ML20043A112
| ML20043A112 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain |
| Issue date: | 04/30/1990 |
| From: | Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-90165, NUDOCS 9005180069 | |
| Download: ML20043A112 (8) | |
Text
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$Publ e Service' Ch P.o. Box 640 Denm. Co 80201 0840 16805 WCR 19 1/2, Platteville, Colorado 80651
+
5 May 15, 1990 Fort St. Vrain Unit No. 1 P-90165 4
U. S. Nuclear Regulatory Commission l
ATTN: Document Control Desk Washington, D.C.
20555' Docket No. 50-267
SUBJECT:
APRIL, 1990 MONTHLY DEFUELING OPERATIONS REPORT
REFERENCE:
Facility Operating i
License Number DPR-34 4
Dear Sirs:
i Enclosed, please find the Monthly Defueling Operations Report for the i
month of. April, 1990, submitted per the requirements of Fort St.
Vrain Technical Specification AC 7.5.1.
If you have any questions, please contact Mr.'M. H.. Holmes at (303) 480-6960.
1 Sincerely, Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station-CHF:DLW/bhb Enclosure i
cc: Regional Administrator, Region IV i
AT7N: Mr. J. B. Baird Technical Assistant Division of Reactor Projects Mr. Robert Farrell
/gp Senior Resident Inspector, FSV
/ r.
Fort St. Vrain.-
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- This. report contains the highlights of the Fort St. Vrain,, Unit No. 1, activities operated under. the provisions of the Nuclear Regulatory Commission. Operating License No. DPR-34. This report is for the month of April, 1990.
t 1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTfNANCE
'The reactor remained shutdown the entire month of April, 1990, following Public Service Company of Colorado's decision to end.
i nuclear operation at Fort St. Vrain.
Preparations for shipping spent fuel are proceeding.
On April 10, 1990, at 0541 hours0.00626 days <br />0.15 hours <br />8.945106e-4 weeks <br />2.058505e-4 months <br />, a fire occurred in the non-essential-Bus #5 4160V/480V transformer, N-9215,.due.to an t
insulation breakdown in the secondary coils. The transformer was de-energized and the fire' extinguished within 9 minutes.
This event has been reported'to the Nuclear Regulatory Commission in Licensee Event Report 90-001.
.}
2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL"VALUE.
None i
3.0 INDICATION-0F FAILED FUEL RESULTING FROM ~ IRRADIATED FUEL c
L EXAMINATIONS 4
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None l'
4.0MpdTHLYOPERATINGDATAREPORT Attached i
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OPERATING DATA REPORT.
' DOCKET NO.
50-267
.i DATE May 15. 1990 COMPLETED BY-M. I.. Block i
TELEPHONE (303) 620-1190 OPERAT*'iG STATUS NOTES l
- 1..Untt Name:
Fort St. Vrain. I' nit No. 1
- i 2.
Reporting Period:
900401 throuch 900430
~
3.
Licensed Thermal Power (MWt):
842 4.
hameplate Rating (Gross MWe):
342 i
5.
Design Electrical Rating (Net MWe):
330 6.
Maximum Dependable Capacity (Gross MWe):
342 i:
7.
Maximum Deoencable Capacity (Net MWe):
330 f
B.
- f Changes Occur in Capacity Ratings (Items Numoer 3 Through 7) Since Last Report, Give Reasons:
Nnne i
9.
Power Level To Which Restricteo, !f Any (Net hWe):
0.0
- 10. Reasons For Restrictions, If Any:
Fnre Er. Vrnin ennend nuclone onnenrinn nn Ananae 90'.
10AQ.
This Month
. Year to Date Cumulative
- 11. Hours in Reporting Period 720
'2.R79 94.96R ~'
f
- 12. Nunoer Of Hours. Reactor Was Critical N/A N /A An197K 7 P
- 13. Reactor 8ieserve Shutdown Hours N/A N/A N/A' l
- 14. ' Hours Generetor On.Line N /A N/A 27.777.4 7
- 15. ' Unit Reserve Shutdown Hours N/A
' N /A
' N /A
- 16. Gross Thermal Energy Generated (MWH)
N/A N/A 14.450.651.2 l
- 17. Gross Electrical Energy Generated (MWH)
N /A ~
N/A diA16.R94.0 j
.38..
