ML20196F597
| ML20196F597 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/26/1988 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20196F603 | List: |
| References | |
| C311-88-2020, NUDOCS 8803040128 | |
| Download: ML20196F597 (2) | |
Text
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GPU Nuclear Corporation NQQIg[
Post Of fice Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
February 26, 1988 C311 2020 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Dear Sir:
Three Mile Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Semi Annual Effluent and Release Report Enclosed is the THI-1 Semi Annual Effluent and Release Report for the period July 1,1987 through December 31, 1987.
This report includes an Executive Summary of the Effluent Release Report, the Disposal and Effluent Release Data, Joint Frequency Tables, and an assessment of the radiation doses due to liquid and gaseous effluents released from the Unit during 1987.
THI Technical Specification Sections 6.9.4.1 and 6.9.4.2 require reporting of effluent data and solid waste shipment data in accordance with Reg. Guide 1.21 for the semi-annual report period. These tables are attached including summaries of liquid and gaseous effluents and the joint frequency tables for the Semi Annual reporting period and an annual Joint Frequency Summary.
In accordance'with Technical Specification Section 6.9.4.2, this report includes an annual summation table and quarterly tables showing the assessment of the radiation doses due to liquid and gaseous effluents released from the Unit during 1987.
Technical Specification Section 6.9.4.2 also requires in part that annually "This same report shall also include an assessnent of the radiation doses from radioactive liquid and gaseous effluents to individuals due to their activities inside the site boundary (Figures 5-3 and 5-4) durinq the report period."
Individuals is construed to mean members of the public.
Since the public does not have unrestricted access to THI-1, no assessrient of dose is applicable.
THI Technical Specification Section 6.9.4.2 also requires that for this report an annual assessment of radiation dose to the likely rest exposed real individual from reactor releases and other nearby uranium fuel cycle sources (THI Unit 2) to show compliance with 40 CFR 190 "Environmental Radiation Protection Standards for Nuclear Power Operations." For the purpose of 8903040128 890226 DR ADOCK 050 9
GPU Nucioar Corporation is a subsidiary of the General Public Utilities Corporation
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C311 7020
-2 February 26, 1988 Technical Specification 6.9.4.2., the annual dose to the maximum exposed individual from effluents for comparison to 40 CFR 190, would be no greater than 0.2 mrem.
This sums together a 7.9E-3 mrem maximum bone dose from Unit 2 and a 0.21 mrem liver dose from Unit 1 for simplicity.
It is further estimated that based on the maximum average fenceline dose rate for the year of 12 mrem above background per standard month, a person residing at the fenceline for the duration specified in RG 1.109 for shoreline exposure, would receive no more than 1.1 mrem direct dose, for a maximum potential total dose of 1.3 mrem for both units.
THI Technical Specification Section 6.9.4.2 requires that annually changes to the Off-Site Dose Calculation Manual (ODCM) be reported in the Semi Annual Report.
Rev. 8 to the ODCM was issued December 21, 1987. Attachment 1 provides details of the changes incorporated in Rev. 8.
TMI Technical Specification Section 6.9.4.2 also requires annually that changes to the Process Control Program (PCP) be reported.
There were no changes to the PCP during the second half of 1987.
Sincerely,
. D.
ki' l Vice President a Director, TMI-1 HDH/DYH/spb:1114A cc:
W. Russell R. Conte Enclosures
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