ML20107B401
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' l ENCLOSURE DESCRIPTION OF VIOLATIONS Jersey Central Power and Light Company Docket No. 50-219 License No. DPR-16 Certain activities under your license appear to be in violation of AEC requirements as indicated below:
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10 CFR 20.201(b) requires, "Each licensee shall nahe or cause to be made such surveys as may be necessary for him to comply with the regulationa in this part."
10 CFR 20.105(b) requires, "fio licensec shall... create in any unrestricted area... radiation levels in excess of 100 mrem in any seven consecutive days."
Contrary to the requirements of 10 CFR 20.201(b) and 20.105(b), in-sufficient surveys were made prior to November 20, 1972, to demonstrate that the exposure rate at the fence East of the waste storare building was less than 100 mren per seven day period.
10 CFR 20,201(b) requires, "rach licensee shall make or cause to be
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2, made'such surveys as may be necessary for hin to comnly with the regulations in this part."
10 CFR 20.101(b) limits whole body exnosures to three rem per quarter and defines dose to the whole body to include any dose to the lens of the eye, Contrary to the requirements of 10 CFP. 20.201(b) and 20.101(b),
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the shielding glass was removed from the drum handling truck in the waste drun storage area without conducting an evaluation to determine the relative exposure between the whole body (that is measured by the film badge) and the lens of the eye when oper-ating the drum handling truck.
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- b. - Contrary to the requirements of 10 CFR 20.101(b), the exposure records show that twelve men were exposed in excess of three rem during the April - June,1972 quarter.
96'04160291 960213 PDR FOIA DEKOK95-258 PDR
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Technical specifications 3.6(c) states, in part, " Maximum amount of I
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. contained in the radwaste storage tanks outside radioactivity,..
the radvaste building shall not ' exceed 10.0 curies."
above requirement, the amount of radioactivity in l
Contrary to the l
the outside radwaste storage tanka was 13.0 euries and 27.7 curies when inventoried on Autant 18, 1972, and September 20, 1972, 4
respec tive ly.
A JCP&L letter to the Directorate of Licensing dated August 28, 1972, 4.
reporting a previous viciation of Paragraph 3.6(c) of the Technical Specifications stated t'aat in order to prevent recurrence, the alarm setting for the concentrated waste tank would be set no higher than 4
957 to minimize the possibility of overfilling the tank.
Contrary to the above commitment, the concentrated waste tank slarm was set greater than 100% on Novenber 17, 1072.
Technical Specification 3.8 renuires the two isolation condenser loops 5.
shall be 'eperable during power operation and whenever the reactor coolant Para-temperature is greater chan 212"F except as specified in C below.
graph C perm.tts contir.ued operation with one inoperable isolation con-denser for a period not to exceed seven days provided the operable isolation condenser is demonstrated to be operable daily.
Contrary to the reouirements of 3.8 of the Technical Specifications.
l both isolation condensers f ailed to operate on August 9,1972 imme-distely following a planned shutdown.
Technical specification 3.2.C requires that "The standby liquid 6.
control system shall be operable at all times when the reactor is not shutdown by control rods..."
3 Contrary to the requirements of Paragraph 3.2.C of the Technical Specifications, the standby liquid control system was rendered in-operable for a period of approximately eighteen hours on September l
25 and 26, 1972 when the power breaker for the A liquid poison pump The design of the interlock between the two liquid j
was racked out.
poison pumps prevented the other pump from starting when either pump J
was racked out.
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