ML18018A547

Forwards Response to Draft SER Open Items 32 & 33 Re irradiation-strengthened Zircaloy Yield Strengths & Predicted Cladding Collapse Time Exceeding Lifetime of Fuel, Respectively

ML18018A547
Person / Time
Site:	Harris
Issue date:	05/18/1983
From:	Mcduffie M CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
LAP-83-175, NUDOCS 8305200384
Download: ML18018A547 (8)

Text

RKGULIAITOR 'VFOR'>>IAIT'ION DCSTRLBUTCOIVI TKNI (RZOS)'CCESS I 0>>Vr, IVBR 8305'29 0384.. DGCI O'A>>TEIL 8'3/0 Sr/'l O'VOITIARZZKOle INOi DOCKEITI ti il

~

FIACCLI!50 400 Shearroflr ilalrr j si IVUc',lear: Power Piia'nti U'nj ~

~ C'a'roiiiinar 4'5000400, 50 401>> Sheair oni Henri sLNLrc,lear: PoHerr Pile'nt>>r U'ni ti 2'i ~ C'aroiliinei 05000401>>

AUTH AN'ANEI AUTHOR'FFCLIIAITCONI 4lCOUFFCKrg Mi, AICblroll ii nel PbWerl II'li gh ti Gbli.

RKGCP>>,NANSEI RKCCPCEIV>>TI AFFZLIIAT'IONr DENTO>>V<KH.R'., Qlf4j ce orfr IVUcl'aar Reactorr RegUI'alti on'r. Dli r ectoPi SUB JECITi: f<og rra<rds~ response ti tol d'r'alf SER: Otren>> Itelns: 32: 8 33>> re i,r raUialtiiop<<strengthen'ed>> Eircelloy; yield strengths L predi'ctedi cilekldingl cail labse time'xceedingl lii fat ime oifr. fLrely r espeL t>>i ve1ir>> ~

DCSTRIBUTCO>>VI CDOKlo 80018'DPCKS RECEIVED!:I.ITR." ' ENGLI i SIZEI: i >>>> i ' '

Lli censi'ngi SLromii ttalli,';- PSAR/F6AR Alndts" 8 Reilrslted>> Cbirr espopde'nce' '>>ITLKI:

NOiTESB RECIIPCKNITI COPrl RKCCPCENiTI

'NCLI COPiIKS'ITITR.

IDI GOOKY>>VA>>XEI KS'ITITR IOI COOK/IVAiIEI ENCLI

>>VR 8'/DLv'ROLI ii 0, ARRl LB3>> BCI 1>> OI iVRR'B3>> LAI 1>> 0 I>>>>'AOA>>98'I g Pr 01>> 1>> 1 I>>V>>TER>>VALI'LO'/H06'1i li 0 IKI FCI.KI 1 IK>>/DKPKR/EPBr 36', 3>> IKVDKPKR'/IRSi 35i I EVOEQA VQABI 22 >> ii >>VRR/OE</AK'ASI'RR/DK</EHEBi 1>> OI IVRR/DK'/GKBr 1L r ir 1>> 1>> 1

>>VRR'/DK>>/KQBl 13>> 2: 2. 2: 2' IVRR/DKVGB>>'8'RR'/DE>>/MEBr NRR/DK'/HGKBi 30; lr'r 1>> ~

IVRR'/DK>>/>>>>IITKBr 17r 1>> 2Q!

18'RR/DKi/SABi ii 1 NRR/OK/SGKBI 25i 2; 2. NRR/DHF6/Hr EB40 1>> 1 VRR/DHF6'/LQSI 32: 1>>'>>

ir VRR/DLVSSPSr 1>> OI

>>VRR/08II/AKBI 25 NRR/DSI/ASBi VITALS'>>

1>> 1>> 1 NRR/DSC/CPBi 1D, 1>> >>VRR/08 I/G3 BI 09, 1>> 1 iVRR/DSC/ I CBBI 1 b 1>> 1 >>VRR/DSI/~IEITBI 12: 1>> 1 NRR'/DBC/P6Br 19 lr 1>> >>VRR'/ RABl 22: 1>> 1 NRR'/08C/RSBr 23>> 1>> Lr FCL 04! 1>> 1 RGiV2: 3>> 3>> I I/RCSr 1>> OI EXTKRNALI: ACRS 4'1>> 6 6 B>>VLI(A>>4lDITSi ONLIY) ~ ii 1 lr FEI>>l'Ai RKPr DIIVI 39 ii LPOR'3>>

