ML19256B153

Monthly Operating Rept for Dec 1978

ML19256B153
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/12/1979
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19256B150	List: ML19256B149 ML19256B153
References
NUDOCS 7901240171
Download: ML19256B153 (6)

Text

y ,

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-368 r UNIT ANO-2 D ATE 01-12 -

COMPLETED BY C.N. Shiyely TELEPHONE 501/968-2519

~

DECEMBER Sf0 NTH

• DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (MWe-Net i O

I 17 0 2 0 18 0 3 0 39 0 4 0 20 0 5 0 o 23 6 0 22 0 7 0 o 73 S 0 0 24 0 -

9 -

25 0 10 0 26 0 11 0 27 0 12 0 2g 22 13 0 ,9 70 14 0 17 30 15 0 3, 57 16

. 0 l INSTRUCTIONS On this formal.hst the sve age daily unit pimer ind :n MWe Net for caeh day in the ree rting mimih. Gimpuie to the nearest whole megawatt.

ps/7 i veoiza ol7 /

OPERATING DAT . REPORT DOCKET NO. 50-368 DATE 0,1-12-79

- COMPLETED BY C.N. Shively TELEPHONE. 501/968 2519 OPERATING STATUS Note 5

1. Unit Name: ._A- kansas Nuclear One - Unit 2 Unit went critical.

~

2. Reporting Period: December 1-31, 1978 on 12/5/78 at 1455 Hours -

281S and First Electricity was

3. Licensed Th'ermal Power (MWt):

4. Nameplate Rating (Gross MWe): 958 generated on 12/26/78 at S. Desien Electrica'l Rating (Net MWe): 912 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />.

6. Maxi:num Dependable Capacity (Gross MWe): NA -

"A I

7. Maximum Dependable Capacity'(Net MWe):

8. If Changes Occur in Capacity Ratings'(Items Number 3 Through 7) Since Last Report.Give Reasons:

None

9. Power Level To Which Restricted,If Any (Net MWe): None

10. Reasons For Restrictions,if Any: NA This Month Yr..to.Date Cumul tive

11. Hours In Reporting Period -

744.0 744.0 744. 0

12. Number Of Hours Reactor Was Critical 434.9 434.9 434.9.

13. Reactor Resene Shutdown Hours 142.2 142.2 142.2

14. Hnurs Generator On.Line 52.8 52.8 52.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 44578.0 44578.0 44578.0 17 Gross Electrical Energy Generated (MWH) 5567.0 ,,

5567.0 5567.0

18. Net Electrical Energy Generated (MWH) 3954 0 39S4.0 3934.0

19. Unit Service Factor

20. Unit Availability Factor

21. Unit Capacity Factor (Using MDC Net) NA Until Commercial Operation

~

22. Unit Capacify Pactor (Using DER Net)

.q(23. ~ Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date and Du. .v. of Eacht:

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup: NA

26. Units in Te>t Status (Prior to Commercial Operation): Foreca>t Achieved INITI A L CRITICA LITY 12/5/78 INITIA L ELECTRICITY 12/"D/ # 8 COMMERCIAL OPER ATION 3/22/79 -

(4/77 )

DOCKET NO. 50-368 UNIT SilUTDOWNS AND POWER REDUC 110NS I UNIT NAME ANO Unie Two .

G ATE 1 - 17 '()

COMPLETED fly C.N. Shively REPORT MONT!! December TELEPHONE 501-968-2519 "t

E- f8 '3 :o E Cause & correctjve Licensee gn.

h53 ,E .,,

N.. n.iie L jj { Event g g C 5i C E2g Report e mo c: o Prevent Re'currence o- e 6 e Di j ,

a .

7.8- 1 781216 S 8.1 F 4 NA NA NA Mode 2 to Mode 3, Reset Trip , .

Setpoints for Fower Operation.

78-2 781220 F 49.7 11 1 NA lill NA To Mode 4, Secondary Chemistry.

78-3 781223 F 68.9 A 1 NA ilF NA To Mode 5, Condenser Tube Leak.

78-4 781226 F 25.4 A 1 50-368/78-29 IIB VALVEX To Mode 3, M.S. Relief Struck Open.

78-5 781227 F 6.8 11 4 NA IIA TURBIN Manual Trip, liigh Vibration. .

