10 *l 1 3x10

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