ML18010A923
| ML18010A923 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/19/1992 |
| From: | Mccarthy D CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-92-321, TAC-M84220, NUDOCS 9211300007 | |
| Download: ML18010A923 (6) | |
Text
i'ccrc.za.~rzo or maunOw oncOxsm~rrax SvSrmc REGULATO INFORMATION DISTRIBUTION TEN (RIDE)
ACCESSION NBR:9211300007 DOC.DATE: 92/11/19 NOTARIZED: NO FACIL:50-400 Shearon,Harris, Nuclear Power Plant, Un', Carolina AUTH.NAME AUTHOR AFFILIATION MCCARTHY,D.C.
Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET 05000400
SUBJECT:
Forwards response to NRC 921106 request for addi info re high head safety injection sys performance.All ref analyses indicated core remained well within acceptance criteria of 10CFR50FApp K.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR l ENCL g SIZE:
E TITLE: OR Submittal: General Distribution S
NOTES:Application for permit renewal filed.
05000400 /
RECIPIENT ID CODE/NAME PD2-1 LA LE,N XNTERNAL: ACRS NRR/DOEA/OTSBll NRR/DST/SXCB8H7 NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: NRC PDR COPXES LTTR ENCL 1
1 2
2 6
6 1
1 1
1 1
1 1
0 1
1 1
1 RECIPIENT ID CODE/NAME PD2-1 PD NRR/DET/ESGB NRR/DST/SELB 7E NRR/DST/SRXB SE REG FXLE 01 NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
0 1
1 1
1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.
ROOM P !-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T HEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL 20
4
~ f
SKK Carolina Power 8 Light Company NOV 19 199K SERIAL:
NLS-92-321 TAC No.
M84220 1
United States Nuclear Regulatory Commission ATTENTION; Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 HIGH HEAD SAFETY INJECTION -
SMALL BREAK LOCA ANALYSES Gentlemen:
As requested by your letter of November 6,
- 1992, the following formally dockets information provided to the staff in early November in response to their requests regarding the high head safety injection system performance.
On October 16,
- 1992, NRC Staff verbally requested that CP6L submit a
"realistic" analysis of the limiting size Small Break Loss Of Coolant Accident (SBLOCA) for the Shearon Harris Nuclear Power Plant (SHNPP),
assuming high head safety injection performance consistent with the "as found" degraded condition described in previous correspondence.
In response to this request, CPSL completed SBLOCA analyses for 2, 3 and 4 -inch break sizes using an unverified, but benchmarked, RELAP 2.5 computer model which was available for SHNPP.
The results of this analysis were plotted graphically for the following parameters:
reactor vessel upper plenum pressure and vapor temperature, total break flow, safety injection flow, steam generator
- outflow, and peak clad temperature and quality at various levels in the reactor core.
The analyses indicated that t:he limiting SBLOCA occurs for the 3-inch break
- size, which is consistent with the results described in the SHNPP FSAR.
Two additional cases, a
20% and a 50% reduction in the "as found" condition, were completed for the limiting break size to establish the sensitivity of the results to reduction in the "as found" high head safety injection degraded condition.
All of these analyses indicated that the core remained well within the acceptance criteria of 10 CFR 50 Appendix K.
Enclosed are copies of the packages described above'3oi.<O 411 Fayettevilte Street I P. O. Box 1551 I Raleigh, N. C. 27602 9211300007
'922119 PDR ADOCK OS000eoo P
Pj)R
1 1
Document Control Desk NLS-92-321 / Page 2
Questions regarding this matter may be referred to Mr. R.
W. Prunty at (919) 546-7318.
Yours very truly, D.
C. McCarth Manager Nuclear Licensing Section
, SDC/sdc Enclosures cc:
Mr. S.
D. Ebneter Mr. N..B. Le Mr. J.
E.
Tedrow
l 4
41 Al a
ai