ML19320A709
| ML19320A709 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/25/1980 |
| From: | Hovey G METROPOLITAN EDISON CO. |
| To: | Jay Collins Office of Nuclear Reactor Regulation |
| References | |
| TLL-302, NUDOCS 8007020534 | |
| Download: ML19320A709 (2) | |
Text
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e Metropolitan Edison Company Post Ofice Box 480 e
Middletown, Pennsylvama 1705' 717 944-4041 Wnter's Daect O'ai %eue June 2 5 1980 TLL 302 TMI Program Office Attn:
J. T. Collins, Deputy Program Director U. S. Nuclear Regulatorv Commission c/o Three Mile Island Nuclear Station Middletown, Pennsylvania 17057
Dear Sir:
Three Mile Island Nuclear Station, Unit II (TMI-2)
Ooerating License No. DPR-73 Docket No. 50-320 Change in TMI Site Discharge Water Composite Sampling Frequencies REFERENCE 1: Telecon to John Collins from S. W. Porter, Jr., of 6/23/80, same subj ec t.
REFERENCE 2: Three Mile Island Nuclear Station, Station Health Physics Drocedure 1699A entitled, " Liquid Release From TMI - Administrative Controls",
Attachnent 2.
A.
BACKGROUND During the early days of the TMI-II accident, a meeting was held between TMI staff, the NRC, and the Dennsylvania Bureau of Radiological Health, with other government agencies present to discuss sampling of TMI Station Liquid Discharge. This discharge point is called 001 on several of the FSAR maps and is known at TMI as the RML-7 sampling and monitoring ooint. This same point is station 13S1 utilizing the off-site Radiological Fnvironmental Monitoring Program polar coordinates. The frecuency of four (4) hours was chosen for taking comnosite samoles and then analyzing them by gamma spectrum analysis. The reason for this frecuency was the fact of the inadvertant TMI-II accident-caused radiocontamination of the IPTS and 1975, as well as the con-cern for the downstream water users.
Later in 1979, the requirement was added to analyze this 4-hour composite sample for gross beta activity because of the fact that strontiums were beginning to become a significant nercentage of the total activity of the Unit-II primary coolant.
Presently, no water is being discharged from Unit II.
All discharges origi-nate only from Unit I.
Discharges only occur in the batch mode, af ter each batch has been carefully samoled by gamma spectrum analysis and by liquid scintillation analvsis for tritium.
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.o-John T. Collina TLL 302 B.
REQUESTED CHANGE FOR THE RML-7 COMPOSITE SMTPLING PERIOD It is requested that the RML-7 continuous composite sample be changed from the present 4-hour period to a 24-hour period.
It is also requested that the long-term composite sample for tritium, low-level gamma scan, gross beta, and strontium -90 be changed from once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to once per month. These changes will be made to Attachment 2 of Reference 2.
C.
JUSTIFICATION No TMI accident produced radionuclides have been seen in the station discharge for almost one year. The downstream water users are now being monitored with continuous composite samplers at the frequency of once per month. The TMI
. station discharge long-term composite sample should be at the same frequency as the downstream water users in order to have a valid comparison of water station sampling results.
The Fennsylvania Bureau of Radiological Health has concurred with this suggested reduction in composite sampling rates as well as the Radiological Controls Manager for Unit I, W. E. Potts, and John Barton, Unit II Superintendant. Also concurring have been J. G. Herbein and W. E. Riethle, III.
Sincerely, yQ W ' Y G. K. Hovey g,
Director, TMI-II GKH:EDF:RH: dad cc:
J. G. Herbein W. E. Potts J. Barton W. E. Riethle, III M. Reilly, PA BRH B. Elam P. Ruhter E. D. Fuller S. W. Porter, Jr.
T. Cintula D. DiIanni B. H. Grier R. W. Reid H. Silver B. J. Snyder V. Stello l
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