ML20043G114
| ML20043G114 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/31/1990 |
| From: | Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-90192, NUDOCS 9006190076 | |
| Download: ML20043G114 (8) | |
Text
{{#Wiki_filter:, e . Public Sery ce' Oh ' P.o. Box B40 Denver. Co 80201 0840 , i 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 June 15,1990 Fort St. Vrain Unit No. 1 P-90192 l g U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 E Docket No. 50-267
SUBJECT:
MAY, 1990 MONTHLY DEFUELING - o OPERATIONS REPORT
REFERENCE:
Facility Operating License Number DPR-34
Dear Sirs:
Enclosed, please find the Monthly Defueling Operations report for the month of May, 1990, 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, mis Charles H. Fuller 7 Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF:DLW/bh l Enclosure cc: Regional Administrator, Region IV ATTN: Mr. J. B. Baird Technical Assistant Division of Reactor Projects Mr. Robert Farrell l Senior Resident Inspector, FSV Fort St. Vrain i j i 9006390076 900531 PDR lIl 1 R ADOCK 05000267 ) PDC ' l
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3 This report contains the highlights of the Fort St. Vrain, Unit t ' No. 1, activities operated under the provisions of the Nuclear
, Regulatory Commission Operating License No. OPR-34. This report is for the month of May,.1990.
1.0 NARRATIVE
SUMMARY
OF- OPERATING EXPERIENCE AND MAJOR SAFETY-
- RELATED MAINTENANCE 3 a The' reactor remained shutdown the entire month of May, 1990, .
following Public Service Company of Colorado's- decision to end nuclear operation at Fort St. Vrain. 1 Preparations for shipping spent fuel are proceeding. : n' 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS 0F 10% OF THE ALLOWABLE ANNUAL VALUE , 3< None , 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL (" @ $ATIONS Ncn,e 4.0MONT3L(,0PERATINGDATAREPORT , Nttached L i e i E h
5 s f~ OPERATING DATA REPORT DOCKET NO. 50-267 DATE June 19. 1000 COMPLETED BY M. 1- . Block TELEPHONE (303) 620-1180 OPERA?'N3 ST:.TUS N01&S
- 1. Unit hame: port St. Vrnin. l' nit No. 1
- 2. Peporting Period:
- 3. Licensed Thermal Power (MWt): 842 l- '4 hameplate Rating (Gross MWe): 342
- 5. Oesign Electrical Rating (Net MWe): 330
- 6. Maximum Dependable Capacity (Gross MWe): 342
- 7. Maximum Depencable Capacity (Net MWe): 330 ,_
B. Changes Occur in Capacity Ratings (1: ems humper 3 Througn 7) Since Last Report. Give Reasons: Nnno ,
- 9. Fower Level To Which Restricteo. If Any (Net MWe): 0.0
- 10. Reasons for Restrictions. If Any: port St. Venin enn=ca nucione nnerneinn nn Anonne 90. Toro.
This Month Year To Date Cumulative-
- 11. Mours In Reporting Period 744 3.623 95.712
- 12. Nunoer Of Hours Reactor Was Critical N /A N /A lin . 5 7K . 7
- 13. Reactor Reserve Shutoown 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. ' Gross Electrical Energy Generated (MWH) N /A N/A 4.996.R14.0
- 18. Net Electrical Energy Generated (MWH) -1.742 -0.350 4.263.654 l
- 19. Unit Service Factor N/A N /A M/A I
- 20. Lnit Availability Factor N/A N/A N/A ;
- 21. Unit Capacity Factor (Using MOC Net) n /A N/A N/A ;
- 22. Unit Capacity Factor (Using DER Net) N/A N/A N/A
- 23. Unit Forced Outage Rate v /A y/A w /i
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): Fort St. Vrain ceased nuc1one nnorneinn nn Aucust 29. 1989.
- 25. *f Shut Down At End Of Report Pertoa. Estimated Date Of Startup: N/A
- 26. ; nits In Test Status (Prior To Connercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A
~
COPHERCIAL OPERATION N/A N/A i
+- AVERAGE DAILY UNIT POWER LEVEL
^*l Docket No.-50-267 Unit' Fort St. Vrain Unit No. 1 "
,Date June 15, 1990 [
Completed By M. L. Block Telephone (303) 620-1180 , Month MAY ! DAY AVERAGE DAILY POWER-LEVEL DAY AVERAGE DAILY POWER LEVEL .i (MWe-Net) (MWe-Net) ., 1 0.0 17 0.0 -
'2 0.0 18 0.0 l -t 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 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. If 4
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REFUELING INFORMATION l l l ! 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. l FSV is expected. l. !
I I l i l 3. Scheduled date for restart l N/A l i j following refueling. l l l l 1 l l 4. Will refueling or resumption ofl N/A l t I operation thereafter require a l l j l- technical specification change l l l or other license amendment? l l
-l .
I I ! l If answer is yes, what, in l ---------------- l ! l general, will these be? l l l l I ; I If answer is no, has the reloadl l i l fuel design and core configura-l l l tion been reviewed by your l l ll l Plant Safety Review Committee l N/A l I to determine whether any unre- l l l viewed safety questions are l l i l associated with the core reloadj l l (Reference 10 CFR Section l l l 50.59')? i _ l l . I I i l If no such review has taken l N/A l l place, when is it scheduled? l ,_ l l l l l 5. Scheduled date(s) for submit- l ~l ; I ting proposed licensing action l ---------------- l '! l and supporting information. l l I . I l i l 6. Important licensing considera- l l ;
- j tions associated with refuel- l l ;
l ing, e.g., new or different l l i j fuel design or supplier, unre- l ---------------- l l viewed design or performance l l l analysis methods, significant l l 4 l changes in fuel design, new l l l operating procedures. I l 1 I __ I l 7. The number of fuel assemblies l l l (a) in tte core and (b) in the l a) 1023 HTGR fuel elements l l spent fuel storage pool. I b) 447 spent fuel elements I 1
l 4
- REFUELING INFORMATION (CONTINUED)
I I I l 8. The present licensed spent fuell l , I pool storage capacity and the l l l size of any increase in l Capacity is limited in size to l l licensed storage capacity that I about one-third of core l l has been requested or is l (approximately 500 HTGR elements).l l planned, in number of fuel l No change is planned. l l assemblies. l l ! I I 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 charged to the spent fuel pooi l l l l l assuming the present licensed l l
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l capacitv. l l l 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. TS storage capacity is presently sized to accommodate eight fuel segmants. It is estimated . that the eighth fuel segment will be discharget in 1991. Discussions I concerning the disposition of ninth fuel segment are in progress with 00E, Nuclear Operations at Fort 5ts Vrain were terminated August 29, l 1989. ; i 4 1 _ _ _ _ _ _ _ _ _ o}}