ML20197D435

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Monthly Operating Repts for Feb 1986
ML20197D435
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 02/28/1986
From: Kanipe L, Nix H
GEORGIA POWER CO.
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LR-MRG-009-0386, LR-MRG-9-386, NUDOCS 8605140269
Download: ML20197D435 (16)


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NARRATIVE REPORT UNIT ONE February 1st 0000' Unit in cold shutdown for Refueling Outage.

February '6th 0206 Core reload in progress.

2 February 28th 2400 Unit in cold shutdown for Refueling Outage. Fuel load in progress. Expected startup April 01, 1986.

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NARRATIVE REPORT UNIT TWO February 1st 0000 Unit on line at 679 GMWE and 2068 CMWT (84.9% power). Holding power per management decision to help relieve offgas activity in reactor and turbine buildings.

February 15th 0100 Reducing power to 75% for Turbine and MSIV testing.

0345 Ramping back to 85% power.

0600 Back at 85% power.

Ukitat85%powerwithnomajor February 28th 2400 equipment problems.

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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR FEBRUARY 1986 NUMBER DATE COWLETED DESCRIPTION 85-2287 02-01-86 Installed 8 new RTD's with supports per WPS-81-196-J001, J002, and J003 Ref. DCR 81-196.

82-0329 02-01-86 Installed HVAC systems in Unit 2 annex portion of building for Technical Support System.

Ref. DCR 80-157 Rev. 1.

85-0603 02-05-86 Installed internal wiring from SPDS power inverter 1R44-5004 to the 125/250V D/C Swgr local control panel.

Ref. DCR 80-157 Rev. 1.

84-7867 02-01-86 Removed, repaired, and replaced multiplexer (X75-K109) wiring and supports in panel X75-P104 for Emergency Response Facility per

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WPS-80-157-EM51.

Ref. DCR 80-157 Rev. 1.

85-2505 02-01-86 Installed internal

, jumpers in panel 1Hil-P602 and rewired cables in panel i

X75-P104

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Ref. DCR 80-157 Rev.1.

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86-0277 02-01-86 Change out 250 Volt DC breakers (R22-5016) with refurbished breaker equipped with modified trip elements.

Ref. DCR 85-221 Appendix "R".

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s HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR FEBRUARY 1986 NUMBER DATE C0fCLETED DESCRIPTION 85-6274 02-13-86 Disconnected cables from recorder lEll-R608 per WPS 81-138-T039.

Ref. DCR 81-138 Rev. 1.

86-0571 02-01-86 Corrected wiring on the RSCS 5 volt DC power supply per WPS-84-321-E004 Ref. DCR 84-321.

84-8394 02-01-86 Built and installed support for power supply ICll-P59 in panel 1Hil-P616 per WPS 84-321-E003 and E004 Ref. DCR 84-321.

85-4058 02-01-86 Added jumper and rewired cables in panel 1Hil-P601 for SPDS per WPS-80-157-EM71.

Ref. DCR 80-157 Rev 1.

85-7674 02-26-86 Removed pipe clamp on pipe support and shorten eyerod length to minimum clearance of 8 inches.

Ref. DCR 85-120 85-7402 02-26-86 Removed shim plates on recirc piping 12" riser to provide access for weld overlay and reinstalled new shim plates upon completion of weld overlay.

Ref. DCR 85-120. 7104 02-14-86 Performed flush and hydro test of newly Installed ATTS tubing in accordance with plant procedures.

Ref. DCR 81-138 Rev. 1.

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR FEBRUARY 1986 NUMBER DATE COPLETED DESCRIPTION 85-7079 02-16-86 Upgrade HFA relays in the lE51A system in panels lHil-P621 and P623 to GE Century Series relays per WPS 82-171-E033 Ref. DCR 82-171.

85-6509 02-17-86 Adjustment and tested upgraded HFA Century series relays per WPS 82-171-E030 and procedure 42SP-DCI-013-lS.

Ref. DCR 82-171.

84-5277 02-17-86

" Pulled and terminated class lE analog cables to panels 1Hll-P691 A&B and pulled non-class lE cables from panel 1H11-P691 A&B to SPDS consoles per WPS 80-157-ECO3.

Ref. DCR 80-157 Rev. 1.

