ML20141K858
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October 2, 1970
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W. R. Stratton, Chairman Oyster Creek Subcoemittee OYSTER CREEK SUBComITLEE MEETING OCTOBER 14, 1970
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The Oyster Creek Subcomittee will meet on October 14, 1970 in Washington, D. C to consider the proposed increase in maximum power level froa.1600 MWt to 1690 MWt, an increase of about 5.6%.
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Regulatory Staf f evaluation was transmitted to members on September 30, 1970.
l The tentative schedule for Wednesday, October 14, 1970 is:
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8:30 AM Executive Session J
j 9:30 AM Heating with the Regulatory Staff 10:00 AM Heating with Jersey Central Power and Light Company 11:45 AM LUNCH 12:45 PM Continue meeting with Jersey Central 3:00 PM Caucus 3:30 PM Adjourn Topics to be discussed include:
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Operating history l-2.
Effects of the power level increase j
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Core spray effectiveness l
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Monitoring reactor vessel integrity 5.
Problems not yet brought to the attention of the ACRS I -
The apolicant will make a 20-30 minute presentation on operating experience and justification for the power increase.
Topics may be added to or deleted from the above list at the discretion of the Subcomittee Chairman.
-Attendance by Dr. Stratton, Dr. Bush and Dr. Hendrie to sluicipated.,,
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Original signed by' dkV '
J. C. EcKinley
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Preisett Oyster Creek p (g Statust Provisional Operating License Issued Operation at increased power requested
Background:
December 12, 1968 ACKS operating license report April 9, 1969 - POL issued H6y 3, 1969 - Initial criticality December 22, 1969 - Coutpleted 100 hr full power (1FJO Hwt) demonstration May 5,1970 - Amendment No. 55 requesting authorisation to operate at 1690 Nwt June 2,1970 - Amendment No. 57 correcting and supplement.
ing Amendment No. 55 l
July 30, 1970 - Amendment No. M, startup test results september 17, 1970 - Amendment No. 63, additional inform-ation in support of Amendment No. 55 September 30, 1970 - DRL report on tha proposed power I
increase October 14, 1970 - Subcocunittes meeting i
DRL's previous review of Oyster Creek engineered safety features and
.I radiological consequences of an accident were based on a steady stata l
power level of 1860 Hwt. On that basis they conclude that operation at 1690 Hwt does not present any significant hasard not previously
,I considered. DRL does plan to require the installation of additional scram signals based on turbine trip and load rejection.
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10/8/70 out>
Form AF.C 818 %v. D-63) us sonenwrwiramtmsorrg1,im.-&as44ee j
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