1CAN079604, Monthly Operating Rept for June 1996 for ANO-1
| ML20115H026 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/30/1996 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN079604, 1CAN79604, NUDOCS 9607220187 | |
| Download: ML20115H026 (7) | |
Text
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" = 333 R a t.& AR 72501 Tcl 501858 5000 July 15,1996 1CAN079604 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 for June 1996 is attached.
This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Very tmly yours, YA Dwight C. Mims Director, Nuclear Safety DCM/eas attachment
^
9607220187 960630 PDR ADOCK 05000313 R
PDR DO4
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U. S. NRC July 15,1996 r
1CAN079604 Page 2 cc:
Mr. Leonard J. Callan l
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 l
Arlington, TX 76011-8064 I
i 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
.s OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
July 15,1996 COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reponing Period:
June 130 3.
Licensed ThermalPower(MWt): 2,568 4.
Nameplate Rating (Gross MWe): 903 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: N/A 9.
Power Level To Which Restricted. If Any (Net MWe): None 10.
Reasons For Restrictions. If Any: N/A MONTH YR-TO-DATE CUMULATIVE 11.
Hours in Reponing Period.
720.0 4,367.0 188,754.0 12.
Number of Hours Reactor was Critical.
720.0 4,245.5 141,077.6 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 5,044.0 14.
Hours Generator On-Line.
720.0 4,225.1 138,707.0 15.
Unit Reserve Shutdown Hours..
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH).
1,645,982 10,442,850 322,916,766 17.
Gross Electrical Energy Generated (MWH).
558,056 3,614,029 108,184,074 18.
Net Electrical Energy Generated (MWH).
531,604 3,455,127 102,953,340 19.
Unit Service Factor.
100.0 96.8 73.5 20.
Unit AvailabilityFactor.
100.0 96.8 73.9 i
21.
Unit Capacity Factor (Using MDC Net).
88.3 94.6 65.2 22.
Unit Capacity Factor (Using DER Net).
86.9 93.1 64.2 1
23.
Unit Forced Outage Rate.
0.0 3.2 10.0 1
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling outage IR13 scheduled to commence September 17,1996 with an approximate duration of 30 days.
25.
If Shut Down At End of Repon Period. Estimated Date of Stanup:
N/A 26.
Units in Test Status (Prior to Commercial Operation)-
None 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 UNIT:
One DATE:
July 15,19%
COMPLETED BY: M. S. Whitt TELEPHONE:
(501) 858-5560 MONTH June 19%
DAY AVERAGE DAILY POWER LEVEL (MWe-Net) l.
847 2..
848 3
848 4
847 5...
845 6.
845 7
846 8.
847 9.
847 10.
847 846
- 11....
12 =
843 13.
843 j
14.
840 15..
839 16.
837 17.
835 18..
837 19....................
834 20....
837
- 21......
500 22...
369 23......
277 24.
273 25....
272 26.
300 27:
808 28...
832 2 9.....
832 30...
832 i
AVGS: 738 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.
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR JUNE 1996 DOCKET NO.
50-313 UNIT NAME ANO Unit I DATE July 15,19%
COMPLETED BY M. S. Whitt TELEPHONE
$01-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M
DATE TYPE' (HOURS)
REASON 2 REACTOR 8 REPORT #
CODE' CODES PREVENT RECURRENCE 96-04 960620 F
0 A
5 N/A SJ PSF Power was reduced to 40% in order to secure the "A" main feedwater pump. A pipe fitting failure caused an oil leak on the inboard bearing.
96-05 960621 F
0 A
5 N/A JK DCC A feedwater control system problem caused a main feedwater pump trip resulting in an automatic runback to 42%.
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 of Test 2 - Manual Scram.
Entry Sheets for Licensee 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)
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
JUNE 1996 UNIT ONE The month began with the unit operating at 100% power.
A power reduction was commenced at 0320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br /> on the twenty-first in order to secure the "A" main feedwater pump (MFWP) due to a pipe fitting failure which caused an oil leak on the inboard motor bearing. Following replacement of the fitting, the unit was returned to 100%
power the same day. As the result of a feedwater control system problem, the "A" MFWP turbine tripped at 0405 hours0.00469 days <br />0.113 hours <br />6.696429e-4 weeks <br />1.541025e-4 months <br /> on the twenty-second which resulted in a plant run back to 42% power.
Following trouble shooting of the Lovejoy feedwater control system on the twenty-sixth, a power escalation was commenced with 100% power attained at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on the twenty-seventh.
The unit operated the remainder of the month at 100% power.
s Reporting Period: June 1996 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown: September 17.1996 3.
Scheduled date for restart following refueling: October 17.1996 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? IT aswer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determme whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?
Yes. relocate the reactor coolant system (RCS) pra mee-t---Mure orntMive limite and the variabic low RCS nressure trin to the Core Operatian I imite P_aaad.
5.
Scheduled date(s) for submitting proposed licensing action and supportmg information:
Submitted in Anril 1996 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 7.
'Ihe number of fuel assemblies (a) in tie core and (b) in the spent fuel storage pool; a) 171 b) 20!
7 8.
'Ihe 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 26_8 increase size by 0 9.
'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
DATE:
L926 (Loss of full core off-load capability)