ML20076H128

Monthly Operating Rept for May 1983

ML20076H128
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/09/1983
From:	Fuller C, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-83216, NUDOCS 8306160434
Download: ML20076H128 (10)

Text

t PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 112 May, 1983 l

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8306160434 830609

[M ADDCM 05000267 j

PM

O 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, 1983.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE Mechanical

repairs, Nuclear Regulatory Commission (NRC)

Licensing examinations, annual requalification examinations and plant startups were the principal items of concern during May, 1983. The following activities occurred during May:

The electric driven boiler feed pump repair was completed and the pump was satisfactorily tested. The pump testing included pressure and flow verification and vibration evaluation.

The IB condensate pump impeller shaft was received, machined and installed. The pump was returned to service and tested for performance and vibration. All testing was satisfactory.

A Loop I bearing water pump was installed. This new pump is part of a continuing changeout process to increase the capability of our bearing water pumps. The pump satisfactorily passed all test requirements. The old volute was sent to Goulds

Pumps, Inc.,

to be machined and returned for the next bearing water pump to be upgraded.

Four of the six pumps have been completed.

Investigation on the core-support floor continue to evaluate vent system capacity, gas waste system capacity and operational characteristics.

The final report has not been written, but should be completed in the immediate future.

Helium Circulator ID internal piping was installed and passed the leak check requirements.

It was then insulated, external piping replaced, and the circulator returned to service.

HV-2224, HV-22153 and PV-22129 were repaired and returned to service.

The bearing water makeup pump recycle valve (FV-21333) had to be removed from the line for repair. Site Engineering prepared a Change Notice to install manual isolations and a bypass valve around FV-21333.

FV-21333 was then removed, repaired, and returned to service without interrupting system operation.

The Results Department has installed and i.cjusted boosters on the Helium Circulator Main Drain valves.

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e The Nuclear Regulatory Commission administered both oral and written tests to the license candidates.

Formal response on the results has not been received.

The licensed operators all completed their annual requalification exams. They are presently being graded.

The May 17, 1983 snowstorm caused a loss of electric power (LDEP) at Fort St. Vrain. Due to the configuration and status of the diesel generators during the actual LOEP, two LOEP tests were subsequently performed to prove diesel generator operability.

A clearance returned on the 1A diesel generator output breaker was erroneously tested resulting in the diesel being momentarily motorized. No serious problems resulted, and a diesel load test was performed to verify generator operability.

IB diesel engine on the 1A emergency generator had a head gasket leak. The head had to be removed and maintenance performed.

The generator was then load tested to verify operability.

The reactor was brought critical on May 24, but power was restricted by moisture levels. At the end of the month, the reactor was being maintained at low power levels to continue primary coolant impurities clean-up.

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

None 1

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

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TSP-3 Attechment-35 Issue 2 OPEMTING DATA REPORT DOCKET NO.

50-267 DATE June 9. 1983 CoxetETED nT C. H. Fuller Trt.ErnoNE (303) 785-2224 CPERAn NC STATUS NOTES 1.

enit N e:

Fort St. Vrain 2.

Reporeing period:

830501 through 830531 3.

Licensed Thermal Power (Wt):

842 Nameplate Racing (Gross We):

342 5.

Design Electrical Rating (Net We):

330 6.

Maximum Dependable Capacity (Gross We): 342 7.

Maximus Dependable Capacity (Net We):

330 8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None 9.

Power Level To Vhich Restricted, If Any (Net We):

231

10. Reuons for Patrictions, If Any:

Restriction to 70% pendina resolution of contractual matters.

This Month Year to Data Cumulative

n. nours in Reporting period 744 3,623 34,344 1:. Number of nours Ructor vu Critical 175.2 1,329.1 21,075.8

13. Reactor an erve Shutdown sours 0.0 0.0 0.0 14.

nours c.narator On-une 0.0 905.0-14,079.5

15. unit Rau rve Shutdown nours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (WR) 2.660.3 466.792.5 3.445.538.3 i

17. Cross Electrical Energy Generated (WR) 0 140,814 2,467,718

18. Net nectrical Energy cenerated (wws)

-3.453 116.850 2.239.960

19. Unit Se ce Ta tor 0.0 25.0 41.0

20. cnic Avanabnity raetor 0.0 25.0 41.0

21. Unit Capacity Factor (Using HDC Net) 0.0 9.8 19.8 I

22. Unit Capacity Factor (Using DER Net) 0.0 9.8 19.8

23. Unic Forced Outage Rate 100.0 75.0 42.6

24. Shutdowns Scheduled over Nez: 6 Months (Type. Date, and Duration of Each):

830601 throuah 830621 (504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br />) for primary coolant impurities cleanup.

