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=Text=
=Text=
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NRC DISTRIBUTION roR PART 50 DOCKET rd'ATERIAL FROM:                                               oATE or occVMENT                                     ,
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T;.
Duke Power Company 7/27/77 Mr. Edson G. Case William O. Parker, Jr.
Duke Power Company                                               7/27/77 Mr. Edson G. Case                                             William O. Parker, Jr.                             oATE REcEivEo                                       o Charlotte, North Carolina                                         8/1/77                               >
oATE REcEivEo o
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ONOTomt2ED PROP 9NPUT FORM NUMBER OF COPIES RECE!VEo 5
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Consists of information regarding Mark CR assemblies.....
ENCLOSU RE oEsemPTsCg Consists of information regarding Mark CR assemblies.....
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,,,sv PLANT NAME:
                                                                                                                                                                              #c.,
0.onec Unit No. 2 9l m
                                    ,,,sv PLANT NAME:             0.onec Unit No. 2                                                                                                                                   m 9l 2d RJL             8/2/77                                                                                                                                                 %
2d RJL 8/2/77 FOR ACTION /INFORMATION ENVIPfiNMENTAL f.,
FOR ACTION /INFORMATION                         ENVIPfiNMENTAL                                       f.,
1AFEW I
1AFEW                                                                                                                                                             )j siGNE Lgp                          .
ASSIGNED AD:
I ASSIGNED AD:     V. MOORE (LTR)
V. MOORE (LTR)
V s-xiCH CHIEF-                          '  ''
)j siGNE Lgp
                                                          '"
?'? 7 3''' f" C BRANCH CHIEF:
                                                                    ?'? 7 3''' f" C                     BRANCH CHIEF:                                                         n!
n!
SOJECT t'ANAGER:
V s-xiCH CHIEF-b SOJECT t'ANAGER:
                                                                              ~~
~~
PROJECT MANAGER:                                                     b LICENSING ASSISTANT:
PROJECT MANAGER:
LICENSING ASSISTANT:
A CFJSING ASSTiSTANT:
A CFJSING ASSTiSTANT:
i                                                                                                B. HARLESS x.:~ .
x B. HARLESS
[        _ _ __ _.T
.:~.
                          <                                                INTERNAL DISTRIBUTION                                                                               h 5 f uEn FT' Ec
i
  "*tisc pnn~
_ _ __ _.T INTERNAL DISTRIBUTION h
j                        SYSTFMS SAFETY HEINuAN PLANT SYSTEMS TEDESCO SITE SAFETY &
[
ENVIRON ANALYSIS h
h 5 f uEn FT' Ec j
T
SYSTFMS SAFETY PLANT SYSTEMS SITE SAFETY &
  '-
"*tisc pnn~
is? M -                                     SCHROED_ER                                     BENAROYA                       DENTON & MULLER
HEINuAN TEDESCO ENVIRON ANALYSIS T
  's      nein
is? M -
                                                                                            '
SCHROED_ER BENAROYA DENTON & MULLER Y.ATNAS CRITTruFTFT D "h
Y.ATNAS                       CRITTruFTFT D                             "h
's nein C09 SICK & STAFT ENGINEERING IPPOLITO wairru RNTCHT
                                                                                                                                                                            '
!F. ROSA ENVIRO TECH.
C09 SICK & STAFT                             ENGINEERING                                 IPPOLITO wairru                                       RNTCHT                                     !F. ROSA                         ENVIRO TECH.
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BOciAK                                    l                                ERNST                                      l I v t ur'
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                                            "''          SluWELL                                      OPERATING REACTORS            EALLARD                                    d
. I c_t sE SluWELL OPERATING REACTORS EALLARD djj tinyn PA%1TCKI STELLO YOUNGELOOD ETCENH1TT i
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                                                                                                ^
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ETCENH1TT                                                                 i i
Son Tect VANACEVENT PEACTOR SAFETY
I Son Tect VANACEVENT                           PEACTOR SAFETY                         -V       SHAO                       _._ _ _.
