ML20063J514

From kanterella
Revision as of 11:53, 23 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Monthly Operating Rept for Jan 1994 for Arkansas Nuclear One,Unit 2.W/940215 Ltr
ML20063J514
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 01/31/1994
From: Mims D, Whitt M
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN029403, 2CAN29403, NUDOCS 9402230323
Download: ML20063J514 (8)
v • d • e


Text

4

. ~- cat rsv on r tiaa iac-

-- Enter 9Y n , 1 s , wo .

Operations ~

- e. ace ,

. ea o .

_ . , , , . - . _ . _ _ . . . . . _ _ . . . . . _ . . . _s.._ _ _ . _ , _ . . _ . . , _ . _ _ , . . . _ _ . . . . . _ . . _ . . _ _ _ _ . _ . _ _ . _ . .

February 15,1994 2CAN029403 U. S. .uclear Regulatory Commission Document Control Desk hiail Station Pl-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report Gentlemen:

The Arkansas Nuclear One - Unit 2 Monthly Operating Report (MOR) for January,1994 is attached. This report is submitted in accordance with ANO-2 Technical Specification 6.9.1.6. Also,in accordance with ANO-2 Technical Specification 6.9.1.5.c and NUREG-0737, Item II.K.3.3, attached is the 1993 Annual Report of Challenges to Pressurizer Safety Valves.

Very truly yours, l

i Af qd C. -th'6 ,

Dwight C. Mims l Director, Licensing DCM/jrh Attachment l

1 I l hR hhD C B i t _.

't U.S.NRC February 15, 1994 .

2CAN029403 Page 2 cc: Mr. Leonard 1 Callan  !

Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400  ;

Arlington, TX 76011-8064 '

i NRC Senior Resident inspector ,

Arkansas Nuclear One - ANO 1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801  !

Mr. George Kalman NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852  ;

i j Mr, Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 131I-3 ,

One White Flint North  ;

11555 Rockville Pike Rockville, Maryland 20852 I

t L

S I

A e

t E

. _._ ..- _ __ ~._ _ . _ - , _ .

OPERATING DATA REPORT l DOCKET NO: 50-368 DATE: February 3,1994 COMPLETED BY: M. S. Whitt TELEPHONE: (501) 964-5560 QPfiMTING STATUS q i

1. Unit Name: Arkansas Nuclear One - Unit 2  !
2. Reporting Period: January 1-31,1994
3. Licensed Thermal Power (MWI): 2.815 t 4 Nameplate Rating (Gross MWe): 942.57
5. Design Electrical Rating (Net MWe): 912  ;
6. Maximum Dependable Capacity (Gross MWe): 897
7. Maximum Dependable Capacity (Net MWe): 858 l
8. If Changes Occur in Capacity Ratings (ltems Number 3 Through 7) Since j Last Report, Give Reasons: i
9. Power Level To Which Restricted. If Any (Net MWe): None l
10. Reasons For Restrictions. If Any: Nonc j MONTH YR-TO-DATE GMULATIVE I 1. Hours in Reporting Period . 744.0 744.0 121,440.0
12. Number ofIlours Reactor was Critical . . . 744.0 744.0 93,565.7  !
13. Reactor Reserve Shutdown llours . . 0.0 0.0 0.0 I4. llours Generator On-Line . 744.0 744.0 91,670.0
15. Unit Reserve Shutdown Hours . . 0.0 0.0 0.0 -
16. Gross Thermal Energy Generated (MWII) . . 2,060,587 2,060,587 243,040,570 '
17. Gross Electrical Energy i Generated (MWH) . 681,903 681,903 80,004,240
18. Net Electrical Energy Generated (MWH) . 651,769 651,769 76,124,678 ~ 7
19. Unit Service Factor . . 100.0 100.0 75.5
20. Unit Availability Factor . 100.0 100.0 75.5
21. Unit Capacity Factor (Using MDC Net) . 102.1 102.1 73.1 l
22. Unit Capacity Factor (Using DEC Net) . 96.1 96.1 68.7
23. Umt Forced Outage Rate . . .

0.0 0.0 11.1

24. Shutdow ns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):  !

Refueling Outage 2R10 is scheduled for March 11.1994 through April 24.1994.

25, if Shut Down At End of Report Period. Estimated Date of l Startup.

