ML19317F420
| ML19317F420 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/18/1972 |
| From: | Schwencer A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001140665 | |
| Download: ML19317F420 (1) | |
Text
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FEB 181972 NOTE TO FILES OCONEE POWER STATION UNITS 2 AND 3 REVIEW PLAN DOCKET NOS. 50-270/287 Based on a discussion with Mort Fairtile, the Materials Engineering Branch, DRS, will review certain aspects of the reactor coolant systen and containment as follows: (reference made to Oconee Review Plan dated February 16, 1972)
Item 4.5 Max Bolotsky will review Item 4.8 Mr. Fairtile concludes no further review is required related to reactor coolant pump flywheel integrity and that an adequate review has already been performed.
Item 4.11 Max Bolotsky will review Item 4.12 Max Bolotsky will review; this Item is directly related to Item 4.11 Item 4.13 No review is required at this time in light of Safety Guide Number 2, " Thermal Shock to Reactor Pressure Vessels", which states that a determination on thermal shock is five years away and that individual cases will not be further reviewed in this area unless significant changes in presently approved core or reactor pressure vessel designs are proposed for Oconee Units 2 and 3.
Since no significant changes have been made, such review for Oconee is unnecessary.
Item 5.14 Based on information on the record and from discussions at the February 10, 1972 meeting with Duke Power Company, Mr. Fairtile concludes that Item 5.14 has been satisfied on Oconee 2 and 3 without further evaluation.
4 MtW A. Schwencer cc:
R. C. DeYoung S. Pawlicki M. Fairtile i
I. Peltier A. Schwencer l
PWR-4 Reading l
8001140 h b._
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