ML030420570
| ML030420570 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/30/2003 |
| From: | Gordon Peterson Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML030420570 (5) | |
Text
Duke I-Power A Duke Energy Company GARY R. PETERSON Vice President Catawba Nuclear Station Duke Power CN01VP / 4800 Concord Rd York, SC 29745 803 831 4251 803 831 3221 fax grpeters@duke-energy corn January 30, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Technical Specification Bases Changes Pursuant to 10CFR 50.4, please find attached changes to the Catawba Nuclear Station Technical Specification Bases.
These Bases changes were made according to the provisions of 10CFR 50.59.
Any questions regarding this information should be directed to A.
P. Jackson, Regulatory Compliance, at (803) 831-3742.
I certify that I am a duly authorized officer of Duke Energy Corporation and that the information contained herein accurately represents changes ade to the Technical Specification Bases since the previ9us su mittal.
Attachment www duke-energy.com A'oo I
U.S. Nuclear Regulatory Commission January 30, 2003 Page 2 xc:
L.
A. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II R.
E. Martin, Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, Mail Stop 0-8-G9 E. G. Guthrie Senior Resident Inspector Catawba Nuclear Station
S Duke DUKE POWER
~ [dPower Catawba Nuclear Station 4800 Concord Rd A Duke Energy Company York, SC 29745 803 831 3000 January 30, 2003 Re:
Catawba Nuclear Station Technical Specifications (TS) Manual Please replace the corresponding pages in your copy of the Catawba Technical Specifications Manual as follows:
REMOVE THESE PAGES INSERT THESE PAGES List of Effective Pages Tab 3.4.16 B 3.4.16-5 B 3.4.16 B 3.4.16-6 If you have any questions concerning the contents of this Technical Specification update, contact Jill Ferguson at (803) 831-3938.
Gary D. Gilbert Manager, Regulatory Compliance www duke-energy corn Page 22 Page 22
Page Number B 3.4.13-5 B 3.4.13-6 B 3.4.14-1 B 3.4.14-2 B 3.4.14-3 B 3.4.14-4 B 3.4.14-5 B 3.4.14-6 B 3.4.15-1 B 3.4.15-2 B 3.4.15-3 B 3.4.15-4 B 3.4.15-5 B 3.4.15-6 B 3.4.16-1 B 3.4.16-2 B 3.4.16-3 B 3.4.16-4 B 3.4.16-5 B 3.4.16-6 B 3.4.17-1 B 3.4.17-2 B 3.4.17-3 B 3.5.1-1 B 3.5.1-2 B 3.5.1-3 B 3.5.1-4 B 3.5.1-5 B 3.5.1-6 B 3.5.1-7 B 3.5.1-8 B 3.5.2-1 Amendment Revision 2 Revision 1 Revision 0 Revision 1 Revision 0 Revision 0 Revision 0 Revision 1 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 1 Revision 0 Revision 0 Revision 0 Revision 0 Revision 1 Revision 0 Revision 0 Revision 0 Revision 1 Revision 0 Revision 0 Revision 1 Revision 2 Revision 1 Revision 0 Revision 0 Revision 0 Revision 0 Revision Date 2/18/02 2/18/02 9/30/98 2/26/99 9/30/98 9/30/98 9/30/98 2/26/99 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/13/01 9/30/98 9/30/98 9/30/98 9/30/98 1/28/03 1/28/03 9/30/98 9/30/98 5/19/00 9/30/98 9/30/98 10/02/00 10/02/00 10/02/00 9/30/98 9/30/98 9/30/98 9/30/98 Catawba Units 1 and 2 I I 01/28/03 Page 22
RCS Specific Activity B 3.4.16 BASES SURVEILLANCE REQUIREMENTS (continued)
Trending the results of this Surveillance allows proper remedial action to be taken before reaching the LCO limit under normal operating conditions.
The Surveillance is applicable in MODES 1 and 2, and in MODE 3 with Tavg at least 5000F. The 7 day Frequency considers the unlikelihood of a gross fuel failure during the time.
SR 3.4.16.2 This Surveillance is performed in MODE 1 only to ensure iodine remains within limit during normal operation and following fast power changes when fuel failure is more apt to occur. The 14 day Frequency is adequate to trend changes in the iodine activity level, considering gross activity is monitored every 7 days. The Frequency, between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power change > 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, is established because the iodine levels peak during this time following fuel failure; samples at other times would provide inaccurate results. If the power excursion is one continuous process spanning over several hours, there is no need to sample every hour, only 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the last major power change of
> 15% RTP, since this sample will encompass the maximum potential for additional iodine release to have occurred.
SR 3.4.16.3 A radiochemical analysis for E determination is required every 184 days (6 months) with the plant operating in MODE 1 equilibrium conditions.
The E determination directly relates to the LCO and is required to verify plant operation within the specified gross activity LCO limit. The analysis for E is a measurement of the average energies per disintegration for isotopes with half lives longer than 10 minutes, excluding iodines. The Frequency of 184 days recognizes E does not change rapidly.
This SR has been modified by a Note that indicates sampling is required to be performed within 31 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. This ensures that the radioactive materials are at equilibrium so the analysis for E is representative and not skewed by a crud burst or other similar abnormal event.
REFERENCES
- 1.
10 CFR 100.11, 1973.
- 2.
UFSAR, Section 15.6.3.
Catawba Units 1 and 2 B 3.4.16-5, Revision No. 1