ML20198T073
| ML20198T073 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/29/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198T076 | List: |
| References | |
| NUDOCS 9711140192 | |
| Download: ML20198T073 (3) | |
Text
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4 B.
in Sen/ ice inspection and Testing of Safety Class Components Other than Steam Generator Tubes 1.
Inservice inspection of ASME Code Class 1, Class 2 and Class 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g) modified by Section 50.55a(b), except where specific written relief is granted by the NRC, pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
a.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
2.
Containment isolation valves will be tested in accordance with the Containment Leakage Rate Testing Program.
3.
Inservice testing of ASME Code Class 1,2, and 3 pumps, valves, and snubbers shall be performed in accordance with Section XI of the ASME Boiler and Pressura Vessel Code and applicable Addenda as required by 10 CFR 50.55a.
a.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
Basis The steam generator tube inspection requirements are based on the guidance given in NRC Regulatory Guide 1.83," Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes." ASME Section XI Appendix IV is being used for defining the basic requirements or the inspection method. However, at the present time, changes and improvements in steam generator eddy current inspection are occurring faster than the code can be revised. Thus, in order to ensure that the best possible exam of the tubing and/or sleeves is being dona, the technique utilized will, in general, be the Idest industry-accepted technique. This means that complete word-for-word compliance with Appendix IV may not be possible. However, the basic requirements and intent will be met, to the extent practical.
Specification 15.4.2.8 delineates programmatic requirements for establishing inservice inspection and Testing programs in accordance with the ASME Section XI Code and 10 CFR 50.55a requirements. The Code establishes criteria for system and component inspection and testing to ensure an appropriate level of reliability and detection of abnormal conditions. Failure to meet Code requirements is evaluated on an individual system or component bases to determine operability. Appropriate LCOs are entered if a system or component is detennined to be inoperable.
1 As stated in 15.4.2.8.1, safety class components, other than the steam generator tubing, will be inspected in accordance with ASME Section XI. The code edition / addenda utilized for the inspection interval will be as defined in Unit 1 - Amendment No. 63,95,449,181 Unit 2 - Amendment No. 68,99,464,185 Corrected October 24,1997 9711140192 971024 15.4.2-5 l
PDR ADOCK 05000266 p
=a
-h 15.6.12 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A.
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.
7 B.
The peak design containment intemal accident pressure, P, is 60 psig.
C.
The maximum allowable primary containment leakage rate, L, at P.,
shall be 0.4% of containment air weight per day.
D.
Leakage rate acceptance criteria are:
1.
The containment leakage rate acceptance criterion is s1.0 L,..
2.
During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.6 L, for the combined Type B and Type C tests and s 0.75 L, for
. Type A tests.
E.
The provisions of Specification 15.4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
F.
The provisions of Specification 15.4.0.3 are applicable to the Containment Leakage Rote Testing Program.
. Unit 1 - Amendment No. 449,181
- Unit 2 - Amendment No. 4M, '85 Corrected October 24,1997 15.6.12 L.
u
e-DATED: : October 24,' 1997 CORRECTION LETTER TO AMENDMENT NOS.181 AND 185 TO FACILITY OPERATING LICENSE NOS. DPR 24 AND DPR POINT BEACH UNITS 1 AND 2 ADockat File.:7 PUBLIC ~
PDill-1 Reading E. Adensam (EGA1)
C. Jamerson L. Gundrum OGC G. Hill (4)
W. Beckner.
J. Pulsipher ACRS J. McCormick-Barger, Rlli 6.,
J