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Text

Monthly Operating Repts for Apr 1986
	ML20207C722
Person / Time
Site:	Hatch
Issue date:	04/30/1986
From:	Gucwa L, Koerber G; GEORGIA POWER CO.
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	0537C, 537C, SL-741, NUDOCS 8607210424
	Download: ML20207C722 (23)
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NARRATIVE REPORT i

UNIT ONE April 1st 0000 Unit in cold shutdown for refueling outage.

t April 30th 2400 Unit in cold shutdown for Refueling Outage.

Expected i

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Startup May 02, 1986.

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f HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 NUMBER DATE COMPLETED DESCRIPTION 82-0331 04-05-86 Install. piping / plumbing for TSC in the Unit 2 service building.

Ref. DCR 80-157.

82-7268 04-08-86 Install supports for breakglass stations and conduit supports for i

Drywell personnel airlock.

Ref. DCR 78-359.

82-8486 04-02-86 Install panels X75-P200A&B.

Ref. DCR 80-157.

83-0103 04-10-86 Modify TSC HVAC ductwork.

Ref. DCR 80-157.

83-1348 04-04-85 Fabricate and install packing leakage piping for B21-F016.

Ref. DCR 83-035.

83-6022 04-05-86 Install misc. mechanical portions required by the Emergency Response Facilities.

Ref. DCR 80-157.

83-6023 04-05-86 Install civil portion of the Emergency Response Facility.

Ref. DCR 80-157.

84-0219 04-21-86 Install Control Room Access Barriers and gate sections.

Ref. DCR 83-230.

84-3052 04-21-86 Fabricate and install all the conduit and conduit supports required to complete the ATTS modifications.

Ref. DCR 81-138.

84-3756 04-23-86 Fabricate and install all tubing supports and local instruments per WPS 81-138-J001,2.

Ref. DCR 81-138.

84-4084 04-23-86 Fabricate and install all tubing supports and local instruments per WPS 81-138-J004,5.

Ref. DCR 81-138.

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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 84-4226 04-12-86 Install drain line and supports for racks H21-P036 and H21-P415A&B.

Ref. DCR 81-138, 84-4840 04-10-86 Install partial fire protection riser system.

Ref. DCR 83-219.

84-4884 04-21-86 Fabricate and install tubing / piping and their supports per WPS 81-138-J013,14.

Ref. DCR 81-138.

84-5153 04-07-86 Redline of power supply cables to Foxboro analog isolator panels.

Ref. DCR 80-157.

84-5821 04-21-86 Install ATTS panel entries associated with WPS 81-138-R016.

Ref. DCR 81-138.

84-6052 04-21-86 Fabricate and install all conduit and conduit supports associated with WPS 81-138-R018, T015.

Ref. DCR 81-138.

84-6178 04-25-86 Install class IF cables.from main control room panels to'ERF/SPDS panels X75-P200A,B.

Ref. DCR 80-157.

85-0067 04-05-86 Install chains and break away locks on new fire protection riser isolation valves on T43 system.

Ref. DCR 83-219.

85-0665 04-05-86 Install decontamination ports for hydrolasing on Reactor building floor drains.

Ref. DCR 85-196.

85-1544 04-07-86 Replace motor on lEll-F004A.

Ref. DCR 86-028.

85-3755 04-11-86 Install sprinkler system T43185WO3.

Ref. DCR 83-246.

85-4932 04-17-86 Replace scram discharge volume switches 1Cll-N013A-F.

Ref. DCR 86-105.

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-4972 04-11-86 Remove RWCU piping insulation to provide access for weld overlay.

Reinstall when complete.

Ref. DCR 85-120.

85-4973 04-10-86 Remove Recirc piping insulation to provide access for weld overlay.

Reinstall when complete.

Ref. DCR 85-120.

85-4974 04-07-86 Remove RHR piping insulation to provide access for weld overlay.

Replace when through.

Ref. DCR 85-120.

85-5174 04-04-86 Replace unqualified MOV motors and actuators on B31 to meet the requirements of I.E.B.

79-OlB.

Ref. DCR 81-093.

85-5176 03-24-86 Install Time Delay Relay E41-K63.

Ref. DCR 83-214.

85-5443 04-15-86 Implement a portion of DCR 81-138 Rev. 1 (ATTS) per WPS 81-138-T032 and WPS 81-138-T038.

Ref. DCR 81-138.

85-5585 04-09-86 Fabricate and install tubing supports and fittings for A70.

Ref. DCR 81-138.

85-5610 04-09-86 Complete the termination of 3 cables for X75 Emergency Response Facilities.

Ref. DCR 80-157.

85-5622 04-15-86 Complete cable termination and redlining originally issued under 80-157-EC04, 07, 11 per work package 80-157-EM74A.

