ML030770234
| ML030770234 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/12/2003 |
| From: | Martin R NRC/NRR/DLPM/LPD2 |
| To: | Gordon Peterson Duke Energy Corp |
| References | |
| TAC MB5254, TAC MB5255 | |
| Download: ML030770234 (2) | |
Text
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.
5.5.1 Offsite Dose Calculation Manual (ODCM)
The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program.
Licensee initiated changes to the ODCM:
- a.
Shall be documented and records of reviews performed shall be retained.
This documentation shall contain:
- 1.
sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and
- 2.
a determination that the change(s) do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;
- b.
Shall become effective after the approval of the Station Manager; and
- c.
Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
5.5.2 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exceptions:
- a.
The containment visual examinations required by Regulatory Position C.3 shall be conducted 3 times every 10 years, including during each shutdown for SR 3.6.1.1 Type A test, prior to initiating the Type A test; and (continued)
Amendment Nos. 205/198 Catawba Units 1 and 2 5.5-1
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Containment Leakage Rate Testing Program (continued)
- b.
NEI 94-01-1995, Section 9.2.3: The first Type A test performed after the November 14, 2000 (Unit 1) and February 7, 1993 (Unit 2) Type A test shall be performed no later than November 13, 2015 (Unit 1) and February 6, 2008 (Unit 2).
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 14.68 psig. The containment design pressure is 15 psig.
The maximum allowable containment leakage rate, La, at Pa, shall be 0.3% of containment air weight per day.
Leakage Rate acceptance criteria are:
- a.
Containment leakage rate acceptance criterion is < 1.0 La. During the first plant startup following testing in accordance with this program, the leakage rate acceptance criteria are _ 0.75 La for Type A tests and < 0.6 La for Type B and Type C tests.
- b.
Air lock testing acceptance criteria for the overall air lock leakage rate is
- 5 0.05 La when tested at > Pa For each door, the leakage rate is < 0.01 La when tested at > 14.68 psig.
The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.
5.5.3 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable.- The systems include Containment Spray, Safety Injection, Chemical and Volume Control, and Nuclear Sampling. The program shall include the following:
- a.
Preventive maintenance and periodic visual inspection requirements; and
- b.
Integrated leak test requirements for each system at refueling cycle intervals or less.
5.5.4 DELETED (continued)
Amendment Nos.
205/198 Catawba Units 1 and 2 5.5-2