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t | ,W PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION l | ||
MONTHLY OPERATIONS REPORT l | l h | ||
February, 1989 | t I | ||
4 1 | |||
MONTHLY OPERATIONS REPORT l | |||
NO. 181 I | |||
l February, 1989 l | |||
l l | l l | ||
j | l j | ||
l l | l l | ||
'A 2 4 | |||
/ | |||
\\ | |||
( | |||
l 8903220109 G90228 | |||
) | |||
i PDR ADOCK 05000267 PDC H | |||
1 l | |||
l | |||
g - - - -, | |||
3 | |||
--.)- | |||
R R | R R | ||
_1.- | _1.- | ||
This : report contains the~ highlights of the Fcrt St.1Vrain, Unit | This : report contains the~ highlights of the Fcrt St.1Vrain, Unit l | ||
No.1, activities operated- under the provisions of the Nuclear | No.1, activities operated-under the provisions of the Nuclear j | ||
Regulatory Commission! Operating. License No. DPR-34. 'The report.for' | ',~ | ||
Regulatory Commission! Operating. License No. DPR-34. 'The report.for' j | |||
the monthly partial scram / maximum temperature reports for control. rod drive and orificing assemblies is.not included this month because the-reactor was critical for a. short duration for ' operator ' training startups only. | |||
This ' report' is for the month of February,: 1989, MA' OR SAFETY 1.0 NARRATIVE - | |||
==SUMMARY== | ==SUMMARY== | ||
- 0F OPERATING EXPERIENCE' AND | - 0F OPERATING EXPERIENCE' AND J | ||
Recovery .of the reserve shutdown material is expected to be | RELATED MAINTENANCE The reactor remained shutdown the entire month of _ February,1989, i | ||
for the continuation of removal of in-core reserve shutdown j | |||
material.and primary. coolant cleanup. | |||
completed by the end of March.1 At current moisture levels, | 1 1 | ||
progress. A completion date of. March, 1989, is anticipated. | Recovery.of the reserve shutdown material is expected to be completed in early March of 1989. | ||
2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS-0F_J0% OF-THE ALLOWABLE ANNUAL VALUE None | J | ||
1 | .1 Moisture is currently is excess of levels permitted for; reactor. | ||
1 startup. "An evacuation of the vessel for'. moisture removal | |||
- i purposes will begin~ approximately March lith. and should:be completed by the end of March.1 At current moisture levels, 1 | |||
reactor startup is anticipated by April 1, 1989.' | |||
i The proposed cylinder' head refurbishment, repairs and inspections program for the Emergency; Diesel' Generators are. currently ' n-i progress. A completion date of. March, 1989, is anticipated. | |||
1 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS-0F_J0% OF-THE ALLOWABLE ANNUAL VALUE None 1 | |||
? | ? | ||
o W | o W | ||
.) | |||
c; | - c; | ||
3.0 INDICATION | . 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None q | ||
4.0 MONTHLY OPER TING DATA REPORT Attached 1 | |||
5.0 CONTROL R00 DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT l | 5.0 CONTROL R00 DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT l | ||
Not required this month. | Not required this month. | ||
1 i | 1 i | ||
I l | I l | ||
l | l 1 | ||
f 1 | |||
l | i l | ||
l l | l l | ||
.y s | |||
6 | |||
*) | |||
. OPERATING DATA REPORT DOCKET NO. | |||
C.0MPLETED BY | 50-267 DATE March 15, 1989 C.0MPLETED BY M.L. Block TELEPHONE (303) 620-1180 OPERATING STATUS NOTES l | ||
TELEPHONE | 1. | ||
OPERATING STATUS NOTES l | Unit Name: | ||
Fort St. Vrain, Unit No. 1 2. | |||
Reporting Period: | |||
890201 t.h rou ch 890228 l | |||
3. | |||
Licensed Thermal Power (MWt): | |||
330 | 842 4. | ||
Nameplate Rating (Gross MWe): | |||
None | 342 l | ||
S. | |||
Design Electrical Rating (Net MWe): | |||
: 11. Hours In Reporting Period | 330 l | ||
: 12. Number Of Hours Reactor Was Critical | 6. | ||
