2CAN108607, Monthly Operating Rept for Sept 1986
| ML20207F563 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/30/1986 |
| From: | Enos J, Harrison D ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 2CAN108607, NUDOCS 8701060129 | |
| Download: ML20207F563 (7) | |
Text
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.0PERATING DATA REPORT DOCKET NO:
50-368 DATE:
September, 1986 COMPLETED BY:D. F. Harrison TELEPHONE:
(501)964-3743 OPERATING STATUS 1.
Unit Name: Arkansas Nuclear One - Unit 2 2.
Reporting Period:
September 1-30, 1986 3.
Licensed Thermal Power (MWt):
2,815 4.
Nameplate Rating (Gross MWe):
942.57 5.
Design Electrical Rating (Net MWe):
912
-6.
, Maximum Dependable Capacity (Gross MWe):
897 7.
Maximum Dependable Capacity (Net MWe):
858 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 CUMULATVE 11.
Hours in Reporting Period....
720.0 6,551.0 57,119.0 12.
Number of Hours Reactor was
. Critical.....................
423.4 4,276.7 39,913.4 13.
Reactor Reserve Shutdown Hours........................
0.0 0.0 1,430.1 14.
Hours Generator On-Line......
355.6 4,187.4 38,623.1 15.
Unit Reserve Shutdown Hours..
0.0 0.0 75.0 16.
Gross Thermal Energy Generated (MWH)........................
494,342.0 11,159,176.0 98,196,527.0 17.
Gross Electrical Energy Generated (MWH)..............
154,415.0 3,699,504.0 32,188,746.0 18.
Net Electrical Energy Generated (MWH)..............
132,407.0 3,507,775.0 30,617,309.0 19.
Unit Service Factor..........
49.4 63.9 67.6 20.
Unit Availability Factor.....
49.4 63.9 67.7 21.
Unit Capacity Factor (Using MDC Net)..............
21.4 62.4 62.5 22.
Unit Capacity Factor (Using DER Net)..............
20.2 58.7 58.8 23.
Unit Forced Outage Rate......
18.1 4.1 15.6 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 INITIAL ELECTRICITY COMMERCIAL OPERATION h
-n#
a k
.w.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-368 UNIT:
Two DATE:
September. 1986 COMPLETED BY: D. F. Harrison TELEPHONE:
(501)964-3743 MONTH September DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.............
-14 2.............
-12 3.............
-11 4.............
-14 5.............
-18 6.............
-30 7.............
-31 8.............
-30 9.............
-31 10............
-31 11............
-31 12............
-19 13............
84 14............
199 15............
203 16............
209 17............
205 18............
222 19............
404 20............
407 21............
411 22............
410 23............
620 24............
279 25............
-25 26............
-25 27............
46 28............
802
=29............
768
~30............
572 31............
AVGS:
184 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month.
Compute to the nearest whole megawatt.
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
SEPTEMBER 1986 UNIT TWO l
The unit began the month shutdown for refueling and maintenance.
At 1247 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.744835e-4 months <br /> on the ninth, the reactor was critical, but was taken subcritical at 2024 hours0.0234 days <br />0.562 hours <br />0.00335 weeks <br />7.70132e-4 months <br /> on the tenth to perform maintenance on CEA #2.
At 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br /> on the eleventh, the reactor achieved criticality, and the unit was tied on line at 1948 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.41214e-4 months <br /> on the twelfth. A power reduction was started on the thirteenth at 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> to perform the Turbine Overspeed Trip Test, which was completed at 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />. The unit was tied on line at 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br /> and power was increased to 30%.
The unit was held at this power level for physics testing.
At 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br /> on the eighteenth, a power increase to 50% was started and was completed at 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br />, where the unit was held for additional physics testing.
On the twenty-third at 0392 hours0.00454 days <br />0.109 hours <br />6.481481e-4 weeks <br />1.49156e-4 months <br />, a power increase began and at 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br /> on the twenty-fourth, the unit reached 100% power.
