ML20212D972
| ML20212D972 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/23/1986 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 84-18, NUDOCS 8701050193 | |
| Download: ML20212D972 (2) | |
Text
Commonwealth Edloon
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One First National Plaza, Chicago, Illinois
/ Address Reply to: Post Ofhce Box 767 p
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\\d Chicago, lilinois 60690 0767 December 23, 1986 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Conunission Region III 799 Roosevelt Road Glen Ellyn, IL.
60137
Subject:
Braidwood Station Unit 2 10 CFR 50.55(e) Interim Report No. 84 Reactor Vessel Nozzle Indication NRC Docket No. 50-457 References (a): November 21, 1984 letter from D.H. Smith to J.G. Keppler (b): April 16, 1986, letter from A.D. Miosi to J.G. Keppler
Dear Mr. Keppler:
5teference (a) provided the 30-day report pursuant to 10 CFR 50.55(e) regarding the weld indication identified during the Unit 2 preservice inspection at Braidwood Station.
In the report it was stated that the l
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indication would be removed and the weld would be repaired as necessary prior t
to plant start-up. Reference (b) informed you that General Electric had performed an ASME code evaluation of the Reactor Inlet Nozzle F which demonstrated that the ASME Code Section III requirements could be maintained by performing a specified grindout and no weld repair would be necessary.
This analysis had been submitted to NRR for review and concurrence.
On November 22, 1986, an ultrasonic (UT) examination was performed to identify the location of the indication so that the grindout could be performed. The results of the UT examination showed that the indication has a size and location different than that originally found via the original Combustion Engineering in-vessel UT examination. The new data demonstrates that the indication size meets ASME Section XI IWB-3512, 1977 Edition up to and including the Summer 1978 Addenda. As a result, the need to perform an indication grindout is no longer necessary.
b 4 8701050193 861223 PDR ADOCK 05000457 5
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e J. G. Keppler December 23, 1986 As a part of the Braidwood Inservice Inspection (ISI) program the indication size will be monitored via the in-vessel tool examination method.
If any measurable increase in the size of the indication is identified by this method, a subsequent manual UT examination shall be performed from the outside surface. The examination results shall be compared to the present manual UT results to define the extent of change in the size of the indication.
This information has been submitted to NRR for their review and acceptance. Upon resolution with NRR, a final 55(e) report will be filed.
If you have any questions concerning this matter, please contact this office.
Very truly yours, h
S. C. Hunsader Nuclear Licensing Administrator la cc: Braidwood Resident Inspector 2542K