ML20154H533
| ML20154H533 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain |
| Issue date: | 08/31/1988 |
| From: | Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| P-88336, NUDOCS 8809220041 | |
| Download: ML20154H533 (8) | |
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PUBLIC SERVICE COMPANY OF COLORADO t
T FORT ST. VRAIN NUCLEAR GENERATING STATION i
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I MONTHLY OPERATIONS REPORT
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NO. 175 f
I August, 1988 i
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SSO9220041 880831 I
PDR ADOCK 05000267 i
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4 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. OPR-34. The report for the monthly partial scram / maximum temperature reports for control red drive and orificing assemblies is not included this month because the reactor was not in operation.
This report is for the month of August, 1988, 1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown the entire month of August, 1988, for helium circulater bolt replacement.
On August 16, 1988, Public Service Company of Colorado notified the NRC of a change in the CONTEMPT-G comouter program utilized in developing the Fort St. Vrain E.O. temperature profiles. This j
change caused the CONTEMPT-G program to calculate lower peak building temperatures for certain small line break scenarios.
This event will be investigated and reported to tne Nuclear Regulatory Commission in Licensee Event Report 88-012.
On August 29, 1988, at 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />, while preparing "C" helium circulator for bolt replacement, five personnel received minor contamination on their hands and feet when helium and water sprayed out of the circulator interspace. The personnel and the area were decontaminated with soap and water. Calculated whole body costs were determined to be negligible.
During this month, bolts in Loop I helium circulators were replaced and the loop was returned to service.
Bolts in Loop II helium circulators will be replaced during the month of Septemcer, 1988.
2.0 $!NGLE RELEASES OF RADICACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10*. OF THE ALLOWABLE ANNUAL VALUE None
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2-I 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL l
EXAMINATIONS P
None 4.0 MONTHLY OPERATING DATA REPORT Attached 5.0 CONTROL R00 DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT Not required this month, t
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OPERATING DATA REPORT 00CKtt h0.
50-267 OAft Sentenber 15. 1988 COMPLETED BY M.
I,. Block TELEPHONE (303) 620-1180 OPERAT!hG STATUS h0Tt5 1.
Unit hariet Fort St. Vrain. I' nit No. 1 2.
Reporting Period:
880801 through 880831 3.
Licensed Therir.41 Power (Fdt):
842 4.
Nameplate Rating (Gross Fde):
342 5.
Design Electrical Rating (het F.e):
330 6.
Maximum Dependable Capacity (Gross Fse):
342 7.
Maxirum Dependable Capacity (het Fde):
110 C.
If Changes Oc;ur 1r. Capac*.ty Ratint,s (!ters hwmeer 3 Through 7) Since Last Report. Give Reasons:
None 9.
Power Level To khich Restricted. If Any (het Fne):
270.6
- 10. Ressor.s For Restrictions. If Any:
Reanalysis of safe shutdevn cooling following a 90 minute interruption of forced cooline.
This Month fear to Date Cumulative
- 11. Hours in Reporting Period 7&4 5.855 80.400 12 huner Of Hours Reactor has Critica) 0.0 3.798.1 37.244.8
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On Line 0.0 3.487.3 25.072.8 _
15 Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thereal Energy Generated (F.H) 0.0 1.954.375.5 12.887.110.1
- 17. Gross Electrical Energy Generated (FnH) 0.0 718.184.0 4.260.404.0
- 18. het Electrical Energy Generated (FeH)
-2188
_ 670.805.0 3.761.071.0
- 19. Unit Service Factor 0.0 59.6 31.2
- 20. Unit Availability Factor 0.0 59.6 31.2
- 21. Unit Capacity Factor (Usirg MDC het) 0.0 34,7 14.2
- 22. Unit Capacity Factor (Using OtR het) 0.0 34.7 14.2
- 23. Unit Forced Outage Rate 100.0 _
40.4 62.5 24 5hutde=ns Schecsled Over heut i Montns (Type. Cate, and Dsration cf tach):
Helium Circulater Repairs.
880901. 960 hours0.0111 days <br />0.267 hours <br />0.00159 weeks <br />3.6528e-4 months <br />.
