ML20080K368

Forwards Monthly Operating Repts for Jan 1984

ML20080K368
Person / Time
Site:	Hatch
Issue date:	02/10/1984
From:	Nix H GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
References
GM-84-113, NUDOCS 8402150391
Download: ML20080K368 (1)

Text

Georgis Pow:r Company Post Offic> Bo. 43')

Bixity, Georgit 31513 Telephone 912 367-7781 912 537-9444 m

Georgia Power Edwin 1. Hatch Nuclear Plant February 10, 1984 GM-84-ll3 PLANT E.

I. HATCH NRC Monthly Operating Report Office of Plans and Schedules Directorate of Licensing United States Nuclear Regulatory Commission Washinnton, D.

C.

20545

Dear Sir:

Per Tech Specs section 6.9.1.6 please find attached the NRC Monthly Operating Report for Hatch Unit 1, Docket #50-321, and for Hatch Unit 2,

Docket #5C-366.

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NARMATIVE REPURT UNIT 1 January 1st 0000 Unit at rated power.

January 6th 2356 Load reauction for weekly turbine test.

January 7th 0146 Weekly turoine test complete ramping to ratea power.

January 7th 0500 Unit at rated power.

January 15th 0015 Load reouction weekly turbine test.

January 15th 0312 Weekly turoine test complete ramping to rated..

January 15th 0400 Unit at rated power.

January 22nd 0440 Load reduction for weekly turbine test.

January 22no 0950 Turbine test complete ramping to ratea.

January 22nd 1400 Unit at rated power.

January 28th 0025 Loao reduction for weekly turbine test.

Jentary'28th 0150 Turbine test complete ramping to rated.

Janucry 28th 0400 Unit at rated power.

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NAMRATIVE REPORT UNIT 2

' January ist 0000 Ramping to rated aftel 4160 "A"

bus tripped causing "A" recirc pump to trip.

January 2nd 0000 Unit at rated power.

January 8th 0010 Load reduction for weekly turbine test.

January 8th 0500 Unit at rateo power.

January 13th 0857 Ramping down for recirc pipe replacement outage & refueling.

January 13th 2009 Reactor manually scrammeo'to start recirc. pipe replacement outage ano refueling.

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HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR JANUARY 1984 82-7899 11-28-83 E41, aojust u-Dolt on support E41-HPCIH-35 per drawing E41-HPCIH-35 &

E41-105, Ref. DCR 81-58.

83-8739-12-20-83 1E41-HPSEH-55, L31 hyd.

snubbers. This snubber was leaking & was replaced with a new one.

83-8737 12-20-83 1E41-HPSEH-918 L31. This snubber was leaking it was replaced by a new one.

83-8736 12-20-83 1E41-HPSEH-92 same as above HR.

83-8734 12-20-83 IEll-RHRH-202 work same as above.

83-7903 12-02-83 1C41 pipe support adjusted u-bolt on snubber C41-F1-H001, Ref. DCR 81-58.

83-7897 12-06-83

-P52 pipe support adjust u-bolt. Ref. LER 1981-103, DCR 81-58.

83-7902 11-28-83 Ell pipe support adjust u-bolt. Ref. LER 1981-103.

83-7938 12-06-83 L36 pipe insulation removed pipe insulation for u-oolt adjustment & then replaced.

Ref. DCR 81-58.

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83-728 12-08-83 lZ43, fabricated & install supports & installed conduits for DCR 80-348.

82-6688 10-17-83 lEll-RHRH-20 moulfied existing support per attached sketches for DCR 62-75.

83-7895 12-02-83 P41, adjusted u-bolts for DCR 81-58.

HATCH 1 5AFETY-RELATED MAINTENANCE REQUESTS 70 bE REPORTED FOR JANUARY 1984 NUMBER DATE COMPLETED DESCRIPTIOf4 83-8491 12-06-83 IC11 reactor protection system, scram dischurge volume, installeo new raceways & supports Ref. OCR 82-219.

82-7603 11-11-83 1Z43, fire detection cables, disconnect cables shown on sketch 8-E-80-348-275 reconnect cables as shown on sketch B-E-80-348-276 atter conduit IMC-7963 is rerouted. Ref. DCR 80-348, Rev.

1.

82-7373 11-11-83 1Z43, fire detection system reworked cables for DCH 80-398.

