ML20235S531

Monthly Operating Rept for June 1987

ML20235S531
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/30/1987
From:	Novachek F, Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-87260, NUDOCS 8707210687
Download: ML20235S531 (9)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION

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MONTHLY OPERATIONS REPORT NO. I61 June, 1987 t

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8707210697 870630

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PDR ADOCK 05000267

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I 's 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,1987.

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1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE On June 12, 1987, at 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br />, a Loop 1 shutdown occurred upon moving the Interlock Sequence Switch (ISS) from " Low Power" to

" Power".

The cause of the Loop 1 shutdown was determined to be an improper grounding configuration in a contact for the Loop I hot reheat steam block valve handswitch (HS-2253). This provided the Plant Protective System with indication that the valve was closed when the ISS was placed in the " Power" position.

Following the Loop 1. shutdown, the turbine was manually tripped at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />.

Following the turbine trip, main steam was automatically diverted to the bypass flash tank, resulting in a reduction of steam available to drive the helium circulators or the turbine driven boiler feed pumps. The reactor was manually scrammed at.1431 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.444955e-4 months <br /> due to the interruption of forced circulation. The reactor was taken critical on June 15 at 0555 hours0.00642 days <br />0.154 hours <br />9.176587e-4 weeks <br />2.111775e-4 months <br />, and the -turbine generator was returned to service on C3 Juna 17 at 0222 hours0.00257 days <br />0.0617 hours <br />3.670635e-4 weeks <br />8.4471e-5 months <br />. This event w:is investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-015.

On June 17, 1987, the Nuclear Regulatory Commissioners voted 4-0 to allow Fort St. Vrain to operate at power levels above 35 percent, but not to exceed 82 percent.

On June 22, 1987, at 0913 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.473965e-4 months <br />, all even control rod drives that were withdrawn gravity scrammed approximately 20

inches, resulting in a turbine runback and trip on low main steam temperature. This event occurred while the contacts on the main scram contactors were being cleaned by a plant electrician. The scrammed control rods were returned to their previous positions and the tubine generator was returned to service at 1029 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.915345e-4 months <br />.

On June 25, 1987, at 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br />, a reactor scram was automatically initiated by the. Plant Protective System while reactor operators were attempting to place both steam driven boiler feed pumps in " auto parallel".

When the recirculation valve on "C"

boiler feed pump was closed as part of this evolution, feedwater flow suddenly increased.

The reactor operators inadvertently decreased the feedwater flow below the fixed feedwater flow low trip, while responding to this change in

,i feedwater flow.

This caused a steam turbine trip of all four helium circulators, and resulted in a two loop trouble scram.

-k The reactor was taken critical on June 26 at 1213 hours0.014 days <br />0.337 hours <br />0.00201 weeks <br />4.615465e-4 months <br />, and the turbine generator was returned to service on Jur.e 27 at 1815 g

hours.

This event will be investigated and reported to the unnloor o m,1oney enmsec<nn

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, -w 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 1.

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. 3.0 INDICATION OF FAILED FUEL' RESULTING FROM IRRADIATED FUEL l

EXAMINATIONS L

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4.0 MONTHLY OPERATING DATA REPORT Attached (I"

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oPrxAnn: DATA nrPorf Doca:T xa.

50-267 j

dan July 15. 1987 l

CovLrIED sI F. J. Novachek TELrruoNI (303) 620-1007 i

oPERAUNO STATUS NOTES j

- 1.

Unit Name Fort St. Vrmin. Urdt No. 1 2.

Reporting Period:

A*70601 through 870630 3.

Licensed Thermal Power (wt):

842 4 Nameplate Rating (cross W e):

342

' 5.

Design Electrical Rating (Net We):

330 6.

Maximum Dependable Capacity (cross We):

342 7.

M== Dependable Lapacity (Net we):

330 8.

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

None 9.

Power Level Io Which Restricted If Any (Net We):

115.5 10.

Raasons for Restrictions. If Any:

Per commitment t o the Nu cl ear Regui n e nrv c emnr 4 = = 4 nn.

do not. operate a'oove 35% until approved by the NRC.

