ML19351A324
| ML19351A324 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/13/1989 |
| From: | Crawford A PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19351A325 | List: |
| References | |
| P-89395, NUDOCS 8910200037 | |
| Download: ML19351A324 (3) | |
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.h Public Service' cJ."l1 P.O. Box B40 Denver CO - 80201 0840 A. Cleg;, Crawford
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October 13, 1989 Vice President Fort St. Vrain Unit No 1 P-89395 l
t U. S. Nuclear Regulatory Commission b
ATTN: Document Control Desk Washington, D. C. 20555 6
ATTN:
Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate l
Docket No. 50-267 I
SUBJECT:
Proposed Technical Specification Change To Section 6.1 - Defueling
REFERENCE:
PSC Letter, Crawford t
to Weiss, Dated September 14, 1989 (P-89350)
Dear Mr. Weiss:
This is an amendment request to the Fort St.
Vrain Technical Specifications, Section 6.1, to document design features for the defueling phase of operation.
This letter supersedes PSC Technical Specification Amendment request submitted September 14, 1989-(Reference 1).
Per a telephone conversation between Mr. Ken Heitner, r
NRC Project Manager, and Mr. M.
H.
Holmes, PSC Nuclear Licensing
- Manager, it was determined that this resrbmittal of Design Features Section 6.1 is desirable. The additional changes in this submittal are' indicated by double revision marks in the margin.
On August 29, 1989, PSC announced the end of operations for Fort St.
.Vrain.
NRC Meeting Memorandum, Heitner to Weiss, dated August 18, 1989 (G-89291) expressed a staff concern that Section 6.1 of the Technical Specifications is not being changed to describe the defueling elements. The Fort St. Vrain reactor core will be defueled using the fuel handling machine, similar to a refueling.
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defueling elements will be used to maintain the structural integrity of the core during and after defueling, to provide neutron absorption for the fuel elements remaining in the core until defueling is
- complete, and to allow coolant flow through the core during defueling.
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'P-89395'. October 13, 1989
,Three attachments are included with this proposed amendment:.
. Summary of Proposed Changes e - Proposed Changes'
. Attachment 3 - No Significant Hazards Consideration Analysis-PSC. is pursuing a high priority effort to submit these changes,x obtain NRC approval, and implement these changes.
- However, PSC is-concerned that 'an approved amendment may not be issued.in time to support current plans to start defueling by. November 27,
- 1989, Therefore, ~ PSC requests the NRC staff's~ assistance in placing these Technical Specifications in effect prior'to November 27,'1989.
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If. you have any questions or comments concerning the enclosed ninformation, please call Mr. M. H. Holmes at (303) 480-6960.
Very truly yours,
.s:
o A. Clegg Crawford s
s Vice President Nuclear Operations ACC/JMW/km Attachments cc: : Regional Administrator, Region IV ATTN:
Mr. T. F. Westerman, Chief Projects Section B l
Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain Mr. Robert M. Quillen
'I Radiation Control Division Colorado Department of Health j
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j UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 7
In the Matter
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Docket No. F. 267 i
Fort St. Vrain Unit No. 1
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AFFIDAVIT f-i A. Clegg Crawford, being first duly sworn, deposes and says: That he is Vice President, Nuclear Operations, of Public Service Company of Colorado. the Licensee herein, that he has read the foregoing Application for Amendment to Appendix A of the. Facility -Operating License and -knows the contents thereof, and that the statements and i
matters set forth therein are true and correct to the best of his knowledge, information and belief.
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Vice President Nuclear Operetions STATE OF
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