ML20246L735
| ML20246L735 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/30/1989 |
| From: | Cook G, Morris K OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-89-674, NUDOCS 8907180501 | |
| Download: ML20246L735 (21) | |
Text
{{#Wiki_filter:_ _ _ _ _ s , Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536 4000 July 14, 1989 LIC-89-674 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555
Reference:
Docket No. 50-285 Gentlemen:
SUBJECT:
June Monthly Operating Report Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1), please find enclosed one copy of the June 1989 Monthly Operating Report for the Fort Calhoun Station Unit No. 1. Sincerely, ,
/-
K. . 9M" orris Division Manager Nutlear Operations KJM/pjc c: R. D. Martin, NRC Regional Administrator P. H. Harrell, NRC Senior Resident Inspector Office of Management & Program Analysis (2) R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers 8907180501 890630 5 PDR ADOCK 0500 R /
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e-AVERAGE DAILY-UNIT POWER LEVEL j DOCKET NO. 50-285 UNIT. Fort Calhoun Station DATE.. July 11,=1989 COMPLETED BY G. M. Cook TELEPHONE (402)636-2490 l MONTH --June 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY F0WER LEVEL (MWe-Net) (MWe-Net) 1 464 17 464 2 465 18 463 3 464 19 463-4 463 20 461 5 463 21 460 6 403 22 460 7 462 23 460-8' 462 24 462 _ 9 461 25 461 10 463 26 __ 460 11 463 _ 27 458 12 463 28 457 13 463 29 457 14 464 30 458 15- 465 16 465 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day , in the reporting month. Compute to the nearest whole megawatt. l _ _ = _ _ _ - _ _ _ -- _-_. _ _ _. _ . _ _ _ _ _ _ ___J
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OPERATING DATA REPORT DOCKET NO. 50-285 UNIT Fort Calhoun Station ~ DATE July 11, 1989 COMPLETED BY G. M. Cook TELEPHONE (402)636-2490 OPERATING STATUS
- 1. Unit Name: Fort Calhoun Station Notes
- 2. Reporting Period: June 1989
- 3. Licensed Thermal Power (MWt): 1500
- 4. Nameplate Rating (Gross MWe): 502
- 5. DesignElectricalRating(NetMWe): 478
- 6. MaximumDependableCapacity(GrossMWe): 502
- 7. MaximumDependableCapacity(NetMWe): 478
- 8. If changes occur in Capacity Ratings (Item Numbers 3 through 7) Since Last Report, Give Reasons:
N/A
- 9. Power Level to Which Restricted, If Any (Net MWe): N/A
- 10. Reasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720.0 4,343.0 138,193.0
- 12. Number of Hours Reactor was Critical 720.0 3,500.8 106,850.6
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5
- 14. Hours' Generator On-Line 720.0 3,283.3 105,698.6
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 ]
- 16. Gross TMrmal Energy Generated (MWH) 1,076,891.7 ~
4,515,441.7 137,404,435.6
- 17. GrossElectricalEnergyGenerated(MWH) 348,978.0 1,466,162.0 45,210,290.2
- 18. NetElectricalEnergyGenerated(MWH) 332,662.2 12 394,085.T 43,165,590.1
- 19. Unit Service Factor 100.0 75.6 76.5
- 20. Unit Availability Factor 100.0 75.6 76.5
- 21. Mi',CapacityFactor(UsingMDCNet) 96.7 67.2 67.6
- 22. Unit Capacity Factor (Using DER Net) 96.7 67.2 65.9
- 23. Unit Forced Outage Rate 0.0 5.0 3.0
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None
- 25. If Shut Down at End of Report Period, Estimated Date of Startup: N/A
- 26. Units In Test Status (Prior to Commercial Operation): Forcast Achieved INITIAL ~ CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION ,
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.' Refueling Information i Fort Calhoun - Unit No. 1 Report for the month ending June 1989
- 1. Scheduled date for next refueling shutdown. February 1990
- 2. Scheduled date for restart following refueling. May 1990
- 3. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes
- a. If answer is yes, what, in general, will these be?
- Incorporate specific requirements resulting from reload safety analysis
- b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee 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. Scheduleddate(s)forsubmittingproposedlicensing action and support information. January 1990
- 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. None Planned
- 6. The number of fuel-assemblies: a in the core 133 assemblies b in the spent fuel pool 437 c spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel pin consolidation or dry cask storage
- 7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present '
licensed capacity. 1994*
- Full core offload of 133 assemblies lost.
