ML19262A313
| ML19262A313 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/12/1976 |
| From: | METROPOLITAN EDISON CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| GQL-0176, GQL-176, NUDOCS 7910260640 | |
| Download: ML19262A313 (3) | |
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o-Mr. J. P. O'Reilly, Director Office of Inspection and Enforcement, Region 1 i-s U. S. Nuclear Regulatory Cer=ission 631 Fark Avenue Fing of Prussia, Pennsylvania 19h06 THREE !CLE ISLAND NUCLEAR STATION UNIT 1 (TIE-1)
OPERATING LICENSE 50. DFR-50 DCCKET UO. 50-289
Dear Sirs:
By cur letter of January 13, 1976, we informed you that we were reviewing the steam line break accident analyses presented in the CII-l FSAR. This reviev was conducted since the results of preli= int.ry analyses for steam line break accident analyses conducted for C E-2 had indicated maximum tolerable water inventories were less than that presented in the T!E-1 FS W..
As a result, we considered it necessary to verify that the cenclusion in the CC-1 FSAR concerning suberiticality margin during the transient retained valid.
'"hese analyses in the T!E-1 FSAR vere conducted using a different ec=puter ecde than the TIE-2 steam break analyres. The ecde used for the !?E-2 analyses is more efficient (in terms of eccputer time and ranpcVer requirements) than the cede used for the C E-1 FSAR analyses. In order to achieve this efficiency, additional conservatis s had to be inccrporated into the new code. The maximum tolerable water inventeries for steam break accidents predicted by the code utilized for TIE-2 was therenre incensistent with the conservatively assured tolerable water inventories tamtlated in the SII-l FSAR.
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February 12, 1976 TJ. OlTc Page 2 Re: 3REE ClE ISU.'TD ITUCLEAR STATIC: U:!IT 1 (241-1)
CPERATI!G LICE !SE IiO. DPR-50 ECCKET :IO. 50-289 On January 13, 1976, when our first letter in this regard was fervarded, we had no knowledge of the differences between these two ec=puter codes.
'4e have since verified that the code an1 analyses presented in the T:'!-l FSA".
are adequate and factual. In addition, we have confirmed that even utilizing the =cre ecnservative ec=puter code ec=bined with conservatively assumed water inventories based or as-built parameters, the TMI-l FSAR conclusiens regarding the reacter's suberiticality =argin during the transient are stin true.
Should you have any further questiens in this regard, please centact me.
Sincerely, r
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