1CAN029505, Monthly Operating Rept for Jan 1995 for ANO-1
| ML20078Q964 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/31/1995 |
| From: | Hayes K, Mims D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN029505, 1CAN29505, NUDOCS 9502220149 | |
| Download: ML20078Q964 (8) | |
Text
C h==ENTERGY Entergy operations,Inc.
mmm amecc :,a 7n:n Id f Ol ET((/jO February 15,1995 ICAN029505 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for January 1995 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3. Also, in accordance with ANO-1 Technical Specification 6.12.2.4 and NUREG-0737, Item II.K.3.3, attached is the 1994 Annual Report of Safety and Relief Valve Failures and Challenges.
Very truly yours, k%jht C.7)lA Dwight C. Mims Director, Licensing DCM/dwb Attachments i
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V 9502220149 950131 DR ADOCK 0500 3
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U. S. NRC February 15,1995 1CAN029505 Page 2 i
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Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One 1448 S. R. 333 Russellville, AR 72801 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
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OPERATING DATA REPORT DOCKET NO:
50 313 DATE:
February 15,1995 COMPLETED BY: K. R. Hayes TELEPHONE:
(501) 858-5535 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
January 1-31,1995 3.
Licensed Thermal Power (MWt): 2,568 4.
Nameplate Rating (Gross MWe): 902.74 5.
Design Electrical Rating (Net MWe): 850 6.
Maximum Dependable Capacity (Gross MWe): 883 7.
Maximum Dependable Capacity (Net MWe): 836 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): Nonc 10.
Reasons For Restrictions. If Any:
None MONTli YR-TO-DATE CUMULATIVE 11.
Ilours in Reporting Period.
744.0 744.0 176,371.0 12.
Number ofIlours Reactor was Critical.
744.0 744.0 130,000.2 13.
Reactor Reserve Shutdown Ifours.
0.0 0.0 5,044.0 14.
IIours Generator On.Line.
744.0 744.0 127,732.0 15.
Unit Reserve Shutdown llours.
0.0 0.0 817.5 16.
Gross Thermal Energy Generated 1,3%,4%.6 1,3%,4%.6 295,550,385.8 (MWII) 17.
Gross Electrical Energy Generated (MWil).
474,290.0 474,290.0 98,786,210.0 18.
Net Electrical Energy 452,516.0 452,516.0 93,978,213.0 Generated (MWil).
19.
Unit Senice Factor.
100.0 100.0 72.4 20.
Unit Availability Factor.
100.0 100.0 72.9 21.
Unit Capacity Factor (Using MDC Net)..
72.8 72.8 63.7 22.
Unit Capacity Factor (Using DER Net) =
71.6 71.6 62.7 23.
Unit Forced Outage Rate.
0.0 0.0 10.6 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling outage IR12 began on February 14,1995. Restart is scheduled for April 7,1995.
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 08/06/74 INITIAL ELECTRICITY 08/17/74 COMMERCIAL OPERATION 12/19/74
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313 i
UNIT:
One DATE:
February 15,1995 COMPLETED BY: K. R. Hayes TELEPHONE:
(501)858 5535 MONTH January 1995 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) l 1.
807 2.
587 3..
602 4.
603 5....
602 6....
603 7
601 8..
601 9
601 i
10.
602 1 1.........
603 12.
602 13..
602 14...
601 15.............
601 16....
602 17...
601 18...
601
- 19....
601 602 20 -
21.
602 l
22...
602 2 3.....
602 2 4......
603 l
25.
604
- 26....
603 2 7.......
603 28.
603 29.
603 30..
603 31.
603 AVGS: 608 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.
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l NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
JANUARY 1995 UNIT ONE Arkansas Nuclear One, Unit One, began the month operating at 100% power. On the first, at 21:22 hours, plant power was decreased to 60% due to indications of failure in the "B" Reactor Coolant Pump (RCP) Motor bearings. The plant was stabilized at 60%
power and the "B" RCP was stopped at 21:30 hours. On the second at 05:08 hours the unit power was increased to 72.5% power. The unit operated at this power for the remainder of the month.
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UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR J:nu:ry 1995 DOCKET NO.
50-313 UNIT NAME ANO Unit i DATE February 15,1995 COMPLETED BY K. R. iia 3rs TELEPliONE 501-964-5535 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M
DATE TYPE 8 GIOURS)
REASON 2 REACTOR S
REPORT #
CODE' CODES PREVENT RECURRENCE 95-01 950101 F
0 A
5 N/A AB MO Failure of the B Reactor Coolant Pump Motor bearings resulted in 3 RC pump operation at 72% power.
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1 2
3 4
F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A - Equipnient Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram Entry Sheets for Ucensee C-Refseling 3 - Automatic Scran Event Report (LER) File (NUREG-0161) j 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)
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DATE: January 1995 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit I 2.
Scheduled date for next refueling shutdown: February 14.1995 3.
Scheduled date for restart following refueling: April 7.1995 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amaadment? 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.10CFR Section 50.59)?
Technical Soecification chanze to relocate additional cycle specific carameters to the Core Operatina Limits Report (COLRL Technical Soccification chance to allow modification of the vital instmment i
electrical power system.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
These channes were submitted August 30.1994.
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 planned 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
a) 171 b)241 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 2f61 increase size by 0 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assundng the present licensed capacity:
DATE:
1996 (Loss of full core off-load capability)
ATTACHMENT ANNUAL REPORT OF SAFETY VALVE AND RELIEF VALVE FAILURES AND CHALLENGES i
This annual repon is submitted in the January Monthly Operating Repon in response to requirements implemented as a result ofNUREG-0737, Item II.K.3.3 and to fulfill Technical Specification reporting requirements (TS 6.12.2.4).
For ANO-1, there were no failures or challenges to the primary system code safeties or automatic actuations of the electromatic relief valve (ERV) during 1994.
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