Net Electrical Energy Generated (MWH)
-1.751.0
-7.608.0-4.26L 396.0 L
- 19. Unit Service Factor
'N/A N/A N/A
{
- 20. Unit Availability factor N/A N/A-N/A i
- 21. Unit Capacity Factor (Using MDC Net)
N/A w/A
' N/A r
- 22. Unit Capacity Factor (Using DER Net)
N/A' N/A N/A'
. 23. Unit Forced Outage Rate v /i viA w /i
- 24. Shutdowns $cheduled'0ver Next 6 Months-(Type. Date, and Duration of Eacn):
Fort St. Vrain ceased-9 nuclone nnorneinn nn Atmu n t 29. 1989.
- 25. If Shut Down At End Of teport Period. Estimated Date Of Startup:
N/A o
- 26. Units in Test Status (Prior To Commercial Operation):
Forecast Achieved INITIAL CRITICALITY
'N/A' N/A I
INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A 1
. )
i 8
AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1
.Date May 15, 1990 Completed By M. L. Block Telephone (303) 620-1180 Month APRIL OAY AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)'
1 0.0 17 0.0 2
0.0 18-0.0
'3 0.0 19 0.0-4 0.0 20 0.0 5
0.0 21 0.0
.6 0.0 22 0.0 i
7 0.0 23 0.0 j
8 0.0 24' O0 9
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 0.0 14 0.0 30 0.0-15 0.0 31
- N/A 16 0.0
+
a Nuclear Operations at Fort St. Vrain were terminated on August 29, 1989.-
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I UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-267 UNIT MAME Fort St. Vrain Unit fio. 1 DATE May 15. 1999 COMPLETED BY M. L. Block TELEPHONE f3031 620-1180 REPORT MONTH-A PR I L.
1990 l
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I NO. I DATE ITYPEI DURATION I REASON IDOWN I
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ISYSTEMICOMPONENil TO PREVENT RECURRENCE I
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I 3-l 189-091 9001:01 1 F i 720.0 i
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N/A l N/A 1 N/A I
Nt! clear Operations were terminated on l
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REFUELING INFORMATION l
l l
lf l. Name of Facility l Fort St. Vrain Unit No. 1 l
l l
l l 2.
Scheduled date for next.
l None, no further refueling st l
l refueling shutdown.
1 FSV is expected.
l l
I I
l 3.
Scheduled date for restart l N/A l
following refueling.
l l
1 I
l '4..Will refueling or resumption ofl N/A l
operation thereafter require ~a l l
l technical specification change l.
l l
or other license amendment?
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If answer is yes, what, in l
general will these be?
l
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l
~If answer is no, has the reload l l
l fuel design and core configura-l l.
l tion been reviewed by your.
l l
l Plant Safety Review Committee l N/A l
l to determine whether any unre-l l
l viewed safety questions are l
l 1
associated with the core reloadt l
l (Reference 10 CFR Section l
l l
50.59)?
l l
1 l
l l
If no such review has taken l N/A l.
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place, when is it scheduled?
l l
l l S.
Scheduled date(s) for submit-l l
l ting proposed licensing' action l ----------------
l-l and supporting information.
l l
1
-l l
l 6.
Important licensing considera-l l.
l tions associated with refuel '- l l
1 l
ing. e.g., new or different l
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fuel design or supplier, unre-1 l
l viewed design or performance.
l l
analysis methods, significant l
l-changes in fuel design, new l
l_
l operating procedures.
l l.
I I
l l 7.
The number of fuel assemblies l l
l (a) in the core and (b) in the l a) 1023 HTGR fuel elements l
l spent fuel storage pool.
I b) 447 spent fuel elements
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REFUELING INFORMATION (CONTINUED) l i
l l
l 8.
The present licensed spent fuell l
l pool storage capacity and.the l
l l
size of any increase in l Capacity is limited in size to l
f l
licensed storage capacity that l about one-third of core
.l has been requested or.is l (approximately 500 HTGR elements),
i l
planned, in number of fuel l No change is planned.
I l-assemblies.
l t
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l
. l 9.
The projected date of the last l No further refueling'is
' l l
refueling that can be dis-l anticipated at Fort St..Vrain.
- l l
charged to the spent fuel pool l-.
l 4
l assuming the present licensed ~ l l
l_
capacity.
l l
r 4
Under Agreements AT(04-3)-633 and DE-SC07-791001370'between'Public Service Company of Colorado, General Atomic Company, and DOE, spent fuel discharged during the defueling process will be stored by DOE at the Idaho Chemical Processing Plant.
The storage capacity is.
presently sized to accommodate eight fuel segments.
It is estimated that the. eighth fuel segment will be discharged in 1991' Discussions concerning the disposition of ninth fuel segment are in progress with i
DOE., Nuclear Operations at Fort St. Vrain were terminated August 29, 1989.
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