ML20043G665
| ML20043G665 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/13/1990 |
| From: | Labarge D Office of Nuclear Reactor Regulation |
| To: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| TAC-76861, NUDOCS 9006200546 | |
| Download: ML20043G665 (3) | |
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WASHINGTON, D, C,20665 June 13. 1990 i
Docket No. 50-333 k
. Mr. John C. Brons Executive Vice President - huclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Brons:
SUBJECT:
EVALUATION OF REACTOR VESSEL HEAD FLAW INDICATION-I INSPECTION AND EVALUATION SUBMITTAL - J.A.-FITZPATRICK NUCLEAR POWER PLANT (TAC NO. 76861)
By~ letter dated May 25, 1990, you submitted your analysis report to the NRC' detailing the reactor vessel head weld flaw. indications detected during the 1990 refueling. outage at the James A. FitzPatrick Nuclear Power Plant. The report was submitted.in accordance with-Section XI of the 1980 Edition of-the~
- American Society of Mechancial Engineers (ASME) Boiler and Pressure Vessel t
Code.
The report describes several recordable flaws that were detected in reactor vessel head Weld Number VC-TH-1-2 as a result of routine ins)ections conducted in.accordance with the Inservice' Ins outageusingultrasonictesting(UT)pectionProgramduringtie1990 refueling techniques.
It also contains an
. evaluation report from the General Electric Company called, " Structural Evaluation of Indications in the Reactor Top Head at the.JA FitzPatrick Power i
Station," dated May 1990 (DRF #137-0010).
Initially, the routine tests conducted-in accordance with the inservice inspection program revealed several indications along the circumferential weld-between the dollar plate and the vertical dome segments. As a result,.
supplemental exams were conduc wd from both the inside and outside surfaces of the head, and-com) uter techniques were used to enhance radiographs taken during construction'of t1e head and during the 1990 outage. Also an automated UT process.was used to better examine and define the flaw sizes.
As a result of this effort, four se)arate flaw indications were identified.
Your. resort concludes that two of tle flaws were acceptable without repair under t1e flaw acceptance standards of the ASME Code,-Section XI. The remaining two flaws exceeded the Acceptance Standards in ASME Code Section XI,
.IWB-3500 and were evaluated analytically by the General Electric Company using the' Flaw Evaluation Criteria of ASME Code Section XI, IWB-3600. This analysis showed that the flaws were not service induced, that the flaws were not evident on the inside surface of the vessel head, and that the growth prediction at the end-of the next fuel cycle is well below the depth allowed by the, Code.
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Mr. John C. Brons
-2 June 13, 1990 Based on your analysis, you conclude that the flaws are subsurface, were due to
' original welding imperfections, and that continued operation of the reactor with the existing reactor vessel head flaw indications do not constitute a safety concern.
Based on the data presented and your analytic evaluations of the flaws, the staff has determined that the reactor vessel head has sufficient fracture toughness to preclude fracture of the head with the flaws remaining in the component and the head is acceptable for continued service for at least one H
additional fuel cycle.
In accordance with IWB-3142.4, components accepted for continued service based on analytical evaluation shall'be-reexamined during the next three refueling outages.
The results of the reexaminations should be-incorporated into an analytic evaluation to justify operation for each of the three subsequent operating cycles. The results of the reexamination and-the reevaluation should be submitted for NRC staff review prior to resumption of reactor operation for each of the respective operating cycles.
Sincerely, original signed by David E. LaBarge, Project Monager Project Directorate I-1 Division of. Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION
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0FFICIAL RECORD COPY
-Document Name:
EVALVATION 76861
' Mr. John C. Brons-'
James A. FitzPatrick Nuclear
- ?
' ' Power Authority of 'the State of New York -
-Power Plant CC:
Mr. Gerald C. Goldstein Ms. Donna Ross Assistant General Counsel New York State Energy Office Power Authority of the State 2 Empire State Plaza of New York 16th Floor 1633 Broadway Albany, New York 12223 New York, New York 10019 Resident Inspector's Office Regional Administrator, Region I U. S. Nuclear Regulatory Comission U. S. Nuclear Regulatory Comission Post Office Box 136
~475 Allendale Road Lycoming, New York 13093 King of Prussia, Pennsylvania 19406-j Mr. William Fernandez Mr. A. Klausman Resident Manager Senior Vice President - Appraisal James A. FitzPatrick Nuclear and Compliance Services Power Plant Power Authority of the State-Post Office Box 41 of New York Lycoming, New York 13093 1633 Broadway New York, New York 10019 L
Mr. J. A. Gray, Jr.
Mr. George Wilverding, Manager Director Nuclear Licensing - BWR Nuclear Safety Evaluation l
Power Authority of the State Power Authority of the State e
of New York of New York 123 Main Street 123 Main Street White Plains, New York 10601 White Plains, New York 10601 Supervisor Mr. R. E. Beedle li Town of Scriba.
Vice President Nuclear Support R. D..#4 Power Authority of the State-l-
Oswego, New York 13126 of New. York 123 Main Street White Plains, New York 10601--
fir. J. P. Bayne, President Power Authority of the State of New York fir S. S. Zulla 1633 Broadway Vice President Nuclear Engineering l
_123 Main Street l
Mr. Richard Patch White Plains, New York 10601 Quality Assurance Superintendent James A. FitzPatrick Nuclear Power Plant Post Office Box ~41 Mr. William Josiger, Vice President '
Lycoming, New York 13093 Operations and Maintenance Power Authority of the State of New York 123 Main Street Charlie Donaldson, Esquire White Plains, New York 10601 Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271
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