ML20236C373
| 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) | |
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,W PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION l
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MONTHLY OPERATIONS REPORT l
NO. 181 I
l February, 1989 l
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l 8903220109 G90228
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This : report contains the~ highlights of the Fcrt St.1Vrain, Unit l
No.1, activities operated-under the provisions of the Nuclear j
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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.
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Recovery.of the reserve shutdown material is expected to be completed in early March of 1989.
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.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
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. 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.
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. 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
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i AVERAGE DA8LY UNIT POWER' LEVEL 3 E
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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.
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REFUELING' INFORMATION l-1.
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Name' of Facility
'l Fort St. ' Vrain Unit' No.1 4
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Scheduled date for next l June.7, 1989 l'
l refueling shutdown.
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Scheduled date'for restart.
j' July 30, 1989-l l
following refueling.
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Will refueling or resumption ofl No
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. operation thereafter require a l
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technical specification change.I l'
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If answer is yes, what, in 1 ----------------
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l general, will these be?
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l If answer is no, has the reload l l'
I fuel design and core configura-l
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tion been reviewed by your l
'l-l Plant Safety Review Committee.1 No l
l to determine whether any unre--l 1
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. viewed safety questions are.
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. associated with the core reloadj l
l (Reference 10 CFR Section l
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50.59)?,_
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l If no such review has taken i 1989 l
l place, when is it scheduled?
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Scheduled date(s) for submit-1.
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I ting proposed licensing action l ----------------
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and supporting information.
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Important licensing considera-l
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tions associated with refuel-l l
l ing,.e.g., new or different
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l fuel design or supplier, unre-l ----------------
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viewed design or performance l
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analysis methods,.significant' l l
l changes in fuel design, new l
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operating procedures.
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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
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- p REFUELING INFORMATION (CONTINUED)'
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The present. licensed spent fuell.
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' pool storage capacity and the l l.
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' 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.
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has been requested or i's' l.(approximately 500 HTGR elements).l.
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assemblies.
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. The projected date of the last l 1996 under Agreements'AT(04-3)-6331 I
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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.
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capacity.
l Company, and DOE.*
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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
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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.
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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)
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480-6960.
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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 \\
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