ML20078F178
| ML20078F178 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/20/1995 |
| From: | Pontious H COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20078F181 | List: |
| References | |
| NUDOCS 9502010354 | |
| Download: ML20078F178 (2) | |
Text
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Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk
Subject:
Byron Nuclear Power Station, Unit 1 Residual Heat Removal (RHR) Heat Exchanger (HX) Nozzle to Vessel Welds Inservice Inspection Results NRC Docket No. STN 50-454
References:
1.
Teleconference between Commonwealth Edison Company (Comed) and the Nuclear Regulatory Commission (NRC) held on January 16,1995 regarding Byron and Braidwood Stations, Units 1 and 2, RHR HX Nozzle to Vessel Weld Inservice Inspections 2.
Robert M. Pulsifer (NRC) letter to Thomas J. Kovach (Comed) dated November 21,1991 transmitting the Safety Evaluation Report (SER) for the Braidwood Station, Unit 2, RHR HX Nozzle to Vessel Welds Fracture Mechanics Analysis The purpose of this letter is to transmit the results of the last ASME Section XI Inservice Inspection of the Byron Unit 1 RHR HX Nozzle to Vessel Welds as requested in Reference 1. These inspections were conducted during the Byron Unit 1 Cycle 5 Refuel Outage (BIR05) which began February 5,1993, and concluded April 10,1993.
During these inspections, ultrasonic reflectors greater than those allowable by ASME Section XI Subarticle IWB-3500 were detected. These indications were subsequently evaluated using fracture mechanics analysis performed in accordance with ASME Section XI Subarticle IWB-3600 and determined to be acceptable. The fracture mechanics analysis that was used is documented in Westinghouse Letter Report MMDT-SMT-062(92), Fracture Mechanics Evaluation Byron and Braidwood Units 1 and 2 Residual Heat Exchanger Tube Side Inlet and Outlet Nozzles. The methodology outlined in this report has been previously reviewed and approved by the Staff (See Reference 2).
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NRC Document Control Desk January 20,1995 As shown in the enclosure, all indications fall within ASME Section XI acceptance standards in Subarticles IWB-3500 and IWB-3600. Those
. indications determined to be acceptable through the fracture mechanics analysis will be monitored by examinations during future Byron Unit 1 outages as required by ASME Section XI, IWC-2420.
Please address any further comments or questions regarding this matter to this office.
Sincerely, Harold D.
ontious, Jr.
Nuclear Lice'nsing Administrator Enclosure ec-J. B. Martin, Regional Administrator - Region III H. Peterson, Senior Resident Inspector - Byron G. F. Dick Jr., Byron Project Manager - NRR Office of Nuclear Facility Safety - IDNS i
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