ML20066E635
| ML20066E635 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/14/1981 |
| From: | Bramlett L ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20066E627 | List: |
| References | |
| NUDOCS 8211150343 | |
| Download: ML20066E635 (5) | |
Text
o.
OPERATING DATA REPORT DOCKET NO.
50-368 -_
DATE 08/14/81 COMPLETED By L. S. Bramlett TELEPilONE 501-968-2519 OPERAllNG STAl US N"'"
Arkansas Nuclear One - Unit 2
- 1. Unit Name:
- 2. Reporting Period:
Jul y l_, - 31'. 1981 2815
- 3. Licenwd Thennal Power (MWI):
942.57
- 4. Nameplate Rating (Gross MWe):
912
- 5. Design Electrical Rating (Net MWe):
897
- 6. Masimum Dependable Capacity (Gross MWe):
858
- 7. Masimum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gise Reasons:
- 9. Power Lesel To which Rntricted. If Any (Net MWe):
N/A
- 10. Reasons For Restrictions. If Any:
This Month Yr..to.Dat e Cumulatise 744.0 5087.0 11831.0
!!. Ilours in Reporting Period 676.2 2669.1_
7699.9
- 12. Number Of liours Reactor has Critical 00 54.9 859.5
- 13. Reactor Resene Shutdown llours 569.3 2521.5_
7437.5 14.11ours Generator On-Line 0.0 0.0_
75.0
- 15. Unit Resene Shutdown liours 951509.0 6046394.0
__17890556.0
- 16. Gross Thermal Energy Generated (MWill 295888.0-1969477.0 5802378.0
- 17. Gross Electrical Energy Generated (MWil) 277335.0.
_]817240.0 5524437.0 IS. Ne Electrical Energy Generated (MWill s
76.5 49.6 62.9
- 19. Unit Senice Factor
- 20. Unit Asailability Factor 49.6 63.5 76.5
- 21. Unit Capacity Factor (Using MDC Net) 43.0 54.4 43.4 40.9 40.5 51.2
~
l
- 22. Unit Capacity Factor (Using DER Net) 9.4 6.4 21.2
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Nest 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 io Commercial Operation):
Forecast Achiesed INITI \\ L CRillCA LITY INITI \\ L ELECIRICITY l
COMMERCI AL OPER ATION 8211150343 810814 PDR ADOCK 05000368 P'/77)
R PDR
AVER AGE DAILY UNIT POWER LEVEL, DOCKET NO.
50-368 UNIT 2
DATE 08/14/81 COMPLETED BY L. S. Bramlett 501-968-2519 TELEPHONE MONTH _. duly DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe-Net )
0 17 409 2
0 is 377 3
0 19 306 4
0 20 402 5
6 21 382 22 632 6
31 7
128 23 633 8
371 24 638 9
384 25 628 10 398 26 616 11 405 27 627 12 406 28 635 13 310 651 29 14 0
681 30 15 271 3:
824 16 406 INSTRUCTIONS On this format,hst the average dail) unit powcr lesel in MWe. Net for each day in the reponing month. Compute to the nearest whole megawait.
(9/77)
^
REFUELING INFORMATION
{P}
1.-
Name of facility. __ Arkansas Nuclear One - Unit 2
- 2. -
Scheduled date for next refueling shutdown. 9/1/82 3.
Scheduled date for restart following refueling.
11/1/82 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license acendcent?
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 Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
Yes.
Cescription of effects of new core loading.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
6/1/82 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.
Possible utilization of Core Protection Calculator (CPC) semi-addressa'ble constants.
~
i i
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 b) 60 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 nudber of fuel assemblies.
present 485 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:
1989 b
i
NRC MONTHLY OPERATING REPORT OPERATING
SUMMARY
- JULY 1981 UNIT II The unit began the month in mode 2 while performing low power physics testing.
The unit was limited to one feedwater pump operation because "B" pump turbine was destroyed during functional testing in June.
On July 1, 1981, the reactor was manually tripped for physics testing and was returned to criticality later that day.
On July 3, 1981 the reactor tripped on low steam generator level while in mode 2 operation and was returned to operation later that day.