This Month Yaar to Date Cumulative

n. Bours in Raporting Period 720 4,343 70,128

12. Nunbar of Bours Beacter Was Critical 640.5 1,710.0 32.247.8

13. Reactor Reserve Shutdon Rours 0.0 0.0 0.0 24 nours cenerator on-Line 564.7 1,214.6_

20,769.7

15. Unit Reserve Shutdown Bours 0.0 0.0 0.0

14. crosa Thermal Energy cenerated (Ws) 148,478.7 328,339.3__,

10.593,739.1

17. cross Elmetrical Energy cenerated (su) 47,784.0

98. 562.(L 3,432,558.0

18. Net nectrical Energy cenerated (wa) 43,270.0' 79,124.fL 3,027,404.0

29. Unit Service Tactor 78.4 28.0 29.6

20. Unit Availability Tactor 78.4 2 8.p_

29.6 21.

Unit Capacity Tactor (Using HDC Net) 18.2 5_5 1 *4.1 e

22. Unit Capacity Tactor (Dzing DER Net) 18.2 SL 13.1

23. Unit Terced outage Rate 21.6 72.0 63.3 24 Shutdowns Scheduled ovest Next 6 Nnths (Type. Date, and Duration of Each): Jone 1

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

N/A l

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Units in Test Status (Prior to Commercial operation):

Torecast Achieved INITIAL CRInCALIn N/A N /A IxInAL ELEC32CIn N /A N /A CDt0CRCIAL OPIRAUCN N/A N/A

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date July 15, 1987 Completed By F. J. Novachek Telephone (303) 620-1007 Month JUNE,1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 80.3 17 56.7 2

79.3 18 67.5 3

80.2 19 75.5 4

75.9 20 76.9

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74.8 22 73.0 7

79.3 23 80.8 8

79.9 24 82.2 9

74.2 25 66.9 10 73.4 26 0.0 11 74.9 27 10.3 12 42.7 28 90.5 l

13 0.0 29 92.5 l

14 0.0 30 89.2 15 0.0 31 N/A l

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• Generator on line but no net generation.

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R_EFUELING INFORMATION E

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

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Schedu'.ed date for next l

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refueling shutdown.

I September 14, 1988 l

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Scheduled date for restart l November 14, 1988 l-1 l

l' fo110wir:0 refueling.

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Will refueling or resumption ofl No l

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operation thereafter require a l l

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i If answer.is' yes,.what, in l ----------------

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general, will these be?-

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If answer is.no, has the reloadl l

l fuel design and core configura-l l

-l tion been reviewed by your l

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Plant Safety Review Committee l No l

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l viewed safety questions are l

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associated with the core reload l l

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50.59)?-

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. If no such review has taken l 1987 l

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placa, when is it scheduled?

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Scheduled date(s) for submit-l l

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and supporting information.

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Important licensing considera-l l

l tions associated with refuel-- l l

l ing, e.g., new or different l

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fuel design or supplier, unre-l ----------------

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viewed design or performance l

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analysis methods, significant l l

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operating procedures.

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The number of fuel assemblies l l

l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l

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' spent fuel storage pool.

I b) O spent fuel elements l

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E..lf REFUELING INFORMATION (CONTINUED) l l

1 l 8.

The present. licensed spent fuell l

l pool storage capacity and the l l

l size.of any increase in l Capacity is limited in size to l

l licensed storage capacity that l about one-third of core l

l has been requested or is l (approximately 500 HTGR element:;).l l

planned, in number of fuel l No change is planned.

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assemblies.

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l l 9.

The projected date of the.last l 1992 under Agreements AT(04-3)-633l l

refueling that can be dis-l and DE-SC07-79ID01370 between l

l charged to the spent fuel pool l Public Service Company of l

l assuming the present licensed l-Colorado, and General Atomic l

l capacity.

I Company, and 00E.*

l The 1992 estimated date is based on the understanding that spent fuel discharged during the term of the Agreert.ents will be stored by DOE at the Idaho Chemical Processing Plant.

The storage capacity.has evidently been' sized to accommodate eight fuel segments.

It is estimated that the eighth fuel segment will be discharged in 1992.

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16805 WCR 19 1/2, Platteville, Colorado 80651 July 15,1987 Fort St. Vrain Unit No. 1 P-87260 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555 Docket No. 50-267

SUBJECT:

MONTHLY OPERATIONS REPORT FOR JUNE,1987

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of June, 1987.

If you have any questions, please contact Mr. M. H. Holmes at (303) 480-6960.

Sincerely, P

R.O.t.Odh,% b R. O. Williams, Jr. 3 Vice President, Nuclear Operations Enclosure cc:

Mr.. J. E. Gagliardo U.S. NRC, Region IV ROW:djm t#h l

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