ML20147D019
| ML20147D019 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/26/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20147D023 | List: |
| References | |
| NUDOCS 8803030212 | |
| Download: ML20147D019 (4) | |
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7590-01 UNITED STATES HUCLEAR REGULATORY COMMISSION COMMONWEALTH EDISON COMPANY DOCKET NO 50-249 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Commission) is censidering issuance of schedular exemptions from the requirements of 10 CFR 50 to the Commonwealth Edison Company (CECO) (the licensee) for the Dresden Nuclear Power Station, Unit No. 3, located at the licensee's site in Grundy County, Illincis.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed action would grant schedular exemptions from requirements of Section III.D.2(b) and III.D.3 (type B and type C tests respectively) of Appendix J to 10 CFR 50 relating to the primary reactor containment leakage testing for water-cooled reactors. The purposes of the tests are to assure that leakage th, rough primary reactor containment shall not exceed allowable leakage rate values as specified in the Technical Specifications and that periodic surveillance is performed.
The Need for the Proposed Action:
By letter dated January 10, 1988, the licensee requested, pursuant to 10 CFR 50.12(a), a schedular exemption for Dresden Unit 3 from the 2 year test interval for certain Type B and C leak rate tests required by 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3. The exemption is requested to support the current refueling outage schedule and avoid the potential for an earlier reactor shutdown.
8803030212 880226 PDR ADOCK 05000249 P
7E90-01 L The Dresden Unit 3 shutdown for its End of Cycle 9 (E0C 9) refueling and Recirculation Pipe Replacement (RPR) began on October 28, 1985. Due to the extensive RPR program, the E0C 9 outage was unusually long with startup not occurring until September 1906. Type B and C local leak rate testing cenwenced on September 27, 1985 and continued through August of 1986.
As a result of the extensive RPR outage, a four week midcycle outage related to feedwater system problems, and other considerations, the shutdown for refueling has been delayed to March 26, 1988. Maintaining this schedule will result in exceeding the two year test interval.
Environmental Impacts of the Proposed Action:
The proposed action includes exemptions from performing certain type B and C tests for a period of 90 days from January 10, 1988. As stated in 10 CFR 50 Appendix J, the purpose of the primary containment leak rate testing requirements is to ensure that leakage rates are maintained within the Technical Specification requirements and to assure that proper maintenance and repair is perfomed through-out the servicel life of the containment boundary components.
The requested exemp-tion is consistent with this intent in that it represents a one time only schedular
. extension of short duration. The required leak tests will still be performed to assess compliance with Technical Specification recuirements, albeit later, and to assure that any required maintenance or repair is performed. As noted in Sections III.D.2 and III.D.3 of Appendix J, it was intended that the testing be perfomed during refueling outages or other convenient intervals.
Extending the 2 year interval by a small amount to reach the next refueling outage will not significantly impact the integrity of the containment boundary and therefore will not significantly impact the consequences of an accident or transient in the unlikely event of such an occurrence during the 90 day extended period.
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.. This is further supported by the information provided ir the application.
The pathways affected were tested during the July 1986 Integrated Leak Rate Test (ILRT). Although some local leak rate testing intervals will exceed two years by the end of the current operating cycle, the fact that a number of these pathways were tested as part of the ILRT within two years provides assurance that containment integrity has not been compromised.
In addition, the pathways for which testing would be deferred have in general demonstrated good local leak rate test results as indicated in the application.
Finally, the estimated current total leakage, which was based on past data from the same pathways, from all applicable pathways is below the value allowed by the Technical Specifications.
Based on the staff's evaluation, the level of safety in the areas involved in these exemptions is equivalent to that achieved by compliance with the technical requirements of Sections III.B.2(a) and III.B.3 of Appendix J to 10 CFR Part 50.
Thus, radiological releases will not differ from those detemined previously and the proposed exemptions do not othentise affect facility radiological effluents or occupational exposures. The proposed exemptions do not affect plant nonradiological effluents and have no other environmental impact.
- Therefore, the Conrnission concludes there are no measurable radiological or nonradiological environmental impacts associated with the proposed exemption.
Alternatives to the Proposed Action:
Since the Consnission has concluded there is no measurable environmental impact associated with the proposed exemption, any alternatives with equal or greater environmental impact need not be evaluated.
The principal alternative to the exemption would be to require rigid compliance with the requirements of i
Section III.D.2(a) and III.D.3 of Appendix 0 to 10 CFR Part 50. Such action would not enhance the protection of the environment and would result in unjusti-fied costs for the licensee.
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.e 7590-01 Altc natives to the Proposed Action:
Since the Corinission has concluded there is no measurable environmental impact associated with the proposed exemption, any alternatives with equal or greater environmental impact need not he evaluated.
The principal alternative to the exemption would be to require ripid compliance with the requirements of Section III.D.2(a) and III.D.3 of Appendix J to 10 CFR Part 50.
Such action would not enhance the protection of.the environment and would result in unjustified costs for the licensee.
Alternative Use Resources:
This action does not involve the use of resources not considered previously in the Final Environmental Statement for Dresden, Units 2 and 3 dated November 1973.
Agencies and Persons Corsulted: The NRC staff reviewed the licensee's request and did not consult other agencies or persons.
FINDING OF N0 SIGNIFICANT IMPACT The Commission has determined not to prepare an environmental inpact state-ment for the proposed exe;nption.
Based upon the environmental assessment, the NRC staff concludes that the proposed action will not have a significant effect on the quality of the human envi ronicant.
For further details with respect to this proposed action, see the licensee's letter dated January 10, 1984. This lettei is available for public inspection at the Connission's Public Document Rcom,1717 H. Street, N.W., Washington, D.C.
and at the Morris Public Library, 604 Liberty Street, Morris, Illinois 60451.
Dated at Rockville, Maryland this 26th day of February 1988.
FOR THE NUCLEA REGULATORY COPNISSION Daniel R.
uller, Director Project Directorate III-2 Division of Peactor Projects - III, IV, V, and Special Projects PDIII-2 PDIII-2.
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