ML20077C259

Monthly Operating Rept for Apr 1991 for Fort St Vrain

ML20077C259
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/30/1991
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-91165, NUDOCS 9105210131
Download: ML20077C259 (8)

Text

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Q Publ 16805 WCR 19 1/2, Platteville, Colorado 80651 May 15,' 1991 1 Fort St. Vrain '

Unit No. 1 P-91165 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

APRIL, 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 April, 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,

/ "

J,Xu//x.

Cha/rles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF:DLW/bh Enclosure cc: Regional Administrator, Region IV Mr;-J. B. Baird Senior Resident Inspector Fort St. Vrain 9105210131 910430 1

PDR ADOCK 05000267 R FDR

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

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MONTHLY DEFUELING OPERATIONS REPORT NO. 207 April, 1991 I

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.-,_.mm__.-~~-.- _. .._,__.__-_;.__.~._. _-__________i

1-Ibis 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. OPR-34. This report is for the month of April, 1991.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY fiEUTEDIfRTEW9M The reactor remained shutdown the entire month of April, 1991, 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.

-2.0 SINGLE- RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS 6P 10*; 0F THE ALLodABLE ANNUAL VALUE ,

i None P

3.0 INDICATION OF FAILED FUEL' RESULTING FROM IRRADIATED FUEL EXAM [NXfl0N5 None 4.0 MONTHLY OPERATING DATA REPORT Attached l

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• OFERATIN3 CATA REPORT 00CKET NO. 50-267 DATE fiav 15.1991 COMPLETED BY M. L. Block OPERA?";3 S**TUS

?ELEPHONE /303) 6?O-1213 NOTES

1. Unit Name: Fort St. "rnin. l'n!t Nn. 1

2. Eeoorting Perloa: 010401 thrnuch 010410

3. Licensea Therinal Power (MWt): 842 4 Nameplate Rating (Gross MWe):

342 5, :esign Electrical Rating (Net MWe): 330

6. Maximum Ceoencable Capacity (Gross MWe):

342 Maximum Oeoendable Capacity ('.et Mwe): 330 S.

:hanges Oct.ur in Capacity Ratings ,.:ets Numeer 3 Through 7) Since Last Feoort. Give fe: sont.

Mnnn

9. b=er Level To nhich Restrictea. If Any Oet Mne): 0.0

10. Feasons for Festrictions. If Any:

Pntt Sr. Vrnin nwed sum onr n.s n rn r i nn an Annune 'O. loRo.

This Month Year To " te Cumulative

11. rours in Reporting Period 719 _ _. 2.879 .__ 103.728

12. Numoer Of Hours Reactor was Crittcal N/A N/A An 97K 7__

13. Reactor 4 serve Shutdown Nours N/A N/A N/A

14. cours Generator On-Line yf3 yjg 77,777,4

15. Lnit Reserve Shutcown Hours N/A N/A N/A

16. iress Themal Energy Generatea (Mww)

N/A N/A 14 . 4 'io . 6 51. 2

7. Gross Electrical Energy Generatec (MdH)

N/A N/A '..R16.834.0

13. Net Elec*.rical Energy Generated (MWH)

.l.571 -6.677 4.245.002

19. Vnit Se vice facter N/A '! /A N/A

20. Lnit Avillability factor

21. Lntt Capacity Factor (Using MDC Net)

N/L N/A N/A N/A y/A 9 /A

22. Lett Capacity Factor (Using DER Net)

N/A N/A N/A

23. Lnit Forced Outage Rate y/r y/r

24. y/r inutcowns Scheculea Over hext 6 Months (Type, Oate, and Duration of Each):Fort St. Vrain ceased nuninar nnnr,tinn on Aucurt ?o. 1080 21.

' $ nut Ocwn At End Of Report Perica. Estimated Date Of Startuo: N/A 26.

.ntis in Test Status (Peter To Comercial 0:eration); Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAi. ELECTR1;!Ty 3f; yfg COMMERCIAL 0FERAi!0N N/A N/A

AVERAGE DAILY UNIT POWER LEVEL ---

Docket No. 50-267 4 Unit Fort St. Vrain Unit No. 1 Date May 15, 1991 Completed By M. L. Block Telephone [30'11620-1313 Month APRIL 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 0.0 20 0.0 -

5 0.0 21 0.0 6 0.0 22 0.0 l 7 0.0 23 0.0 8 0 ,0, 24 0.0 9 0.0 25 0.0 I i

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10 0.0 26 0.0 l 11 0.0 27 0.0 i

l 12 0.0 28 0.0 i  !

l 13 0.0 __

29' O.0 14 0.0 30 0.0

• 15 0.0 31 N/A  !

16 0.0 j

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

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Docket No. 50-267 Unit [ortSt.VrainUnitNo.1 Date M ya15, 1991 Completed By N. L IBlock TelephoneTT03)620-1313 REFUEllNG INFOR* 0104 l 1 l-1. Name of Facility _ l I l Fort St. Vrain Unit No. 1_ _ _ l l

i 2. Scheduled date for next l Ilone, no further refueling at l

l refueling shutdown.

l FSV is expected. l l l l

l 3. Scheduled date for restart i N/A 1

l following refueling. l l

} l l

l 4. Will refueling or resumption ofi N/A 1 i

l operation thereafter require _a l l l technical specification change l l

] or other license amendment? I l l l

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

l l

-l general, will these be? I l l I

l l If answer is no, has the reload! ',

l fuel design and core configura-l l

l tion been reviewed by your l-i Plant Safety Review Committee l N/A l I

l to determine whether any unre- l l viewed safety questions are l

{ t l associated with the core reloadj t l

l (Reference 10 CFR Section l l

l 50.59)? I '

l_

I i

1 l If no such review has taken i N/A

! place when is it scheduled?

l I l  ;

I i S. Scheduled date(s) for submit- [

ting proposed licensing action ! ----------------

I l

, l and supportino_information. J.

l l l

_l l 6. Important licensing considera- 1 I l

l tions associated with refuel- l

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

l l fue l design or supplie r, un re- l ---------------- 1

-l - viewed design or performance l l' analysis methods,~significant' l l

-l changes in-fuel design, new' l. ,

l l operatino procedures.~ -l -

1 l

l l i l 7. The number of fuel assemblies i I

l l-(s) spent in the fuelcore and pool.

storago (b) in the_l a) 1024 HTGR fuel elements l l

'l b) 452 HTGR fuel elements l

- , . . . . . - . - . - - . . _ , . _ . _ . .-_-..._._-..-c ,_ _.- - , -. ,.-. .. ,.... ..- -. , , _ . _ . - - . , - - , . _ - - . , . . _ , . _ - , . _ , _ . - . -

1

.~ '..

.. 0 REFUELINGINFORMATIONIC0NTINUED}

l l 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, l l size of any increase in 1 504 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) l l planned, in number of fuel I with a capacity of 1620 FSV HTGR l l assemblies.

1 element's is proceeding

• l l l .

l-l 9. The projected 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 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 sphce 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.

l l