85-7673 02-15-86 Removed pipe support to provide clearance for IHSI per WPS 85-120-M012.

Ref. DCR 885-120.

85-7403 02-20-86 Removed insulation from the recirculation system sampling line per procedure AG-ADM-22-0585 Ref. DCR 85-120.

86-0320 02-22-86 Performed flush and hydro test on E41 system for ATTS per procedures 42SP-DCT-043-lS and 42SP-DCT-044-lS.

Ref. DCR 81-138 Rev. 1.

85-7435 02-22-86 Performed flush and hydro test of ATTS tubing on lE11 (loop B) system. Also performed pneumatic test to determine the operability of instruments 1C71-N050 C&D and 1 Ell-N094 B&D.

Ref. DCR 81-138 Rev.1.

85-7080

$13-86 Upgraded HFA relays in lE41A system J

in panel 1H11-P620 to G.E. Century Series relays per WPS 82-171-E032 Ref. DCR 82-171.

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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR FEBRUARY 1986 NUMBER DATE COWLETED DESCRIPTION 85-5611 02-01-86 Terminated 8 cables, revised terminal points, and added cell switches in switchgear R22-S001, S002, S003, and S004 per WPS 80-157-EM 77 Ref. DCR 80-157 Rev.1.

85-5950 02-01-86 Performed internal wiring and installation of devices in panel Di21-P331 Der WPS 78-359-E001.

Ref. DCR 78-359 i

85-6989 02-25-86 Replaced existing Rosemont Transmitters with new Rosemont transmitters and seals per WPS 84-205-E001, M001, J001, and J002 Ref. DCR 84-235 84-7868 02-06-86 Removed defective power supply from panel 1H11-P605A and i

replaced with new power supply.

Ref. DCR 80-157 Rev. 1.

85-5174 02-01-86 Replaced Limitorque motor actuators on the 1831 system 1

per WPS 81-093-E002 Ref. DCR 81-093 85-7272 02-06-86 Installed temporary power c'bles and disconnect switches a

in order to perform work activities on DCR 85-120 (IHSI weld overlay repair).

85-6548 02-03-86 Upgraded HFA relays in lEllA system in panel 1H11-P617 to G.E. Century series relays per WPS 82-171-E023 Ref. DCR 82-171.

85-6556 02 03-86 Upgraded HFA relays in lA718 and 1C61 systems in panel lH11-P623 to Century series relays per WPS 82-171-E027 Ref. DCR 82-171.

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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR FEBRUARY 1986 NUMBER DATE COWLETED DESCRIPTION 85-7945 02-10-86 Upgraded WA relays in panel 1H11-P652 to Century Series relays per WPS 82-171-E037 Ref. DCR 82-171.

84-6081 02-06-86 Set breaker trip element per design and perform bench test for proper function operation for D.C. breakers frame 48 of D.C. switchgear 1R22-S016.

Ref. DCR 80-157 Rev.1.

i 84-5809 02-06-86 Replaced existing Buchanan terminal blocks with new Beau l

type terminal blocks per WPS 80-157-EM29.

Ref.80-157 Rev. 1.

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HATCH 2 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR FEBRUARY 1986 NUMBER DATE CO R ETED DESCRIPTION 85-0563 02-06-86 Replaced limitorque motor rewound by Forest Park with a new motor.

Ref. DCR 85-238.

85-4895 02-01-86 Replaced limitorque motor on 2E11-F047B with new E. Q. motor Ref. DCR 85-238.

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c-OPERATING DATA REPORT 00CKET NO.

50-321 DATE 03-10-86 COMPLETED BY: Lee Kanipe TELEPHONE (912) 367-7851 x 2882 l

OPERATING STATUS

1. Unit Name: E. I. Hatch Nuclear Plant Unit 1
2. Reporting Period:.

02-86

3. Licensed Thermal Power (MWt):

2436

4. Nameplate Rating (Gross MWe):

809.3

5. Design lElectrical Rating (Net MWe):

777.3

6. Maximum Dependable Capacity (Gross MWe):

801.2

7. Maximum endable Capacity (Net MWe):

768.0

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

N/A

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 672 1416 89087
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

