0CAN079706, Monthly Operating Repts for June 1997 for Arkansas Nuclear One,Units 1 & 2

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Monthly Operating Repts for June 1997 for Arkansas Nuclear One,Units 1 & 2
ML20196G845
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 06/30/1997
From: Mims D, Whitt M
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0CAN079706, CAN79706, NUDOCS 9707230141
Download: ML20196G845 (14)
v • d • e


Text

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5 C Ent rgy Operations,Inc.

@[ 1448 SR 333 RussdMRe, AR 72801 Td 501858 5000 July 15,1997

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OCAN079706 ,

U. S. Nuclear Regulatory Commission Document ControlDesk Mail Station OPl-17 I

Washington, DC 20555 -

Subject:

Arkansas Nuclear One -Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Monthly Operating Report

Gentlemen: ,

p Arkansas Nuclear One (ANO), Units 1 and 2 Technical Specifications 6.12.2.3 and 6.9.1.6, respectively, require the submittal of a Monthly Operating Report. The purpose of this letter ,

. is to complete the reporting requirement for June 1997. .I Very tmly yours, I W/4 Dwig C.Mims ,

Director, Nuclear Safety ]

DCM/eam attachment t

9707230141 970630 PDR ADOCK 05000313 PDR l{lll.ll.ll.llull[.hl{l{h R ,

!20140

U. S. NRC '

July 15,1997 OCAN079706 Page 2

. 'cc:- -Nr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission i Region IV l 611 Ryan Plaza Drive, Suite 400 l Arlington, TX 76011-8064 i l

NRC Senior Resident Inspector l Arkansas Nuclear One -

P.O. Box 310 London, AR72847 I

l Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H One White Flint North-1l555 Rockville Pike Rockville, MD 20852 1

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Arkansas Nuclear One i

! Unit 1 Monthly Operating Report p

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, , OPERATING DATA REPORT -

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DOCKET NO: 50-313 DATE: July 15,1997 COMPLETED BY: M. S. Whitt TELEPHONE: (501) 858-5560 QPERATING STATUS

1. Unit Name: ' Arkansas Nuclear One - Unit 1 1
2. Reporting Period: June 1-30
3. Licensed Thermal Power (MWt): 2,568-
4. Nameplate Rating (Gross MWe): 903
5. Design Electrical Rating (Net MWe): 850
6. Maximum Dependable Capacity (Gross MWe): 883 l
7. Maximum Dependable Capacity (Net MWe): 836 I
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: I
9. Power Level To Which Restricted. If Any (Net MWe):
10. Rease, .or Restrictions. If Any:

MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period . 720.0 4,343.0 197,514.0
12. Number ofHours Reactor Was Critical 720.0 4,343.0 148,838.6
13. - Reactor Reserve Shutdown Hours 0.0 0.0 5,044.0
14. ~ Hours Generator On-Line 720.0 4,343.0 146,438.3
15. Unit Reserve Shutdown Hours 0.0 0.0 817.5
16. Gross Thermal Energy Generated (MWH) - 1,791,153 10,728,660 342,256,450 17, Gross Electrical Energy Generated (MWH) , 615,648' 3,730,782 114,880,158-
18. Net Electrical Energy Generated (MWH) 589,093- 3,573,932- 109,359,164
19. Unit Service Factor 100.0 100.0 74.1
20. Unit AvailabilityFactor 100.0 100.0 74.6
21. Unit Capacity Factor (Using MDC Net) 97.9 98.4 66.2

- 22. Unit Capacity Factor (Using DER Net) 96.3 96.8 65.1

23. ~ Unit Forced Outage Rate 0.0 0.0 9.6
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 _

08/06n4 INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-313 UNIT: One DATE: July 15,1997 ,

COMPLETED BY: M. S. Whitt TELEPHONE: (501) 858-5560 MONTH June 1997 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1: . . . . 852 2...................... 852 3....................... 851 4; . . . .. 851 5..................... 850 6.................. 849 7.................... 849

8. . . . . . . . . . . . . .

847

9. . . .

848 10 . .... .. 851 11................... 851

12. . . . 849 13........................ 849 14 . .... 848 15 . ........... 846 16 .. 845
17. .

848 18.. . . . . . .

848

19. ........ . ..

847 20 .. . . .

844 ,

21. . 844 22................ 842 2 3 . ... . . . . . .. .. . ..

842 24................... 841 25= ,

839 26................. 840 27 .. . . .

841 28 .. 839 29....................... 434 i 3 0 .. ..... .. . . . .. . . . . .

