ML20244E215

Monthly Operating Rept for Mar 1989 for Fort St Vrain

ML20244E215
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/31/1989
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-89134, NUDOCS 8904240351
Download: ML20244E215 (10)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 182 March, 1989 8904240351 890331 PDR ADOCK 05000267

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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. The report for the. monthly partial scram / maximum temperature reports for control rod drive and orificing assemblies is _ not included this month.

The reactor was critical at low power through the end of the month.

This report is for the month of March, 1989.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE During -the first week of March, 1989, the removal of all the Reserve Shutdown material from the PCRV was successfully completed.

On March 17,

1989, PSCo determined that the Emergency Diesel Generators had been in a condition.where their ability to perform their long term safety function was in question.

Several. engine head coolant flow directors were found missing, which could have led to-inadequate cooling under long term loaded conditions.

This event is being reported to the Nuclear Regulatory Commission in Licensee' Event Report 89-03.

An evacuation of the PCRV for moisture removal purposes was performed between March 12 and. March 19, 1989. A total of approximately 180 gallons was. removed from the vessel.

From March 21 through March 24, 1989, the reactor scram circuitry was spuriously actuated 13 times.

These actuations were due to electronically induced noise signals in the wide range neutron flux monitors. These spurious actuations are being reported to the Nuclear Regulatory Commission in Licensee Event Report 89-04.

On March 23, 1989, the PCRV was pressurized to 107 psia while the Region 27 refueling penetration interspace pressurization line was isolated. The Technical Specifications prohibit pressurizing the PCRV to greater than 100 psia unless the interspaces are pressurized above PCRV pressure with purified helium, to preclude leakage of primary coolant into the reactor building.

Both primary and secondary seals were operable and there was minimal primary coolant circulating activity due to the previous extended outage.

This event is being reported to the Nuclear Regulatory Commission in Licensee Event Report 89-05.

On March 26, 1989, the reactor was taken critical at 0746 hours0.00863 days <br />0.207 hours <br />0.00123 weeks <br />2.83853e-4 months <br />.

On March 29, 1989, PSCo discovered that surveillance SR 5.6.1d-M, which is required for Emergency Diesel Generator (EDG) operability, had not been performed prior to increasing plant power to greater than 2?;.

EDG's are required to be available above 2?; power level.

This event is being reported to the Nuclear Regulatory Commission in Licensee Event Report 89-06.

j l

r The cylinder head replacement / refurbishment, repairs and i

inspections for the Emergency Diesel Generators nave been successfully completed.

Construction progress for the Security Diesel Building is proceding more slowly than anticipated. A successful operational and preliminary acceptance test was performed on the EDG system control panel.

Delivery is subject to construction progress of the building.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10?o 0F THE ALLOWABLE ANNUAL VALUE None

. 3.0 INDICATION OF 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 TEMPERATURE REPORT i

Not required this month.

I I

L OPERATING DATA REPORT DOCKET NO.

50-267-DATE

' April 15, 1989 COMPLETED BY M.L. Block TELEPHONE (303) 620-1180 OPERATING STATUS NOTES 1.

Unit Name:

Fort St. Vrain, Unit No. I 2.

Reporting Period:

890301 through 890331 3.

Licensed Thennal 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 Througn 7) Since Last Report, Give Reasons:

None.

9.

Power Level To Which Restricted, If Any (Net MWe):

270.6 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 Reporting Period 744.0 2,160.0 85,489.0

12. Number Of Hours Reactor Was Critical 135.2 192.8 37,437.6

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) 4,935.1 5,122.3 12,892,832.4

17. Gross Electrical Energy Generated (MWH) 0.0 0.0 4,260,404.0

18. Net Electrical Energy Generated (MWH)

-2,813.0

-9,090.0 3,740,904.0

19. Unit Service Factor 0.0 0.0 29.3

20. Unit Availability Factor 0.0 0.0 29.3

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 13.3

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 13.3

23. Unit Forced Outage Rate 100.0 100.0 65.1 24.

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

None.

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

N/A

• Forecast Achieved

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

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

• Reactor taken critical on March 26, 1989, at 0746 hours0.00863 days <br />0.207 hours <br />0.00123 weeks <br />2.83853e-4 months <br />.

AVERAGE DAILY UNIT POWER LEVEL l'

Docket No. 50-267

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l Unit Fort St. Vrain Unit No. 1 Date April 15,1989 Completed By M. L. Block Telephone (303) 620-1180 Month MARCH 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.

REFUELING INFORMATION i

l l

l 1.

'Name of Facility i Fort St. Vrain Unit No. 1 l

l l

l l 2.

Scheduled date for next l None, no further refueling at l

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refueling shutdown.

I FSV is expected.

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l 3. ' Scheduled date for restart l N/A l

l followino refuelino.

l l

l l

l l 4.

Will refueling or resumption ofi N/A l

l operation thereafter require a l l

l technical specification change l l

l or other license amenoment?

I l

l l

1 l

If answer is yes, what, in l ----------------

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general, will these be?

I j.

l 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 1

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 l

associated with the core reload l l

l (Reference 10 CFR Section l

l l

50.59)?

l l

l 1

l l

If no such review has taken l N/A l

l place, when is it scheduled?

I 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

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

f uel de si g n or s uppl i e r, un re-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

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(a) in the core and (b) in the I a) 1482 HTGR fuel elements l

l spent fuel storage pool.

I b) 0 spent fuel elements l

REFUELING INFORMATION (CONTINUED) l 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

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-SC07-791D01370 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 Comoany, 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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i hPublic Service-

":3; L.e April 14,1989 Fort St. Vrain Unit No. 1 P-89134 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555 Docket No. 50-267

SUBJECT:

MARCH 1989 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sir:

Enci o. sed, please find the Monthly Operations Report for the month of March 2989, submitted per the requiraents of Fort St.

Vrain Technical Specification AC 7.5.1.

If you have any questions, please contact Mr. M. H. Holmes at (303) 480-6950.

Sincerely,

d. l4. Eller by y

C. H. Fuller

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Manager, Nuclear Production CHF/mk Enclosure cc:

Regional Administrator, Region IV ATTN:

Mr. T. F. Westerman, Chief i

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

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