Text

Monthly Operating Repts for Mar 1986
	ML20206D944
Person / Time
Site:	Hatch
Issue date:	03/31/1986
From:	Koerber G, Nix H; GEORGIA POWER CO.
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	LR-MGR-029-0386, LR-MGR-29-386, NUDOCS 8606230005
	Download: ML20206D944 (17)
	v • d • e

.

NARRATIVE REPORT UNIT ONE March-1st 0000 Unit in cold shutdown for Refueling Outage.

March 7th 0532' Core reload complete.

March 31st 2400 Unit in cold shutdown for Refueling Outage.

Expected startup April 21, 1986 i

l 8606230005 860331

~

DR ADOCK 0500 1

3- (g3]

Er l

. ~.. -

~_

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR MARCH 1986 NUMBER DATE COMPLETED DESCRIPTI0tl 82-0330 03-01-86 Install structural work in Unit 2 annex for TSC.

Ref. DCR 80-157 82-0332 27-86 Install electrical work.

in Unit 2, annex for TSC per H-27115, H-27116, H-27117.

Ref. DCR 80-157 82-3901 03-12-86 Remove cir. breaker and panel from lR24-SO48, compt. lA and install in 1R24-S026, compt.

4A.

Install conduit supports and raceways.

Ref. DCR 80-157 83-2137 03-06-86 Pour concrete pads for 1Rll-S0098 and 1Rll-S0108.

Ref. DCR 80-157 Ref. DCR 82-172 84-4893 03-18-86 Repair Kennedy-magtape Y33-R016.

Ref. DCR 80-157 84-5520 03-04-86 Modify internal. wiring of MCR panels 1H11-P601, P602, P700-relative to class 1E digital signals.

Ref. DCR 80-157

i HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR MARCH 1986 NUMBER DATE COMPLETED DESCRIPTION 85-2341 03-02-86 Seal penetration in the north wall of the MG Set Room El. 158'.

Ref. DCR 83-244 85-5611 03-04-86 Complete the termination of 8 cables in switchgears 1R22-S001, S002, S003, S004.

Ref. DCR 80-157.

85-5814 03-01-86 Replace CS bowl assembly and transition column with SS components on the RHRSW pump B.

Ref. DCR 84-65 85-5950 03-18-86 Fabricate panel 1H21-P331 per drawing H-19626 and WPS 78-359-E001.

Ref. DCR 78-359 85-6946 03-19-86 Implement ATTS design changes per special instructions procedures 42SP-DCI-009-1S and 42SP-DCI-007-1S.

Ref. DCR 81-138.

85-7044 03-01-86 Replace motor on Limitorque with an EQ motor (lC11-F1408).

Ref. DCR 85-280 85-7051 03-06-86 Change set pressure of l

core spray suction valves lE21-F032A & B.

Ref. DCR 81-138 i

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS-TO BE REPORTED FOR MARCH 1986 NUMBER DATE COMPLETED DESCRIPTION 85-7094 03-10-86 Perform flushing / hydro of newly installed ATTS tubing for E41 system.

Ref. DCR 81-138 85-7095 03-11-86 Functional test new ATTS C71 instruments.

Ref. DCR 81-138 85-7098 03-19-86 Functional test new ATTS G31 instruments.

Ref. DCR 81-138 85-7099 03-10-86 Functional test new B21 instruments.

Ref. DCR 81-138, 85-7131 03-14-86 Remove shim plates on Reactor recirc system piping 12" risers for weld overlay access.

Reinstall when completed.

Ref. DCR 85-120.

85-7132 03-02-86 Construct weld head support for recirc B loop manifold end cap.

Ref. DCR 85-120, 85-7274 03-06-86 Remove structural steel tube strut from drywell platform.

Ref. DCR 85-120.

85-7392 03-10-86 Perform flushing / hydro on G31 system.

Ref. DCR 81-138 85-7395 03-10-86 Perform hydro test per H-78,79,80 on E21 system.

Ref. DCR 81-138 85-7400 03-06-86 Install temporary plant service water to the IHSI pump station.

Ref. DCR 85-120.

