ML18018B819

Forwards Response to SER Confirmatory Item 11 Re pressure-temp Curve.Present Curves Do Not Require Rev

ML18018B819
Person / Time
Site:	Harris
Issue date:	11/21/1984
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NLS-84-248, NUDOCS 8411260268
Download: ML18018B819 (6)

Text

REGUL'ATOR NFORMAT ION DISTRIBUTION TEM (R IDS)

ACCESSION NBR; 8411260268 DOC ~ DATE! 84/11/21 NOTARI'ZED e NO DOCKET5000400

.FACIL:50-400 Shearon Harris Nuclear Power Plantg Uni"t 1~ Carolina AUTH+NAME AUTHOR AF F ILI ATXON ZIMMERMANiS ~ R ~ Car o l i na Power. 8 . I.'i gh t Co.>

REC IP', NAME RECIPIENT AFFILIATION DENTONgH,RE Officet of Nuclear Reactor Regulationi Director, SUBJECT! Forwards response to SER Confirmatory Item 11 >re pressure"temp curVe, Present curves do not require r ev.

Dl'STRIBUTION CgDgs A001D,~COPIES RECEIVEDtLTR -. ENCL t "" SIZE'

'TITLE: OR Submittal! General Distribution NOTES!

RECIPIENT COPIES RECIPIENT COPIES "ID CODE/NAME-. LTTR- ENCL> ID CODE/NAME- LTTR -ENCL NRR LB3- BC 01 7 t7 INTERNAl.; ACRS Q9 6 6 ADM/LFMB 1 0.

ELD/HDS1 1 0 NRR/DE/MTEB 1~

NRR/DL DIR 1 1 NRR/DL/ORAB 1 Q NRR I'/ B 1 1 NRR/DSI'/RAB 1 1 Q4 1 RGN2 1 EXTERNAL: LPDR 03 ,1 .1 NRC~ PDR ~

02 1 1-NSIG 05 1 1 NTIS 1 1 TOTAl. NUMBER OF COPIES REQUIRED! LTTR 26 ENCL 23'

v n '<1<< l N ~ vv Qv<< l fv "~-'

1I s! I Qt(l $ <<,v y>>

v v E

~jlj f C I ') <<y!' ~

'

y a I 'l R Rti f %4gQ f g v!) f >>n '1 ><<v << f ))>>' f)<<, y

>>0"! v "%jtf p<<>> Q!y fi jc r9 <<>>>>'1 f L~ j'!! 'jj v'>> Il ) 'f fwgvv lg "I <<lv'<<,g v)! ~ f~'<<<<+P +@A l>>"

qTjj; v]J hajj),'j f1>jt f l4 fili f k,'1,<<!" lv", f<<, N 'Ij f ')f~<, p>> . jj 1 f <

Il I 'i~.>> 'Y'!7 ],~, <

v tV" l !1tT,<< j s%

f

>> I ll Pl ill, wv <<, Ii >>,, 'v y, < f,'

j

"',(Nv<<!<<I:lv' I

@ME, Carolina Power 8 Light Company NOV 31 1984 SERIAL: NLS-84-248 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO. 50-400 PRESSURE-TEMPERATURE CURVE

Dear Mr. Denton:

Carolina Power 6 Light Company hereby submits additional information concerning the pressure-temperature curve, per Appendix G, 10 CFR 50, for the Shearon Harris Nuclear Power Plant. This information is in response to Safety Evaluation Report Confirmatory Item 11 from the Materials Engineering Branch.

If you have further questions or desire additional information, please contact our staff.

Yours very truly, S. . mmerman nager Nuclear Licensing Section JHE/ccc (200NLU)

Attachment cc: Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. John D. Runkle

'r. Travis

,

Mr. J. P. O'Reilly (NRC-RII)

Mr. Daniel Payne (KUDZU)

F. Read (CHANGE/ELP)

Dr.

Mr.

Richard D. Wilson G. 0. Bright (ASLB)

Dr. J. H. Carpenter (ASLB)

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

'Wake County Public Library 84ii260268 84i.i2i I~

PDR *DOCK E

05000400.

PDR .> ~~

,e(

411 Fayettevitte Street o P, O. Box 1551 o Raleigh, N. C. 27602

Xo W hl t d r

~ I!

SHEARON HARRIS NUCLEAR POWER PLANT SAFETY EVALUATION REPORT CONFIRMATORY ITEM NO. 11 ITEM The applicant's pressure-temperature curves meet all the requirements of Appendix G, 10 CFR 50, except for the safety margins required for the closure flange region materials. However, the applicant has indicated that he will revise the pressure-temperature limits to conform with the safety margins required by Appendix G, 10 CFR 50, for the closure flange region materials.

RESPONSE

The limiting beltline material for Shearon Harris Nuclear Power Plant (SHNPP)

Unit 1 is correctly stated in the Safety Evaluation Report as being plate B-4197-2, with an RTND 90'F. The RTN T's for the closure flange regions of the SHNPP Unit 1 vessel are O'F for the%egad flange and -8'F for the vessel flange. Thus, application of the new Appendix G rule will not modify the SHNPP Unit 1 pressure-temperature curves. When pressure exceeds 20 percent of the preservice system hydrostatic test pressure (3106 psig) or 621 psig, the temperature of the closure flange regions (i.e., the temperature of the reactor coolant) must exceed 120'F.. The present curves bound that value.

Likewise, for hydrostatic tests and inservice leak testing, the temperature of the closure flange regions must exceed 90 F. The present SHNPP Unit 1 curves bound this condition; therefore, the pressure-temperature curves for SHNPP Unit 1 do not require revision. SHNPP Unit 2 was canceled in December 1983; therefore, information relative to that unit is no longer necessary.