ML20215E316

Monthly Operating Rept for May 1987

ML20215E316
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/31/1987
From:	Novachek F, Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-87223, NUDOCS 8706190328
Download: ML20215E316 (8)

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PUBLIC SERVICE COMPANY OF COLORADO 1

FORT ST. VRAIN NUCLEAR GENERATING STATION i

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MONTHLY OPERATIONS REPORT NO. 160 ,

1 May, 1987 i

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8706190328 870531 V .

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h E. _3, 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 May, 1987.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained critical the entire month.

On May 4, 1987, at '0510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br />, during radiography of an instrument drain line, high count rates registered on tne hot reheat header activity monitors when the radiography source was exposed. The Plant Protective System initiated a Loop 2 shutdown due to the high count rate.- Loop 2 was recovered and the turbine generator was returned to service at 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br /> on May 6..

This event has been investigated and reported to the Nuclear ,

Regulatory Commission in Licensee Event Report 87-014.

On May 9, 1987, the. turbine generator was taken off line and reactor power was reduced to less than 2 percent to repair a hydraulic oil leak on the actuator for the Loop 2 feedwater flow n . control valve (FV-2206). The reactor was returned to power LJ' operation and the turbine generator was returned to service at 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br /> on May 10. l l

On May 26, 1987, at 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, 'C' helium circulator tripped on {

Loss of Bearing Water during troubleshooting of the bearing  !

cartridge differential pressure controller. A minor moisture l ingress resulted. The reactor dew point entered the 90-Day '

Limited Acceptable region of the LCO 4.2.11 curve at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, and peaked at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />. Moisture returned to the Acceptable region of LCO 4.2.11 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on May 27.

Work on CN-2646, replacement of the five valve manifold for FT-2210, has been completed to allow operation above 30% reactor power.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None ,

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL I EXAMINATIONS ]

. None j

l 4.0 MONTHLY OPERATING DATA REPORT

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Attadrrnt-JS Issue 2 Pcge I sf 1 OPERATINC DATA REPORT DOCKET ra. 50-267 DATE June 15, 1987 1- COMPLETED BY F. J. Novachek TELEPHONE (303) 620-1007 CPERATINC STAT'JS

. NOTES

1. Unit Names Fort St. Vrain. Unit No. 1

2. Reporting Period: 870501 through 870531

3. Licensed Thermal Power (Wt): 842

4. Nameplate Rating (Cross We): 342

5. Design Electrical Rating (Net We): 330

6. Maximum Dependable Capacity (Gross We): 342

7. Maximius Dependable Capacity (Net We): 330

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

1 None

9. Power Level To Which Restricted, If Any (Net We): 115.5

10. Reasons for Restrictions, If Any: Per commitment to the Nuclear Reculatory Commission.

do not operate above 357. until approved by the NRC.

This Month Year to Date Cumulative

11. Hours in Reporting Period 744 3.623 69.408

12. Number of Bours Reactor Was Critical 744.0 1.069.5 31.607.3

13. Reactor Reserve Shutdown Eours 0.0 0.0 0.0

14. nours cenerator on-Line 647.4 649.9 20.205.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Energy cenerated (WH) 164.842.3 179.860.6 10.445.260.4

17. cross Electrical Energy cenerated (WH) 50.635.0 50.778.0 3.384.774.0

18. Net Electrical Energy cenerated (WE) 45.787.0 35.854.0 2.984.134.0

19. Unit Service Factor 87.0 17.9 29.1

20. Unit Availability Factor 87.0 17.9 29.1

21. Unit Capacity Tactor (Using HDC Net) 18.6 3.0 13.0

22. Unit capacity Tactor (Using DER Net) 18.6 3.0 13.0

23. Unit Forced Outage Rate 13.0 82.1 63.8 24 Shutdowns Scheduled over Next 6 K>nths (Type, Date, and Duration of Each): Licensed coerator

.trnining startupn. 871001. 168 hourn.

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

26. Units In Test Status (Prior to Cornercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELEGCIIT N/A N/A ._

COMMERCIAL OFERATICN N/A N/A

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' AVERAGE DAILY UNIT PO';!ER LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1

- Date June 15, 1987 Completed By F. J. Novachek Telephone (303) 620-1007 Month MAY DAY AVERAGE DAILY POWER LEVEL -DAY AVERAGE DAILY POWER LEVEL' (MWe-Net) (MWe-Net) 1 61.6 17 -76.6 2- 63.1 18 79.3 3 67.5 19 74.9 4 8.3 20 77.1 5 0.0 21 77.5 i

6 2.8 22 77.6-7 64.6 23 75.8

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8 68.4 24 -

76.6 9 11.0 25 80.1 10 '14.9 26 71.8 11 63.8 27 73.7 12 67.2 28 78.0 13 66.6 29 72.4 14 67.9 30 74.5~

15 69.4 31 79.7 16 73.5

• Generator on line but no net generation.

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- REFUELING INFORMATION ]

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l-l 1. Name of Facility l Fort St. Vrain Unit No. 1 l L l- l I l l l 2. Scheduled date for next refueling shutdown.

l I November 1, 1988 l l 1 .

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!j l January 31, 1989 l

'l 3. Scheduled date for restart following refueling. l l k l l h l

l t j 4. Will refueling or resumption ofl No l 9

l l operation thereafter require a l j l

technical specifi.ation c change l l '

l l or other license amendment? '

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If answer is yes, what, in l ---------------- l l

l general, will these be? l l

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If answer is no, has the reload l l

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fuel design and core configura-l tion been reviewed by your l l

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Plant Safety Review Committee l No l

to determine whether any unre- l l viewed safety questions are l l

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associated with the core reloadj l l

(Reference 10 CFR Section l l l l 50.59)? I '

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1 l l If no such review has taken l 1987 place, when is it scheduled? l l l l l l 5. Scheduled date(s) for submit- l 'l l ting proposed licensing action l ----------------

l and supporting information. l l 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 fuel design or supplier, unre- l ---------------- l l

l viewed design or performance l l analysis methods, significant l l l

l changes in fuel design, new l l

l operating procedures. l l

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l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l a)I 1482 HTGR b) 0 spent fuel fuel elements elements l l spent fuel storage pool.

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, . . l1 I -REFUELING INFORMATION (CONTINUED)

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- l 8. The present licensed spent fuell l

l , pool storage capacity and the 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 1 has been requested or is I (approximately 500 HTGR_ elements).l l '

planned, in number of fuel l No change is planned. 9k l l

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l assemblies. I l l l . -

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

' refueling that can be dis- l and DE-SC07-791001370 between. -l  ;

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charged to the spent fuel pool l Public Service Company of l l

assuming the present licensed l Colorado, and General Atomic l capacity. I Company, and DOE.* l l

• 'The 1992 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 1992.

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16805 WCR 19 1/2, Platteville, Colorado 80651

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June 15, 1987 Fort St. Vrain Unit No. 1  !

P-87223 i

U. S. Nuclear Regulatory Commission i

-ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

MONTHLY OPERATIONS REPORT FOR MAY, 1987-

REFERENCE:

Facility Operating License No. DPR-34 ,

l

Dear Sir:

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

i:

If you have any questions, please contact Mr. M. H. Holmes at (303) 480-6960.

Sincerely, f0 & lllitivs, ] ( kf <f R. O. Williams, Jr. i Vice President, Nuclear Operations J

)

Enclosure cc: Mr. J. E. Gag'liardo U.S. NRC, Region IV R0W:djm 4