26. Units in Test Status (Prior to Commercial Operation): '

Forecast Achieved INITIAL CRD ICALITY 12/05/78 INITI AL ELECTRICITY 12/26n8 COMMERCIAL OPERATION 03/26/80  ;

i i

AVERAGE DAILY UNIT POWER LEVEL

  • DOCKET NO: 50-368 UNIT: Two ,

DATE: February 3,1994 COMPLETED BY: M. S. Whitt TELEPilONE: (501) 964-5560 MONTil 1;tmaryJ994 DAY AVERAGE DAILY POWER LEVEL ,

(MWe-Nei)

I . 895 2 896 3 896 4 896 I 5 896 .

6 894 7 898 8 896 9 , , 896 10 . . 897

11. .. 894 12 . , 887 s 13 . . 890 ,

14 . 892 i- 15, 893  ;

16 , 893

17. . 892 >

18, 892

19. 890 l 20. . .. 890 4
21. 724 22 . 704
23. 794 I
24. . 882  ;
25. 880
26. 881
27. . 881 l
28. 884 i
29. 884 .i

! 30. 884 l

! 31. 888 I l

i AVGS: 876 j i

i LNSTRUCTION

-i 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.  ;

i 1

i a

l; -

t. . .

-l

'1 l

l NRC MONTIILY OPERATING REPORT 1

OPERATING

SUMMARY

JANUARY 1994

]

UNIT TWO i l

The unit began the month of January operating at 100% power. At 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on the twenty-Grst, an elective power reduction was initiated to locate and plug a very small condenser tube leak. The leakage was low enough that the steam generator chemistry  ;

remained within speciGcations. After the tube was plugged at 1125 on the twenty-third, the unit return to full power operation at 1717 on the same day. Unit 2 operated at 100% power for the remainder of the month.

t i

l l

l i

l a

4 UNIT SilUTDOWNS AND POWER REDUCTIONS

, REPORT FOR JANUARY,1994 .

DOCKET NO.. 50-368 UNIT NA31E ANO Umt 2 DATE February 3,1994 COMPLETED BY M. S. Whin TELEPIIONE 501- % *-5560 SIETIIOD OF LICENSEE DURATION SilUTTING DOWN EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO M DATE TYPE' (IfoURS) REASONt REACTOR 2 REPORTE CODE' CODE 5 PR EVENT RECI'RR ENCE

. none W

t i

1 2 3 4 I

F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A - Equipment Failure (Esplain) 1 - Manual for Preparation of Data B - Maintenance of Test 2 - Manual Scram. Entry Sheets for Licensee C - Refueling 3 - Automatic Scram. Event Report (LER) Flie (NUREG-0161)

D- Regulatory Restriction ~ 4 - Continuation

! E - Operator Training & Ucense Examination 5 -lead Reduction i F-- Administration 9 - Other - 5 G - Operational Ermr Exhibit 1 - Same Source II - Other (Explain)

. . . . . . . . _ -- - . . - . ..- . . - - ~_ ~ ..

~

e 4 DATE: January,1994 REFUELING INFORMATION

1. Name of facility: Arkansas Nuclear One - Unit 2
2. Scheduled date for next refueling shutdown. Mprch 11.1994 l
3. Scheduled date for restart following refueling. April 24.1994
4. Will refueling or resumption of operation thereafler 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 yc,ur Plant Safety Review Committee to determine whether any unreviewed safety questions are associated -

with the core reload (Ref.10 CFR Section 50.59)? -

Xes. Technic.aLSaesification chinges to relocate;2qlqJpscific par.gmelers to a Core OpsIatiDELinlits.Jlep.g_rL

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

QuLngelsub1nitted July 22,199_3L

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.

EQut  :

7. The number of fuel assemblies (a)in the core and (b) in the spent fuel storage pool.

a) 177 b) 565

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 988 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: 1997 (Loss of full core off-load capability) ,

g .e-..e t,- * , . , i-.,- - ,s-. o +- e , ---w - , , .. , e ., - - w

(J I . =

ATTACilMENT

.l l

ANNUAL REPORT OF SAFETY VALVE  :

I FAILURES AND CIIALLENGES UNIT TWO ,

This annual report is submitted in the January Monthly Operating Report in response to requirements implemented as a result of NUREG-0737, Item II.K.3.3 and to fulfill Technical Specification reporting requirements (TS 6.9.1.5.C).

For ANO-2, no challenges to the primary system code safeties have occurred in the year 1993.

4 1

i 4

._ _ _ _ .

Retrieved from "https://kanterella.com/w/index.php?title=ML20063J514&oldid=2668436"