ML20034E748
| ML20034E748 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/17/1993 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20034E749 | List: |
| References | |
| NUDOCS 9303010297 | |
| Download: ML20034E748 (4) | |
Text
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l' Duke 1%uer Company T C KManN
.i McGuire Nuclear Generation Department ike Ivesidcat e
12 :00 Hagm ferry Road (MG01A)
(704)8754N00 Hunterwdle. NC28078-8985 (704)S754809hk DUlU? POWER February 17, 1993 U.
S.
Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Supplement to Technical Specification Amendment i
Relocation of Cycle-Specific Parameter Limits i
Dear Sir; In a letter dated January 13, 1993, and supplemented on i
January 28, 1993, Catawba and McGuire Nuclear Stations I
submitted-technical specification changes which would relocate.certain cycle-specific parameter limits to the Core i
Operating Limits Report (COLR).
Since that time, an additional change to McGuire Technical Specification 6.9.1.9 has been identified which would add an approved topical report to the list of topicals used for determining the core j
operating limits.
Accordingly, please find attached the marked-up McGuire technical specification along with the technical justification and no significant hazards analysis.
i Please contact Paul Guill at (704) 875-4002 if there are any questions regarding this technical specification amendment i
request.
l Very truly yours, I
f Y
v T. C. McMeekin
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9303010297 930217
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Nuclear Commission February 17, 1993 page 2-cc:
with attachments Mr.
S.
D.
Ebneter Regional Administrator, Region II U.
S.
Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 l
Atlanta, Georgia 30323 l
t Mr.
P. K. Van Doorn
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Senior NRC Resident Inspector, McGuire McGuire Nuclear Station
[
Mr. T. A.
Reed, Project Manager Office of Nuclear Reactor Regulation l
U.
S.' Nuclear Regulatory Commission j
One White Flint North, Mail Stop 9H3 l
Washington, D.C.
20555 j
Mr. Dayne Brown, Chief Division of Radiation Protection P.O. Box 27687 Raleigh, North Carolina 276111 i
i i
U.
S.
Nuclear Regulatory Commission l
February 17, 1993 Page 3 bxc: With Attachment G.
A.
Copp (NS)
G.
B. Swindlehurst (NS)
M. E. Carroll (NS)
R.
O.
Sharpe M. T.
Cash P. F. Guill R. H. Clark (NS)
L.
T. Burba (NS) [ File:MC801.01]
M.
E.
Pacetti File: 801.01
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Proposed Revision to Technical Specification 6.9.1.9 Add NRC approved Topical DPC-NE-1004A, " Nuclear Design Methodology Using CASMO-3/ SIMULATE-3P" to the list of analytical methods used to determine the core operating limits.
NRC approval of the topical report was provided by a letter dated November 23, 1992.
i Technical Justification This change is administrative in nature sf.ce it updates the reference list with a newly approved topit21 which describes the methodology used to determine core operating limits.
The addition of this topical is necessary to allow future reloads to be carried out under 10 CFR 50.59.
No Sfynificant Hazards Analysis The proposed change to Technical Specification 6.9.1.9 adds approved topical DPC-NE-1004A to the list of analytical methods used_to determine core operating limits.
This change is administrative, adding a topical report which has i
been approved for use on McGuire to the list of analytical methods used to determine core operating limits.
Since this change is administrative, it has been determined that no i
significant hazards are involved.
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