At 0822 hours0.00951 days <br />0.228 hours <br />0.00136 weeks <br />3.12771e-4 months <br /> on the twenty-fourth, the unit tripped from 100% power due to a high level in the "A" moisture separator reheater. While shutdown, work on the pressurizer code safety valves was performed.
At 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br /> on the twenty-seventh, the reactor achieved criticality, and the unit was placed on line at 1458 hours0.0169 days <br />0.405 hours <br />0.00241 weeks <br />5.54769e-4 months <br /> on the same day.
100% power was attained at 0627 hours0.00726 days <br />0.174 hours <br />0.00104 weeks <br />2.385735e-4 months <br /> on the j
twenty-eighth.
At 1343 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.110115e-4 months <br /> on the twenty-ninth, power was reduced to 65% due to a j
suspected condenser tube leak.
On the thirtieth at 0542 hours0.00627 days <br />0.151 hours <br />8.96164e-4 weeks <br />2.06231e-4 months <br />, power was reduced to 55% due to CEA #1 dropping.
CEA #1 was repaired, and a power increase was commenced at 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br /> on the thirtieth.
The unit reached 90%
at 2022 hours0.0234 days <br />0.562 hours <br />0.00334 weeks <br />7.69371e-4 months <br /> and was held for an ASI check.
At 2218 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.43949e-4 months <br />, a power increase commenced, and the unit ended the month escalating to 100% power.
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR SEPTEMBER 1986 DOCKET NO 50-368 UNIT NAME ANO Unit 2 DATE September, 1986 COMPLETED BY D. F. Harrison TELEPHONE (501)964-3743 Method of Licensee Cause & Corrective Duration Shutting
. Event System Component
' Action to No.
Date Type (Hcurs)
Reason 2 Down Reactor 3 i
Report #
Code 4 Code 5 Prevent Recurrence 8607 09/01/86 5 285.8 C
4 NA XXXX ZZZZZZ Refueling and maintenance outage.
8608 09/24/86 F 78.6 A
3 Not SB MSR Unit trip on high level Available in the "A" moisture at this separator reheater. Work Time.
performed on pressurizer code safety valves during.
the shutdown.
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 or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation 1022)
E-Operator Training &
5-Load Reduction License Examination 9-Other 5
F-Administrative Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain)
O
4 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR SEPTEMBER 1986 DOCKET NO 50-368 UNIT NAME ANO Unit 2 DATE September, 1986 COMPLETED BY D. F. Harrison TELEPHONE (5011964-3743 Method of Licensee Cause & Corrective Duration Shutting Event' System Component Action to 2
No.
Date.
Type (Hours)
Reason 2 Down Reactor 8 Report #
Code 4 Code 5 Prevent Recurrence 8609 09/29/86 F 26.5 A
5 NA SG TBG Power reduced due to a suspected condenser tube leak.
CEA #1 dropped while at the reduced power.
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 or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation 1022)
E-Operator Training &
5-Load Reduction License Examination 9-Other 5
F-Administrative Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain)
O 4
DATE:
September 1986 REFUELING INFORMATION 1.
Name of facility:
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown.
January 1988 3.
Scheduled date for restart following refueling.
March 1988 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. 10 CFR Section 50.59)?
No.
However, reload fuel design is in the planning stage.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
If required. Technical Specification change requests will be submitted before December 1987.
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 are expected.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 289 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 988 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.
DATE:
2003
-.__.--..-.__._y-m
._..._...__m_
- D'..
ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK, ARKANSAS 72203 (501) 371-4000 October 15, 1986 2CAN198507 Mr. Harold S. Bassett, Director Division of Data Automation and Management Informatior.
Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report
Dear Mr. Bassett:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report for September 1986 is attached.
Very truly yours,
/
. Ted Enos, Manager Nuclear Engineering and Licensing JTE:MCS:sg Attachment cc:
Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 M
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