ML20203E119

Monthly Operating Repts for Jan 1986

ML20203E119
Person / Time
Site:	Hatch
Issue date:	01/31/1986
From:	Kanipe L, Nix H GEORGIA POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LR-MGR-032-0286, LR-MGR-32-286, NUDOCS 8604240111
Download: ML20203E119 (13)

Text

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1 OPERATING DATA REPORT DOCKET NO.

50-321 DATE 02-10-86 COMPLETED BY: Lee Kanipe TELEPHONE (912) 367-7851 x 2882 OPERATING STATUS

1. Unit Name: E. I. Hatch Nuclear Plant Unit 1

2. Reporting Period:

01-86

3. Licensed Thermal Power (MWt):

2436

4. Nameplate Rating (Gross MWe):

809.3

5. Design Electrical Rating (Net MWe):

777.3

5. Maximum Dependable Capacity (Gross MWe):

801.2

7. Maximum bependable Capacity (Net MWe):

768.0

8. If changes occur in capacity ratings (Items Nunber 3 through 7) since last report, give reasons:

Item 7 changed from 752.2 to 768.0 because of Peak Period Continuous Rating Data. The change was based on actual performance during the previous year.

9. Power level to which restricted, if any (Net MWe)

No Restrictions

10. Reasons for restrictions, if any:

N/A This Month Yr-to-Date Cumulative

11. Hours In Reporting. Period 744 744 88415

12. Number of Hours Reactor was Critical 0.0 0.0 62126.2

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line; 0.0 0.0 58561.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 0 0.0 124631490

17. Gross Electrical Energy Generated (MWH) 0 0.0 40242130

18. Net Electrical Energy Generated (MWH) 0 0

38210136

19. Unit Service Factor 0.0 0.0 66.2

20. Unit Availability Factor 0.0 0.0 66.2

21. Unit Capacity Facter (Using HE Net) 0.0 0.0 56.3

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 55.6

23. Unit Forced Outage Rate 0.0 0.0 17.5

24. Shutdowns scheduled over next 6 months (Type, Date, and Duration of Each):

Refueling Outage began November 27, 1985 14 weeks b

25. If shutdown at end of report period, estimated date of startup: April 1, 1986

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

N/A D

B604240111 860131 PDR ADOCK 05000321 R

PDR

AVERAE DAILY UNIT POWER LEVEL DOCKET NO.

50-321 DATE:

02-10-86 COMPLETED BY: Lee Kanipe TELEPHONE (912) 367-7851 x 2882 MONTH 01-86 DAY AVERAGE DAILY POWER LEVEL DAY AVERAT DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1

-5 17

-6 2

-5 18

-5 3

-5 19

-5 4

-5 20

-6 5

-6 21

-6 6

-6 22

-6 7

-6 23

-6 8

-6 24

-5 9

-5 25

-5 10

-5 26

-5 11

-5 27

-5 12

-6 28

-5 13

-6 29

-5 14

-6 30

-4 15

-6 31

-4 16

-6 0

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UNIT SHJTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-321 UNIT NAE HATCH OE COMPLETED BY Lee M. Kanipe Jr.

TELEPHONE (912) 367-7851 (2882) DATE FEBRUARY 10,1986 REPORT MONTH JANUARY l

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F: Forced Reason:

Method:

Events reported involve S: Scheduled A-Equipmqnt Failure (Explain) 1-Manual a greater than 20% reduction B-Maintenance or Test 2-Manual Scram in average daily power level C-Refueling 3-Automatic Scram for the preceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D-Regulator l. 7estriciton 4-Continuations E-Operator aning & License 5-Load Reduction Examination 9-Other (Explain)

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

NARRATIVE REPORT UNIT 2 January 1st 0000 Unit at 705 GMWE and 2136 CMWT.

Ramping toward rated Maximuni Dependable Capacity (MDC) following scram on December 25, 1985. No major equipment problems.

0600 Reducing power to approximately 400 GMWE to clean circ water screens.

1110 Ramping toward rated K)C.

January 2nd 1000 Back at rated Mr.

January 5th 0000 Reducing power for weekly turbine testing.

0306 Testing complete. Ramping back to rated MDC.

0627 Back at rated MDC January 8th 1805 Reducing power to 85%.

Management decision to reduce power to help relieve offgas activity in reactor and turbine buildings.

Jaruary 18th 1615 Reducing load to take 2A P.ecirc Pump out of service due to Pump Motor Cooler Housing Leak alarm.

January 19th 0058 Turbine Generator off line.

0533 Rx. Scram on group ene isolation.

January 22nd 0110 Reactor startup in progress.