82-5064 12-05-83 lY42, fire protection storage tanks level switches engraved annunciator winoows 79 & 80 on panel H11-655.

Ref. DCR 79-462.

83-7761 12-05-83 1C11-F014A, CRD pump discharge valve. Tne hand wheel on this valve was fixed so it could be turned.

DCR 83-256.

83-8738 12-19-83 1E41-HPSEH-608 3 kip snubbe r L-31 replaced snuober with new hydraulic snubber.

83-8735 12-19.-83 lEll-RHRH-249 L31 hydraulic j

snubbers, this snubber had a 1eak it was replaced with a new one.

83-8751 12-21-83 C11-LE-N060A,B,C,D &

C11-Lb-N660A,B,C,0 reactor protection system perform DCR 82-219 modifications as per attacneo work package.

Ref. DCR 82-219.

83-7896 12-02-83 831, pipe supports adjust u-bolts on supports 631-101-H001 & b)J-F12-H801.

Ref. UCR 61-58.

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HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR JANUAHY 1984 NUMBER DATE COMPLETE DESCRIPTION 83-le58 01-09-o4 2A70 ATTb paas a tubing supports, painted the ATTS paas & tubing. Hef. DCR 81-139.

83-2324 12-06-63 2C11 CRD vents & drains.

Pulled cables per cable pull cards. Ref. OCR 82-206.

83-5027 11-09-83 2T28 Painted all hangers &

piping on attachea list.

ref. DCR 62-076.

83-4943 12-06-83 2C11-N060A,b,C,D reactor protection system / scram discharge volume. Calibrated level elements & level switches. Ref. DCR 62-220.

83-4788 11-22-83 2V43 Hadwaste sprinkler system engraved annunciator window.s 17 & 18. Ref. CLR 82-128.

83-2428 06-08-83 2831-GOOl Elbow to pipe weld overlayea the weld with ER306L wela material as per DCH 83-63 a associated welaing procedures Ref. DCR 83-o3 & hhp-2-10174 & WP5-35.

83-2879 06-08-83 2831-G001 Pipe to pipe weld overlayed the weld with ER3066 weld material as per DCR 83-63 & associated welding procedures. Ref. DCR

• 83-63 HNP-2-10174 & WSP-35.

83-2876 06-08-83 2831-GOOl pipe to elbow weld overlayed the weld with ER 308L weld material as per DCR 63-63 & associated weloing procedures. Ref. DCR 83-63, HNP-2-10174 WPS-35.

83-2877 06-08-63 2831-G001 Pipe to pipe weld overlayeo weld with weld material as per DCR 83-63 &

associateo welding procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.

HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TU BE REPORTED FOR JANUARY 1984 83-2577 06-08-63 2831-G001 Pipe to pipe weld overlayed weld with welo material as per DCR 83-63 &

associated weloing proceoures. Ref. DCH 83-63, HNP-2-10174, WPS-35.

83-2582 06-08-83 2631-G001 Pipe to pipe weld overlayed welo with weld material as per DCR 83-63 &

associated welding procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.

83-2581 06-08-83 2831-G001 Pipe to pipe weld overlayed weld with welo material as per DCR 83-63 &

associated welding procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.

83-2583 06-08-83 2831-GUO1 Pipe to elbow welo overlayed weld with ER308L welo material as per DCR 83-63 & associated welding procedures. Hef. DCR 83-63, HNP-2-10174, WPS-35.

83-2385 06-08-83 2B31-G001 Pipe to elbow weld overlayed weld with ER308L weld material as per DCR 83-63 & associated welaing procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.

83-2473 06-08-83 2831-G001 Pipe to elbow welo overlayeo weld with ER308L weld material as per DCR 83-o3 & associatea weloing procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.

83-2448 06-08-83 2831-G001 Pipe to elbow weld overlayeo weld with Ek30el weld material as,er DCR o

83-o3 & associateo weloing procedures. Ref. DOR 83-63, HNP-2-10174, WPS-35.

83-2522 06-08-83 2B31-G001 Pipe to elbow weld overlayeo welo with ER308L weld naterial as per DCR 83-63 & associateo welding procedures. Ref. OCR 83-63, HNP-2-10174, WPS-35.

