ML20050D417

Monthly Operating Rept for Mar 1982

ML20050D417
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/07/1982
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Office of Nuclear Reactor Regulation
References
P-82098, NUDOCS 8204120190
Download: ML20050D417 (10)

Text

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Public Service Company Cf Onbrede 16805 Road 19 1/2, Platteville, Colorado 80651-9298 VR April 7, 1932 4

Fort St. Vrain Unit No. 1 O

D P-82093 RECg;V%

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Director o' Nuclear Reactor Regulation r

ATTN:

W. P. Gammill, Chief t^

8 Operating Reactors Safeguard Branch 6

Division of Operating Reactors

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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 Operations Report for the month of March, 1932.

Very truly yours, i

W Don Warembourg

.i Manager, Nuclear Production DW/cis Enclosure l

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8204120190 820407 l

PDR ADOCK 05000267 l

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PUBLIC SERVICE COMPANY OF COLORADO 4

FORT ST. VRAIN NUCLEAR GENERATING STATION l

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MONTHLY OPERATIONS REPORT NO. 99 March, 1982 3

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1 This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated uncer the provisions of the Nuclear j

Regulatory Commission Operating License DDR-34 This report is for the month of March, 1982.

I 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary i

The loop split work was complete at the beginning of the month, but excessive moisture concentrations in the prica"y coolant required the reactor to remain shutdown.

In an effort to remove the moisture, tne prestressed concrete reactor vessel was evacuated three times using tne purge vacuum pumps and tne condenser with all circulator brakes and seals set.

At month's end, the prestressed concrete reactor vessel was still under vacuum.

The main cooling tower was drained on March 20 so that an attempt could be made to repair the circulating water pump isolation valve seating rings.

Attempts to isolate IB circulating water puma for repair had been unsuccessful with the rest of the system operating. The condenser and main cooling tower was placed back in service on March 25.

The 480 VAC essential bus was in limited service at the beginning of the month due to a faulty main breaker which was repaired and back in service on March 16.

1.2 Ocerations Removing moisture from the primary coolant has been the main thrust of the operating efforts throughout the month of March. A planned forced circulation outage was began on March 1 to facilitate evacuation of the prestressed concrete reactor vessel.

The prestressed concrete reactor vessel was repressuriced to approximately 90 psia on March 3.

and forced circulation resumed to cetermine the effects of evacuation.

Forced circulation was again stoppea on March 5, and evacuation of the vessel continued until March 14 which was the calculatec maximum length of

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time allowable without forced circulation.

After repressuricing and establishing forced circulation, the i

moisture monitors still indicated excessive moisture levels.

j Cn March 17, evacuation was again started and vacuum was j

maintained on the vessel through tne end of the month.

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i 1 A program to exercise control roc drives and orifice valves to demonstrate operacility wnicn was started in Feorua y, continued tnrough tne month of March.

On February 23, the main breaker for 480 VAC essential bus 3 failed. The breaker was pulled for repair, and the bus was sucolied from the bus 2 tie breaker requiring the loads on busses 2 and 3 to be limited.

The breaker was repaired, and the bus returned to normal on March 16.

Liquid effluents were cirected to the St. Vrain River via the slough on March 2 to make repairs to the Goosequill Ditch.

Repairs were completed March 24, and effluents were returned to the normal cischarge path.

An error in a valve lineup at the beginning of a gas waste release resulted in tne rupture of a rupture disc on the gas waste vacuum tank.

Although the gas was to be released, tne incident was consicered as an unplanned release.

18 circulating water pump lost a bearing on March 11.

Attempts to isolate the pump for repair were unsuccessful with the system operating.

On March 20, the tower was drained to repair the pump isolation valves.

Repairs were partially successful, and the system was placed cack in service on March 25. The pump repairs were not complete at the end of the month.

A review of all outstanding Change Notices is being done to determine the status of each, and to establish priorities from the perspective of plant personnel.

It is intended that the information be supplied to the Nuclear Engineering Division and that a continuous effort be made to monitor and coordinate Change Notices.

The pressure control valves have been installed on the supply oiping to both steam generator loop penetrations, which will permit operation of the steam generator penetration interspace at or slightly aoove cold reheat steam pressure. Sample piping from the penetration to the radiation monitors is not yet installed.

A new valve, HV-62249, was installed in the liquid waste effluent line downstream of the oil separator to help prevent uncontrolled releases of accumulated waste in the oil separator following a controlled release of liquid waste.

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2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS 3F

'0", OF THE ALLC'<lA3LE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FRCM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY CPERATING DATA REPORT Attacned l

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50-267 cAn April S. 1982 CoxPLI Es sr L. M. McBride trLzruost (303) 785-2224 cerumc sm*;s sotts 1.

Unit same:

Fort St. Vrain

. Reporting Period:

820301 through 820331 3.

Licensed 2ermal Power (We):

842 Nameplace Racing (Grose We):

342 5.

Oe ign tiectrical Racing (Net We):

330 6.

Maxima cependable capacity (cruse We):

342 7.

Maximes Dependable Capacity Ukt We):

110 8.

If Change. Occur in capacity Racing (Items suneer 3 3 rough 7) Since Last Report. Give Reasone None 9.

?over Levet to '.litch Restricted. If Amy ("et We):

231 N.

Reasone for Reecrictione. It Any:

NRC restriction of 70% oendincr resolueton of temperature fluctuations This N ach Year to Data Cumulative 11.

dours in Reporting Period 744.0 2.160.0 24.121

. Numeer of :iours anactor was Critical 0.0 101.9 14.680.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 0n 14.

Sours Generator on-Line 0.0 0.0 4_ong 1 i3.

Cait Reserve Shutdown Hours 0.0 0.0 0.0 it.

Grose Ther: sal Energy Generated (WH) 0.0 0.0 4.933.944.8 L7.

Crose Electrical Inergy Generated (WR) 0.0 0.0 1.691.356 u.

set tiectrical Energy cenerated (Wa)

-2.788

-7.365 1.546.894

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nic service ractor 0.0 0.0 41.1

20. Unic Availantlity ractor 0.0 0.0 a1_1

1. cnit Capacit, ractor (retag MDC Net) 0.0 0.0 19.4

. : nit Capacity rector (reing Ora set) 0.0 0.0 19.4 23.

Cait rorted outage Rate 0.0 0.0 34.0

.. shutdowns scheduled over sent 6 2nthe (Trpe. Date, and curation of Zach):

Maintenance outage - 4/1/82 to 4/15/82 (360.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) 3.

If Shut Down at Ind of Report Period. Eatinated Date of Startup:

4/2/92 26.

Unit. In Test Status (Prior to Commercial @eration):

rarecast Achieved In 7.AL CRInCAL:n N/A N/A

nnAL cLECnIC:n N/A VM CCNCIAL CPERA!:Os N/A N/A

TSP-3 Attachnent-3A 18 8 " 2 AVERAGE DAILY CIIT POWER LEVEL Page 1 of 1 Docket No.

50-267 L* nit Fort St. Vrain Date April 8, 1982 Completed 3y L. M. McBride Telephone (303) 784-2224 Month March DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER 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 3

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 23 0.0 13 0.0 29 n_o 14 0.0 30 0.0 13 0.0 31 0.0 16 0.0

• Generator on line but no net generation.

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in-- Sc. 7 1in Unt- ??c. ;

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Scheduled data for res: 3r fol!= wing sfeeld=r.

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Use of type H-451 graohite.

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e 1'7UEI.ING INFORMATICN (CONTINUED) 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 : Company of Colorado, General Atomic pool assuming the present j Company, and DOE.*

licensed capacit-r.

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• 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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