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DUKE Powere Co>nwxy Powrn !!riunxo 422 Soinn Curucu STuttT. CurumrTE, N. C. una sa w,uia e Anncm,sa.
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July 27, 1977 v.cc >=c sic e=,
July 27, 1977 5ttaw PeoovCtiou.
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            .Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation qMb; Y U. S. Nuclear Regulatory Commission                       s-Y4 ,6\        . gy C Washington, D. C.
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.Mr. Edson G. Case, Acting Director wqMb; Y s-Y,6\\ gy C Office of Nuclear Reactor Regulation 4.
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==Dear Sir:==
==Dear Sir:==
 
My letters dated May 6, 1977 and June 21, 1977 requested amendments to the Oconee Nuclear Station Technical Specific.tions to provide for the operation of the Oconee 2, Cycle 3 core within applicable fuel design and performance criteria.
My letters dated May 6, 1977 and June 21, 1977 requested amendments to the Oconee Nuclear Station Technical Specific.tions to provide for the operation of the Oconee 2, Cycle 3 core within applicable fuel design and performance criteria. The report BAW-1452 "Oconee Unit 2, Cycle 3 Reload Report" was provided to support this amendment.
The report BAW-1452 "Oconee Unit 2, Cycle 3 Reload Report" was provided to support this amendment.
In the. report, it is pointed out that two Mark CR assemblies were to be included in this reload. The following information is provided concerning these assemblies.
In the. report, it is pointed out that two Mark CR assemblies were to be included in this reload.
The Mark CR demonstration fuel assemblies differ structurally from the Mark.C demonstration assemblies described in BAW-1424 only in the reconstitutable lower end fitting. The reconstitutable feature is provided by positioning the lower end fitting to the lower grid by flange sleeves on the guide tubes rather than.by welding the lower grid to the lower end fitting. Also, the lower end fitting is fastened                                               !:
The following information is provided concerning these assemblies.
to the guide tubes by torque nuts as in the Mark C demonstration assemblies; however,
The Mark CR demonstration fuel assemblies differ structurally from the Mark.C demonstration assemblies described in BAW-1424 only in the reconstitutable lower end fitting.
        -locking cups rather than by welding.the                 nuts are The cups          arebrazed prevented on a from     rotat,ing by swage retainer plate tube nut. that is restrained flush against the lower end fitting by a guide                                         8' The retainer plate cup brazement captures all 24 nuts by means of deformed metal tangs, so all nuts have to be untorqued before the brazement, including nuts, can be removed.
The reconstitutable feature is provided by positioning the lower end fitting to the lower grid by flange sleeves on the guide tubes rather than.by welding the lower grid to the lower end fitting.
t The Mark CR' design has been subjected to a 300 hour test at simulated reactor full power conditions with no deterioration or wear of any of the' parts flange              of the retainer system (brazement nuts, lawer end fittings sleeves).                                                                           ,
Also, the lower end fitting is fastened to the guide tubes by torque nuts as in the Mark C demonstration assemblies; however,
Cold water' tests were performed and the Mark CR design was found to have the same resonant frequency and amplitude as the Mark C design.- Bench tests have been performed on the retainer system to assure the locking cups are securely brazed to the nut plate and the swaged cups will prevent loosening of the nuts which are captured within the nut plate brazement. The Mark CR demonstration assemblies have been designed to maintain.their structural integrity through three cycles of operation and to successfully withstand seismic and los_s-of-coolant f
-locking cups rather than by welding.the nuts are prevented from rotat,ing by swage The cups are brazed on a retainer plate that is restrained flush against the lower end fitting by a guide tube nut.
loads.
The retainer plate cup brazement captures all 24 nuts by 8 '
Ver ! truly yours,
means of deformed metal tangs, so all nuts have to be untorqued before the brazement, including nuts, can be removed.
                                      \'
The Mark CR' design has been subjected to a 300 hour test at simulated t
A.Ld. a William O. Parker, Jr               .
reactor full power conditions with no deterioration or wear of any of the' parts of the retainer system (brazement nuts, lawer end fittings flange sleeves).
MST:ge U                                                                               ~}}
Cold water' tests were performed and the Mark CR design was found to have the same resonant frequency and amplitude as the Mark C design.- Bench tests have been performed on the retainer system to assure the locking cups are securely brazed to the nut plate and the swaged cups will prevent loosening of the nuts which are captured within the nut plate brazement. The Mark CR demonstration assemblies have been designed to maintain.their structural integrity through three cycles of operation and to successfully withstand seismic and los_s-of-coolant loads.
f Ver ! ruly yours, t
\\'
A.Ld. a William O. Parker, Jr MST:ge U
~}}

Latest revision as of 21:44, 1 January 2025

Submits Info Re Two Mark CR Demonstration Fuel Assemblies to Be Included in Cycle 3 Reload
ML19317F452
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 07/27/1977
From: Parker W
DUKE POWER CO.
To: Case E
Office of Nuclear Reactor Regulation
References
NUDOCS 8001140687
Download: ML19317F452 (2)


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Dear Sir:

My letters dated May 6, 1977 and June 21, 1977 requested amendments to the Oconee Nuclear Station Technical Specific.tions to provide for the operation of the Oconee 2, Cycle 3 core within applicable fuel design and performance criteria.

The report BAW-1452 "Oconee Unit 2, Cycle 3 Reload Report" was provided to support this amendment.

In the. report, it is pointed out that two Mark CR assemblies were to be included in this reload.

The following information is provided concerning these assemblies.

The Mark CR demonstration fuel assemblies differ structurally from the Mark.C demonstration assemblies described in BAW-1424 only in the reconstitutable lower end fitting.

The reconstitutable feature is provided by positioning the lower end fitting to the lower grid by flange sleeves on the guide tubes rather than.by welding the lower grid to the lower end fitting.

Also, the lower end fitting is fastened to the guide tubes by torque nuts as in the Mark C demonstration assemblies; however,

-locking cups rather than by welding.the nuts are prevented from rotat,ing by swage The cups are brazed on a retainer plate that is restrained flush against the lower end fitting by a guide tube nut.

The retainer plate cup brazement captures all 24 nuts by 8 '

means of deformed metal tangs, so all nuts have to be untorqued before the brazement, including nuts, can be removed.

The Mark CR' design has been subjected to a 300 hour0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> test at simulated t

reactor full power conditions with no deterioration or wear of any of the' parts of the retainer system (brazement nuts, lawer end fittings flange sleeves).

Cold water' tests were performed and the Mark CR design was found to have the same resonant frequency and amplitude as the Mark C design.- Bench tests have been performed on the retainer system to assure the locking cups are securely brazed to the nut plate and the swaged cups will prevent loosening of the nuts which are captured within the nut plate brazement. The Mark CR demonstration assemblies have been designed to maintain.their structural integrity through three cycles of operation and to successfully withstand seismic and los_s-of-coolant loads.

f Ver ! ruly yours, t

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A.Ld. a William O. Parker, Jr MST:ge U

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