ML19323G102

Monthly Operating Rept for Mar 1980

ML19323G102
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/02/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19323G096	List: ML19323G095 ML19323G102
References
NUDOCS 8005300391
Download: ML19323G102 (8)

Text

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O PUBLIC SERVICE COMPANY OF COLORADO MRT ST. VRAIN NUCLEAR GENERATING STATION f

MONTHLY OPERATIONS REPORT NO. 75 MARG, 1980 e

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This report contains the highlights of the Fort St. Vrain, Unit No.1 activi-ties, operated under the provisions of the Nuclear Regulatory Commission Oper-ating License, DPR-34. This report is for the month of March,1980.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary At the beginning of this period, preparations were made for plant startup. On March 5,1980, at 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />, the turbine generator was synchronized and the electric load increased to eighty mega-watts. On March 6, 1980, the turbine generator actual overspeed tests were performed. The unit was resynchronized after the test, and the electrical load was increased to one hundred megawatts.

Excessive oxidant contuninants in the primary coolant helium, as well as various control system problems caused the electrical load capability to be somewhat variable over the next several days of operation.

1.2 Operations Early in the morning of March 11, 1980, the east side return water distribution header on the main cooling tower ruptured. Large amounts of circulatirg water spilled over the distribution box near the rup-ture onto the ground. The yard drainage system in this area did not have the capatility to handle this quantity of water, resulting in the water leve'. in the surrounding area to reach a depth of several inches . Some c f this water entered the manhole containing cables and associated conduits for the circulating water pump system. This water damaged JeD3ral electrical motors of the Circulating system.

The main turbine gecerator was tripped and the reactor scrammed when it was evident that condenser vacuum could not be maintained.

Repairs were made and the reactor was brought critical again on the same day, but because of the damage to the circulating water pumps and the loss of acceptable feedwater chemistry, reactor power could not be increased above two percent until March 15, 1980.

On March 16, 1980, the " number two" auxiliary boiler tripped off the line from undetermined causes. During the attempt to start " number one" auxiliary boiler, some boiler tubes were damaged due to low water level in the drum which rendered " number one" boiler inoperable. .

" Number two" boiler was repaired and restarted after this occurrence.

The turbine generator was synchronized on March 16, 1980, and load was gradeally increased to two hundred thirty megawatts on May 18

. and remained at that level until May 21, 1980.

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, The reactor scrammed and Loop 2 shutdown due to an upset of the Plant Protective System on March 21, 1980. It remained shutdown until March 23 until some repairs were made. Low power operation continued until March 25, awaiting cleanup of secondary coolant.

On March 26, 1980, the turbine generator was synchronized and elec-tric load increased to two hundred twenty-five megawatts.

A leaking "B" circulator steam piping flange caused reactor power to be lowered to fifty percent on March 26. Vhile "B" circulator was off, "A" circulator buffer seal malfunctioned. The "A" circu-lator and Loop 1 were shutdown manually and reactor power decreased to two percent. "A" and "B" circulators were restored to service and Loop 1 was recovered on March 29. Reactor power was increased to forty-five percent, and the turbine generator loaded to one hun-dred forty megawatts electrical.

1.3 Testing Testing completed during the month of March,1980, was the normally scheduled Surveillance Tests.

2.0 SINGLE RELEASES OF RADIOACTIVITY 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 4.0 MONTHLY OPERATING DATA REPORT Attached l

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CFEaAT!3C dan RzPot! DOCErr 30. 50-267 Darz 800402 court.r:zo sr J. W. Gahm TEz.zrsosz (303) 785-2253 OPEIATING STATUS

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1. Unit same: Fort St. Vrain #1

2. Reporting rectod: 800301 through 800331 1

3. \

f.icensed Ihermal Power Otit): 842 j

4. Nameplate Rating (Gross We): 342

3. Desian nectrical natins Olet We): 330

6. %w- DepenAmhle Capacity (Gross We): 342

7. WM- Dependable Capacity Olet We): 330 ,

S. If changes Occur in Capacity Eatinge (%tene Nueber 3 Ihrough 7) Since I.aet Report, Give Reasone:

None l

9. Power f.evel To '.ihich teatricted. If Any Clet We): 231 l

10. Reasone for aestrictione If Any: Nuclear Regulatorv Commission restriction 70% oending resolution of temperature fluctuations.

