ML18010A505
| ML18010A505 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 01/15/1992 |
| From: | Mozafari B Office of Nuclear Reactor Regulation |
| To: | Eury L CAROLINA POWER & LIGHT CO. |
| References | |
| TAC-M81779, NUDOCS 9201240062 | |
| Download: ML18010A505 (7) | |
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UNITED STATES NUCLEAR REGULATORY COIVIIVIISSION WASHINGTON, D.C. 20555 january 15, 1992 Docket No.
50-400 Mr. Lynn W. Eury Executive Vice President Power Supply Carolina Power 8 Light Company Post Office Box 1551 Raleigh, North Carolina 27602
Dear Mr. Eury:
SUBJECT:
EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL CHANGES-SHEARON HARRIS NUCLEAR POWER PLANT, UNIT I (TAC NO. M81779)
By letter of July 26, 1991, Carolina Power 5 Light Company (CPSL) reported a
significant change, under 10 CFR 50.46, to the Emergency Core Cooling System (ECCS) Evaluation Model (EM) for its Shearon Harris Nuclear Power Plant, Unit l.
The submittal identifies changes to the large break loss-of-coolant accident (LOCA) analysis of record which would result in a cumulative change in calculated peak cladding temperature (PCT) of 64'F.
Fifty degrees of this amount are attributable to a temporary transition core penalty.
You have indicated that the large break LOCA PCT change is not significant; it appears that you have interpreted that this temporary 50'F change is not applicable in the determination of significance under 10 CFR 50.46.
The resultant PCT is 2169.2'F, which is within the performance requirements of 10 CFR 50.46.
The submittal also contained a report of a 178'F impact on calculated PCT for small break LOCAs with a resulting PCT of 1957.2'F.
This change is significant (greater than.50'F) under 10 CFR 50.46.
The small break spectrum continues to be non-limiting versus large break LOCAs.
You do not propose a schedule in your submittal for reanalysis or other reconciliation with the 10 CFR 50.46 model and related requirements.
The reporting requirements of 10 CFR 50.46 call for you to propose a schedule for restoration of the analyses of record to conformance with the requirements of 10 CFR 50.46 and 10 CFR 50, Appendix K.
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tpg The Duly 26, 1991, submittal satisfies the 10 CFR 50.46 requirements to report the changes and to assure that 10 CFR 50.46 performance requirements continue to be met.
however, you still must'propose a schedule for restoration of the analyses of record, for both large and small'break LOCAs, to conformance with the requirements of'0 CFR 50.46 and 10 CFR.50,, Appendix K.
Please inform us of your proposed sche'dule within 30 days of receipt of, this letter.
Sincerely,
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See next page Orignal signed by:
Brenda L., Mozafari, Project Manager Project.Directorate II-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation C: A:
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Mr. L'. W. Eury Carolina Power 5 Light Company Shearon Harris cc:
Mr. H.
Ray Starling Manager - Legal Department Carolina Power 5 Light Company P. 0.
Box 1551
- Raleigh, North Carolina 27602 Resident Inspector/Harris NPS c/o U. S. Nuclear Regulatory Commission Route 1, Box 3158 New Hill, North Carolina 27562 Mr. R.
B. Richey, Vice President Harris Nuclear Project Harris Nuclear Plant P. 0.
Box 165 New Hill, North Carolina 27562 Mr. H. A. Cole Special Deputy Attorney General State of North Carolina P. 0.
Box 629
- Raleigh, North Carolina 27602 Regional Administrator, Region TI U.S. Nuclear Regulatory Coomission 101 Marietta Street Suite 2900 Atlanta, Georgia 30323 Mr. C. S. Hinnant Plant General Manager Harris Nuclear Plant P. 0.
Box 165 New Kill, North Carolina 27562 Mr. Dayne H. Brown, Director Division of Radiation Protection N. C. Department of Environmental, Commerce 5 Natural Resources P. 0.
Box 27687 Raleigh, North Carolina 27611-7687
1 DOCUHENT NAME:
LTR EURY M81779 14E4 14H3 14B20 14B20 14B20 15B20 8E23 8E23 8E2
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DISTRIBUTION NRC PDR LPDR S.
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