ML20058Q166

Monthly Operating Rept for Jul 1990 for Fort St Vrain. W/900814 Ltr

ML20058Q166
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/31/1990
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-90254, NUDOCS 9008210131
Download: ML20058Q166 (8)

Text

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P.o Box 840 Denver, Co 80201 0840 16805 WCR 19 1/2, Platteville, Colorado 80651 August 14, 1990 Fort St. Vrain Unit No. 1 P-90254 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267  ;

SUBJECT:

JULY, 1990 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 July, 1990, 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,

1. J. A Char es H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF:DLW/bh Enclosure cc: Regional Administrator, Region IV ATTN: Mr. J. B. Baird Technical Assistant Division of Reactor Projects Mr. D. Garrison Site Resident Inspector Fort St. Vrain 4

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MONTHLY DEFUELING OPERATIONS REPORT 1  !!

NO. 198 ,

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July,1990 }

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l This: report contains the highlights of the Fort:St. Vrain, Unit -

l No. I, activities operated under the provisions o f; the Nuclear L' Regulatory Commission Operating _ License No. DPR-34. This report is for the month of July, 1990. '

1.0 NARRATIVE

SUMMARY

OF OPERITING EXPERIENCE AND MAJOR SAFETY t RELATED MAINTENANCE The reactor remained shutdown the entire month of July,1990, following Public Service Company of~ Colorado's decision to end 'i nuclear ~ operation at Fort St. Vrain. ,

j'reparatice 'c'-

shipping spent fuel are proceeding.

During the month of July, lesy oli remaining Segment 10. fuel was ,

shipped offsite.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS

-0F '95 0F THE ALLOWABLE ANNUAL VALUE. ,?

None 2 0 INDICATION OF FAILED FUEL RESULTING. FROM -IRRADIATED FUEL-EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT

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OPERAT!NG DATA REPORT DOCKET r.. 50-267- l DATE August 15. 1990 I

COMPLETED BY M. L. Block

, TELEPHONE =(303)~620-1180 ~

OPEl ,.T"G STATUS NOTES [; *

1. Unit Name: Fort St. Vrtfin. Unit No. 1

2. Reporting FJiod: 900701 throemh-400711 i

3. Licensed Thermal Power (MWt): 842

~4 Nameplate Rating (Gross MWe): 342

5. Design Electrical Rating (Net MWe): 330 '

G. Maximum Dependable Capacity (Gross MWe): 342'

7. Maximum Dependable Capacity (Net MWe): 330

8. 'f Changes Occur in Capacity Ratings (!tems Numoer 3 Through 7) Since Last Report, Give Ressons:

Nnne i

9. Power Level To Which Restricted, if Any (Net MWe):' O.0 ,

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10. Reasons For Restrictions, If Any: Fort St. Vrnin canand nuclenr nonrneinn nn Aimune 70.-14R4.

This Monih Year To Date Cuculative'

11. Hours in Reporting Period 744 5.087 97.176 i

12. Nunoer Of Hours Reactor Was Critical N/A N/A lin 97K 7-

13. Reactor Reserve Shutdown Hours N/A- N/A N/A

14. . Hours Generator On Line N/A' 'N/A 27.777.4

15. Unit Reserve Shutdown' Hours 'N/A N/A N/A L 16. Gross Thennal Ene'gy Generated (MWH) -}

N/A N/A 14.450.651.2 l 17. Gross ElectrMal Energy Generated (MWH) N/A- N/A- 4.R16.814.0-t i

18. Net Electrical. Energy Generated (MWH) -1.869' -13.004 4.260.000.0-  ;

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

20. Unit Availability Factor N/A- N/A N/A 21.- Unit Caoacity Factor (Using MDC Net) N/A N/A N/A

22. Unit Capacity Factor (Using DER Net) N/A N/A N/A-

23. Unit Forced Outage Rate v/A n/A-

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24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Fort ~St. Vrain ceased I nuelnne nnerneinn nn Aueust 29. 1989. l

, 25. -If Shut Down At End Of Report Period. Es " mated Date Of Startup: N/A

26. Units in Test Status (Prior -To Consnercial- Operation): Forecast Achievej l INITIAL CRITICAL!iY N/A N/A INITIAL ELECTRICITY N/A~ 'N/A

!. COMMERCIAL OPERATION N/A i N/A 1

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=AVERACE-DAILY UNIT POWER LEVEL

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Docket No.'50-267 Unit Fort St. Vrain Unit No. l'

