ML20077F839

Monthly Operating Rept for May 1991 for Fort St Vrain

ML20077F839
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/31/1991
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-91212, NUDOCS 9106200261
Download: ML20077F839 (8)

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f P o Boa 140 Deme, to 10201 OMO 16805 WCR 19 1/2, Platteville, Colorado 80651 June 17, 1991 Fort St. Vrain Unit No. 1 P-91212 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555 Docket No. 50-267

SUBJECT:

MAY, 1991, MONTHLY DEFUELING OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sirs:

Enclosed please find the Monthly Defueling Operation; report for the month of May, 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,

, o/

Mj];,//(

Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF:DLW/bj Enclosure cc: Regional Administrator, Region I

Mr. J. B. Baird Senior Resident Inspector Fort St. Vrain 9106200261 910531 J

PDR ADOCK 05000267 R

PDR

\\

e PUBLIC SERVICE COMPANY OF COLORADO FORT $T. VRAIN NUCLEAR GENERATING STAT 10!1 MONTHLY DEFUELING C>PERATIONS REPORT NO. COB May, 1991 1

_ _ _.. _ _..~._ _ _ ___ -_ _ -._ __ _ _.- - _ --.. - -

1 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. DPR-34.

This report is for the month of May,-1991, 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY TiEATEF~MATNTililiTCB The reactor remained shutdown the entire month of May, 1991, j

following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain.

Preparations for shipping spent fuel are proceeding.

Construction of the Independent Spent Fuel Storage Installation (ISFSI) is proceeding.

On May 21, 1991, the Nuclear Regulatory Commission issued Amenament No. E2 to Facility Operating License No. DPR-34 to l

modify the Fort LSt. Vrain Operating License to a Possession Only status.

2,0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS dFW, WF TEIE A'LT67ATLE ANNUAL VALUE None

[

B 3.0 INDICATION OF FAILED-FUEL RESULTING FROM IRRADIATED FUEL

$\\AMTEXTf655 i

None 4.0 MONTHLY OPERATING DATA REPORT' Attached

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i UlRATING DATA REPORT DOCKET NO.

50-267 DATE June 17. 1991 COMPLETED BY M.

1,. Mock TELEPHONE (300 90-1313 OPERAT N STATU$

~ NOTL5 1.

Unit Name Fort St. Vrnin. Unit No. 1 2.

Reporting Perica:

910501 throuch 910531 3.

Licensea Themal Power (Mdt):

R42 4.

Nameplate Asting (Gross Mde):

342 5.

esign Electrical Rating (het MWe);

330 I

6. - Martmum Dependable Capacity (Gross MWe):

?42 7.

M.ansmum Depencable Capacity l Net MWe):

330 i

S.

' Changes Occur in Capacity Ratings litems Nsmber 3 Througn 7) Si' ce Last Report. Give Eeasons!

Nnne 9.

hwer Level To Which Restricteo. If Any (het MWe):

0.0

10. Reasons for Restrictions. If Any:

rnrt sr. Vrnin cone.nd nylonr noornr4nn nn Atmu. t

'o.

toro.

This Month Year To Date Cumulative

11. Hours in Reporting Period 74a 3.623 104.472

12. Numoer Of Hours Reactor Was Critical N/A N/A

!> 0 _ % 7 K _ 7__ _

13. Reactor 'eserve Shutdown Hours N/A

!!/A N/A 14 Hours Generator On Line M/A N/A 21.777.4

15. Unit Reserve Shutdown Hours N/A N/A

-N/A

16.. 3ross Thermal Energy Generatec (FWH)

N/A N/A,

14.430.651.2

17. Gross Electrical Energy Generated (MdH)

N/A N/A 4. R %. 83 !.

0

18. Net Electrical Energy Generatea (MWH) 1.458

-8.135 4.243.544

19. Unit Service Factor N/A M/A N/A

20. Lntt Avatlability factor N/A N/A N/A

21. Lnit Capacity Factor (Using MDC Net)

M/A N/A M/A

22..Vr.it tapacity f actor (Using DER Net)

N/A N/A_

N/A

23. Unit Forced Outage Rate M/A M/A M/A 24 Snutdowns Scheduled Over Next 6 Montns tType. Oate, and Juration of Each):

Fort St. Vrain consed niminne nnnrnrinn en Augge 29. loa 9.

25. :f Shut Oc.n At Eno Of Feoort Perioc. Estimatec Date Of Startup:

M/A

26. Units In Test Status (Prior To Commercial C eration):

Forecast Acnteved INITIAL CRITICALITY N/A N/A IN!TIAL ELECTRICliy N/A N/A COMMERCIAL CPERATION N/A N/A l

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AVERAGE' DAILY UNIT POWER I.EVEL Docket No. 50-267 Unit fo7t St. Vrain Unit No. 1 DateJunel'771T91~

Completed By IC L. Block Telephone [153)620?TfD

~

Month MAY UAY AVERAGE DA!LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(M4e-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 i

9

0. 0 -

25 0.0 l

10 0.0 26

- 0.0 l

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 0.0 31 0.0 t 0.0 Nuclear ~0perations at Fort St.-Vrain were terminated on August 29, 1989.

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Docket No. 50-267 l

Unit fort St._Vrain Unit No. 1 Date June T7, 1911 1

Completed By H. L.'iflock Telephone TTO] T2F1313 i

REFUELING INFORMATION I

i l

l 1.

Narne of' Facility

{ Fort St._Vrain__ Unit No. 1 l

l l

l l 2.

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

a l

refueling shutdown.

I FSV is expected.

l I

i 1

1 3.

Scheduled date for restart l N/A l

l following refuelin_g.

l I

I l4 Will refueling or resumption ofl N/A l

l operation thereafter tequire a l l

l technical specification change l l

l or other license amendment?

l

_l 5

I I

I I

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

l l

general, will these be?

1 l

l l-l l

If answer is no, has the reload l l

l

-fuel design and core configura-l l

I tion been reviewed by your i

l l

Plant Safety Review Committee l N/A l

l to_ determine whether any unre-l l_

l viewed sa_fety questions are l

l l

associated with the core reload l

-l l.

(Reference 10 CFR Section l

l l

l 50.59)?

l l

1 1

I l

If no such review has taken l N/A l

l_

'olace, when is it scheduled?

_l l

l I

l i

1 5.

Scheduled date(s) for submit-l l

l ting proposed licensing action l-----------------

l l

l_

and supporting information.

I l

l 1

l l 6.

Important licensing considera-l l

l tions-associated with refuel-l l

1

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

-l 1

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

l l

viewed design or performance l

.I l

analysis methods, significant l l-l changes in-fuel design, new l

l l-operating procedures.

l l

l i

I 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 s,oent fuel storage pool.

I b) 452 HTGR fuel elements l

l l:

~... _ _. - _.. -.. _ _. _ _... - _ _. -, -. _. - -,.. _. - -.. _ _ _.. _ _, -,.

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REFUELINGINFORMATION(CONTINUED) 1 I

I i

l l 8.

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, 1

I size of any increase in-l 504 HTGR elements.

Construction j I

licensed storage capacity that I of an Independent Spent Fuel 1

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

planned, in number of fuel l with a capacity of 1620 FSV HTGR l l

essemblies.

_ _ l elements is proceeding,*

l l

l 1

l 9.

The projected date of the last j 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 present licensed l

l

-l _

capacity.

_ l l

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 olements.

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 00E at the Idaho Chemical Processing Plant.

The storage capacity is i

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

- 00E.

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

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