- 25. If 5mst 00=n At (no Of Report Perica, titiratec Cate Of 5tartuo:
October 11. 1989 2f. Lnits In Test $tatus (Prior To Comercial Operation):
Forecast Achievec INITIAL CRITICAL!TV
%/A N/A I't!TIAL !.!*TRICITi hia N/A COPERCI AL CFIRATICN N'A N/a l
l AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date Septemoer 15,1988 Completed By M. L. Block l
Telephone (303) 620-1180 Month AUGUST I
l OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
(Mde-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 t
9 0.0 25 0.0 10 0.0 26 0.0 l
U 0.0 27 0.0 12 28 0.0 0.0 13 0.0 29 0.0 l
i la 0.0 30 0.0 15 0.0 31 0.0 l
l 16 0.0 i
Generator en line cut no net gereration, j
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At tactet TSP-3C tsaue 2 Page 1 of 1 mlJJnvIlxwM1JNopB_ Ell 2EDMS pocetti neo. lrQ-267 unir mA sc Le n J t.
vrain Unit peo. 1 DATC 391eea tr_nJpe n
COMPLETLD SY M. L Block ittt PHoest 130))._620-1180 RIPORI MONIM AUGUST. 1905 3 ~ l~
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i m/A I Att I cme i Reactor Manua s sy st=tdown f or scheduled
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I Rep sacement or po s sum Ci rcusator so f ts.
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REFUELING INFORMATION I
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Name of Facility I Fort St. Vrain Unit No. 1 l
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Seneduled date for next l
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refueling shutdown.
l April 4, 1989 l
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Scheduled date for restart i May 27, 1989 l
l following refueling.
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Will refueling or resumption ofl No l
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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
l fuel design and core configura-l l
l tion been reviewed by your l
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Plant Safety Review Comittee l No l
l to determine whether any unre-l l
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viewed safety cuestions are l
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l associated with the core reloadj l
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50.59)?
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Olace, when is it scheduled?
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Scheculed date(s) for submit-l l
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- ing proposee licensing action l --"----~-------
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an: sceporting information.
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I portant licensing considera-l l
l tions associated with refuel-l l
l ing, e.g., new or different l
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l fuel cesign or supplier, unre-1 ----------~----
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viewee cesign or performance l
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analysis eethods, significant I l
I changes in fuel cesign, new l
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l eeerating otocedures.
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(4) in the ccre and (b) in tee I a) 14S2 HIGR fuel ele-ents 7
l seent fuel storage tool.
! b) O scent fuel elements l
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P REFUELING INFORMATION (CONTINUED) i i
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The present licensed spent fuell l
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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
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planned, in number of fuel l No change is planned.
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assemblies.
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The projected date of the last l 1996 undt* Agreements AT(04-3)-633l I
refueling that can be dis-l and DE-St07-791001370 between l
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charged to the spent fuel pool l Public Service Company of I
l assuming the present licensed l Colorado, and General Atomic l
l caeacity.
I Ceepany, and 00E.*
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The 1996 estimated date is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by DOE at the Idaho Chemical Processing Plant.
The storage capacity has l
evidently been sized to accommodate eight fuel segments.
It is l
estimated that the eighth fuel segment will be discharged in 1996.
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4 0 Public Serv:ce~
Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 September 15, 1988 Fort St. Vrain Unit No. 1 P-53336 U. 5. Nu: lear Regulatory Commission ATTN:
Docu ent Centrol Desk Washington 0.C.
20555 Docket he. 50-267 SLEJ ECT :
AUGUST 193E MONTHLY OFERATICNS REPORT
REFERENCE:
Facility Operating License Nu cer OPR-34 Cear Sir:
En:lesec, please find the Monthly Creratiers Report for tne month of August 1933, suo-ittec cer the recuirerents of Fort St.
Vrain Te:hnical Specifi:4 tion A: 7.5.1.
If you have any cuestions, please contact Mr. M. H. Holres at (303) 450-6960.
Sir:erel),
C A \\,W %f C. H. Fuller Marager, Nuclear Frecu:tien Enclosure cc:
Re;ienal A::?inistratcr, Regier IV ATTN:
Mr. T. F. 'ne:,terman, Cnief Freje:t Se:tien E Mr. R: tert Farrell Serier Resi:ent Insce: tor, F5V Fort St. Vrain CHE:kad
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