ML19256F327
| ML19256F327 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/11/1979 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML19256F326 | List: |
| References | |
| NUDOCS 7912180503 | |
| Download: ML19256F327 (4) | |
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 69 SEPTEMBER, 19 79 I
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This report contains the highlights of the Fort St. Vrain, Unit No.1 activi-ties, operated under the provisions of the Nuclear Regulatory Commission Oper-ating License, DPR-34. This report is for the month of September,1979.
1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFET7 RELATED MAINTENANCE 1.1 Summary The plant was shutdown September 1,1979, and essentially remained in a shutdown condition for the month of September.
The plant shutdown was necessary to resolve problems discovered in a sample audit of Class 1 two and one-half inch and larger piping and hangers which was conducted in response to I & E Bulletin 79-14.
Fluctuation testing (RT-500F) was completed up to 50% power prior to shutting down.
Rise to power af ter hanger discrepancies were resolved, was ha=pered by loss of condensate through leaking relief valves. Water recovery systems were devised to recover condensate.
These relief valves will be repaired at the next scheduled shutdown.
1.2 Discussion g
Plant shutdown was completed on September 1,1979, to resolve dis-crepancies detected in a sample audit of Class 1 two and one-half inch and larger piping and hangers. All discrepatt hangers detetted in the sample audit were qualified by analysis with the exception of hanger #9A-H-46130. Hanger 9A-H-46130 was qualified by analysis af ter the fillet weld metal buildup on all welds was increased from 3/8 inch to 5/8 inch.
The reactor was taken critical at 0543 hours0.00628 days <br />0.151 hours <br />8.978175e-4 weeks <br />2.066115e-4 months <br /> September 15, 1979, and remained at less than 2% power until September 28, 1979. F/ actor power remained at less than 11% for the remainder of September, 1.3 Testing Setup and checkout of the primary coolant plateout probe handling equipment was successfully completed using the mockup penetration.
The dry run procedure was completed with the assistance of a General Atomic Company representative.
Loss of outside power test, SR 5.6.lb-SA, was successfully completed.
Fluctuation testing per RT-500F wascompleted up to 50% power prior to plant shutdown. The observedluctuations appear to be similar to E
those experinced for the Cycle I core with the exceptions that ac-tivity on the nuclear channels was considerably smaller for the l
Cycle 2 core and the threshold line (core resistance and core dif-ferential pressure versus power) appears to be lower for the Cycle 3
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1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE (continued) 1.3 Testing (continued) 2 core. No definitive conclusions can be made at this time as the major portion of the data is presently being reduced by General Atomic Company.
1.4 Eq uipment Since the exact length of the shutdown could not be determined, main-tenance work was scheduled on equipment which could be repaired and returned to service in a seven to ten day period.
The following maintenance work was performed:
Gasket leaks were repaired on strainers M-22801 and M-22802, upstream of Loop 1 and Loop 2 preflash tanks, respectively.
Permanent tie-in of the reactor building chilled water syster was made to primary coolant analytic moisture monitors 9306 and 9307.
Pump replaced and relief valve repaired on reverse osmosis unit.
Pressure seal replaced on main steam stop check valve, HV-2223.
SV-2105, " A" helium circulator steam speed control valve, was disassembled to repair anoil leak at the "0" ring between the operator cylinder and the lower block. Inspection of the valve components revealed that the operator shaf t was scored.
The shaf t was sent off site f or flame spraying. The valve has been reassembled and returned to service.
M-5202 on the bypass flash tank steam outlet line, was disas-sembled and the cage assembly was replaced.
A rupture disc was replaced on nitrogen compressor, C-2931.
Turbine building load center #5 4160/480 volt transformer was changed out. The change consisted of replacing the temporary transformer with the original transformer which had been re-wound. See Reportable Occurrence Report No. 50-267/79-17.
Reverse osmosis unit was chemically cleaned.
V-2247, Loop 2 main steam safety relief valve, was repaired.
C-2105S, "B" buffer helium _ecirculator compressor, shaf t s eal was replaced.
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Failed diaphram on inlet damper of temporary auxiliary boiler was repaired.
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r 2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 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 r
i 1609 096 3
gMUNC DA*A M?OC DOCKIT No.
50-267 Der 791001 COMPLEIID IT J. W.
Gahe TI:.trHoNI (303) 785-2253 Ortu IN: Su ts NoTrs 1.
Unit Nam :
Fort St. Vrain. Unit No. 1 2.
Reporting Period:
790901 thru 790930 3.
Licensad Thermal Power OMt):
842 4.
Nameplate Rating (Gross We):
342 5.
Design Electrical Rating (Net We):
330 1609 097 6.
Har* m e Dependable Capacity (Gross We):
342 7.
Maximum Dependable Capacity (Net We):
330 8.
If Changes Occur in Capacity Ratings (Itens Number 3 *hrough 7) Since Last Report. Give Raasons:
None 9.
Power Level To Which Restricted. If Any (Net We):
231 1c. asasons for Eastrictions, If Any: Nuclear Regulatorv Coc=ission restriction (70%) pending resolution of temperature fluctuations.
This Month Year to Date Cumulative 11.
Hours in Reporting Period 720 6,551 2,208
- 12. Number of Hours Raactor Was Critical 396.3 2.952.3 16,426.0 13.
Reactor Reserve Shutdown Hours 0.0 0.0 0.0 14.
Hours Generator on-:.ine 13.7 1.307.1 9.149.7
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 16.
Gross Ther=al Energy Generated (WH) 16,162 644,453 3.847,451
- 17. Gross Electrical Energy Generated (WE) 1.828 204.281 1.152.551 18.
Net Electrical Energy Generated (WE) 0.0 183.045 1.034.496
- 19. Unit Service Factor 1.9%
29.1%
29.1%
- 20. Unit Availability Factor 1.9%
29.1%
29.1%
21.
Unit Capacity Factor (Using MDC Net) 0.0%
11.2%
11.2%
22.
Unit Capacity Factor (Using DER Net) 0.0%
11.2%
11.2%
- 23. Unit Forced Outage Rate 98.1 24.
Shutdowns Scheduled over Next 6 Months (Type, Date, DUPLICATE DOCUMENT Maintenance Shutdown October 20 1979 Entire document previously
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25.
If Shut Down at zad of Report Period, Estimated Date entered into system under:
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26.
Units In Test Statr 'rior to Comercial operation)
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INInAL CRITICALITT N o.
of pages:
/ c / J / j.j s - s IN1AL ELECTRICITY Cs..wIRCIAL OPERATION