2CAN029506, Monthly Operating Rept for Jan 1995 for ANO Unit 2
| ML20078Q892 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/31/1995 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN029506, 2CAN29506, NUDOCS 9502220121 | |
| Download: ML20078Q892 (8) | |
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nanua m mm id 501 EfA f,iOO February 15,1995 2CAN029506 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 i
Monthly Operating Report Gentlemen:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report (MOR) for January 1995 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6.
Also, in accordance with ANO-2 Technical Specification 6.9.1.5.c and NUREG-0737, Item II.K.3.3, attached is the 1994 Annual Report of Failures and Challenges to Pressurizer Safety Valves.
Very truly yours, j
dktC.-f)$ -
Dwight C. Mims Director, Licensing DCM/dwb i
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9502220121 950131 PDR ADOCK 05000369 R
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U. S. NRC i
February 15,1995 2CAN029506 Page 2 I
cc:
Mr. Leonard J. Callan l
Regional Administrator U. S. Nuclear Regulatory Commission Region IV i
611 Ryan Plaza Drive, Suite 400 l'
Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One 1448 S. R. 333 l
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 l
One White Flint North l
11555 Rockville Pike Rockville, MD 20852 L
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OPERATING DATA REPORT DOCKET NO:
50-368 DATE:
February 15,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 OPERATING STATUS 1.
Unit Namc: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
.lanuary 1-31 3.
Licensed Thermal Power (MWt): 2,815 4.
Nameplate Rating (Gross MWe): 942.57 5.
Design Electrical Rating (Net MWc); 912 6.
Maximum Dependable Capacity (Gross MWe): 897 7.
Maximum Dependable Capacity (Net MWe): 858 8.
If Changes Occur in Capacity Ratings (l' ems Number 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level To Which Restricted. If Any (Net MWe): 884 (actual Net MWe) 10.
Reasons For Restrictions. If Any:
Self-imposed 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 C1f fULATIVE I 1.
Ilours in Reporting Period.
744.0 744.0 130,200.0 12.
Number of Hours Reactor was Critical..
320.4 320.4 100,881.8 13.
Reactor Reserve Shutdown Ilours.
0.0 0.0 0.0 14.
Ilours Generator On-Line.
316.0 316.0 98,949.1 7
15.
Unit Reserve Shutdown llours.
0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWII).
757,638 757,638 263,099,847 17.
Gross Electrical Energy Generated (MWII).
251,576 251,576 86,621,149 18.
Net Electrical Energy 233,700 233,700 82,431,489 Generated (MWil)...
19.
Unit Service Factor..
42.5 42.5 76.0 20.
Unit Availability Factor.
42.5 42.5 76.0 21.
Unit Capacity Factor (Using MDC Net).
36.6 36.6 73.8 22.
Unit Capacity Factor (Using DER Net).
34.4 34.4 69.4 23.
Unit Forced Outage Rate.
20.4 20.4 10.5 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 12/05n8 INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80
1 AVERAGE DAILY UNIT POWER LEVEL
+
DOCKET NO:
50-368 UNIT:
Two DATE:
February 15,1995 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 i
MONTil January 1995 DAY AVERAGE DAILY PO%T.R LEVEL (MWe-Net) 1 900 2
899 3
900 4
898 5.
899 6..
823 7
-22 8..
-12 9
-11 10:
-11 11.
-10
-10 12.
13.
-10 14.
-11 15..
-10 16.
10 17.....
-10 18.....
-10 l
19...
-10 2 0............
-19 l
21...
-20
- 22..
-11 23...
-16 24
-20
- 25.............
187 241 26..
27.
692 28..
882
- 29..
891 30 880 31.
879 AVGS: 314 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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NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
JANUARY 1995 UNIT TWO The unit began the month of January operating at 99% power.
A power reduction to take the unit offline for 2P95-1, Steam Generator (SG) Tube Inspection Outage, commenced at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> on the sixth and was completed at 2336 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.88848e-4 months <br /> that same day. During heatup following the completion of the SG tube inspections, a reactor coolant pump seal failed to stage properly (i.e., one stage of the four stage RCP seal was degraded). The unit was returned to cold shutdown to effect repairs. Following the RCP seal repair, the unit was placed on-line at 1937 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.370285e-4 months <br /> on the twenty-fourth. Due to T-hot limitations and the additional 300 steam generator plugs installed during 2P95-1, the maximum reactor power level that could be attained was 98.4%.
The unit maintained 98.4% power for the remainder of the month.
s UNIT SilUTDOWNS AND POWER REDUCTIONS REPORT FOR JANUARY 1995 DOCKET No.
50-368 UNIT NAME ANO Unit 2 DATE February 15,1995 COMPLETED BY M. S. Whitt TELEPHONE 501-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO E
DATE M'
(HOURS)
REASON' REACTOR' REPORT #
CODE' CODE' PREVENT RECURRENCE 95-01 950196 5
346.9 H
I N/A ZZ 77.7.777.
Unit off line for Steam Generator Tube Inspection.
95-01 950121 F
81.1 A
4 N/A AB SEAL During bestup froma SG tube laspection outage, a reactor coolant pump seal did not stage property (Le., see stage of the four stage RCP seal was degrc ded). The unit was returned to cold shutdown to repair the RCP seal 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 of Test 2 - Manual Scram.
Entry Sheets for IJcensee C-Refueling 3 - Automatic 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 (Explain)
DATE: January 1995 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown: Scotember 22.1995 3.
Scheduled date for restart following refueling: November 6.1995 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 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)?
l Delete reauirement for verification of oosition stons for the high pressure safety iniection throttle valves. Revise Technical Specifications to account for the replacement ofpart-lenath control element assemblies with full-lenath control element asse nblies. Revise the reference in the Admmistrative i
Controls section to allow use of the Modified Statictical Combinatiaa of Uncer*=iatia for detm..hi.2 core operatina limits. Relocate the value usel to decrease the core power operatina limit based on l
DNBR when neither CEAC is operable to the Core Occratina Limits Report.
i 5.
Scheduled date(s) for submitting proposed licensing action and supportmg information:
Anril 1995 6.
Important licensing considerations associated with refuel ng, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
i None planned l
7.
The number of fud assemblies (a) in the core and (b) in the spent fuel storage pool:
l t
a) 122 b) M2 i
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 98 increase size by 9 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the f
present licensed capacity:
i DATE:
1997 (Loss of full core off-load capability) b
.~.
ATTACHMENT ANNUAL REPORT OF SAFETY VALVE FAILURES AND CHALLENGES This annual report is submitted in the January Monthly Operating Report in response to requirements implemented as a result of NUREG-0737, Item II.K.3.3 and to fulfill Technical Specification reporting requirements (TS 6.9.1.5.C).
For ANO-2, no failures or challenges to the primary system code safeties occurred during 1994.
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