410

. AVGS: 818 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.

b

' UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FORJUNE 1997 --

DOCKET NO. 50-313 -

UNIT NAME ANO Unit I DATE

  • dy 15,1997 COMPLETED By ~4. S. Whitt* ,

TELEPHONE $01-858-5560 METHOD OF LICENSEE DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M DAT5 E' GIOURS) REASON 2 REACTOR 8 REPORT # CODE' CODES PREVENT RECURRENCE 97-03 970629 S 11.3 B 5 N/A ZZ 777777 Power redaction to 40% for main turbine testing.

97-04 970629 F 35.8 A 5 N/A SJ CLU Power held at 55% due to a short la power supply to clutch in anotor operator for main feedwater block valves.

l I 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 IJcec-**  !

C - Refueling 3 - Automatic Scram Event Report (LER) File (hTREG-4161) i D- Regulatory Restriction 4 - Continuation ,

E - Operator Training & License Examination 5 -Imad Reduction  !

F- Administration 9 - Other 5 G - Operational Error Exhibit I- Same Source H - Other (Explain) t

l NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

l JUNE 1997 i l  ;

l UNIT ONE l I

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The month began with the unit operating at 100% power.  ;

i At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on the twenty-ninth, a power reduction to 40% was commenced for main turbme  ;

testing. Following test completion at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> that same day, problems were encountered with j the main feedwater block valves. The unit was held at 55% power while trouble-shooting and i repairs could be performed. The unit operated the remainder of the month at 55% power. I i

There were no challenges to the primary system code safeties nor automatic actuations of the l electromatic relief valve during this reporting period.

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L: Reporting Period: June 1997 l '

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! REFUELING INFORMATION l 1. Name of facility: Arkansas Nuclear One - Unit 1 i

j 2. Scheduled date for next refueling shutdown: March 20.1998

3. Scheduled date for restart following refueling: May 9.1998

! 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 safety questions are associated with the core reload (Ref.10CFR

,l Section 50.59)? c l

No.No l

5. . Scheduled date(s) for submitting proposed licensing action and supporting information:

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N/A

( 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. .

l None olanned

. 7. He number of fuel assemblies (a) in the core, (b) in the spent fuel storage pool and (c) dry cask

- storage:

1 a)122 b)1585 c) 48

8. The present licensed spent fuel pool storage capacity and the size of any incre::se :a ",M & rage capacity that has been requested or is planned, in number'of fuel assemblies:

L present 968 increase size by 0

9. De projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Full core off-load capability no lonner available until a sufficient amount of spent fuel can be placed in on-site dry storane.

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Arkansas Nuclear One Unit 2 ,

Monthly Operating Report l

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, . OPERATING DATA REPORT l .

DOCKET NO: 50-368 DATE: July 15,1997 l COMPLETED BY: M. S. Whitt TELEPHONE: (50l) 858 5560 OPERATING STATUS

1. Unit Name: Arkansas Nuclear One - Unit 2
2. Reportmg Period - June 1-30
3. Licensed ThermalPower(MWt): 2,815 '
4. Nameplate Rating (Gross MWe): 942.57
5. Design Electrical Rating (Net MWe): 8%

l' 6. Maximum Dependable Capacity (Gross MWe): 897 l l

7. Maximum Dependable Capacity (Net MWe)
858 l
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since i Last Report, Give Reasons: A modification to the high pressure turbine was made allowing the l' unit to operate at 100% power. This change reduced the design electrical rating to 896 MWe Net.
9. Power Level To Which Restricted. If Any (Net MWe):
10. Reasons For Restrictions. If Any:

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MONTH YR-TO-DATE CUMULATIVE

11. Hoursin Reporting Period 720.0 4,343.0 151,343.0
12. Number of Hours Reactor Was Critical 532.1 3,626.6 119,161.0
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

, 14. Hours Generator On-Line 502.8 3,597.3 116,925.3 '

j- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 ,

16.~ Gross Thermal Energy Generated (MWH) 1,271,034 9,620,527 311,955,944 l 17. Gross Electrical Energy Generated (MWH) 405,344-- 3,228,630 102,979,875

18. Net Electrical Energy Generated (MWH) 381,508 3,075,933 98,020,497 l 19. Unit Service Factor 69.8 82.8 77.3
20. Unit AvailabilityFactor 69.8 82.8 77.3
21. Unit Capacity Factor (Using MDC Net) 61.8 82.5 75.5
22. Unit Capacity Factor (Using DER Net) 58.I 77.7 71.0
23. Unit Forced Outage Rate .

