ML20095D734

Monthly Operating Rept for Jul 1984

ML20095D734
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/31/1984
From:	Fuller C PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20095D733	List: ML20095D730 ML20095D734 ML20095D739
References
126, NUDOCS 8408230457
Download: ML20095D734 (8)

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

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MONTHLY OPERATIONS REPORT NO. 126 July, 1984 b

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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 DPR-34. This report is for the month of July, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor has renained shutdown for the entire month of July for inspection and refurbishmbnt of the six control rod drives which failed to automatically insert on June 23, 1984, and two others which successfully inserted. As of August 1, three control rod drives have been inspected and returned to the core.

Inspection is continuing on the remaining control rod drives.

The main turbine generator has been balanced and is operating on the turning gear while blanketed with carbon dioxide.

The hot reheat Marmon flanges on B-2-5 and B-1-3 steam generator .

modules have been replaced with spool pieces, heat treated, and returned to service.

On July 7 and 8, 1984, a concentrated effort, by many plant personnel, was made to clean the plant as part of the overall housekeeping effort.

Numerous Nuclear Regulatory Commission (NRC) personnel were on site during the week of July 9, to audit and analyze Fort St.

Vrain operations. Also, during the same week, Nuclear Regulatory Commission personnel administered oral requalification examinations to six plant persons. All involved personnel passed the Nuclear Regulatory Commission administered exams.

Segment 3 spent fuel shipping commenced this month.

To date, approximately 232 gallons of water have been removed from the primary coolant system.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None.

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-' 3.0 INDICATION OF ' FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATION None.

4.0 MONTHLY OPERATING DATA REPORT Attached.

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- OPERA *ING DATA RIPOltT DOCKET No. 50-267 DATE August 13, 1984 _

COMPLETED BY Chuck Fuller

, TELEPn0NE (303) 785-2224 OPERATING STATUS NOTES 1.' Unit Name: Fort St. Vrain .

2. Reporting Period: 840701 through 840731

3. Licensed Thermal Power (Wt): 842

4. Nameplate Rating (Gross We): 342

5. Design Electrical Rating Olet We): 330

6. Maximum Dependable Capaci y (Gross We): 342

7. Maximum Dependable Capacity (Not We): 330 l

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

None

9. Power Level To Which Restricted. If Any (Net We): 280

10. Raasons for Restrictions, If Any: Per commitment to tne NRC, long term operation above 85% power is pending completion of the B-0 Startup Testing.

I 1his tenrth Year to Date C ualative

11. sours in Reportsas Period 744 5,111 44,592

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, 12. Number of Hours Reactor Was Critical 0.0 1,324.1 27,151.4 l

13. Raaetor Reserve Shutdown sours 0.0 0.0 0.0

14. nours cenerator On-Line 0.0 660.1 18,463.3 f

15. Unit Reserve Shutdown soure 0.0 .0.0 0.0

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l 16. cross Thermal Energy cenerated (W s) 0.0 340,407.9 9,861,725.3 l 17. Cross Electrical Energy Generated Osrd) 0 95,144 3,248,594 4

i 18. Net Electrical Energy Generated (WE) -3,637 70,361 2,941,888

, 19. Unit S'ervice Factor 0.0 12.9 41.4

20. Unit Availability Tactor 0.0 12.9 41.4

21. Unit Capacity Factor (Using MDC Net) 0.0 4.2 20.0

22. Unit Capacity Factor (Using DER Net) 0.0 4.2 20.0 1

23. Unit Forced Outage Rate 100.0 59.7 40.6

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): 8-1-84 through 11-1-84, 2208 hours0.0256 days <br />0.613 hours <br />0.00365 weeks <br />8.40144e-4 months <br />, Control Rod Investigation

25. If Shut Down at End of Report Period. Estimated Date of Startup: 11-1-84

26. Units In Test Status (Prior to Consnercial Operation): Torecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A' N/A f COMMERCtAL OPERATION N/A N/A

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Attechment-3A AVERAGE DAILY UNIT POWER LEVEL Ia m 2 Peg 21 of 1 Docket No. 50-267 Unit . Fort St. Vrain Date August 13, 1984 Completed By Chuck Fuller Telephone (303) 785-2224 Month July, 1984 .

- DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

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(MWe-Net) (MWe-Net) 1 0.0 17 0.0 2 0'. 0 18 0.0

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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 i 9 0.0 25 0.0 10 0.0 26 0.0 4

11 0.0 27 0.0 12 0.0 28 0.0

, 13 0.0 29 0.0 i 14 0.0 30 0.0 15 0.0 31 0.0 1

16 0.0

• Generator on line but no net generation.

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REFUELING INFORMATION -

l l l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l 4th_ Refueling: l l refueling shutdown. 1 February 1, 1986 l l l l l 3. Scheduled date for restart '

l May 1, 1986 l l following refueling. l l l l l l 4. Will refueling or resumption ofl No l l operation thereafter require a l l l technicr1 specification change l l l or other license amendment? l l l l l l If answer is yes, what, in l ---------------- l l general, will these be? l l l 1 l '

l If answer is no, has the reload l l l fuel design and core configura-1 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

l l (Reference 10 CFR Section l l l 50.59)? l l l l l l If no such review has taken l 1985 l l place, when is it scheduled? l l 1 l l l

l 5. Scheduled date(s) for submit- l l l ting proposed itcensing action l ---------------- l l l and supporting information. l l l l l l l 6. Important licensing considera- l l l

l 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 l l changes in fuel design, new l l l operating procedures. l l I l l l 7. The number of fuel assemblies l l i

l (a) in the core and (b) in t.he l 1482 HTGR fuel elements l l spent fuel storage pool. l 245 spent fuel elements l l

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' REFUELING INFORMATION (CONTINUED)

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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 l planned, in number of fuel -l No change is planned. l l assemblies. l l

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, - l 9. The projected date of the last l 1992 under Agreements AT(04-3)-633l 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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