Reactor Operator Training Program Outline Detailing Course Duration & Tentative Lecture SubjsML20085A716 |
Person / Time |
---|
Site: |
Three Mile Island |
---|
Issue date: |
08/08/1968 |
---|
From: |
BABCOCK & WILCOX CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20085A715 |
List: |
---|
References |
---|
TASK-*, TASK-GB GPU-0519, GPU-519, NUDOCS 8307070081 |
Download: ML20085A716 (5) |
|
|
---|
Category:OPERATOR TRAINING/REQUALIFICATION PROGRAM
MONTHYEARML20154K8351988-05-0303 May 1988 Rev 5 to 7811-PGD-2613, TMI-1 Licensed Operator Requalification Training Program ML20238D8861987-12-14014 December 1987 Rev 3 to 7821-PGD-2613, TMI-2 Licensed Operator Requalification Training Program ML20126A0371985-05-29029 May 1985 Rev 1-00 to Administrative Manual 6212-ADM-2611.04, Fuel Handling Senior Reactor Operator Training Program,Unit 2 ML20100H6351984-08-29029 August 1984 Rev 0-00 to Procedure 1000-POL-1210.02, Gpu Nuclear Records Retention Policy ML20092P5131984-06-12012 June 1984 Rev 1 to Licensed Operator Requalification Program Description (Unit 1) ML20126A0081984-02-10010 February 1984 Rev 0 to Administrative Procedure Manual 4210-ADM-2610.01, Requirements for Certification of Candidates for NRC Operator Licenses ML20041C9691981-12-31031 December 1981 Radiological Field Operations Personnel Qualification Training Program. ML20085B1261979-01-19019 January 1979 Simulator Training Documentation for Met Ed,790115-19. Classroom Schedule Encl ML20085A6391978-02-16016 February 1978 Annual Reactor Operator & Senior Reactor Operator Requalification Exam Results (Cycle 5) ML20085B1141974-11-0303 November 1974 Plant Operations Exam.Simulator Training Evaluation Encl ML20024C8071974-11-0101 November 1974 Plant Operations Exam. ML20085A7161968-08-0808 August 1968 Reactor Operator Training Program Outline Detailing Course Duration & Tentative Lecture Subjs 1988-05-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
[Table view] |
Text
w _ .
~. _
_m_ _
_ ~ , __
t,- - .s .
' Tin .1*.I':e ,
C..*.1Ine . W I-4;
' Operator Traisin , r;.- .
"' .ch . - 2 .- * - f .- (i ? . c c ~*..y i 1. .
Ccur:c dur:.ti::: v:e:: t j ~~
1: :re/Wc:: eit.ecree . tice I Cless SI:c: 2: .c:./cir.zs , .-
'Isti sted, t ize , hr ._
hb.'cet thLthr .
15 F.e ct:.: Fi.ysles ,
Feriev of rescter physics r.s s;;;ied te U.e c'yceirie +
12.~.: dgsica.
13 Ecat ':r .sfer's:-d Fluid flov.
Ecrie.* cf the nuclear pie.t'dcr!, 4:sica ebjectives, res:ter desicn conciderctic s z:1 limitatiens-. .
73 -
Res.:ter Tessel and Intern:Is - .
~
- 1. 3escter vessel dcciCr., r.iteri Is, fabrication, * -
Inspectics,' IIIf1T. - ,
- 2. Eccator internals deceristier, i: sign, =aterials.
y:r;cses. .
3
- Fuel elesents and control rois - design c.sd icbrication. -
.- 13 Pr'-"/ LNp Cc=;onents .. .
S1:plified t'vo-loop he:t t :.:s;:rt1 systes.
Ecseription of4 piping, ;;;;s, a: pressuri'cr.
- 1. s -
2.
- 3. Desica considerations, a:Cyses ; rfo: .ed, materials.
. 1$ ,
0 :e-7:.rcu@. Eters Cencrators
- Ocs:riptie=,peculielities,1.csttrz:stercharceteristles,
=c:ht:Ical deciCn considerati: s, r.1terials, ehesistry .
=cetssities, r.aintensace. ,
. 30 Eateter'/.ux1113./ Syster.s .
It::tienti requirements (:::=212:1 e:ercency).
-l
- 1. .
~
- 2. retics objectives and criteria. .
3 3csic.s a;;rcach an.1 andyses.
