ML20090L062
| ML20090L062 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/29/1992 |
| From: | Block M, Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-92108, NUDOCS 9203200053 | |
| Download: ML20090L062 (9) | |
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-J6805 WCR;19 1/2, Platteville, Colorado 80651 March.3, 1992 Fort St.-Vrain Unit'No. 1
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P-92108
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_0. S Nuclear Regulatory Commission-ATTN: -Occument Control Oesk Washington, D.C.
- 20555 1
Docket No. 50-267
SUBJECT:
FEBRUARY,- 1992, MONTHLY DEFUELING OPERATIONS REPORT
REFERENCE:
Facility' Operating
- License Number DPR-34~
Dear 5 irs.
Enclosed, please find the Monthly Defueling Operations report for the s-month cf February..:1992,. submitted per the requirements of Fort.St.
Vrain Technical Specification AC 7.5.1.
- !f.you have any' questions,- please contact Mr.
M. H. Holmes-at
-(303) 620.-1701.
Sincerely, th)h1 Yam, bua D. W,:Varembourg_
J L-Manager, Nuclear Oaerations
- Fort St, Vrain Nuclear Generating. Station
-DWW:MLB/as' Enc'losureD cc:. Regional Administrator, Region'IV-Mr.. J. ' B, ' Bai rd.
-Senior. Resident Inspector Fort St,1Vrain p
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16805 WCR 19 1/2, Platteville, Colorado 80651 March 13, 1992 Fort St. Vrain Unit No. 1 P-92108 U. S, Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
J0'55 docket No. 50-267
SUBJECT:
FEBRUARY, 1992. MONTHLY DEFUELING OPERATIONS REPORT
REFERENCE:
Facility Operating License Number DPR-34
Dear Sirs:
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Enclosed, please find the Monthly Defueling Operations report for the month of Februery, 1992, submitted per the requirements of Fort St.
Vraia Technical Specification AC 7.5.1.
If you have any questions, please contact Mr.
M. H. Holmes at (303) 620-1701.
Sincerely,
- 0 V Wew s.Jue.
D. W. Warembourg u
Manager, Nuclear Operations Fort St. Vrain Nuciece Generating Station DVW:MLB/as Enclosure cc: Regional Administrator, Region IV Mr. J. B. Baird Senior Resident inspector Fort St. Vrain
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. 'JRAIN NUCLEAR GENERATING STATION O
f MONTHLY DEFUELING OPERATIONS-REPORT l
NO. 217 1
February, 1992 s
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This report contains the highlights af the Fort St. Vrsin, Unit No. 1, activities operated under the provisions of the Nuclear Regulatory Commissien Operating License No. OPR-34. This report is for the month of February,1992.
1.0 ~ NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown the entire month of February, 1992, following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain.
During the mo.ith of February,1992, thirty-eight loads (228 fuel elements) were deposited in the Fort St. Vrain Independant Spent Fuel Storage Installation (ISFSI).
2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS 0F 10*.' OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached O
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OPERATING DATA REPORT DOCKET NO.
50-267 DATE March 11. 1447 COMPLETED B'l M. L. Block TELEPHONE (303) 620-1313 OPERA?'*1 ST'TUS NOTES 1.
Unit han.e:
Fort St. Vrnin. Unit No. I 2.
Reporting Period:
920201 through 920229
- 3. - Licensed Therrial Power (MWt):
842 4.
Namentate Rating (Gross MWe):
342 5.
Cesign Electrical Rating (Net MWe):
330 e.
Maximum Decencable Capacity (Gross MWe):
342
- 7. ' Maximum Oeoencable Capacity (Net MWe):
330 6.
- ' Changes Occur in Capacity Ratings (items humoer 3 Througn 7) Since Last Report. Give Reasons:
None 9.
fe.er Level To Which Restrictt:c, If Any thet MWe):
0.0
- 10. Eeasons For Restrictions, if Any:
Fort Sr. Vrnin cenned nuclonr nnornMgn nn Atenct 79. 10R9.
