ML20205C706
| ML20205C706 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/31/1985 |
| From: | Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT |
| To: | Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| LIC-85-405, NUDOCS 8509230162 | |
| Download: ML20205C706 (9) | |
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.=,m AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-285 Fort Calhoun Static g3,7 DATE COMPLETED BY 402-536-4733 TELEPHONE August,1%5 go,,
DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe Net) 472.4 17 d69 A 2
472.6 18 471.2 472.0 3
39 471.0 4
472.0 20 471.5 470.3 5
2 471.7 467.3 472.5 6
22 7
465.7 23 471.7 466.3 469.9 8
24 466.2 470.9 25 to 467.5 26 472.9 469.6 is 27 472.3 471.5 470.5 12
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- 3 470.4 29 469.1 470.5 468.8 34 3o 469.5 469.9 15 3
16 469.7 INSTRUCTIONS
- On this format. list the average daily unit power level in MWe. Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77 )
8509230162 850831 PDR ADOCK 05000295 R
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OPERATING DATA REPORT J
1 DOCKET NO.
50-285 l
DATE Q-06.R5 CO5tPLETED BY I.P. Matthews TELEPilONE 407 536-4733 OPERATING STATUS Fort Calhoun Station Notes
- 1. Unit Name:
- 2. Reporting Period:
AuQust. 1985
- 3. Licensed Thermal Power (siWr):
1500 502
- 4. Nameplate Rating (Gross 5tWe):
478
- 5. Design Electrical Rating (Net StWe):
- 6. Stasimum Dependable Capacity (Gross 51We):
En?
- 7. Stasimum Dependable Capacity (Net alwei-a7A
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:
N/A
- 9. Power f.esel To Which Restricted.lf Any (Net 31We):
N/A
- 10. Reasons For Restrictions. If Any:
None i
This 31onIh Yr.-to-Date Cumulatise 744.0 5,831.0 104,617.0 i1. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical 744.0 5.804.6 R1 nR4.R
- 13. Reactor Resene Shutdown flours 0.0 0.0 1.309.5
- 14. Hours Generator On.Line 744.0 5,796.7 80,464'1
- 15. Unit Resene Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (5tWil) 1,110,355.5 8,589,290.9 102,776,057.9 36/,158.0 Z,890,436.0 33,660,061.0
- 17. Gross Electrical Energy Generated (5thil)
- 18. Net Electrical Energy Generated (%1WH)
'444 R55.4 7.7R7.7an.0 32.168_B78.2
- 19. Unit Senice Factor 100.0 99.4 76.9
- 20. Unit Asailability Factor 100.0 99.4 76.9
- 21. Unit Capacity Factor (Using 51DC Neti 98.4 98.9 64.8 98.4 98.9 64.6
- 22. Unit Capacity Factor (Using DER Net) 0.0 0.0 3.5
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Nest 6 5tonths(Type. Date,and Duration of Each t:
1985 Refuelina Shutdown is tentatively scheduled for Santomber 27. 1QAG with startup tentatively scheduled for December 6,1985.
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
N/A
- 26. Units in Test Status (Prior to Commercial Operationi: N/A rorecast Achiesed INITIAL Cf'!TICA LITY INITIA L ELECTRICITY CO\\14tERCI A L OPER A TION (9/77 )
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-285 UNIT N AME Fort Calhoun Station DATE 9-06-R5 August, 1985 COMPLETED BY TD Matthawe REM)RT MONTH TELEPHONE 402-536-4733
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h.E' Licensee
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Cause & Corrective No.
Date
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3g 2iE Event gg g?
Action to f-5 g ;jj Report a mV H
g' Prevent Recurrence d
There were no unit shutdowns during the month of August,1985.
1 1
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 ci Test 2-Manual Scram.
Entry Sheets for Laecnsee C Refueling 3-Automatic Scram.
Esent Repor 1 LE Ri File I NU RI G-D-Regulatory Restriction 4-Other (Explain) 0161i E-Operator Training A Ucense Examination F Administrative 5
G. Operational Error I Explain t Eshibis 1 - Same Source 19/77)
Il-Other ( Explain) 1
Refueling Information Ibrt Calhoun - Unit No.1 Report for the tronth ending Augnet_ l oM 1.
Scheduled date for next refueling shutdown.
October. 1985 2.
Scheduled date for restart following refueling.
December. 1985 3.
Will refueling or restaption of operation thereafter require a technical specification change or other license amendment?
Yes a.
If answer is yes, what, in general, will these be?
Technical Specification chonged submitted September 3, 1985 b.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Ctmittee 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?
4.
Scheduled date(s) for sutsnitting proposed licensing Submitted action and support information.
SeDtember 3.1Wi 5.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
Submitted and approved 6.
'Ihe ntuber of fuel assentlies: a) in the core 133 assemblies b) in the spent fuel pool 305 c) spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel pin consolidation 7.
