ML19312C582

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Forwards Suppl to BAW-1447, Oconee 1,Cycle 4 Reload Rept, Which Accounts for Unexpected Replacement of Three Batch 4 Fuel Assemblies
ML19312C582
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 09/08/1977
From: Parker W
DUKE POWER CO.
To: Case E
Office of Nuclear Reactor Regulation
Shared Package
ML19312C583 List:
References
NUDOCS 7912180889
Download: ML19312C582 (2)


Text

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. . FROM: OATS oP OCCqE_ _77 E G Case Duka Pow r Comoany Charlotte, NC OATE mECalvv0 W 0 Parker 9-12-77

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Mr. Edson G. Case, Acting Director J Office of Nuclear Reactor Regulation g U. S. Nuclear Regulatory Commission f-M ." , ..

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RE: Oconee Unit 1 s, ,

Docket No. 50 g h ,

Dear Mr. Case:

By letter of March 30, 1977, we submitted proposed Technical Specification changes and the supporting reload report applicable to Oconee 1 Cycle 4.

This submittal was supplemented by our letter of August 23, 1977, to take into account the operation of Cycle 3 up to 308 EFPD. During the refueling operation, however, fuel assembly 1D40, a Batch 4 fuel assembly intended to undergo Cycle 4 operation in core location N-12, was damaged while it was being examined in the Post Irradiation Examination facility. The nature of the damage was s ch that the upper portion of a corner fuel rod was displaced from the upper fuel assembly skirt and as such is considered unsuitable for re-insertion into the core. Therefore, this fuel assembly is to be replaced by a once-burned Batch 2 fuel assembly. Because of this replacement, three other Batch 4 fuel assemblies in 1/4-core-symmetric locations are to be replaced with Batch 2 assemblies to maintain core s mmietry.

The nuclear, mechanical, thermal-hydraulic and safety considerations of the substitution of four Batch 2 assemblies for the Batch 4 assemblies have been evaluated, and 't has been determined that the conclusions re-garding the safety of Cycle 4 operation as described in the reload report (BAW-1447, March 1977) are unaffected by the modified core loading.

Furthermore, it has been deternined that no changes are required for the Technical Specifications previously established for Cycle 4 operation.

The attached report provides additional details cf the modified core load-ing and supplements the information provided in the reload report.

Very uly yours,

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Jilliam O. Parker, Jr./

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