ML20198M900
| ML20198M900 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 01/09/1998 |
| From: | Johnson I COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9801200155 | |
| Download: ML20198M900 (2) | |
Text
., Commonwealth f.dkun Company M
1400 0pua Place s.
Downers Grove, !!E3154701 m
January 9,1998 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Clarification Related to Containment Vessel Structural Integrity Technical Specifications Amendment Byron Nuclear Power Station, Units 1 and 2 NRC Docket Numbers: 50-454 and 50-455 Braidwood Nuclear Power Station, Units 1 and 2 NRC Docket Numbers: 50-456 anc' 50-457
References:
- 1. J. Hosmer letter to the Nuclear Regulatory Commission dated June 17, 1997, transmitting Request to Amend Technical Specification Related to Containment Vessel Structural Integrity
- 2. G. Dick letter to I. Johnson dated September 30,1997, transmitting Request for Addition Information
- 3. 3. Hosmer letter to the Nuclear Regulatory Commission dated November 26,1997, transmitting Response to Request for Additional Information Related to Containment Vessel Structural Integrity
- 4. Telecon between M. Lesniak et al (Comed) and S. Bailey (Nuclear Regulatory Commission), dated January 8,1998 Reference I transmitted the Commonwealth Edison Company's (Comed) request to amend the Technical Specifications related to the Containment Vessel Structural Integrity Programs at Byron and Braidwood Units I and 2. Subsequent to that submittal, the Nuclear Regulatory Commission issued a Request for Additional Information (RAI) via
\\
._d Reference 2. Comed's response to the RAI was contained in Reference 3. This letter
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clarifies information discussed in Reference 4.
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USNRC January 9,1997 4
Currently, Technical Specification (TS) 3.6.1.6.b. states a Special Report will provided to the Commission within 15 days if any abnormal degradation of the structuralintegrity is found other than what is stated in ACTION a. The proposed TS 6.9.1.11 states any abnormal degradation of the containment structure detected during the tests required by the Containment Vessel Structural Integrity Program shall be reported to the Commission within 30 days. The proposed change in reporting requirement frequency is an administrative change that does not affect existing plant safety margins. The change from 15 days to 30 days for notification is consistent with Section 5.6.9 of NUREG-1431 and is consistent with similar reporting practices (10 CFR 50.73). Therefore, because the change is administrative in nature and is consistent with industry standards, the proposed change is acceptable for implementation at Byron and Braidwood Stations.
If you have any questions regarding this response, please contact this office.
Sincerely,
[
I Irene M. Johnson Licensing Operations Director cc:
Regional Administrator-Pi:1 Byron /Braidwood Project Manager-NRR Senior Resident Inspector-Byron Senior Resident Inspector-Braidwood Office of Nuclear Safety-IDNS L:nla\\byrbwd\\sgrp\\iwiciar. doc