ML20206F687

Monthly Operating Rept for Oct 1988 for Fort St Vrain Nuclear Generating Station

ML20206F687
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/31/1988
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-88406, NUDOCS 8811210270
Download: ML20206F687 (9)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST VRAIN NUCLEAR GEN 5 RATING STATION MONTHLY OPERATIONS REPORT i

NO. 177 October, 1988 5-

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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 not in operation. This report is for the month of October, 1988, 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND M10R SAFETY RELATED MAIN 1ENANCE The reactor remained shutdown the entire month of October, 1988, for helium circulator bolt replacement and primary coolant cleanup.

A few individual cells in the new A and B station batteries were fou3d with low, but acceptable ,pecific gravity ur cell voltage.

The batteries are being closely monitored to insure operability is maintained.

In the September, 1988 Monthly Operations Report, it was reported that two fire barrier penetration seals in the auxiliary boiler room were Jetermined to be deficient. This was to ce reported to the Nuclear Regulatory Commission in a Licensee Event Report.

Further investigation verified that the seals were operable and i

the condition was determined not reportable.

l On October 7, 1988, PSC determined that a Class 1A hydraulic l shock supressor had not been inspected in accordance with Technical Specification requirements. This condition was reported to the Nuclear Regulatory Commission in Licensee Event Report 88-013.

On October 8 and again on Octot,er 3,1988, .n unexpected Loop II l shutdown actuation of the Plant Protective System was caused by a "0" helium circulator trip on "Loss of Bearing Water". At the time of each event Loop II secondary coolant system was shutdown and isolated, both "C" and "0" helium circulators were self- i turbining, and no valve actuations occuried. These events were reported to the Nuclear Regulatory Commission in Licensee Event Report 8S-014.

On October 12, 1988, during the performance of a Loss of Outside Electric Power test, the essential bus loads were not automatically energized from the stancDy diesel generators.

Power was restored within the FSAR requirements and the event was

' determir.ed not recortable. It was decided that this evunt will voluntarily be reported to the Nuclear Regulatory Ccemi,sion in Licensee Event Report 83-015.

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1 I L On October 18, 1988, the "Loss of Outside Electric Power"

, surveillance was successfully completed.

Primary coolant moisture levels are currently in excess of levels permitted for reactor st: ries. Moistare removal is in progress.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS D T Tif 0F THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL ERAMINATIONS ,

None 4.0 MONTHLY OPERATING OATA REPORT Attached 5.0 CONTROL ROD ORIVE PARTIAL SCRAM TEST RESULTS A'NO MAXIMUM OAILY TIMPERATURE REPORT Not required this month.

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OPERAT! NIL DATA RfPORT t DOCKET NO. 50-267 DATE Noveciber 15. 1988 COMPLETED BY M.L. Block itLEPHONE (303) 620-1180 0PERATING STATUS h0Tf.5

1. Unit Name: For,t St. Vrain. Unit No. 1

2. Reporting Period: 881001 through 881031

3. Licensed Therral Power (MWt): 842

4. Nameplate . ting (Gross MWe): ,.

342

5. Design Electrical Rating (Net Fde): 330

6. Manium Dependable Capacity (Gross MWe): 342

7. Maximum Dependable Capacity (Net Fde): 330

8. If Changes Occur In Capacitf Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

None

9. Power Level to which Restricted. If Any (Net FWe): 270.6

10. Reasons For Restriccions. If Any: Reanalysis of safe shutdown cooling folleving a 90 minute interruption of forced cooling.

This Month Year To Date Cumulative

11. % rs in Reporting Period 745.0 7.320.0 81.865.0

12. Number Of Hours Reactor Was Critical _.

0.0 3.798.1 37.244.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On Line 0.0 3.487.3 25.072.8

15. Unit Reserve Shutdown 8 m rs 0.0 0.0 0.0

16. Gross There41 Energy C nerated (KdH) 0.0 1.954.375.5 _ 12,887,710.1

17. Gross Electrical Energy Generated (F4H) 0.0 718.184.0 4.260.404.0

18. het Electrical Energy Generated (FwH) -2.857.0 666.150.0 3.756,416.0 ,

19. Unit Service Factor 0.0 47.6 _

30.6

20. Unit Availabtitty Factor 0.0 47.6 ,

30.6

21. Unit Capacity Factor (Using VDC het) 0.0 27.6 ,

13.9

22. Unit Capactty Factor (Using CER Net) 0.0 27.6 13.9

23. Unit forced Outage Rate 100.0 52.4 63.3

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

Primary Coolant Clean up. 881101, 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> t

25. If Snst 0 wn At Eed Of Report Period. Esttirated Cate O' 5tartuo:

• November 14. 1988 Forecast Acnteied

26. Units In Test Status (Prior To Comercial 0:eration): l INITIAL CRITICALITV N/A Nf4 INIT!M. ELECTRICITY h/A h/A COMMERCIAL OPERATION h/A N/A f 1

• Dependent on Moisture i

, AVERAGE DAILY UNIT POWER LEVEL

- Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date November 15, 1988 Completed By M. L. Block Telephone (333) 620-1100 Month OCTOBER 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 20 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 bi.$ no net generation.

