2CAN109504, Monthly Operating Rept for Sept 1995 for ANO Unit 2

Monthly Operating Rept for Sept 1995 for ANO Unit 2

ML20093G702
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/30/1995
From:	Mims D, Whitt M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN109504, NUDOCS 9510190202
Download: ML20093G702 (7)

Text

a Entargy Opsrttions, Inc.

c==-ENTERGY wasa 333 RusscPA AR 72801 Tel 501858 'A00 October 16,1995 2CAN109504 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 September 1995 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.

' Very truly yours, A k ~)$C

• C '77/ ~'

t Dwight C. Mims Director, Licensing DCM/eas 100084 9510190202 950930 k

t PDR ADOCK 05000368 I\\

R

.PDR.,

U. S. NRC l

October 16,1995 2CAN109504 Page 2 cc:

Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission RegionIV 611 Ryan Plaza Drive, Suite 400 Arlington,17 76011-8064 NRC Senior Resident Inspector

]

Arkansas Nuclear One P.O. Box 310 London, AR 72847 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 i

4 i

i e

OPERATING DATA REPORT DOCKET NO:

50-368 DATE:

October 16,1995 COMPLETED BY: M. S. Whitt TELEPIIONE:

(501) 858 5560 Q.PERATING STATUS 1.

Unit Name: Arkansas Nuclear One - Unit 2 2.

Reporting Period:

September 130 3.

Licensed Thermal Power (MWt): 2,815 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 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 instilled during outage 2P951.

MONTH YR-TO-DATE CUMULATIVE I 1.

Ilours in Reporting Period.

720.0 6,551.0 136,007.0 12.

Number of Hours Reactor was Critical.

485.0 5,892.4 106,453.7 13.

Reactor Reserve Shutdown i

11ours.

0.0 0.0 0.0 14.

Hours Generator On-Linc.

469.4 5,872.3 104,505.5 i

15.

Unit Reserve Shutdown Hours.

0.0 0.0 0.0 l

16.

Gross Thermal Energy Generated (MWH).

1,236,674 15,987,606 278,329,815 17.

Gross Electrical Energy Generated (MWH).

411,845 5.342,157 91,711,729 18.

Net Electrical Energy Generated (MWH).

388,988 5,092,652 87,290,441 19.

Unit Service Factor.

65.2 89.6 76.8 20.

Unit Availability Factor.

65.2 89.6 76.8 21.

Unit Capacity Factor (Using MDC Net).

63.0 90.6 74.8 l

22.

Unit Capacity Factor (Using DER Net).

59.2 85.2 70.4 l

23.

Unit Forced Outage Rate.

11.0 2.3 10.0 l

24.

Shutdowns Scheduled Over Next 6 Months (Typc, Date, and Duration of Each):

Refueling outage 2RI1 commenced SepMmber 23.1995 with a scheduled duration of 29 days.

25.

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

October 23,1995 26.

Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY

, 12/05/78 12/26/78 i

COMMERCIAL OPERATION 03/26/80

)

~.-.

C AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-368 4

UNIT:

Tuo 1

DATE:

October 16,1995 COMPLETED BY: M. S. Whitt TELEPHONE:

(501) 858-5560 MONTH Sepicmbst192.5 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

]

402 2

-32 l

3

-26 4

419 5

841 6...

878 3

7 877 4

8..

882 9

883 10.

882 11.

881 12......

881 13.

880 j

14..........

877 15..

880 16.

879 17.'

880 i

18..

881 l

19.

877 20..

827 21.

793 22.

738 4

23...

-21 24...

17 25..

-16 26..

-6

,(

2 7.....

-3 l

28.

-4 29..

-3 30.

2 31...

O AVGS: 540 INSTRIJCTION i

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.

l NRC MONTIILY OPERATING REPORT OPERATING

SUMMARY

SEPTEMBER 1995 UNIT TWO The unit began the month of September at 98.3% power.

