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=Text=
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      /
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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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,/ i- - i
RE:       Oconee Unit 1                                               s,    ,
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Docket No. 50                           g                              h                ,
Mr. Edson G. Case, Acting Director J
Office of Nuclear Reactor Regulation g
U. S. Nuclear Regulatory Commission f-M.",.
Washington, D. C.
20555 RE:
Oconee Unit 1 g
h s,
Docket No. 50


==Dear Mr. Case:==
==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.
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.
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.
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.
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.
The attached report provides additional details cf the modified core load-ing and supplements the information provided in the reload report.
Very           uly yours,
Very uly yours,
                    .                  /                   ~
/
              ,l ) ~ n t .       l.b .           /~
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Latest revision as of 01:19, 2 January 2025

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 
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 5 6

.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.",.

Washington, D. C.

20555 RE:

Oconee Unit 1 g

h s,

Docket No. 50

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,

/

~

,l ) ~ n t.

l.b.

/~

Jilliam O. Parker, Jr./v, PMA:ge Attachment t