ML19332C815: Difference between revisions
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in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, . | in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, . | ||
Sectior, 40.41 of Part 40, Sections 50.54 and 50.59 of Part : | Sectior, 40.41 of Part 40, Sections 50.54 and 50.59 of Part : | ||
, 50, and the appropriate sections of Parts 70 and 73; is i | , 50, and the appropriate sections of Parts 70 and 73; is i subject-to all applicable provisions of the Act and to the rules,- regulations, and orders of the Commission now or hereafter in effect;- and is subject to the additional conditions specified'or' incorporated below: | ||
subject-to all applicable provisions of the Act and to the rules,- regulations, and orders of the Commission now or hereafter in effect;- and is subject to the additional conditions specified'or' incorporated below: | |||
(1) Maximum Power Level [ | (1) Maximum Power Level [ | ||
l l The-licensee is not authorized to operate the reactor at [ | l l The-licensee is not authorized to operate the reactor at [ | ||
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p r | p r | ||
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Revision as of 11:47, 18 February 2020
| ML19332C815 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain |
| Issue date: | 11/21/1989 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML19332C814 | List: |
| References | |
| NUDOCS 8911290036 | |
| Download: ML19332C815 (5) | |
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c- o Fort St. Vrain H c . Toctnical' Specifications q Lictnse Information ;
Enclosure (1) to AEC ;
Letter riated 12/21/73 i Amendment No.
Page 4 of 5 -
L D. This license sFall 9e d:cmed to contain and is subject to the f conditions sper.ified in the following Commission regulations ,
in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, .
Sectior, 40.41 of Part 40, Sections 50.54 and 50.59 of Part :
, 50, and the appropriate sections of Parts 70 and 73; is i subject-to all applicable provisions of the Act and to the rules,- regulations, and orders of the Commission now or hereafter in effect;- and is subject to the additional conditions specified'or' incorporated below:
(1) Maximum Power Level [
l l The-licensee is not authorized to operate the reactor at [
l' any power level. ,
(2) Technical Specifications '
The Technical Specifications contained in Appendices A l and B, as revised through Amendment No. , are hereby incorporated in the license. -The licensee shall operate -
the facility in accordance with. the Technical Specifications, _
(3) Physical Protection-r i
-The licensee shall fully implement and maintain in effect..all provisions of the Commission-approved ,
physical security, guard training and qualification, and ,
i safeguards contingency plans including amendments -made '
pursuant .to. provisions of the Miscellaneous Amendments and Search Requirements revisions .to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).. The plans, which contain ,
&. # Safeguards Information protected under 10 CFR 73.21, are entitled: -" Fort St. Vrain . Security Plan," with l revisions submitted through July 15, 1988; " Fort St. ,
Vrain Guard Training and Qualification Plan," with l revisions submitted through February 27, 1987; and " Fort >
St. Vrain Safeguards Contingency Plan," with revisions submitted through February 27, 1987. Changes made in -
accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. -
9 7
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LP .;t, . Fort St. Vrain .
l Technical Specifications
>J . ----
License Infctmation Enclosure .(1) to AEC tetter dated 12/21/73 Amendment No.
Page 5 of 5 I lL
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E. ~This license is1 subject to all Federal, State, and local K . standards imposed pursuant to the requirements of the Federal Water Pollution Control Act of 1972.
b
'3.- This .licensei is -effective as of the date of issuance-and shall expire at midnight, September 17, 2008.
FOR THE ATOMIC ENERGY COMMISSION l'
"0RIGINAL SIGNED BY:"
c A. Giambosso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:
- Appendices A and B - Technical Specifications-Datefof Issuance: December 21, 1973 N
1
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t ATTACHMENT 3 TO P-89452 NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS l-t
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-f51 NO'SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS'
,4 This proposed amendment to the Facility Operating License prohibits
> operation of the FSV: reactor at any power. level. PSC has no ,
intention of taking .the FSV. reactor -critical again. -Existing-
' analyses address potential accident scenarios from a reactor shutdown condition through-power operation.' Maintaining the core suberitical.
results:in an increase in margins of ' safety from an accident analysis e_ standpoint. No new accidents. or failure modes. are created by F maintaining the reactor suberitical.
- i. ,
This amendment proposal- involves no significant hazards because
- operation of. Fort 'St. Vrain in accordance with this amendment-proposal would not:
' l) involve.a significant-increase in the probability or consequences of an1 accident previously evaluated; or e 12 ) create the > possibility of a new or different kind of accident.
from any accident previously evaluated; or
- 3) involve a significant reduction in a margin of safety.
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