ML20149F844
| ML20149F844 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/31/1988 |
| From: | Novachek F, Robert Williams PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 168, P-88071, NUDOCS 8802170402 | |
| Download: ML20149F844 (9) | |
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT l
NO. 168 January, 1988 i
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8802170402 880131 ~~
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[N PDR ADOCK 05000267
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, n This : report contains _the highlights of the Fort St. Vrain, Unit No. 1,-activities : operated under the : provisions of the - Nuclear
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Regulatory. Commission.0perating License No. DPR This_ report is' L
for the month of January, 1988.
1.0 NARRATIVE
SUMMARY
OF-OPERATING EXPERIENCE AND-MAJOR SAFETY RELATED MAINTENANCE l
L The reactor remained critical and the turbine generator. remained in_ service throughout the month of January, 1988.
On January 2, 1988, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, "B" helium circulator tripped I
on program speed mismatch as.the reactor. operator attempted to j
place handswitch SC-2111~ -- i n - "Remote / Auto".
Subsequent investigation determined that a solenoid valve on SV-2111 had failed.
The solenoid valve SV-2111 was repaired and."B" helium L
circulator was returned to service at 0330- hours on -January 5, I
1988.
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As reactor power was increased toward 70%, total primary coolant oxidants' trended upward as expected..The 10-day grace period for LCO 4.2.10 was entered at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on January 6, 1988, when the i
l total oxidants exceeded.10 ppm. primary coolant oxidants peaked at 28.2 ppm at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on January 7, 1988. Total primary-l coolant oxidants were reduced to less 'than 10 ppm and the LCO 4.2.10 10-day grace period was exited at-2300 hours on January 10, 1988.
On January 14, 1988, at 0913 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.473965e-4 months <br />, "C" helium circulator tripped l
on buffer-mid-buffer during troubleshooting of FV-2272.
The i
. reactor was automatically runback.
"C" helium circulator was i'
returned to service at 2002 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.61761e-4 months <br />.
l Reactor power was increased and reached approximately 77% on January 16, 1988. This started the first period of sustained operation above 72% since September, 1983.
On January 21, 1988, reactor power was reduced to approximately 55% to repair a leak in the Loop I attemperation line.
At 1719 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.540795e-4 months <br /> an automatic control rod runback to 30% and subsequent manual turbine generator load reduction occurred while work was l-being performed on a flow modifier associated with attemperation.
1 The plant was recovered and returned to 55% power at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />.
Repairs to the Loop I attemperation line were completed and the reactor was returned to 77% power on January 22, 1988.
On January 25, 1988, at 1649 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.274445e-4 months <br />, a reactor runback to 60%
_, i occurred during surveillance pulse testing.
The reactor was returned to 77% power at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.
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L 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10*. OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED-FUEL
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EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached i'
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t OPERATING DATA REPORT D0CKET N0.
50-267 DATE February 12. 1988 COMPLETED BY F. J. Novachek TELEPHONE (303) 620-1007 OPERATING STATUS h0TE5 t
1.. Unit Name:
Fort St. Vrain. Unit No. 1
- 2.
Reporting Period:
880101 throuah 880131 3.
Licensed Thermal Power (MWt):
842 4.
Nameplate Rating (Gross MWe):
342 S.
Design Electrical Rating (Net MWe):
330 6.
Maxia.we Dependable Capacity (Gross MWe):
342 7.
Maximum Dependable Capacity (Net MWe):
330 8.
If Changes Occur in Capacity Patings (Items Number 3 Through 7) Since Last Report, Give Reasons:
None 9.
Power Level To Which Restricted. If Any (Net MWe):
270.6
- 10. Reasons For Restrictions, if Any:
Reanalysis of safe shutdown coolina followina a 90 minute interruntion of forecd enolina.
