ML20076L665

Monthly Operating Rept for Aug 1983

ML20076L665
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/09/1983
From:	Fuller C, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-83302, NUDOCS 8309190023
Download: ML20076L665 (9)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NL' CLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 115 August, 1983 e

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1- l 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 . l the month of August, 1983.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE Reactor power has been at 70% for most of August. The plant has restonded very well to several transients which has allowed the reactor to remain critical for the entire month of August.

Severai events had an effect on plant operation during August.

. . The flow control valve on the discharge of the electric driven feedpump is not allowing flow. Estensive trouble shooting did not disclose the problem, and the valve can not be isolated for removal. Therefore, the main discharge valve has been opened and all transients are being followed by the steam driven feedpumps.

One of the two steam driven feedpumps became inoperable and had to be repaired. This repair took almost four weeks. This limited our capability to near 68% power.

- Attempting to resolve a reheat intercept valve problem caused a N severe transient and load reduction. The plant operators were able to control the problems and prevent a plant trip.

Extensive repairs were required on the helium purification regeneration system. The repairs were completed and the

purification train was satisfactorily regenerated.

On August 18, the turbine tripped on loss of-the EHC unit.

Reactor power was effectively reduced. The loss of the EHC unit was due to a relay dropout in the EHC control system. The relay was replaced and the turbine was resynchronized after nine hours. A review of this transient and system respon:;o is being performed.

On August 24, a controller failure in the back-up bearing water circuit caused a "1A" helium circulator trip. The resulting bearing water / buffer helium transient did not cause any priaary coolant moisture problems. The circulator was recovered and power returned to normal. The controller failure was traced to a monitoring computer that was disrupting the controller measured signal.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS e OF 10% OF THE ALLOWABLE ANNUAL VALUE 3

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None J

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3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 6

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Attscheent-38 Isaus 2 Page 1 of 1 50-267

. OPERATING DATA REPORT DOCKET NO.

DATE September 9. 1983 COMPLETED BY C. H. Fuller TELEPHON" (303) 785-2224 OPERATING STATUS soTEs

1. Unit Name: Fort St. Vrain

2. Reporting Period: 830801 thru 830831

3. Licensed Thermal Power (Wt): 842

4. Nameplate Rating (Cross We): 342

5. Design Electrical Rating (Net We): 330

6. Na=1== Dependable Capacity (Gross We): 342

7. Pa=4== Dependable Capacity Clet W=): ,

330

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

None

-9. Power Level To Which Restricted If Any (Net We): 231

10. Reasons for Restrictions, If Any: Restriction to 70% pendina resolution of contractural matters.

This Month Year to Date- Cumulative

11. Hours in Reporting Period' 744 5,831 36,552

12. Number of sours Raaetor um Critical 744.0 3.308.0 23.054.7

13. Reactor asserve Shutdown acurs 0.0' O.0 0.0 14.- sours cenerator on-Line 735.0 2.001.2 15.175.7

15. vatt Reserve Shutdown sours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (WR) 408.158.5 1.064.697.3 7.854.122.7

17. - Cross Electrical Energy Generated (WR) 140.498 315.643 2.642.547

. ls. Net E1.etrical snergy cenerated (Wu) 131,724 270,302 2,393,412-

19. Unit Service Factor 98.8 34.3 41.5

20. Unic Availability Factor 98.8 34.3 41.5

1. Unit Capacity ractor (using MDC Net) 53.6 14.0 19. g_

22. Unit ' Capacity Tactor (Using DER Net) 53.6 14.0 19.8

23. Unit Forced Outase ante 1.2 65.7 43.2

24. Shutdowns Scheduled Over Next 6 Months (Type.. Data, and Duration of Each): Refueling -

February 1, 1983 thru May 1, 1983

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

26. Units In Test Status (Prior to Cosmarcial Operation): Torecast Achieved INITIAL CRITICAL m N/A N/A INITIAL ELECTRIC m N/A N/A amHERCIAL CPERATIoN N/A N/A

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. TSP-3 Acccchment-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2

. ,Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date September 9, 1983 Completed By C. H. Fuller Telephone (303) 785-2224 Month August, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL., ,

(MWe-Net) (MWe-Net) 1 151.3 17 186.4 2 139.7- 18 183.0 3 166.4 19 112.4 4 169.9 20 199.2 5 188.9 21 198.8 .

