ML20094D671

Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1

ML20094D671
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/30/1991
From:	Block M, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-91433, NUDOCS 9112230258
Download: ML20094D671 (8)

Text

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December 13, 1991 Fort St.-Vrain Unit No. 1 P-91433 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267 0S

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REFERENCE:

bR Facility Operating License Number DPR-34

Dear Sirs:

Enclosed, please find the Monthly Defueling Operations report for the month of November, 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.

l$1rcerely, b 771gwcAv.~M D.~W. b, embourg Manage , Nuclear Production 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 9112230253 911jfp PDR Ikk

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i l PUBLIC-SERVICE COMPANY OF COLORADO FORT-ST .VRAIN NUCLEAR GENERATING STATION f5 i

MONTHLY DEFUELING' OPERATIONS REPORT-NO. 214

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November, 1991 Y

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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 Commission Operating License No. OPR-34. This report is for the month of November, 1991.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTEN E G The reactor remained shutdown the entire month of November, 1991, following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain.

On November 4, 1991, the Nuclear negulatory Commission issued Materials License No. SNM-2504, Docket 72-9, for the Fort St.

Vrain Independent Spent Fuel Storage Installation (ISFSI),

pursuant to 10CFR72.

Preparations for transferring went fuel to the ISFSI are proceeding.

2.0 SINGLE RELEASES OF RADIDACTIVITY OR RADIATION EXPOSURE IN EXCESS

'0F 10*!, OF THE ALLdWABLE-'NNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM -IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached

OPIR$ TING DATA RFPORT DOCKET NO. $0-267 OATE December 13. 1991 COMPLETED BY M . 14 . Block TELEPHONE f 303) 620-1313 ,

OPERA **'43 $71Til$

NOTE $

1, Unit Name: ,

Feti_St. Vraig , l' nit No . 1 Reporting Feriodi 911101 f hrnuah 411,12[L ,_, I 2.

J. Litented Thermal Power (M :): p)2 4 hafneplate Rating (Gross MWe'f ,

. 3 4 2 ,,

5. Cesign Electrical Rating (het MWu. 330 _

6. Matimum Dependabit+ Canacity (Gross MWe); 3lg2

7. Mastmum DepeneMr Caoacity (Net MWe): 330, i,_. _

B.  ? Changes Occur in Cacscity Ratings (!ters Number 3 Through 7) $1hta tant Report. Give Reasons:

Nnne

9. fe.er eyel To Which Restrictea. If Any (Net Mae): . 0. 0 _

10. Reasons for Restrictions, if Any: AML Yrnin ceanei_pucient onevntinn nn Ancune 70. 14R9.

This Month Year To Date Cumulatye l 13. Hours in Peporting Period 720 8.016 _,,

108.865 L 12. Numoer Of Hours Reactor Was Critical N/A N/A & n _ ti7(;A l 13. -Fesctor :leserve Shutcown Hours N/A N/A N/A

14. bours Generator On Line N/A N/A 27.777.4 ,

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

i 10. Gross Thermal Energy Generat d (MWH) N/A ,

N/A 14.450.651 ;,_

'17 Gross Electrical Energy Genera *.ed (MW) N/A N/A 4.8 1 834.0 l- 18. - het Electrical Energy Generat*d ir r 1 -1.790 -17.686 4 233.993

19. Unit $ervice factor N/A N/A N/A

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20. Lnit' Availability factor N/A N/A N/A

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

22. Onit Caoacity factor (Using DER het) N/A _

N/A N/L 2 3.' Mit Forced Outage Rate _ v /L - y/A N/A ,

24 Snutdowns scheduled Over hext 6 t'onths (Type, Date. and Duration of Each): -Fort St.-Vrain ceased nuclonr nnnrnrinn on Aucust 29. 1989. . ,

25. I' En;,it Open At End Of Report Period. Esttratea Date Of !+artup: J /A .

Forecast Achiend 26, Units in Test Status (Prior To Comercial Operatior.):

INITIAL (RITICAllif N/A N/A _

INITIAL ELECTRICITV N/A _,

,_ , h/A COMMERCIAL OPERATION N/A N/A _

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A_VERAGE DAILY UNIT POWER LEVEL Do.ket No. 50-267

.- JM t Fort St. Vrain Unit No. I hate December 17 3 91 ~

Completed By H. l. M ock-Telephone DMT7JDMF_

Month NOVEMBER DAY AVERAGE DAILY. POWER LEVEL OAY AVERACE CAILY 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 7 _

0.0 23 0.0 8- 0.0 __

24 0 ,0 9 _

0.0 25 0.0 10 0.0 26 0.0 -

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 __

N/A

-16 -0.0 t

Nuclear Operatibns at Fort St. Vrain were termin. M on August 29, 1989.

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Docket No. 50-267 -

Unit fo E tt. Vrain Unit No. 1  :

Date DeceE er 13, 1B 1 ~

. Completed By NEf]Gek ,

Telephone (303) 620;1313 ,

REFUCi.ING INFORMATION >

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l __1. Name of Facility _ j_ Fort St. Vrain_ Unit No. 1 l l l l 1-2. Scheduled date for next l None, no further refueling at l >

refueling shutdown. l_FSVisexpected. _ l l 1 1 3. Scheduled date for restart l N/A l 1 following refueling. l l L -

1 -l d 4. -

Will refueling or resumption ofl N/A .)

I operation thereafter require a_l l

-technical specification change l l l _ or othe_r license amendment? [ _l l l_

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

general, will thest be?

If answer is no, has the reload l l fuel design and core configura-l -l

-tion been reviewed by your l .

l Plant Safety Review Committee l tuA l to determine whether any unre-_l -,

-viewed. safety questions are l

. associated with the core reloadj .l (Reference 10 CFR Section - l -l l' 50.59)? l l l 1 l

-l_ 'If no such~ review has.taken- l N/A l 11 place, when is it scheduled? l _ _ l

.- 1 I l 5. Scheduled date(s) for submit- l -l L ting proposed licensing action l ---------------- l l _

and supporting:information. l -l ,

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6. Important licensing'considera- l l-l tions-associated with_ refuel-- l l ing, e.g., new or~different l l fuel-design or supplier, unre -l ---------------- -l

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

l!' changes in' fuel: design, new l l t

-l operating procedures. _ l ,_, l l .

_-l l-l 7. The number of fuel assemblies l l l -' (a) in the core.and (b),in the I a) 1024 HTGR fuel elements l^

l- spent fuel storage pool, l' b) - 440 HTGR fuel elements- _l m__ _ .--

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REFUELINGINFORMATION__(CONTINUED} l

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l l l l 8. The present licensed spent fuell Onsite capacity is limited in l pool storage capacity and the l size to about one-third of core, l size of any increase in l 504 HTGR elements, Construction l I licensed storage capacity that l of an Independent Spent Fuel l I

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

L planned, in number of fuel l with a capacity of 1620 FSV HIGR l assemblies. l elements has been completed and l l and the facility has been l l licensed by the NRC.* l l l l l 9. The projected date of the last l No further refueling is j 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 L  ; capacttyj l l i

The Independent Spent Fuel Storage Installation (IEFSI), which is

• presently undergoing final testing, will be capable of storing the entire FSV core (1482 HTGR fuel elements) with storage space for an additional 138 HTGR fuel elements.

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Under Agreements AT(04-3)-633 and DE-SC07-791001370 between Puolic 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 limited to 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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