ML20085D986

Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/

ML20085D986
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/30/1991
From:	Block M, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-91325, NUDOCS 9110170312
Download: ML20085D986 (8)

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16805 WCR 19 1/2, Platteville, Colorado 80651 October 15, 1991 Fort St. Vrain Unit No. 1 P-91325 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 205S5 Docket No. 50-267

SUBJECT:

SEPTEMBER, 1991, 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 September, 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.

Sincerely, M ,7714s,.u[m u D. W. Warembourg Manager, Nuclear Pro uction Fort St. Vrain Nuclear Generating Station DWW:MLB/as Enclosure cc: Regional Administrator, Region IV Mr. J. B. Baird Senior Resident Ir.spector Fort St. Vrain 9110170312 7109so F'OR ADOCK O'Jo00 M7 R PDR f f

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST VRAIN NUCLEAR GENERATING STATION-MONTHLY DEFUELING OPERATIONS. REPORT NO. 212:

September, 1991

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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. DPR-34. This report is for the month of September, 1991.

1,0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY-

-FELATED MAINTENANCE The reactor . remained shutdown the entire month of September.

-1991, following Public Service Company of-Colorado's decision to end nuclear operation at Fort St. Vrain. l

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Testing of- the Independent Spent Fuel Storage Installation (ISFSI) is proceeding.

On September 23, 1991, Public Service Company- of Colorado received notification of a favorable ruling from the Ninth Circuit Court- of Appeals which lifted the Stay that had prevented-shipment of spent _. fuel _ to the Idaho National . Engineering Laboratory. Preparations for spent fuel shipping are proceeding

- 2.0 SINGLE RELEASES-OF-RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF -10% OF THE ALLOWABLE ~ ANNUAL' VALUE None l 3.0 INDICATION- 0F FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS

-None i 4.0 MONTHLY OPERATING DATA REPORT L

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C;ERATip LATA REPORT DOCKET NO. 50-267 DATE October 15, 1991 COMPLETED BY M. l.. Block TELEPHONE (303) 620-1313 Ort n T: n s Tus NOTE",

1. Unit hame: Fort St. 'J r:11n d' nil No . 1

2. Re:orting ferioc: 41n001 tbrnugl910930

3. Licensed Themal Power (Mdt): 842 4 hameolate Rating (Gross MWe): 342

5. :esign Electrical Rating (Net Mie): 130

5. Patinum De?cndaole Capacity (Gross Ne): 342 Maximum DeDencable Capacity (Net Mde): _ 330 ,

E. Changes Occur in Capac1ty Ratings (;tems Nuneer 3 Tr.rougn 7) Since Last Report, G{ Feasons:

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9. %er t.evel To which Restrictec, If Any t het MWe): 0.0 4,

10. ;easons for Festrictions, If Any: part st. Venin renned nuclonr nenrnrinit,,2,W egust % 1080 This Month Year To Date CumJiative

11. Pours In Reporting Period 720 6,551 107,400

12. Num.oer Of Hours Reactor Was Critical N/A N/A _

'O.576.7

13. Reactor 4 serve Shutdown Hours N/A N/A N/A

14. curs Generator Or-Line N/A N/A 27.777.4

15. vnit Reserve Shutcown Hours N/A N/A N/A

16. Gross Themal Energy Generate WWH ) N/A N/A 14.4E0,65!.2 N/A

17. 3ross Eie:trical Energy Generated {MWH) N/A i R V 814.(L.,

13. Net Electrical Er.ergy Generated MWH) -1.473 -14,192 4.237.487

19. unit Service Factor y/A N/A N /L

20. Lnit Availability Facecr N/A N/A , N/L

21. Unit Cacacity Factor t using MDC Net) y/A N /A N/A

22. n1t Cacacity f actor tusing DER het) N/A N/A N/A

23. '. nit Forced Outage Rate e /3 y /3 y/3 2A. 5'ividowns Scheduled Over Next 6 Months (Type, Oate, and Duration of Eacn): Fort St. Vrain ceased nuc1.nr nnnrntinn nn Aucunt 29. 1989.

5. Snut Wn At End Of Pecort Period, Bt1matec Date Of Startup-  :/A F recast Achievea

5. nits ;r Test Status (Prior To Comercial Cceration):

INITIAL CRIT!CALITV N/A N/A INITIAL ELECTRICI!i tu A N/A

CMMERCIAL CPERATION N/A N/A

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 _ _ _

Unit Fort St. Vrain Unit No. 1 Date October 15, 1991 Completed By M. L. Block

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Telephone [303) 6_20-1313 2 __

Month SEPTEMBER _

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY 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 Nuclear Operations at Fort St. Vrain were terminated on August 29, 1989.

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-*' Docket No. 50-267 ~

Unit Fort St. Vrain Unit No.__1_ .

Date-October-15, 1991 Completed By M. L._ Block Telephone.(303) 620-1313  :

i REFUELING INFORMATION l- 1 I l 1. Name of Facility i Fort St. Vrain Unit No. 1 l I I I l-2. Scheduled date for next l None, no further refueling at l l refueling shutdown. j FSV is expected. I l - 1 l l 3. Scheduled date for restart l N/A l l- following refueling. l l l -

I l l 4_, Will refueling or resumption ofl N/A l l= operat_ ton thereafter require a l l l technical specification change l l or other' license amendment? l l i I If answer is yes, what, in_ l ---------------- l, ll Egenera'i, will these be? l l:

I - I .1 l ~If answer is no,3has the reload l

- 1 l fuel design and: core configura-1_ i

-l  : tion-been revlewed by your j i l Plant _ Safety Review Committee l N/A l

-] to determine whether any-unre- 1 l i viewed safety questions are l l l- associated with the core reload l l

l. (Reference 10 CFR Section l l l 50.59)? I l l- I -

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i If no such. review has taken- l N/A l l nlace, when is it scheduled?- l- -

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

-l- and supporting information. I l l -

l- I l 6. - Important licensing considera- l -l 1; tions associated with refuel- l l

-- l ~ing, e.g., new or different

. ] [

-i fuel design or supplier, unre- l----------------- l l- viewed design or performance l l

_l analysis: methods, significant i j 1; 1 changes.'in; fuel d' sign, new

. l l l coeratina procedures. l l l . l .I

. l: 7. The number of-fuel assemblies l l

-1 (a) in the core and (b) in_the I a) 1024 HTGR' fuel elements l L l spent fuel storage pool. I b) 452'HTGR fuel elements l-r a *

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_ REFUELING INFORMATION (CONTINUED)

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l l 8. The present licensed spent'fuell. Current capacity is. limited in l l- pool storage capacity and the l size to about one-third of core, l l_ size of any increase in l 504 HTGR_ elements. Construction lL

-l licensed storage capa; tty that-l of an Independent Spent Fuel- l

-l has been requested or is l Storage installation (ISFSI)-- . l 1 planned, in number of fuel I with a capacity of 1620 FSV HTGR I -

I assemblies. I elements is_ proceeding.* l l l l l 9. The projected date of the last l No further refueling is l l -refueling that can be dis- l 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-i I

- The' Independent Spent Fuel Storage-Installation (ISFSI) will be .

capable of storing the entire FSV core (1482 HTGR fuel elements) with

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storage space for an add;tional 138 HTGR fuel elements.

• • Under Agreemants AT(04-3)-633 and'0E-SC07-791001370 between Public Service Company of Colorado, General Atomic Comoany, and DOE, spent fuet discharged during the defueling process will be stored by 00E 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 DOE, Nuclear Operations at Fort St. Vrain were terminated August 29

-1989. -

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