ML20207N384

Monthly Operating Rept for Sept 1988 for Fort St Vrain

ML20207N384
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/30/1988
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-88382, NUDOCS 8810190122
Download: ML20207N384 (10)

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

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MONTHLY OPERATIONS REPORT

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NO. 176

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' September, 1988 i

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_ esto190122 080930 I

PDR ADOCK 05000267 R PDC

2-t 3.0 INDICATION OF FAILED FUEL RESULTING FROM :RRADIATED FUEL

' EXAMINATIONS None 4.0 N NTHLY OPERATING DATA REPORT Attached l 5.0 CONTROL ROD ORIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY [

TEMPERATURE REPORT Not required this month.  !

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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 a

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 September 1988.

1.0 NAR MTIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown the entire month of September, 1988, for helium circulator bolt replacement.

Station batteries A and 8 have been replaced and passed service

. discharge surveillance tests. Test data is being evaluated i

further to assess the battery conditions.

On September 20, 1988, NRC Commissioner Rogers visited Fort St.

Vrain.

J On September 27, 1988, two fire barrier penetration seals in the auxiliary boiler room were determined to be deficient. This

. event will be investigated and reporteo to the Nuclear Regulatory l Commission in Licensee Event Report 88-013.

During this month, bolts in Loop II helium circulators were

, replaced and the loop was returned to service. All four helium circulators were returned by the end of the month.

Primary coolant moisture levels are currently in excess of requirements for reactor startup. Moisture removal !s 'n progress.

i 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS i 0F 10% OF THE ALLOWABLE ANNUAL VALUE

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l 3.0 INDICATION OF FAILE0 FUEL RESULTING FROM IRRAOIATED FUEL EXAMINATIONS None 4.0 _ MONTHLY ODERATING DATA REPORT Attached 5.0 CONTROL R00 ORIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM OAILY TEMPERATURE REPORT Not required this month.

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OPERATING DATA REFORT DOCKET NO, 50-267 DATE October 15, 1988 COMPLETED BY M.L. Block TELEPHONE (303) 620-1100 OPERAT!NG STATUS NOTES

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

2. Reporting Period: 880901 through 880930

3. Licensed Thermal Power (Kdt): 842

4. Nameplate Rating (Gross MWe): 342

5. Design Electrical Ratirg (Net Kde): 330

6. Maximum Dependable Capacity (Gross NWe): 342

7. F)ximum Dependable Capacity (Net Kde): 330

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

9. Power cevel To Which Restricted, If Any (Net K4e): 270.6 ,,

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

This Month Year To Date Cumulative

11. Hours In Reporting Period _ 720.0 6.575.0 81.120.0

12. Number Of Hours Reactor Was Critical 0.0 3,798.1 _

37,244.8

13. Reactor Reserve Shutdowr, Hours 0.0 0.0 0.0

16. Hours Generttor On Line 0.0 3,487.3 25,072.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (K4H) _

0.0 1,954,375.5 12,887,710.1

17. Gross Electrical Energy Generated (K4H) 0.0 718,184.0 4,260,404.0

18. Net Electrical Energy Generated (KdH) -1798.0 _669,007.0 3,759,273.0

19. Unit Service Factor 0.0 53.0 31.0

20. Unit Availability Factor 0.0 53.0 31.0

21. Unit Capacity Factor (using MDC Net) 0.0 31.0 14.0

22. Unit Capacity Facter (Using DER Net) 0. 0 ___ , , _

31.0 14.0

23. Unit forced Outage Rate 100.0 47.0 63.0

24. Shutdowns Scheduled Over hext 6 Months (Type Date, and Duration of Each): Helium Circulator Bolt Replacement, 881001, 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br />.