This Month Year To Date Cumulative
- 11. Hnurs In Reporting Period 744 744 75.299
- 12. Number Of Hours Reactor Was Critical 744.0 744.0 34,190.7
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 744.0 744.0 22.329.5
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 x
- 16. Gross Themal Energy Generated (MWH) 402.862.8 402.862.8 11.336.197.4
- 17. liross Electrical Energy Generated (MWH) 151.431.0 15].431.0 3.693.651.0
- 18. Het Electrical Energy Generated (MWH) 143.462.0 143.462.0 3.259.499.0
- 19. Unit Service Factor 100.0 100.0 29.7
- 20. Unit Availablilty Factor 100.0 100.0 20.7
- 21. Unit Capacity Factor (Using MDC Net) 58.4 58.4 13.1
- 22. Unit Capacity Factor (Using DER Net) 58.4 58.4 13.1
- 23. Unit Forced Outage Rate 0.0 0.0 63 R 24 Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
Helium Circulator Repairs. 880312. 2.303.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />
- 25. If Shut Down At End Of Report Period Estimated Date Of Startup:
N/A
- 26. Units In Test Status (Prior To Comercial Operation):
Forecast Achieved INITIAL CRITICALITY N/A N/A
!NITIAL ELECTRICITY
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N/A COMMERCIAL OPERATION N/A N/A a
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AVERAGE DAILY' UNIT-POWER LE"El Docket No. 50-267
-Unit Fort St. Vrain Unit No. 1 Date February 12, 1988 Completed By e. J. Novachek Telephone (303) 620-1007 Honth JANUARY DAY AVERAtlE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 73.3 17 242.7' 2
70.0 18 214.8 3
69.4 19 237.4 4
72.2 20 214.6 l
5 93.3 21 145.2 6
146.3 22
-217.5
.7 203.0 23 235.0 8
217.3 24 237.8 9
216.2 25 230.8 10 214.4 26 239.1 11 213.4 27 233.3 12 215.1 28 236.5 13 231.0 29 234.7 14 136.8 30 233.5 15 159.8 31 235.1 16 231.3 Generator on line but no net generation.
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- k TSP-3 Attachment TS P-3C Issue 2 LHili SHUTDOWNS A800 POWER REDOCTIOMS DOCKET No. 50-267 UNI T
- TAME fo rt St. Vra i n Un i t 80 0. 1 OATE February 12. 1938 COMPLET ED HY. F rank J.
Iloyvaghek REPORY MONTH JA800ARY. 1988 I
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IMETHoo Oil i
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ISHUTTINc l l
1 l CAUSE AND CORRFCTIVE ACil0N l
l NO. I DATE lIYPEl DURATION I REASON IDOWN I
LER g ISYSTEMICOMPONENil TO PREVENT RECURRE8eCE I
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188-011 880114 i F 1 N/A l
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N/A l XX l FCV I C He l ium Ci rcu la to r T rip And Powe r I
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i Reduct80n While Troubleshooting FV-2272.
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188-021 880121 l f (
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M/A I S8 i PSI' l Power Reduction To Repai r. Leak in Loop 8 l
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l l Hot Reheat Attemperation t.ine.
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,a REFUELING INFORMATION l
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l 1.
Name of Facility l Fort St. Vrain Unit No. 1 l
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Scheduled date for next l
l-l refueling shutdown.
1 April 4, 1989 l
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Scheduled date for restart l May 27, 1989 l
l following refueling.
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Will refueling or resumption ofl No 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 I ----------------
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general, will these be?
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If answer is no, has the reloadj l
l fuel design and core configura-l l
l tion been reviewed by your l
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Plant Safety Review Committee l No l
l to determine whether any unre-l l
l viewed safety questions are l
l l-associated with the core reload l l
l (Reference 10 CFR Section l
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50.59)?
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If no such review has taken l 1988 l
l place, when is it scheduled? d l
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Scheduled date(s) for submit-l l
l ting proposed licensing action I ----------------
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and supporting information.
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Important licensing considera-l l
l tions associated with refuel-l l
l ing, e.g., new or different l
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fuel design or supplier, unre-l ----------------
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l viewed design or performance l
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analysis methods, significant l l
l changes in fuel design, new l
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operating procedures.
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The number of fuel assemblies l
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(a) in the core and (b) in the l a) 1482 HTGR fuel elements l
l spent fuel storage pool.
I b) O spent fuel elements l
M empup I
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REFUELING INFORMATION (CONTINUED)
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The present licensed spent fuell l
l pool storage capacity and the l l
l size of.any increase in l Capacity is limited in-size to I
l licensed storage capacity that l about one-third of core l
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_ l has been requested or is l (approximately 500 HTGR elements).l l
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 under Agreements AT(04-3)-6331 l
refueling that can be dis-l and DE-SC07-79ID01370 between
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charged to the spent fuel pool l Public Service Company of l
l assuming the present licensed l Colorado, and General Atomic l
- l capacity.
I Company, and DOE.*
l The 1996 estimated date is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by 00E at the Idaho Chemical Processing Plant.
The storage capacity has evidently been sized to accommodate eight fuel segments.
It is estimated that the eighth fuel segment will be discharged in 1996.
p m.
h Public Service ~
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16805 WCR 19 1/2, Platteville, Colorado 80651 February 12, 1988 Fort St. Vrain Unit No. 1 P-88071 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Docket No. 50-267
SUBJECT:
JANUARY, 1988 MONTHLY OPERATIONS REPORT
REFERENCE:
Facility Operating License NJ. DPR-34
Dear Sir:
Enclosed, please find the Monthly Operations Report for the month of January, 1988, 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, Y lk.fn A?0l0dddnu R. O. Williams, Jr.
Vice President, Nuclear Operations Enclosure cc:
Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief Project Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain R0W:djm 1