ML20246N289
| ML20246N289 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/01/1989 |
| From: | Crawford A PUBLIC SERVICE CO. OF COLORADO |
| To: | Weiss S NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| P-89342, NUDOCS 8909080079 | |
| Download: ML20246N289 (2) | |
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Public Service' 2*,";?titte.io a.
P.O. Box 840 Denver CO 80201- 0840 September 1, 1989 Fort St. Vrain A. Clegg Crawford i
Unit No. 1 Vice President P
P-89342 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 ATTN: Mr. Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate Docket No. 50-2C7
SUBJECT:
Termination of Fort St. Vrain Operations
REFERENCE:
- 1) PSC Letter, Williams to Calvo, dated December 5, 1988 (P-88422)
- 2) PSC Letter, Crawford to Weiss, dated August 16,1989(P-89287)
Dear Mr. Weiss:
'In our letter of December' 5, 1988 (see Reference 1), the Public Service Company of Colorado (PSC) announced its intention to terminate operation of the Fort St. Vrain Nuclear Generating Station on or before June 30, 1990. On August 18, 1989, PSC shut down Fort St. Vrain when a control rod drive assembly in Region 19 failed to pass a routine surveillance test. Upon examination, the control rod drive assembly was found to have one control rod stuck in its guide tube, with both control rod to cable clevis pins broken.
Subsequently, PSC discovered a number of hairline cracks in several steam generator module ring headers.
The generic implications of these two separate technical issues are significant.
Following a thorough analysis of the impact of these two issues upon restart of Fort St. Vrain, the PSC Board of Directors has decided not to restart the plant. As outlined in PSC's Defueling Safety Analysis Report (see Reference 2), Fort St. Vrain has now entered into the planned cool down period, prior to commencing defueling activities.
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P-89342 Page 2..
September 1,.1989:
PSC 'is; in the process of assessing'the two technical issues as.they relate'to defueling. Once PSC's sssessment is completed, PSC will review with the NRC the corrective actions that will be undertaken to resolve these issues as'necessary to proceed with defueling.
PSC remains concitted to high standards of performance and safety as we enter the.defueling phase of Fort St. Vrain activity.
We are looking forward to a continued strong relationship with the NRC to meet and resolve the challenges that this new area of effort will involve..
Shauld you have any questions concerning the above matters, please
' contact Mr. M. H. Holmes at (303) 480-6960.
Very truly yours, ff W
A.'Clegg Crawford Vice President Nuclear Operations ACC/MHH: ens o-cc: Regional Administrator, Region IV Attn: Mr. T. F. Westerman, Chief.
Projects Section B Mr. Robert.Farrell Senior Resident' Inspector Fort St. Vrain
- Mr. Robert M. Quillen, Director Radiation Control Division Colorado Department of Health 4
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