I

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR MARCH 1986 NUMBER DATE COMPLETED DESCRIPTION 85-7402 02-26-86 Remove shim plates on Reactor recirc piping to provide access for weld overlay.

Reinstall when through.

Ref. DCR 85-120.

85-7404 03-11-86 Construct a temporary weld head support for Recirc A loop manifold end cap.

Ref. DCR 85-120.

4 85-7405 03-01-86 Remove temporary steel box in accordance with WPS-85-120-C009.

Ref. DCR 85-120.

85-7407 03-12-86 Remove ISI instrumentation track on recirc piping at all discharge and suction nozzles to provide access for weld overlay.

Ref. DCR 85-120, 85-7408 03-12-86 Remove RWCU hangers for weld overlay access.

Reinstall when through.

Ref. DCR 85-120.

85-7411 03-06-86 Remove shim plates on Reactor recirc piping to provide access for weld overlay.

Reinstall when complete.

Ref. DCR 85-120.

85-7414 03-06-86 Coped out 1/4" plate that overlaps hoop of whip restraint.

Ref. DCR 85-120.

85-7435 02-22-86 Flush / hydro of newly installed ATTS tubing loop B.

Ref. DCR 81-138 l

i

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR MARCH 1986 NUMBER DATE COMPLETED DESCRIPTION 85-7674 02-26-86 Remove pipe clamp and shorten eye rod length on Ell-RHRH-327.

Ref.85-120.

85-7675 03-01-86 Loosened supports on either end of 3/4" sampling line of the Reactor Recirc system and removed U bolts in the middle supports of vertical run for IHSI work to be performed on RWCU.

Ref. DCR 85-120.

85-7862 03-14-86 Disconnect snubber B31-SS-B14 from recirc pipe clamp and slide the camp clear of weld for IHSI.

After completion of weld work reinstall clamp and snubber.

Ref. DCR 85-120.

4 85-7863 03-06-86 Remove handrail to provide access for weld overlay equipment.

Reinstall upon completion.

i Ref. DCR 85-120 85-7960 03-13-86 Remove pipe support of equipment drainage piping due to interference with overlay welding.

Ref. DCR 85-120, 85-8004 03-11-86 Remove 3/4" pipe guide which interferes with weld overlay and reinstall when through.

Ref. DCR 85-120 f

l-

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR MARCH 1986 NUMBER DATE COMPLETED DESCRIPTION 86-003 03-01-86 Remove insulation from main steam line "D" to allow clearance for weld overlay.

Ref. DCR 85-120 1

86-0155 03-18-86 Change out breaker 1R22-S016 frame 1B & 3M with refurbished breaker equipped with modified trip elements.

Ref. DCR 85-221.

86-0320 02-22-86 Perform flush / hydro on E41 system.

Ref. DCR 81-138.

86-0321 03-14-86.

Perform flush / hydro of newly installed ATTS tubing for E51 system.

Ref. DCR 81-138 86-0325 03-17-86 Perform flush / hydro of newly installed ATTS instrument tubing.

Ref. DCR 81-138 86-0571 03-08-86 Correct the wiring on the RSCS j

SV DC power supply 1C11A-P59 Ref. DCR 84-321.

86-0605 03-14-86 Restore pipe clamp and snubber RWCU-S-17.

Ref. DCR 85-120 86-0606 03-06-86 Reinstall insulation on recirc system sampling line.

Ref. DCR 85-120.

4 t

I 1

l

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR MARCH 1986 NUMBER DATE COMPLETED DESCRIPTION 86-0607 03-06-86 Restore pipe clamp and snubber B31-SS-A14 Ref. DCR 85-120 86-0766 03-11-86 Reinstall structural steel tube strut which was removed by MWO 1-85-7274 Ref. DCR 85-120 86-0923 03-03-86 Change out 1R23-S004 breaker 48 with modified micro versa trip device.

Ref. DCR 85-219.

86-1227 03-14-86 Disconnect temporary temp.

recorder from 1P41-C0018.

Ref. DCR 85-106.

86-1375 02-18-86 Readjust the long time pickup to 80% on 1R22-S016, frame 28, 2M, 4M.

Ref. DCR 85-221.

