2CAN089208, Monthly Operating Rept for Jul 1992 for ANO Unit 2
| ML20114A722 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/31/1992 |
| From: | James Fisicaro, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN089208, 2CAN89208, NUDOCS 9208200244 | |
| Download: ML20114A722 (7) | |
Text
{{#Wiki_filter:~ .g.. Entergy c"'~g er a" Operations August 14, 1992 2CAN089208 U. S. Nuclear Regulatory Corynission Document 3ontrol DeFk Mail Stop P1-137 Washington, D.C. 20$55 SUllJECT Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No NPF-6 Monthly Operating Report Gentlemen Monthly Operating Report statistics for Arkansas Nuclear One, Unit-2, for July, 1992 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6. Very truly yours, bn& .h&Lcpm James J Fisicaro Director, Licensing JJF/SAB/sjf Attachment 9208200244 92073i ft ( l PDR ADOCK 05000368 R ppg (
,0. S..NRC August 14.-1992 Pagn 2-cc: Mr. James 1.. H11hoan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Pfar.a drivo. Suite 40. Arlington, TX 76011-8064 NRC Senio Resident Inspector Arkansas Nuc1 car One - ANO-1 6 2 Numbet 1, Nuclear Pinnt Roatl Russellvillo, AR 72801 Mr. Thomas W. Alexion NRR Project Managnr, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Hall -Stop 13-11-3 Ono Whit o Flint Nort h 11555 Rockvillo Pike Rockvillo, Maryland 20852 Mn. Sheri-Peterson NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North -11555 Rockvillo Piko Rockv111n, Maryland 20852 1 ) l'
OPERATJNG DATA REPORT DOCKET NO: 50-368 DATE: August 3,_1992 COH1'LETED llY :M. 8. WhJ tt TELEPil0NE: Q01)_964-5560 QEERATING STATUS i. Unit Namot Arkansas Nucinar One - Unit 2 '2. Reporting Period: J u ly_1 - 31,3 1992 3 Licensed Thormal Power (HWt i: 2 815 1 4. Nameplate Rating (Gross HWn): 942.57 -5. Dosigt Elcetrical Rating (Net HWe): 912 6. Maximum Dependablo Capscity (Gross HWo): 897 7.- Maximum Dependobin Capacity (Not HWo): 858 8. If Changes occur in Capa.:ity Ratings (items Number 3 Through 7) Sincn Last Report Give Reasons: ~ 9. - Power-Lovel To Which Restricted. If Any (Net HWo): Nono; 10. Reasons-For Restrictions. If Any: Nono MONTil YK-TO-DATE CUMULATIVE
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Ilours in Reporting Period.... 744.0 5,111.0 108,263.0 12. Number of flours Ronctor was i Critical..................... 744.0 3,821.6 81,799.0 13. Reactor Penerve Shutdown llours........................ 0.0 0.0 0.0 Ilours Generator On-Linn...... 744.0 3,806.2 79,993.4 =14. 15. Unit Reserve Shutdown llours 0.0 0.0 0.0 -16. Gross Thermal Energy Generated ( HW il )........................ - 2,089,942.0 10,510,691.0 210,769,799.0 17. Gross Electrical Enorgy Gene ra ted (HWil).............. 680,510.0 3,465,820.0 69,318,651.0 =18.- Net Electrical Energy Generated. (HWil).............. 649,866.0 3,301,733.0 65,929,546.0 19. Unit Service Factor.......... 100.0 74.5 73.9 20. Unit Availability Factor..... 100.0 74.5 73.9 21. Unit Capacity Factor ( Us i ng HDC No t).............. 101.8 75.3 71.0 22.- Unit Capacity Factor - (Using DEC Not).............. 95.8 70.8 66.8 23, Unit Forced Outage Rate...... 0.0 25.5 12.5
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Shutdowns Scheduled 0ver Next 6 Honths (Type, Date, and Duration of Each): - 2R9 ref.ieling_outago' is scheduled to begin_ September l 1992,_anI will i last approximately 52 days. 25. If Shut Down At End of Report Period. Estimated Dato;of Gtartup - 2 6.~ - Units in. Test Status (Prior to Commercial Operation): -i Forecast Achieved l . INITIAL CRITICALITY 12L05/78-INITIAL ELECTRICITY 12[26L.7_8 i COMMERCIAL OPERATION 03/26L80 1 ,~,,,..m....... .. -....,,,,,,,,,., ~. ..,,..,.,.m., _,,-,_.__.,_m