.6 187.9 22 186.8 ,

7 187.6 23 186.5 8 187.4 24 146.6 9 189.5 25 177.6 10- 186.1 26 177.7 11 182.3 27 160.6 12 182.8 28 189.3 l

13 182.8 29 188.4 f

I 14 182.7 30 188.2 l

l 15 180.0 31 189.8 l

i 16 186.1

• Generator on line but no net generation.

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1SP-1 At talieemt-3C Issue 2 4

UNIT SHUTIM1WNS AND POWER RFDUC1DNS

- . _ DocEET No, 50-267

-UNIT NAME Fort St. Vrain DATE September 9, 1983 CotFLETED BY C. H. Fuller 5

REroRT tawn August, 1983 TELErnoNE (303) 785-2224

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l METHODII[

SHUTTING DOWN SYSTEM Cutt 0NENT No. DATE TYPE DURATION REASON REACTOR LER I CODE 0)DE CAUSE AND CORRECTIVE ACTION TO PREVENT RFEURRENCE 83- 830818 F 9 H 4 N/A HBD INSTRU Turbine trip due to lo'ss of electro-013 hydraulic control power. Reactor remained critical.

83- 830824 F 11 H 4 N/A CBI BLOWER Power reduction caused by A circulator 014 trip due to seal malfunction. Turbine generator remained on line.

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! 83- 830827 F 9 H 4 N/A CBI BLOWER Power reduction to recover back up 015 bearing water on Loop I. Turbine generator remained on line.

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• a, REFUELING INFORMATION

1. Name ' of Facility. Fort St. Vrain Unit No. 1

2. Scheduled date for next- refueling. February 1, 1983 shutdown. -

3. Scheduled date for restart May 1, 1983 following refueling.

4. Will refueling or resumption of operation thereafter require a -

technical specification change or other license amendment? Yes If answer is yes, what, in general, will these be? Use of type H-451 graphite.

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to deter- ~~

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mine whether any unreviewed safety questions are associated with the core reload (Reference 10CFR Section 50.59)?

If no such review has taken _______________

place, when is it scheduled?

5. ' Scheduled date(s) for submitting proposed licensing action and Not scheduled at this time; supporting information. to be determined.

6. Important licensing considera-l tions associated with refueling, e.g., new or different fuel de- -

sign or supplier, unreviewed - - - - - - - --

design or performance analysis methods, significant changes in fuel design, new operating pro-cedures.

7. The number of fuel assemblies 1482 HTGR fuel elements.

(a) in the core and (b) in .

the spent fuel storage pool. 11 spent HTGR fuel elements

8. The present licensed spent fuel pool storage capacity and the Capacity is limited in size to about one-size of any increase in licensed third of core (approximately 500 HTGR storage capacity that has been requested or is planned, in elements). No change is planned.

number of fuel assemblies.

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, s REFUELING INFOR&iTION (CONTINUED) i

9. The projected date of the ' 1992 under Agreements AT(04-3)-633 and last refueling that can be DE-SC07-791D01370 between Public-Service discharged to the spent fuel i Company of Colorado, General Atomic pool assuming the present l Company,andDOE.*

licensed capacity. I

• 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

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eighth fuel segment will be discharged in 1992.

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r public Service Company of C@ endo 16805 Road 19 1/2, Platteville, Colorado 80651-9298 Septemb,er 13, 1983 Fort St. Vrain Unit No. 1 P-83302 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

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

Dear Sir:

Enclosed please find our Monthly Operations Report for the month of August, 1983.

Very truly yours, h WWI Don Warembourg Manager, Nuclear oduction DW/djm Enclosure cc: Mr. John T. Collins O

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