-V SHAO
                                                                                                                                      " ' " ' ~ "
" ' " ' ~ "
* POSS                                  V           EAER gynvuoi.T 1 001.TTNS                                 NOVAK                                 V           EUTLER                     GAMMILL               (2)                         !
* V EAER gynvuoi.T POSS 1 001.TTNS NOVAK V
ROSZTOCZY                                 Y       GRIMES                                                                 4
EUTLER GAMMILL (2)
_        unnSmN Y CHECK                                                                           SITE ANALYSIS
!4 unnSmN ROSZTOCZY Y
_M tJ 2 HELTrMES                                                                                                                 VOLLMER                                    g W                                         AT&I                                                                         BUNCH                               .      .a SALTZMAN                                                             V     J. COLLINS
GRIMES Y CHECK SITE ANALYSIS
                  -                                    RUTSEFG                                                                  ' KREGER CONTROL NUMBER EXTERNAL O!STRIBUTICN                                                                                                   e%
_M tJ 2 g
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VOLLMER HELTrMES W
      .
AT&I BUNCH
    ''
.a SALTZMAN V
TIC
J. COLLINS RUTSEFG
* V        NSIC                                                              7                                                h
' KREGER e%
                                                                                                                                                                            ' N "AT LAB                                                                                                                                   __,m
EXTERNAL O!STRIBUTICN CONTROL NUMBER 2:
                                                                                                                                                                        /       h
u m2. w.e. m 7
_
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__ _ _ ___
NSIC TIC "AT LAB
                                                                                                                                                - - -                                  ,
__,m
REG IV (J. HANCHETT)I i                               --                                                              -
/
Y        16 CYS ACRS SENT CAT 3 GORY B                                                                                                             $
' N h
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REG IV (J. HANCHETT)I i Y
v e .c : u 1..ia.1.'                                                                                                                                                         #
16 CYS ACRS SENT CAT 3 GORY B
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                                        '
+
                                                                                      +
DUKE Powere Co>nwxy Powrn !!riunxo 422 Soinn Curucu STuttT. CurumrTE, N. C. una sa w,uia e Anncm,sa.
  , ,_                                        DUKE Powere Co>nwxy Powrn !!riunxo 422 Soinn Curucu STuttT. CurumrTE, N. C. una sa w,uia       e Anncm,sa.
July 27, 1977 v.cc >=c sic e=,
v.cc >=c sic e=,
5ttaw PeoovCtiou.
July 27, 1977 5ttaw PeoovCtiou.
GN me. osc 4.c. 7c.
                                                                              ,,Mi GN         [f me. osc 4.c. 7c.
,,Mi
                                                                          ,,
[f 373 4083
r,                  373 4083 iN          }m w
}m r,
            .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.
,,iN
                                                                    ,  -
.Mr. Edson G. Case, Acting Director wqMb; Y s-Y,6\\ gy C Office of Nuclear Reactor Regulation 4.
M 20555                    ';3 Es,x.myNE[%#
U. S. Nuclear Regulatory Commission Es,x.myNE[% M Washington, D. C.
ff'           e   I
20555
: r. 2.\                     d RE: Oconee Unit 2                                                                 gc,
';3 ff' I
                                                                        'N                   g/
e
Docket No. 50-270 g            'g,                  '                                .
: r..\\
                                                                                                                                    '
d RE: Oconee Unit 2 2
gc,
'N g/
g
'g, Docket No. 50-270


==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.
                                                                                                                                ;
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 The cups          arebrazed prevented on a from     rotat,ing by swage retainer
-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 hour test at simulated t
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.
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).
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).                                                                           ,
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.
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
f Ver ! ruly yours, t
loads.
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Ver ! truly yours,
A.Ld. a William O. Parker, Jr MST:ge U
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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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