ML20070P481

Monthly Operating Rept for Feb 1991 for Fort St Vrain.W/

ML20070P481
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/28/1991
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-91095, NUDOCS 9103270307
Download: ML20070P481 (8)

Text

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Pubhc Gervko Publ c Service' P J. 00 640 Denver Co trJ010MO 16805 WCR 19 1/2, Platteville, Coloredo SG651 i

March 14, 1991 Fort St..Vrain Unit No. 1 P-91095 i

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

20555 Docket No. 50-267

SUBJECT:

FEBRUARY, 1991, MONTHLY DEFUELING OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sirs:

Enclosed, please find the Monthly Defueling Operations report for the month _of February, 1991, submitted per the requirements of Fort St.

Vrain Technical. Specification AC 7.5.1.

If you have any questions, please contact Mr.

M. H. Holmes at (303).480-6960.

Sincerely, n

Charles H..uller Manager, Nuclear Production Fort-St. Vrain Nuclear Generating Station-CHF:0LW/oh Enclosure cc: Regional Administrator, Region IV ATTN: Mr. G. L. Constable, Chief l

Technical-Support Section Division of Reactor Projects 280001Mr. J. B. Baird h>

Senior Site Resident Inspector 9103270307 910228

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION 1

i MONTHLY DEFUELING OPERATIONS REPORT NO. 205 February, 1991 L:

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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 No. 0PR-34.

This report is for the month'of February, 1991.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELA'T[D RKiliiENANCE The eactor remained shutdown the entire month of February, 1991, following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain.

Preparations-for shipping.p?nt fuel are proceeding.

Constructica of the independent Spent Fuel Storage Installation-(ISFSI) is proceeding.

2.0 SINGLE' RELEASES OF RADIOACTIVITY OR RADIATION FXDOSURE IN EXCESS BF 10*4 0F THE X E0WX5LE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 1

4,0 MONTHLY OPERATING DATA REPORT Attached l

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-OPERAT!hG DATA REPORT DOCKET NO.

50-267 DATE March 15. 1001 COMPLETED BY-M. L. lilock' L

'I TELEPHONE (303) 620-1313

'.0PERATING $7A,Tjl5.

t NOTES Lt. Unit Nase:-

Fort St. Vrain. Uni

• No. 1

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2.f Reporting Periods.

Q1(1901 -thenngh 910228-l3. Licensed Thennal Power (MWt):-

'842 4.

Nameplate Rating -(Gross MWe) -

342 n

5.

Design Elec rica) Ratin: (Net MWe):'

-330

6. "Vaximuut L;en. M topacity. (Grcss MWe);

342 17.

,sm;mam papend?.* ;apacity (Net MWe):

330=

8.1 E!! Chinees Oct

1 CaWcity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons

-

.f 7 d ne fj 9.'- Power Level To Which Restricted. If Any (Net MWe):

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.10. : Aeasons For Restrictions,. lf Any - 'Fnre St.=Vrnin consed nucienr-conrnrinn nn Auenne 90. 10RO.

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This Month

-Year To Date.

Cumulative 3

011. -~ Hours In Reporting Period 672

~1.416

'107.965'

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!12., Numoar Of Hours Reactor Was: Critical N/A' N/A'

~

-60.r7K 7_.

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13?RAactr. Reserve Shutdown Hours N/A-

'N/A-N/A-14im neur. Generator On-Line N/A N/A 27.777.4-

"15 L unit Reserve Shutdown. Hours -

N/A N/A-N/A

, sl6.' { Gross, Thermal Energy Generated. (MWH)

N/A N/A-14.450.65) 2 g

17. Gross Electrical Energy Generated (MWH)

N/A

-N/A' 4.R16.814.0

.]

VIO-NetElectricalEnergyGenerated'_(MWH):

-LR5_

-3,366-4.248.313 59 y va. ; Service factori M/A '

' N / A,_

N/A'

f 120! Unit Availability factor

. N / A... _ _.

