ML20210Q269

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Advises That 850509 Request for Exemption from GDC 4 Requirements No Longer Required Based on Existing Info. Request for Exemption to GDC 4 at Completion of NRC Review of SEP Topic III-5.A May Be Needed
ML20210Q269
Person / Time
Site: Yankee Rowe
Issue date: 05/06/1986
From: Clifford J
Office of Nuclear Reactor Regulation
To: Papanic G, Papanin G
YANKEE ATOMIC ELECTRIC CO.
References
REF-GTECI-A-02, REF-GTECI-RV, TASK-03-05.A, TASK-3-5.A, TASK-A-02, TASK-A-2, TASK-OR, TASK-RR GL-84-04, GL-84-4, NUDOCS 8605140017
Download: ML20210Q269 (4)


Text

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MAY001ssa Docket No.50-029 Mr. George Papanic, Jr.

Senior Project Engineer-Licensing Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701

Dear Mr. Papanic:

SUBJECT:

GENERAL DESIGN CRITERIA 4 EXEMPTION REQUEST Generic Letter 84-04, dated February 1,1984, provided the staff Safety Evaluation Report addressing the analyses used by a group of utilities to address Generic Issue A-2, dealing with asymmetric loss of coolant accident (LOCA) loads. As part of this letter, the staff stated that exemptions from General Design Criteria (GDC)-4 were required for those plants that wanted to remove, or not install, devices that would protect against asymmetric LOCA loads in primary coolant pipin You submitted an exemption request for the Yankee Nuclear Power Station (g. Yankee) in a May 9, 1985 letter from J. A. Kay to J. A. Zwolinski.

A modification to GDC-4 has been issued (51 FR 12502), and will be effective May 12, 1986. The modification includes an exclusion of consideration of the dynamic effects of postulated primary coolant pipe ruptures when analyses demonstrate the probability of rupturing such piping is extremely low under design basis conditions. This modification removes the current need for an exemption to GDC-4 for Yankee.

The acceptability of the analyses performed to demonstrate the likelihood of piping ruptures is currently being reviewed in conjunction with the Systematic Evaluation Program (SEP) review of topic III 5.A, " Effects of Pipe i

Break on Structures, Components, and Systems Inside Containment."

If this

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review confirms the acceptability of your reactor coolant system piping analysis for asymmetric LOCA loads, no further action will be required.

If your analysis is found unsatisfactory, a request for exemption may again need to be submitted based on the issues that exist at the end of our review.

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. Your request for exemption is, therefore, no longer required based on existing information. You may need to request an exemption to GDC-4 at the completion of our review of SEP topic III-5.A.

James W. Clifford, Project Manager Project Directorate #1 Division of PWR Licensing-A cc: See Next Page Office:

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Mr. George Papanic, Jr.

Yankee Atomic Electric Company Yankee Nuclear Power Station cc:

Mr. James E. Tribble, President Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701 Thomas Dignan, Esquire Ropes and Gray 2

225 Franklin Street Boston, Massachusetts 02110 f.

Mr. N. N. St. Laurent Plant Superintendent i-Yankee Atomic Electric Company Star Route j

Rowe, Massachusetts 01367 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Resident Inspector Yankee Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350 I

Regional Administrator, Region I U.S. Nuclear Regulatory Cormission 631 Park Avenue l

King of Prussia, Pennsylvania 19406 l

Robert M. Hallisey, Director Radiation Control Program Massachusetts Department of Public Health 150 Tremont Street, 7th Floor Boston, Massachusetts 02111 1

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