ML20100R743

Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/

ML20100R743
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/31/1992
From:	Block M, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P92157, NUDOCS 9204170163
Download: ML20100R743 (8)

Text

4 hPubi c Service-  %" 2 % .e If>805 CR 191/2, Plattr .11e, Colorado 80051 l

April 15, 1992  ;

Fort 5t, Vrain Unit No. I  !

P-9?i57 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk i Washington, D.C. 20555 i

Docket No. 50-267  :

SUBJECT:

MARCH, 1992, MONTHLY DEFUELING OPERATIONS REPORT

REFERENCE:

Facilitj Operating Liccnse Number DPR-34

Dear Sirs:

Enclosed, please find the Monthly Defueling Operations report for the

• month of March, 1992, submitted per the requirements of Fort St.

Vrain Technical Specification AC 7.54 1, if you have any questions, please contact Mr. M. H. Holmes at (303) 620-1701.

Sincerely,

.0JY1hu D. W. karembourg k '

Manager, Nuclear Opefations Fort St. Vrain Nuclear Generating Station DWW:MLB/as Enclosure cc: Regional Administra' , Region IV Mr. J. B. Baird Senior Resident Inspector Fort St. Vrain l

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4 MONTHLY DEFUELING OPERATIONS REPORT NO. 218 March, 1992

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O 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 . March, 1992.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND~~ MAJOR SAFETY

_k $_L^T_'f. D~MA~I N_T I N_A_N C_E.

The reactor remained shutdown the entire month of March, 1992, following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain.

During the tnonth of March,1992, thirty-nine loads (234 fuel elerents) were deposited in the Fort St. Vrain Independent $ pent Fuel Storage Installation (ISFSI).

2.0 SINGLE RELEASES OF RADICACTIVITY OR RADIATION EXPOSURE IN EXCESS 6 F10'. OF THE ALLOWABLE..~ANiUAL V4~LOf ~ ~ ~ ~ ~ ~ ^ ' ~ ~ ~ '

None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL O None 4.0 MONT.'LY . OPERATING DATA REPORT Attached O

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T crt AT_!N3 CATA c! PORT 00Ct[i NO, 50 267 DATE April 1 W 292

MPLETED tv M. t. mer IELEPH0ht E31 QQ-DD crt m .ss m 5

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1. Lntt Na'ne: rett St. Vrain, Unit NA' 1 {

. seportseg period: 920301 through 920331

3. Liceesed iter 1ral Power (Wt): 442 4 NsMolett Rating (Gross MWe): 342

. :esign Electrical Rating (het Ne): 130 i j

waiimum Cerencable Capacity (Gross We): j

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32 i j

7. "animum C-et1encable Capacity (het Mae): 330 i

6. ;tanges Ocewr in 'acacity Ratings i:te s tutter 3 Throsgn 7) Since Last GeDert, m e 6casons:

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9. ft .er Level to anten Gestrictec. If Any (het We): 0.0

0. Ae sons F

e pestrictions. If Any: rnrt et. Train ceased nucicar sperntio m futg.unt 79. 19R9.

'his Month fear to Date Cumulative

11. -curs in eeporting Feriod 744  ?,184 111.793

12. Wmoer Of Hours Reactor nas Critical '; / A '1/ A '. O % 7 6 . 7_ _

13. Eeacter Geserve Shutcown Hours * /A N/A N/A

14. eeurs Generator On.Line i: / A N /A 27.777.'4

15. Lnit Reserve Snutdown Hours N/A N/4 N/A i t; . Gross freemal Energy Generated (MdH) N/A N/A 14.450.651.2

'. 7 . Gross Electrical Eeergy Generated (NH) *t / A *:/L '.. 836.935.0

18. Net Electrical Energy Generated (NH) 1 2 0.9 _ , -5.194 4.226.958

9. unit Service Factor N/A N/A_ _.

