2CAN028702, Monthly Operating Rept for Jan 1987
| ML20205B481 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/31/1987 |
| From: | Enos J, Harrison D ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 2CAN028702, 2CAN28702, NUDOCS 8703270614 | |
| Download: ML20205B481 (7) | |
Text
l OPERATING DATA REPORT-
. DOCKET NO:
50-368 DATE:
January 1987
~.. < -
COMPLETED BY:D. F. Harrison TELEPHONE:
'(501) 964-3743 1
OPERATING STATUS 1.
Unit Name: ' Arkansas Nuclear One - Unit 2 2.
Reporting Period:
January 1-31, 1987 3.
Licensed Thermal Power (MWt):
2,815 4.
Nameplate Rating (Gross MWe):
942.5/
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....
744.0 744.0 60,072.0 12.
Number of Hours Reactor was Critical.....................
744.0 744.0 42,750.7 13.
Reactor Reserve Shutdown Hours........................
-0.0-
- ---9.0 1,430.1-14.
Hours Generator On-Line......
744.0 744.0 41,455.7 15.
Unit Reserve Shutdown Hours..
0.0 0.0 75.0 16.
Gross Thermal Energy Generated (MWH)........................
2,088,753.0 2,088,753.0 105,957,868.0 17.
Gross Electrical Energy Generated (MWH)..............
696,325.0 696,325.0 34,769,101.0 18.
Net Electrical Energy Generated (MWH)..............
666,154.0 666,1540.0 33,080,901.0 19.
Unit Service Factor..........
100.0 100.0 69.0 20.
Unit Availability Factor.....
100.0 100.0 69.1 21.
Unit Capacity Factor (Using MDC Net)..............
104.4 104.4 64.2 22.
Unit Capacity Factor (Using DER Net)..............
98.2 98.2 60.4 23.
Unit Forced Outage Rate......
0.0 0.0 14.9 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 870327061487@01 1{, 9
^"cx o
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-368 UNIT:
Two DATE:
January 1987 COMPLETED BY: D. F. Harrison TELEPHONE:
(501) 964-3743 MONTH January 1987 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.............
896 2.............
896 3.............
896 4.............
895 5.............
895 6.............
895
'7.............
897 8.............
896 9.............
896 10............
897
- 11............
897 12............
895' 13............
895 14............
894 15............
894 16............
896 17............
898 18............
897 19............
897 20............
897 21............
897 22............
897 23............
896 24............
894 25............
896 26............
895 27............
895 28............
894 29............
891 30............
893 31............
894 AVGS:
995 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.
- =
. c-NRC MONTHLY.0PERATING REPORT OPERATING SUMARY
~~
JANUARY 1987 UNIT TWO The unit began the month at 100% power.
At 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br /> on the twenty-fourth, power was reduced to 95% for turbine control valve stroke testing.
Following completion of the test, the unit was returned to 100% power at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />.
The unit remained at 100% power through the end of the month.
4
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s
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1 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR JANUARY 1987 DOCKET NO 50-368 UNIT NAME ANO Unit 2 DATE January 1987 COMPLETED BY D. F. Harrison
~ TELEPHONE (501) 964-3743 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to t No. Date Type (Hours) Reason 2 Down Reactor 3 Report # Code 4 Code 5 Prevent Recurrence Nonn 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 s F-Administrative Exhibit I - Same Source G-Operational Error (Explain) H-Other (Explain)
c L. 3. DATE: January 1987 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 safecy questions are associated with the core reload (Ref. 10 CFR Section 50.59)? No. However, reload fuel desian 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: 1999
,.m ANNUAL REPORT OF SAFETY VALVE AND RELIEF 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 6.12.2.4 for Unit 1 and TS 6.9.1.5.c for Unit 2). For ANO-1, no challenges to the primary system code safeties nor electromatic relief valve (ERV) have occurred in the year 1986. For ANO-2, no challenges to the primary system code safeties have occurred in the year 1986. However, on September 24, 1986 an automatic reactor trip occurred. Post trip evaluation of the transient data showed indications that a primary system code safety valve had partially lifted prematurely during the event. This event is further described in LER 86-012-00. ANO-2 does not have an ERV.
2<s ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK, ARKANSAS 72203 (501)371-4000 February 17, 1987 2CAN028702 Mr. Harold S. Bassett, Director Division of Data Automation and Management Information 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 Operting Report for January 1987 is attached. Very truly yours, c . Ted Enos, Manager Nuclear Engineering and Licensing JTE:MCS:sg Attachment cc: U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 ATTN: Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ATTN: Mr. James M. Taylor, Director lf( Office of Inspection and Enforcement s-E24 'r MEMBEA MiOOLE SOUTH UTIUTIES SYSTEM}}