ML19351F663
| ML19351F663 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/18/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| References | |
| NUDOCS 8101130710 | |
| Download: ML19351F663 (3) | |
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UNITED STATES
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5 Docket Nos. 50-440 and50-4pl DEC 181980 l
Mr. Dalwyn R. Davidson Vice President, En9ineering The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101
Dear Mr. Davidson:
SUBJECT:
ULTIMATE CAPACITY ANALYSES OF MARK III CONTAIhMENTS -
PERRY NUCLEAR POWER PLANT, UNITS 1 & 2 As part of the staff's generic review of the effects of hydrogen evolving from a postulated accident, all applicants who have either an ice condenser or Mark III pressure-suppression containment design are being requested to perform an ultimate capacity analysis for the containment. Since the Perry Nuclear Power Plant utilizes the Mark III containment design, we request that you perfonn such an analysis, as described in the enclosure.
We further request that within 30 days of your receipt of this letter, you identify the schedule by which the results of this analysis will be submitted to the staff.
Sincerely, Robert L. Tedesco Assistant Director for Licensing Division of Licensing
Enclosure:
Ultimate Capacity Analyses of i
Ice Condenser and fiark III Continments cc w/ enclosure:
See next page l
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Mr. Dalwyn R. Davidson Vice President, Engineering The Cleveland Electric Illuminating Company DEC 18 03B0 P. O. Box 5000 Cleveland, Ohio 44101 cc: Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 Donald H. Hauser, Esq.
Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 U. S. Nuclear Regulatory Commission Resident Inspector's Office Parmly at Center Road Perry, Ohio 44081 1
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ULTIMATE CAPACITY At:ALYSES OF ICE Cor10EllSER At!D i; ARK III C0tlTAltIMEt:TS Detailed analyses are to be performed to assess the effect on containment integrity of a potential hydrogen burn. Ultimate capacity of the containment should be evaluated using a finite element model. Uniform static pressure capability should be calculated. Dynamic local and overall pressure capability should also be assessed. Based on the actual material strengtji variations indicated by mill test certificates and other uncertainities, the mean, an estimate of disperson, and lower and upper bounds of the containment capacity should be established. The details of the analyses and the results should be submitted in report form. The following information should be rt.adily identifiable in the report:
1.
Design pressure; 2.
Calculated static pressure retaining capacity; 3.
Calculated dynamic pressure strength considering appropriate pressure time histories; 4.
The associated failure modes (axisymmetric burst pressure, buckling, rebar yielding, penetration failure, closure failure, or others);
5.
The criteria governing the original design and the criteria used to establish failure; 6.
Analysis details and general results; and 7.
Appropriate engineering drawings adequate to allow verification of modeling and evaluation of analyses employed for penetrations.
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