ML20064N335
| ML20064N335 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/21/1994 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20064N338 | List: |
| References | |
| NUDOCS 9403290267 | |
| Download: ML20064N335 (2) | |
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P.0 Eku 1006 Senior Vice President Owlone.NC282011006 Nuclear Generation (704)382-2200 otnce (704)3824360 Fax DUKEPOWER March 21,1994 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk
Subject:
Catawba Nuclear Station Docket Numbers 50-413 and -414 Technical Specification Revision to Change Method of Measuring Reactor Coolant System Flow Rate By letter dated January 10, 1994, Duke Power Company submitted an application to change the method by which reactor coolant system flow is measured for Technical Speci6 cation surveillances at McGuire and Catawaba Nuclear Stations. The proposed method involves normalizing the cold-leg elbow tap APs to constants derived from previously-performed calorimetric heat balances. While initial NRC review indicates that the proposed method may be acceptable, some issues have emerged which require further study. However, the Staff has expressed a willingness to consider the proposed change, to be effective for a limited time at Catawba Unit I (the duration of the current fuel cycle),~ to enable Unit I to reach 100% power. Unit 1 is currently limited to 98% power due to an erroneous flow measurement.
Therefore, Duke Power hereby submits this supplemental application, to justify the proposed change, as submitted in the January 10,1994 letter, to be effective for the remainder of Catawba Unit 1 Cycle 8.
This proposed change is applicable to Unit 1 of Catawba Nuclear Station only.
The marked-up Technical Speci6 cation pages are contained in Attachment I, and additional justification to support the limited-duration change appears in Attachment II. This justification includes an analysis of the safety significance in the event that the low flow measurement were assumed ta be correct, and other information requested by the Staff in a March 16,1994 meeting. Because this application does not change the original intent or process of the original submittal, the No Significant Hazards analysis presented in the January 10,1994 letter is considered to remain valid.
If any additional information is required, please call Scott Gewehr at (704) 382-7581, h a.fi' M. S. Tuckman 9403290267 940321
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' U. S. Nuclear Regulatory Commission March 21,1994 Page 2
-l cc: Mr. V. Nerses, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 14H25, OWFN Washington, D. C. 20555 Mr. R. E. Martin, Project Manager Of0ce of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 14H25, OWFN Washington, D. C. 20555 Mr. S. D. Ebneter, Regional Administrator U.S. Nuclear Regulatory Commission - Region 11 101 Marietta Street,- NW - Suite 2900 Atlanta, Georgia 30323 G. F. Maxwell Senior Resident inspector McGuire Nuclear Station R. J. Freudenberger Senior Resident Inspector Catawba Nuclear Station Dayne Brown, Director Division of Radiation Protection P. O. Box 27687 Raleigh, North Carolina 27611-7687 Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina
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