2CAN118504, Monthly Operating Rept for Oct 1985

Monthly Operating Rept for Oct 1985

ML20136G753
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/31/1985
From:	Enos J, Harrison D ARKANSAS POWER & LIGHT CO.
To:	Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
2CAN118504, NUDOCS 8601080468
Download: ML20136G753 (9)

Text

{{#Wiki_filter:. OPERATING DATA REPORT DOCKET NO: 50-368 DATE: October, 1985 COMPLETED BY:D.F. Harrison TELEPHONE: (501)964-3743 OPERATING STATUS 1. Unit Name: Arkansas Nuclear One - Unit 2 2. Reporting Period: October 1-31, 1985 3. Licensed Thermal Power (MWt): 2815 4. Nameplate Rating (Gross MWe): 942.57 5. Design Electrical Rating (Net MWe): 912 6. Maximum Dependable Capacity (Gross MWe): 897 7. Maximum Dependable Capacity (Net MWe): 858 8. If Changes Occur in Capac.ity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: 9. Power Level To Which Restricted. If Any (Net MWe): None 10. Reasons For Restrictions. If Any: None MONTH YR-TO-DATE CUMULATVE 11. Hours in Reporting Period.... 745.0 7,296.0 49,104.0 12. Number of Hours Reactor was Critical..................... 554.4 5,112.1 34,371.4 13. Reactor Reserve Shutdown Hours........................ 0.0 0.0 1,430.1 14. Hours Generator On-Line...... 528.4 4,781.0 33,174.2 15. Unit Reserve Shutdown Hours.. 0.0 0.0 75.0

16. Gross Thermal Energy Generated (MWH)........................

1,144,537.0 11,667,403.0 83,721,082.0

17. Gross Electrical Energy Generated (MWH)..............

376,040.0 3,866,945.0 27,383,701.0 18. Net Electrical Energy Generated (MWH).............. 350,678.0 3,646,542.0 26,056,873.0 19. Unit Service Factor.......... 70.9 65.5 67.6 20. Unit Availability Factor..... 70.9 65.5 67.7 21. Unit Capacity Factor (Using MDC Net).............. 54.9 58.3 61.8

22. ' Unit Capacity Factor (Using DER Net)..............

51.6 54.8 58.2

23. Unit Forced Outage Rate......

29.1 14.1 16.9 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): 25. If Shut Down At End of Report Period. -Estimated Date of Startup: -26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8602080468 852031 -{DR ADOCK 05000368 PDR [ > li

AVERAGE DAILY UNIT POWER LEVEL' DOCKET NO: 50-368 UNIT: Two DATE: October, 1985 COMPLETED BY: D.F. Harrison TELEPHONE: (501)964-3743 MONTH October DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1............. -5 2............. -18 3............. -25 4............. -27 5............. 116 6............. 195 7............. 523 8............. 385 9............. '411 10............ 863 11............ 886 12............. 888 13............ 887 14............ 892 15............ 890 16............ 784 17........... 685 18........... 378 19. 181 20.. -27 21............ -26 22............ -27 23............ 131 24............ 867' 25............ 651 26............ 718 27............ 670 28............ 719 29............ 661 30............ 682 31............ 674 AVGS: 471 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month. Compute to the nearest whole~ megawatt.

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

OCTOBER 1985 UNIf TWO The unit began'the month shutdown for repairs to a' leaking RCP seal pressure sensing line. Following repairs, the reactor was taken critical at 2014 hours on the 4th. The unit was tied to the grid at 0347 hours on the 5th, and full power operation was attained at 2004 hours on the 7th of October. At 1050 hours on the 8th of October, the reactor tripped on high steam generator level when "B" main feedwater pump regulating valve 2CV-0740 closed due to desiccant from the instrument air system in the valve controller. Following repairs, the reactor was taken critical at 2105 hours on the same day, and the turbine was tied on line at 0443 hours on the 9th. The unit reached 100% full' power at 0700 hours on the 10th. On the 16th, power was reduced to search for condenser tube leaks. Following tube plugging, a power escalation was begun. The unit reached 90% full power at 1455 hours-on the 17th. Later that day, a power reduction was started to investigate problems with feedwater heater 2E-6B. A leaking tube was suspected, but testing indicated no leakers. A power escalation was begun, and full power was attained at 0102 hours on the 19th. At 0639 hours on the 19th, the reactor tripped following loss of condenser vacuum when the circulating water pump 2P-3B discharge valve did not close when the pump was secured. During the shutdown it was discovered that an expansion joint on an extraction line to 2E-6B had ruptured. The joint was replaced and all other joints in the area were inspected. Repairs were made to other degraded joints and the reactor was taken critical at 2248 hours on the 22nd. The turbine was tied on line at 0933 hours on the 23rd. 100% . full power was achieved at 0442 hours on the 24th. At 2346 hours on the 24th, a power reduction was started to search for condenser tube leaks. When. power was~ increased to 95% on the 26th, indication of a condenser tube leak occurred. Power was reduced to 75% full power at 1000 hours on the 28th, and was held there through the end of the month for tube. leak testing.

i UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR October, 1985 DOCKET NO 50-368 UNIT NAME ,ANO - Unit 2 DATE November 5, 1985 COMPLETED BY D.F. Harrison TELEPHONE-(501)964-3743 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to t No. Date Type (Hours) Reason 2 Down Reactor 3 Report # ' Code 4 Code 5 Prevent Recurrence 8516 851008 F 17.9 A 3 2-LER-85-022 SJ V Reactor trip on high level in "A" steam generator when "B" MFW-pump regulating valve closed. 8517 851016 F 0 H 4 NA SG TBG Power reduced to search for condenser tube leaks. 1 2 3' 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-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 4-Continuation 1022) E-Operator Training & 5-Load Reduction License Examination 9-Other 5 F-Administrative Exhibit I - Same Source G-Operational Error (Explain) H-Other (Explain) l

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR October, 1985 DOCKET NO 50-368 UNIT NAME ANO - Unit 2 DATE November 5, 1985 COMPLETED BY D.F. Harrison TELEPHONE (501)964-3743 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No. Date Type (Hours) Reason 2 Down Reactor 3 l Report # Coded Code 5 Prevent Recurrence 8518 851017 F 0 H 4 NA SM ZZZZZZ Power reduced to investigate problems with feedwater heater 2E-68. 1 2 3. 4 F: Forced Reason: Method: Exhibit G - Instructions 5: Scheduled A-Equipment Failure (Explain) 1-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 4-Continuation 1922) E-Operator Training & 5-Load Reduction License Examination 9-Other 5 F-Administrative Exhibit I - Same Source G-Operational Error (Explain) H-Other (Explain) 1

UNIT SHUiDOWNS AND POWER REDUCTIONS REPORT FOR October, 1985. DOCKET N0 50-368 UNIT NAME ANO - Unit 2 DATE November 5, 1985 COMPLETED BY D.F. Harrison TELEPHONE-(501)964-3743 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to l No. Date Type (Hours) Reason 2 Down Reactora Report # Code 4 Codes . Prevent Recurrence 8519' 851019 F 98.9 A 3 2-LER-85-023 SD V Reactor trip following loss of condenser vacuum when the circulating pump 2P-3B discharge valve did not close when securing pump. During shutdown it was discovered that an-expansion joint on an s extraction line to 2E-6B had ruptured. The joint was repaired and the unit was placed back on line. 1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-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 4-Continuation 1022) E-Operator Training & 5-Load Reduction License Examination 9-Other 5 -F-Administrative Exhibit I - Same Source G-Operational Error (Explain) H-Other'(Explain)

.-_. _ _. ~,.... UNIT SHUTDOWNS AND POWER REDUCTIONS-REPORT FOR October, 1985 DOCKET N0 50-368 i UNIT NAME ANO - Unit 2 DATE November 5,-1985 COMPLETED BY D.F. Harrison TELEPHONE (501)964-3743 Method of Licensee Cause & Corrective f Duration Shutting Event System Component Action to t No. Date Type (Hours) Reason 2 Down Reactora Report # Code 4 Codes Prevent Recurrence ( 8520 851024 F 0 H 4 NA SG TBG Power reduced to search for condenser tube leaks. t 8521 851026 .F 0 H 4 NA SG TBG Power reduced to search forcondensertubeleaks.] 8522 851028 F 0 H 4 NA SG' TBG Power reduced to~ search for condenser tube leaks. ; I 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 or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report.(LER) File (NUREG-D-Regulatory Restriction 4-Continuation 1022) E-Operator Training & 5-Load Reduction License Examination 9-Other s F-Administrative Exhibit I - Same Source G-Operational' Error (Explain) H-Other (Explain) m v --e e nn-,- m

_. ~ - s DATE: October,1985 l REFUELING INFORMATION 1. Name of facility: Arkansas Nuclear One - Unit 2 2. Scheduled date for next refueling shutdown. Cycle 5 was initiated in May 1985. The next refueling shutdown is scheduled for June 1986. 3. Scheduled date for restart following refueling. August 1986 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer is yes, what, in general, will.there be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)? Cycle 6 details are still being reviewed. A modified CPC program is scheduled to be installed after Technical Specification approval in l November. 5. Scheduled date(s) for submitting proposed licensing action and supporting information. If required, submission will be by May, 1986. j 6. 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. The fresh fuel will have a modification to the CEA guide tube wear sleeves which has been reviewed. (Ref. SER dated September 7, 1984 .for C-E Report LD-84-043). A longer cycle and a change in in-core fuel management from out-in-in to in-in-out are also planned. 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 168 1 l 8. The present licensed' spent fuel pool storage capacity and the size of i any increase in licensed. storage capacity that has been requested or is planned, in number of fuel assemblies. I present 988' increase size by 0 9. The projected date of the last refueling that can be discharged to the ~ spent fuel pool assuming the present licensed capacity. DATE: 2003 4, 1 iL.

?" ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501) 371-4000 November 15, 1985 2CAN118504 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D. C. 20555 h

SUBJECT:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen: The Arkansas Nuclear One - Unit 2 Monthly Operating Report for October 1985 is attached. Very ly yours, j J. Ted E os Manager, Licensing / JTE:MCS:sg / Attachment cc: Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 A 7 \\ i ueveen Moote sours uTiuries sysreu}}