Letter Sequence Other |
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Results
Other: ML13333A351, ML15245A133, ML19211A816, ML19339A074, ML19350E688, ML19350E689, ML20070B347, ML20071Q646, ML20072B114, ML20072R831, ML20151H523
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MONTHYEARML19339A0741978-04-11011 April 1978
Forwards to All Licensees Current NRC Guidance Re Radiological Environ Monitoring.Branch Technical Position Encl
Project stage: Other
ML13333A3511979-01-18018 January 1979
Forwards Staff Recommendations Re General Contents of Offsite Dose Calculation Manual to Be Submitted W/Proposed Radiological Effluent Tech Specs.Ltr Addressed to All Power Reactor Licensees
Project stage: Other
ML19282B5281979-03-0808 March 1979
Notification That License Amend Application to Incorporate Requirements of 10CFR50 App I Into Tech Specs Will Not Be Completed by Requested Date of 780315
Project stage: Request
ML15245A1331979-09-17017 September 1979
Informs That Effective Date for Implementation of EPA Std for LWR U Fuel Cycle Is 791201.Requests Compliance W/ Radiological Effluent Tech Spec Implementing LWR Provisions. Method for Implementation Requested by 791101
Project stage: Other
ML19211A8161979-12-0404 December 1979
Notifies That Rept Required by Tech Specs 2.4.1.8 & 2.4.3.3 App B Should Include Dose Assessment W/Respect to Conformance W/Code
Project stage: Other
ML19294B3201980-01-0909 January 1980
Safety Evaluation Re zirconium-water Correction to ECCS Analysis.Nrc Considers ECCS Reanalysis Acceptable for Plant Operation W/Up to 1% of Steam Generator Tubes Plugged
Project stage: Approval
ML19323C5621980-05-14014 May 1980
Application for Amend 46 to Ol,Providing Proposed Tech Spec Changes.Revisions Include Addition of safety-related Hydraulic Snubbers to Table 3.7-4 & Mod of Surveillance Requirements for Auxiliary Feedwater Sys.Affidavit Encl
Project stage: Request
ML19350E6891981-05-31031 May 1981
Revised Process Control Program
Project stage: Other
ML19350E6861981-06-18018 June 1981
Application to Amend License DPR-66,submitted as Proposed Revision to Amend 36 of Tech Spec App A,Permitting Use of Radiological Access Control Permit to Control Entry Into Plant Areas.Forwards Revised Process Control Program
Project stage: Request
ML19350E6881981-06-18018 June 1981
Proposed Tech Specs 6.12.1,6.12.2 & 6.13 Re Administrative Controls & Radiological Environ Monitoring Program
Project stage: Other
ML20027C8211982-10-22022 October 1982
Revised Application for Amend to License DPR-66, Incorporating Proposed Radiological Effluent Tech Specs Into App a
Project stage: Request
ML20027C8191982-10-22022 October 1982
Forwards Revised Application for Amend to License DPR-66, Consisting of Proposed Change Request 36,Revision 3, Incorporating Radiological Effluent Tech Specs Into App A. Offsite Dose Calculation Manual & App B Will Follow
Project stage: Request
ML20070B3471982-12-0101 December 1982
Forwards Revision to Beaver Valley Unit 1 Offsite Dose Calculation Manual, Supporting 821022 Revision 3 to Proposed Tech Spec Change 36.Revisions to Section 2.2.2, Deleting Refs to Food & Ground Pathways,Forthcoming
Project stage: Other
ML20072B1141983-02-0303 February 1983
Radiological Effluent Tech Spec Implementation (A-2), Beaver Valley Power Station Unit 1, Technical Evaluation Rept
Project stage: Other
ML20072R8311983-03-28028 March 1983
Amend 66 to License DPR-66 Establishing New Limiting Conditions for Operation for Quarterly & Annual Average Release Rates
Project stage: Other
ML20151H5231983-04-26026 April 1983
Revised Pages to Amend 66 to License DPR-66 Incorporating Liquid Effluent Monitoring Instrumentation Into Tech Specs
Project stage: Other
ML20071Q6461983-05-25025 May 1983
Rev to Amend 66 to License DPR-66,consisting of Tech Spec Page Changes to Correct Administrative Errors
Project stage: Other
1981-05-31
[Table View] |
Informs That Effective Date for Implementation of EPA Std for LWR U Fuel Cycle Is 791201.Requests Compliance W/ Radiological Effluent Tech Spec Implementing LWR Provisions. Method for Implementation Requested by 791101| ML15245A133 |
| Person / Time |
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| Site: |
Millstone, Calvert Cliffs, Davis Besse, Oconee, Saint Lucie, Arkansas Nuclear, Crystal River, Maine Yankee, Rancho Seco, Fort Calhoun, Crane  |
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| Issue date: |
09/17/1979 |
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| From: |
Gammill W
Office of Nuclear Reactor Regulation |
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| To: |
ARKANSAS POWER & LIGHT CO., BALTIMORE GAS & ELECTRIC CO., FLORIDA POWER & LIGHT CO., FLORIDA POWER CORP., METROPOLITAN EDISON CO., NORTHEAST NUCLEAR ENERGY CO., OMAHA PUBLIC POWER DISTRICT, SACRAMENTO MUNICIPAL UTILITY DISTRICT, TOLEDO EDISON CO., YANKEE ATOMIC ELECTRIC CO. |
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| References |
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| GL-79-41, TAC-8132, NUDOCS 7910250215 |
| Download: ML15245A133 (2) |
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Similar Documents at Millstone, Calvert Cliffs, Davis Besse, Oconee, Saint Lucie, Arkansas Nuclear, Crystal River, Maine Yankee, Rancho Seco, Fort Calhoun, Crane |
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Text
p9REG~t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 September 17, 1979 TO ALL POWER REACTOR LICENSEES Gentlemen:
The effective date for implementation of the EPA Uranium Fuel Cycle Standard, 40 CFR Part 190 for light-water reactors, is December 1, 1979. By agreement, NRC is responsible for the implementation of this standard for licensed power reactors. Compliance with Radiological Effluent Technical Specifications (RETS), NUREG-0472 (Rev. 2) for PWRs or NUREG-0473 (Rev. 2) for BWRs, implements the LWR provisions to meet 40 CFR Part 190. Due to the delays in receiving and processing these Technical Specifications as scheduled in the letter to you from B. Grimes, Assistant Director for Engineering and Projects, dated November 15, 1978, the Radiological Effluent Technical Specifications may not be in effect for your facility on December 1, 1979.
The lack of Technical Specifications which implement the provisions of 40 CFR Part 190 does not relieve you of the responsibility to conform to the EPA standard. Therefore, you should determine how you will demonstrate to the NRC conformance with the provisions of 40 CFR Part 190 until such time as the revised RETS are issued. A commitment to the provisions of Specification 3.11.4 of the RETS, Revision 2, as explained in Chapter 3.8 of NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for.Nuclear Power Plants" is an acceptable method for demonstration of conformance. This commitment or an alternative method of demonstrating compliance with 40 CFR Part 190 should be submitted to NRC no later than November 1, 1979.
If you have any questions, please contact us.
Sincerely, William P. Gammill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors
('~1oZ5MAY
Florida Power Corporation cc:
Mr. S. A. Brandimore Vice President and General Counsel P. 0. Box 14042 St. Petersburg, Florida 33733 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Crystal River Public Library Crystal River, Florida 32629 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304