ML20082U775

Monthly Operating Rept for Nov 1983

ML20082U775
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/30/1983
From:	Fuller C, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-83400, NUDOCS 8312190174
Download: ML20082U775 (8)

Text

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r public servlee company of? cch ade i VA 16805 Road 19 1/2, Platteville, Colorado 80651-9298 December 13, 1983 Fort St. Vrain Unit No. 1 P-83400 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Facility Operating License No. DPR-34 Docket No. 50-267

Dear Sir:

Enclosed please find our Monthly Dperations Report for the month of November, 1983.

Very truly yours, Oos (N..n 6.rsy & MN?mAA l Don Warembourg l

"anager, Nuclear Production DW/djm Enclosure cc: Mr. John T. Collins 8312190174 831130 PDR ADOCK 05000267 R PDR f 6 28/

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L I MONTHLY OPERATIONS REPORT NO. 118 Noye.mber, 1983 l

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9 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 DPR-34. This report is for the month of November, 1983.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The plant was shutdown the first several days of November due to a reactor scram on October 29. The shutdown time was utilized to repair the "1B" electric driven feedpump discharge control valve, tighten marmon flange bolts, perform the " Loss of Outside Electrical Power" surveillance, and perform miscellaneous valve repairs.

The reactor was taken critical on November 3, and the generator placed in service on November 7. Power was raised to 70%

between November 7 and November 13 and remained steady throughout the month, except for a short term runback on November 22, which was the direct result of surveillance testing.

"1C" boiler feedpump has continued to be a problem. The pump seized during turning gear operation. We have determined that pump alignment changes when piping temperatures change.

Manufacturers representatives are investigating the problem k[E:. history of this pump. Several things have and are being done in an attempt to return the pump to service.

Gas waste compressor 1A and IB were rebuilt due to pumping problems. They are presently working satisfactorily.

The Auxiliary Cooling Method (ACM) diesel supercharger blower became inoperable, and the ACM bectne a possible ;butdawn item.

A spare blower was located and the ACM was repaired and returned to service.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE l , ,

• r None l 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL l EXAMINATIONS

None l

4.0 MONTHLY OPERATING DATA REPORT

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TSP- 3 Att a ch:wn t-35 Issue 2 50-267

' ' I 'I 9EraTIN: DATA nrPORT DOCKET No.

exyg December 12, 1983 Cor:rLETED BY Chuck Fuller m EraoNE (303)785-2224 CPreATING STATUS soTEs

1. Unit Name: Fort St. Vrafn

2. Reporting Period: 831101 thru 831130

3. Licensed Thermal Power (Wt): 842

4. Nameplate Rating (Cross We): 342

5. Design Electrical Rating (Net We): 330

6. P.aximua Dependable Capacity (Cross We): 342

7. Maximua Dependable Capacity (Net We): 330

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

None

9. Power Level To Which Rastricted. If Any (Not We): 231

10. Reasons for Restrictions. If Any: Restriction to 70% pending resolution of ,

contractual matters.

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Ihis Pbath Year to Date Cumulative

11. Hours in Reporting Period 720 8,016 38,737

12. Nuader of nours Reactor was Critics 1 666.0 5,377.0 25,123.7

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13. Reactor Reserve shutdown sours 0.0 0.0 0.0

14. nours Generator on-Line _

533.0 3,957.1 17,131.6

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (W H) 314,465.8 2,183,434.1 9,124,419.5*

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17. Cross Elaetrical Energ- Generated (W u) 100,999 696,083 3,022,987 j

18. Net Electrical Energy Generated (WR) 93,334 626,197 2,749,307 l

19. Unit Service Factor 76.8 49.4 44.2

20. thit Availability Factor 76.8 49.4 44.2

21. Unit Capacity Tactor (Using }:DC Net) 39.3 23.7 21.5

22. thit Capacity Tactor (Using DER Net) 39.3 23.7 21.5 l

! 23. Lhit Torced Ducase Rate 23.2 50.6 40.7 l

! 24. Shutdowns Scheduled over Next 6 Months (Type, Date, and Duration of Each): Refueline 1-15-84 through 4-13-84, 2,160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br />.

25. If Shut Down at End of Report Period. Estimated Date of Startup: N/A

26. Units In Test Status (Prior to Commercial Opt stion): Forecast Achieved m TIAL CRITICALITY N/A , , ,

N/A INITIA1. ELECTRICm N/A N/A Co:ezRCIAL OPERATION N/A N/A

• Includes a +7.5 E.F.P.D. Cycle 3 burnup adjustment.

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. Aceschnene-3A AVERAGE DAILY IMIT POWER LEVEL Issue 2 Docket No. 50-267 Unic Fort St. Vrain _

Date December 12, 1983 Completed By Chuck Fuller Telephone (303)?SS-2224 Month November, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

(We-Net) (We-Ne t) 1 0.0 17 192.4 2 0.0 18 192.1 3 0.0 19 192.0 4 0.0 20 186.8 5 0.0 21 191.0 6 0.0 22 178.6 7 0.0 23 188.3 8 51.3 24 188.8 9 54.6 25 188.7 10 ,

123.3 26 188.9 11 145.9 27 188.5 12 166.0 28 188.1 l 13, 184 8 29 187.9 i

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! 15 192.5 31 N/A

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A REFUELING INFORMATION I I I l 1. Name of Facility I Fort St. Vrain Unit No. 1 l l l l l 2. -Scheduled date for next l January 15, 1984 l l refueling shutdown. l l l l l l 3. Scheduled date for restart  ! April 14, 1984 l l following refueling. l l l l l l4 Will refueling or resumption ofl l l operation thereafter require a l l l technical specification change l l l or other license amendment? I Yes l l l l l If answer is yes, what, in l l l general, will these be? I Use of type H-451 graphite. l l l l l If~ answer is no, has the reload l l l fuel design and core configura-l l l tion been reviewed by your l l l Plant Safety Review Committee l --------------------- 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)? I l l l l l If no such review has taken l --------------------- l l place, when is it scheduled? l l l l l l 5. Scheduled date(s) for submit- l l l ting p.roposed licensing action l Not scheduled at this time; l l and supporting information. I to be determined. 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 ue l de s i g n or s upp l i e r , un ra- 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 l l (a) in the core and (b) in the l 1482 HTGR fuel elements. l l spent fuel storage pool. I 11 Spent HTGR fuel elements. l i

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REFUELING INFORMATION (CONTINUED) i l l l 8. The present licensed spent fuell l l pool storage capacity and the l l l sire of any increase in l Capacity is limited in size to l l licensed storage capacity that I 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 1992 under Agreements AT(04-3)-6331 l refueling that can be dis- l and DE-SC07-79ID01370 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

• The 1992 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 accomodate' eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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