JPN-96-052, Forwards Results of Reactor Vessel Head Weld Insps Conducted During 1996 Ro.Insp Data Shows No Changes from 1992 Data, Thus,Reactor Vessel Head Weld Indications Do Not Constitute Safety Concern
| ML20135E358 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/05/1996 |
| From: | William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20135E361 | List: |
| References | |
| JPN-96-052, JPN-96-52, NUDOCS 9612110200 | |
| Download: ML20135E358 (3) | |
Text
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123 Main Street White Plains, Now York 10601 914-681-6840 914-287 3309 (FAX)
- > NewY0rkPower M80rW William J. Cahill, Jr.
Chief Nuclear Othcer December 5,1996 JPN-96-052 United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 l
Washington, D.C. 20555
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Reactor Vessel Head Weld Flaw Indication Examination and Evaluation l
References:
see below j
Dear Sir:
Indications were detected in reactor vessel head weld VC-TH-1-2 during routine in-service inspections in 1990. Evaluations of the indications were performed in accordance with the 1
ASME code.. Reference 1 transmitted these evaluations to the NRC. The evaluations confirmed the existence of subsurface flaws due to original welding or manufacturing
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imperfections. It was concluded that restor operations with the existing weld flaws did not constituto a safety concern.
l In order for the reactor vessel head to be asepted for continued service, the NRC required in Reference 2 that a re-examination of the weld be performed during the next three refueling outages in accordance with /f ME,Section XI. The NRC also requested that the results of the reexaminations be incorpora ec into an analytic evaluation to justify continued operation and i
i that the evaluations should be st 5mitted to the NRC for staff review prior to resumption of reactor operation from each of the three subsequent operating cyc!es.
Examinations of reactor vessel head weld VC-TH-1-2 were performed in 1992 and 1995 and the examination results and analyses were submitted to the NRC in References 3 and 5. The NRC reviewed the 1992 and 1995 examination results and analyses and concluded that
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g continued operation of the FitzPatrick plant with the existing reactor vessel head flaw indication was acceptable (Referenc% 4 and 6).
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The attachment to this letter includes the results of the reactor vessel head weld inspections conducted during the 1996 refueling outage. The inspection data show no changes from the 1992 inspection data. Therefore, the original flaw evaluation remains valid. Based on the results of these inspections, the reactor vessel head weld indications do not constitute a safety concern.
9612110200 961205 i
PDR ADOCK 05000333 G
PDR Q9D
Based on the 1992,1995 and 1996 reactor vessel head weld flaw indication examinations and evaluations, the requirements of the NRC as detailed in Reference 2 have been met and the future weld examination schedule will revert to the original schedule as required by ASME Section XI.
If you have any questions, please contact Ms. C. D. Faison.
Very truly yours,
/4 (A 4 William J.
ahill, Jr.
Chief Nuclear Officer cc:
see next page i
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References:
1.
NYPA letter, J. C. Brons to NRC (JPN-90-040) dated May 25,1990, l
" Reactor Pressure Vessel Head Flaw Indication Inspections and i
Evaluation Analysis" 2.
NRC letter, D. E. LaBarge to J. C. Brons (TAC 76861) dated June 13, 1990, " Evaluation of Reactor Vessel Head Flaw Indication inspection and Evaluation Submittal-J. A. FitzPatrick Nuclear Power Plant" B
3.
NYPA letter, R. E. Beedle to NRC (JPN-92-036) dated July 9,1992,
" Reactor Pressure Head Welds Flaw Indication inspections and Evaluation Analysis" j
4.
NRC letter, B. C. McCabe to R. E. Beedle (TAC M84030) dated August i
11,1992, " Evaluation of Reactor Vessel Head Flaw Indication inspection -
and Evaluation Submittal - James A. FitzPatrick Nuclear Power Plant" 5.
NYPA letter, W. J. Cahill, Jr. to NRC (JPN-95-005) dated February 9, 1995, " Reactor Vessel Head Weld Flaw Indication inspections and Analysis" t
6.
NRC letter, C. E. Carpenter to W. J. Cahill, Jr. (TAC M91526) dated i
March 8,1995, " Evaluation of Reactor Vessel Head Flaw Indication Inspections and Evaluation - James A. FitzPatrick Nuclear Power Plant" cc:
Regional Administrator U. S. Nuclear Regulatory Commission 475 Allendale Road King Of Prussia, PA 19406
. Office of the Resident Manager U. S. Nuclear Regulatory Commission P. O. Box 136 Lycoming, NY 13093 Ms. K. Cotton, Acting Project Manager Project Directorate I-1 Division of Reactor Projects 1/11 Mail Stop 14B2 U. S. Nuclear Regulatory Commission Washington, DC 20555 i
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