Control rod withdrawal commencing.

0220 Reactor critical.

January 23rd 2008 Turbine generator on line.

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Ramping toward 85% power.

January 24th 0430 Scram Time Testing in progress.

0900 Scram Time Testing complete.

Ramping toward 85% power.

January 26th 0800 Back at 85% power.

January 31st 2400 Unit on line at 679 GMWE and 2068 CMWT (84.9% power).

HATCH 2 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR JANUARY 1986 NU EER DATE COMPLETED DESCRIPTION 85-5059 01-08-86 Installed new static-O-ring pressure switches for Drywell Pneumatic system (2P70-N003) per WPS-85-180-J002, M002, E002, and E003 Ref. DCR 85-180 85-4186 01-14-86 Replaced LED's and added jumpers on trip units in control room, Group 100, 400, 500, and 600 of 2A71 (ATTS) system.

Ref. DCR 81-139.

84-6393 01-20-86 Installed Non-Class lE analog cables between panels X75-P601 and 2H11-P645 per

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WPS-80-157-EC17.

Ref. DCR 80-157 Rev 1.

85-5056 01-25-86 Reworked spared cables, tagged unidentified cable, and installed correct tags per WPS-80-157-EM78. Ref.

Deficiency Report 2-85-446 and DCR 80-157 Rev. 1.

84-6143 01-25-86 Provide a separate power supply for 2Y33-P008 per WPS-80-157-EC16 and RCO2.

Ref. DCR 80-157 Rev. 1.

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l OPERATING DATA REPORT l

DOCKET NO.

50-366 DATE 02-10-86 COWLETED BY: Lee Kanipe TELEPHONE (912) 367_-7851 x 2882 OPERATING STATUS 1.

Unit Name: E. I. Hatch Nuclear Plant Unit 2 2.

Reporting Period:

01-86 3.

Licensed Thermal Power (MWt):

2436 4.

Nameplate Rating (Gross PVe):

817.0 5.

Design Electrical Rating (Net MWe):

784.0 6.

Maximum ?ependable Capacity (Gross MWe):

803.9 7.

Naximum Sependable Capacity (Net MWe):

777.0 8.

If changes occur in capacity ratings (Items Number 3 through 7) since last report, give reasons:

Item 7 changed from 747.9 to 777.0 because of Peak Period Continuous Rating Data. The change was based on actual performance during the previous year.

9.

Power level to which restricted, if any (Net MWe):

No Restrictions

10. Reasons for restrictions, if any:

N/A This Month Yr-to-Date Cumulative

11. Hours In Reporting. Period 744 744 56041

12. Number of Hours Reactor was Critical 675.2 675.2 38246.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line; 628.8 628.8 36497.0

15. Unit Reserve Shutdown Iours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1313008 1313008 79496214

17. Gross Electrical Energy Generated (MWH) 435870 435870 26217370

18. Net Electrical Energy Generated (MWH) 415930 415930 24954584 r

19. Unit Service Factor 84.5 84.5 65.1

20. Unit Availability Factor 84.5 84.5 65.1

21. Unit Capacity Factor (Using MDC Net) 71.9 71.9 57.3

22. Unit Capacity Factor,(Using DER Net) 71.3 71.3 56.8

23. Unit Forced Outage Rate 15.5 15.5 11.0 c

24. Shutdowns scheduled over next 6 months (Type, Date, and Duration of Each): N/A

25. If shutdown at end of report period, estimated date of s: artup:

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

N/A

1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-366 DATE:

02-10-86 COMPLETED BY: Lee Kanipe TELEPHONE (912) 367-7851 x 2882 MONTH 01-86 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 637 17 653 2

772 18 515 3

774 19

-13 4

779 20

-14 5

772 21

-13 6

782 22

-12 7

781 23 6

8 766 24 306 9

671 25 618 10 665 26 654 11 662 27 660 12 662 28 655 13 659 1

29 652 14 659 30 655 15 657 31 656 16 654 e

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UNIT SFUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-366 UNIT NAE HATCH TWO COWLETED BY Lee M. Kanipe TELEPHONE (912) 367-7851 (2882) DATE FEBRUARY 10, 1986 REPORT MONTH,3ANUARY l

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Method:

Events reported involve S: Scheduled A-Equipment Failure (Explain) 1-Manual a greater than 20%' reduction B-Maintenance or Test 2-Manual Scra:n in average daily power level C-Refueling 3-Automatic Scram for the preceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D-Regulatory Restriciton 4-Continuations E-Operator Training & License 5-Load Reduction Examination 9-Other (Explain)

F-Adminis';rative G-Operational Error (Explain)

H-Other (Explain)

UNIT SRITDOWNS AND POWER REDUCTIONS DOCKET NO.