0.0 0.0 9.8 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 Operatir;n): Forecast Achieved INITIAL CRITICALITY 12/05n8 l

INITIAL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80 i

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  • AVERAGE DAILY UNIT POWER LEVEL l 1

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, l DOCKETNO: 50-368 j UNIT: Two- 1 l

! DATE: July 15,1997 l l

COMPLETED BY: M. S. Whitt TELEPHONE: (501) 858-5560 i l

I MONTH June 1997 l

\

l DAY AVERAGE DAILY POWER LEVEL.-

l (MWe-Net) 1 .. . . . . . . . . . -4 l 2........................... -6  ;

3= . . . . . . . . . . . . . . -7

4 .. . . . . . . . . . . . . 6 )

5: . . . . . . . . . . . -8 j 6............... .. -15 j 7...................... -29 l 8 .... -34 l

, 9 .. . . . . . .. .. -26 l 10................... 36 11.................. I62 394 l 12..................

-13....................... 6%

14 . . . . . . . . . . . .

853 15 .. ... . .. 852 16 ........ . .

856 17 .... . . . . . . . . . . .

870 18.................. 871 i 19 ... ...... . . . . . . . .

872 2 0 ..... . ... .. . . . . . .

870 21....................... 868 22....................... 868 2 3 .. . . . . . . . .. . 868 2 4 .. ... .. . . . . .. . 869 25 . ...

868 26.. . . . . . . . . . . . . . .

871

27. . . . . . . . . .

869

28. 874 874 2 9 .. . .. . .... . . . . .

l 3 0 . . . . .. .. .. ... . . ..

870 AVGS: 530 i

j INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month. Complete to the nearest whole megawatt.

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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR JLWE,1997 .

DOCKET NO. 50-368 ,

UNIT NAME ANO Unit 2 6 DATE July 15,1997 ,

COMPLETED BY - M. S. WIN TELEPHONE 501-858-5560  ;

[

METHOD OF LICENSEE i DURATION SHUTTING DeWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO [

M DATE M3 RIOURS) REASON 2 REACTOR 8 REPORT # CODE

  • CODES PREVENT RECURRENCE 97-05 970601 S 217.2 C 1 N/A ZZ 777777 Unit offline for 2R12 refseling outage.

97-06 970610 S 5.1 H 9 N/A ZZ 777777. Unit taken offline for turbine evenpeed l trip test.

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1 2- 3 4 [

F: Forced Reason: Methed: Exhibit G -Instructions  !

S: Scheduled A- Equipaseat Failure (Explsla) 1 - Manual for Preparattom of Data l B-Malatenance of Test  : 2 - Manual Scram. Entry Sheets for IJceasee  !

C- Refueling 3 - Autesnatic Screen. Event Report (LER) File (NUREG-4161) ,

D- Regulatory Restriction 4 - Continuation i E - Operator Training & IJcease Examinetton 5 -Imad Reduction l F- Administration 9 - Other 5  !

G - Operational Error Exhibit I- Same Source H - Other(Explain)

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. NRC MONTIILY OPERATING REPORT i

OPERATING

SUMMARY

JUNE 1997 UNIT TWO i

The month began with the unit in refueling outage 2R12.

Criticality was achieved at 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br /> on the eighth. At 2004 hours0.0232 days <br />0.557 hours <br />0.00331 weeks <br />7.62522e-4 months <br /> on the ninth, the unit was

placed on-line marking the end of refueling outage 2R12. The turbine was taken off-line at 0936 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.56148e-4 months <br /> on the tenth for the turbine overspeed trip test, and placed back on line at 1444 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.49442e-4 months <br /> that _same day. One hundred percent power was attained at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on the sixteenth. The unit was operated at 100% power the remainder of the month.

4 There were no challenges to the primary system code safeties nor automatic actuations of the low temperature overpressure protection valves during the reporting period.

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. Reporting Period: June 1997 REFUELING INFORMATION l 1. Name of facility: Arkansas Nuclear One - Unit 2 l .

2. Scheduled date for next refueling shutdown: January 8.1999
3. Scheduled date for restart following refueling: February 22.1999
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 l- fuel design and core configuration been reviewed by your Plant Safety Review Committee to -

I determine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR

, Section 50.59)?

l I

Ho.No

5. Scheduled date(s) for submitting proposed licensing action and supporting information:
N/A l

j 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or .

j supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new j' operating proceduas, i

l None olanned j

! 4

7. The number of fuel assemblies (a) in the core (b) in the spent fuel storage pool and (c) dry cask j storage-l l a) 122 b)242 c) 48 i i

- 8. 'Ihe present licensed spent fuel pool storage capacity and the size of any increase in licensed storage

l. capacity that has been requested or is planned, in number of fuel assemblies:

present 281 increase size by 0

9. 'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the presentlicensed capacity:

Full core off-load capability no lonner available until a sufficient amount of spent fuel can be olaced in on-site dry storage.

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