ML20058H882

Monthly Defueling Operations Rept for Oct 1990 for Fort St Vrain Nuclear Generating Station

ML20058H882
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/31/1990
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-90337, NUDOCS 9011260110
Download: ML20058H882 (8)

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PublicLService' "h c-P.O. Box 940 o.nver.co so200 ouo 16805 WCR 19 1/2, Platteville, Colorado 80651

[ November 15, 1990 Fort St. Vrain Unit ik '

P-90337 U. S. Nuclear Regulatory Commission '

ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

OCTOBER, 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 October, 1990, submitted per the requirements of Fort-St.

Vrain Technical Specification AC 7.5.1.

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

Sincerely.

a/./

v valN-Charles H. Fuller m Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station.

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=- Enclosure cc: Regional Administrator, Region IV ATTN: Mr. G. L. Constable, Chief Technical Support Section Division of Reactor Projects r

Mr. J. B. Baird Site Resident Inspector Fort St. Vrain r pf1

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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 Cor. mission Operating License No. DPR-34. This report is for.the month of October, 1990.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE

• The reactor remained shutdown the entire month of October, 1990, following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain.

Preparations for shipping spent fuel are proceeding.

On October 18, 1990, an Enforcement Conference was held with Region IV in Arlington,' Texas, as a result of an unplanned exposure event on September 19, 1990. This event resulted in 6 Notices of Violation.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS 0." 10?. OF THE ALLOWABLE ANNUAL VALUE None 3.0 IN0! CATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None

'4,0 MONTHLY OPERATING DATA REPORT Attached

I OPERAT!NG DATA REPORT DOCKET NO. 50-267 DATE Hnvombor 15. 1990 COMPLETED BY M. L. Block TELEPHONE (303) 620-1190 OPER A"*;3 5*MUS NOTES

. Unit Name: Fort St. Vrnin. Unit No. I

2. Reporting Period: QO1001 thrnunh 4A1011

3. L1censeo Thermal Power (MWt): 842 4 Nameplate Pating (Gross MWe): 342

5. ;esign Electrical Rating (Net MWe): 330

6. - Mastmum Dependaole Capacity (Gross MWe): 342

7. - Maximum Dependable Capacity (Net MWe): 330

6. I' Changt3 Occur in Capacity Ratings l'tems Numoer 3 Througn 7) Since Last Report. Give Aeasons:

Nnne

9. Power Level To Which Restricteo. If Any (Net MWe): 0.0

10. Reasons For Restrictions. If Any: Fort St. Vrnin canned nuciane nnarnrinn nn Auenne 90. 10AQ.

This Month Year To Date Cumulative

11. -ours In Reporting Period 745 7.296 99.335

12. humoer Of Hours Reactor Was Critical N/A N/A an:M7K.7 13.' Reactor Reserve Shutdown Hours N/A N/A N/A

-14. Pours Generator On-Line N/A N/A 27.777.4 15.~ Lntt Reserve Shutdown Hours N/A N/A N/A

16. Gross Them41 Energy Generated (MWH) N/A N/A 14.450.651.2_

l

17. Gross Electrical Energy Generated (MWH) N /A N/A 6.R16.R14.0

18. Net Electrical Energy Generated (MWH) -1.660 -18.075 4.254.929

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

20. Lntt Availability Factor N/A N/A N/A

21. Unit Capacity Factor (Using MOC Net) N/A N/A M/A

22. unit Capacity Factor (Using-0ER Net) N/A N/A~ N/A

23. Unit Forced Outage Rate v/A y/A y/A I

24 Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): Fort St. Vrain ceased nunlear nnerneinn nn Anonnt 29. 1989.

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25. If Shut Down At End Of Report Period. Estimated Date Of Startup: N/A

26. units In Test Status (Prior to Comercial Operation): Foncast Achieved }

INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

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, .u AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267

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Unit Fort St. Vrain Unit No. 1 Oate November 15, 1990 Completed By IC L. Block i Telephone (303) 620-1180 l 1

Month OCTOBER I

DAY ' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  ;

(MWe-Net) (MWe-Net) l 1 0.0 17 0.0 .l l

2 0.0 18 0.0 3 0.0 19 0.0 l

4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 7 0.0 23 0.0 x 8 0.0 24 0.0 9 0.0 25 0.0 10 0.0 26 0.0 -

11 0.0 27 0.0 j 12 0.0 28 0.0 ]

13- 0.0 29 0.0 14 0.0 30 0.0  !

