ML20197B611
| ML20197B611 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 10/27/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20197B571 | List: |
| References | |
| GL-85-19, NUDOCS 8610300338 | |
| Download: ML20197B611 (2) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION D
- j WASHINGTON, D. C. 20555 e,,,s SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.90 TO FACILITY OPERATING LICENSE NO. DPR-36 MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309
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1.0 INTRODUCTION
By letter dated January 29, 1986, dated January 29, 1986 Maine Yankee Atomic Power Company (MYAPCo), pro)osed a license amendment to Facility Operating License No. DPR-36 for tie Maine Yankee Atomic Power Station.
Supplemental information was provided by MYAPCo. by letter dated July 29, 1986. The proposed change would: (1) delete the short-tenn reporting requirements related to primary coolant specific activity levels; (2) no longer require plant shutdown if the priraary coolant specific activity limits are exceeded for an accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />; and (3) incorporate a figure from the Standard Technical Specifications for Combustion Engineering plants related to specific activity limits for primary coolant.
2.0 EVALVATION Technical Specification 3.2 for Maine Yankee currently requires that:
(1)theplantmustbemadesubcriticalwithT less than 500'F within 6hoursifthespecificactivityoftheprima89 coolant is greater than 1.0 microcurie / 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 equivalentI-131;(2)theplantmustbemadesubcriticalwithin48 hours l
if the primary coolant specific 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; and (3) the licensee must submit a Special Report to the NRC if the total cumulative operating time at a primary coolant specific activity greater than 1.0 microcurie / gram dose-equivalent I-131 exceeds 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive 6 month period.
On September 27, 1985 the NRC staff issued Generic Letter 85-19.
" Reporting Requirements on Primary Coolant Iodine Spikes," to all licensees and appitcants for operating power reactors and holders of construction pennits 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-tenn report (i.e., Special Report or Licensee Event Report) to an item to be included in the Annual Report; and (2) existing shutdown requirements based on exceeding the primary coolant specific activity limits for an accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> paho%B8u8th8%g9 P
. were no longer necessary. The 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 TS which reflect these findings.
Maine Yankee Atomic Power Company has proposed revising the TS to match the model TS and to incorporate a figure regarding dose equivalent I-131 primary coolant specific activity limit as a function of percent of rated power (proposed Figure 3.2-1).
In accordance with Generic Letter 85-19, the portion of the TS regarding plant shutdown if the primary coolant specific activity limits are exceeded 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 would not be affected by the proposed TS change..
Since this proposed change is consistent with the model TS enclosed in Generic Letter 85-19, the NRC staff finds this change acceptable.
In regard to proposed Figure 3.2-1, the proposed figure is the same as a previonly reviewed Figure 3.4-1 in the " Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors" (NUREG-0212, Revision 2, Fall 1980). The staff finds this change acceptable.
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The staff has reviewed the proposed change to TS 3.2 for Maine Yankee.
The proposed change would delete the short-term reporting requirements related to primary coolant specific activity levels and no longer require plant shutdown if the primary coolant specific activity limits are exceeded for an accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />. As discussed in the preceding paragraphs, the staff finds that the proposed change meets the applicable regulatory guidance and requirements and is, therefore, acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
We have 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 Consnission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: October 27, 1986 Principal Contributor:
Edward F. Brannagan, Jr.