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4 | 4 c-o Fort St. Vrain H | ||
c- | Toctnical' Specifications c | ||
Enclosure (1) to AEC | q Lictnse Information Enclosure (1) to AEC Letter riated 12/21/73 i | ||
Letter riated 12/21/73 | Amendment No. | ||
Page 4 of 5 | Page 4 of 5 L | ||
D. | |||
in 10 CFR Chapter I: | This license sFall 9e d:cmed to contain and is subject to the f | ||
Sectior, 40.41 of Part 40, Sections 50.54 and 50.59 of Part | 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 | |||
(1) Maximum Power Level | 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: | ||
l l | (1) Maximum Power Level | ||
l' | [ | ||
(2) Technical Specifications | l l | ||
The Technical Specifications contained in Appendices A l | The-licensee is not authorized to operate the reactor at | ||
the facility | [ | ||
(3) Physical Protection-r i | l' any power level. | ||
(2) Technical Specifications The Technical Specifications contained in Appendices A l | |||
physical security, guard training and qualification, and | 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 | |||
Vrain Guard Training and Qualification Plan," with | .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).. | ||
St. Vrain Safeguards Contingency Plan," with revisions submitted through February 27, 1987. Changes made in | The | ||
accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. | : 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 | 9 7 | ||
a: | a: | ||
LP .;t, | LP.;t, Fort St. Vrain l | ||
l | >J Technical Specifications License Infctmation Enclosure.(1) to AEC tetter dated 12/21/73 Amendment No. | ||
Page 5 of 5 I | |||
License Infctmation Enclosure .(1) to AEC tetter dated 12/21/73 Amendment No. | lL | ||
Page 5 of 5 I | |||
?: | ?: | ||
E. ~This license is1 subject to all Federal, State, and local K | 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 | 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' | FOR THE ATOMIC ENERGY COMMISSION l' | ||
"0RIGINAL SIGNED BY:" | |||
c | 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 | 1 | ||
) | |||
J-4 L | J-4 L | ||
y_ | y_ | ||
4 . | 4. | ||
l l | l l | ||
t ATTACHMENT 3 TO P-89452 NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS l-t | t ATTACHMENT 3 TO P-89452 NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS l-t | ||
v^ | |||
ge = ;, | |||
=- | |||
k'm- | k' m- | ||
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ps | 'e c?-[ | ||
ps | |||
'.( | |||
4 | ' ko 4 | ||
-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. | |||
intention of taking .the FSV. reactor -critical again. -Existing- | -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 _ | |||
results:in an increase in margins of ' safety from an accident analysis | standpoint. | ||
No new accidents. or failure modes. are created by F | |||
This amendment proposal- involves no significant hazards because | maintaining the reactor suberitical. | ||
i. | |||
This amendment proposal-involves no significant hazards because operation of. Fort 'St. | |||
from any accident previously evaluated; or | 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 12 ) create the > possibility of a new or different kind of accident. | |||
e from any accident previously evaluated; or | |||
: 3) involve a significant reduction in a margin of safety. | : 3) involve a significant reduction in a margin of safety. | ||
L- | L- | ||
| Line 411: | Line 603: | ||
p r | p r | ||
!? | !? | ||
4 | 4 6 | ||
W f-W | |||
-P}} | |||
Latest revision as of 02:48, 31 December 2024
| 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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4 c-o Fort St. Vrain H
Toctnical' Specifications c
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
a:
LP.;t, Fort St. Vrain l
>J Technical Specifications License Infctmation Enclosure.(1) to AEC tetter dated 12/21/73 Amendment No.
Page 5 of 5 I
lL
?:
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
)
J-4 L
y_
4.
l l
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 12 ) create the > possibility of a new or different kind of accident.
e from any accident previously evaluated; or
- 3) involve a significant reduction in a margin of safety.
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