At 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> on the first, an automatic reactor trip occurred due to a IJi water level in "B" steam generator. The high water level was the result of a painter inadvertently stepping on an instrument valve which vented the high pressure side of the "B" feedwater flow transmitter (2LT-ll29.) This caused a low feed flow signal to be processed in the feedwater control system that resulted in the "B" steam generator being over fed with water. The reactor achieved criticality at 1526 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.80643e-4 months <br /> on the second, but during startup activities to place the unit back on line, the unit experienced another automatic reactor trip at 1927 hours0.0223 days <br />0.535 hours <br />0.00319 weeks <br />7.332235e-4 months <br /> the same day.

4 The trip was generated due to the Axial Shape Index (ASI) exceeding its trip setpoint. After the reactor trip review was completed, the reactor attained criticality at 1011 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.846855e-4 months <br /> on the third, with the turbine placed on line at 2146 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.16553e-4 months <br /> the same day. Power was increased until 0111 hours0.00128 days <br />0.0308 hours <br />1.835317e-4 weeks <br />4.22355e-5 months <br /> on the fifth when the system dispatcher requested a power hold at 89%. At 0502 hours0.00581 days <br />0.139 hours <br />8.300265e-4 weeks <br />1.91011e-4 months <br /> on the fifth, the dispatcher released the unit to continue power escalation.

The unit attained its 600 F T-hot limitation at 1327 hours0.0154 days <br />0.369 hours <br />0.00219 weeks <br />5.049235e-4 months <br /> on the fifth; and due to an apparent increase in fouling of the steam generators caused by the trip, initially the maximum power achievable was 97.8%. Over the next two weeks power was slowly increased back to 98.3%

as the fouling on the steam generators decreased to pre-trip levels. At 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br /> on the eighteenth, a power coastdown was commenced in preparation for ANO-2's eleventh refueling outage (2R11.)

Plant shutdown began at 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br /> on the twenty-second. The reactor was manually tripped at 2338 hours0.0271 days <br />0.649 hours <br />0.00387 weeks <br />8.89609e-4 months <br /> the same day, marking the beginning of refueling outage 2RI1.

The unit was offline for the remainder of the month.

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR SEPTEMBER 1995 DOCKET NO.

50-368 UNIT NAME ANO Unit 2 DATE October 16,1995 COMPLETED BY M. S. %1titt TELEPHONE 501-558-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M

DATE H.M' (HOURS)

REASON 2 REACTOR 8 REPORT #

CODE' CODES PREVENT RECURRENCE 95-64 950901 F

32 H

3 2-95-802-80 SJ V

An automatic reactor trip on high water level in the "B" steam generator occurred when a painter inadvertently stepped on an instrument valve; thus, vesting off the high side of the "B" main feedwater flow transmitter. This caused a low feed flow signal to be processed in the feedwater control system that resulted in the "B" steam generator being over fed with water. The completed and planned corrective actions for this event were submitted in correspondence 2CAN099504, dated September 28,1995.

95-05 950902 F

26.3 G

3 2-95-803-80 JC 777777 An automatic reactor trip occurred during startup due to the ASI exceeding its trip setpoint. The -.- t ^d and planned corrective actions for this event were submitted la correspondence 2CAN099502, dated September 26,1995.

95-06 950922 S

192.4 C

1 N/A ZZ 777777 The unit is off line for refueling outage 2R11.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instructions I

S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data l

B - Maintenance of Test 2 - Manual Scram.

Entry Sheets for Ucensee C-Refueling 3 - Autosnatic Scram.

Event Report (LER) File (NUREG-4161)

D-Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Examination 5 -Imad Reduction F-Administration 9 - Other 5

G - Operational Error Exhibit I-Same Source H - Other (Explain)

'e Reporting Period: September 1995 REFUELING INFORMATION 1,

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

Scheduled date for next refueling shutdown: Scotember 23.1995 3.

Scheduled date for restart following refueling: October 23.1995 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 myiewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?

Yes.

De!de reauirement for verification of position stoos for the hiah oressure safety iniection throttle yalves. Revise Tachaieml Soecifications to accamt for the replacement of aart-lenath control element mamblies with full-lenath control element assemblics. Revise containment coolina system resoonse time to acemnt for modification to eliminate water hammer.

5.

Scheduled date(s) for submitting proposed licensing action ar.d supporting information:

Submittnd durina March and April 1995 l

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.

None olanned i

7.

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

a).121 b) #22 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:

present 288 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:

4 DATE: 1997 (less of full core off-load capability) i i

1

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