: 13. Reactor Reserve Shutdown Hours | Maximum Dependable Capacity (Gross MWe): | ||
: 14. Hours Generator On-Line | 342 7. | ||
: 15. Unit Reserve Shutdown Hours | Maximum Dependable Capacity (Net MWe): | ||
O.0 | 330 8. | ||
: 16. Gross Thermal Energy Generated (MWH) | If Changes Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: | ||
: 17. Gross Electrical Energy Generated (MWH) | None 9. | ||
: 18. Nst Electrical Energy Generated (MWH) | Power Level To Which Restricted, If Any (Net MWe): | ||
: 19. Unit Service Factor | 270.6 f | ||
: 20. Unit Availability Factor | : 10. Reasons For Restrictions, If Any: | ||
: 21. Unit Capacity Factp (Using MDC Net) | Reanalysis of safe shutdown cooling following' a 90 minute interruption of forced cooling. | ||
: 22. Unit Caoacity Factor (Using DER Net) | l This Month Year To Date Cumulative l | ||
: 23. Unit Forced Outage Rate | : 11. Hours In Reporting Period 672.0 1,416.0 84,745.0 | ||
: 12. Number Of Hours Reactor Was Critical 0.0 57.6-37,302.4 | |||
: 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 | |||
: 14. Hours Generator On-Line 0.0 0.0 25,072.8 | |||
: 15. Unit Reserve Shutdown Hours 0.0 0.0 O.0 | |||
: 16. Gross Thermal Energy Generated (MWH) 0.0 187.2 | |||
-12,887,897.3 | |||
: 17. Gross Electrical Energy Generated (MWH) 0.0 0.0 4,260,404.0 | |||
: 18. Nst Electrical Energy Generated (MWH) | |||
;2.448.0 | |||
-6,277.0 3,743,717.0 | |||
: 19. Unit Service Factor 0.0 0.0 29.5 | |||
: 20. Unit Availability Factor 0.0 0.0 29.5 | |||
: 21. Unit Capacity Factp (Using MDC Net) 0.0 0.0 13.4 | |||
: 22. Unit Caoacity Factor (Using DER Net) 0.0 0.0 13.4 | |||
: 23. Unit Forced Outage Rate 100.0 100.0 64.8 | |||
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): | : 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): | ||
Nonc | |||
: 25. If Shut Down At End Of Report Period, Estimated Date Of Startup: | : 25. If Shut Down At End Of Report Period, Estimated Date Of Startup: | ||
: 26. Units In Test Status (Frior To Comercial Operation): | April 1, 1989 I | ||
COMMERCIAL OPERATION | Forecast Achieved | ||
: 26. Units In Test Status (Frior To Comercial Operation): | |||
INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l | |||
i | i | ||
~> | |||
i | i AVERAGE DA8LY UNIT POWER' LEVEL 3 E | ||
l a | |||
Docket' No'' 5'0-267 - | |||
Docket' No' | Unit Fort:St.- Vrain< Unit No.<1-a Date March 15,1989 | ||
' Completed By M. L. Block Telephone (303) 620-1180 Month FEBRUARY-2 AY AVERAGE DAILY POWER LEVEL DAY -AVERAGE DAILY POWER LEVEL D | |||
l (MWe-Net) | |||
(MWe-Net) 2 | |||
.u 1 | |||
0.0 17-0.0 2 | |||
10 | 0.0 18 0.0-2 3 | ||
13 | 0.0 19 0.0 4 | ||
* Generator on line but no net generation. | 0.0 | ||
.20. | |||
0.0 | |||
.5 0.0 21 | |||
-0.0 6 | |||
0.0 22 0.0-l 7 | |||
0. 0, 23. | |||
0.0' 8 | |||
0.0 24 0.0 9 - | |||
i 0.0 25 0.0 t | |||
10 0.0 | |||
~ 26 | |||
'0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 N/A 14 0.0 30-N/A 15 0.0 31 | |||
'N/A 16 0.0 | |||
* Generator on line but no net generation. | |||
j I | j I | ||
l I | l I | ||
_.____.._________m__._. | _.____.._________m__._. | ||
W.' | W.' | ||
O; | |||
~ | |||
REFUELING' INFORMATION l- | ..y Q" | ||
l l 3. Scheduled date'for restart. | REFUELING' INFORMATION l-1. | ||
l-l | l l | ||
I | l 1. | ||
l | Name' of Facility | ||
l | 'l Fort St. ' Vrain Unit' No.1 4 | ||
l l. | |||
l l | .1 l 2. | ||
l 5. Scheduled date(s) for submit- 1. | Scheduled date for next l June.7, 1989 l' | ||
I | l refueling shutdown. | ||
l | I | ||
l 6. Important licensing considera- l | 'l l | ||
L l-l l 3. | |||
l | Scheduled date'for restart. | ||
L | j' July 30, 1989-l l | ||
following refueling. | |||
l l | |||
