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Monthly Operating Rept for Oct 1987
	ML20236Q789
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/31/1987
From:	Novachek F, Robert Williams; PUBLIC SERVICE CO. OF COLORADO
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	P-87403, NUDOCS 8711200287
	Download: ML20236Q789 (9)
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Issue 2

, Pep 1 of 1 07ERATINC DATA REPORT DOCKET NJ. 50-267 i i

DATE November 16, 1987 '

COMPLETED st- F. J. Novachek TELrPa0xE (303) 620-1007 OPERATINC STAT'.!S NOTES

' 1. Unit Names Fnre Sr. Vrnin. Unit No. 1

2. Reporting Period: 871001 through 871031

3. Licensed Thermal Power (Wt): 842

4. Nameplate Rating (Cross we): 342

5. Design Electrical P4 ting (Net We): 330

6. Maximum Dependable capacity (Cross We): 342 l

7. Maximum Dependable Capacity (Net We): 110

8. If Changes occur in capacity Ratings (Items Number 3 3 rough 7) Since last Report, Give Reasons:

None l

9. Power Level To Which Restricted If Any (Net me): 270.6

10. Reasons for Restrictions, if Any: Rennalysis of safe shutdown cooline followine a 90 l

minute interruption of-forced cooling.

This Month Year to Date Cumulative

11. Hours in Reporting Period 745 7.296 73.081

12. Number of Hours Reactor Was Critical 48.2 2.461.5 32.999.3

13. Reactor Reserve Shutdown Ecurs 0.0 0.0 0.0

14. nours cenerator on-Line 0.0 1.811.7 21.366.8

15. Unit Reserve Shutdovo nours 0.0 0.0 0.0

16. cross Thermal Energy cenerated (mu) 3.860.9 580.493.I 10.845.892.9

17. Cross Electrical Energy Generated (su) 0.0 189.789.0 3.523.785.0 la. Net Electrical Energy Generated (WH) 0.0 155.288.0 3.103.568,0

19. Unit service Factor 0.0 24.8 29.2 E

20. Unit Availability Factor 0.0 24.8 29.2

21. Unit Capacity Factor (Using MDC Net) 0.0 6.4 12.9 wh 22. Unit Capacity Factor (Uring DER Net) O. O 6.4 12.9 l n O C.

I 00 23. Unit Forced Outage Rate 100.0 75.2 64.1 i wO O 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Fire Recnverv.

y 871101. 1.064 hours7.407407e-4 days 0.0178 hours 1.058201e-4 weeks 2.4352e-5 months ,

hh 25. If Shut Down at End of Report Period. Estimated Date of Startup: December 15. 1987 /\

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l e 26. Units In Test Status (Prior to Cornercial Operation): Torecast Achieved /.

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InTIAL CRITICALITY N/A N/A f I

InTIAL ELEC3ICIIY N/A N/A CO WERCIAL OPERATICN N/A N/A

l. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

AVERAGE DAILY UNIT POWER LEVEL ;

+- '

i Docket No. 50-267 1

~ Unit Fort St. Vrain Unit No. 1 Date November 16, 1987 l

. Completed By F. J. Novachek I Telephone _(303) 620-1007 i

Month OCTOBER !

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'l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) f (MWe-Net) '

1 0.0 17 0.0 2 0.0 18 0.0 ;

3 0.0 19 0.0 1

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 l 16 0.0

Generator on line but no net generation.

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REFUELING INFORMATION

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l l-F l'1. -Name of Facility l Fort St. ' Vrain Unit No.1 l~

l l- l 1 2. Scheduled date for next l. l.

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refueling shutdown. I February 26, 1989 [

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l l t !!3. Scheduled date'for' restart l May 20, 1989 l -.

-l following refueling. -l l I l . l' l 4. Will~ refueling or resumption ofl No l' 1 operation thereafter require a l l

l. technical specification change'l -l l or other license amendment? 'l -l l l l

.I If answer is'yes, what, in> l ---------------- l

.l- general, will these be? I j.

l .

. I I I If answer is no, has the reload l l l- fuel design.and core configura-l l

[ tion been reviewed by your l l l Plant Safety Review Committee l No 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 l l l If no such review has taken l 1988. l l- place, when is it scheduled? l l l . .

l l l 5.. Scheduled date(s) for submit- l ~l j ting proposed licensing action l ---------------- l l and supporting information. l' l

! l l l 6. Important licensing considera- l l

.f l tions associated with refuel- l l l ing, e.g., new or different l l l-l fuel design or supplier, unre-'l ---------------- l

'l. viewed design or performance l l l analysis methods, significant J l

l. changes in fuel design, new l l l operating procedures. l l

'l .

l l ll 7. The number of fuel assemblies l l l (a) in the core and (b) in the l a) I'182 HTGR fuel elements l l spent fuel storage pool. I b) 0 spent fuel elements l ;

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REFUELING INFORMATION (CONTINUED) i I I l 8. The present licensed spent fuell l pool' storage capacity and the l l l l size of any increase in l Capacity is limited in size to l J

l licensed storage capacity that [ about one-thira of core l 1 l has been requested or is l (approximately 500 HTGR elements).l l planned, in number of fuel l No change is planned. l l assemblies. l l l i l l l

l 9. The projected date of the last l-1996 under Agreements AT(04-3)-633l I l refueling that can be dis- l and DE-SC07-79ID01370 between l j l charged to the spent fuel pool l Public Service Company of l l assuming the present licensed l Colorado, and General Atomic {

l :j l capacity. I Company, and DOE.* l 1 i

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 the Idaho Chemical Processing Plant. The storage capacity has evidently been sized to accommodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1996.