25.

If Shut Down at End of Report Period. Estimated Date of Startup:

830621

26. Units In Test Status (Prior to Commercial Operation):

Foracast Achieved INInAL CMnCAun N/A N/A INC*AL E.ECTUCIn N/A N/A ComC:AL orEnnoN N/A N/A

4 TSP-3 A Issue 2 AVERAGE DAILY UNIT POWER LEVEL i

Page 1 of 1 Docket No.

50-267 Unit Fort St. Vrain Date June 9. 1983 Completed By C. H. Fuller Telephone (303) 785-2224 Month May. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

. (We-Net)

(We-Ne t) 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 11 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 0.0 16 0.0 l

• Generator on line but no net generation.

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1SP-1 At t arhorn t-3C

!= sue 2 Page 1 of 1 UNIT SHUTD06NIS AND POWER RFJRICTUNS nnCERT No.

50-267

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vMiT mNE Fort St. Vrain mTE June 9, 1983 CONri.Etro nT C. H. Fuller

_(303)785-2224 REPORT N0ptrH _ % 2 E 83 TELErnoNE HE11MM) OF SNUTTINC DnWN SYSTD1 COPPONENT NO.

DATE TYPE DURATION REAS006 REACTOR I.ER #

_ CODE 0)DE CAUSE AND COR_RQEVE ACTION 19 PREVENT RECURRENCE 83-010 830501 F

744.0 B

3 N/A CBI BLOWER Shutdown continued from reactor scram on 830317 for maintenance to "D" helium circulator "B" boiler feed pump and primary coolant chemistry clean-up.

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REFUELING INFORMATION 1.

Name of Faciliev.

Fort St. Vrain Unit No. 1 2.

Scheduled date for next refueling shutdown.

February 1, 1984 3.

Scheduled date for restart following refueling.

April 1,1984 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 tvoe H-451 araphite.

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to deter-mine whether any unreviewed safety questions a?;e associated with the core reload (Reference 10CFR Section 50.59)?

If no such review has taken

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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-tions associated with refueling.

e.g., new or different fuel de-sign or supplier, unreviewed design or performance analysis me' hods, significant changes in t

fuel design, new operating pro-

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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 size of any increase in licensed Capacity is limited in size to about one-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.

REFUELING INFORMATION (CONTINUED) 9.

The projected date of the 1992 under Agreements AT(04-3)-633 and last refueling that can be DE-SC07-791001370 between Public Service discharged to the spent fuel Company of Colorado, General Atomic POO1 Assuming the present Company, and D0E.*

licensed capacitv.

• 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 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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pubile service company e cono1mdIo ve

-16805 Road 19 1/2, Platteville, Colorado 80651-9298 June 14, 1983 Fort St. Vrain Unit No. 1 P-83216 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C.

20555 j

Reference:

Facility Operating License l

No. DPR-34 Docket No. 50-267 4

Dear Sir:

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

l Very truly yours, I

Wtuu n l %

i Don Warembourg y

l Manager, Nuclear Production DW/cis Enclo:ure o

r cc:

Mr. John T. Collins 1

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MONI1tLY OPERATIONS REDORT DISTIRBUTION Number of Copies Office of Inspection and Enforcement - - - - - - - - - - - - - - - - - - - - - - 12 (Original of P Letter)

ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C.

20555 1 (P Letter)

Mr. John T. Collins, Regional Administrator Region IV Nuclear Regulatory Commiission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011 1 (P latter)

Mr. Philip C. Wagner, Project Manager Region IV Nuclear Regulatory CoWssion 611 Ryan Plaza Drive Suice 1000 Arlington, Texas 76011 Depar tmen t o f Energy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Technical Information Center P. O. Box 62 Oak Ridge. Tennessee 37P30 1 (P IAtter)

Colorado Deoartment of Health ATTN: Mr. Al Hazel 4210 East lith Avenue Denver, Colorado 80220 1 (P Letter)

Gas Cooled Reactor Associates ATTN: Mr. R. A. Evans 3344 North Torrey Pines Court Suite 300 LaJolla, California 92037 1 (P Letter)

Electric Power Research Institute ATTN: Mr. Eelvin E. Lapides 3412 Hillview Avenue P. O. Box IJ412 Palo Alto, California 94303 1 (P Letter)

INPO Records Cancer Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 Mr. Mike Dolphin - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

FSV..GA Technologies, Inc. Site Representative CA Technologies, Inc.

16864 Weld County Road 191/2 Platteville, Colorado 80651 1 (? Letter)

NRC Resident Site Inspector s

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