ML20235F762
| ML20235F762 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/21/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235F761 | List: |
| References | |
| NUDOCS 8709290308 | |
| Download: ML20235F762 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 27 TO FACILITY OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. STN 50-483
1.0 INTRODUCTION
By letter dated March 30, 1987, Union Electric Company submitted a request for changes to the Technical Specifications. The amendment would delete the short-term reporting requirements related to primary coolant specific activity levels; and (2) no longer require plant shutdown if the primary coolant specific activity exceeds the limit of 1.0 microcurie / gram dose equivalent I-131 for an accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12-month period.
2.0 DISCUSSION Technical S3 edification 3.4.8 for Callaway Unit I currently requires that: (1) t1e plant must be made subcritical with T less than 500'F l
within6hoursifthespecificactivityoftheprimUScoolantisgreater l
than 1.0 stierocurie/ gram dose equivalent I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 60 microcuries/ gram dose equivalent I-131; (2) the plant must be made suberitical if the primary coolant specific activity exceeds the limit of 1.0 microcurie / gram dose equivalent I-131 for an accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12-month period; and (3) the licensee must submit a Special Report to the NRC if the primary coolant specific activity is greater than 1.0 microcurie /
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gram dose equivalent 1-131.
On September 27, 1985, the NRC staff issued Generic Letter 85-19,
" Reporting Requirements on Primary Coolant Iodine Spikes," to all licensees and applicants for operating power reactors and holders of construction permits for power reactors.
In Generic Letter 85-19, the staff determined that: (1) reporting requirements related to primary coolant specific activity levels, specifically iodine spikes, could be reduced from a short-term report (i.e., Special Report or Licensee Event Report) to an item to be included in the Annual Report; ar.d (2) existing shutdown requirements based on exceeding the primary coolant specific activity limit of 1.0 microcurie / gram dose equivalent I-131 for an The accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> were no longer necessary.
8709290308 870921 PDR ADOCK 05000403 P
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- change in these requirements is based on an improvement in the quality of nuclear fuel over the past 10 years, and the fact that appropriate actions would be initiated long before approaching the limit as currently specified. Generic Letter 85-19 also presented model Technical Specifica-tions which reflect these findings.
3.0 EVALUATION Union Electric Company has proposed amending the Technical Specifications for Callaway Unit 1 to match the model Technical Specifications.
In accordance with Generic Letter 85-19, the portion of the Technical Specifications regarding shutdown if the primary coelant specific activity exceeds 1.0 microcuries/ gram dose equivalent I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval, or is greater than 60 microcurie / gram dose equivalent I-131 would not be affected by the proposed changes. Report-ing requirements related to primary coolant specific activity levels would be included in Technical Specification 6.9.1.5.
Page B 3/4 4-6 of the Bases would be changed accordingly. Since the proposed changes are consistent with the model Technical Specifications which were enclosed in Generic Letter 85-19, the NRC staff finds the proposed amendment acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the installation or use of a facility component located within the restricted
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area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released I
offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this amendment meets the eligibility criteria for categorical I
exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no
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environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
5.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
6.0 ACKNOWLEDGEMENT Principal Contributors:
E. Brannagan, PRPB Tom Alexion, PD III-3 Dated: September 21, 1987 i