ML20086C545

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

ML20086C545
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/31/1991
From:	Block M, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-91373, NUDOCS 9111220296
Download: ML20086C545 (8)

Text

.- .. . _ . _ . _ . . . . __

'e

-. y e-

• i l

Public Service 1 c-  :

0 PublicService' i 1

16805 WCR 19 1/2, Platteville, Colorado 80651 November 15, 1991 Fort St. Vrain Unit No. 1 P-91373

.U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

. OCTOBER, 1991, MONTHLY DEFUELING OPERATIONS REPORT

REFERENCE:

Facility Operating.

License Number DPR-34

Dear' Sirs:

Enclosed, ple'ase find the Monthly Defueling Operations report ior the month of October, 1991, submitted per the requirements of Fort St.

Vrain--Techn? cal Specification AC 7.5.1.

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

Sincerely, b /}'- WantuAbt.

D. W. Warembourg Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station DWW:MLB/as Enclosure cc: Regional Administrator, Region IV Mr. J. B. Baird Senior Resident Inspector Fort St. Vrain bbbk $ddhjjg.

PDR v d

1 -c r-.- ., ,. - = ~ - - - - . . .

1'~ .

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

.j '

MONTHLY DEFUELING OPERATIONS. REPORT NO. 213

^

October, 1991 i-

^

4 i

p l?

y 'wN V y T F 1-rr'r'ey s'J-waw ' rf"M w v m (y yp- 'T'*q-T- M- y ww h- *nhus--' 'M ' e %4. er- W +',% 1, ."e31%-+' N 3 1- e Y' '--

W-W

C ..

4 This report contains cthe highlights of the Fort St. Vrain, Unit 110 . - 1, activities operated under the provisions of the Nuclear Regulatory Commission Operating License No. DPR-34. This report is for the month of October, 1991.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR - SAFETY REU~TTD MAINf~ETANCE

~Thc reactor remained shutdown the entire month of October, 1991, following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain.

Testing of the Independent Spent Fuel . Storage Installatioen (ISFST) is proceeding.

-Curing the month of Octobar, 1991, Public-Sarvice Company of I Colorado made 3 spent fuel shipments to the Idaho National Engineering Laboratory. Further spent fuel shipments-have been ,

suspended pending resolution of Idata Stat - Air Quality Permit l and Shoshone-Bannock Tribe iss es. Pitoa ations for transferring i spent fuel to the ISFSI are proceeding.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10P. OF' THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTPLY CPERATING DATA REPORT Attached I

l i

(

l

OPERATING DATA REPORT DOCKET NO. 50-267 ,

DATE November 15. 1991 COMPLETED BY M . 1. . Block TELEPHONE (303) 670-1313 OPERAT'*G STtTUS

~IIOTES

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

2. Reporting Period: 911001 thrnunh 411011

3. Licensed Themal Power (MWt): 842

4. Nameplate Rating (Gross MWe): 342

5. Design Electrical Rating (Net MWe): 330

6. Maximum Dependable Capacity (Gross MW.3): 142

7. Maximum Deceno3 Die Capacity (Net MWe): 330

8. I' Changes Occur in Capacity Ratings (!tems humper 3 Througn 7) Since Lott Report

• Reasons:

Nonn

9. Power Level To Which Restricted, if Any (Net MWe): 0.0

10. Reasons for Restrictions, if Any: Fort 9t. Vrnin cenned mirl ent n,nrntinn nn Anmmt '9- 19R9.

This Month Year To Date Cumulative

11. Hours in Report 1ng Perted 744 7.296 10R_149

12. Numoer Of Hours Reactor Was Critical N/A N/A 40_97Fi 7

13. Reactor :eserve Shutt'own Hours N/A N/A N/A

14. Hours Generator On.Line N/A N/A 27.777.4

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

16. Gross Thermal Energy Generated (MWH) N/A N/A 14.450.651.2 17 iross Electrical Energy Generated lMWH) N/A N/A_ 4.816 R14.0

18. Net Electrical Energy Generated (MWH) -1.704 -15.896 '4.935.783

19. Unit iervice Factor N/A N/A N/A

'20. Lnit Ava11acility Factor N/A N/A N/A

21. Unit Cacacity factor (Using MDC Net) N/A N/A N/A

22. Unit Cacacity Factor (Using DER Net) N/A N/A N/A f _

l 23. Unit Forced Outage Rete y/a y/a y/A

24. Shutdowns Scheduled Over Next 6 Months (T / pe, Cate, and Duration at Each): Fort St. Vrain ceased nncinar nnornrinn nn Ancunt 29. 1989.

25.  ;' Shut Cown At End Of Report Pertoa Estimated Date Of Stariso: N/A Forecast Achieved

26. units in Test Status (Prior To Commercial Oceration):

Ih!TIAL CRITICALITY N/A N/A INITIAL. ELECTRICITY h/A N/A COMMERCIAL OPERATION N/A N/A 1

l

.. , . - -. -- ., - . . .~ ....

s.

