1CAN059403, Monthly Operating Rept for Apr 1994 for ANO Unit 1
| ML20029E353 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/30/1994 |
| From: | Hayes K, Mims D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN059403, 1CAN59403, NUDOCS 9405180184 | |
| Download: ML20029E353 (7) | |
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, Operations n-May 13,1994 1CAN059403 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
A kansas Nuclear Or it1 Docket No. 50-313 L; ense No. DPR-51 Monthly Operating Report Gentlemen; The Aikansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for April 1994 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Very truly yours, jfGW
('
Dwig h ;. Mims c)#7 Direc y, Licensing I
DCM/jrh Attachment 9405100184 940430 i
PDR ADOCK 05000313 99 R
PDR f
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U. S. NRC
- May 13,1994 1CAN059403 - Page 2
)
cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV j
611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 j
Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. George Kalman NRR Project Manager, Region IV/ANO-t U. S. Nuclear Regulatory Commission NRR Mail Stop 13-II-3 One White Flint North 11555 Rc.2ville Pike Rockville, Mary land 20852 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission 1
NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 i
i 1
l I
1
OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
May 3,1994 COMPLETED BY: K. R. Ilayes TELEPHONE:
(501) 964-5535 QPERATING STM 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
April 1-30,1994 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 Repott, Give Reasons:
9.
Power Level To Which Restricted. If Any (Net MWc): Nonc 10.
Reasons For Restrictions. If Any: Nonc
. MONTH YR-TO-DATE CUMULATIVE I 1.
Ifours in Reporting Period.
719.0 2879.0 169746.0 12.
Number of Hours Reactor was Critical.
641.3 2776.8 123375.2 13.
Reactor Reserve Shutdow n Ilours.
0.0 0.0 5044.0
.14.
Ilours Generator On-Linc.
633.7 2763.4 121107.0 15.
Unit Reserve Shutdown liours.
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWil).
1609629 7064133 279114695 17.
Gross Electrical Energy Generated (MWH).
549375 2419060 93212095 18.
Net Electrical Energy Generated (MWil).
523605 2315985 88643121 19.
Unit Service Factor.
88.1 96.0 71.3 20.
Unit Availability Factor,
88.1 96 0 71.8 21.
Unit Capacity Factor (Usinc MDC Net).
87.1 96.2 62.5 22.
Unit Capacity Factor (Using DEC Net).
85.7 94.6 61.4 l
23.
Unit Forced Outage Rate.
I 1.9 4.0 11.1 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25.
If Shut Down At t:nd of Report Period. Estimated Date of Startup:
26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved
~
INITIAL CRITICALITY 08/06n4 INITIAL ELECTRICITY 08/17/74 j
COMMERCI AL OPERATION 12/19n4 1
'a g
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-313 UNIT:
One DATE:
May 3,1994 COMPLETED BY: K. R. Hayes j
TELEPHONE:
(501) 964-5535 j
MONTil 6plil 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) l 843 2
843 3
843 i
4 843 5
843 6
843 7
843 8
841 9
844 10.
h43 11.
720 12.
-32 13.
-33 14,
-33 15.
209 16.
832 17.
841 18.
841 19.
840 20.
839 21.
840 22.
839 23.
839 24,
83';
25, 841 26.
840 27.
839 28.
839 29.
840 30.
840 31.
- N/A AVGS: 728 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.
I NRC MONTIILY OPERATING REPORT OPERATING
SUMMARY
APRIL 1994 l
UNIT ONE Arkansas Nuclear One, Unit One, began the month operating at 100% power. On the eghth at 19:00 hours, the unit load was de:reased to 95% to perform planned testing of the turbine throttle / governor valves. The unit was returned to full power at 20:55 hours the same day.
On the eleventh at 20:41 hours, the unit tripped due to a lightning strike. The lightning strike caused an automatic initiation of the Main Steam Line Isolation (MSL1) which resulted in a Reactor Protection System initiated automatic reactor trip on high RCS l
pressure. The unit returned on-line at 10:00 hours on the filleenth and reached 100%
)
power on the sixteenth at 02:45 hours.
Unit 1 operated at full power for the remainder of the month.
)
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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR April,1994
~~
DOCKET NO.
50-313 UNIT NAME ANO Unit i DATE May 4,1994 COMPLETED BY K. R. Hayes TELEPHONE 501-9 % 5535 METilOD OF LICENSEE DURATION SilUTTING DOWN EVENT SYSTEM CO%iPONENT CAUSE & CORRECTIVE ACTION TO M
DATE TY PE' tilOURS)
REASON 2 REACTORi REPORT #
CODE' CODE 5 PREVENT RECURRENCE 94-02 940411 F
85.3 11 3
94-002 XX 777.777.
lightning strike caused an automatic e<tuation of the M ain Steam Line Isolation which resulted in a Reactor Protection Sy stem initiated automatic reactor trip on high RCS pressure.
I 2
3 4
F: Forced Reason:
Metbod:
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 Ucensee C - Refueling 3 - Automat.c Scram.
Event Report (LER) File (NUREG-0161)
D - Regulatory Restriction 4 - Continuation E - Operator Training & Ucense Exaniination 5 - lead Reduction F-Administration 9 - Other 5
G - Operational Error Exhibit I-Same Source II-Other (Explain) a.
4 DATE: April 1994 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear _One - Unit 1 2.
Scheduled date for next refueling shutdown. EchnialyM 1991 3.
Scheduled date for restart following refueling. April.7.19M 4.
Will refueling or resumption of operation thereafler 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.10 CFR Section 50.59)?
.I
.Unknnrtatthinimt 5.
Scheduled date(s) for submitting proposed licensing action and supponing information.
Unknown althinime.
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.
NOMplannsd_
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a; 177 b) 6M 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 968 increase size by 0 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present nicensed capacity.
DATE: 1996 (Loss of full core off-load capability) a