86-1376 02-21-86 Correct the long time pickup for each breaker at 1R22-S016, frame 18 and 3M.

Ref. DCR 85-221.

86-1623 03-01-86 Retagged cable to it's original number and reterminated cable H11-P612-ES0-C068.

Ref. DCR 81-196.

86-1894 03-13-86 Determinate wires and remove HGA relay in 4160 volt SWGR bus lE frame 6 per WPS 86-66-E001.

Ref. DCR 86-66.

OPERATING DATA REPORT DOCKET NO.

50-321 DATE 04-10-86 COMPLETED BY: Gary Koerber TELEPHONE (912) 367-7851 x 2882 OPERATING STATUS

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

2. Reporting Period:

03-86

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

7. Maximum Dependable Capacity (Net MWe):

768.0

8. If changes occur in capacity ratings 1

(Items Number 3 through 7) since last report, give reasons:

N/A

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

No Restrictions i

10. Reasons for restrictions, if any:

N/A This Month Yrsto:Date Cumulative

11. Hours In Reporting Period 744 2160 89831

12. Number of Hours Reactor was Critical 0

0 62126.2

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 0

0 58561.1 I

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

124631490

17. Gross Electrical Energy Generated (MWH) 0 0

40242130

18. Net Electrical Energy Generated (MWH) 0 0

38203544*

19. Unit Service Factor 0

0 65.2

20. Unit Availability Factor 0

0 65.2

21. Unit Capacity Factor (Using MDC Net) 0 0

55.4

22. Unit Capacity Factor (Using DER Net) 0 0

54.7

23. Unit Forced Outage Rate 0

0 17.5 24 Shutdowns scheduled over next 6 months (Type, Date, and Duration of Each):

Refueling Outage began November 27, 1985 17 weeks I

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

April 21, 1986

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

N/A NOTE:

The cummulative Net Electrical Generation includes station service used while shutdown.

w-

... - -.. - -. ~..

^

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-321 j

DATE:

04-10 COMPLETED.BY: Gary Koerber TELEPHONE (912) 367-7851 x 2882 MONTH 03-86 i

l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER. LEVEL l

(MWe-Net)

(MWeiNet) l

-1 0

17 0

l 2

0 18 0

3 0

19 0

i 4

0 20 0

5 0

21 0

r 6

0 22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

i 12 0

28 0

13 0

29 0

14 0

30 0

115 0

31 0

16 0

t NOTE:

Net power level-does not include the station service used while shutdown.

9 t

I

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-321 UNIT NAME HATCH ONE COMPLETED BY Gary M. Koerber TELEPHONE (912) 367-7851 (2882)

DATE_ APRIL 10,1986 REPORT MONTH MARCH I

I I

l l

1R I l

l S l

l l

1 I

I I

l E l l

l Y l

l i

l l

IT I

!A l METHOD OF l LICENSEE l SC I l

l l

l 1Y I IS I SHUTTING I

EVENT l T0 l l

CAUSE & CORRECTIVE I

I l

l P 1 DURATION IO I DOWN I

REPORT IED l COMPONENT l ACTION TO I

I NO.

I DATE IEl (HOURS) l N I REACTOR I

NUMBER l MEI CODE I

PREVENT RECURRENCE I

I I

I l

1 86-003 l 860301 l S I 744 iC 4

l N/A l RC I

FUELXX l Refueling Outage l

l I

l l

l l Continues l

I I

I i

1 I

I I

I l

l I

i l

I I

I l

l I

I I

l l

1 1

I I

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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)

]

NARRATIVE REPORT UNIT TWO March 1st 0000 Unit at 85% power with no major equipment problems.

Holding power per management decision to help relieve offgas activity in reactor and turbine buildings.

March 21st 2107 Reducing power for weekly turbine testing.

March 22nd 0600 Back at 85% power.

March 28th 0300 Reducing power for rod pattern adjustment.

March 30th 1000 Back at 85% power.

1615 Reducing power for weekly turbine testing and CRD testing.

2400 Back at 85% power.

March 31st 2400 Unit at 85% power with no major equipment problems.

HATCH 2 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR MARCH 1986 NUMBER DATE COMPLETED DESCRIPTION 85-1630 02-27-86 Paint pipe and hangers on T43 system.