./ ~Date August 15, 1990 i

. Compieted By M.1. Block i

-Telephone (303) 620-1180 l Month JULY-t DAY AVERAGE DAILY POWER' LEVEL ' DAY'AVERAGEDAILYP%RLENEL 1

-(MWe-Net) (Mwe-Net)  ;

1 0.0 17 0.0 l

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-2 0.0 -18. 0.0

'3 0.6 19 0.0 1:

I 4 0.0 20 0.0  ;

i L 5- 0.0- '21 0.0

.6 0.0: 22' O.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 l

l- 11 0.0 27 0.0 <

1 l 12 0.0 28 0.0:

13 0.0 29- 'O0- ,

14 0.0 30 _

0.0 15 0.0 31 0.0 t

16 0.0 Nuclear Operations at Fort St. Vrai, were terminatedton August 29, 1989.

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4 UNIT SHUIDOWNS AND POWER REDUCTIONS

• DOCKET NO. 50-267

. UN I T MAME Fort St. Vra in Uni t No. 1 DATE Auaust 15. 1990 COMPLETED BY M. L. Block TELEPHONE (303) 620-1180 REPORT MONTH JULY. 1990 l l l l l METHOD Ofl l I l l l l 1 l l SHUTTING l l I I CAUSE AND CORRECitVE ACTION I NO. I DATE :TYPEl DURATION i REASON lDOWN 'l LER # ISYSTEMICOMPONENTl TO PREVENT RECURRENCE I i ll ll l l REACTOR l ICODE ICODE _1 1 I l H I l .

I i 1 - l 189-091 900701'l F 744.0 l F i 1 i N/A l N/A I N/A I Nuclear Operations were terminated on - I l l I if 1: 1 1 l l August 29, 1989,.see LER 89-018. I I I l .I I I I I I i I i 1 '

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-REFUELING INFORMATION l- . l .

1 i 1.- Name of Facility l Fort St. Vrain Unit No. 1 l l I I l None,.no further refueling at l' 2. Scheduled date for next l l refueling shutdown. 1 FSV is expected. l l -

I l' l 3. Scheduled date for restart l N/A l l' following refueling. 1- l.

.1- I l l 4. Will refueling or resumption oflLN/A l l operation thereafter require a l l l technical specification change l- l l or other license amendment? l l y l .

I I 1 l If answer is yes, what, in l ---------------- l 1 l genarol, will these be?

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l If answer is no, has the reload l- l l fuel design and. core configura_l- l l tion been reviewed by your l l l Plant Safety Review Committee l N/A - l l to determine whether any unre- l. l [

l viewed safety questions are l l i

l associated with the core reload l_

{ (Reference 10 CFR Section l l )

l 50.59)? l l l l l '

l .If no such review has taken l N/A l I place, when is it scheduled? l l _

l l l l l 5. Scheduled date(s) for submit- l l- l l ting proposed licensing action l ---------------- l_ i l and supporting information. I ~l f '

I l l l 6. Important licensing considera- l l 4 l tions associated with refuel- l l l ing, e g., new or different l l l fuel design or supplier, unre- l ---------------- l l viewed design or performance l l l analysis methods, significant l l l changes in fuel design, new l l j l operating procedures. l l i

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l I i l 7. The number of fuel assemblies l l l (a) in the core and (b) in-the I a) 1023 HTGR fuel elements l l spent fuel storage pool'. I b) 447 spent fuel elements l e

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REFUELING INFORMATION (CONTINUED) j L

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8. The present licensed. spent fuell l pool storage capacity and the: l- .

l _l l size of any increase in l Capacity is limited in size tof l l licensed storage capacity that l about one-third of core l_ 1 l- has been requested or is . l (approximately 500 HTGR~ elements).l-l planned, in. number of fuel -l No change is' planned.. -l-l l assemblies. I l. .I '

I l - . - I l 9. The projected date of the last.l No further refueling is .

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

• l_ charged to the spent fuel pool l )

l assuming the present' licensed l l 1 l capacity. l l-Under Agreements AT(04-3)-633 and'DE-SC07-791001370 between Public-Service Company of Colorado, General Atomic Company, and . 00E, ' spent- t 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 t that the eighth fuel ~ segment will be discharged-in 1991.1 Discussions concerning the disposition of ninth fuel segment ~ are in progress with D0E. Nuclear Operations at Fort St. Vrain were terminated. August 29,

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