2CAN129506, Monthly Operating Rept for Nov 1995 for ANO Unit 2

Monthly Operating Rept for Nov 1995 for ANO Unit 2

ML20095H348
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/30/1995
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN129506, NUDOCS 9512220291
Download: ML20095H348 (6)

Text

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December 15,1995 2CAN129506 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555

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 November 1995 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

Very truly yours, dy5fC.W/A Dwight C. Mims Directoi, Nuclear Safety DCM/eas l

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U. S. NRC December 15,1995 2CAN129506 Page 2 cc: Mr. Leonard J. Callan Regional Ad 'inistrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR72847 Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 l

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. OPERATING DATA REPORT DOCKET NO: 50-368  ;

DATE: December 15,1995 COMPLETED BY: M. S. Whitt TELEPHONE: (501) 858-5560 OPERATING STATUS

1. Unit Name: Arkansas Nuclear One - Unit 2

2. Reporting Period: November 1-30

3. Licensed Thermal Power (MWt): 2,815

4. Nameplate Rating (Gross MWe): 942.57

5. Design ElectricalRating (Net MWe): 912

6. Maximum Dependable Capacity (Gross MWe): 897

7. Maximum Dependable Capacity (Net MWe): 858

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted. If Any (Net MWe): 895

10. Reasons For Restrictions. If Any: Selfimposed power restriction to ~ 98.4% power based on T-hot limitations and the additional 300 steam generator plugs installed during 2P95-1.

MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period . . 720.0 8,016.0 137,472.0

12. Number of Hours Reactor was Critical . . . . 283.8 6,176.2 106,737.5

13. Reactor Reserve Shutdown Hours ... . . . . . . . . . . . .. 0.0 0.0 0.0

14. Hours Generator On-Line .. .. 48.6 5,921.0 104,554.1

15. Unit Reserve Shutdown Hours . 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) . ... . . . . 54,935 16,042,542 278,384,751

17. Gross Electrical Energy Generated (MWH) . . . . 6,075 5,348,232 91,717,805

18. Net Electrical Energy Generated (MWH) . . . . 8,978 5,081,011 87,278,799

19. Unit Service Factor . .. . 6.8 73.9 76.1

20. Unit Availability Factor .. .. . 6.8 73.9 76.1

21. Unit Capacity Factor (Using MDC Net) . .. .. -1.5 73.9 74.0

22. Unit Capacity Factor (Using DER Net) . .. . . . .. -1.4 69.5 69.6

23. Unit Forced Outage Rate . . .. 85.5 6.7 10.2

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Dm vion of Each):

25. If Shut Down At End of Report Period. Estimated Date of Startup:

26. Units in Test Status (Prior to Conuncreial Operation):

Forecast Achieved INITIAL CRITICALITY 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80

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AVEP AGE DAILY UNIT POWER LEVEL l DOCKET NO: 50-368 UNIT: Two DATE: December 15,1995 l COMPLETED BY: M. S. Whitt TELEPIIONE: (501) 858-5560 i

MONTH November 1995  !

DAY AVERAGE DAILY POWER LEVEL (MV/e-Net)

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I.. . . . . . . . . . . -4 2 . . . . . . . . . .. -10

3. . . . . . . . . -11 4 .. .. . . . . . -11 5 ... .. . . . . . -11 6 .. . . . -11 7 .. . . . . . . -11 8..... .. .. -12 9 . . . .. . 10 l

10. . . . . . ... .. -11

11. . ... . . . . . . -11 12.. .. . .. -12 13 . .... . . . ... . . . . . -11 14 .. .. . . . . . . . . . . . . -15 15 . . . . . . . . -26

16. . . . . .. -28 17 . .. . . . . 12

18. . .. . -27 19 . .. .. . . -30

20. . . . . . .. . . -5 2 1 . , . . . . . . . .. . .. .. -27

22. .. . . . . 7 1 23... .. . . . . . -29 e

24. .. .. . . . . 31 25 .. . .. . . -33

26. . . .. . .. -33

27. ... . . . -34

28. ..... . . .. -33 29 .. . . . . . . . . . .. -34

30. . . . . . 152 AVGS: 12 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

NOVEMBER 1995 UNIT TWO The month began with the unit offline for refueling outage 2R11.