85-1632 02-27-86 Paint pipe and hangers on T43 i

system.

t 85-4882 03-22-86 Install limit switch and terminal block on Unit 2 overhead crane.

Ref. DCR 82-230 I

f.

I o

i i

I

.I i

4

}

i 1

i i

1 1

I f-f

OPERATING DATA REPORT DOCKET NO.

50:366 DATE 04-10486 COMPLETED BY: Gary Koerber TELEPHONE (912) 367-7851 x 2882 OPERATING STATUS 1.

Unit Name: E.

I. Hatch Nuclear Plant Unit 2 2

Reporting Period:

03-86 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 Dependable 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 Yreto-Date Cumulative

11. Hours In Reporting Period 744 2160 57457

12. Number of Hours Reactor was Critical 744,0 2091.2 39662.8

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 744.0 2044.8 37913.0

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1520640 4220656 82403862

17. Gross Electrical Energy Generated (MWH) 496760 1389660 27171160

18. Net Electrical Energy Generated (MWH) 472793 1325182 25863836

19. Unit Service Factor 100.0 94.7 66.0

20. Unit Availability Factor 100.0 94.7 66.0

21. Unit Capacity Factor (Using MDC Net) 81.8 79.0 57.9

22. Unit Capacity Factor (Using DER Net) 81.1 78.3 57.4

23. Unit Forced Outage Rate 0

5.3 10.7

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

Refueling Outage beginning September 06, 1986 8 weeks 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

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50 366 DATE:

04 10a86 COMPLETED BY: Gary Koerber TELEPHONE (912) 367 7851 x 2882 i

i MONTH 03-86 t;

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i

(MWe-Net)

(MWe Net) l 1

656 17 643 2

653 18 638 3

646 19 635 4

650 20 641 5

653 21 639 j

6 650 22 636 7

650 23 643 8

652 24 639 9

642 25 639 1

10 634 26 638 l

11 635 27 639 12 634 28 524 t

13 633' 29 583 14 638 30 616 15 643 31 635 16 642 I

i m,,

--m.-

~,.

e

.w-

UNIT SHUTD0';;NS AND POWER REDUCTIONS DOCKET NO.

50-366 UNIT NAME HATCH TWO COMPLETED BY Gary M. Koerber TELEPHONE (912) 367-7851 (2882)

DATE APRIL 10,_1986 REPORT MONTH MARCH I

I I

l l

1R I I

l S l

l l

l 1

1 I

IE l l

l Y l

l l

1 l

l T l l A l METHOD OF l LICENSEE ISC l l

l l

l l Y l l S l SHUTTING l

EVENT l T0 l I

CAUSE & CORRECTIVE l

l l

l P l DURATION l 0 l DOWN l

REPORT IED l COMPONENT l ACTION TO l

l NO.

l DATE l E I (HOURS) l N l REACTOR I

NUMBER IME l CODE l

PREVENT RECURRENCE I

l l

l 1

I I

l l

l 86-013 1 860301 l S l 651.0 l H I 5

l N/A l ZZ l

ZZZZZZ l Management decision l

l l

l l to reduce power to l

I l

l l

l l 85%.

High offgas l

l l

l l activity in Rx. and l

l l

l l Turbine building l

l l

l l caused by leakinn fuell l

l l

l was slowing down Unit l I

l l

l One Outage Work.

I I

i 1 86-014 1 860328 l S I 55.0 lB l 5

l N/A I RC I

CONROD IRod pattern Adjustment.1 1

I I

I l

i I

l 86-015 l 860330 l S I 38.0 lH I 5

l N/A l ZZ l

ZZZZZZ l See 86-013 l

l l

I I

I 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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)

1 '. z Georgi 2 P;wsr Comptny Post Offica Box 439 Baxley, Georgia 31513 Telephone 912 367-7781 f

912 537-9444 m

Edwin 1. Hatch Nuclear Plant April 10, 1986 LR-MGR-029-0386 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.

W H. C. Nix General Manager g

GMK/kel xc:

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

e 9

i\\\\

ML20206D944

Text

Dear Sir:

Navigation menu

Search