25. If Shut Down At End Of Report Period Estitrated Date Of Startup: October 20, 1988

26. Units In Test S htus (Prior To Co m rcial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITV N/A h/A COMMERCIAL OPERATION N/A N/A

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.  ; , AVERAGE DAILY UNIT POWER LEVEL

. Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date October 15, 1988 Completed By M. L. Block Telephone (303) 620-1180 Month _ SEPTEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY PCWER 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 N/A 16 _

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• Generator on line but no net generation.

s TSP 3 Attschment ISP-3C

• Is',ue 2

! age 1 of 1

• UNIT SHUTDOWNS AND POIILR REDUCTION}

DOrKET NO. $0-267 .

UNIT NAME fort St. Vra in Unit No. 1 OATE October 15. 1988 COMPI_ETED BY H. I. , DBck REPORT MONTH TELEPHONE 0031 620-1180 SFPTEMBER. 1988 I I I I I I AEliiOif Ui l i I I I I I I I I ISHUTTING 1 l l  ! CAUSE AND CORRECTIVE ACTION 1 1 an. I Dart livPt i OUHAI40N i REASON IDOWN l LER # ISYST EMICOMPONENTl 10 PREVENT RECURRENCE l l._ _l _ __ _ l _ l l lFifACIOR j IQ9Q L lCODE l l l I I I I I I I I I i 183-l?l 880908 l S I 720.0 I H I 1 1 N/A l AB l CMP 1 Reactor Manually Shutdown for Scheduled i i i I 1 l l l l l l Replacement Of Helium Ci rculator Dolts. I j i l i l i i l l I Refer To EER 87-019. I i 1 1 I I l I l i 1 I I I I I I I I I i I I i I 1 I i i l I I i l I i 1 I I  ! I I I I I 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 I I I I i 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 I I I I I I I I I I i I I I I I I i l l 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 I I I I I i 1 I I I I I i l i i l I I I I I I i l 1 I I I I I I I I I i I I I I I i 1.

1 I I I I I I I I I I i I i 1 i i l i I I I I I I I I I I I I I I I I I I i 1 1 I I l i I I I I I I I I I I I I I I l I 1 i I I l l  ! I .' I I I 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 l  ! I I I 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 I I I I I I I I I I I I I I I I I i I i i I m_ _ . _ _ _ _ .____ _ _ - - _ _ _ _ _ _ _ _.-- _ - _ - _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ - _ - _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ - _ - . . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ - - . _ _ _ _ . _ _ _ - - _ - - _ _ _ _ - . _ . - - _ _ _ . _ _ _ _ _ _ _ _

REFUELING INFORMATION l l l l 1. Name of Facility l Fort St. Vrain Unit No. 1 I I I I l 2. Scheduled date for next l l l refueling shutdown. I April 4, 1989 l l 1 l l 3. Scheduled date for restart l Ma/ 27, 1989 l l____, following refueling. l l l 1 I l 4. Will refueling or resumption ofl No 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 1 ---------------- l l general, will these be? l l 1 l 1 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 l No l l to determine whether any unre- l l l viewed safety questions are l l l associated with the core reloadj l l (Reference 10 CFR Section i I l 50.59)? l l 1 1 I 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- 1 I l ting proposed licensing action l ---------------- l l and succortino information. I l i l I l 6. Important licensing considera- 1 I 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 1 l cnanges in fuel design, new l l l operating procedures. l l l l l l 7. The numtt>:' of fuel assemblies l l l (a) in t e core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) 0 spent fuel elements l

REFUELING INFORMATION (CONTINUED)

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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 l4 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 I l assuming the present licensed l Colorado, and General Atomic i l capacity. l Company, and 00E.* l 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 Idahc 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, i

Public Service ~ ~ ms.,*.

Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 October 15, 1988 Fort St. Vrain Unit No. 1 P-88382 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

SEPTEMBER 1988 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for tne month of September 1988, 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, M'.ad-C. H. Fuller Manager, Nuclear Production Enclosure cc: Regional Administrator, Region IV ATTN: Mr. T. F. Westermin, Chief Projects Section B Mr. Robert Farrell l Senior Resident Inspector For*. St. Vrain

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