On July 4, 1981, the reactor was manually shutdown in accordance with technical specification 3.6.1.4 (Containment pressure, temperature and humidity limits). The reactor was brought critical on July 5, 1981 after maintenance was performed on the 1-B main-chiller and the containment building was brought within the limits of T.S. 3.6.1.4.
Later that day the unit was tied on line and tripped off on reverse power. Again the unit was tied on line, however later that day it was taken off line for main-enance on a main feedwater block valve.
The unit was tied on line on July 6, 1981 and tripped on July 7, 1981 due to an inadvertant reverse power turbine / generator trip, with reactor power manually reduced to approximately 9%.
Later that day while increasing reactor power to approximately 13% the reactor tripped on high steam generator level (Generator "A") due to sensitive feedwater flow control at less than 15% power. The reactor was brought critical and the unit placed on line later that day. During power escalation to 50% full power the unit experienced several turbine runbacks due to the stator coolant flow switch being out of cali-bration. On July 8, 1981 the unit reached approximately 50% full power for further physics testing.
On July 13, 1981 the unit was manually tripped when "A" MFW pump speed reduced drastically due to a speed sensing circuit board failure.
The unit was returned to 50% power on July 15, 1981 for continued physics testing.
On July 18, 1981 the unit tripped on high LPD and low DNBR due to a combined penalty factor induced when PLCEA #26 dropped during physics testing.
The unit was returned to 50% power on July 19, 1981 for completion of physics testing. On July 21, 1981, power was reduced to 35% for a capacity test on an atmospheric steam dump valve and was returned to 50% power with escalation up to approximately 75%
power. _ Power was limited to approximately 75% power due to a condenser hotwell temperature limit of 135 F.
This limit was reached due to one circulating water pump being in n>aintenance. On July 23, 1981 a functional test of an atmospheric steam dump was performed by holding reactor power constant and decreasing turbine capacity approximately 13%. This was repeated on July 24, 1981.
On July 26, 1981 reactor power was reduced to 60% power for a capacity test on an atmospheric steam dump valve and was later returned to approximately 75%
power. On July 30, 1981 the circulating water pump was returned to service and reactor power was increased to 90%. On July 31, 1981 the reactor was brought to 99% power to complete the month.
rr
.,m
-i.
r
~
DOCKET NO.
- 68 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME ANO - I'n f t TT DATE R A-R1 COMPLETED BY L. S.
Bramlett REPORT MONTH July TELEPHONE (501) 968-2519 E
E No.
< - Date
- h #5 f k
3 {El MT
'E Licensee E-t E'%
Cause & Corrective y
E Event Action to H
g 3,.,5 j di g Report r mV Prevent Recurrence g
6 81-06 810328 S
87.7 C.
4 None ZZ ZZZZZZ Refueling 810701 /
S 1.5 B-
'l None ZZ ZZZZZZ Low Power Physics Testing g
F 2.2 H
3 None ZZ ZZZZZZ tow Steara Generator Level 810703 810704 ~lF 24.5 F
1 50-368/024 ZZ ZZZZZZ T.S. 3.6.1.4 4
81-07 810705 F
.2 11 3
None ZZ ZZZZZZ Reverse Power Trip 81-08 810705 F
13.8 B
1 None CH VALVEX Maintenance on W Block Valve 81-09 810707 F
2.7 H
3 None ZZ ZZZZZZ Reverse Power Trip 810707 F
1.9 11 3
None ZZ ZZZZZZ liigh Steam Generator Level 81-10 810713 F
35.1 A
1 None CII INSTRU Failure of circuit board in "A" MW pump speed sensing circuit 81-11 810718 F
5.1 B
3 None ZZ ZZZZZZ PLCEA #26 Dropped 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 3-Automatic Scram-Event Report (LER) File (NUREG-C-Refueling 4-Continuation 0161)
D-Regulaury Restriction E-Opernor Training & Ucense Examination 5-Load Reduction 5
F Administrative 9-Other G-Operational Error (Explain)
Exhibit 1 - Same Source W/77)
Il Other (Explaini L
.