ML20082F311
| ML20082F311 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 04/04/1995 |
| From: | Pontious H COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9504120081 | |
| Download: ML20082F311 (3) | |
Text
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- O>mnH>nwealth lifiwn Company 16C) Cpus Place lM-Ikrwners Grove, liddi%15 April 4,1995 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Completion of Containment Hydrogen Monitoring System Design Modifications Braidwood Nuclear Power Station, Units I and 2 NPF-72 and NPF-77: NRC Docket Nos. 50-456 and 50-457 Byron Nuclear Power Station, Units 1 and 2 NPF-37 and NPF-66: NRC Docket Nos. 50-454 and 50-455
References:
See Attachment Gentlemen:
In Reference 1 the Nuclear Regulatory Commission (NRC) identified a discrepancy between the as-built configuration of containment hydrogen monitoring system at Commonwealth Edison Company's (Comed's) Byron and Braidwood Stations and the system description of the containment hydrogen monitoring system contained in the Byron /Braidwood Updated Final Safety Analysis Report (UFSAR). This system description was essentially unchanged from that accepted by the NRC in the original Byron /Braidwood Safety Evaluation Report (SER) NUREG-0876 dated February 1982.
In Reference 2, as revised by Reference 3, Comed proposed an alternative design to the containment hydrogen monitoring system that ensures both containment isolation and hydrogen monitoring system operability, in the event an electrical 125VDC Engineered Safety Features (ESP) division is lost following a loss-of-coolant accident, to address this discrepancy. Reference 4 provides the NRC's acceptance the alternative design of the containment hydrogen monitoring system proposed by Comed and the NRC agreed that interim plant operation was justified until the modifications were implemented in accortlance with the schedule Comed proposed in Reference 2.
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USNRC Document Control Desk April 4,1995 The modifications were installed in accordance with the schedule proposed in Reference 2:
Modification M6-1-90-021 was installed at Byron Unit I during the Cycle 4 Refueling Outage (BIR04) conducted during the period September 6,1991, through November 7,1991, Modification M6-2-90-021 was installed at Byron Unit 2 during the Cycle 3 Refueling Outage (B2R03) conducted during the period February 28,1992, through April 30,1992, Modification M20-1-90-014 was installed at Braidwood Unit I during the Cycle 3 Refueling Outage (AIR 03) conducted during the period September 5,1992, through November 3,1992, and Modification M20-2-90-014 was installed at Braidwood Unit 2 during the Cycle 2 Refueling Outage (A2R02) conducted during the period September 13,1991, thmugh November 26,1991.
Comed considers this matter closed.
Please address any comments or questions regarding this matter to this office.
Very tmly you Harold D. Pon ious.).
Nuclear Licensing Administrator Attachment ec:
J. B. Martin, Regional Administrator - RIII R. R. Assa, Braidwood Project Manager - NRR
- 3. F. Dick Jr., Byron Project Manager - NRR S. G. DuPont, Senior Resident Inspector - Braidwood H. Peterson, Senior Resident Inspector - Byron Office of Nuclear Facility Safety - IDNS k:nla.tiyrbwd pnivt2
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ATTACHMENT.
References' w.
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Leonard N. Olshan (NRC) letter to Thomas J. Kovach (Comed), Design of ci Containment Hydrogen Monitoring System, dated July 25,1989 i
2.
S. C. Hunsader (Comed) letter to Dr. Thomas Murley (NRC), Containment Hydrogen Monitoring System, dated June 29,1990 3.
S. C. Hunsader (Comed) letter to Dr. Thomas Murley (NRC), Containment i
Hydrogen Monitoring System, dated August 24,1990 4.
Anthony H. Hsia (NRC) letter to Thomas J. Kovach (Comed), Supplemental Safety Evaluation of Containment Hydrogen Monitoring System Design at j
I Byron Station, Unit Nos.'I and 2, and Braidwood Station, Unit Nos. I and 2 (TAC No. 74547,74548,74549, and 74550), dated April 19,1991 j
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