ML20063N187
| ML20063N187 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 09/08/1982 |
| From: | Short R OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20063N184 | List: |
| References | |
| NUDOCS 8209200072 | |
| Download: ML20063N187 (7) | |
Text
{{#Wiki_filter:. AVERAGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO. UNIT Fort Calhoun Station DATE September 8,1982 COMPLETED BY R. W. Short TELEPl!ONE (402) 536-4543 MONTil August, 1982 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL t MWe-Net) (MWe Net) 461.4 466.1 37 2 460.4 464.2 18 459.2 463.5 3 39 4 459.0 463.5 20 5 460.5 462.9 21 6 458.6 462.1 22 7 440.5 463.3' '~ 23 8 439.8 464.4 ,4 9 459.8 464.7 25 to 462.9 465.9 26 13 464.6 467.0 27 466.3 468.0 12 28 467.3 469.5 13 29 14 468.9 471.4 3g 15 467.6 468.7 3: 16 465.7 INSTRUCTIONS On this format. list the average daily unit power level in MWe Net for each day in the reporting m.inth. Compute to the nearest whole megawatt. e 19177) 8209200072 820908 PDR ADOCK 05000285 R PDR
OPERATING DATA REPORT DOCKET NO. 50-285 DATE September 8, 1982 COMPLETED BY R. W. Short TELEPilONE (402) 536-4543 OPERATING STATUS
- 1. Unit Name:
Fort Calhoun Station Note $
- 2. Reporting Period:
August, 1982
- 3. Licen ed Thermal Power (MWr):
1500 501
- 4. NamepLte Rating (Gross MWe):
478
- 5. Design Electrical Rating (Net MWe):
i
- 6. Masimum Lependable Capasity (Gross MWe):
501 NO
- 7. Maximum Di pendable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
None
- 9. Power Level To Which Restricted.If Any(Net MWel:
N/A
- 10. Reasons For Restrictions,if Any:
NOne This Month Yr.-to Date Cumulatise i1. Ilours In Reporting Period 744.0 5,831.0 78,312.0
- 12. Number Of flo':rs Reactor Was Critical 744.0 5,764.9 62,003.9
- 13. Reactor Reserve Sherdown flours 0.0-0.0 1,309.5
- 14. Ilours Generator On-Line 744.0 5,755.8 60,845.8
- 15. Unit Resene Shutdown flours 0.0 0.0
~0.0
- 16. Gioss Thermal Energy Generated (MWil) 1.105.355.3 8,483,597.8 75,185,427.9
- 17. Grow Electrical Energy Generated (MWill 361,680.0_,
2,842,977.9 24,916,923.5
- 18. Net Electrical Energy Generated (MWil) 344,339.3 2,710,837.6 23,558,706.1
- 19. Unit Senice Factor 100.0 98.7
//./
- 20. Umt Availability Factor 100.0 98.7 77.7
- 21. Unit Capacity Factor (Using MDC Net) 96.8 97.3 65.4
- 22. Unit Capacity Factor (Using DER Net) 96.8 97.3 65.1
- 23. Unit Forced Outage Rate 0.0 1.3 3.7
- 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each):
1983 Refueling Outage Scheduled to Commence January 3, 1983, for Three Months.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
N/A
- 26. Units in Test Status (Prior to Commercial Operation):
None Forecast Achiesed INillA L CRITICA LITY INITI AL ELECTRICITY CO\\tMERCIA L OPERA TION (9/77)
50-285 DOCKET NO. UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun Station DATE Septernber 8,1982 REPORT MONTil August, 1982 COMPl.ETED ilY R. W. Short TELEPilONE (402) 536-4543 ~E E j3 "h 4YE Licensee ,E n, ye, Cause & Corrective No. Date c-E2 E:$ Event u?
- a. ?
