ML20041G078
| ML20041G078 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/03/1982 |
| From: | Snyder B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20041G076 | List: |
| References | |
| NUDOCS 8203190180 | |
| Download: ML20041G078 (5) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 2 Introduction By letter dated October 30,1981(LL2-81-0237) and amended by letter dated December 3, 1981 (LL2-81-0270) the Metropolitan Edison Company (then managing.
licensee, now the General Public Utilities Nuclear Corporation) requested changes to the Technical Specifications of Operating License No. DPR-73 for the Three Mile Island Nuclear Station Unit No. 2 (TMI-2).
The requested changes to Appendix B of Operating License No. DPR-73 pertain to the following:
(1) deleting the actual environmental sampling locations from the technical specifications and in turn replacing them with references to tables in the Offsite Dose Calculatinn Manual (0DCM);
(2) Changing the Lower Limits of Detection (LLD) for gross beta, H-3, Zr-95, Nb-95, I-131 in water, milk and food products and for Cs-134, Cs-137 and Ba-140 in airborne particulates and food products and changing the reporting level of H-3 in water; (3) Requiring sampling and analysis for Sr-90 in milk 6
at least once per 92 days, together with specifications on LLD and reporting the level for Sr-90 concentration and (4) Adding to Section 5.6, reporting require-ments which were deleted from Section 3.2 of the Environmental Monitoring Program.
-Discussion and Evaluation The staff has reviewed the proposed amendments and has the following findings for each of the proposed changes:
(1)
Dele tion of the environmental sample location tables -(Tables 3.2-1, 2) from the Technical Specifications and replacing them with reference to the 8203190180 820303 PDR ADOCK 05000320 P
. locations stated in the ODCM does not change the actual locations where This environmental monitoring samples are to be taken for analysis.
amendment would provide the licensee with the flexibility of permitting future changes of environmental sampling locations to be reflected in the ODCM without an amendment to the Technical Specifications.
- However, the amended Technical Specifications, as proposed, would also require the licensee to provide the NRC with prior notification of any intended changes of environmental sampling locations in the ODCM.
Thus, the NRC would have an opportunity to review those intended changes, prior to their implementation, to assure that the environmental monitoring program would remain adequate and that continuity with the previous, baseline data, would be maintained.
On the other hand, explicit specification of those locations in the technical specifications is not necessary to provide the equivalent. degree of I
assurance to meet the requirement that radioactive materials in effluents released to unrestricted areas be kept as low as reasonably achievable per 10 CFR Part 50.36a.
e (2)
The licensee has proposed to replace the table on " Detection Capabilities for Environmental Sample Analysis" (Table 3.2-3) with the table on
" Maximum Values for the Lower Limits of Detection (LLD)" (Table 3.2-2).
By the proposed amendment, the values of LLD would be raised by factors ranging from about 1.2 (e.g., for I-131 in milk) to a factor of about 5 (e.g., for Cs-134 in airborne particulates) for a number of isotopes.
The LLD for H-3 in water would be raised to 2,000 pCi/l from 330 pCi/1.
Although the proposed LLD values are less stringent than those in the present technical specifications, the amended table of LLD values is consistent with those values presented in NUREG-0472, Revision 2,
. " Radiological Effluent Technical Specifications for PWR's" and is also consistent with the technical specification requirements of most operating PWR licensees. These LLD values as proposed, represent detection limits for routine environmental measurements in industrial laboratories and also represent concentraticn levels well within any levels which would likely result in doses to the exposed public in excess of design objectives of Appendix I to 10 CFR Part 50 (those design objectives are technical specification limits for TMI-2).
Radioactivi ty releases are controlled by the Technical Specifications Section 2.1, Radioactiva Discharges.
The environmental monitoring program thereby supplements.the radiological effluents monitoring program by verifying that measurable concentrations of radioactive materials are no higher than expected on the basis of the effluentt,,
measurements and mode of environmental exposure pathways. The proposed amendment, therefore, would not change the permissible level of effluents released to the environment. At the same time, the proposed LLD values,
(
would still enable the licensee to detect measurable concentrations of radioactive materials in the environment, with a substantial margin, at levels which would be likely to result in doses to the public in excess of the numerical design objectives of Appendix I to 10 CFR Part 50.
On this basis, the proposed amendment on LLD values should be acceptable, The licensee has also proposed to change the reporting level of H-3 from 4
3 X 104 pCi/1 in water to 2 X 10 pCi/1 in drinking water samples.
Tite lower level of concentration is consistent with thn EPA's Drinking Water Standard concentration set forth in 40 CFR Part 141.
l (3)
The requirement to sample and analyze for Sr-90 in milk is proposed to be i
i "at least once per 92 days" instead of "if I-131 is greater than 10 pCi/l."
.' Although since the accident, I-131 has decayed to insignificant amounts,
Sr-90 remains one of the dominant contaminants during the cleanup of TMI-2.
Therefore, the proposed amendment to require sampling and analysis of Sr-90 independent of I-131 concentration, is appropriate for TMI-2.
(4) The proposed amendment to delete wordings associated with reporting require-ments from Section 3 of the Technical Specifications and replace them in Section 5, " Administrative Control", is editorial in nature and introduces no substantive changes to the requirements of the technical specifications.
The proposed amendment will not result in a significant increase in the probability or consequences of accidents previously considered, nor a significant reduction in a margin of safety and does not therefore involve a significant hazards consideration.
Environmental Consideration We have determined that the amendment does not authorize a change in effluent tynes of total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have c
further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5 (d) (4),
that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this l
amendment.
Conclusion Based on the considerations discussed above, we have concluded that:
(1) Because the amendment does not involve a significant increase in tne probability or consequences of accidents previously considered and does not involve a significant reduction in a margin of safety, it does not
. involve a significant hazards consideration.
(2)
There is reasonable assurance that the health and safety of tne public will not be endangered by operation in the proposed manner.
(3)
Such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.
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