ML20064H355
| ML20064H355 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/07/1978 |
| From: | Shively C ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20064H354 | List: |
| References | |
| NUDOCS 7812190152 | |
| Download: ML20064H355 (5) | |
Text
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AVERAGE DAf LY UNIT POWER LEVEL DOCKET NO.
50-368 LWIT aMn-2 12/7/78 DATE C. N. Shively COMPLETED BY TELEPHONE 501/968-2519 MONTH November
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DA/
AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Ne I (MWe Neti 1
0 0
7 2
0 0
,g 3
0 0
19
~
0 0
4 n
0 21 -
0 6
0 0
22 7
0 23 0
8 0
24 0
9 0
25-0 10 0
0-26 0
0 11 12 0
0 2s 13 0
0 29 0
I4 30 15 0
NA 3r 16 0
INSTRUCTIONS On this tbrmar. list the average d:i!) unit power leset in MWe Net for each day in the reporting month. Lompute to the nearest whole megawatt.
e4/771 781219016a
l OriRATING DATA REPORT DOCKET NO.
50-368 DATE 12/7/78 COMPLETED BY.C.
N._ Shively TELEPHONE 501/.968-2519 OPERATING STATUS
- 1. Unit Name: Arkansas Nuclear One - Unit 2 Notes Unit was in hot
- 2. Reporting Penod:
November 1-30, 1978 functional testing and
- 3. Licensed Thermal Power (MWtp:
2815 final preparations for 958 initial criticality
- 4. Nameplate Rating (Gross MWe):
- 5. Desigr Electncal Rating (Net MWe): 912 throughout the month.
- 6. li,ximum Dependable Capacity (Grom MWe):
NA
- 7. Maximua Dependable Capacity (Net MWe):
NA
- 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):
MA
- 10. Reasons For Restrictions.If Any:
None e
This Month Yr.-to-Date Cumulative NA NA NA I1. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On-Line a
n
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
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- 17. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH) i
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Net)
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- 22. Unit Capacity Factor (Using DER Net) l
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each1:
NA I
- 25. If Shut Down At End Of Report PeriM. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICA LITY 1/T77[9 12/10 70 INITIAL ELECTRICITY COMMERCIAL OPERATION l
(9/77)
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DOCKET NO. 50-3 6 8 UNIT SIIUT1) OWNS AND POWER REDUCTIONS UNIT NAME ANO-2 DATE 17 /7 /7R November EOMPLE1ED BY C.
N.
Shively REPORT MONTil TELEPflONE 5 01/9 6 R-7 til 9 "k
!E 3
Ik I icensee
$3, f",
Cause & Correttive No.
Date i
3g 4
jy5 Event
- s!
Q Action to
$E 5
j if, {
Report
- iE 0 0
Prevent Recurrence P
6 NA NA NA NA NA NA NA NA NA NA 1
2 3
4 F: Forted Reason:
Method:
Exhibit G. Insienctions 5: S(haluteil A-Equipinent Failure (Explain) 1-Manual for Prepasation of Data B-Maintenance of Test 2-Manual Scrain.
Entr> Sheets hn I.icensec C Refueling
.1-Automatic Scram.
Event ReporI (l.I'R) File t NURI G-D-Regulator) Resleitsion 4-Other (Explain) 0161) 1 -Ope ator Training & 1itense Examination F Adminitirative 5
G-Operational I.o rni (E xplain)
Exhibit 1 Sanic Source I'l/77 )
Il-Other (Explain)
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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?
j
]
If answer is no, has the reload fuel design and core configuration i
been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Raf. 10 CFR Section 50.59)?
Yes, Description of effects of new core loading.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
01-01-80 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 7.
The number of fuel assemblies (a) in the core and (b) 0in the spent fuel storage pool, a) 177 b) 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
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9.
The projected data of the last refueling that can be discharged to the apent fuel pool assuming the present licensed capacity.
DATE: va re h 1999 e
S
i NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
- NOVEMBER 1978 UNIT II The Unit continued with Post Core Hot Functional Testing throughout the report period.
Testing of the Main Steam Safety Relief Valves revealed lift setpoints that were less than con-s servative.
The procedure was identified as being incorrect when used with relief valves supplied by this vendor.
All valves setpoints were set and their blowback was adjusted (Reference RO 50-368/78-10).
On 11/7, the Condensate Storage Tank level fell below 80% for a period of about five hours.
The low level was caused by the inability of the Makeup Plants to produce condensate to meet the abnormally high demand.
The Makeup Plants were hampered by periods of unusually low city water quality.
Por-table DI trucks were brought in to assist in the making of condensate (Reference RO-50-368/78-12).
On 11/7, ANO was notified by the manufacturer of the Emergency Diesel Generator Units that the speed switch "urnished had a design problem that could cause e failure of the switch (Ref-erence RO-50-368/78-13).
The typ'e switch in question was found on the "B" Diesel.
After changeout, during the surveil-lance to prove its operability, the diesel tripped on low lube oil pressure and high water temperature.
The Unit was brought'to Cold Shutdown Conditions.
Inspsction of the diesel revealed damage to rod and main bearings, oistons and crank-shaft.
The mode of failure was not identified.
During re-testing following repair, another bearing was wiped.
It was i
postulated that oil aeration may be the problem, but no con-clusions could be made.
During ratesting following repair, another bearing was wiped.
An oil sample from the sump was taken and analyzed, but all specifications were in tolerance.
The Gulf oil was, however, changed out with a Mobil oil which met the required specifications.
During inspection, a base plate mounting screw was found loose, which may have not allowed uniform expansion of the machine.
After repairs, the Unit was load tested and surveillance tested and declared operable (Reference RO-50-368/78-16).
On 11/18, a waiver to allow con'tinuance of the Post-Core Hot Functional Testing with one Emergency Diesel Generator out of service was received.
Testing continued throughout the remainder of the month.
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