ML031750650
| ML031750650 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/16/2003 |
| From: | O'Connor T Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LRN-03-0182 | |
| Download: ML031750650 (2) | |
Text
PSEG Nudear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 JUN1 6 2003 LRN-001 82 C) PSEG Nuclear LLC U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Attn: Document Control Desk 2002
SUMMARY
OF REVISED REGULATORY COMMITMENTS SALEM GENERATING STATION SALEM UNIT NOS. I AND 2 DOCKET NOS. 50-272 AND 50-311 Gentlemen:
This correspondence is being transmitted in accordance with the Nuclear Energy Instiute (NEI) process for managing Nuclear Regulatory Commission (NRC) commitments. It provides a summary of changes to NRC commitments that have been made but not reported by other means. The following information is provided regarding each of the changed commitments and their source documents.
- 1. NRC IE Bulletin 79-13, Cracking In Feedwater System Piping, and NRC Information Notice 93-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators.
The above NRC Bulletin and Information Notice identified instances of feedwater pipe cracking in a number of nuclear utilities and required that the inspection program described in the bulletin be completed for all pressurized water reactor facilities.
PSEG Nuclear (PSEG) responses to the bulletin resulted in commitments of the Salem Unit 1 and 2 Inservice Inspection (ISI) Programs (Long Term Plan) to perform required volumetric exams of Steam Generator Feedwater (SGF) piping nozzles and transition pieces at a frequency greater than required by ASME Section Xl. This was due to industry concems pertaining to thermal fatigue cracking assisted by corrosion and loading stresses.
Subsequently, Salem Units I and 2 SGF nozzle transition pieces have been redesigned with material that is less suscepfible to thermal fatigue. The design modification to the steam generator nozzle transition pieces replaced the existing SGF reducers and 95-2168 REV. 7199
I -
I JUN1 6 Document Control Desk LRN-03-0182 2
adjacent elbows with a forged single piece tuning fork fabricated from SA508, Grade 2, Class I low alloy steel material.
The above changes provide protection against erosion/corrosion thermal sleeve degradation and reduce the susceptibility of the welds to cracking while, maintaining the ability to safely operate the steam generators and feedwater system. These new transition piece forgings eliminate the need for increased examination frequencies.
Current and future examinations will be conducted in accordance with the requirements of ASME Section Xl, as required by Technical Specifications 4.0.5 and I OCFR50.55a.
Should there be any questions please contact Howard Berrick at 856-339-1862.
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Mr. H. J. Miller Regional Administrator USNRC, Region 475 Allendale Road King of Prussia, PA 19046 U. S. Nuclear Regulatory Commission ATTN: Mr. Robert Fretz, Licensing Project Manager - Salem Mail Stop 08B2 Washington DC 20555-001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625