l l | |||
1 I 4. | |||
Will refueling or resumption ofl No | |||
.1 l | |||
. operation thereafter require a l | |||
-l l | |||
technical specification change.I l' | |||
l-l or other license amendment?- | |||
1 l | |||
l | |||
} | |||
l l | |||
If answer is yes, what, in 1 ---------------- | |||
1 J | |||
l general, will these be? | |||
l- | |||
'l' l | |||
I I: | |||
l If answer is no, has the reload l l' | |||
I fuel design and core configura-l | |||
'l' l | |||
tion been reviewed by your l | |||
'l-l Plant Safety Review Committee.1 No l | |||
l to determine whether any unre--l 1 | |||
.l | |||
. viewed safety questions are. | |||
I 1 | |||
l | |||
. associated with the core reloadj l | |||
l (Reference 10 CFR Section l | |||
.i l | |||
50.59)?,_ | |||
l l-1 I | |||
l 1 | |||
l If no such review has taken i 1989 l | |||
l place, when is it scheduled? | |||
l l | |||
l. | |||
l 5. | |||
Scheduled date(s) for submit-1. | |||
l. | |||
I ting proposed licensing action l ---------------- | |||
l l | |||
and supporting information. | |||
I | |||
[ | |||
l l | |||
l l | |||
l 6. | |||
Important licensing considera-l | |||
.l l | |||
tions associated with refuel-l l | |||
l ing,.e.g., new or different | |||
-l l | |||
l fuel design or supplier, unre-l ---------------- | |||
l l | |||
viewed design or performance l | |||
l l | |||
analysis methods,.significant' l l | |||
l changes in fuel design, new l | |||
l l | |||
operating procedures. | |||
l l | |||
l 1 | |||
l l 7. | |||
The number of fuel assemblies l l | |||
l (a) in the core and (b) in the l a) 148?. HTGR fuel elements l | |||
l spent fuel storage pool. | |||
I b) 0 spent fuel elements l | |||
l L | |||
.v. ' | |||
:p REFUELING INFORMATION (CONTINUED)' | :p REFUELING INFORMATION (CONTINUED)' | ||
l | l | ||
,l' l | |||
l | l' 8. | ||
The present. licensed spent fuell. | |||
I l | |||
' pool storage capacity and the l l. | |||
l | l | ||
' size of any increase in l Capacity is-limited'in size to-l l | |||
licensed storage capacity that I about one-third of core l-j j' | |||
planned, in number of fuel l No. change is planned. | |||
l. | |||
j l | |||
has been requested or i's' l.(approximately 500 HTGR elements).l. | |||
l_ | |||
assemblies. | |||
l l. | |||
l l | |||
. The projected date of the last l 1996 under Agreements'AT(04-3)-6331 I | |||
l. | |||
~ | |||
I. 9.- | |||
l refueling that can be dis-l and DE-SC07-79ID01370 between l | |||
I charged to the spent fuel pool l Public Service Company of l | |||
l assuming the present licensed -l Colorado, and General Atomic l. | |||
a l | |||
capacity. | |||
l Company, and DOE.* | |||
l' 1 | |||
The 1996 estimated date is based on the understanding that' spent fuel' discharged during the term of the Agreements will.'be stored by DOE'at | |||
~ | |||
the Idaho Chemical Processing Plant. | |||
The storage capacity has evidently been sized to accommodate ~ eightL fuel segments.. It' is i | |||
estimated that the eighth fuel segment will be discharged in 1996. | |||
l 9 | |||
l l | |||
e | e 6 | ||
6 | ~ | ||
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r 3ce n | |||
N A A | 9 0 | ||
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il1IIII | 8 8 | ||
d au a | |||
9 1 | |||
n d | |||
Sts r | |||
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n TAI V | |||
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5 l | |||
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1 1 | |||
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p 7 | |||
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T m | |||
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5 F | |||
M M. | |||
2 EC l | |||
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o a | |||