-( O This Month Year To Date Cumulative
- 11. Hours in Reporting Period 696 1.d40 111 044
- 12. Numoer Of Hours Reactor Was Critical N/A N/A
!in. 5 7K _7
- 13. Feactor Reserve Shutdown Hours N/A N/A_
N/A
- 14. hours Generator On-Line N /L N/A 27.777.4-
- 15. Lnit Reserve Shutdown Hours N/A N/A N/A
- 16. Gross Thermal Energy Generated (MWH)
N/A N/A 14.450.651.2 17; 3ross Electrical Energy Generated (MWH)
N /A N/A 4.R16.814.0
.18.
het Electrical Energy Generated (MWH)
-1,603
-3,385 4.228.767
- 19. Unit Service Factor N /A N/A N/A
- 20. Lnit Availability Factor N/A N/A N/A
- 21. Lntt Caoacity factor (Usina MDC Nett s/A N/A N/A 22.
t, nit Capacity Factor (Using DER Net)
N/A N/A N/A
- 23. _Lnit Forced Outage-Rate y/A y/A M/A 24 Shutdowns Scheduled Over Next 6 Months (Type, Cate, and Duration of Each):
Fort St. Vrain ceased nonlone nnnenednn nn Aucust 20
- 1099,
- 25. :' Shut Down At End'0f Report Perioc. Estimated Date Of Startup:
N/A Forecast Achie ud
- 26. Lnits in Test Status (Prior To Comercial Operation):
INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A
AVERAGE DAILY UNIT POWER' LEVEL DocLet No. 50-267 Unit' Fort St. Vrain Unit No. 1 Date Rarch 13 1992 x
Completed By M. L. Block Telephone (303)- 620-1313 Month FEBRUAr,y DAY AVERAGE DAI_LY POWER LEVEL DAY 3VERAGE 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 J.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 N/A 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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UJjiT' SHUTDOWNS'AND POWER REDUCT4ONS--
T DOCKET NO. 50-267 UNIT NAME. Fort St. Vra in Unit No. 1 DATE Ma rch 13. 1992 COMPLETED BY U. Block TELEPHONE ( 3031 620-1313 REPORT MONTH FEBRUARY. 1992'
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-l l SHUTTING l l.
l l CAUSE AND CORRECTIVE ~ACT3ON NO.
DATE.lTYPE DURATION REASON LDOWN l
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!SYSTEMICOMPONENT l' TO PREVENT RECURRENCE '
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l 1 REACTOR l (CODE ICODE l-l l
' 89-09 920201 i F I 696.0 l
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l August 29 1989, see LER 89-018.
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Docket No. 50-267
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Unit Fort St. Vrain Unit No. 1 Date March 13, 1992 Completed By M. L. Block Telephone (303) 620-1313 REFUELING INFORMATION l
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l 1.
Name of Facility I Fort St. Vrain Unit No. I
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l 2.
Scheduled date for next l None, no further refueling at l
l' refueling shutdown.
I FSV is expected.
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Scheduled date for restart l N/A l
l following refueling.
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Will refueling or resumption ofi N/A l
l-operation thereafter require a l l
- l technical specification change l l
.l or other license amendment?
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If answer is yes, what, in l ----------------
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general, will these be?
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If. answer is no, has the reload l l
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_ fuel design and core configura-l l
l tion been. reviewed by your l
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_ Plant Safety Review Committee l N/A l
_ l to determine whether any unre-l l
l viewed safety questions are l
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associated with the core reloadl l
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(Reference 10 CFR Section l
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_ l-50.59)?
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If no such review has taken l N/A l-l
-place, when-is it scheduled?
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Scheduled date(s) for submit-l l
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ti ng proposed licensing acti on l ----------------
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and supporting information.
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- l l 5.. Important licensing considera-l
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tions associated with refuel-l-
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- ing, e.g., new or_different l
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fuel--design or supplier, unre-l ----------------
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.. viewed design or performance l
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analysis methods, significant l
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changes in_ fuel design, new l
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- l-
-operating procedures.
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l.7.
The number of fuel assemblies l
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- l (a) in the core and (b) in the I a) 580 HTGR fuel elements
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_ l spent fuel storage pool.
I b) 392 HTGR fuel elements l
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4 REFUELING INFORMATION (CONTINUED) i-
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The present licensed spent fuell Onsite capacity is limited in l
l pool storage capacity and the j size to about one-third of core, j
l size of any increase in l SO4 HTGR elements. 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.
l elements has been completed and l
l l and the facility has been l
l l licensed by the NRC.*
l 1
1 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
The Independent Spent Fuel Storage Installation (ISFSI), which is presently undergoing fuel 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 DOE, 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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