Ei AVERAGE DAILY UNIT POWEH LEVEL t DOCKET NO: 50-368 UNIT: Two DATE: A_uguit_3; i992 COMPLETED BY: M. S. Whitt TELEPil0NE: [50 i L964-5560 HON 111.Juln 1992 4 DAY AVERAGE DAll.Y POWER LEVEL l (HWe-Not) 1............... 877 2'.............. 872 3.............. 879 4............... 874-5.............. 876 6.............. 874 7.............. 874 8.............. -868 9.............. 863 -10_............-. _868 -{ -11............. 873 12............. 872-13............. 873 14............. 874 15............. 874 -16 ............e 879-17............. 879 '18............. 878 19............. 876 20....'......... 874 21............. 878 22............. 877 23-............. - 874 24............. 864 25-............. 861 26............. 869 27J............. 875 28............. 874 29............. 874 -30............. 876 31............. 878 ~- AVGS : 873. 1[aTRUCTIDN; 'On this. format, list the averago daily unit: power level in MWe-Not-for each -day-in reporting month.- Compute to the nearest whole megawatt.
... _ _. _..... _... _ _.. _ - - - - _ _ _.. _. _..__.= __._._.._._ _. _ _ _, _. i MONTilLY OPERATING REPORT OPERATING
SUMMARY
JULY, 1992 UNIT TVO P Thn unit began the month operating at 100% power. At 2125 hours on the twenty-fourth, a power reduction to 95% was conmenced due to the turbino control valve test.- The unit returned to 100% power after completing the test (July 25, 0530 hours) and operated at 100% power for the remainder of the month.- b L 1 l l (. -. :.......... 2
l UNIT SEUTDOWNS AND POEER REDUCTIONS . REPORT FOR JULY 1992. DOCKET NO. 5_0-168 UNIT NAME ANO Ur,it Two DATE Aurist 7. 1992 COMPLETED BY M. S. Whitt TELEPHONE GOI) 964-5560-Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to Wo. Date Type * (Hours) Reason Down Reactor Reoort # Code' Code Prevent Recurrence 2 8 None 1 2 3 6 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 'l-Manual for. Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic' Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction <+-Continuation 0161) E-Operator Training 6 5-Load Reduction 5 License Examination 9-Other F-Administrative Exhibit I - Same Source G-Operational Error (Explain) E-Other (Explain) a 1
n DATE: July, 1992 i REFUELING INFORMATION 1. Namn of facility: Ariann.fuLNuginar One - Unit 2 2. Scheduled date for next refuelitig shutdown. Sentember 4 1992. j u 3. Schedulod dat e for restart. following refueling. DrJ.pher 17. 1992 l 4. Will refueling or resumption of operation thereaf ter rnquire a - technical specification change or other liconsn amendment? If answer is yes, what, in general, will there bo? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committen to detntmine whether any unroviewed safety quer.tlons are associated with the core reload (Ref. 10 CFR Section 50.59)?- No Technical Specification changes _or license _amondments are anticipated.as a result of the reload. However, changes due to other issuns-such as RCS pressure reduction u.outai:1mentJ ressure c trnnsmitter channeouta steam generator sleeving, and ECCS analysis assump,tions havn been submitted to the NRC. 5. Scheduled date(s) for submitting -proposnd licensing action and supporting information. - Previously submitted - 6. Important ifconsing considerations associated with refueling, n.g., now or dif ferent fuel design or supplier, unroviewed design or performance analysis methods,-significant changes in fuel dnsign, new operating procedures. . flone 7. The number of fuel assemblics (a) in the coro and (b) in the spent fuel storage pool, a) 177 b) 489 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storar, capacity that has been requested or is planned, in number of fuel assemblies. present.288 increase size by 0 t 9.- The projected date of the last' refueling that can be discharged to thn spent fuel pool assuming the present licensed capacity. DATE: 12.9] - (hoss of fullcore offload capability) f vt-'-
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