ML19312C582
| ML19312C582 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| 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
u.Eb NUCLOACJ C UWLURhLWW45%iR@ OCCXET NUM 5M
-- ~I C her.u 195 56 .2 6 9 kRO DISTRIBUTION con PART 50 DCCKET MATERIAL
. . FROM: OATS oP OCCqE_ _77 E G Case Duka Pow r Comoany Charlotte, NC OATE mECalvv0 W 0 Parker 9-12-77
,1M R CNOTCRIZED PRCP INPUT PCMM NUM8ER CP CCPIES RECElv50 2CHIG 6N Al= MNCLASSIPIE D pcCPv / J/W60 bCEtPTION ENCLCSURE Supplemant to BX4-1447 Ocenee 1, Cycle 4 Reload Report September, 1977 ....................
submitted in support of their 3-30-77 raquast p . ".' , for tech specs change .
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Mr. Edson G. Case, Acting Director J Office of Nuclear Reactor Regulation g U. S. Nuclear Regulatory Commission f-M ." , ..
20555
- Washington, D. C. -
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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