38207686*

19. Unit Service Factor 0.0 0.0 65.7
20. Unit Availability Factor 0.0 0.0 65.7
21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 55.8
22. Unit Capacity Factor (Using DER Net) 0.0 0.0 55.2 l
23. Unit Forced Outage' Rate 0.0 0.0 17.5
24. Shutdowns scheduled over next 6 months (Type, Date, and Duration of Each):

l Refueling Outage began November 27, 1985 14 weeks l

25. If shutdown at end of report period, estimated date of startup: April 1, 1986 l
26. Units in Test Status (Prior to Commercial Operation):

N/A l

  • NOTE: The cumulative Net Electrical Generation includes station service used while shutdown.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-321 DATE:

03-10-86 COMPLETED BY: Lee Kanipe TELEPHONE (912) 367-7851 x 2882 4

F MONTH 02-86 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

t 3

0 19 0

l 4

0 20 0

5 0

21 0

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0 22 O

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0 23 0

8 0

24 0

9 0

25 0

10 0

26 0

l 11 0

27 0

l 12 0

28 0

13 0

14 0

I 15 0

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16 0

l NOTE: Net power level does not include the station service used while shutdown.

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l DOCKET NO.

50-321 UNIT NAE HATCH ONE COWLETED BY Lee M. Kanipe Jr.

TELEPHONE (912) 367-7851 (2882) DATE MARCH 10,1986 REPORT MONTH FEBRUARY I

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Method:

Events reported involve S: Scheduled A-Equipment Failure (Explain) 1-Manual a greater than 20% reduction l

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 Restriciton 4-Continuations E-Operator Training & License 5-Load Reduction j

Examination 9-Other (Explain)

F-Admin 13trative G-Operational Error (Explain)

H-Other (Explain)

OPERATING DATA REPORT DOCKET NO.

50-366 DATE 03-10-86 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:

02-86 3.

Licensed Thermal Power (MWt):

2436 4.

Nameplate Rating (Gross MWe):

817.0 5

Design Electrical Rating (Net MWe):

784.0 6

Maximum Dependable Capacity (Gross MWe):

803.9 7

Maximum M ndable Capacity (Net MWe):

777.0 8

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

N/A 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 672 1416

% 713

12. Number of Hours Reactor was Critical 672.0 1347.2 38918.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 672.0 1300.8 37169.0
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1387008 2700016 80883222
17. Gross Electrical Energy Generated (MWH) 457030 892900 26674400
18. Net Electrical Energy Generated (MWH) 436459 852389 25391043
19. Unit Service Factor 100.0 91.9 65.5
20. Unit Availability Factor-100.0 91.9 65.5
21. Unit Capacity Factor (Using EC Net) 83.6 77.5 57.6
22. Unit Capacity Factor (Using DER Net) 82.8 76.8 57.1
23. Unit Forced Outage Rate 0.0 8.1 10.9
24. Shutdowns scheduled over next 6 months (Type, Date, and Duration of Each):

Refueling Outage beginning September 06, 1986 8 weeks i

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25. If shutdown at end of report period, estimated date of startup: N/A
26. Units in Test Status (Prior to Commercial Operation):

N/A

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-366 DATE:

03-10-86 COWLETED BY: Lee Kanipe TELEPHONE (912) 367-7851 x 2882 MONTH 02-86 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 654 17 647 2

653 18 646 3

651 19 645 4

650 20 650 l

5 648 21 643 6

647 22 644 7

652 23

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8 651 24 648 l

9 649 25 653 10 644 26 652

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12 653 28 655 1

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UNIT SHUTDOWNS ANO POWER REDUCTIONS DOCKET NO.

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

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F: Forced Reason:

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

F-Administrative G-Operational Error (Explain)

H-Other (Explain) l

UNIT SHUTDOWNS AND POWER REDUCTIONS

-DOCKET NO.

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

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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 Examination 9-Other (Explain)

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

Georgia Power Company s

Post Offica C:x 439 Baxley, Georgia 31513 Telephone 912 367-7781 912 537-9444 Edwin 1. Hatch Nuclear Plant March 10, 1986 LR-MGR-009-0386 PLANT E. I. HATCH NRC Monthly Operating Report Director Office of Management and Program Analysis U. S. Nuclear Regulatory Commission Washington, D. C.

20555

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 #50-366.

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H. C. Nix General Manager L*/kel xc:

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

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