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Monthly Operating Rept for May 1989 for Fort St Vrain
	ML20245C447
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/31/1989
From:	Block M; PUBLIC SERVICE CO. OF COLORADO
To:	;
Shared Package
ML20245A280	List: ML20245A277; ML20245C447; ML20245C458;
References
	NUDOCS 8906260190
	Download: ML20245C447 (8)
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I PUBLIC SERVICE COMPANY OF COLORADO !

FORT ST. VRAIN NUCLEAR GENERATING STATION l I 1

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1 MONTHLY OPERATIONS REPORT NO. 184 May, 1989 j

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This report. contains the highlights of. the Fort St. Vrain,. Unit No.'1, activities operated under the provi sions of the : Nuclear- ;

Regulatory Commission Operating License No. DPR-34. This report

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includes the monthly; partial scram / maximum temperature reports for ;

control rod drive and orificing assemblies. This report is for the '

month of May, 1989.

1.0 NARRATIVE

SUMMARY

-- 0F OPERATING EXPERIENCE AND MAJOR SAFETY.

RELATED MAINTENANCE =

i Replacement and testing of Regions 3 and 7 control rods was- I successfully completed during the first week of May,1989.

1 Investigation and troubleshooting was performed on the ACM Diesel' during the.first week of May,1989, .to determine the reasons for the load swinging that was being experienced. The problems > -e resolved and the diesel was declared operable on May 5,1989, at '

2215 hours0.0256 days 0.615 hours 0.00366 weeks 8.428075e-4 months .

The reactor was taken critical on May 5,1989, at 2355 hours0.0273 days 0.654 hours 0.00389 weeks 8.960775e-4 months and remained critical the entire month of May. J q

The Turbine Generator was placed on line May 7, 1989, at 1833 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and remained on line the entire month of May. j The reactor was maintained at 50% power for a.few days during ;

the month due to problems being experienced with the flux l controller sending spurious signais to the regulating rod.

Troubleshooting and repairs 'were initiated and the -flux controller was returned to automatic operation.

l A steam leak was identified on Hot Reheat drain line L- 22207. j Repairs were completed'on May 29, 1989. ;

I Reactor power and Turbine Generator load were increased during the month a. moisture and oxidant levels permitted. ;

l The reactor reached _80% power on May 29, 1989, and remained at '

power threugh the end of May, 1989.

On May 30, 1989, the ACM diesel load swinging problems i

resurfaced. The ACM was declared inoperable at 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months , i entering the 7 day Srace period of LC0 4.2.17. '

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL' VALUE None o

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'i 3.0 INDICATION OF FAllED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS 1

None 4.0 MONTHLY OPERATING DATA REPORT I J

Attached 1 i

5.0 CONTROL ROD DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY I TEMPERATURE REPORT j Attached 1

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l OPERATING DATA REPORT DOCKET NO, 50-267 DATE June 15, 1989 COMPLETED BY M.L. Block TELEPHONE (303) 620-1180 OPERATING STATUS NOTES

1. Unit Name: Fort St. Vrain, Unit Number 1

2. Reporting Period: 890901 thrnuch 890531

3. Licensed Thermal Power (MWt): 842

4. Nameplate Rating (Gross MWe): 342

5. Design Electrical Rating (Net MWe): 330

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 (82%)

10. Reasons For Restrictions, If Any: Reanalysis of safe shutdown cooling following a 90 minute interruption of forced cooling.

This Month Year To Date Cumulative

11. Hours In Reoorting Period 744.0 3,623.0 86,952.0

12. Number Of Hours Reactor Was Critical 624.I 1,444.0 38,688.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 581.4 873.4 25,946.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross inermal Energy Generated (MWH) 295.085.6 410,489.1 13,298,199.2 l 17. Gross Electrical Energy Generated (MWH) 109,796.0 138,487.0 4,398,891.0

18. Net Electrical Energy Generated (MWH) 102.530.0 117,749.0 3,867,743.0

19. Unit Service Factor 78.2 24.1 29.8

20. Unit Availability Factor 78.2 24.1 29.8 l 21. Unit Capacity Factor (Using MDC Net) 41.8 ,

10.0 13.5

22. Unit Caoacity Factor (Using DER Net) 41.8 10.0 13.5

23. Unit Forced Outar ate 21.9 75.3 64.6

24. Shutdowns Schedulu dver Next 6 Months (Type. Date, t; Duration of Each):

None.

25. If Shut Down At End Of Report Period Estimated Date Of Startup: N/A

26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

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~ AVERAGE DATLY UNIT POSER LEVEL

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Docket No.' 50-267 .

Unit Fort St. Vrain Unit No. 1

. . .Date June 15, 1989-Completed By M. L. Block- .

Telephone (303) 620-1180 < '

Month MAY DAY ~ AVERAGE DAILY' POWER LEVEL. DAY AVERAGE DAILY POWER' LEVEL l (MWe-Net)~ (MWe-Net) 3

.i1 1 0.0i 17 204.2 j

2 0.0 -18 205.7

.3 .- 0 . 0 19 218.6 4 0.0 '20 211.2 j 1

5- 0.0 .21 208.9 6 0. 0' 22 209.0 7 0.0

23 210.5' 8 58.1 24' 209.8 9 63.6 25 211.8' 10 70.6 26 211.7 11 96.1 27 213;3 12 154.0 28 214.6 13 148.8 29 230.0 14 147.9 l30 251.5' 15 150.1 31- 250.4 16 152.3

Generator en line but no net' generation.

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REFdELING INFORMATION l l l l 1. Name of Facility l Fort St. Vrain Unit No. 1 (

l l 1 l 2. Scheduled date for next l None, no further refueling at l l refueling shutdown. I FSV is expected. l l l l l 3. Scheduled date for restart l N/A l l following refueling. l- l 1 I I l l 4. Will refueling or resumption ofi N/A l l l operation thereafter require a l l l technical specification change l l l or other license amendment? l l l l l l If answer is yes, what, in l ---------------- l l general, will these be? I l l l l 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 I l to determine whether any unre- l l l viewed safety questions are l l l associated with the core reloadl l l (Reference 10 CFR Section l l l 50.59)? I l l 1 I l If no such review has taken l N/A l l place, when is it scheduled? l l l l l l l

l 5. Scheduled date(s) for submit- l l l ting proposed licensing action l ---------------- l l and supporting information. l l 1 1 I 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 l l l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) 0 spent fuel elements l l

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REFUELING INFORMATION (CONTINUED)

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l- I 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 Ll l licensed storage capacity that I about one-third of. core l l has been requested or is. l (approximately 500 HTGR elements).]

l.- planned, in number of fuel l No change is' planned.. l l assemblies. l l 1 I. .

l l 9. 'The projected date of the last I .1993 under Agreements AT(04-3)-633l ~

l refueling that can be dis- l and DE-SC07-791001370 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 l capacity. I Company, and DOE.*. l No further refueling is anticipated at Fort St. Vrain. 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 1993.

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ML20245C447

Text

SUMMARY

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