ML20009C439

Monthly Operating Rept for June 1981

ML20009C439
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/01/1981
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20009C437	List: ML20009C436 ML20009C439
References
NUDOCS 8107210054
Download: ML20009C439 (9)

Text

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 90 JUNE, 1981 5

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81072100Ni 810715 PDR ADOCK 05000267 R PDR +

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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 June,1981.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary The reactor was shutdown during the entire reporting period for main turbine generator inspection and repair, refueling, 1B helium circulator change-out, general plant outage maintenance, and surveillance requirements. -

Once each week, during the month, an unannounced fire drill was held in the Control Room with a followup critique for the swing shift personnel.

1.2 Operations Non-interruptible plant protective system instrument bus 3 tripped on June 2 from excessive temperature in the 480V Room. It was connected to interruptible bus 3 until June 26, at which time it was returned to normal inverter feed.

Severe weather conditions (high winds and tornadoes sighted in the area) on June 3 were reported to the State Division of Disaster Emergency Services.

1B helium circulator was physically removed from the prestressed concrete reactor vessel on June 4.

Region 4 refueling and control rcd drive installation were completed on June 5 and preparations for refueling region 36 began.

Various types of problems were experienced with the fuel handling machine on June 7. These problems continued to plague the fuel handling machine throughout the month.

Loop 1 was shutdown on June 9 for system component repair work and calibrations. Reactor cooling was maintained on Loop 2 via the decay heat exchanger.

On June 11, General Electric conducted ultrasonic testing on the low pressure turbine blading which revealed no problems other than the loose blocks on the 16 stage shroud.

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m Work on the main cooling tower.and basin was completed, and the circulating water system was returned to service.

On June 12, auxiliary boiler #1 was shutdown and cleared out for safety modifications. This required taking the deaerator out. of service and cycling secondary coolant flows to maintain System 46 (prestressed concrete reactor vessel liner cooling) temperatures within Technical Specification limits.

Loop 1 was returned to normal.on June 14.

IB helium circulator replacement was installed and the primary seal bolted down on June 16, with the brake and seal manually set.

Region 36 refueling was completed on June 18, and Region 4 and region 36 control rod drives were tested for operability. ,

Flushing of 1B helium circulator bearing water piping commenced on June 25.

The main turbine generator oil system was returned to service on June 26, and the turbine was placed on the turning gear to check for rubs. None were' evident.

Platteville Fire Department was called out on June 28 to extinguish a fire in a cottonwood tree next to, but outside, the exclusion area fence.

Bearing water makeup pump, P-2105, suction casing washed

i. out and was cleared out for repairs on June 29.

! On June 30, the condenser clearance was returned, vacuum was pulled, and the bypass flash tank drains were rerouted from the decay heat exchanger to the main condenser.

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 EXAMINATIONS None

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4.0 MONTHLY OPERATING DATA REPORT Attached I

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,nPERA M C OATA REPORT DOCKr! N0. 50-267 CATE 810701 COMPLZTZD SY T_. . M . McB id n l TILEPHONE (101) 785_22:%

OPERATING STATUS 30Tzt.

1. Cait Names Fort St. Vrain

2. Reporting Period: R10 An1 .h rn,,ok Ai n 6_1n

3. Licensed thermal Power Osit): 842

6. Nameplate Racing (.Groes We): 342

5. Design Electrical Racing Otet we): 330 .

6. Fa wi = = Dependable Capacity (Cross We): 342

7. *r4== Dependable Capacity Olet We): 330

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

None

9. Power Level To Which Rastricted. If Any (Net We): 211

10. Raasons for Restrictions, If Any: NRC restrictinn 70Y naadi g rounin t-4 m nf temperatura fluctuations this Mont:2-- Tear to Data Cumulative

11. dours in Reporting Period 720 4.343 17.544

12. Number of Hours Reactor Was Critical O_0  ? 665.5 11.800.7 O_O O_0 0,0

13. Reactor Reserve Shutdown Bours

14. nours cenerstar on-Line 0.0 2.131.5 7.824.8 0.0 0.0 0.0

13. Unit Reserve Shutdown Hours

16. cros Thermal Emersy cenerated (ws) 0.0 1.102.586.8 3,810.679.6

17. cross Electrical Energy cenarated cera) 0.0 400.445 1.272.239

18. Net Electrical Energy Generated (wn) 0.0 369.305 1.168.606 0.0 49.1% 44.6%

19. Unit Service Tactor

20. Unit Availmhility Factor 0.0 49.1% 44.6%

Unit Capacity Factor (Csing MDC Net) O_0 25.95 20.2%

21.

22. Unit Capacity Factor (Ceing DE1 Net) 00 25.97 20.2% .

O_0 15_95 16,og

23. Unit Forced Outage Rate

26. Shutdowns Sched:c. led over Next 6 !buths (Type, Date, and Duration of Each): Wintemnce /

modification shutcown Seutenber 1. 1981 lastine 4 months.

25. If Shut Down at End of Report Period. Escinated Date of Startup: Julv 20. 1981

" nits In Test Status (Prior to Cosearcial Operation): Forecas t Achieved 26.

INITIAL CRITICAL 1:! N/A N/A INITIAL ILECTRICITT N/A N/A C :ecLCIAL CPERA!!CN N/A N/A

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unic Fort St. Vrain Date 810701 Completed By L. M. McBride Telephone (303) 785-2224 1

Month June DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-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 8 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 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15 n_n 31 N/A 16 0.0

• Generator on line but no net generation, l

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REFUELING INFORMATION I

1. Name of Faciliev. Fort St. Vrain Unit No.1

2. Scheduled date for next refueling shutdown. May 20. 1981 (Tn orneresA i

3. Scheduled date for restart following refueling. Juiv 20- 1081

4. Will refueling or resumption of ,

operation thereafter require a technical specification change or other license amendment? No If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Saf ety Review Consmittee to deter-mine whether any unreviewed safety questions are associated with the cora reload (Reference 10CFR Section 50.59)? Yes .

If no such review has taken olace, when is it scheduled 7

5. Scheduled dace (s) for submitting l proposed licensing action and suoportina information.

6. Important licensing considera- Peripheral fuel elements changed from tions associated with refueling, thin thorium buffer to thick thorium e.g., new or different fuel de- D"fI'#*

sign or supplier, unreviewed design or performance analysis nachods, significant changes in fuel design, new operating pro-l cedures.

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

(a) in the core and (b) in b) 178 spent HTGR fuel elements.

the soent fuel storage onol.

I S. The presa : licensed spent fuel Capacity is limited in size to about one-pool storage capacity and the third of core (approximately 500 HTGR size of any increase in licensed elements). No change is planned.

storage capacity that has been requested or is planned, in

! number of fuel assemblies.

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REFUELING INFORMATION (CONTD:UED)  !

9. The projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to the spent fuel Service Company of Colorado (PSCo), and pool assuming the present General Atomic Company.*

• licensed capacitv.

• The 1986 date is based on the understanding that spent fuel discharged during the term of the Three Party Agreement will be shipped to the Idaho Na'tional Engineering Laboratory for storage by DOE at the Idaho Chemical Processing l Plant (ICPP). The storage capacity has evidently been sized to accomodate I fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement. ,

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