ML19317F452

From kanterella
Revision as of 21:44, 1 January 2025 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
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)


Text

_ -. - _.

Q :;>

0 o

.NRc7aT Uls u.s. NuctE.n nEcuLs.roRv cNtuission cocxET NuurEn

. S

,'? 7 C ir,m NRC DISTRIBUTION roR PART 50 DOCKET rd'ATERIAL

"""8'"

FROM:

oATE or occVMENT T;.

Duke Power Company 7/27/77 Mr. Edson G. Case William O. Parker, Jr.

oATE REcEivEo o

Charlotte, North Carolina 8/1/77 U LE TTE;)

ONOTomt2ED PROP 9NPUT FORM NUMBER OF COPIES RECE!VEo 5

r D'NcLAssirsED

' ' do;;icsN AL.

$ 4 r*a r_s c* cl u

CccPs

~

& -1Ae it. Lf" S-C-77

  • L 2/~%

ENCLOSU RE oEsemPTsCg Consists of information regarding Mark CR assemblies.....

l 9l

,, 6 i

(1-P)

', 5 5.

ll

,QrjQ,C t

L.

W

. 7. -7

.J 3-1.s,

  1. c.,

,,,sv PLANT NAME:

0.onec Unit No. 2 9l m

2d RJL 8/2/77 FOR ACTION /INFORMATION ENVIPfiNMENTAL f.,

1AFEW I

ASSIGNED AD:

V. MOORE (LTR)

)j siGNE Lgp

?'? 7 3 f" C BRANCH CHIEF:

n!

V s-xiCH CHIEF-b SOJECT t'ANAGER:

~~

PROJECT MANAGER:

LICENSING ASSISTANT:

A CFJSING ASSTiSTANT:

x B. HARLESS

.:~.

i

_ _ __ _.T INTERNAL DISTRIBUTION h

[

h 5 f uEn FT' Ec j

SYSTFMS SAFETY PLANT SYSTEMS SITE SAFETY &

"*tisc pnn~

HEINuAN TEDESCO ENVIRON ANALYSIS T

is? M -

SCHROED_ER BENAROYA DENTON & MULLER Y.ATNAS CRITTruFTFT D "h

's nein C09 SICK & STAFT ENGINEERING IPPOLITO wairru RNTCHT

!F. ROSA ENVIRO TECH.

l I v t ur' BOciAK l

ERNST

. I c_t sE SluWELL OPERATING REACTORS EALLARD djj tinyn PA%1TCKI STELLO YOUNGELOOD ETCENH1TT i

i

^

Son Tect VANACEVENT PEACTOR SAFETY

-V SHAO

" ' " ' ~ "

  • V EAER gynvuoi.T POSS 1 001.TTNS NOVAK V

EUTLER GAMMILL (2)

!4 unnSmN ROSZTOCZY Y

GRIMES Y CHECK SITE ANALYSIS

_M tJ 2 g

VOLLMER HELTrMES W

AT&I BUNCH

.a SALTZMAN V

J. COLLINS RUTSEFG

' KREGER e%

EXTERNAL O!STRIBUTICN CONTROL NUMBER 2:

u m2. w.e. m 7

h V

NSIC TIC "AT LAB

__,m

/

' N h

REG IV (J. HANCHETT)I i Y

16 CYS ACRS SENT CAT 3 GORY B

i i y

80011@ h[f [

v e.c : u 1..ia.1.'

+

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=,

5ttaw PeoovCtiou.

GN me. osc 4.c. 7c.

,,Mi

[f 373 4083

}m r,

,,iN

.Mr. Edson G. Case, Acting Director wqMb; Y s-Y,6\\ gy C Office of Nuclear Reactor Regulation 4.

U. S. Nuclear Regulatory Commission Es,x.myNE[% M Washington, D. C.

20555

';3 ff' I

e

r..\\

d RE: Oconee Unit 2 2

gc,

'N g/

g

'g, Docket No. 50-270

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

\\'

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

~