ML17037B594

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Letter Enclosing Copy of Notice of Granting an Exemption from the Requirements of General Design Criterion 50, Containment Design Basis of Appendix a to 10 CFR Part 50
ML17037B594
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 03/22/1978
From: Lear G
Office of Nuclear Reactor Regulation
To: Dise D
Niagara Mohawk Power Corp
References
Download: ML17037B594 (12)


Text

,

Distribution

,~ocket MARCH 2 2 1978. ORB ¹3 Local PDR NRC PDR GLear Docket Vo. 50-220 ,

SSheppard RClark Attorney, GELD OI8IE (3)

DEisenhut TBAbernathy Niagara Hohavrk Power Corporation JRBuchanan ATTN: tir. Donald P. Disc ACRS (16)

Vice President Engineering 300 Erie Boulevard Mest Syracuse, New York 13202 Gentlemen:

Enclosed for your infornation is a copy of a l!otice of Granting an Exemption from the Requireaents of General Design Criterion 50, OContainment Design Basis", of Appendix A to 10 CFR Part 50 for Nine Hile Point Unit Ho. 1 which has been filed with the Office of the Federal Register for publication.

Sincerely, Original signed bp George Lear, Chief Operating Reactors Branch ¹3 Division of Operating Reactors

Enclosure:

Exemption cc v/enclosures:

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 MARCH Docket NIo. 50-220 Niagara Mohawk Power Corporation ATTN: Mr. Donald P. Disc Vice President - Engineering 300 Erie Boulevard Hest Syracuse, New York 13202 Gentlemen:

Enclosed for your information is a copy of a Notice of Granting an Exemption from the Requirements of General Design Criterion 50, "Containment Design Basis", of Appendix A to 10 CFR Part 50 for Nine Mile Point Unit No. 1 which has been filed with the Office of the Federal Register for publication.

Sincerely, George L, Chief Operating Reactors Branch 83 Division of Operating Reactors

Enclosure:

Exemption cc w/enclosures:

See next page

Niagara Mohawk Power Corporation - 2- MARCH 2 8 1978 cc: Eugene B. Thomas, Jr., Esquire LeBoeuf, Lamb, Leiby 8 MacRae 1757 N Street, N. W.

Washington, D. C. 20036 Anthony Z. Roisman Natural Resources Defense Council 917 15th Street, N. W.

Washington, D. C. 20005 T, K. DeBoer, Director Technological Development Programs State of New York Energy Office Swan Street Building CORE 1 - Second Floor Empire State Plaza Albany, New York 12223 Mr. Robert P. Jones, Supervisor Town of Scriba R. D. ¹4 Oswego, New York 13126 Niagara flohawk Power Corporation ATTN: Mr. Thomas Perkins Plant Superintendent Nine Mile Point Plant 300 Erie Boulevard West Syracuse, New York 13202 Chief, Energy Systems Analysis Branch (AW-459)

Office of Radiation Programs U. S. Environmental Protection Agency Roon 645, East Tower 401 M Street, N. W.

Washington, D. C. 20460 U. S. Environmental Protection Agency Region II Office ATTN: EIS COORDINATOR 26 Federal Plaza New York, New York 10007 Oswego County Office Building 46 E. Bridge Street Oswego, New York 13126

UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-220 NIAGARA MOHAWK POWER CORPORATION

'OTICE OF GRANTING AN EXEMPTION FROM THE REQUIREMENTS OF GENERAL DESIGN CRITERION 50 CONTAINMENT DESIGN BASIS OF APPENDIX A TO 10 CFR PART b0 The U.S. Nuclear Regulatory Commission (The Commission) has granted an exemption from the requirements of General Design Criterion 50, "Contain-ment Design Basis", of Appendix A to 10 CFR Part 50 to Niagara MohawR Power Corporation (the Licensee). This exemption relates to the demonstrated safety margin of the Hark I containment system for Nine Mile Point Unit No. 1 for recently identified hydrodynamic suppression pool loads associated with a postulated design basis loss of coolant accident and provides for operation under the conditions specified in the NRC staff's "Hark I Containment Short Term Program Safety Evaluation Report" and under any resulting Technical Specification requirements. To this extent, this exemption encompasses any related requirements of 10 CFR Part 50, Section 50.55(a), and General Design Criterion 1. This exemption i s effective as of the date of its issuance.

The Commission has evaluated the demonstrated safety margin of the containment system for Nine Nile Point Unit No. 1 under present

conditions and has concluded that sufficient margin exists to preclude undue risk to the health and safety of the public. This evaluation is documented in the staff's "t1ark I Containment Short Term Program Safety Evaluation Report," NUREG-0408, December 1977.

This exemption is granted for an interim period of approximately two years while a more detailed review is conducted. At the conclusion of this re-view, the design safety margin of the containment system for Nine flile Point Unit No. 1 will be restored to that which was originally intended at the time Nine Nile Point Unit No. 1 was licensed for operation. The basis for this exemption is set forth in the letter to the licensee granting the exemption, dated February 28, 1978.

The Commission has determined that the granting of this exemption will not result in any significant environmental impact and that pursuant to 10 CFR Section 51.5(d)(4 ) an environmental impact statement or negative declara-tion and environmental impact appraisal need not be prepared in connection with this action.

For further details with respect to this action, see ( 1) the Commission's letter to the licensee dated February 28, 1978, and (2) the Commission's

I' C "Mark I Containment Short Term Program Safety Evaluation Report," NUREG-0408, December 1977.

These items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D. C. and at the Oswego County Office Building, 46 E. Bridge Street, Oswego, New York 13126. A co copy of item (1) may be obtained upon request addressed to the

.S. Nuclear Regulatory Commission, Washington, D.C. 20555, U.S. Attention:

Director, Division of Operating Reactors. A copy of item (2 ) may be obtained upon request addressed to the National Technical information Service, Springfield, Yirginia 22161.

Dated at Bethesda, Maryland this 22nd day of March 1978.

FOR THE NUCLEAR REGULATORY COMMiSSiON George Lear, Chief Operating Reactors Branch 83 Division of Operating Reactors