VN p | |||
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E E Y E TR R | |||
g O M T | |||
B N CR n. | |||
N A A O | |||
EU tp ip N D D H RC l u nu T | |||
E P | |||
RE on in E T T | |||
E OR Ba aa E L C | |||
e re K | |||
I C N L E T | |||
rl Tl O U P | |||
T DN oC C | |||
D M | |||
NE t | |||
r O | |||
AV at ot C | |||
E l n tn ER ua aa SP cl rl U | |||
ro eo AO o po i | |||
S CT CC OC NO il l | |||
l il1IIII lIl l | |||
ll1 l | ll1 l | ||
I T | I T | ||
T | T N | ||
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l | 8 N | ||
P D | |||
O | 9 O | ||
T | M Z | ||
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T | PE C | ||
Z R | |||
MD Z | |||
DI | Y OO Z | ||
HTNC | R R | ||
TUWA | CC E | ||
ElOE i MSDR IllIiIllIlIiIII1iIlIIIII1 | A 1IllI hlIIlI l | ||
N | .II l | ||
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iiillilIIIIl | E P | ||
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11lIl1ll1ilIiIlI | M L | ||
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1 1 | |||
HTNC TUWA ElOE i | |||
MSDR IllIiIllIlIiIII1iIlIIIII1 1II1lllIIIlI1 N | |||
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I1 llllI!: | |||
l1ll N | |||
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8 t | |||
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1 5 | |||
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9 9 | |||
8 8 | |||
1 il! | |||
1 I!.I | |||
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8 9 | |||
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.li l | |||
.c Public Service' Ch March 15, 1989 Fort St. Vrain I | |||
U. S. Nuclear Regulatory Commission | Unit No. 1 P-89090 1 | ||
U. S. Nuclear Regulatory Commission i | |||
ATTH: Document Control Desk Washington, D.C. | |||
20555 j | |||
Docket No. 50-267 | |||
==SUBJECT:== | ==SUBJECT:== | ||
| Line 231: | Line 484: | ||
==REFERENCE:== | ==REFERENCE:== | ||
Facility Operating License Number DPR-34 | Facility Operating License Number DPR-34 f | ||
==Dear Sir:== | ==Dear Sir:== | ||
Enclosed, please find the Monthly Operations Report for the mor.ch of February 1989, submitted per the requirements of Fort St. | |||
Technical Specification AC 7.5.1. | Vrain Technical Specification AC 7.5.1. | ||
i If you have any questions, please contact Mr. M. H. Holmes at (303) | i If you have any questions, please contact Mr. M. H. Holmes at (303) | ||
480-6960. | I I | ||
Sincerely, | 480-6960. | ||
l | { | ||
Sincerely, b | |||
cc: | l C. H. Fuller Manager, Nuclear Production CHF/cas Enclosure l | ||
ATTN: | 1 cc: | ||
l}} | Regional Administrator, Region IV ATTN: | ||
Mr. T. F. Westerman, Chief Projects Section B l | |||
Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain fff I \\ | |||
l | |||
~}} | |||
Latest revision as of 02:50, 3 December 2024
| ML20236C373 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain |
| Issue date: | 02/28/1989 |
| From: | Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-89090, NUDOCS 8903220109 | |
| Download: ML20236C373 (9) | |
Text
-.
4
.i
~
E
,W PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION l
l h
t I
4 1
MONTHLY OPERATIONS REPORT l
NO. 181 I
l February, 1989 l
l l
l j
l l
'A 2 4
/
\\
(
l 8903220109 G90228
)
1 l
l
g - - - -,
3
--.)-
R R
_1.-
This : report contains the~ highlights of the Fcrt St.1Vrain, Unit l
No.1, activities operated-under the provisions of the Nuclear j
',~
Regulatory Commission! Operating. License No. DPR-34. 'The report.for' j
the monthly partial scram / maximum temperature reports for control. rod drive and orificing assemblies is.not included this month because the-reactor was critical for a. short duration for ' operator ' training startups only.