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x hPublic Service ~ a c 'l a .

16805 WCR 19 1/2, Platteville, Colorado 80651 ;.

November 16, 1987 Fort St. Vrain Unit No. 1 P-87403 U. S. Nuclear Regulatory Cominission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

OCTOBER, 1987 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of October, 1987, 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.

Sincerely, !

l W4./n. Ao.toiuuws i R. O. Williams, Jr. .,

Vice President, 1 Nuclear Operations j i

Enclosure i cc: Regional Administrator, Region IV I ATTN: Mr. T. F. Westerman, Chief 'l Project Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain R0W:djm

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PUBLIC SERVICE COMPANY OF COLORADO j FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 165 October, 1987 J

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- R 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:0ctober, 1987.

1.0 NARRATIVE

SUMMARY

.OF OPERATING EXPERIENCE AND MAJOR SAFETY

-RELATED MAINTENANCE '

'The month began with the reactor critical, in power ascension- !

prior to-placing-the turbine generator on line.

On October 2, 1987, at 2359 hours0.0273 days 0.655 hours 0.0039 weeks 8.975995e-4 months , with the reactor at approximately 26 percent power and all four helium circulators i operating on nuclear steam, a hydraulic oil fire was discovered in the area of HV-2292. On October 3, 1987, at 0001 . hours, "D"'

' helium circulator was placed in the self-turbining mode to allow isolating hydraulic oil from the fire area. Simultaneously, "C" helium ' circulator speed was raised in order to maintain primary coolant flow in Loop II. At 0006 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , "C" helium circulator tripped, shutting down Loop II. At 0008 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , a Loop I (automatic) Shutdown on Hot Reheat Activity.High occurred as a result of fire damage to cables for the power supplies to two of three Loop I h.ot reheat activity monitors. At 0009 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months , a manual ~ reactor scram was inserted because of the indicated loss of primary and . secondary coolant flow. At 0015 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months , the fire was extinguished by. the plant fire brigade. At 0020 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , primary and secondary coolant flows were re-established on Loop I with "A" ' helium circulator on emergency condensate. At 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , an ALERT.was declared as a precaution against further plant . degradation. At 0815 hours0.00943 days 0.226 hours 0.00135 weeks 3.101075e-4 months , with two independent safe shutdown paths available for' maintaining' core cooling, the ALERT j was terminated. A Nuclear Regulatory Commission Augmented ,

Inspection Team (AIT) was onsite from October 3 through October 6 '

to conduct an initial inspection of the fire and its i consequences. The AIT findings were reported in AIT Inspection Report 50-267/87-26. This event was investigated and reported to 4 the Nuclear Regulatory Commission in Licensee Event Report !87-023, preliminary. Fire recovery activities are continuing.

'~ 1 On October 9, 10, 11, and 14, 1987, the Plant Protective System (PPS) reactor scram logic and alarm circuitry was actuated a total of 11 times on Wide Range Channels (WRC) III and V neutron flux rate of ~ change high. The actuations were caused by electrical noise induction in the wide range channels. The l source of the electrical noise was repeated switching )

(" chattering") of relay FS-11263-X, which in turn was caused by i

, an intermittent ground in the associated flow switch FS-11263.

i This event was investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-024.

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On: October 30,'1987,~at 2215 hours0.0256 days 0.615 hours 0.00366 weeks 8.428075e-4 months , a Loss;of.0utside F.lectrical-Power (LDEP): occurred when a contract electrician inadvertently activated the' fire ~ water deluge system on the Reserve Auxiliary c . Transformer (RAT). The deluge system activation automatically caused the grid.. feeder- breakers to the' RAT to.open, thereby E

.de-energizing outside. electric power. Since the' Main -Power-

. Tran s forme r. and Unit' Auxiliary Transformer were not in service, the loss of the RAT resulted in a. loss of all outside electric-power. The emergency diesel generators automatically: started and ,

. loaded, and all needed ' equipment . functioned -as. designed. . At' approximately 2250 hours0.026 days 0.625 hours 0.00372 weeks 8.56125e-4 months -the RAT feeder breakers were reclosed~

and Outside Electric Power was Lrestored. This event will be.

investigated and reported to the Nuclear Regulatory Commission in' Licensee Event Report 87-025, 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS' 0F 10% OF THE ALLOWABLE ANNUAL VALUE None e 3.0 INDICATION OF FAILED FUEL RESULTING FROM' IRRADIATED FUEL EXAMINATIONS None 4,0 MONTHLY OPERATING DATA REPORT Attached

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ML20236Q789

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