15 0.0 31 0.0 16 0.0 i i

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

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>- n UNIT SHU1 DOWNS AND POWER REDUCTIONS DOCKET NO. 50-261 UNIT MAME f ort St. Vra in Unit No. 1

' DATE November 15. 1990 COMPLETED BY & t. Block _

TELEPHONE L10 M 20-1_100 REPORT MONTH OCTOBER. 1990 .

t i I I I I IMEIH00 OII. 1 l l l l l 1 1 I ISHUITING I I l 1 CAUSE AND CORRECTIVE ACTION I l No. I DATE ITYPEl DURATION l REASON lDOWN l LER # ISYSTEMICOMPONINil 10 PREVENI RECURRENCE I I i l i 1 1 REACTOR I ICODE ICODE 1 I i 1 1 i l l l l 1 I I 189-091 901001 l ri 78:5.0 i r i 1 i N/A 1 N/A l N/A I Nuclear Operations were terminated on i l l I l l l l 1 l l August 29, 1989, see tER 89-018. I I i 1 1 I I I i i I I I I 1 1 1 1 I i 1 i I I I I i 1 -l 1 1 I I i 1 1 1 i i I I 1 1 i I i i I I i 1 1 1 I I I J l i I i i i I I i i i i i i i l i i i i i l i i l I i i i l I .

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I I I I i 1 "I I I I I l l l l l l 1 1 I I i l 1 I i 1 1 I I I i 1 1 1 1 I I I I I I I 1

1 1 I i i 1 1 i I 8 I I I I I I I i i i I I I I l 1 1 I l 1 I I i i 1 i i i i i i 1 i i i u I  ; I I I I I I l

I I I I I I I I I I i i i I I i 1 1 I I I i i 1 1 1 1 1 1 I I I I I i 1 1 1 1 'I i 1 I I 1 I I I I I i l I i 1 i 1 I I i I i i i I i I i l I I l 1 I L1 I I I

i i i 1 i 1 i 1 I I l l 1 I I i 1 I i l i i i i I i i i i i l' I i

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'4I REFUELING INFORMATION I I I  !

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

I I l l 2. Scheduled date for next i None. no further refueling at l 1 l refueling shutdown. I FSV is expected. l l l I l l 3. Scheduled date for restart i N/A l l following refueling. l l l l l l 4. Will refueling or resumption ofl N/A l l operation thereafter require a l l l technical specification change l l l or other license amendment? I  !

I l .i l If answer is yes, what, in l ---------------- l l general, will these be? 1 l 1 I 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 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 l associated with the core reload! l l (Reference 10 CFR Section_ l l l 50.59)? I l L l l l L l If no such review has taken l N/A l L l place, when is it scheduled? l l l I I l S. Scheduled date(s) for submit- l l l -l ting proposed licensing action 1 ---------------- l l- and supporting information. l l l l l 1 6. Important licensing considera--l l

-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 i changes in fuel design, new l l l operating procedures. I I l l 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. I b) 458 spent fuel elements l

_ _ . ._.;_=...=_..___._____..._._..._.....=.. -

49

. . .. s REFUELING INFORMATION JCONTINUED) l l l 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 j (approximately 500 HTGR elements).l l planned, in number of fuel l No change is planned. I l assemblies. l l 1 -

1 I l 9. The projected date of the last i No further refueling is l l refueling that can be dis- l anticipated at Fort St. Pain.

• l l charged to the spent fuel pool l l l assuming the present licensed l l l capacity. 1 l Under Agreements AT(04-3)-633 and DE-SC07-791001370 between Public Service Company of Colorado, General Atomic Company, and 00E, 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 1991. Discussions concerning the disposition of ninth fuel segment are in progress with 00E. Nuclea, Operations at Fort St. Vrain were terminated August 29, 1989.

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