This ' report' is for the month of February,: 1989, MA' OR SAFETY 1.0 NARRATIVE -
SUMMARY
- 0F OPERATING EXPERIENCE' AND J
RELATED MAINTENANCE The reactor remained shutdown the entire month of _ February,1989, i
for the continuation of removal of in-core reserve shutdown j
material.and primary. coolant cleanup.
1 1
Recovery.of the reserve shutdown material is expected to be completed in early March of 1989.
J
.1 Moisture is currently is excess of levels permitted for; reactor.
1 startup. "An evacuation of the vessel for'. moisture removal
- i purposes will begin~ approximately March lith. and should:be completed by the end of March.1 At current moisture levels, 1
reactor startup is anticipated by April 1, 1989.'
i The proposed cylinder' head refurbishment, repairs and inspections program for the Emergency; Diesel' Generators are. currently ' n-i progress. A completion date of. March, 1989, is anticipated.
1 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS-0F_J0% OF-THE ALLOWABLE ANNUAL VALUE None 1
?
o W
.)
- c;
. 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None q
4.0 MONTHLY OPER TING DATA REPORT Attached 1
5.0 CONTROL R00 DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT l
Not required this month.
1 i
I l
l 1
f 1
i l
l l
.y s
6
- )
. OPERATING DATA REPORT DOCKET NO.
50-267 DATE March 15, 1989 C.0MPLETED BY M.L. Block TELEPHONE (303) 620-1180 OPERATING STATUS NOTES l
1.
Unit Name:
Fort St. Vrain, Unit No. 1 2.
Reporting Period:
890201 t.h rou ch 890228 l
3.
Licensed Thermal Power (MWt):
842 4.
Nameplate Rating (Gross MWe):
342 l
S.
Design Electrical Rating (Net MWe):
330 l
6.
Maximum Dependable Capacity (Gross MWe):
342 7.
Maximum Dependable Capacity (Net MWe):
330 8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
None 9.
Power Level To Which Restricted, If Any (Net MWe):
270.6 f
- 10. Reasons For Restrictions, If Any:
Reanalysis of safe shutdown cooling following' a 90 minute interruption of forced cooling.
l This Month Year To Date Cumulative l
- 11. Hours In Reporting Period 672.0 1,416.0 84,745.0
- 12. Number Of Hours Reactor Was Critical 0.0 57.6-37,302.4
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 0.0 0.0 25,072.8
- 15. Unit Reserve Shutdown Hours 0.0 0.0 O.0
- 16. Gross Thermal Energy Generated (MWH) 0.0 187.2
-12,887,897.3
- 17. Gross Electrical Energy Generated (MWH) 0.0 0.0 4,260,404.0
- 18. Nst Electrical Energy Generated (MWH)
- 2.448.0
-6,277.0 3,743,717.0
- 19. Unit Service Factor 0.0 0.0 29.5
- 20. Unit Availability Factor 0.0 0.0 29.5
- 21. Unit Capacity Factp (Using MDC Net) 0.0 0.0 13.4
- 22. Unit Caoacity Factor (Using DER Net) 0.0 0.0 13.4
- 23. Unit Forced Outage Rate 100.0 100.0 64.8
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Nonc
- 25. If Shut Down At End Of Report Period, Estimated Date Of Startup:
April 1, 1989 I
Forecast Achieved
- 26. Units In Test Status (Frior To Comercial Operation):
INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l
i
~>
i AVERAGE DA8LY UNIT POWER' LEVEL 3 E
l a
Docket' No 5'0-267 -
Unit Fort:St.- Vrain< Unit No.<1-a Date March 15,1989
' Completed By M. L. Block Telephone (303) 620-1180 Month FEBRUARY-2 AY AVERAGE DAILY POWER LEVEL DAY -AVERAGE DAILY POWER LEVEL D
l (MWe-Net)
(MWe-Net) 2
.u 1
0.0 17-0.0 2
0.0 18 0.0-2 3
0.0 19 0.0 4
0.0
.20.
0.0
.5 0.0 21
-0.0 6
0.0 22 0.0-l 7
0. 0, 23.
