ML12264A591

Supplemental Information for Relief Request Number ISI-09 R. E. Ginna Nuclear Power Plant - Fifth Interval Inservice Inspection Program Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii) Component Cooling Water 1 Inch Half-Cou

ML12264A591
Person / Time
Site:	Ginna
Issue date:	09/18/2012
From:	Mogren T Constellation Energy Group, EDF Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12264A591 (2)

Text

Thomas Mogren Manager, Engineering Services R.E. Ginna Nuclear Power Plant, CENG a joint venture of LLC 1503 Lake Road Ontario, New York 14519-9364 585.771.5208 0 1Iflt"lO *-O-%eDF Thomas. Moqren(Mcenqllc.com September 18, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

R.E. Ginna Nuclear Power Plant Docket No. 50-244 Supplemental Information for Relief Request Number ISI-09 R. E. Ginna Nuclear Power Plant - Fifth Interval Inservice Inspection Program Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii) Component Coolina Water 1 Inch Half-Couplina Weld Leak

REFERENCES:

(a) Letter from Mr. Thomas Mogren (Ginna LLC) to Document Control Desk (NRC) dated September 6, 2012,

Subject:

Relief Request Number ISI-09 R. E. Ginna Nuclear Power Plant - Fifth Interval Inservice Inspection Program Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii) Component Cooling Water 1 Inch Half-Coupling Weld Leak By Reference (a), R.E. Ginna Nuclear Plant, LLC (Ginna LLC) submitted Relief Request ISI-09 per 10 CFR 50.55a (a)(3)(ii), seeking relief from the requirement to perform code repairs during the next scheduled refuling outage (RFO). The following supplemental information is being provided to support the previous request.

On September 6, 2012, the ASME Section XI Code Mandatory Appendix IX mechanical clamp was removed in order to perform a supplemental Radiographic Examination (RT).

The RT examination was performed with a shot at 0 degrees and a shot at 90 degrees.

Both RT shots utilized an ASTM wire Image Quality Indicator (IQI), the smallest wire visible was 0.013 "Diameter.

The RT supplemental examination confirmed the initial visual examination results that this original manufacturing defect was lack of fusion. The RT 0 degree shot confirmed that the lack of fusion was 0.25" long. The RT 90 degree shot confirmed that the indication appears to be non-fusion on the fillet weld leg and through wall. No additional weld flaws were identified as a result of the RT supplemental examination.

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Document Control Desk September 18, 2012 Page 2 Ultrasonic Examination (UT) was also attempted with the mechanical clamp removed but due to the joint configuration, UT was unable to volumetrically interrogate the area of concern. UT shear wave was able to interrogate the instrument side piping base metal and found no indications.

With the mechanical clamp removed, a VT-1 Visual Examination of the affected weld area was performed and no changes were identified or leakage noted. When the mechanical clamp was reassembled, an ASME Section XI VT-2 leakage examination was performed and no leakage was identified.

The supplemental RT examinations confirmed the findings of the original visual examination results that the indication is lack of fusion. The RT supplemental examination also confirms the geometric size of this original manufacturing lack of fusion. The geometric sizing of this original manufacturing lack of fusion indication is bounded by the analysis described within R. E. Ginna Nuclear Power Plant's In-service Inspection Relief Request ISI-09.

There are no new regulatory commitments identified in this correspondence. If you have any questions or need any other clarifying information, please contact Thomas L.

Harding, at (585) 771-5219.

Sincerely, Thomas Mogren cc: M.C. Thadani, NRC Ginna Resident Inspector, NRC W.M. Dean, NRC