ML20028G175
| ML20028G175 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/01/1983 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| Shared Package | |
| ML20028G176 | List: |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR LSO583-02-005, LSO583-2-5, NUDOCS 8302070485 | |
| Download: ML20028G175 (3) | |
Text
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February 1, 1983 Docket No.50-029 LS0583 005 Mr. James A. Kay Senior Engineer - Licensing Yankee Atomic Electric Company 1671 Worcetter Road Framingham, Massachusetts 01701
Dear Mr. Kay:
SUBJECT:
SEP TOPIC III-6, SEISMIC DESICN CONSIDERATIONS YANKEE NUCLEAR POWER STATION Enclosed is our final safety evaluation report for the seismic design of the Yankee Nuclear Power Station. Since YAEC has not yet completed the seismic reevaluation of Yankee, the safety evaluation was based upon preliminary analyses, several working-level meetings between YAEC and NP.C personnel and their consultants, and YAEC's consnents on our draft safety evaluation which was issued on October 4, 1982. Therefore, the conclusions presented in the evaluation may be revised should new information be presented in the final YAEC seismic report.
To date, YAEC has evaluated the non-isolable parts of the hot shutdown piping systems to both the NRC site specific spectrum and the Yankee Composite Spectrum and the balance of piping systems for cold shutdown and accident mitigation to the Yankee Composite Spectrum. YAEC has
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proposed the installation of a dedicated hot shutdown system and not to upgrade the balance of structures and systems necessary for cold shutdown and accident mitigation.
In the enclosed safety evaluation, the staff concluded that Yankee was generally capable of withstanding postulated seismic loads, except for certain portions of structures, piping systems and nechanical and electrical equipment (includingsupports). Additional information and analyses from YAEC are necessaty to enable the staff to cocplete the seismic design review. These open issues will be evaluated and resolved during the integrated assessment.
This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built conditions at your facility. With respect to the potential modifica-tions outlined in the conclusion of this report, a determination of the N
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Sincerely.
O'1 1Dal aigneg by, 8
Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
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-i CC Mr. James E. Tribble, President Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701
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U. S. Environmental Protection.
Agency Region 1 Office ATTN: Regional Radiation Representative JFK Federal Building Boston, Massachusetts 02203 Resident inspector Yankee Rcwe Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350
.Honald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 4
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