N/A-N/A-

}21. - Unit'. Caoacity; Factor _(Using. MDC Net)

N /A' N/A N/A j

22. ". unit Capacity Factor (Using OER Net)

N/A N/A' N/L l

23.Junit Forced Outage-Rate M/A N/A-y /t i

l24i, Shutdowns Scheduled:Over Next 6 Months (Type, Date, and Duration of, Each);

Fort St.'Vraiti c or.a ed

-f nn=Aucust 29. 1989.

R nucione nnnrnrinna G,

L25. ?IfiShut;Down At End 0f' Report Period. Estimated Date Of Startup:

N /A j

Forecast

-Achieved [

" 226.. Units. In1 Test Status (Prior To Commercial Operation):

INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY

-N/A

'N/A i

-COMMERCIAL OPERATION N/A N/A l

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AVERAGE DAILY UNIT POV.'.R LEVEL f

Docket No. 50-267 Unit' fort St. Vrain (fnit No. 1 Date March 15 J 91 Completed By M. L. Block Telephone U5E6fD' 1Tif Month FEBRUARY _

I 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

00 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 N/A-14 0.0 30 N/A

=15 0.0-31 N/A 16 :.

0.0 Nuclear Operations at Fort St. Vrain were terminated on August 29, 1989.

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Docket No.-50 267

-Unit Port St. Vrain Tinit No. 1 Date February 15, 1991 CompletedBy[H.L. Block Telephone 303T620-1313 REFUELING INFORMATION l

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Name of Facility J Fort St. Vrai_n_ Unit No. 1 l

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Scheduled date for next l None, no further refueling at l

l refueling shutdown.

_{ FSV i s expected.

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Scheduled date for restart l N/A l

l followi_ng refueling.

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Will refueling or resumption ofl N/A l

l operation thereafter require a l l

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_ technical specification change l l

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or other license amendment?

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If_ answer is yes, what, in l ----------------

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_l-general, will these be?

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l If answer is no,-has.the reloadj l

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-fuel design and core configura-l l

l tion been reviewed by your l

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Plant Safety Review Committee l N/A l-l to determine whether any unre-l l

l viewed safety questions are I

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associated with the: core reload l l

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-(Reference'10 CFR Section l

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50.59)?

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~If no such review has taken l N/A l

. l_t. lace, when is it scheduled?

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l l 5.

Scheduled date(s) for submit-l l

l ting proposed licensing actio'n l ----------------

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-j and supporting'information.

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Inportant' licensing considera-l l

.l tions_ associated with-refuel--- l l

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

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fuel design or supplier, unre-I ----------------

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viewed design or performance l

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analysis-methods,_significant l

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changes in fuel design, new-l l

l operating procedures.

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l l 7.

The number of fuel assemblies l

l l-(a) in the core and (b) in the l a) 1024 HTGR fuel elements l

l spent fuel storage _ pool.

Lb) 452 HTGR fuel elements l

REFUELINGINFORMATION(CONTINUED).

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The present licensed spent fuell Current capacity is limited in l

l pool _ storage capacity and the l size to about one-third of core, l

l size of any increase in l 504 HTGR elements.

Construction l

l licensed storage capacity that l of an Independent Spent Fuel l

l has been requested or is l Storage Installation (ISFSI)_

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planned.in number of fuel

! with a capacity of 1620 FSV HTGR l l_

assemblies.

j elements is proceeding.*

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The projecteo date of the last l No further refueling is l

l refueling that can be dis-l anticipated at Fort St. Vrain. ** l l

charged to the spent fuel pool l l

l assuming the prese.t licensed 1 l

l capacity.

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The Independent Spent Fuel Storage Installation (ISFSI) will be capable of storing the entire FSV core (1482 HTGR elements) with storage. space for an additional 138 HTGR elements.

- Under Agreements AT(04-3)-633 and DE-SC07-791001370 between Public Service Company of Colorado, General Atomic Company, and DOE, spent fuel discharged during the defueling process will be stored by DOE at the Idaho Chemical Processing Plant.

The storage capacity is presently sized to accommodate eight fuel segments.

It is estimated that the eighth fuel segment will be discharged in _1992.

Discussions concerning the disposition of ninth fuel segment are in progress with

DOE, Nuclear Operations at Fort St Vrain were terminated August 29, 1989.

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