'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1996 1
Prepared by a,- Addw Date September 13, 1985
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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 August, 1985 Monthly Operations Report I.
OPERATIONS
SUMMARY
Fort Calhoun Station operated at 100% power through August,1985. An Auxiliary Operator-Nuclear training class was started with four students, i
An Equipment Operator-Nuclear (Turbine) class was started with seven students. SR0 upgrade training commenced with four candidates. Licensed operator requalification, C/RP technician, emergency plan and general employee training continued.
A SARC Security Audit was conducted in August.
Corrective actions have been submitted and initiated in response to areas of concern identified during this audit.
The following personnel changes were effective in August:
J. J. Fisicaro was appointed Acting Supervisor-Administrative Services and Security, M. E. Kallman was appointed Supervisor-Security and L. P. Walling was appointed Supervisor-Administrative Services.
No safety valve or PORV challenges or failures occurred.
A.
PERFORMANCE CHARACTERISTICS None B.
CHANGES IN OPERATING METHODS None C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since
-it only involved the evaluation of data from a surveillance test to verify that a fuel assembly uplift condition did not exist.
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Monthly Operations Report i
August,1985 Page Two D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)
Procedure Description SP-NFR-1 Fuel Receipt Procedures.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure provided for receipt, inspection and storage of new unirradiated fuel. Appropriate radiological and load handling limits were observed.
System Acceptance Committee Packages for August,1985:
Package Description / Analysis EEAR FC-79-165 Long Term Core Cooling.
In March of 1975, the NRC required the District to review the Fort Calhoun Station's Emergency Core Cooling System capabilities and operating procedures.
Studies showed that the High Pressure Injection System and the Auxiliary Pressurizer Spray Line could be used to provide emergency core cooling for a large break LOCA providing redundant valves were placed in series with HCV-238 and HCV-239 (in the CVCS), and in parallel with HCV-240 and HCV-308 (in the HPSI system), and lastly, one isolation valve in the HPSI header and a check valve in the auxiliary spray line.
- Hence, this modification provided for installation of the aforementioned valves. This modification does not have an adverse effect on the safety analysis.
EEAR FC-79-191 Post Accident Sampling System.
This modification provides a system which can be used to analyze liquid and gas samples in contain-ment following an accident while minimizing exposure to personnel.
This modification does not have an adverse effect on the safety analysis.
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Monthly Operations Report August, 1985 Page Three D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)
System Acceptance Committee Packages for August,1985:
(Continued)
Package Description / Analysis EEAR FC-80-139 Waste Gas Header.
This modification replaced the carbon steel pae on the vent header that services the waste hold-up tanks with stainless steel pipe. This will improve flow, reduce corrosion and improve repairability of that line and associated valves.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-81-30 Potable Water Priming Line for AC-16.
This modification provided for a potable water line to be piped ta the AC-16 suction to provide priming as necessary.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-84-190 Security of Room 81 Pressure Relief Vent Openings.
This modification was installed to prevent access into Room 81 through the blowout panels in the roof.
A metal grating was installed just below the blowout panels which meets the requirements of a security barrier.
E.
RESULTS OF LEAK RATE TESTS None F.
CHANGE IN PLANT OPERATING STAFF During July, Mr. J. J. Foley was appointed Supervisor-I&C and Electrical Maintenance to replace Mr. R. J. Mueller who was appointed Plant Engineer.
During August, Mr. J. J. Fisicaro was appointed Acting Supervisor-Administrative Services and Security, Mr. M. E. Kallman was appointed Supervisor-Security and Mr. L. P. Walling was. appointed Supervisor-Administrative Services.
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Monthly Operations Report August,1985 Page Four G.
TRAINING During August, an Auxiliary Operator-Nuclear training class was started with four students.
An Equipment Operator-Nuclear (Turbine) class was started with seven students.
SRO upgrade training commenced with four candidates.
Licensed operator requalification, C/RP technician, emergency plan and general employee training continued.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T010CFR50.59 Amendment No.
Description No. 90 This amendment changes the testing frequency of the auxiliary feedwater pumps from quarterly to monthly.
No. 91 This amendment adds new technical specifications addressing the surveillance requirements related to the solid radioactive waste Process Control Program (PCP).
II. MAINTENANCE (Significant Safety Related)
None
-W-W. Gary Gates Manager Fort Calhoun Station o
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Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 402/536-4000 j
September 13, 1985 LIC-85-405 Mr. James M. Taylor, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
Docket No. 50-285
Dear Mr. Taylor:
August Monthly Operating Report Please find enclosed ten (10) copies of the August,1985 Monthly Operating Report for the Fort Calhoun Station Unit No.1.
Sincerely, t '?---
R. L. Andrews Division Manager Nuclear Production RLA/TPM/rs Enclosures cc: NP,C Regional Office Office of flanagement & Program Analysis (2)
Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers NRC File d
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