- h. Syster-ty-syste descripti::; *pi; cent description,
- a.ra:cesent, parmeters. -
'5 Ipir.e:t access and =aintess:.e. .
e4
$A $ $7 S[>$ $
O 13 2 !>.'>.J .0 ,~7:.U . .
j 7 .,..;.,F q.,6
n _ _ _ _ .
i i
~
.-~.
. l Table *1 (Cc .t '<i)
Sul *e:t l'1tter
.' Esti:2tci ti. e, hr.
Cor.' trol T..d 172'cs
- 1. Der:ri itI:.:4 cf drives. !
- 2. , DescrI;. ::. of c.:ntrol4. . .
Instrd.ca% ticn asi Centrol 30
~
- 1. . nar.ctit d requirc=cr.ts .and deccript100.
- 2. Ir. c rs'.c' ;1 ant cor. trol cystec.
- 3. Nccicar instrumentation and recctor protective cy: ten. .
- k. Pria.:y . Icep n:nnucicar instrumentati:.n.
- 5. B %ctGr Lu;cil$tritZ nCnheuC1ct,. in tr.:st ~,%*.$ %:.
- 6. Ince.re sonitoring systen descriptien,a.i f.:::ti03. ,
l
. 7. 'Au:.csstic dv .a leccinc and on-line ec:;;te;- rn uire ents. , [
.' t Normal.r.d Entrcer.:y Pover Requirements ,
. T.5 [
- 1. Descr1; tion of functier.21 needs, ,
- 2. Proctiures. .
Chemistry- .
, 7.5 g i
- 1. k'r' ster cht:istry application to t!.c nuclear pla.t. 1
- 2. Radiocht:!stry scrisurements. ,
f
.3. Sceplir.; ar.d enc:sical analysis.
[
.. Health Physics .
75
- 1. Radiatica monitoring syste:as.
- 2. Decor.tsmination m:thods c.nd precauticas. '
, ' 3. Administrstive' procedures and controls.
Safety Analysis -
15 1 Potential plant accide.nts and hazsrds. .
- 2. Cencral public protection end. acceptance.
- 3. Ad-inistrative safeguards.
i
- 4. Accider.t analysis. (MHA, MCA, rea:tivity ac:idents,.
- 1. equi;:est failures such as loss of cerlar. f .ov)
Examination and Zeviev T. S
. 'Ity AL 180 a J
I
'. a. ' J . ./ r,',-
i l v ,.)-...: ;, ;. .. c.
cd; .
.,. l . ,
0132 ?
....- I l '
O -~ ~
. . - ~ . . . . .. . - - .
. _ , . . . n ..
f .._
e
/*'*-
"- ' Idle 2 Tc:.L:ti to
~~ Cou-se Outline, Introducticr. .: M :ts: Op ratier.s
. . er.d l'roctice2 h ut:r *:7 tics t
The ht*** Ihc17.5.r hv .i ;;'.:.t C u.ter ?
ra:Ility:
- I.ynchter- ;:, 1 7.u.:.:t
.* Tir.e: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> ;.
I Class size: 6 sen/cJ.sss Estimatei a tir2 tr.
Eutfeet Shtter
- 1. Introdu:ti - Gencral orientatien, building a.i h? %
- rules; c:tline of prccram; intr: duction t,- .Th; IFh
- 6perati c prset-dures and linitsticus.
Cor. trol hi Calibration - Cal'.trate se.fety rs' ty .
d' i 2.
rod-t . -;triod ec.h d; ec=;. .re by e.iterr.ste st2.ed.'
~
Inverse **:ltir.lichtien with Rois - Startic.g vitt's.
2' 3~ shutssv. reactor, obtain reciprocal culti;~.i:stic'n .
4ata as s. fun =tica of rod poultion a:.d ; h . *.s
~
pro'ict critical K sition. .
- h. Inverse N21tittlication vith Fuel - E. '*e f:a1 t,o assc ble a r cv (to the studer.t) core cdr.ficastisc;
^
take and pact data,to prdict the critica" as rs.
Power ristritution Measurecents - Mee;ure ; vs 5 5
.utilizir.; fcils or all-solid ir. core sc=i'::s .a study the effects of local power perturta.icas.
Detecti:n Syste=s '. Experimentally study c;<ratics 10
- 6. .
of varicas radiation actectors. ;
T. Intred:etien to Health Physics - Perfor az;+ ise ts 1% .
to study shieldir.g. inverse square lav, rar;re7* g, .
airtorne rr.dioactivity, a:wi contaminatics fetya-Ion. .