0.0' 8
0.0 24 0.0 9 -
i 0.0 25 0.0 t
10 0.0
~ 26
'0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 N/A 14 0.0 30-N/A 15 0.0 31
'N/A 16 0.0
- Generator on line but no net generation.
j I
l I
_.____.._________m__._.
W.'
O;
~
..y Q"
REFUELING' INFORMATION l-1.
l l
l 1.
Name' of Facility
'l Fort St. ' Vrain Unit' No.1 4
l l.
.1 l 2.
Scheduled date for next l June.7, 1989 l'
l refueling shutdown.
I
'l l
L l-l l 3.
Scheduled date'for restart.
j' July 30, 1989-l l
following refueling.
l l
l l
1 I 4.
Will refueling or resumption ofl No
.1 l
. operation thereafter require a l
-l l
technical specification change.I l'
l-l or other license amendment?-
1 l
l
}
l l
If answer is yes, what, in 1 ----------------
1 J
l general, will these be?
l-
'l' l
I I:
l If answer is no, has the reload l l'
I fuel design and core configura-l
'l' l
tion been reviewed by your l
'l-l Plant Safety Review Committee.1 No l
l to determine whether any unre--l 1
.l
. viewed safety questions are.
I 1
l
. associated with the core reloadj l
l (Reference 10 CFR Section l
.i l
50.59)?,_
l l-1 I
l 1
l If no such review has taken i 1989 l
l place, when is it scheduled?
l l
l.
l 5.
Scheduled date(s) for submit-1.
l.
I ting proposed licensing action l ----------------
l l
and supporting information.
I
[
l l
l l
l 6.
Important licensing considera-l
.l l
tions associated with refuel-l l
l ing,.e.g., new or different
-l l
l fuel design or supplier, unre-l ----------------
l l
viewed design or performance l
l l
analysis methods,.significant' l l
l changes in fuel design, new l
l l
operating procedures.
l l
l 1
l l 7.
The number of fuel assemblies l l
l (a) in the core and (b) in the l a) 148?. HTGR fuel elements l
l spent fuel storage pool.
I b) 0 spent fuel elements l
l L
.v. '
- p REFUELING INFORMATION (CONTINUED)'
l
,l' l
l' 8.
The present. licensed spent fuell.
I l
' pool storage capacity and the l l.
l
' size of any increase in l Capacity is-limited'in size to-l l
licensed storage capacity that I about one-third of core l-j j'
planned, in number of fuel l No. change is planned.
l.
j l
has been requested or i's' l.(approximately 500 HTGR elements).l.
l_
assemblies.
l l.
l l
. The projected date of the last l 1996 under Agreements'AT(04-3)-6331 I
l.
~
I. 9.-
l refueling that can be dis-l and DE-SC07-79ID01370 between l
I charged to the spent fuel pool l Public Service Company of l
l assuming the present licensed -l Colorado, and General Atomic l.
a l
capacity.
l Company, and DOE.*
l' 1
The 1996 estimated date is based on the understanding that' spent fuel' discharged during the term of the Agreements will.'be stored by DOE'at
~
the Idaho Chemical Processing Plant.
The storage capacity has evidently been sized to accommodate ~ eightL fuel segments.. It' is i
estimated that the eighth fuel segment will be discharged in 1996.
l 9
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.c Public Service' Ch March 15, 1989 Fort St. Vrain I
Unit No. 1 P-89090 1
U. S. Nuclear Regulatory Commission i
ATTH: Document Control Desk Washington, D.C.
20555 j
Docket No. 50-267
SUBJECT:
FEBRUARY 1989 MONTHLY OPERATIONS REPORT
REFERENCE:
Facility Operating License Number DPR-34 f
Dear Sir:
Enclosed, please find the Monthly Operations Report for the mor.ch of February 1989, submitted per the requirements of Fort St.
Vrain Technical Specification AC 7.5.1.
i If you have any questions, please contact Mr. M. H. Holmes at (303)
I I
480-6960.
{
Sincerely, b
l C. H. Fuller Manager, Nuclear Production CHF/cas Enclosure l
1 cc:
Regional Administrator, Region IV ATTN:
Mr. T. F. Westerman, Chief Projects Section B l
Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain fff I \\
l
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