ML20094L265
| ML20094L265 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/19/1992 |
| From: | Crawford A PUBLIC SERVICE CO. OF COLORADO |
| To: | Weiss S NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20094L267 | List: |
| References | |
| P-92115, NUDOCS 9203250033 | |
| Download: ML20094L265 (3) | |
Text
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h Public Service' l 2 * %.-
16805 WCR 19 1/2, Plattovillo, Colorado 80651 March 19, 1992 Fort St. Vrain l
Unit No. 1 P-92115 U.
S. Nuclear Regulatory Commission ATTH: Document Control Dosk Washington, D. C. 20555 ATTH: Dr. Seymour 11. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorato Docket No. 50-267
SUBJECT:
DECOMMISGIONING TECl!NICAL SPECIFICATIONS
REFERENCE:
PSC Lotter, Crawford to Wolsa, dated August 30, 1991 (P-91278)
Dear Dr. Weiss:
This_. letter submits a proposed amendment to the Fort St.
Vrain (FSV) Facility Licenso and Technical Specifications, to provido-controls and limits appropriato for FSV docommissioning.
Thi'A submittal reflects soveral administrative changes tc the proposed Facility License and Decommissioning Technical Specif acations (DTS) that Public Service Company of Colorado (PSC) previously submitted to the NRC via the referenced lotter.
The administrativo-changos reflected in the attached submittal were identified during PSC's decommissioning planning efforts, and includo.the following:
Revisions-to management -position-titles to reflect a revised organizational-structure, Revision of the high radiation area definition e
to allow use of either the existing 10 CFR 20 critoria-or the revised 10 CPR 20 critoria, 1
d l
9203250033 920319 l
PDR-ADOCK 05000267 P
PDR 4
P-92115 March 19, 1992 Pago 2 Extension of the timo allowed to submit the Somiannual Radioactivo Ef fluent Roloano report t
from 60 to 90 days, and Revision to the Facility Licenso requiroments to explicitly permit rocoipt of radioactivo material prodo-ad during previous plant operations or d iln da';oR?issioning activj tion.
s The submittal of thoso pro yg.
sege,s m includod in the s
following attachmonts:
Attachmont 1 - Summary of P.vpound Changes - Proposed Facility Licenso and Decomminsioning Technical Specifications - Justification of Changos from Proviously Submitted Pacility Licenso and Decommissioning Technical Specifications - No Significant Hheards consideration Analysis Attachmont 2 includes the proposed Facility License and Decommissioning Technical Specifications in their entirety.
This attachment' is intended to totally supersado and replace PSC's previously referenced submittal.
To assist in your review, changes from the referenced submittal havo boon marked in the left-hand margin and are explained in.
The Ho Significant Hazards Consideration Analysis has boon revised to address the steam gonorator primary modulo drop accident. This accident was identified during the responso to NRC questions on the Proposed Ducommissioning Plan. The l
identification and analysis of this accident did not result in-any changes to the DTS limiting conditions or surveillanco requirements becauso - tho-accident analysis does not take credit for reactor building confinomont or filtration by the ventilation exhaust system.
i P-92115 March 19, 1992 Page 3 PSC roquests that the proposed Facility Licenne and Decomminoloning Technical Specifications be approved for implementation at the beginning of decommionjoning activition, af ter all nuclear fuel han boon retnoved f rom the Roactor Building and af ter the NRC has approved the Proposed Decommissioning Plan.
The attached DTS are intended to replaco the current FSV Technical Specifications and Environmental Protection Plan (!1on-Radiological), Appendicos A and D, ronpectively, to the PSV Facility Operating Licenso.
If you have any questions regarding thoco propoced changen, please contact Mr. M.11. llolmes at (303) 620-1701.
Very truly yourn, f
G
~ f A.
Clogg Crawfor Vice Prooident Electric Production l
ACC/SWC/Img l
Attachments cc Regiotial Administrator, Region IV Mr. J.
B. Daird l
Senior Resident Inspector Fort St. Vrain L
Mr. Robert M. Quillin,. Director Radiation Control Divialon i
Colorado Department of licalth
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