ML031500477
| ML031500477 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/29/2003 |
| From: | Marshall M NRC/NRR/DLPM/LPD2 |
| To: | |
| References | |
| TAC MB6987, TAC MB6988 | |
| Download: ML031500477 (2) | |
Text
ADMINISTRATIVE CONTROLS
- h.
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. Visual examination and testing, including test intervals and extensions, shall be in accordance with Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995 with exceptions provided in the site implementing instructions. Performance of the spring 2003 containment integrated leakage rate (Type A) test may be deferred up to 5 years but no later than spring 2008.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 12.0 psig.
The maximum allowable containment leakage rate, La, at Pa, is 0.25% of the primary containment air weight per day.
Leakage rate acceptance criteria are:
- a.
Containment overall leakage rate acceptance criteria is s 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the combined Type B and Type C tests, and s 0.75 La for Type A tests;
- b.
Air lock testing acceptance criteria are:
- 1. Overall air lock leakage rate is s 0.05 La when tested at 2 Pa.
- 2. For each door, leakage rate is s 0.01 La when pressurized to > 6 psig for at least two minutes.
The provisions of SR 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of SR 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
- i.
Configuration Risk Management Program (DELETED)
Amendment No. 217, 241, 281, 287 SEQUOYAH - UNIT 1 6-1 Oa
ADMINISTRATIVE CONTROLS 6.8.4 f.
Radioactive Effluent Controls Program (Cont.)
of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,
- 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be in accordance with the following:
- 1.
For noble gases: Less than or equal to a dose rate of 500 mrem/yr to the whole body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and
- 2.
For lodine-1 31, lodine-1 33, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/year to any organ.
- 8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,
- 9)
Limitations on the annual and quarterly doses to a member of the public from lodine-1 31, lodine-1 33, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and
- 10)
Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
The provisions of SR 4.0.2 and 4.0.3 are applicable to the radioactive effluent controls program surveillance frequency.
- 9.
Radiological Environmental Monitorinq Program (DELETED)
- h.
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. Visual examination and testing, including test intervals and extensions, shall be in accordance with Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995 with exceptions provided in the site implementing instructions. Performance of the fall 2003 containment integrated leakage rate (Type A) test may be deferred to no later than spring 2007.
The peak calculated containment internal pressure for the design basis loss of coolant accident, P, is 12.0 psig.
The maximum allowable containment leakage rate, La, at P., is 0.25% of the primary containment air weight per day.
Leakage rate acceptance criteria are:
- a.
Containment overall leakage rate acceptance criteria is S 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are S 0.60 La for the combined Type B and Type C tests, and <
0.75 La for Type A tests; SEQUOYAH - UNIT 2 6-9 Amendment No. 28, 50, 64, 66, 134, 165, 202, 207, 223, 265, 272, 276