ML20215L948
| ML20215L948 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/23/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215L940 | List: |
| References | |
| GL-85-19, NUDOCS 8610290385 | |
| Download: ML20215L948 (3) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 46 TO FACILITY OPERATING LICENSE NO. NPF-11 AND AMENDMENT NO. 28 TO FACILITY OPERATING LICENSE NO. NPF-18 COMMONWEALTH EDIS0N COMPANY LA SALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374
1.0 INTRODUCTION
By letter dated June 27, 1986, Comonwealth Edison requested changes to the la Salle County Station, Units 1 and 2 Technical Specifications to change reporting requirements for iodine spiking from a short term report to an item which is included in the Annual Report, in accordance with Generic Letter 85-19, " Reporting Requirements on Primary Coolant Iodine Spikes", dated September 27, 1985, to delete unnecessary reporting require-ments.
2.0 EVALUATION Licensees for operating power reactors have been required to report to the NRC iodine spiking events within 30 days, and to shutdown a plant if coolant iodine activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12 month period.
Generic letter No. 85-19, " Reporting Requirements on Primary Coolant Iodine Spikes", provides relaxation of the above requirements to the effect that the reporting recuirements for the iodine spiking can be reduced from short-term reporting (within 30 days) to an item which is to be included in the Annual Report. Additionally, Generic letter No. 85-19 states that the existing requirements to shutdown a plant if iodine activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12 month period can be eliminated. The change does not alter the Technical Specification limits for primary coolant act-ivity, nor does it change the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> shutdown requirement. The quality of nuclear fuel and fuel management has been greatly improved in recent years, such that norman coolant iodine activity is maintained well below the mini-mum limits. Appropriate actions would be initiated long before accumulat-ing(800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> above the iodine activity limit.(b) 1)(ii) requires that the NRC be no In addition 10 CFR 50.72 cipal safety barrier degradation occurring during operation; therefore, these Technical Specification limits are no longer necessary. Commonwealth Edison proposed revisions of Sections 3.4.5, Bases 3/4 4.5, and Administra-tive Control Section 6.6.
The text of the proposed La Salle Technical Specifications changes is identical with the "Model Technical Specifications l
Showing Revisions to STS Reporting Requirements for Primary Coolant Specific l
Activity" (which are a part of Generic letter No. 85-19).
I 9610290385 861023 DR ADOCK 0500 3
3.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes in the installation and use of a facility ceinponent located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. The staff has determined that these amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumu-lative occupational radiation exposure. The Consnission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding.
Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be pre-pared in connection with the issuance of these amendments.
4.0 CONCLUSION
The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (51 FR 28994) on August 13, 1986, and consulted with the state of Illinois. No public comments were received, and the state of Illinois did noc have any comments.
The staff has concluded, based on the considerations discussed above, that:
f1) there is reasonable assurance that the health and safety of the public will not be endanoered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regula-tions and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
F. Skopec, NRR Dated:
October 23, 1986
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l AMENDMENT N0. 46 TO FACILITY OPERATING LICENSE NO. NPF LA SALLE, UNIT 1 AMENDMENT N0. 28 TO FACILITY OPERATING LICENSE NO. NPF LA SALLE, UNIT 2 DISTRIBUTION:
Docket Nos.- 50-373/374 NRC PDR Local PDR PRC System NSIC BWD-3 r/f ABournia (4)
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EAdensam Attorney, OELD CMiles RDiggs JPartlow BGrimes EJordan LHarmon TBarnhart(8)
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