ML20235J618

Monthly Operating Rept for Jan 1989 for Fort St Vrain Nuclear Generating Station

ML20235J618
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/31/1989
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-89062, NUDOCS 8902240347
Download: ML20235J618 (9)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION y,.

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MONTHLY OPERATIONS REPORT NO. 180 January, 1989 2

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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. OPR-34. The report for  !

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 fort. operator training.

'startups only. This report is for the month of-January,1989.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE- AND MAJOR SAFETY RELATED MAINTENANCE

.On January 5, 1989, the reactor was taken critical at 1614 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.14127e-4 months <br /> for reactor operator'startup training purposes, s

> On January 5, 1989, two loop shutdown actuations of the Plant Protective System occurred, due.to high moisture levels in the primary coolant system. These actuations were reported to the

.. Nuclear Regulatory Commission in Licensee Event Report 89-01.

On January' 13, 1989, the reactor was manually shutdown at 1454 hours0.0168 days <br />0.404 hours <br />0.0024 weeks <br />5.53247e-4 months <br /> for, continuation of the moisture removal. process.

n On January 19, 1989, reserve. shutdown material was

() unintentionally released into seven of the thirty-seven refueling regions in the reactor core, during surveillance testing. This event will be' reported to the Nuclear Regulatory Commission in Licensee Event Report 89-02.

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

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t h 3.0 INDICATION- 0F FAILED' FUEL RESULTING- FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 5.0 CONTROL ROD DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY' TEMPERA'IURE REPORT Not required this month.

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

1. Unit Name: Fort St. Vrain, Unit No. 1

2. Reporting Period: 890101 through 890131

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: Re-analysis of safe shutdown cooling following a 90 minute interruption of forced cooling.

This Month Year To Date Cumulative

11. Hours In Reporting Period 744.0 744.0 84,073.0

12. Number Of Hours Reactor Was Critical 57.6 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 0.0

16. Gross Thermal Energy Generated (MWH) 187.2 187.2 12.887.897.3

17. Gross Electrical Energy Generated (MWH) 0.0 0.0 4.260.404.0

18. Net Electrical Energy Generated (MWH) -3.829.0 -3.829.0 3.746.165.0

19. Unit Service Factor 0.0 0.0 30.0

20. Unit Availability Factor 0.0 0.0 30.0

21. Unit Capacity Factor (Using MDC Net) _

0.0 0.0 13.5

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 13.5

23. Unit Forced Outage Rate 100.0 100.0 64.4

24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):

Week of April 24, 1989, 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.

25. If Shut Down At End Of Report Period, Estimated Date Of Startup: April 1. 1989 Forecast Achieved

23. Units In Test Status (Prior To Commercial Operation):

INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A j

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date February 15, 1989 Completed By M. L. Block Telephone (303) 620-1180 Month JANUARY DAY 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 7 0.0 23 0.0 8 0.0 24 0.0 9 0.0 25 0.0 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 0.0 16 0.0

• Generator on line but no net generation.

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' - . - j REFUELING INFORMATION I

l i l l l 1. Name of Facility i Fort St. Vrain Unit No. 1 [ j l l l l 2. Scheduled date for next l None, no further refueling at l l refueling shutdown. I FSV is expected. l l . .

! l l 3. Scheduled date for restart l N/A l l following refueling. l l l l 4. - Will refueling or resumption ofl N/A- l l l operation thereafter require a l l l technical specification change l l l or other license amendment? i l l

l If answer is yes, what, in l

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l general, will these be?  ! l 1 l l l If answer is no, has the reloadj l l fuel design and core configura-l l l tion been reviewed by your l l l Plant Safety Review Committee i N/A l l to determine whether any unre- l l 1

l viewed safety questions are l l l associated with the core reloadj l l (Reference 10 CFR Section l l l 50.59)? l l I I I l If no such review has taken l N/A l l place, when is it scheduled? l l 1 I I l 5. Scheduled date(s) for submit- l l .

ting proposed licensing action l ----------- ---- 1 l l l and supporting information. l l l 1 l l 6. Important licensing considera- l l ,

I tions associated with refuel- l l l ing, e.g., new or different l l l fuel design or supplier, unre- l ---------------- l 3 l viewed design or performance l l l l analysis methods, significant l l j 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) 1482 HTGR fuel elements l l spent fuel storage pool. I b) 0 spent fuel elements l l

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REFUELINGINFORMATION(CONTIhuiD}

l l 1 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 l licensed storage capacity that l 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 l l l l 9. The projected date of the last l 1993 under Agreements AT(04-3)-6331 l refueling that can be dis- l and DE-SC07-791001370 between l l 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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h Public Service ~ February 15, 1989 -

Fort St. Vrt '.a Unit No. 1 ,

P-89062 U. S. Nuclear' Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

JANUARY 1989 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of l January 1989, submitted per the requirements of Fort St. Vrain l Technical Specification AC 7.5.1.

If you have any questions, please contact Mr. M. H. Holmes at (303) 480-6960.

Sincerely, C . \4.fi.tdh-C. H. Fuller Manager, Nuclear Production CHF/cas Enclosure .

cc.: Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief '

Projects Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain i

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