At 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br /> on the thirteenth, the plant heatup was halted due to leakage in the body to bonnet seal weld for pressurizer high point vent valve 2SV-4636-1. The unit was cooled back down in order to allow repair of the seal weld. Upon completion of this repair, plant heatup was resumed at 2035 hours0.0236 days <br />0.565 hours <br />0.00336 weeks <br />7.743175e-4 months <br /> on the fourteenth. A second cool down was initiated at 2036 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.74698e-4 months <br /> on the sixteenth due to leaks on pressurizer spray valve 2CV-4651 and a blank flange on the top of the pressurizer. After the leaks were repaired, heatup was again resumed at 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> on the eighteenth. The reactor attained criticality at 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br /> on the nineteenth, and the unit was placed on line at 0447 hours0.00517 days <br />0.124 hours <br />7.390873e-4 weeks <br />1.700835e-4 months <br /> on the twentieth marking the end of the refueling outage.

At 1146 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.36053e-4 months <br /> on the twentieth, the unit was taken off lino to perform the main turbine overspeed trip test. Main turbine generator lockout relays 286-G2-8 and 286-G2-9 failed to reset and the test was halted at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />. It was discovered that 286-G2-8 had a design flaw that would not allow it to be reset after it had been tripped.

After de-energizing the trip signal being sent to 286-G2-8, the lockout relays were able to be reset and the main turbine overspeed trip test was continued at 1708 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.49894e-4 months <br /> on the ~wentieth.

The test was completed at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> and work to modify 286-G2-8 lockout rey was started. Modifications to lockout relay 286-G2-8 were completed and the unit was ph ced on line at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> on the twenty-first. The unit performed normal power ascension to 30%

until 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br /> on the twenty-second when the unit was taken off line due to excessive leakage past the main generator hydrogen seal. Following repairs to the seal, the unit was placed on line at 0102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br /> on the thirtieth. The month ended with the unit at 30% power.

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l UNIT SHUTDOWNS AND POWER REDUCTIONS l REPORT FOR NOVEMBER 1995

• DOCKET NO. 50-368 i UNIT NAME ANO Unit 2 DATE December 15,1995 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 i t

METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO EOQ DATE TYPE 8 GIOURS) REASON: REACTOR 8 REPORT # CODE' CODES PREVENT RECURRENCE 95-06 951101 _S 379.9 C 4 N/A ZZ 777777 The unit was offline for 2R11 Refueling Q Outage.

95-07 951113 F 28.9 A 4 N/A AB VTV While in bestup,2SV-4636-1 (pressurimer high point vent valve) developed a pinhole leakin the body to bonnet seal weld. The plant was cooled back down to allow the seal weld to be repaired.

95-08 951116 F 49.2 A 4 N/A AB V During the second heatup,2CV-4651 (pressuriser spray valve) and a blank flange on the top of pressuriser developed leaks. The plant was cooled back down to allow the leaks to be repaired.

95-09 951120 S 1.9 H 5 N/A TA 777777 Unit taken offline to perform main turbine overspeed trip test.

95-10 951120 F 32.8 A 5 N/A TB 86 The main turbine generator lockout relays (286-G2-8 and 286-G2-9) would not reset due to a design flaw.

95-11 951122 F 175.9 A 5 N/A TB SEAL The unit was taken offline due to excessive hydingen leakage past the main generator hydrogen seat 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 of Test 2 - Manual Scram. Entry Sheets for IJcensee C- Refueling 3 - Autonistic Scram. Event Report (LER) File (NUREG-0161)

D- Regulatory Restriction 4 - Continuation E - Operator Training & License Examination 5 - Imad Reduction F- Administration 9 - Other 5 G - Operational Error Exhibit I- Same Source H - Other (Eup!ain)

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.. 1 Reporting Period: November 1995 REFUELING INFORMATION

1. Name of facility: Arkansas Nuclear One - Unit 2

2. Scheduled date for next refueling shutdown: March 21.1997

3. Scheduled date for restart following refueling: May 5.1997 l

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 Resiew Committee to I determine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?

No.No

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

N/M

6. Important licensing condderations associated with refueling, e.g., new or different fuel design or supplier, terniewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

None planned 1

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

a) J12 b)6.J1

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

l present 188 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:

1 DATE: 1997 (Loss of full core off-load capability) I 1