ML040850314
| ML040850314 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/19/2004 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Khanna M, NRR/DLPM/EMCB, 415-2150 | |
| Shared Package | |
| ML040850665 | List: |
| References | |
| TAC MC1069, TAC MC1070, TAC MC1071 | |
| Download: ML040850314 (3) | |
Text
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
- g.
Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site-to areas at or beyond the site boundary:
- 1. For noble gases: less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin. and
- 2. For iodine-131. iodine-133. 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 mrems/yr to any organ:
- h.
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 10 CFR 50, Appendix I:
- i. Limitations on the annual and quarterly doses to a member of the public from iodine-131. iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I: and
- j. Limitations on the ann~ual dose or dose coimnitment 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 190.
5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR Section 3.9.1.1 cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments. including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with ASME Code Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC.
The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.
(continued)
PALO VERDE UNITS 1.2.3 5.5-4 AMENDMENT NO. 4-29,m5
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.15 Safety Function Determination Program (continued)
- b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or
- c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.
The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are.required to be entered.
When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.
5.5.16 Containment Leakage Rate Testing Program
- a.
A program shall be established to implement the leakage rate i
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:
- 1. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50.
Appendix J. Option B testing, will be performed.in accordance with the requirements of and frequency specified by ASME Code Section XI, Subsection IWL, except where relief has been authorized by the NRC. The containment concrete visual examination may be performed during either power operation. e.g.. performed concurrently with other containment inspection-related activities such as tendon testing, or during a maintenance/refueling outage.
- 2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50. Appendix J. Option B testing. will be performed in accordance with the requirements of and frequency specified by ASME Code Section XI. Subsection IWE.
except where relief has been authorized by the NRC.
(continued)
PALO VERDE UNITS 1 AND 3 5.5-23 AMENDMENT NO. 43_7,151 PALO VERDE UNIT 2 AMENDMENT NO. 44,151
Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
- 5.5.16 Containment Leakage Rate Testing Program (continued)
- b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa. is 52.0 psig for Units 1 and 3.
and 58.0 psig for Unit 2. The containment design pressure is 60 psig.
- c. The maximum allowable containment leakage rate, La. at Pa. shall be 0.1 % of containment air weight per day.
- d. Leakage Rate acceptance criteria are:
- 1. Containment leakage rate acceptance criterion is < 1.0 La.
During the first unit startup following testing in accordance with this program, the leakage rate acceptance are < 0.60 L. for the Type B and C tests and s 0.75 Lafor Type A tests.
- 2.
Air lock testing acceptance criteria are:
a)
Overall air lock leakage rate is 5 0.05 La when tested at 2 Pa-b)
For each door, leakage rate is
- 0.01 La when pressurized to 2 14.5 psig.
- e. The provisions of SR 3.0.2 do not apply to the test frequencies in the Containment Leakage Rate Testing Program.
- f. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
PALO VERDE UNITS 1,2,3 5.5-24 AMENDMENT NO. 434,151