,- -AVERAGE DAILY-UNIT POWER LEVEL

~

. Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date. November 15, 1991 Completed By M.-L. Block Telephone (303) 620-1313

-Month OCTOBER OAY 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 0.0 16 0.0 Nuclear Operations at Fort St. Vrain were terminated on August 29, 1989.

'l l

1 i

l i

UNil SituTDOWNS AND POWER REDUCTIONS ,.

DOCKET NO. 50-267 UNIT NAME fort St. Vra in Uni t No. 1 DATE Novembe r 15, 1991 COMPLETED BY M. L. Block TELEPHONE L391) 620-1313 REPORT MONTH CCTOBER. 1H1 1 1 1 1 1 INEIHOD Oti i i i l i I  !  ! I ISHUTTING l i I I CAUSE AND CORRECTIVE ACT'ON I I NO. I DATE ITYPEl DURATION l REASON IDOWN i LER # ISYSTEMICOMPONENT! TO PREVENT RECURRENCE i i i i  ! I IREACTOR ! l CODE ICODE I I I l l 1 1 I I I I I i 189-091 911001 i f i 7%.0 i f i 1 l N/A I N/A l N/A l Nuc lea r Opera t ions were termina ted on f i l I i i l i I i I August 29, 1989, see LER 89-018. 1 I i l I i l i I I I i i i i l I I i l i I I i  ! 1 1 I I I I i i l i  ! I i l i I I I I I I I I I I I I I I I I I i 1 1  ! I I i l i l  ! I I I I I i l i i i l i l i  !

I I i l I 1 i l i I I I I I i l i i 1 1 1 I i i i l i i 1 1 I I I I i i l I i l i I I  !.

I I i l i 1 I i l I i l I I i l I i l i I I i i i l I  ! I I I I I i l I I i 1 i l i  !

I i l i i i I I I i i l I i i l  ! I I I I i l I i e i i i i l i i r i I I i l* i i 1 I i 1 1 1 I l I i  ! I I i l I i i i l i i i i i l I i i  ! I I I i i l i i i i l i I I I i i l i l I i l 1 I i i I I i l i I i I I i l 1 1 l 1 I i i l i i i i i l i 1 I I I i l i . I I I 1 1 I I I I I I I I I I I I I I I I i i l 1 I i i i i l i l I I l  !  ! 1 1 I I i 1 I I I I i  ! l I I I I l

].

Docket No. 50-267-Unit Fort St. Vrain Unit No. 1

'. Date November 15, 1991 Completed By M. L. Block Telephone (303) 620-1313 REFUELING.INFORMATION I I I

] 1. Name of Facility l Fort St. Vrain Unit No 1 l l 1 -l l 2. Scheduled date for next i None, no further refueling at l l refueling shutdown. I FSV is expected. [

l i I l 3. 3cheduled date for restart l N/A l

_l following refueling. 1 [

l I l l 4. Will refueling or resumption _ofl N/A l

.l operation thereafter require a l l l technical specification change ! [

] or other license amendment? l l I I I l If answer is yes, what, in l --------------- - [

l general, will these be? I l l 1 l l If answer is no, has the reloadj l l fuel design and core configura-l l l- tion been reviewed by your l l

l. Plant Safety Revi_ew 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 reloadi l l (Reference 10 CFR Section l l l 50.59)? l [

l I l

-l If no.such review has taken l N/A [

l place, when is it scheduled? l l l l 1 l 5. Scheduled date(s) for submit- l l l ting proposed licensing action [ ---------------- [

] and supporting information. l l l l l l 6. Important licensing considera- l l l tions associated with refuel- l l l ing', e.g., new or different l l l f uel de si gn or suppl i e r, unre- l ---------------- 1

'l viewed design or performance l l

-1 analysis methods, significant l l l changes in fuel design, new l 'l l operating procedures. _[ l 1 1 I l 7. The number of fuel assemblies I l l (a) in the core and (b) in the l a) 1024 HTGR fuel elements l l spent fuel storage pool. -l b) 440 HTGR fuel elements l

, REFUELING INFORMATION (CONTINUE 0) l .

I -l

, l 8. The present licensed spent fuell Curi-et capacity is limited in l l pool storage capacity.and the I size o about one-third of core, I l size of any increase in . ] 50~. L. 1 clements. 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 I with a capacity of 1620 FSV HTGR .l l assemblies. I elements is proceeding.* l 1 1 1

- 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 j assuming the present licensed l l l capacity.- l l The Independent Spent Fuel Storage Installation (ISFSI) will be capable of storing the entire FSV core (1482 HTGR fuel elements) with storage space for an additional 138 HIGR fuel elements.

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 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. Otscussions concerning the disposition of ninth fuel segment are in progress with 00E. Nuclear Operations at Fort St. Vrain were terminated August 29, 1989.

I i

l I

l 1

-