ML15280A422
| ML15280A422 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/19/2015 |
| From: | Farideh Saba Plant Licensing Branch II |
| To: | Nazar M Nextera Energy |
| Buckberg P, NRR/DORL, 415-1383 | |
| Shared Package | |
| ML15280A377 | List: |
| References | |
| TAC MF4694, TAC MF4695 | |
| Download: ML15280A422 (2) | |
Text
ADMINISTRATIVE CONTROLS (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.
- 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and
- 3) Participation in a lnterlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
- h. Containment Leakage Rate Testing Program A program to implement the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions. This program is in accordance with the guidelines contained in NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," except that the next Type A test performed after the December 8, 2005 Type A test shall be performed no later than December 8, 2020.
The peak calculated containment irltl3rriaf pressure for the design basis loss of coolant accident Pa, is 42.8 psig. The containment design pressure is 44 psig.
The maximum allowed containment leakage rate, La. at Pa. shall be 0.50% of containment air weight per day.
Leakage rate acceptance criteria are:
- a. Containment leakage rate acceptance criterion is .:s_ 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests,
.:::. 0.75 La for Type A tests, and.:::. 0.096 La for secondary containment bypass leakage paths.
- b. Air lock testing acceptance criteria are:
- 1) Overall air lock leakage rate is .:s_ 0.05 La when tested at~ Pa.
- 2) For the personnel air lock door seal, leakage rate is < 0.01 La when pressurized to~ 1.0 Pa.
- 3) For the emergency air lock door seal, leakage rate is < 0.01 La when pressurized to~ 1O psig.
ST. LUCIE - UNIT 1 6-15b Amendment No. 00, 89, 423, 449, 48'.f., 497, 200, 243 I 226 Corrected by letter dated 10/19/15
ADMINISTRATIVE CONTROLS 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,
- 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 Specifications 4.0.2 and 4.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.
- g. Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide ( 1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of the environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.
- 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are maderlf required by the results of this census, and
- 3) Participation in a lnterlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
- h. Containment Leakage Rate Testing Program A program to implement the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions. This program is in accordance with the guidelines contained in NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," except that the next Type A test performed after the December 18, 2007 Type A test shall be performed no later than December 18, 2022.
The peak calculated containment internal pressure for the design basis loss of coolant accident Pa, is 43.48 psig. The containment design pressure is 44 psig.
The maximum allowed containment leakage rate, La, at Pa, shall be 0.50% of containment air weight per day.
ST. LUCIE - UNIT 2 6-15b Amendment No. e4-, ~. 4-6G, 44Q, 440, 463, 1 76 Corrected by letter dated 10/19/15