1 S3-2523 06-08-83 2831-G001 Pipe to elboo weld

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overlayea weld with ER308L weld material as per DCR 83-63 & associated welding procedures. Ref. OCR 63-63, HNP-2-10174, WPS-35. 6058 11-22-83 2G31-F069 RWCU condensate pressure control valve-installed 200 PSI bourdon tube in 2G31-F089. Ref. UCR 83-221.

83-2578 06-08-83 2831-G001 Pipe to elbow weld overlayea weld with ER308L weld material as per DCR 83-63 & associated welaing procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.

s 83-6481 12-21-63

' 2G31-N012 RWCU flow inaicator repairea indicator. Ref. OCR 83-285.

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OPERATING DATA REPORT DOCKET NO.

50-321 DATE 02-10-84 COMPLETED BY: D. P.-Rafeedie TELEPHONE (912) 367-7851

' OPERATING STATUS Notes 1.

Unit Name: E. I. Hatch NLJclear Plant Unit 1 2.

Reporting Period: 01-84 3.

Licensed Thermal Power (MWt): 2436 4.

Nameplate Rating (Gross MWe): 809.3 5.

Design Electrical Rating (Net MWe): 777.3 6.

Maximum Dependable Capacity (Gross MWe): 801.2 4

7.

Maximum Dependable Capacity (Net MWe): 752.2 8.

If Changes Occur in Capacity Ratincp (Irems Number 3 through 7) Since Last Report, Give Reasons:

The MDC (Net MWe) Value Has Been UpdattJ 9.

Power Level to hhich Restricted, If Any (Net MWe)

10. Reasons for Restrictions, If Any:

1 i

This Month Yr-to-Cate Cumulative

11. Hours In Reporting Period 744 744 70871 4

12. Number of Hours Reactor was Critical 744.0 744.0 50269.2

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 744.0 744.0 47137.0

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1799976 1799976 99018004

17. Gross Electrical Energy Generated (MWH) 599160 599160 32057330 5~

18. Net Electrical Energy Generatea (MWH) 574346 574346 30433709 4

19. Unit Service Factor 100.0 100.0 66.5

20. Unit Availability Factor 100.0 100.0 66.5 i

21. Unit Capacity Factor (Using MDC Net) 102.6 102.6 57.1

22. Unit Capacity Factor (Using DER Net) 99.3 99.3 55.2

23. Unit Forcea Outage Rate 0.0 0.0 18.2

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

25. If Shutdown at End of Report Period, Estimated Date of Startup:

1

26. U11ts in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

AVERAGE DSILY UNIT POWER LEVEL DOCKET NO.

50-321 DATE:

02-10-84 J

COMPLETED BY: D. P. Rafeedie TELEPHONE (912) 367-7851 MONTH 01-84 l

l DAY AVERAGE GAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) l 1

767 17 7 71 2

774 IS 772 3

774 19 776 4

774 20 777 5

773 21 776 6

775 22 742 7

756 23 772 8

775 24 772 9

773 25 7 71 10 766 26 775 11 773 27 776 12 777 28 769 13 776 29 777 14 776 30 779 15 765 31 779 16 773 (9/77)

OPERATING DATA REPORT DOCKET NO.

50-366 DATE 02-10-84 COMPLETED BY: D. P. Rafeedle TELEPHONE (912) 367-7851 OPERATING STATUS Notes 1.

Unit Name: E. I. 9 tch Nuclear Plant Unit 2 2.

Reporting Perior: 01-84 3.

Licensed Therma: Power (MWt): 2436 4.

Nameplate Rating (Gross MWe): 317.0 5.

Design Electrical Rating (Net MWe): 784.0 6.

Maximum Dependable Capacity (Gross NWe): 803.9 7.

Maximum Dependable Capacity (Net MWe): 747.9 i

8.

If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons:

The MDC (Net MWe) Value Has Been Updated 9.