Ref. DCR 80-157, 85-5768 04-14-86 Replace motor on B21-F019 per I.E.B.79-01B.

Ref. DCR 81-113.

85-5910 04-09-86 Calibrate new ATTS RTD trip units.

Ref. DCR 81-138.

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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-5923 04-26-86 Calibrate transmitters for new ATTS system.

Ref. DCR 81-138.

85-5955 04-09-86 Calibrate new ATTS trip units per 57CP-CAL-102-lS.

Ref. DCR 81-138.

85-5993 04-09-86 Replace Barton transmitters with Rosemount transmitters on 1C71-N050A-D and 1 Ell-N094A-D.

Ref. DCR 80-138.

85-6947 04-23-86 Implement A"Ts changes on HPCI Loop "B" T030-and RCIC Loop T025.

Ref. DCR 81-138.

85-6988 03-26-86 Implement ATTS changes on NSSS Loop "A" T034 per 42SP-DCI-006-lS.

Ref. DCR 81-138.

85-6990 04-22-86 Mount alarm relay for RWCU in panel H21-P602.

Ref. DCR 81-124.

85-6993 04-08-86 Implement ATTS changes per 42SP-DCI-005-1S.

(SLD Loop T033)

Ref. DCR 81-138.

85-7052 04-23-86 Implemented a portion of DCR 81-138 Rev. 1 as per WPS 81-138-T040.

Ref. DCR 81-138.

85-7095 03-11-86 Functional test new C71 ATTS instruments.

Ref. DCR 81-138.

85-7096 04-23-86 Functional test new E21 ATTS equipment.

Ref. DCR 81-138.

85-7097 04-09-86 Functional test new E51 ATTS Instruments.

Ref. DCR 81-138.

85-7100 04-09-86 Functional test new E41 ATTS Instruments.

Ref. DCR 81-138.

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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-7101 04-24-86 Functional test new RHR ATTS instruments.

Ref. DCR 81-138.

85-7123 04-02-86 Modified E11-F008 to meet Appendix "R" 10CFR50 "Hi-Low" requirements.

Ref. DCR 85-119.

85-7219 04-09-86 Implement ATTS changes on ECCS Loop "F" T036 per 42SP-DCI-008-1S, Ref. DCR 81-138.

85-7220 04-09-86 Implement ATTS changes on Ind Loop T031 per 42SP-DCI-004-lS.

Ref. DCR 81-138.

85-7344 04-22-86 Replace motors and actuators on valves lE21-F004A,B and lE21-F005A,B.

Ref. DCR 81-093.

85-7401 04-05-86 Remove shim plates on recirc piping to provide access for weld overlay.

Reinstall new shim plates when complete.

Ref. DCR 85-120.

85-7412 04-04-86 Removed snubber from Recirc piping clamp and reinstall after weld overlay was complete.

Ref. DCR 85-120.

85-7413 03-18-86 Remove pipe clamp from RWCU piping to provide access for weld overlay.

Ref. DCR 85-120.

85-7957 04-10-86 Remove drywell pneumatic system piping which interferes with the installation of weld overlay equipment.

Reinstall upon completion of weld overlay.

Ref. DCR 85-120.

85-7958 04-05-86 Remove shim plates on recirc piping to provide access for weld overlay.

Reinstall new shim plates when complete.

Ref. DCR 85-120.

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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-7959 04-05-86 Remove beam _ angle and grating on RWCU piping which interferes with weld overlay.

Ref. DCR 85-120.

85-8007 04-07-86 Remove insulation below valve G31-F004 to provide access for weld overlay.

Ref. DCR 85-120.

86-0212 04-10-86 Open Drywell Penetration X43 to route welding cables.

Ref. DCR 85-120.

86-0322 04-22-86 Perform Flush / Hydro on E51 system.

Ref. DCR 81-138.

86-0324 04-04-86 Perform Flush / Hydro on E41 system.

Ref. DCR 81-138.

86-0471 04-02-86 Change out breaker R22-S017 frame 1M with refurbished breaker with modified trip elements.

Ref. OCR 85-221.

86-0602 04-04-86 Install decontamination ports for CRD 8" Scram discharge Heater for Hydrolase work.

Ref. DCR 85-197.

86-0668 04-15-86 Remove main incoming line supply breakers (lR24-S018A,B) and install safety switches.

Ref. DCR 84-204 86-0761 04-24-86 Reworked conduit and cable per WPS 81-138-E020 and ORl-86a8.

Ref. DCR 81-138.

86-0764 04-09-86 Reinstall pipe support for P70 piping which was removed to provide access for weld overlay.

Ref. DCR 85-120.

86-0832 04-09-86 Replace Jet Pump beam #16 (lBil-D233).

Ref. DCR 86-020.

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 86-0833 03-26-86 Determinate and remove 1H11-P613-E59-Cll6 from panel H21-P001.