Ihis Month Year to Data Cusulative _

11. sours in asporting Period 744 2,184 6,601

12. s=her of sours saector '.rae Critical 676.1 863.9 3,396.7*

13. mascear asser, shutdown soure 0.0 0.0 0.0

14. sours cenerator on-r.ine 358.0 358.0 1,340.2

13. Cait asserve shutdown soure 0.0 0.0 0.0

16. Cross Ihermal Energy Generated (WR) 157.856 161.149 639,104

17. Groes nectrical Energy Generated Osts) 48.427 _ 48,427 189,223 is. set nectrical Enerzr enerated c Os#5) 43.047 43,047 166,631

19. Unit service Factor 48.1 16.4 20.3

0. t:mit Availahtlity ractor 48.1 16.4 20.3

21. cait Capecity ractor (Using MDC Net) 17.5 6.0 7.6 -

. cnit Capacity rector (cains DER Net) 17.5 6.0 7.6

23. this Forced outage sate .

51.6 51.6 62.3

24. Shutdowne Scheduled Over Next 6 2nthe (Type, D.te, and Duration of Each): N/A

23. If Shut Down at End of asport Period, Estlasted Date of Startup: N/A

26. Unite In Test Status (Prior to Coseeercial Operation): Forecast Achieved IsI :AI. CRITICAZ.I r N/A ,

N/A IIITIAr. II.zC:1ICIIT N/A ,

N/A oporremr. OPEaATION N/A N/A

• This,,, number is _ corre3t. The Janumr.r 84 e.,r. 4, u,a 12 shoul R@

r i IINlT Stilin0MNS AND FWER NEllllClutiS

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nCEET tu. 50-267 U' 1 i

UNIT NAME Fort St. Vrain #1 I

DATE 800402 courl.ETED Ry J. W. Gahm  ;  ;

REroaf HoNTis Ma rch, 1980 TEl.ErnoNE (303) 785-2253 l,. ,

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I HETHOD OF  ;

Sil FITING  !

IX4RI SYSTEH C0te'UNENT f NO. _DATE 1TFE DUMATION REASON RE*CToR I.ER # CODE Q)DE CAUSE AND CORRECTIVE ACTION to PREVENT NECURRENCE 79-14 791026 S 98.8 B N/A N/A_ N/A _ Scheduled shutdown continued for '

replacement of ruptured static seal.

Refer to LER 80-001/01-T-0. Generator put on line 3-5-80 80-01 800306 S 4.15 B N/A N/A N/A N/A Turbine over-speed trip test.

• 80-02 800311 F 123.8 A 2 N/A N/A N/A Circulating water system 41 shut down due to tower problems. -

i 80-03 800321 F 56.8 A 3 N/A , N/A N/A Reactor scrammed due to instrument  ! ,

problems.  !

80-04 800324 F 49.25 A 2 N/A N/A N/A Loss of conden.ser vacuum.

80-05 800328 F 53.2 A N/A N/A N/A N/A 1A circultator trip and system upset.

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I SlalMARY; Plan to continue operations at 70% power. , f' i

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AVERAGE DAILY CNIT POWER LEVEL Docket No. 50-267

., Unic Fort St. Vrain #1 Date 800402 Completed By J. W. Gahm i I

Telephone (303) 785-2253 l Month March, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net) i 1 0 17 124

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2 0 18 213 3 0 19 217 4 0 20 207 5 45 21 129 6 66 22 0 -

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94 0 23 8 87 24 0 -

9 92 25 0 -

10 , 132 26 83 11 16 27 151 12 0 28 47 13 0 29 0 14 0 30 23 15 0 127 31 16 33

• Generator on line but no' net generation,

REFUELING INFORPATION -

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

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2. Scheduled date for next refueling shutdown. January 1,1981

3. Scheduled date for restart following refueling. March 1, 1981 s 1

4. Will refueling or resumption of oparation 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 The Plant Operations Review Committee will fuel design and core configura- review any questions associated with the cion been reviewed by your Plant core reload.

Safsty Review Committee to deter-mine whether any unreviewed safety questions are associated with the core reload (Reference 10C7R Section 50.59)?

If no such review has taken olace, when is it scheduled? July 1, 1980

5.  !:heduled date(s) for submitting proposed licensing action and supoorting information.

6. Important licensing considera- -

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 a) 1482 HTGR fuel elements.

(a) in the core and (b) in the spent fuel storage cool. b) 244 spent HTGR fuel elements.

8. The present licensed spent fuel Capacity is limited in size to about one-pool storage capacity and the third of core (app 6ximately 500 HTGR size of any increase in licensed elementa). No change is planned.

storage capacity that has been '

requested or is planned, in number of fuel assemblies.

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w REFUELING INFORMATION (_ CONTINUED) s 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 capacity.

• 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 National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP) . The storage capacity has evidently been sized to accomodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

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