ML20116K175
| ML20116K175 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/11/1992 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-92-130 VPNPD-92-348, NUDOCS 9211170052 | |
| Download: ML20116K175 (2) | |
Text
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. Wisconsin 1 Electnc s
POWER COMPANY 231 W M,ctugan. PO tbx 2CLM. Mdwoukeie. W 53201 (MM 221-2345 VPNPD-92-348 NRC-92-130 Novembe; 11, 1992 Document Control Desk U.S.
NUCLEAR REGJLATORY COM*!ISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:
DOCKET 50-266 REACTOR VESSEL OUTLET AND SI NOZZLE INDICATIONS POINT BEACH NUCLEAR PLANT, UNIT 1 In 1984, Wisconsin Electric Power company (WE) contracted with Southwest Research Institute (SWRI) to examine portionc of the Point Beach Nuclear Plant (PBNP) Unit 1 reactor vessel.
During this examination, flaws in the outlet nozzle-to-shell welds were identified which were sized in excess of ASME Section XI allowable limits.
These were addressed in Licensee-Event Report (LER)84-002 dated March 28, 1984.
In accordance with IWB-2420(b) of ASME Section XI, 1977 Edition, Summer 1979 Addenda, the outlet nozzle-to-shell welds required successive examination during the next three inspection periods.
In 1987, WE agein contracted with SwRI to examine the PBNP Unit 1 reactor vessel inc19 ding a successive examination of the outage nozzle-to-shell welds as a result of the 1904 examination.
During this vessel examination, flaws were identified in the SI nuzzle-to-shell welds that exceeded ASME Section XI Code allowable limits, but were found accept'sle for continued operation per evaluation in accordance with IWB-3600.
Thiu evaluation was submitted to you by our' letter dated June 2, 1987.
In accordance with IWB-2420(b) of
-ASME Section XI, 1977 Edition, Summer 1979 Addenda, the SI nozzle-to-shell welds required successive examination during the next three inspection. periods.
In'1990, WE contracted with SwRI to perform-the successive examinations-of the outlet nozzle-to-shell.and the SI nozzle-to-shell welds.
These~ examinations were performed utilizing the SWRI Program and' Remote (par) device.
'In addition, the SI nozzle-to-shell welds were examined with the SwRI Enhanced-Data Acquisition
. System-(EDAS) along with focused beam. transducers to permit more bhhh5 l
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Dpcument; control Desk hovember 11, 1992-
-Page 2 accurate sizing.
This examination method description was submitted
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to you by our letter dated October 11, 1983.
Based-on the examination results using the focused beam technology, the-flaws in the SI nozzle-to-shell welds were found to meet the ASME Section XI-acceptance criteria.- This evaluation was submitted to you by our letter dated April 30, 1990.
Sizing of indications in the outlet nozzle-to-shell welds with focused beam transducers was not performed because of subsequent equipment problems.
Conventional code techniques, which have a tendency to exaggerate the size of the indications were used instead.
Based on the results of the 1990 examinations, WE is planning to perform the final successive examination of the outlet nozzle-to-shell welds during the spring of 1993.
This examination will be performed utilizing the SwRI par device, EDAS, and focused beam sizing transducers.
The SI nozzle-to-shell welds are not subject to successive examination because the examination results in 1990-found the indications to be Code allowable.
The SI nozzle-to-shell
-welds will be examined during the Reactor Vessel 10-year-examination which is currently scheduled for the spring of 1997.
If you have any questions or require any additional information, please contact us.
Sincerely, d'
Bob Link Vice President NucleLr Power
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NRC-Regional Administrator, Region III NRC Resident Inspector T
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