ML20070A458
| ML20070A458 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/15/1991 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| WM-91-0004, WM-91-4, NUDOCS 9101230002 | |
| Download: ML20070A458 (2) | |
Text
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I LFCREEK W@ NUCLEAR OPERATING Bart D. Vemote vreenennt u.0 Chef Esecuhvo oseer January 15, 1991 WH 91-0004 U. S. Nucitecr Regulatory Commission ATTH:
Document Control Desk Hall Station P1-137 Washington, D. C.
20555
Reference:
- 1) Letter dated July 24. 1990 from D. V. Pickett, NRC, i
to B..D. Withers, WCNOC
- 2) Letter WH 90-0194 dated November 30, 1990 from B. D. Withers WCHOC to NRC
Subject:
Docket No. 50-482:
Steam Generator Tube Rupture Operator Action Times for Wolf Creek Generating Station Gentlemen:
The purpose of this letter is to provide confirmation of the actions Wolf Creek Nuclear Operating Corporation (WCN00) intends to perform regarding Steam Generator Tube Rupture (SGTR) operator action times for Wolf Creek i
Generating Station. Reference 1 requested WCN00 provide further information that demonstrates that the. operator response times assumed-in WCGS analysis representative of the current operator population at the plant and that are the maximum. response times fall within the bounds of the analysis.
Reference 2 provided-demonstrated operator response times from five.
-simulated SGTR scenarios.
In subsequent discussion tetween VCNOC and the NRC staff, the staff has a minimum requested that WCN00 demonstrate the simulated SGTR scenarios on of 80 percent of the current operator population.
WCNOC will perform additional design basis steam generator overfill simulator scenarios on a minimum of 80 percent of the current operator population by March 31, 1992.
The performance of these simulator scenarios is a.one-time performance to demonstrate the action times assumed in the analysis.
The results of the simulator scenarios will be provided to the NRC.
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h PA Box 411/ Burkngton, KS 66839 i Phone:(316) 364 8831
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a VM 91-0006 Page 2 It is WCNOC's understanding that the NRC will issue a Safety Evaluation Report on the WCGS Steam Generator Tube Rupture Analysis based upon the commitment to perform additional simulator scenarios.
If you have any questions concerning this matter, please contact me or Mr.
H. K. Chernoff of my staff.
Very truly yours, Bart D. Withers President and Chief Executive Officer BDW/aem cci A. T. Ilowell (NRC)
R. D. Martin (NRC)
D. V. Pickett (NRC)
M. E. Skow (HRC)