1CAN059302, Monthly Operating Rept for Apr 1993 for Ano,Unit 1
| ML20044D053 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/30/1993 |
| From: | James Fisicaro, Hayes K ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN059302, 1CAN59302, NUDOCS 9305170173 | |
| Download: ML20044D053 (7) | |
Text
,
&~ - Entergy
- ~u gne
.iac-Operations
'~
n su l
,n 1
I l
1 I
1 May 14, 1993 1CAN059302 l
U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555 9
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Monthly Operating Report Gentlemen:
t The Arkansas Nuclear One - Unit 1 Monthly Operating Report (MOR) for April, 1993 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Very truly yours, A
Y-[n y.
" James J. Fisicaro
{
Director, Licensing j
i JJF/JRH/prg Attachment l
i i
(
)
T7f11A^
- rSEst te%2 e
1 c
R 6
I.
U.'S. NRC day 14, 1993
]
ICAN059302 Page 2 r
+
+
cc:
Mr. James L. Milhoan i
Regional Administrator I
U. S. Nuclear. Regulatory Commission i
Region IV i
611 Ryan Plaza Drive, Suite 400 i
Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 i
Mr. Roby Bevan
[
NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-11-3 I
One White Flint North i
11555 Rockville Pike Rockville, Maryland 20852 i
Mr. Thomas W. Alexion I
NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission l
NRR Mail Stop 13-H-3 l
One White Flint North 4
1-11555 Rockville Pike Rockville, Maryland 20852 f
1 I
.l I
i l
E i
l 5
i s
I'l ll 1
OPERATING DATA REPORT DOCKET NO:
50-313 DATE:
May 6,1993 COMPLETED BY: K. R. Hayes TELEPHONE:
(501) 964-5535 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 1 2.
Reporting Period:
April 130.1993 3.
Lixnsed 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): None 10.
Reasons For Restrictions. If Any: None MONTH YR-TO-DATE CUMULATIVE 11.
Hours in Reporting Period....
719.0 2879.0 160986.0 12.
Number of Hours Reactor was Critical.
719.0 2837.8 115836.8 13.
Reactor Reserve Shutdown Hours.
0.0 0.0 5044.0 14.
Ilours Generator On-Line.
719_0 2817.5 113639.2 15.
Unit Reserve Shutdown Hours..
0.0 0.0 817.5 16.
Gross Thermal Energy Generated (MWH) -
1692223 7043693 260180847 17.
Gross Electrical Energy Generated (MWH)..
577110 2414175 86792045 18.
Net Electrical Energy Generated (MWH)...
551539 2311176 82511777 19.
Unit Service Factor...
100.0 97.9 70.6 20.
Unit Availability Factor.
100.0 97.9 71.1 21.-
Unit Capacity Factor (Using MDC Net).
91.8 96.0 61.3 22.
Unit Capacity Factor (Using DEC Net).
90.2 94.4 60.3 23.
Unit Forced Outage Rate...._..
0.0 2.1 11.6 24.
Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):
Refueling Outace 1R11 is scheduled to begin September 17.1993 and restart is scheduled for November 12,1993.
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 08/06n4 INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4 m
AVERAGE DAILY UNIT POWER LEVrL l
DOCKET NO:
50-313 i
UNIT:
One DATE:
May 6.1993 l
COMPLETED BY: K. R. Haves TELEPHONE:
(5011 964-5535
{
MONTH April.1993 t
DAY AVERAGE DAILY POWER LEVEL l
(MWe-Net) l..
846 2.
C45 3
846 i
4 845 5
846 6....
847 I
7.
847 8.
847 9.
835 10.
707 11.
706 12 -
798 13.
845 14 845 15.
846 16 829
- 17.
706 18.
707 19.
799 20.
844 21.
844 22..
844 23.
814 l
24.
221 25.
487 26.
652
+
27.
704
{
28.
706
- 29....
706 30.
804 31 -
- N/A e
AVGS: 767 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 da
NRC MONTIILY OPERATING REPORT OPERATING
SUMMARY
APRIL 1993 UNIT ONE Unit one began the month operating at 100% power. On the ninth at 22:20 hours, the unit began a power decrease to 85% power due to reduced load demand. The unit returned to full power on the twelfth at 08:45 hours. On the sixteenth at 20:30 hours the unit began a power decrease to 85% due to reduced load demand. The unit returned to full power on the nineteenth at 08:58 hours. On the twenty third at 20:00 hours, the unit load was reduced to 60% at dispatcher request due to reduced load demand. During the load reduction, the monthly turbine governor and throttle valve testing was completed. At 02:45 hours on the twenty fourth, the load was further reduced to 20% at dispatcher request, which allowed elective repairs to a tube leak in the E3A feedwater heater. After the heater was repaired, the load was returned to 60% power on the twenty fourth at 21:45 hours. The unit load was held at 60% power until 04:45 hours on the twenty sixth.
At this time the load was increased to 85% power and held there per load dispatch direction until the thirtieth at 05:35 hours. The unit retumed to full power at 07:20 hours on the same day and operated at full power for the remainder of the month.
)
a s
UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT FOR APRIL,1993 DOCKET NO.
50-313 UNIT NAME ANO Unit 1 DATE May 3,1993 COMPLETED BY K. R. Ilayes TELEPIIONE 501-964-5535 METIIOD OF LICENSEE DURATION SIIUTTING DOWN EVENT SYSTEM COMPENENT CAUSE & CORRECTIVE ACTION TO M
DATE TYPE' (IIOURS)
REASON' REACTOR 8 REPORT #
CODE' CODE 8 PREVENT RECURRENCE A power reduction to 20% per the request 93-03 930423 5
0 II 5
N/A ZZ ZZZZZZ of the System Dispatcher, allowed repair to the E3A FW IIcater.
I 1
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 - lead Reduction F-Administration 9 Other 5
l G - Operational Error Exhibit 1 - Same Source l
II-Other (Etplain)
DATE: April, 1993 REFUELING INFORMATION 1.
Name of facility: Arkansas Nuclear One - Unit 1 2.
Scheduled date for next refueling shutdown. September 17, 1993 3.
Scheduled date for restart following refueling. November 12, 1993 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
-I I
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 Yes, Technical Specification change to increase fuel enrichment from 3.5% to 4.1% and to reference B&W Topical Report BAW-10179P for the Core
[
Operating Limits Report.
r f
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. The fuel enrichment Technical Specification change request was submitted to the NRC on June 27, 1991 (ICAN069108).
l A Technical Specification change request to reference B&W Topical Report BAW-10179P was submitted on May 7, 1993.
6.
Important licensing considerations associated with refueling, e.g., new l
or different fuel design or supplier, unreviewed desigr. or performance
[
analysis methods, significant changes in fuel design, new operating j
procedures.
{
None.
7.
The number of fuel assemblies (a) in the core and (b) in the spent inel storage pool, a) 177 b) 625 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 licensed capacity..
I DATE:
1995 (Loss of fu11 core offload capability) b b
I N