ML052350189

Technical Specification Bases (Tsb) Change

ML052350189
Person / Time
Site:	Oconee
Issue date:	08/11/2005
From:	Rosalyn Jones Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML052350189 (3)

Text

RONALD A JONES

_ Duke Vice President MWPower, Oconee Nuclear Site Duke Power ON01 VP / 7800 Rochester Hwy.

Seneca, SC 29672 864 885 3158 864 885 3564 fax August 11, 2005 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk

Subject:

Oconee Nuclear Station Docket Numbers 50-269, 270, and 287 Technical Specification Bases (TSB) Change Please see attached Technical Specification Bases Page B 3.5.3-9, which was issued with Amendment 340/342/341 dated September 2, 2004. This page introduced a pagination error.

The attached page will correct that error.

If any additional information is needed, please contact Graham Davenport at 864-885-3044.

Very m yours, R. A.1 Oconee lear Site www. dukepower. comrn 4(,

U. S. Nuclear Regulatory Commission August 11, 2005 Page 2 cc: Mr. L. N. Olshan Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. S. E. Peters Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 Mr. W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mel Shannon Senior Resident Inspector Oconee Nuclear Station Mr. Henry Porter Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia, SC 29201

LPI B 3.5.3 BASES SURVEILLANCE SR 3.5.3.6 REQUIREMENTS (continued) Periodic inspections of the reactor building sump suction inlet ensure that it is unrestricted and stays in proper operating condition. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage, on the need to preserve access to the location, and on the potential for an unplanned transient if the Surveillance were performed with the reactor at power. This Frequency has been found to be sufficient to detect abnormal degradation and has been confirmed by operating experience.

REFERENCES 1. 10 CFR 50.46.

2. UFSAR, Section 15.14.3.3.6.

3. UFSAR, Section 15.14.3.3.5.

4. 10 CFR 50.36.

5. NRC Memorandum to V. Stello, Jr., from R.L. Baer, "Recommended Interim Revisions to LCOs for ECCS Components," December 1, 1975.

6. ASME, Boiler and Pressure Vessel Code, Section Xl, Inservice Inspection, Article IWV-3400.

7. NRC Safety Evaluation of Babcock & Wilcox Owners Group (B&WOG) Topical Report BAW-2295, Revision 1, "Justification for the Extension of Allowed Outage Time for Low Pressure Injection and Reactor Building Spray systems," (TAC No. MA3807) dated June 30, 1999.

OCONEE UNITS 1, 2, & 3 B 3.5.3-9 Amendment Nos. 340, 342, & 341 l