ML20045G224
| ML20045G224 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 07/06/1993 |
| From: | Bauer J COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| TAC-M57080, TAC-M63247, TAC-M64026, TAC-M64053, NUDOCS 9307130065 | |
| Download: ML20045G224 (3) | |
Text
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1 Ccmmonwtalth Edison O
1400 Opus Place O'
Downers Grove. Illinois 60515 July 6,1993 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Rcquiation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Completion of Confirmatory issue Regarding Operator Action Times Assumed in the Steam Generator Tube Rupture (SGTR) Analysis TAC #57080/63247 and M64026/64053 NRC Docket Nos. 50-454/455 and 50-456/457
References:
See Attachment A
Dear Dr. Murley:
J The NRC has previously accepted the Byron /Braidwood SGTR analysis as detailed in the April 23,1993 Safety Evaluation Report (Reference 9). During the course of the evaluation, the NRC requested that CECO validate the operator action times assumed in the SGTR overfill analysis. As specified in Reference 8, two randomly selected typical operating crews were evaluated and successfully demonstrated that the assumed operator action times in the design basis SGTR analysis were realistic and conservative. In addition, CECO committed to evaluate a minimum of 80% of Byron /Braldwood licensed operator simulator crews, comprised of active licensed shift personnel, to further validate the SGTR analysis assumptions. Reference 8 stated that this evaluation would be completed by June 30,1993. The subject NRC Safety Evaluation Report (Reference 9) acknowledged this commitment and requested that the results be provided to the NRC. This item was noted as a confirmatory issue.
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e Dr. T. E. Murley 2
July 6,1993 Two acceptance criteria were established for the licensed operator design basis SGTR simulator training scenario. The first acceptance criteria required the operators to completely isolate the ruptured SG within 16 minutes after the tube rupture occurreo.
The second acceptance criteria required the operators to complete the remaining mitigation actions such that the total cumulative operator action time did not exceed 37 minutes.
As of June 30,1993, all 12 Braidwood simulator crews, and all 12 Byron simulator crews have received the subject training and successfully met the specified acceptance criteria.
This action closes the April 23,1993 Safety Evaluation Report confirmatory issue. All issues regarding the Byron /Braidwood SGTR analysis have now been addressed and closed.
Please address any further comments or questions regarding this matter to this office.
Respectfully,
[ cag v k awt.)
l Joseph A. Bauer Nuclear Licensing Administrator cc:
J. B. Hickman, Byron Project Manager NRR R. R. Assa, Braidwood Project Manager - NRR H. Peterson, Senior Resident inspector - Byron S. G. Dupont, Senior Resident Inspector - Braldwood B. Clayton, Branch Chief - Region 111 I
b ATTACHMENT A REFERENCES 1.
WCAP-10698, "SGTR Analysis Methodology to Determine the Margin to Steam Generator Overfill," dated December 1984.
2.
WCAP 10698-P A, "SGTR Analysis Methodology to Determin : the Margin to Steam Generator Overfill", dated August 1987.
3.
March 30,1987 letter form Charles E. Rossi (NRC) to Alan E. Ladieu (Westinghouse Owners' Group, SGTR Subgroup), " Acceptance for Referencing of License Topical leport WCAP 10698, 'SGTR Analysis Methodology to Determine the Mar 'n to Steam Generator Overfill,'".
4.
April 25,1990 lettei form T. K. Schuster (CECO) to Dr. T. E. Murley (NRC) transmitting Revisio 1 of the plant specific Byron /Braidwood Steam Generator Tube Rupture Anal)
's, 5.
August 22,1991 T(Ic :onference between the NRC (NRR Project Managers for B/B and Human Faciors Branch) and CECO puclear Licensing and Nuclear Fuel Services).
6.
November 13,1991 Teleconference between the NRC (NRR Project Manager for Braldwood and Human Factors Branch) and CECO (Nuclear Licensing, Nuclear Fuel Services, Byron /Braidwood Plant Operating Staffs and Production Training Department).
7.
November 15,1991 letter from T. K. Schuster (CECO) to Dr. T. E. Murley (NRC) transmitting the " Response to Request for Additional Information on Byron /Braidwood SGTR Analysis".
i 8.
January 17,1992 letter from T. K. Schuster (CECO) to Dr. T. E. Murley (NRC) transmitting the " Response to Request for Additional Information on l
Byron /Braldwood SGTR Analysis".
l 9.
April 23,1992 letter from Robert M. Pulsifer (NRC) to Thomas J. Kovach (CECO) transmitting the Safety Evaluation Report accepting the Byron /Braidwood Steam Generator Tube Rupture Analysis.
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