- 8. BA'.*fR ! .d :trination - Tour BA*~ra and oise se c:strol .
rocct c;cra. ion.
~ . . .
9 Recetivi y Iffects - Study the effects cf vs.ricus . 5 sa:ples (u.ra. ium, boric acid solutions , sts.iziess steel, etc.) en the I.PR. . . . . . , ,
- 10. Exa:-instien snd Review - Operating exa.=ist-i.c: am1 C" -
reviev given ty scccone not ascociated .'.h :s:rse _
instructics. If desired, the exa .instics* c r:li te cor.ductci ty a two-man team with cac frcr. .i.e c:sterer.
f 1 .
4
. Dg
.u.,. .1: 9. '.,r.
013~y' M .0..a. .T C'
" - _-_____.____.._/E ______.__.._..___0
-- . . . y.
0-r_
~
Tc. tie 2 (cc.r.t'd)
_v .. . .r .. .s.
tfre, r*. j S 2bjr.e t t.* stter -
I 23
- n. 2:..;:le 0;cru.tica - As c;.crv.t:r er 13:!i t c.*. o;urutcr g
-t e.ir. t!.e rAxima 2 pcecible c;crt*.! . e.v.ric:.ec. i
- .
- .i:.fr.:. of te.n z tart.up as c;.c.-*.*. .c 'ill Ec ealaiued f:t ct:!. student utilizing e.t len .t. ec different .
c:.re c: .fi .trst, ions.
r:-
.w W. . .e
'?.r.; sri =ent airo incluacc tido ns c crst:r sM ar.sistant operator.
- s o;.s.r: cf last operatib; period. ,
e 8 6 'l 9
9 b
G e
G W
e i;
, 9 e #
h * .
e ,
9 >
0
. . . I :.
. = ,
t
'j S
, 6 8 e 9
e 6
e
O e
e 9 e *
. e
09
/
O --
O N .
i=
A* i .
.\. p. .
Q'.']>.*i
~ -=
g $. ,,7 e , , e e . . e e%*
- #4 b e
. ._. _ - . E l '. . . -
1 .
,L Table 3 I,
- s .tutb:e Cutl'nc
- - 'Lecturc 7 n i.:.: :.cri:.c Cp .mt1c:ml I'l..re Of C: ; rs.* t e_T.r ? : t : .- Fr.yr#. . (?hre IV) ,
\ Cirss fi. <.: l' :. n/clus .
Estir.ated
.E 0.;r - * * " < - tice hr.
, ?.es: tor Operation ,
30 Stsrtup, recctivity cor.tr:I g power eperation, trun:isnt operation,' and Jos.< of Ict.d e.1/cr trip.
Tuel Huidlinc , ,
75
- 1. General de:.;ription cf refuelinc, require =ents-on .
operator and sehe'ule.
- 2. Equip m c.descripti (res:ter building,. fuel handlirig .
buildin , .and fuel tre.:ftr syster.). .
3 Detailed refuelir c.:.r::tCu-c. r
- k. Fy,cl stcrage and sht;;isc. .
Estety Ar.22yr.Is .
, 15. '
- 1. 'Polential ple.nt accifer.ts,a.d har.ards (ca2ces and ,
effects). ~
- 2. Core 4.nd cocient* tands:/ rectecticu and analysis. .
3 k.alysis of potential fan.rca ausing release of-radioactivity. .
- k. Occcral public protectics and, accep'.ance. .
~
- 5. Accident preventies (::i?, regtlations, inspections).
- 6. Administrative safecca.r-dz (procedure, technical specifications, opera.. training).
- 7 Accident ana39 sis (fiEA tersus K0A, reactivity accidents, equipment failures su:1. az . loss of coolant flov). .
- d. , Introduction to licerrir.g ;rc.cedure and technical -
specifications.
. Test Program
l
. 1. In5roduction to pre:ri .1 al, startup,' and power ,
operation testing. ,
- l. 2. ,2eview of test spe:iff:a*iens.
l
- 3. Introduction to oi.-si e ;ro:edure r. d tech'niques. .
t e C;erating Procedure: ,
ho Ix*2:instion and Reviev . . 12
119 5
_ . _ _ _ . m. .
, , el. ..i." ... .. I i .9. .4 ' . ' -
O 13 2 }.13J.0 Ml:0 ,
e-..-.=-
,k . . . . h* *
. . -_ -