78-6 781228 F 3.6 II . 2 NA IIA GENERA Turbine Tirp During Generator Voltage Regulator Setup.

lill 78-7 781228 F 3.9 A 4 NA VALVEX Valve Failure. .  ;

78-8 781229 .F 5.1 A 3 -NA Cil NA Low Steam Generator Level.

78-9 781230 F 26.2  !! 3 NA IA NA Spurions CPC Trip.

l 2 3 4 I I .nu I Reaum : Method: Exhibit G Instinctions

5. S in d ileil A liguipment Failure (Explain) 1 -Manual for Picparation of Data

, ll Maintenance or Test -

2 Manual Scram. Entry Sheets im 1.icensee .

(' Refncling 3. Antomatic St ram. ., Event Report 11.1 R1 File (NI'RI G-1).Regniatory Restriction 4-Ot her (lixplam ) 0161) 1 -Operator Training & l.icense I.xannnasion . .

F Adminiusative 5 G-Operational Es tor I Explain) Exhibit I - Same Somcc l'8/77) Il-Ot her (IIxplain ) , ,

, REFUELINGINFORMAT.kON ecember 1978

1. Na.me of facility. rkansas Nuclear One - Unite 2 r 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 thereafte require a -

technical s'pecification change or othek 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 Revieu Committe to determine '

shether any unreviewed safety questions.are associated with the core relocd (Ref. 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 assec611es fuel storage pool, 177 (a) in.thecoreand:(bginthespent a) 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

9. The projected date of the 1 cot refueling thct een be dicchcrged

~

to'the opent fuel pool escuming the present licenced ccpccity.

DATE: March 1988 9

NRC MONTHLY OPERATING REPORT CORRECTED OPERATING

SUMMARY

- NOVEMBER 1978 t

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 conservative. The pro-cedure was identified as being incorrect when used with relief valves supplied by this vendor. All valves setpoints were set and their blowback was adjasted (Reference R0-50-368/78-10) .

On 11/7, the Condensate Storage Tank level fell below 80% for a - .'

period 'oflabout five hours. The low level was caused by the in-ability of the Makeup Plants to produce condensate lto meet the abnormally high demand. The Makeup Plants were hampered y periods of unusally low city water quality. Portable 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; furnished had a design problem that could cause a failure of the switch (Reference R0-50-368/78-13).

The type switch in question was found on the "A" Diesel. The switch was replaced. ',

During a surveillance test on 11-9-78, the "B" diesel tripped on low lube oil pressure and high water temperature. The Unit was brought to Cold Shutdown Conditions Inspection of th'e diesel revealed damage to red and main bearings, pistons and crankshaft. The mode of failure was not identified. During retesting following repair, another bearing was wiped. It was postulated that oil aeration may be the problem, but no conclusions could be made. During retesting 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, howev er , changed out with a Mobil oil which met the required specifi-cations. During inspection,'a base plate mounting screw was fou6d 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 R0-50-368/78-16).

On 11/18, a waiver to allow continuance 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.

~

NRC MONTHLY OPERATING REPORT t

OPERATING SUbi\!ARY - DECEMBER, 1978 Unit II ,

Authorization was obtained from the NRC on'12/4, permitting the unit to go to. Mode 2 operation. Initial criticality was achieved at 1455 hours0.0168 days <br />0.404 hours <br />0.00241 weeks <br />5.536275e-4 months <br /> on 12/5/78. The Zero Power Physics Testing began immediately following cri-ticality. All Zero Power Physics Tests were completed by 12/14 with no major deficiencies noted. A license amendment was received to allow Mode 1 operation and the main turbine was rolled to 1800 rpm. High turbine vibra-tion ~.was experienced resulting in turbine trips on several occasions. The reactor was tripped on several occasions as a result ,of. inability 'to control steam generator levels within the required range. On 12/20 a condenser tube leak was confirmed. After tube plugging, efforts to dilute impurities in

'st'eam geherator water and restore acceptable water quality were unsuccessful.

The unit was cooled down and the steam generators and the condensate and feedwater system was drained and refilled. The unit was returned to service on 12/26. Initial electricity generation occurred at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on 12/26.

On 12/30, a reactor trip on High Local Power and Low DNBR trip was received on channels.A, C, 6 D after channel B-was bypassed to investigate a B CPC failur The unit was returned to service and continued Power Escalation Testing throughout the month.

• a 4

4 v

9