ML20054E724
| ML20054E724 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/28/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054E717 | List: |
| References | |
| TAC-48383, NUDOCS 8206140110 | |
| Download: ML20054E724 (3) | |
Text
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NUCLEAR REGULATORY COMMISSION o
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WASHINGTON. D. C. 20555 0
g usi ORIGINAL Certified B L
V ENVIRONMENTAL IMPACT APPRAISAL BY THE OFFICE OF NUCLEAR REACTOR REGULATION' SUPPORTING AMENDME'NT NOS. g4 AND 77 TO PROVISIONAL OPERATING LICENSE N0. DPR-21 AND FACILITY OPERATING LICENSE NO. DPR-65 NORTHEAST NUCLE R ENERGY COMPANY, ET AL.
MILLSTONE NUCLEAR POWER STATION, UNITS N0. 1 AND 2 DOCKET NOS. 50-245 AND 50-336 Introduction By letter dated May 14, 1982, Northeast Nuclear Engineering Company (NNECO or the licensee) proposed to amend its Operating Licenses No. DPR-21 and DPR-65, for Millstone Nuclear Power Station, Units No.1 and 2, by incor-porating specified charges into the Appendix B Environmental Technical Specifications (ETS). The subje'ct revisions involve Section 2.4.1.2, " Liquid Waste Effluent Specifications", and Section 2.4.1.3, " Liquid Waste Effluent Monitoring Requirements".
The licensee's proposal adds monitoring and sampling requirements for the discharges from the Condensate Polishing Facility radioactive waste evaporator distillate discharge line.
This charge enables the continuous discharge of this effluent. The proposal also revises the limits on liquid radioactive effluents so the limit would be on the dose produced (rather than on the activity released).
Discussion and Evaluation The licensee has stated in the application that since there is no capability to store the distillate from the Condensate Polishing Facility radioactive waste evaporator, continuous (rather than batch) discharges are necessary.
Furthermore, these discharges will not significantly increase the radio-activity released to the environment for the following reasons. First, the radioactivity concentrations in untreated regenerative waste are approx-imately the same as, or less than, the radioactivity concentrations in the steam generator blowdown (which is already being continuously released).
Second, the distillate from the evaporation of this waste normally has radioactivity concentrations that are 1,000 to 10,000 times less than steam generator blowdown radioactivity concentrations.
Third, the volume of condensate polishing evaporator distillate is also a factor of 1,000 to 10,000 less than the volume of steam generator blowdown.
In total, the distillate releases will be a fraction of a percent of the present blow-down releases.
Furthermore, the proposed amendments to the ETS are conser-vative in that they provide essentially the same requirements for the 8206140110 820528 PDR ADOCK 05000 P
9 condensate polishing evaporator distillate and for steam generator blow-down.
We conclude that the provisions for continuous release of the conden-sate polishing evaporator distillate meet the requirements, and are therefore acceptable.
The licensee also requested changes that would limit liquid releases based on the doses produced, rather than on the activity (curies) released. The present limits (no more than 10 Ci/ reactor / quarter or 20 Ci/ reactor / year) were intended to keep releases "as low as reasonably achievable" (ALARA).
These limits meet the ALARA requirements of 10 CFR Part 50, Appendix I, but the present limits do not provide the operational flexibility called for in-Appendix 1.
The licensee has stated that the operational flexibility is now needed because of a small (0.1 gpm) primary to secondary steam generator leak and increased primary activity this cycle.
The proposed ETS changes would limit doses from liquid effluents to no more.
than (a) 1.5 mrems to the total body or 5 mrems to any organ in any calendar quarter, and (b) 3 mrems to the total body or 10 mrems to any organ in any 12 consecutive months. These limits are more stringent than current ALARA requirements and are therefore acceptable.
The licensee also requested changes in the ETS which address treatment of ef fluents, reporting of releases and monitoring of releases.
These changes are needed to make these specifications consistent with the proposed new releases limits. We find that these proposed changes meet current require-ments and are therefore acceptable.
Finally, NNEC0 has proposed a new specification that would specify the manner in which off-site doses would be calculated for evaluating compliance with the new release limits. This specification would require the us'e of an NRC computer code '(LADTAP) with'specified input.
We have reviewed the NNEC0 procedure RAB-4-3, Rev. 0, dated November,1979. We find this procedure, the use of LADTAP and the proposed ETS changes to be in compliance with current requirements and to be acceptable.
The proposed changes to the ETS for Millstone Nuclear Power Station, Unit Nos.1 and 2, have been found to be in compliance with the. requirements of the NRC regulations. The proposed changes do not, in' effect, remove or relax any existing requirement related to the probability or consequences of accidents previously considered and do not involve a significant hazards consideration.
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3-The proposed changes do not, in effect, remove or relax any existing require-ments needed to provide reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner.
Conclusion and Basis for Negative Declaration On the basis of the foregoing analysis, it is concluded that there will be no enviroinental impact attributable to the proposed actions othei than has already been predicted and described in the Commission's Final Environ-mental Statement for Millstone Nuclear. Power Station, Unit Nos.1 and 2 dated June 1973. Having made this conclusion, the Commission has further concluded that no environmental impact-statement for the proposed action need be prepared and that a negative declaration to this'effect is appro-p ri ate.
Date: May 28, 198?
Principal Contributors:
Charles Willis Monte Conner Franklin Research Center S
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