ML20064E624
| ML20064E624 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/13/1978 |
| From: | Ideker R ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20064E623 | List: |
| References | |
| NUDOCS 7811210192 | |
| Download: ML20064E624 (6) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL 0-368 DOCKET NO.
UNIT ANO-2
~ ~
DATE COMPLETED BY R. E. Ideker TELEPHONE 501/371/4355 October MONT11 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Net)
IMWe-Net) 0 0
1 17 0
0 2
18 0
3 4
0 20 0
0 s
21 n
0 0
6 22 0
'0 7
23 0
0 8
24 0
0 9
- s 0
0 10 26 O.
II y
0 I2
,3 0
0 i3 29 f4 0
0 30 l
0 0
15 31 l
0 16 7 811210 19: IL.
INSTRUCTIONS On this tormat, list the average da:13 unit power Inet in MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.
(9 /77 )
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1 I
i OPERATING DATA REPORT DOCKET NO.
50-368 l
DATE 11 7e COMPLETED BY R.E. Ideker TELEPHONE 501/371-4355 OPERATING STATUS Arkansas Nuclear One - Unit 2 Notes Not in Connercial j, y,j,3, October 1-31, 1978 Operation
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
2815 958
- 4. Nameplate Rating (Gross MWe):
912
- 5. Dengn Electrical Rating (Net MWe):
- 6. Maximum Dependaole Capacity (Gross MWe): NA NA
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
NA NA
- 9. Power Level To Which Restricted. If Any (Net MWe):
- 10. Reasons For Restrictions.!f Any:
None This Month Yr..to.Dete Cumulative NA NA
.NA i1. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical n
n
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On.Line n
- 15. Unit Reserve Shutdown Hours n
n
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH) m
- 19. Unit Service Factor n
- 20. Unit Availability Factor n
n
- 21. Unit Capacity Factor (Uslag MDC Net)
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Eachl:
NA
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
NA
- 26. Units In Test Status (Prior to Comme-Fat Operation):
Forecast Achieved INITIA L CRITICALITY 11/23/78 INITIAL ELECTRICITY 12/11/78 COMMERCIAL OPERAI!ON 2/15/79 N/77)
50-368 DOCKET NO..ANO-2 UNIT SiluTI) OWNS AND POWER REDUCI10NS UNIT NAME DATE 11-13-7R COMPLE1ED BY R.E. Ideker October REPORT MONTH TELEPHONE 501/371/4355 "E
hi
$E 3
h.Yk
'Cause & Correceive I.icensee E%
a Adion to fS" da -
Date i
58 4
.s s &
Event sT Prevent Recurrence f
$5 5
j(2g Repose a N0 6
NA NA NA NA 11 NA NA NA NA Unit is on llot Functional Testing 3
I 1
I 2
3 4
F: ForicJ Reason:
Method:
Exhibit G - Instructions S: Siind ulcil A-Equipment Failure (Explain)
I-Manual for Prepasalion of Data B Maineenance oi Tese 2 Manual Scram.
Entry Sheels fos 1.ieensee
)
C-Refueling 3-Automatic Scram.
Event Repost (l_ER) File (NtIRI G-D Regulatory Resisidion 4-Other (Explam) 0161) i Opesator Training & Ucense Examination F Administrative 5
G Operational Error (Explain)
Eshibit I Same Souice 19/77)
Il~Othes (Explain) 4
REFUELING INFORMATION 1.
Name of facility.
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown. 03-01-80 3.
Scheduled date for restart following refueling.
06-01-80 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 these be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Connittee to determine whether any unreviewed safety questions are associated with the core reload (Raf. 10 CFR Section 50.59)7 Yes - Description of effects of new core loading 5.
Scheduled date(s) for submitting proposed licensing action and supporting information. 1-01-80 6.
Impo:: tant licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unrevi~ewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 0 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 486 increase size by 0
9.
The projected date of the last refueling that can be discharged to the opent fuel pool assuning the present licensed capacity.
DATE: blarch 1988 D
--v.
OPERATING SIMtARY - OCTOBER, 1978 UNIT II The unit remained shut down until 10/1/78, when the heatup began to continue the Post-Core Hot Functional Test.
On 10/5/78, the pressurizer code relief valve developed a leak during setpoint testing. The valve was temporarily gagged, allowing the valve to cool and reseat (Reference R.O. 50-368/78-8).
On 10/6/78, an Emergency Feedwater valve's hydraulic pump motor failed, making the valve inoperable. Repairs were made and the emergency feedwater flowpath was reestablished (Reference R.O. 50-368/78-9).
The unit was cooled down on 10/14/78 to allow the change out of a partially shorted upper gripper solenoid coil on a control drive element assembly.
Heatup began on 10/29/78 and reached Mode 3 operation two days later. Post-Core Hot Functional Testing continued the remainder of the month.
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4 s.
OPERATING SUIMARY - SEPTEMBER, 1978 UNIT II Post-core Hot Function Testing began on 9/4/78. On 9/12/78, the condensate storage tank level had reduced to approximately 35% due to an abnormally high use rate. It was not brought to >SO% within the required 7 days. A contractor was brought in to assist in making the required condensate
~
(Reference R.O. 50-368/78-3).
On 9/16/78, following a Unic I plant trip, Fraakers feeding both engineering safeguard busses tripped when off-site power supply for both units transferred to Start-Up transformer #2.
The emergency diesel generators started, but inverter malfunctions caused the inverters to transfer to their alternate source position before the diesel generators were at speed and operable.
In the alternate source position the inverters are aligned exclusively to the diesel generators. Since the alternate source of power to the inverters was not operable, vital instrumentation was without power and a full actuation of the engineering safeguards systems resulted. This included: 1) Reactor Building Spray System actuation, wetting down all equipment, 2) Isolation of component cooling water to the reactor coolant pump seals, 3) Sodium Hydroxide admitted into the Shutdown cooling system. All equipment and components in the Reactor Building was inspected and cleaned, the reactor coolant pump seals were replaced as necessary, and an engineering evaluation of the high chloride concentration in the Reactor Coolant Systems was performed (Reference R.O.
50-368/78-4, 78-5, 78-6 and 78-7).
The Unic remained shut down the rest of the month, s
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