0618</086 NS ICI

( AI>>IOITi8'):

05i ir ii 1>>

1>>

ir iVRCI POR: 02: 1>>

1 1

1 TOITALI NURSER: 0>>r CDPKKB RKBVTRKD,;. LITITR, Bri ENCLI 47

0 it t II k II ~, '

l <<Pt M

II k

iJ'it iltt It i.

bi H fik ~ ) O M,

'l i,,l tl << t. f( I I t'IV

't 'I): fi I

'il 3

'll I I'k ,I) M { t';,IJ I

'HMH g,tit j g I. i

l )I f

'I IH H<< II k I(' t, ' M'

'

)ti i k I JI, h, I

JI Jit Vt Jj JH I Vki I Jt t r JH k I f)t I r

J, ~ re

• j r ) II

SERIAL: LAP-83-175 CXQE, Carolina Power & Light Company MAY 18 1S83 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS. 1 AND 2 DOCKET NOS. 50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSES MATERIALS ENGINEERING BRANCH

Dear Mr. Denton:

Carolina Power 5 Light Company (CPKL) hereby transmits one original and forty copies of the responses to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER) CPAL Open Item Nos. 32 and 33.

Carolina Power 4 Light Company will be providing responses to other Open Items in the DSER shortly.

Yours very truly, M. A. McDuffie Senior Vice President Engineering & Construction PS/cfr (6845PSA)

Attachment Cct Mr. N. Prasad Kadambi (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Dr. Phyllis Lotchin Mr. J. P. O'Reilly (NRC-RII) Mr. John D. Runkle Mr. Barry J. Elliot (NRC-MTEB) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. J. H. Carpenter (ASLB)

Chapel Hill Public Library Mr. J. L. Kelley (ASLB)

Wake County Public Library 830Sf8 8305200384 05000400 PDR ADOCK E PDR 411 Fayetteville Street o P. O. Box 1551 ~ Raleigh, N. C. 27602

1 v(, ,

>> qi -.

( y g~ , i)y( vi <<

~ ~

< 1~6;) sruti ~ ~ s t<<v~

<)0>> I I t\ +~ ~ l r>

'c:..f".'clef"

~,r i r 0 ~ - ~

i

~ f g (I f

'a

.1< i,'IA u'll ) fi . og wc+ ~ 'f i~~Oi I i~ <<tr I i i (If(

SHEARON HARRIS NUCLEAR POWER PLANT DRAFT SAFETY EVALUATION REPORT (DSER) 0 en Item 32 (DSER Sections 4.2.1. 1 and 4.2.3. 1 a es 4-4 4-16 and 4-28)

Resolve the use of irradiation-strengthened Zircaloy yield strengths.

~Res ense The fact that credit is taken for irradiation strengthening for the Zircaloy clad yield strength was documented as part of the WCAP-9500, "Reference Core Report 17x17 Optimized Fuel Assembly," and acknowledged in the NRC's Safety Evaluation dated May 1981 (page 7).

In support of this Westinghouse provided supplementary information to the staff<") that demonstrated excellent agreement between experimental data, BMI-NUREG-1948, and the best estimate curves described in the equation in the Westinghouse Materials Design Manual, WCAP-9179, Rev. 1.

(1) Letter from E. P. Rahe to C. 0. Thomas, NS-EPR-2687, dated November 30, 1982.

Ta',5 i $ f lfPA gh i 'I'H t p~p ) 'gepqr ~g rp r~ ~~ 'I P<t f ) + Call I'PN C

A If Q;Q p 4 M', $

l t 0 0 r

=: Pi'

SHEARON HARRIS NUCLEAR POWER PLANT DRAFT SAFETY EVALUATION REPORT (DSER) 0 en Item 33 (DSER Section 4.2.3.2 a es 4-21 4-22 and 4-29)

Confirm that the predicted cladding collapse time exceeds the expected lifetime of the fuel.

Response

The Shearon Harris fuel is designed and operated go that clad flattening vill not occur as predicted by the Westinghouse model.~ The predicted cladding collapse time for the fuel is )40 000 EFPH. The expected lifetime of the fuel is (40 000 EFPH.

George, R. Ae F et. ale F "Revised Clad Flattening Model", WCAP-8381, July 1974.