ML19353A172
| ML19353A172 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/18/1980 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Collins P Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101070379 | |
| Download: ML19353A172 (4) | |
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B ALTIMORE G AS AND ELECTRIC COMP ANY P. O. B O X 1475 B ALTIMORE M ARYL AN D 21203 AaTwun C. LumovaLL,JR.
v u.., m.
se u June 18, 1980
'aul F. Collins Chief, Ocerator Licensing Branch Office of ;'uclear Reactor Reculation U.S.
!uclear Regulatory Comission Washinnton, DC 20555
Dear Sir:
In answer to Harold R. Denton's letter to All Dower Reactor Anplicants and Licensees dated itarch 28, 1980, we are submitting for your review the nodifications to our Licensed Ocerator Trainina Dronran.
These modifications include trainino in heat transfer, fluid flow, and themodynamics; use of installed clant systens to control or nitigate an accident in which the core is severely damaged; and increased empha-sis on reactor and plant transients. These nodifications are detailed in Attachnents 1, 2, and 3.
Ooerations Instructors currently hold NRC licenses and are, therefore, subiect to the same requalification attendance requirenents as are other licensed operators. This requalification program assures that the instructors are cognizant of current operating history, problems, i
and chances to procedures and administrative linitations.
If there is a need for further information, please contact the Training Grouo at Calvert Cliffs.
Very truly yours 1
j 21 s
~~'T A. E. Lundvall, 3r.
Vice President-Supply "EL/J:iV/qia
. -Heat Transfer, Fluid Flow, and Thermodynamics -ilitication of Core Damaae -Reactor and Plant Transients 8 101070 3
a ATTACHMEilT 1 HEAT TRNISFER, FLUID FLOW N1D THEPJ10DY:1/NICS I.
Introduction II.
Course Outline A.
Procerties of Fluids a t'atter B.
Fluid Statics C.
Fluid Dynamics D.
Heat Transfer by Conduction, Convection and Radiation E.
-C;iange of Phase-Boilina F.
Purnout S Flow Instability G.
Reactor Heat Transfer Linits III.
Plant Specific A.
Heat Balances S.
Scecific Pump Characteristics l
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a ATTACHMENT 2 f1ITIGATI0tl 0F CORE DAMAGE I.
Introduction II.
Course Outline A.
Incore Instrumentation 3.
Excore Instrumentation C.
Instrument Failures D.
Chemistry E.
Radiation Monitoring F.
Accident Analysis i
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ATTAC:i.'tEi!T 3 REACTOR NID PLNIT TRAHSIEilTS A.
Safety Functions 3.
Reactor Trio / Turbine Trip C.
Matural Circulation D.
Excess Feedwater Flow E.
Excess Steam Demand F.
Loss of Main Feedwater 3.
Loss of AC Power 4.
Partial Loss of Reactor Ccolant Flow I.
Steam Generator Tube Ruoture il. Letdown Line Break K.
CEA L'ithdrawal L.
CEA Droo l
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