50-366 UNIT NAE HATCH TWO COMPLETED BY Lee M. Kanipe TELEPHONE (912) 367-7851 (2882) DATE FEBRUARY 10, 1986 REPORT MONTH JANUARY l

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Method:

Events reported involve S: Scheduled A-Equipment Failure (Explain) 1-Manual a greater than 20% reduction B-Maintenance or Test 2-Manual Scram in average daily power level C-Refueling 3-Automatic Scram for the preceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D-Regulatory Restriction 4-Continuations E-Operator Training & License 5-Load Reduction i

i Examination 9-Other (Explain) j F-Administrative G-Operational Error (Explain)

H-Other (Explain)

'O Georgio Power Company Post Orfica Box 439 Baxley, Georgia 31513 Telephone 912 367-7781 912 537-9444 Edwin I. Hatch Nuclear Plant i

l February 10, 1986 LR-MGR-032-0286 l

PLANT C. I. HATCH NRC Monthly Operating Report l

l Director Office of Management and Program Analysis U. S. Nuclear Regulatory Commission i

Washington, D. C.

20555 l

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 i

2, Jocket #50-366.

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/H. C. Nikj General Manager

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J. P. O'Reilly L. T. Gucwa Document Control File Chaouki Tabet e

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5 NARRATIVE REPORT UNIT 1 i.

January 1st 0000 Unit in cold shutdown for i !

Refueling Outage.

January 31st 2400.

Unit in cold shutdown for Refueling Outage. Expected startup April 01, 1986.

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1 HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS -

TO BE REPORTED FOR JANUARY 1986 NUMBER DATE COMPLETED DESCRIPTION 85-7500 01-12-86 Performed retest of relays 1EllA-K54A in panel 1Hil-P617 and A718-K32 in panel 1Hll-P623 in accordance with procedure 42SP-DCI-013-lS.

Ref. DCR 82-171.

85-6555 01-14-86 Upgraded HFA relays in 1821C system in panel 1H11-P628 to G. E.

Century series relays per WPS-82-171-E028.

Ref. DCR 82-171.

85-6552 01-14-86 Upgraded HFA relays in lA718 system in panels 1Hil-P609 to G. E.

Century series relays l

per WPS-82-171-E021.

Ref. DCR 82-171.

85-6554 01-14-86 Upgraded HFA relays in 1A71B and 1C61 systems in panel 1H11-P622 to G. E. Century series relays per WPS-82-171-E026.

Ref. DCR 82-171.

85-7944 01-12-86 Upgraded HFA relays in the IR20-827C system in panel 1H11-P652 to Century seiles relays per WPS-82-171-E036.

Ref.- DCR 82-171.

1 85-5275 01-16-86 Removed cylinder relief valves from Diesel Generator lA (lR43-S001A) and replaced with plugs per WPS-83-123-M003.

Ref. DCR 83-123.

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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR ]ANUARY 1986 9

NUMBER DATE COWLETED DESCRIPTION 85-7485 01-13-86 MWO voided - Work done under MWO l-85-6850 Sealing TSC Area.

Ref. DCR 80-157 Rev. 1.

85-6549 01-19-86 Upgraded HFA relays in the 1EllA system in panel 1H11-P618 to G. E. Century series relays per WPS-82-171-E024 Ref. DCR 82-171.

85-1391 01-30-86 Installed internal jumper between panels X75-P101 and X75-P102 to provide power for X75-P102 lighting, circuits, and receptacles per WPS-80-157-EM79 Ref. DCR 80-157 Rev.l.

85-6550 01-31-86 Upgraded HFA relays in the 1E41A system in panel lH11-P620 to G. E. Century series relays per WPS-82-171-E025 Ref. DCR 82-171.

86-0156 01-31-86 Replaced 250 volt DC breaker with refurbished breaker equipped with modified trip element.

Ref. DCR 85-221 Appendix "R" 85-3238 01-31-86 Changed inscription on annunciator window in panels X75-P101 and P102, and perform wiring in panels X75-P606 and P608 per WPS-80-157-EM67 and EM68.

Ref. DCR 80-157 Rev.1.85-083 01-31-86 Installed raceways in control building for SPDS (X75) per WPS-80-157-RC05, RC06, and RC07 j

Ref. DCR 80-7.57 Rev. 1.

86-0157 01-31-86 Replaced 250 volt DC breakt with refurbished breaker equipped with modified trip elements per WPS-85-221-E002.

Ref. DCR 85-221.

8 1