ML20101F121
| ML20101F121 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 03/19/1996 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-95-05, GL-95-5, NUDOCS 9603250354 | |
| Download: ML20101F121 (2) | |
Text
{{#Wiki_filter:Commonwealth Edimn Company e i I4C3 Opus Place Downers Grow, IL 60515-5701 j March 19,1996 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washinghton, D.C. 20555 Attn: Document Control Desk
Subject:
Additional Information Regarding Commonwealth Edison Company's Implementation of 3.0 Volt Interim Plugging Criteria Probe Wear Criteria Byron Nuclear Power Station, Unit i Braidwood Nuclear Power Station, Unit 1 NRC Docket Nos. 50-454 and 50-456
References:
1. September 15,1995, Letter from H.D. Pontious (Comed) to the Office of Nuclear Reactor Regulation Regarding 3.0 Volt Interim Plugging Criteria Probe Wear Implementation at Byron Unit 1 and Braidwood Unit 1. 2. November 9,1995, Letter from M.D. Lynch (NRR) tc D.L. Farrar (Comed) Issuing Amendment No. 77 to Facility Operating Licenses NPF-37 and NPF-72 for use of 3.0 Volt Interim Plugging Criteria for Steam Generator Tubes 3. January 23,1996, Letter from A. Marion (NEI) to B. Sheron (NRR) Regarding Eddy Current Probe Replacement Criteria for i Use in ODSCC Alternate Repair Criteria. 4. February 9,1996, Letter from B. Sheron (NRR) to A. Marion (NEI) Regarding Eddy Current Probe Replacement Criteria for use in ODSCC Alternate Repair Criteria. 5. February 23,1996, Letter from A. Marion (NEI) to B. Sheron (NRR) Regarding Eddy Current Probe Replacement Criteria for Use in ODSCC Alternate Repair Criteria. In Reference 1, the Commonwealth Edison Company (Comed) requested use of a bobbin coil probe wear criteria that differed from the guidance of Nuclear Regulatory Commission (NRC) Generic Letter 95-05," Voltage-Based Repair Criteria for Westinghouse Steam Generators Affected by Outside Diameter Stress Corrosion Cracking." The probe wear criteria is used in the implementation of the 3.0 volt Interim, I ipg Criteria (IPC). In the NRC Safety Evaluation of the 3.0 volt IPC (Reference 2), t K:nla\\bybwdistgen\\probewrl. doc -{i 9603250354 960319 fs D A Unicom Company PDR ADOCK 05000454 P PDR
i s 1 i NRC Document Control Desk March 19,1996 the Staff found the proposed alternate probe wear criteria was acceptable for the Braidwood Unit 1 Fall 1995 and the Byron Unit 1 Fall 1995 steam generator inspections only. The Staff concluded that "...for future outages the licensee should either: a) provide alternative probe wear methodology which provides detection and sizing i capability equivalent to the probe wear criteria in GL 95-05: or b) follow the GL 95-05 guidance with respect to probe wear." In a letter dated January 23,1996 (Reference 3), the Nuclear Energy Institute (NEI) provided to the Staffjustification for an alternate probe wear criteria. The Staff accepted, i with provisions, the proposed NEI probe wear criteria by letter dated February 9,1996 (Reference 4). Reference 5 agreed to implement the alternate probe wear criteria with the Staff s provisions. Byron and Braidwood will implement the probe wear criteria as described in References 3,4 and 5. If you have any questions concerning this correspondance, please contact this ofrice. 1 i Sincerely, rC- % Denise M. Saccomando Senior Nuclear Licensing Administrator cc: D. Lynch, Senior Project Manager - NRR R. Assa, Braidwood Project Manager - NRR G. Dick, Byron Project Manager - NRR C. Phillips, Senior Resident Inspector-Braidwood H. Peterson, Senior Resident Inspector-Byron H. Miller, Regioral Administrator-RIII Office of Nuclear Safety-IDNS K:nla\\bybwd\\stgen\\probewrl. doc _.}}