Power Level to Which Restricteo, If Any (Net MWe):

10. Reasons for Restrictions, If Any:

I i

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744 744 38497

12. Number of Hours Reactor was Critical 308.2 308.2 27379.4

13. Reactor Reserve Shutdown Hours 0

0 0

l

14. Hours Cenerator On-Line 308.2 308.2 26096.1 l

15. Unit Reserve Shutdown Hours 0

0 0

l

16. Gross Thermal Energy Generated (MWH) 726912 726912 55943167

17. Gross Electrical Energy Generated (MWH) 242640 242640 18a 4420 l

18. Net Electrical Energy Generated (MWH) 230541 230541 17519648

19. Unit Service ' actor 41.4 41.4 67.8 l-

20. Unit Availability Factor 41.4 41.4 67.8 l

21. Unit Capacity Factor (Using MDC Net) 41.4 41.4 60.8

22. Unit Capacity Factor (Using DER Net) 39.5 39.5 58.0

23. Unit Forced Outage Rate 0.0 0.0 13.1

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

l

25. If Shutdown at End of Report Perloc, Estimated Date of Startup:

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

Forecast Achievec INITIAL CRITICALITY.

INITIAL ELECTRICITY COMMERCIAL OPERATION

I AVERAGE DAILY UNIT POWER LEVEL' DOCKET NO. 366 DATE:

02-10-84 COWLETED BY: D. P. Rafeedle TELEPHONE (912) 367-7851 MONTH 01-84 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 647 17

-6 2

768 18

-6 3

775 19

-5 4

776 20

-5 5

780 21

-5 l

6 779 22

-5 7

780 23

-5 1

8 771 24

-5 9

778 25

-5 10 773 26

-3 i

11 773 27

-4 777 28

-4 l

13 524 29

-4 14

-11 30

-4 15

-7 31

-4 l

16

-6 (9/77)

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50-321 UNIT SHUTDOWN 3 AND FOWER REDUCTIONS 4 DOCKETNO. Hat.cn 1 UNIT NA3f E Uz-lu-64 DATE January COMPLETED BY D.P. Rafeedie REFORT MONTri "'

TELEPHONE 912-367-7851

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84-1 l 01-06-84 S

5.1 B

5 NA.

HA TURBIN Weekly turbine test.

84-2 01-15-84 S

2.95 B

5 NA t'A TURBINE Weekly turbine test.

84-3 01-22-84 S

9'.34 8

5 NA HA TURBIN Weekly turbine test.

84-4 01-28-8.4 S

'3.58 8

5 NA HA TURBIN Weekly turb'ine test.

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4 F: Forced Reason:

Ple: hod:

. Exhibit G - Instructions S: Sch:duled A6;uip:n:nt Taitur:(Exp!:in) 1 ?!?.nual tfor Preparation of Data B..!:inte. nance ci Test 2 Lneal S:r:m.

Entry Sh:ets for Licensee C-Refueling J Auturnatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4 -Continuations 0161)

E-Operatar Training & Ucense Examination 5--Ioad reduction 3

F-Administrative 9--Other (Explain) r:

Exhibit I.Same Source G-Operation:1 Error (Explain)

(9/77) ll Oth:r (Exp!:ir:)

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50-366 UNIT SliUTDOWNS AND FOWER REDUCTIONS

- - Ui IE' Hatch 2 DATE 02-10-84 COMPLETED BY D P. Rafooriin REFORTMONTri January 7_

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'Cause & Corrective No.

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~34-1 01-01-84 S

24 A l5 NA CB ELEC0ti Ramp from "A" 4160 ' bus trip which-trip "A" recirc pump.,

84-2 01-08-84 S

2.28 8

5 NA HA TURBIN Weekly-turbine test.

84-3 01-13-84 S

11.2 H

5 NA CB PIPEXX Ramp.down for recirc pipe replacement &

l refueling outage.

84-4 01-13-84 S

435.8 H

2 NA CB PIPEXX Recirc pipe replacement outage.

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4 F: Forc:d R:ason:

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S: S:heduied A E;uip.m:nt'Failur:(Exphin) 14hnuel Exhibit C Instructions

~ for Prep 2 rat;on of Data E.?.hintenance ci Test 2.*.!an ce! Su:m.

Entry Sh:ets for Licensee

c. Refueling 3-Auturnstic S: ram.

Event Report (LER) File (NUREG-D Regulatory Restriction 4 -Continuations 0161)

E-Operator Training & Ucense Examination F-Admimstrative 5-Ioad Itduction G-Operational Error (Exp!.:in) 9-Other (Explain)

S (9/77) li Oth:r (Exp!:in) g-Exhibit I-Same Source

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