ML19353A105
| ML19353A105 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/18/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| Shared Package | |
| ML19353A106 | List: |
| References | |
| TASK-02-02.A, TASK-2-2.A, TASK-RR LSO5-80-12-009, LSO5-80-12-9, NUDOCS 8101070179 | |
| Download: ML19353A105 (1) | |
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NRR Reading DEisenhut Docket No. S0-213 SEPB Reading RPurple LS05-80-12-009 TERA TJCarter OELD JHeltemes, AE0D OI&E (3)
Glainas Mr. W. G. Counsil Vice President ACRS (16)
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Nuclear Engineering and Operations NSIC, JBuchanan RTedesco o Connecticut Yankee Atomic Power Cogany WRussell CBerlingeM Post Office Box 270 DCrutchfield SEP File -
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Dear Mr. Counsil:
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SUBJECT:
HADDAM MECK - SEP TOPIC II-2.A SEVERE WEATHER PHEMOMENg g
__w The SEP review of Topic II-2.A. " Severe Weather Phenomena" has been cogleted. is the staff's safety evaluation (SE) for the Haddam Neck site.
The review was done in conformance with Standard Review Plan 2.3.1 and covers extreme tegeratures, lightning strikes, snow and ice loads and wind and tornado loadings. The wind and tornado loadings analysis was perfortued by the Texas Tech. University Institute for Disaster Research. Enclosure 2 is the Texas Tech. report. Please inform us if your as-built facility differs from the licensing basis assumed in our assessment within 30 days of receipt of this letter.
You will note that the SE identifies a design basis tornado with a probability of 10-7 per year and is consistent with a Regulatory Guide 1.76 design basis tornado. The staff intends to evaluate the structural characteristics of specific structures, systems and cogonents igortant to safety to determine their ability to withstand the severe weather loadings. The plant design parameters will then be comared tc the probability of occurrence of the wind as a part of our structural evaluation. This cogarison will be used to evaluate the necessity of design changes.
Sincerely, Dennis M. Crutchfield, Chief 7
Operating Reactors Branch #5 Division of Licensing
Enclosure:
As stated 1
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NQC FORM 318 (9-76) NRCM 0240 UU.S. GOVERNMENT PRINTING OFFICE: 1979 289-369