Inspect for damage from flood.

Obtain new cable pull and terminate cable.

Ref. DCR 81-138.

86-0837 04-07-86 Readjust the set points on ATTS trip units B21-N685A&B.

Ref. DCR 85-092.

86-0838 04-09-86 Readjust the set points of ATTS i

trip units B21-N682A-D.

Ref. DCR 85-092.

86-0839 04-09-86 Readjust the set points of ATTS trip units B21-N693A-D.

Ref. DCR 85-092.

86-0840 04-09-86 Readjust the set point of ATTs trip units B21-N680A-D Ref. DCR 85-092.

86-0841 04-09-86 Readjust the set points of ATTS trip units B21-N691A-D.

Ref. DCR 85-092.

86-0842 04-09-86 Readjust the set points of ATTS trip units B21-N681A-D.

Ref. DCR 85-092.

86-0843 04-09-86 Readjust the set points of ATTS trip units E41-N660A,B.

Ref. DCR 85-092.

86-0844 04-09-86 Readjust the set points of ATTS trip units on B21-N692A-D.

Ref. DCR 85-092.

86-0845 04-09-86 Readjust the set points of ATTS trip units B21-N690E,F.

Ref. DCR 85-092.

86-0846 04-09-86 Readjust the set points of ATTS trip units B21-N695A,B.

Ref. DCR 85-092.

86-0849 04-09-86 Readjust the set points of ATTS trip units B21-N641B,C.

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Ref. DCR 85-092.

HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 86-0850 04-09-86 Readjust the set points of ATTS trip units E41-N657A,B.

Ref. DCR 85-092.

86-0851 04-09-86 Readjust the set points of ATTS trip units B21-N690A-D.

Ref. DCR 85-092.

86-0923 19-86 Change out R23-S004 Breaker 4B with refurbished breaker equipped with modified micro versa trip device.

Ref. DCR 85-219.

86-0935 04-07-86 Remove MSIV 3/4" leakoff line piping.

Weld pipe caps onto remaining IT45 drain piping.

Ref. DCR 85-161.

86-0988 04-07-86 Replace Barton transmitter with Rosemount transmitter on Ell-N055C.

Ref. DCR'81-138.

86-1006 04-05-86 Remove pipe support and cold spring drain line for.B31-F031A to provide access for weld overlay.

Reinstall after completion.

Ref. DCR 85-120.

86-1019 04-05-86 Remove temporary startup instrumentation bracket on B31 to provide access for weld overlay.

Reinstall when complete.

Ref. DCR 85-120.

86-1056 03-26-86 Flush newly installed ATTS Tubing for E21 system.

Ref. DCR 81-138.

86-1084 04-10-86 Remove damaged cables on E41/E51 and pull new cables.

Ref. DCR 81-174.

86-1085 04-05-86 Removed temporary service water and Demin water hoses and connections'and restore the systems to their normal configurations.

Ref. DCR 85-120.

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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 86-1183 0,4-07-86 Restore pipe. clamp and spring can 1 Ell-RHRH-327 which was removed to provide access for weld overlay.

4 Ref. DCR 85-120.

86-1376 04-22-86 Correct the long term pick-up for R22-S016 Fr. 1B & 3M.

Ref. DCR 85-221.

86-1541 04-11-86 Replace lE21-F001A motor.

Ref. DCR 86-028.

86-1542 04-01-86 Replace motor on E21-F031A.

Ref. DCR 86-028.

86-1610 04-03-86 Rowire and relabel indicating lights ACG and ACJ on R26-M077.

.I Ref. DCR 84-204.

86-1623 04-21-86 Reterminate cable 1

Hil-P612-ESO-C068to enable lEll-N007B.

Ref. DCR 81-196.

86-1880 04-07-86 Close Drywell penetration X43.

Ref. DCR 85-120.

86-1967 04-07-86 Disconnect cables subjected to flooding in the southeast diagonal, northeast diagonal, and i

HPCI room.

Ref. DCR 86-058.

86-2042 04-16-86 Pull back cables, rework conduit, install new terminal boxes, install new conduit and supports.

pull back new cable from new terminal boxes to instruments on B31, Ell, ET.1, E41, and P41.

Ref. DCR Bo-058.

86-2281 04-10-86 Termination of circuits for E21-N001A.

Ref. DCR 86-058.

86-2290 04-09-86 Termination of circuits for Ell-R001A.

Ref. DCR 86-058.

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i HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 i

86-2471 04-22-86 Perform controlled grinding on FW nozzle inspection door F51-N4B to ensure door will close without i

striking FW pipe.

Ref. DCR 86-121.

86-2815 04-09-86 Perform functional test on ATTS per Special Instruction 57SP-0320861.

Ref. DCR 81-138.

