ML20212R590

Safety Evaluation Supporting Amend 102 to License DPR-40

ML20212R590
Person / Time
Site:	Fort Calhoun
Issue date:	01/20/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20212R575	List: ML20212R573 ML20212R582 ML20212R590
References
GL-85-19, TAC-63186, NUDOCS 8702020725
Download: ML20212R590 (2)

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.102 TO FACILITY OPERATING LICENSE N0. DPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285 INTRODUCTION:

By letter dated October 23, 1986, OPPD proposed a license amendment to Facility Operating License DPR-40. The proposed amendment would: (1)deletethe 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.

EVALUATION:

Technical Specification 2.1.3 for Fort Calhoun currently requires that:

(1) the plant must be made subcritical with T less than 536*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ifthespecificactivityoftheprimarycoolaM.91s greater than 1.0 microcurie /

gram dose-equivalent I-131 for more than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> during one continuous time interval or greater than 60 microcuries/ gram dose equivalent I-131; (2) the plant must be made subcritical 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 Licensee Event Report to the NRC if the primary coolant specific activity is greater than 1.0 microcurie / gram dose-equivalent I-131.

On September 27, 1985, the NRC staff issued Generic Letter (G.L.) 85-19

" Reporting Requirements on Primary Coolant Iodine Spikes," to all licensees and applicants for operating power reactors and holders of construction pennits for power reactors. In G.L. 85-19, the staff determined that: (1) reportino requirementsrelatedtoprimarycoolantspecificactivity(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 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 /> 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. G.L. 85-19 also presented model Technical Specifications that reflect these findings.

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Omaha Public Power District has proposed amending Fort Calhoun's Technical' Specifications to match the model Technical Specifications. In accordance with G.L. 85-19, the portion of the Technical Specifications regarding plant shutdown if the primary coolant specific activity exceeds 1.0 microcuries/ gram dose equivalent I-131 for more than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> during one continuous time interval, or is greater that 60 microcurie / gram dose equivalent I-131, would not be affected by the proposed changes. Reporting requirements related to primary coolant specific activity levels would be included in Technical Specification 5.9.4.b.

The proposed changes to Technical Specification 2.1.3 and 5.9.4.b 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 exceeds the limit of 1 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. Since the proposed changes are consistent with the Model Technical Specifications provided in G.L. 85-19 and meet the applicable regulatory guidance and requirements, the staff finds them acceptable.

ENVIRONMFNTAL' CONSIDERATION This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR

$51.22(c)(9). Pursuant to 10 CFR 551.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

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 Commission'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: January 20, 1987 Principal contributor:

Edward F. Branagan, Jr.

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