ML19210B992
| ML19210B992 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 10/26/1979 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | GENERAL ELECTRIC OPERATING PLANT OWNERS GROUP |
| Shared Package | |
| ML19210B970 | List: |
| References | |
| NUDOCS 7911130120 | |
| Download: ML19210B992 (2) | |
Text
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NUCLEAR REGULATORY COMMISSION h ). N I $
WASHING TON, D. C. 20555
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- gv Utility Gentiemen:
RE: ACCEPTANCE CRITERIA FOR THE MARK I CONTAINMENT LONG TERM PROGRAM The staff has completed its review of the generic aspects of the Mark I Containment Long Term Program (LTP). The results of this review are reflected in the enclosed acceptance criteria, which are intended to be used to perform individual plant-unique analyses for each Mark I f acili ty.
These criteria have been developed from the staff's evaluation of the Mark I LTP Load Definition Report, Plant Unique Analysis Appli-cations Guido, and related suppression pool hydrodynamic experimental and analytical programs, which have been submitted by the Mark I Owners Group.
In developing these criteria, we have considered verbal comments providad by representatives of the Mark I Owners Group on a draft of the criteria issued August 2,1979. These comments were presented to the staff curing a meeting held on August 15, 1979, and supplementec by aaaitional information provided in a letter from General Electric cated September 7, 1979. This information and internal comments by the staff and our consultants have resulted in some modifications to the draft criteria.
However, others of the Owners Group recommendations were not adopted for the NRC criteria, based on the staff's judgment relative to the interpretation of specific data or analyses.
In certain cases, the staff's generic criteria identify specific nyoro-dynamic load assessment techniques that will have to be evaluated on a plant-specific basis. However, deviations from any other generic criteria shoula De avoided.
The criteria also identify additional experimental verification that must be obtained for " condensation oscillation" load uncertainty. This requirement was communicated to you earlier in our letter dated October 2, 1979.
1323 050 i
7911130
. Within 30 days of your receipt of this letter, we request that you provide the schedule for submittal of the LTP plant-unique analysis for your f acility. In developing this schedule, you should consider that we are continuing to target the completion of this program and the termination of the exemption issued for your facility for December 1980. The staff presently expects to issue the generic Safety Evaluation Report supporting these criteria in December 1979.
Should you have any questions regarding this action contact C. Grimes (301-492-8204).
Darrell G. Eisenhut, Acting Director Division of Operating Reactors
Enclosure:
As stated 13L23 05i t
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