ML18087A064
| ML18087A064 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/27/2018 |
| From: | Martha Barillas Plant Licensing Branch II |
| To: | Hamilton T Duke Energy Progress |
| Barillas M DORL/LPL2-2 301-415-2760 | |
| References | |
| Download: ML18087A064 (14) | |
Text
Harris Nuclear Plant Pre-Submittal Meeting - March 27, 2018
10 CFR 50.55a Relief Request Proposed Alternative Regarding Repair and Replacement Testing Requirements for Harris Nuclear Power Plants Equipment Hatch Sleeve Weld 2
Duke Energy Participants Keith Henshaw, Reactor Vessel Head Replacement Project Lead Engineer Sarah McDaniel, Licensing Engineer 3
Equipment Hatch & Interference Removal Cut location of the Equipment Hatch Sleeve 4
Equipment Hatch Removal Separation of the Body Ring from the Liner Sleeve after the cut 5
Equipment Hatch Reinstallation 6
Inside groove of reinstallation weld and non-destructive examinations performed first
Equipment Hatch Reinstallation The completed full penetration weld reattaching the Body Ring to the Liner Sleeve 7
Harris Nuclear Plant - Applicable Code Edition and Addenda Inservice Inspection Program (ISI) Third Interval for Containment ASME Boiler and Pressure Vessel Code Section XI, 2007 Edition with 2008 Addenda Containment Vessel Code of Construction ASME Boiler and Pressure Vessel Code Section III, Subsection NE, 1974 Edition with 1975 Winter Addenda 8
Proposed Alternative Installation of the Leak Chase Coupling Assembly 9
Proposed Alternative and Basis for Use 100% magnetic particle testing and 100% volumetric radiographic testing exams of the circumferential weld prior to leakage test Channel strength and simultaneous leakage (pressure decay) test at 115% of design pressure, 51.8 psig Localized leak rate testing in the weld area Bubble test per IWE 5223.4 and ASME Section V, Article 10, Appendix I Testing in this manner is consistent with original Owner requirements in Ebasco Specification CAR-SH-AS-1 1110
FSAR and Original Design Specification HNP FSAR Section 3.8.1.1.3.3 and the original Ebasco Design Specification (CAR-SH-AS-1) identify that the Equipment Hatch penetration sleeve has sufficient material to initially allow for six removals and re-welding HNP performed Equipment Hatch Body Ring removal and reinstallation during the steam generator replacement in Fall 2001 Concrete Containment will not be not modified 11
Precedents Waterford Steam Electric Station, Unit 3, 2012 - steam generator replacement Opening of the steel containment vessel construction hatch required relief from leakage test code requirements under ASME,Section XI, IWE-5221 Davis Besse Nuclear Power Station, Unit 1, 2013 - steam generator replacement Construction openings in the steel containment vessel required relief from the regulatory condition on IWE-5000 in 10 CFR 50.55a (b)(2)(ix)(J) of performing an Appendix J, Type A, integrated leak rate test Watts Bar Nuclear Power Plant, Unit 1, 2006 - steam generator replacement Construction openings in the steel containment vessel required relief from leakage test code requirements under ASME,Section XI, IWE-5221 12
Conclusion The combination of 100% magnetic particle testing and 100% volumetric radiographic testing exams and the localized leak rate test of the reinstallation weld will confirm the full volumetric integrity of the equipment hatch body ring weld.
In accordance with 10 CFR 50.55a(z)(1), the localized leakage testing proposed will provide an acceptable level of quality and safety in lieu of the Type A integrated leak rate test.
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