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REFUEL.ING INFORMATION  ;

l l 1 l l 1. Name of Facility l Fort St. Vrain Unit No, f_ _-

i l 2. Scheduled date for next l l l l refueling _ shutdown. '

June 7,1989 l 1 1 I i l 3. Sched.iled date for restart July 30,1989 l  ;

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following refueling. ._

1 4. Will refueling or resumption ofu No i  !

operation thereafter requite a 1 l  !

I technical specification change h l f l or other license amendment? I l l l l r If answer is yes, what, in l ---------------- l l general, will these be? l l l l l 1 If answer is no, has the reload l l l  !

fuel design and core configura-l l  ;

tion been reviewed by your l l i Plant Safety Review Committee l No

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l to determine whether any unre- l l  !-

l viewed safety questions are l l ,

I associated with the core reload l l t

l (Reference 10 CFR Section l l  !

l 50.59)? l l l l l l l If no such review has taken l 1989 l ,

l place, when is it scheduled? l l l l l l  !

l S. Scheduleddate(s)forsubmit- l l t i ting proposed licensing action l ---------------- l l l and supporting information. l l i i l I l 6. Important licensing considera- l l

[ tions associated with refuel- l l l ing, e.g., new or different l l fuel design or supplier, unre- l ---------------- i  ;

l viewed design or performance l l l

l analysis methods, significant l l t l changes in fuel design, new l l t

] oper1 ting procedures. l l I I 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 l spent fuel storage pool. I b) 0 scent fuel elements l i

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REFUELING INFORMATION (CONTINUE 0) l I 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 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 1996 under Agreements AT(04-3)-633l 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 Comoar.y, and 00Ee* I

The 1996 estimated date is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by 00E 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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f TSP-3 Attachment ISP-3C issue 2 Page 1 or 1 0811 D itylpgweis AND POWER REDUCTIO *l}

DOCK [T seo. 50-267 U4tf NAME fort St. Vrsin Unit No. 1 DATE November 15. 1988 COMPLET[D BY M. L. Bloch TELEPHONE f3031 620-1180 R[ FORT MONTH OCTOBER. 1988 I i 1 1 I IM[t eKg) OFI ~l l I i l 1 1 I I ISHUTTikG l l 1 l CAUSE AND CORRECTIVE ACTION 1 i NO. I DAf[ ITYP[I DURATION l R[ASON IDOWN 1 L[R g ISYSTEMICOMPONE9til 10 PREVENT R[CURRENCE I 1 __ . _ l_ l l i 1 IGQQL .lG90E l l I i 1 i i IEEACIDE_.i 1 i l I i 188-171 881008 1 5 l 145.0 i H l 1 i N/A I AB l CMP I Reactor Manually Shutdown for Scs eduled I 3 I a i 1 1 1 I I I Replacement Of Helipe Circulator Bolts. 1 I 1 1 I I l l l l 1 Refer To LER 87-019. l 1 i 1 i 1 i I I i 1 i i i i i i I I I I I i i l I i i i I I I i i i i l I i i I I I i i l 1 i i i 1 i I i 1 I i i 1 i 1 l 3 I I I I I I I I I I I I I i i i 1 I I I I I i 1 I I I i i I I I I I I I I I i I i I I i 1 1  : I I i 1 1 I I I I I I I I I I I I I I I l I I i i i i i I I I I I I I I I I I I I I I I l i I I I I I i i I i i i i l i I I I I I I I I I I I I I I I l 1 1 I I i i 1 1 1 I I I I I I I I I I I I I I I I I i 1 I I i i I I I I I I I I I I 1 l l 8 I I I I I I I i 1 l l t i i I i l i I I i i I i I i i I I I i 1 l l l 1 1 I I I I I I I i i I I i l I i I l I I i 1 1 I I I I I 1 i 1

. I I I I I i 1 1 I l l 1 I i i i l i i i 1 i 1 I I i I I i 1 1 1 1 1 1 I I I I i 1 l i I I I I I I I I I i 1

hPublic Service ~ ......

Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 November 15, 1938 Fort St. Vrain Unit No. 1 P-88406 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington 0.C. 20555 Docket No. 50-267

SUBJECT:

OCTORER 1983 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of October 1933, 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, d

C. H. Fuller Manager, huclear Production Enc?asure cc: Regional A ministrator, Region IV ATIN: Mr. T. F. kesternan, Chief Projects Section B Mr. Robert Farrell Senior Resident Inspector Fort St, Vrain CHF/cas