ML19254D898

Discusses 790917 Ltr Re Plans for Implementing Requirements of 40CFR190.Beginning 791201,prior to Issuance of Semiannual Radioactive Effluent Rept,Offsite Doses Due to Liquid & Gas Will Be Calculated Per NUREG-0133

ML19254D898
Person / Time
Site:	Prairie Island
Issue date:	10/26/1979
From:	Mayer L NORTHERN STATES POWER CO.
To:	NRC COMMISSION (OCM)
References
NUDOCS 7910300299
Download: ML19254D898 (2)

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MSRB NORTHERN STATES POWER COMPANY M I N N E A PO LI S. MIN N E S OTA 55409 October 26, 1979 Director of Nuclear Reactor Regulation U S Nuclear 9eaulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Implementation of 40 CFR Part 190 In a letter dated September 17, 1979 from Willic a Gammill, Acting Assistant Director of Operating Reactors Projects, Divish of Operating Reactors, USNRC, we were requested to describe how we will implement the requirements of 40 CFR Part 190 until such time as the NRC Staf f completes their review of our 10 CFR Part 50, Appendix I, submittals and issues revised Technical Specifications. Northern States Power Company submitted all required material for NRC Staff review on June 1, 1979 and June 7, 1979.

Beginning December 1, 1979, and continuing until Technical Specification changes which implement 10 CFR Part 50, Appendix I, and 40 CFR Part 190 are issued, we will take the following actions:

1. Prior to submittal of each Semiannual Radioactive Ef fluent Report, offsite doses due to liquid and gaseous effluents will be calculated and compared to the Appendix I design objectives. Calculational methods outlined in NUREG-0133 or NRC computer programs will be used.

2. If the Appendix I design objective annual doses for the site are exceeded during any quarter for liquids or gases, or if twice the design objective annual doses for the site are exceeded for the calendar year, a special report will be submitted to the NRC. This report will contain a calculation of the highest radiation exposure to any member of the general public f rom all uranium fuel cycle sources (including all effluent pathways and direct radiation). If this report shows that exposures exceed the 40 CFR Part 190 standard, we will either apply to the Commission for a variance to continue releases which exceed the 40 CFR Part 190 standard or reduce subsequent releases to permit the standard to be met. This report will be submitted within 90 days of the end of the six-month period for which dose calculations were performed.

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October 26, 1979 Page If you have any questions concerning our interin method of complying with 40 CFR Part 190 please contact us.

hr L 0 Mayer, PE Manager of Nuclear Support Se rvices LOM/DMM/jh cc J G Keppler G Charnoff

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