Prepared by AO Date Julv 7,1989 i
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. . 4 OMAHA PUBLIC POWER DISTRICT ,
Fort Calhoun Station Unit No. 1 { I June 1989 i Monthly Operations Report 1 I. OPERATIONS
SUMMARY
Fort Calhoun Station operated at a nominal 100% power throughout the month of June, 1989. Three design basis issues were addressed during June. Testing showed that i emergency lighting was not as adequate as required per Appendix R. Safety Analysis for Operability No. 89-009 and supplementary measures are in place until permanent emergency lighting upgrades can be completed. Testing of the steam turbine driven auxiliary feedwater pump indicated the speed controller is not functioning corre::tly. This could prevent the pump from developing the design discharge head and flow. The problem was corrected by allowing the pump to operate on the speed limiter so that the pump will attain design characteristics. Raw Water pump AC-10A was removed from service for pump replacement. It was discovered during replacement that the pump's discharge check valve RW-125 was inoperable. The Raw Water pump was replaced and the discharge check valve was reinstalled with its internals removed. SA0-89-10 was l written to analyze the effects of the inoperable check valve. l Continued investigations of charging pump CH-1A low flow problems resolved that one of the internal valves was not seated tight enough in the pump block. The block was replaced, the pump tested and declared operable. Work on the Control Room filter modification to meet GDC 19 habitability requirements for operators has started. A water plant outage is underway to facilitate repairs. A reverse osmosis demineralized unit is being used in place of the resin beds. Two large scale emergency response drills were held during June. Construction continues on the Chemistry / Radiation Protection Buildings. Two operators were hired during June. No safety valves or PORV challenges or failures occurred. A. PERFORMANCE CHARACTERISTICS None
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1 ModthlyOperationsReport L June 1989 Page Two.- B. - CHANGES IN OPERATING METHODS None l C.. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS 1 NoneL D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT-WITHOUT COMMISSION l APPROVAL System Acceptance Committee Packages for June 1989: Packaoe Description / Analysis
.None Procedure Description SP-FW-12 FW-10 Baseline Performance and Speed Limiting Governor Test l
This test determined the speed. limiting governor setpoint for FW-10. This procedure did not l constitute.an unreviewed' safety question as defined by 10CFR 50.59 as the test was performed within the design parameters of the pump and system. -Therefore no new or unanalyzed operating modes were created that would present an unreviewed safety question. E. RESULTS OF LEAK RATE TESTS Reactor coolant system leak rate increased during the middle of June. The source was determined to be Charging Pump CH-1B packing. The packing was replaced and the leak rate returned to normal. F. CHANGES IN PLANT OPERATING STAFF Two operators were hired during June. i
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, Monthly.0perations Report
' June 1989 ~
Page Three G.- TRAINING
-During the' month of June,. construction of the simulator continued.
Simulator testing will commence on July 10,-1989. Thirty-nine of forty-two models have been fully integrated, with the Turbine Generator Auxiliary, Containment and Radiation Monitoring models still to be integrated for all plant modes. . The simulator now-operates in'all modes between cold shutdown and 100% power, although," all models are not stable when the plant is on shutdown cooling. The annual L0 requal exam process was completed during June. All-thirty-two license holders passed. One did fail the written portion, but was successfully remediated. One license holder, supporting simulator testing in-Pittsburgh, is exempted from the test in an arrangement with Region IV. The NRC Generic Fundamentals exam ~was administered June 28,.1989 in Texas. Fort Calhoun Station sent three R0 and two SRO candidates. The Fort Calhoun Station SR0 exam was postponed until October. The two SRO-upgrade candidates will then not need to take the theory exam. The other SR0 candidate (instant SRO) took the June NRC fundamentals exam. H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment Na Description Amendment No. 122 This amendment modifies the Technical Specifications to: (1)extendthe surveillance interval by 25 percent, but the total interval for three consecutive intervals shall not exceed 3.25 times the specificinterval,(2)definetheregular surveillanceintervals,(3)includethe25 percent extension to all applicable codes and standardsreferencedwithin,(4)delayan action statement for up to 24 hours to permit the completion of the surveillance when the allowable outage time limit of the action requirement is less than 24 hours, and (5) eliminate the need to perform surveillance on i inoperable equipment. This license amendment is effective after 90 dayr from the date of issuance.
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. Monthly Operations Report L June 1989 l . Page Four
. II. MAINTENANCE (Significant Safety Related)~ ,
See attached printout. td- s.) {ocG.R.Peterson Manager-Fort Calhoun Station I m- n~._._.._ . _ . . _ . _ - -- -_
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