ML20078P641
| ML20078P641 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 02/10/1995 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9502170164 | |
| Download: ML20078P641 (2) | |
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[ ]0 Commonwrith Edison
/ 1400 Opus Place O
Downers Grove,11tinois 60515
- February 10, 1995 OfhiceofNuclearReactorRegulation U.S. Nuclear Regulatory Commission Washington, D.C 20555 Attention:
Document Control Desk 1
Subject:
Probability of Multiple Steam Generator Tube Rupture Methodology Braidwood Station Unit 1 NRC Docket No. 50-456
References:
1)
Teleconference dated February 9,
- 1995, between Commonwealth Edison Company and the Nuclear Regulatory Commission regarding the Multiple Tube Rupture Probability
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2)
T. K. Schwartz letter to J.B. Martin dated f
January 30, 1995, transmitting Byron Stations's 90 Day Inspection Report for BlR06 3)
R. Assa letter to D.
Farrar transmitting Safety Evaluation Report on Interim Plugging Criteria dated August 18, 1995 Reference letter 3 transmitted the Nuclear Regulatory Commission's (NRC) Safety Evaluation related to Braidwood Station Unit 1 Technical Specification amendment 54.
This amendment removed the 100 day operating limit imposed on Unit 1 in Technical Specification Section 3.4.8.a. by amendment 50.
Section 3.6 of the Safety Evaluation addressed the risk based evaluation and states, "Accordingly, the staff believes that the licensee should develop the methodology for evaluating the probability of multiple steam generator tube ruptures to be prepared for the mid-cycle inspection."
As a result of this
?
requirement, Braidwood has been pursuing resolution of this issue with the Staff.
To evaluate the probability of multiple steam generator tube ruptures for the mid-cycle inspection, Braidwood Station intends to use the methodology described in WCAP-14277, "SLB Leak Rate and Tube Burst Probability Analysis Methods for ODSCC at TSP Intersections," January 1995. This document was transmitted to the NRC via Reference 2.
During the Reference teleconference, the methodology contained in this WCAP was discussed and it is our understanding that the Staff agrees that use of this methodology during the upcoming mid cycle inspection is acceptable.
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9502170164 950210
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l NRC Document Control Desk February 10, 1995 Please address any question regarding this correspondence to this office.
Sincerely, J
Denise M.
c omando Nuclear Licensing Administrator cc:
D.
Lynch, Senior Project Manager-NRR R. Assa, Braidwood Project Manager-NRR S. DuPont, Senior Resident Inspector-Braidwood J. Martin, Regional Administrator-RIII Office of Nuclear Safety-IDNS i
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