ML060870633
| ML060870633 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/16/1997 |
| From: | Essig T Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2005-0293 NUDOCS 9701210377 | |
| Download: ML060870633 (2) | |
Text
MEMCRANDUM TO:
January 16, 1997 John Stolz, Director Project Directorate 1-2 Division of Reactor Projects -
I/11 Office of Nuclear Reactor Regulation FROM:
Thomas H. Essig, Chief Original signed by:
Emergency Preparedness and Environmental Health Physics Section Emergency Preparedness and Radiation Protection Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2, OF CONTAMINATED MATERIAL PURSUANT TO 10 CFR SUPPLEMENTAL INFORMATION ONSITE DISPOSAL 20.2002 -
The Emergency Preparedness and Radiation Protection Branch (PERB) has completed its review of the PECO Energy Company's (the licensee) supplemental information, dated December 2, 1996, to its application, dated April 6, :L995, to dispose of contaminated soil, sediment, and sludges on the Limerick Generating Station site pursuant to 10 CFR 20.2002.
In a letter to the licensee dated July 10, 1996, the NRC approved the licensee's application to dispose of the subject contaminated material on the Limerick site.
Subsequent to that approval, during an inspection of the disposal conducted by NRC Region I personnel, it was determined that the characteristics of the disposal area were different from that described *in the licensee's original application.
The licensee committed to submit supplemental information on the disposal site and a revised analysis to the original 10 CFR 20.2002 application. The licensee's supplemental information dated December 2, 1996 was received and reviewed.
Based on our review, we find that the licensee's supplemental information does not alter our original conclusion that the doses calculated by the licensee appear reasonable, are a small percentage of 10 CFR Part 20 public dose limits, and conforms to the requirements set forth in 10 CFR 20.2002 and is
'herefore acceptable. The licensee should be requested to incorporate this supplemental information into its Radiological Process Control Program.
DockAt NOa.
50-362 50-353 CONTACT:
Stephen Klementowicz, NRR/PERB 415-1084 DISTRIBUTION Docket File FRinaldi JWhite RI PERE Reading File HAstwood RNimitz RI TMartin CMiller SKlementowicz TEssig DOCUMENT NAME:
G:\\LIMRICK1.SPK To recozv a copy of this document, Indicate In the box:
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20555-001 January 16, 1997 MEMORANDUM TO:
John Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation FROM:
Thomas H. Essig, Chief Emergency Preparedness and Environmental Health Physics Section (4k9Emergency Preparedness and Radiation Protection Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2, ONSITE DISPOSAL OF CONTAMINATED MATERIAL PURSUANT TO 10 CFR 20.2002 -
SUPPLEMENTAL INFORMATION The Imergency Preparedness and Radiation Protection Branch has completed its review of the PECO Energy Company's (the licensee) supplemental information, dated December 2, 1996, to its application, dated April 6, 1995, to dispose of contaminated soil, sediment, and sludges on the Limerick Generating Station site pursuant to 10 CFR 20.2002.
In a letter to the licensee dated July 10, 1996, the NRC approved the licensee's application to dispose of the subject contaminated material on the Limerick site.
Subsequent to that approval, during an inspection of the disposal conducted by NRC Region I personnel, it was determined that the characteristics of the disposal area were different from that described in the licersees original application. The licensee committed to submit supplemental information on the disposal site and a revised analysis to the original 10 CFR 20.2002 application. The licensee's supplemental information datPd DPcPmhbr 2 1996 was receedl and dreyewed Based on our review, we find that the licensee's supplemental information does not alter our original conclusion that the doses calculated by the licensee appear reasonable, are a small percentage of 10 CFR Part 20 public dose limits, and conforms to the requirements set forth in 10 CFR 20.2002 and 'is therefore acceptable.
The licensee should be requested to incorporate this supplemental information into its Radiological Process Control Program.
Docket Nos.
50-352 50-353 CONTACT:
Stephen Klementowicz, NRR/PERB 415-1084