ML18004A502
| ML18004A502 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/26/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-316, NUDOCS 8609020155 | |
| Download: ML18004A502 (4) | |
Text
REGULA.
RY INFORMATION DISTRIBUTl SYSTEM (R IDS)
ACCESSION NBR: 8609020155 DQC. DATE: 86/08/26 NOTARIZED:
NO DOCKET ¹ FACIL: 50-400 Shearon Harris Nuclear Poiiier Plant.
Unit 1> Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION ZIMl'lERNAN>S. R.
Carolina Power 5 Light Co.
RECIP. NAME RECIPlENT AFFILIATION DENTQN> H. R.
Office of Nuclear Reactor Regul ation> Director (post 851125
SUBJECT:
Notifies of completion of reanalysis of large break LOCA for plant. Results indicate local water-zirconium reaction of
- 4. 616/
8( total core eater-zirconium reaction less than
- 0. 3/
w/2113 F pealed c lad temp.
DISTRIBUTION CODE:
BOOID COPIEB RECEIVED: LTR Q ENCL 0 BIIE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts Zf Related Correspondence NOTES: Application for permit reneidal filed.
05000400 REC IPIENT ID CODE/NAME PWR-A EB PWR-A FOB PWR-A PD2 PD PWR-A PSB INTERNAL: ADM/LFNB IE FILE IE/DGAVT/GAB Zi NRR PWR-B ADTS NRR/DHFT/NTB R('N2 EXTERNAL: BNL(AMDTS ONLY)
LPDR 03 NSIC 05 COPIES LTTR ENCL RECIPIENT ID CODE/NAME PWR-A EICSB PWR-A PD2 LA BUCKLEY>B 01 PWR-A RSB ELD/HDS1 IE/DEPER/EPB 36 NRR BWR ADTS NRR ROE. M. L 04 I/MIB DMB/DSS (AMDTS)
NRC PDR 02 PNL ('RUEL> R COPIES LTTR ENCL 2
TOTAL NUNBER OF COPIEB REQUIRED:
LTTR 30 ENCL
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SMK Carolina Power & Light Company SERIAL: NLS-86-316 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.50-000 LOCA REANALYSIS
Dear Mr. Denton:
Carolina Power R Light Company (CPRL) has completed reanalysis of the Large Break LOCA for the Shearon Harris Nuclear Power Plant (SHNPP).
Westinghouse performed this reanalysis for CPfgt:L utilizing the 1981 ECCS Evaluation Model with BART per WCAP-9561, Addendum 3, Revision l. The limiting break (C
= 0.0) was reanalyzed using the initial conditions specified in CP6tL's May 22, 1986%atter NLS-86-f67 utilizing an F limitof 2.28 and a steam generator tube plugging limitof 6 percent.
The results show a local water-zirconium reaction of 0.616 percent, and a total core water-zirconium reaction of less than 0.3 percent with a peak clad temperature of 2113'F.
This analysis does not require any changes to the proposed final Technical Specifications and demonstrates conformance to 10 CFR 50.06 for the SHNPP ECCS Large Break LOCA Analysis.
If you have any questions on this subject, please contact me at (919) 836-6202.
Yours.very truly, DCM/vaw (00603DK) cc:
Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
S.. Zi erman ager Nuclear Licensing Section Sb062f020i55 8b082b PDR ADQCY, 05000400 I
A PDR 411 Fayettevilte Street e P. O. Box 1551
~ Raleigh. N. C. 27602 goo<
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