ML20107A179
Text
...
O J
4 9
s4 e k To:
Janos P. O'Reilly-Directorate of Regulatory Operations -
Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 From:
Jersey Central Power & Light Company Oyster Creek Nuclear Generating Station Docket #50-219 Forked River, New Jersey 08731
Subject:
,i, Preliminary Abnotwal Occurrence Report No.
1.3 2a I
The following is a preliminary report being submitted in complianco with the Technical specifications, paragraph 6.6.2 Preliminary Approval:
k / ' \\. -
Afi/
10/31/73 f
VJ. T. Carroll, Jr.I
Date cc: Mr. A. Giambusso j
Q 1
h 9604120173 960213 PDR FOIA l
DEKOK95-2S8 PDR
]
= - -
1
,q VtelinLnary U
Aban=al Occurrence Report No. 73-28 StfPIPCT:
!.eskoge from the reactor building closed cooling water system to the discharge canal via the service wat< r system.
l This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraph 1.15C. Notification of this event, as required by the Technical Specifications, para-graph 6.6.2,a, was made to AEC Region I, Di!s storate of Regulatory Operations, by telephone on Tuesday, October 30, 1973, at 1625, and by telecopier on Wednesday, October 31,1973, at 1605.
SInlATION: On Septerd)er 14, 1973, leakage into the reactor building closed
- cooling water system from a leak in the fuel pool cooling system l
was identified and Isolated, As a result, the closed cooling water system activity was analyzed on several occasions with the highest concentration calculated to be 1.9x10** pCi/a1 in a j
sample taken on Septoder 26, 1973. The activity was identified fjj to be primarily es"" And ca ",
l
)
Plant personnel subsequently began investigating methods of re-t moving the activity from the closed cooling water system, but these have not yet been implemented.
On October 19, 1973, leakage from the closed cooling water system was noted as indicated by a decreasing level in the reactor building closed cooling water system surge tank of up to 4 4,5"/hr (v1.0 gpm).
. kO3D Sdf
~
i Preliminary Abnormal Occurrence Report No. 73 28 October 29, 1973 j
.CAUSE:
The cause of the release was leaking tubes in the 81-2 reactor building closed cooling water heat exchanger.
j RDEIDIAL ACfl0N:
1 Operations personnel immediately began isolating various com-l ponWnts of the closed cooling water system in order to identify i
the source of leakage. As noted before, the rate of leakage from the system was conservatively estimated to be 1.0 gpm. On October 22, 1973, a sample of the closed cooling water system indicated a concentration of 6.JX10 8 pCl/mi, Indicating that leakage had occurred during the period of Septeder 26, 1973 through October 22, 1973. On October 29, 1973, RBCCW heat i
exchanger'81-2 was. identified as the source of leakage. Prior to this date, there was not assurance that Icakage was to the environment. A sample taken on October 30, 1973, following repairs to the heat exchanger, was analyzed to be 2.5x10"' UCi/ml.
SAFETY SIGNIFICANCf!:
A full investigation into the safety significance is now under-way.
It is apparent, however, that the release rate of liquid i
- effluents into the dischargo canal was significantly below the concentrations given in Appendix B, Tabic II, Colmen D, of 10CFR20.
(10CRF20 limits -are 9x10 uC1/ml for Cs88' and 2x10"' pC1/mi for Cs!".)
ff uwk
'\\'
Date:
10/31/73' JFivuated by: