ML061640249
| ML061640249 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/12/2006 |
| From: | Plant Licensing Branch III-2 |
| To: | |
| Miller G, NRR/DLPM, 415-2481 | |
| Shared Package | |
| ML061640077 | List: |
| References | |
| TAC MC8549 | |
| Download: ML061640249 (1) | |
Text
ADMINISTRATIVE CONTROLS 6.14.1 (Continued)
- 3)
A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;
- 4)
An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments thereto;
- 5)
An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto;
- 6)
A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the change is to be made;
- 7)
An estimate of the exposure to plant operating personnel as a result of the change; and
- 8)
Documentation of the fact that the change was reviewed and found acceptable by the SORC.
- b.
Shall become effective upon review and acceptance by the SORC.
6.15 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 exception:
- a.
NEI 94-01-1 995, Section 9.2-3: The first ILRT performed after October 30, 1992 shall be performed no later than April 29, 2008.
The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 49.6 psig.
The maximum allowable containment leakage rate, La, at Pa, shall be 0.15% of primary containment air weight per day.
SEABROOK - UNIT 1 6-22 SEABOOK UNT 1
-22 Amendment No. 22, 66, 88, 1014, 1097, 108