N/A

20. Lntt Availability Factor  ?;/ A N /.A _

N/A

21. :; nit Capacity Factor (Using MDC Net) N/A N/A /A

22. unit Capacity Factor (Using DER het) N/A N /L., N/A

23. Lnit Ferced Outage Rate M/A M / A_ t' / A 24 5%tcouns Scheculed Over hext 6 Months (Tyre. Date, and Duration of Each): Fort St. Vraiu ceased mcinne np rnrinn nn Aucust 29. 1949.

25. ;' St.ut Co.n At End of Reoort Period. Estimates Date Of Startuo: JA F recast Achieved

26. .ntts in ieM Status (Prior To Comercial 0;eration):

INITIAL CR!ilCALITY N/A N/A INITIAL ELECTRIClif N/A N/A COMMEPCIAL 0FERAT!0N N/A N/A i

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. AVERAGE DAILY UN11 POWER LEVEL 8 -

Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 DateA~rliT15 1992 O Completed By M. t. Bl,o_ck Telephone [I6K(20}jli[-~ "-~~[

Month MARCH DAY AVERAGE DA!LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (PWe-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 b.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 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 a Unit Fort St. Vrain.Un.it No. )

i Date April 15, 1992 ' ~ ~ ~

' Completed By M. T ~Bisck Telephone (303)[620'_13fl3' l~

REFUE_ LING INFORMATICN l l l

i 1. Name of Facility _ _ ._..___[ Fort St. Vrain Unit No 1 l l l I

l 2. Scheduled date for next i None, no further refueling at l l refueling shutdown. _ _ .___{ FSV is expected. _

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l 3. Scheduled date for restart l N/A l l following refueling.. j__________. _ . __ _ l I i 1

l 4. Will refueling or resumption ofl W/A l 1 operation thereafter require a l l l technical specification change l l 1 or other license amereent? _ ] __ _ _ _ . _ , _ , _ _ _ _ _ _ l 1 l l

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

l general a will these be? ___. __.j_ _ ___ _ ___ __

._, _ _ l l l l

} if answer is no, has the reloadl j o

l fuel design and core configura-l l tion been reviewed by your [ }

l Plant Safety Review Committee l N/A O l l

to determine whether any unre- 1 viewed safety questions are l l

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l l associated with the core reload! l l

l (Reference 10 CFR 5ection l l 50.59)? _____j_______ _ ._ _ .I I I I

I If no such review has taken l N/A 1 _

l place, when is it scheduled? J_ _ _ _,_ _._ ___l 1 I l

l 5. Seneduled date(s) for submit- 1 l l ting proposed licensing action 1 ---------------- l l and supportin,g information. _] _ _ , _ _ . _ _ ._ _ __ l l I l

l 6. Important licensing considera- ; l l tions associated with refuel- l l 1 ing, e.g., new or different i l fuel design or supplier, unre- 1 ---------------- I i

l viewed design or performance l l l analysis inethods, significant l l j

1 changes in fuel design, new l l_ operating _ procedures. _j __ _ _ _ _ _tl i I J 7. The number of fuel assemblies j l l (a) in the core and (b) in the i a) 330 HIGR fuel elements l l _ __ spent _ fuel st_orage_ pool. l b L 396 H' R fuq[ elements _ . _ l

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A REFUELINGINFORMATION(CONilNED)

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I 8. The present licensed spent fuell Onsite capacity is limited in l l pool storage capacity and.the l size to about one-third of core, l 4 l site of any increase in i 504 HIGR elements. Construction  !

j license d storage capacity that l of an Independent Spent Fuel i j has been requested or is l Storage Installation (ISFS!) I i planned, in number of fuel l with a capacity of 1620 FSV HTGR l l assemblies. I elements has been completad and l l l and the facility has been l l 1 licensed _by the NRC." ___l t I l l l 9. The projected date of the last l No further refueling is l l l refustling that can be dis- l anticipated at Fort St. Vrain. " l l l charged to the spent fuel pool l l l l assuming the present licensed l l l c_apa c i ty . . _ , .

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• The Independent Spent Fuel Storage Installation (ISFSI), which is ,

presently undergoing fuei 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 00E, spent

,O fuel discharged during the defueling process will be stored by DOE at the Idaho Chemical Processing Plant. The storage capacity is l

l 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, 1939.

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