ML20101E576

Monthly Defueling Operations Rept for May 1992 for Fort St Vrain

ML20101E576
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/31/1992
From:	Block M, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-92227, NUDOCS 9206240038
Download: ML20101E576 (8)

Text

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4 h PQblic Service-  :'!A 16805 WCR 19 1/2, Platteville, Colorado 80651 June 15, 1992 Fort St. Vrain Unit No. 1 P-92E27 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk -

Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

MAY, 1992, MONTHLY DEFUELING OPERATIONS REPORT

REFERENCE:

Facility Opetating License Number DPR-34

Dear Sirs:

Enclosed, please find the final Monthly Defueling Operations Report for Fort St. Vrain. This report for the month of May, 1992, is 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) 620-1701. -

Sincere)y, t -

e D. W. Warembourg Manager, Nuclear Operations Fort St. Vrain Nuclear Generating Station DW:MLB/as Enclosure cc: Regional Administrator, Region IV Mr. J. B. Baird Senior Resident Inspector Fort St. Vrain ,

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9206240038 920531 PDR ADOCK 05000267 /{<bd' Y

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. 2 PUBLI. SERVICE COMPANY OF COLORADO FORT S* VRAIN NUCLEAR GENERATING STATION MONTHLY DEFUELING OPERATIONS REPORT NO, 220 May, 1992

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, 1992.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY KtLATED MAliifENANCE l

The reactor remained shutdown the entire month of May, 1992, following Public Service Company of Colorado's decision to end -

nuclear operation at Fort St. Vrain.

During the month of May, 1992, sixty-six loads (396 fuel elements) were deposited in the Fort St. Vrain Independent Spent Fuel Storage Installation (ISFSI).

0 On May II, 1992, at 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br />, the ' st fuel element was removed from the Prestressed Concrete Reactor Vessel.

On June 10, 1992, the final load of spent fuel was transferred to the Fort St. Vrain ISFSI.

On June S, 1992, Amendment No. 84 to the Fort St. Vrain Technical Specifications was issued. This amendment deleted the requirement to submit a Monthly Operations Report. Therefore, this is the final Monthly Defueling Operations Report for Fort St. Vrain.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS -

0F 10% OF THE ALLOWABLE ANNUAL VALUE Not.e 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached

4 OFFCATING DATA REPORT DOCKET NO. 50-267 __

DATE June 15.1992 COMPLETED BY M. !. Block TELEPHONE (303) 6?O-1913 _

OPERAT**G $"TUS NOTES

1. Unit Name: Fort St. Vrain. Unit 'M. 1

2. Reporting Perico: 9?0501 through 9?0931

3. Licensed Thermal Power (MWt): 842 4 Nameplate Rating (Gross MWe): 342

5. Cesign Electrical Rating (Net MWe): 330 -

6. Maximum Cependable Capacity (Gross Ne): 342

7. Maxinum Decencable Capacity (het MWe): 330 E. Changes Occur in Capacity Ratings (:te-s Numeer 3 Througn 7) Since Last Report, Give seasons:

Nann

9. Fo.er Levei To Which Restricteo, If Any (Net Ne): 0.0

10. ;easons F:r Restrictions, If Any: rort St. Vrnin conned nuclear nonrntion nn Anmme 'o_ 1999 ,

This Montn Year to Date Cumulative

11. Pours in Reporting Period 744 3.647 113_?66

12. humoer Of Hours Reactor Was Critical N/A _ .1 40_57E 7

13. Reactor Eeserve Shutdown Hours N/A N/A N/A 14 -curs Generator On-Line N/A _

N/A '7.777.4

15. Lnit Reserve $hutcown Hours N/A N/A N/A 15, 3ress Teermal Energy Generated (MWH1 N/A N/A 14,450.651.2 17 Gross Electrical Energy Ge w ited (MWH) N/A N/A 4.916.834.0

18. set Electrical Energy Generatea (MdH) -1.668 -8.658 4,223,494

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

20. Lnit Availacility Factor N/A N/A N/A

21. Lnit Caoacity factor (Using MDC Net) M/A N/A N/A

22. Leit Caoacity Factor (Using DER het) N/A N/A N/A

23. Unit Forceo Outage Rate y/3 y/A M/A 24 Snutcowns Scheculed Over Next 6 Months (Type, Cate, and Duration of Eacn): Fort St. Vrain ceased nurinnr nnnrnrinn en Aucunt 20, 1989.

25.  :' 5 ut Caan At End Of Report Feriod, Estimatea Cate Of Startuo: N /A Forecast Achieved

26. cntts in Test Status (Prior To Commercial 00eretion):

INITIAL CRITICAL!iY N/A N/A INITIAL ELECTRICITY lu A N/A COMMERCIAL OPERAT;CN N/A N/A l

l l

._ .. _ _ . _ . _ _ _ _ . . _ . _ - _ _ . . . - . _ - . _ . - _ _ _ . _ _ . ._..m. _ ..m...____, , , .

l

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

. Unit Fort St. Vrain Unit-No. 1-Date June-15; 1992 _

Completed By M. L. Block Telephone (303) 620-1313 _

Month MAY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i 1 0.0 17 0.0 2 0.0 18 0.0 3 0.0 19 0.0 4 0.0 20 0.0 l 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 l __10 - 0.0 26 0.0 t

11 0.0 -27 0.0 l:

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

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Docket No. 50-267 t

Unit Fort St. Vrain Unit No.'~[ '--

Date June 15, 199$

Completed By M. L. Block

. Telephone (303) 620-1313 REFUELING INFORMATION l- -

1 I i 1. Name of Facility l Fort St. Vrain unit No. 1 l 1- 1 I l-22 Scheduled date for_next l None, no further refueling at l

, .l refueling shutdown. I FSV is' expected. j .

l .

I I l 3, . Scheduled date for restart l N/A l l- following refueling. l I I .. I l l 4. Jill 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 l- - 1 I l If answer is yes, what, in 1 ---------------- l

- l- general, will these be? I l l i I l If answer is no, has the reloadi I l- . fuel-design.and core _configura-l l l- tion been: reviewed-by your l l

) Plant Safety Review Committee i 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 l [ (Reference 10 CFR-Section l l l 1: 50.59)? I l l 1 -l l= If no-such review has taken l N/A l

). place,-when-is it scheduled?- l l

l. -.

l l l 5 ~. Scheduled date(s) for- submit - l l l ting proposed licensing action l ---------------- l l ' and supporting information. l _]

I l 1

- l 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- 1 ---------------- -l

-l _ viewed design or performance l l I analysis methods, significant l .I

l. l- changes in fuel design, new 1 l l- operating procedures. l l l l 1 17, The number of fuel assemblies l l l (a) in the core'and (b) in the l a) 0 HTGR fuel elements l l spent fuel storage pool. I b) 120 HTGR fuel elements 'l

, . REFUELING IN. FORMATION (CONTINUED) 1 I I l 8. The present licensed spent ruell Onsite capacity is limited in l l pool storage capacity and the i 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) l l planned, in number of fuel l with a capacity of 1620 FSV HTGR l l assemblies. l elements has been completed and l 1 l and the facilit. has been l l ___ _1 licensed by_the NRC.* l l l l l 9. The projected date of the last l No further refueling is l l refueling that can be dis- I 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), which is presently undergoing fuel loading, will be capable of storing the entire FSV core (1482 HTGR fuel elements) with storage space for an additional 138 HTGR fuel 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 limited to eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992. Discu>sions 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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