Action to hg S $8 5 Report
- N0 50 Prevent Recurrence 6
There were no unit shutdowns or power reductions during the month of August,1982. I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Report (LI:R) File (NURFG-D Regulatory Restriction 4-Other ( Explain) 0161) E-Operator Training & Ucense Examination F-Administrative 5 G-Operational Error ( Explain) Eshibit I - Same Source (9/77) 11-91her ( E xplain)
4 i Fefueling Infonration Fort Calhoun - Unit No.1 -{ Pcport for the month ending August 1982 l 1. Scheduled date for next refueling shutdown. January 3,1983 i' 2. Scheduled date for restart following refueling. April 1,1983 T 3. Will refueling or resumption of operation thereafter rcquire a technical specificaticn change or other license anendnent? Yes f a. If answr is yes, what, in general, will these be? i } A Techn# cal Specification Change r j b. If answer is no, has the reload fuel design 1 and core configuration been reviewed by J your Plant Safety Review Conrtittee to deter-mine whether any unreviewed safety questions are associated with the core reload. c. If no such review has taken place, when is ~~ it scheduled? l 4. Scheduled date(s) for submitting proposed licensing i action and support information. November 1, 1982 5. Lmort. ant liennsing considerations associated with I refueling, e.g., nea or different fuel design or supplier, unreviewed dasign or perfonnance analysis nothods, significant changes in fuel design, new operating procedures. I i 1 I. 6. The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 237 c) spent fuel pool i storage capacity 483 i d) planned spent fuel pool storage capacity 728 l 7. 'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. _ _ 1935 l 5 j k Prepared by t M Date September 1, 1982 i L.-
t OMAHA PLELIC POWER DISTRICT Fort Calhoun Station Unit No. 1 August, 1982 Monthly Operations Report I. OPERATICNS
SUMMARY
Fort Calhoun Station operated at a nominal 1005 power for the month of August,1982. The Plant reduced power to shaut 95% for the weekend of August 7-8 to perform a scheduled Moderator Temperature Coeffient test required by the Technical Specifications. The test went very well and pcwer was returned to a nominal 1005 the night of August 8,1982. During August, Fort Calhoun received new fuel for Cycle 8. In all, 32 new fuel bundles have been received and the unloading, inspecting and storing operations are progressing. Also during August, annual licensed operator requalification train-ing began at the Combustion Engineering simulator in Windsor, Connecticut. Requalification training vill continue through October 8, 1982. One Auxiliary Operator-Nuclear, resigned and one new Operator-Helper was assigned to Fort Calhoun. At the end of August, the Operations Depart-ment was three full time operators short of its approved staffing level. Permanent transfer of two operators to Fort Calhoun from within the District is being pursued. In addition, interviews are being conducted to fill the remaining staff openings. No safety valve or PORV chillengea occurred. A. ?ERh CRIT!CE O!RPACTERISTICC LER Number De f! ciency LER-016 During :teady state power operation, it was noted that the "B" channel of the reactor protective system "hxial Power Distribution" unit had a nega-tive axial chape index setpoint which was out-of-tolerance. The cetpoint had drifted in a ncn-con-servative direction. The "B" channel for Axial Power Distribution was bypassed and a maintenance order van written to investigate the problem. Throughout the incident, the redundant RPS Axial Power Distribution channels (A, C & D) reme.ined operable and available to perform their des ign function of initiating a reactor trip if ne cessary. B. CHANGES IN OPERATING ;fETHCDS NONE
a / Monthly Operations Report August, 1932 Page Two C. RESULTS OF SURVEILLA'!CE TESTS A'ID INSPECTIONS Surveillance tests as required by the Technical Specifications Section 3 0 and Appendix B, were performed in accordance with the annual surveillance test schedule. The following is a summary of the surveillance tests which resulted in operations Incidents and are not reported elsewhere in the report: Operations Incident Deficiency 01-1570 ST-RM-2 Failed Fuel Monitors, RM-1 & RM-2 not calibrated on return to power. D. CHANGES, TESTS AND EXPERDIEI;TS CARRIED OU"' WITHOUT COMMISSICN APPROVAL Procedure Description SP-FAUD-1 Fuel Accembly Uplift Condition Detection. This procedure did not constitute an unreviewed safety question as defindd by 10CFR50 59 since it only involved evalua-Ling data from a curveillance test. SP-FAUD-1 8-16-82 Fuel Assembly Uplift Condition Detection. This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved evalua-ting data frca a curveillance test. E. RESULTS OF LEAK RATE TESTS NOME F. CHANGES IN PLANT OPERATING STAFF NONE G. TRAINING Training for August included normally scheduled training for opera-tors and maintenance personnel. Training was also conducted for Monitor Team, Emergency Duty Officers and Recovery Organisation Personnel.
e f.... Monthly Operations Report August, 1982 Page Three H. CHA:!GES, TESTS A!!D EXPERIME ;TS REQUIRI:IG ITUCLEAR REGULATCRY CC:OiISSIC:I AUTHORIZATIO!! POSUA!IT TO 10CFR50.59 IIO:lE II.
- /.AI iTE:IA?!CE (Significant Safety Related)
M. O. # Date Descripticn Corrective Action 15760 T-23 82 Charging Pump CH-1A leaked while in Replaced packing cooling water standby operation but not while run-solenoid valves. ning., 16131 8-6-82 Channel LIC-281 high alarm failed to Replaced alarm LED and recali-actuate. brated. 15794 7-29-82 Radiation Monitor PM-050 will not Adjusted suction valve on pump. clear low flow alarm. 16180 8-12-82 "D" Safety Injection Tank level indi-Filled reference log for "D" cation keeps drifting. Safety Injection Tank tightened fitting on narrow range level transmitter. 10 ] A w.
- 3. cates Plant Manager
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