86-2835 04-17-86 Recalibrate P70-KR10,12,20,22 and replace the annunciator cards and cover gasket for pressure switch P70-N016.

Ref. DCR 81-111.

86-2840 04-09-86 Perform initial leak tests and pre-service calibration checks on 1P33-P001A&B.

Ref. DCR 81-132.

86-2898 04-08-86 Replace 2nd Stage MSR steam flow pressure transmitter (N38-N772D) with a Rosemount Diferential transmitter.

DCR 86-124.

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OPERATING DATA REPORT DOCKET NO.

50-321 DATE 05-10-86 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:

04-86 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 (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 719 2879 90550

12. Number of Hours Reactor was Critical 0.0 0.0 62126.2

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 0.0 0.0 58561.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0

16. Gross Thermal Energy Generated (MWH)

C 0

124631490

17. Gross Electrical Energy Generated (MWH) 0 0

40242130

18. Net Electrical Energy Generated (MWH) 0 0

38197524*

19. Unit Service Factor (%)

0.0 0.0 64.7

20. Unit Availability Factor (%)

0.0 0.0 64.7

21. Unit Capacity Factor (% Using MDC Net) 0.0 0.0 54.9

22. Unit Capacity Factor (% Using DER Net) 0.0 0.0 54.3

23. Unit Forced Outage Rate 0.0 0.0 17.5

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 startup: May 11, 1986

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

N/A

NOTE:

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

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

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AVERAGE DAILY UNIT POWER LEVEL

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I DOCKET NO.

50-321 1

DATE:

05-10-86 COMPLETED BY: Gary Koerber j

TELEPHONE (912).367-7851 x 2882 MONTH 04-86

~

I DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

I f

1 1

0 17 0

1 i

2 0

18 0

i 3

0 19 0

I 4

0 20 0

5 0

21 0

4 i

6 0

22 0

i 7

0 23 0

t 8

0 24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

l 13 0

29 0

14 0

30 0

15 0

31 0

l 16 0

1 I

i k

i i

UNIT SHUTDOWNS AND POWER REDUCTIONS l

DOCKET NO.

50-321 UNIT NAME HATCH ONE COMPLETED BY Gary M.

Koerber TELEPHONE (912) 367-7851 (2882)

DATE MAY 10,1986 REPORT MONTH APRIL i

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IR I I

IS I

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IE I I

IY I

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IT l l A I METHOD OF I LICENSEE ISC l I

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I l Y I IS I SHUTTING I

EVENT ITO I l

CAUSE & CORRECTIVE I

I l P l DURATION IO I DCWN I

REPORT IED l COMPONENT I ACTION TO I

NO.

I DATE IE l (HOURS) i N l REACTOR I

NUMBER IME I CODE I

PREVENT RECURRENCE I

I I

i i

i l

I 86-004 l 860401 1S I 719 iC I 4

l N/A I RC i

FUELXX l Refueling Outage I

I I

l l

l 1

I I Continues I

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I i

I I

i l

l I

I I

I i

I I

l 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)

l NARRATIVE REPORT UNIT TWO April 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.

April 12th 0227 4160 Volt bus 2A, Recirc pump 2A, and Circ water pump 2A all tripped.

Recovery in progress.

1400 Back at 85% power.

l 2330 Reducing power for weekly turbine j

testing.

April 13th 0300 Back at 85% power.

April 20th 0101 Rx Scram Turbine trip on erroneous MSR A high level.

0510 Scram Recovery in progress.

April 21st 1537 Reducing to 55% rated power to j

remove RFPT 2B from service.

April 22nd 0520 RFPT 2B back in service.

1900 Back at 85% power.

April 24th 2334 Rx Scram.

Excessive condensation in the Generator Exciter caused a Generator Field Ground and subsequent turbine trip.

Source of condensation was an approximately 18" rupture in the 6th~ stage "A" extraction line.

April 28th 1336 Scram Recovery in progress.

April 29th 1900 Back at 85% power.

April 30th 2400 Unit at 85% power with no major equipment problems.

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HATCH 2 SAFETY-RELATED MAINTENANCE -WORK ORDERS

]

TO BE REPORTED FOR APRIL 1986 i

NUMBER.

DATE COMPLETED DESCRIPTION 83-0429 04-10-86 Install conduit l

2MB0441, 2MB1356,7,8,9 and supports.

Ref. DCR 80-157.

[

I 83-1348 04-12-86 Install panels.

I 2X75-P200A&B.

Ref.'DCR 80-157.

]

83-1432 04-12-86 Pour concrete pads for 2Rll-S100, 2R25-S133, and 2R44-S005.

I Ref. DCR 80-157.

83-2238 04-12-86 Install panels 2R25-S133 and-R25-S0108 in vital AC room Units 1 & 2.

Ref. DCR 80-157.

I 85-1265 04-11-86 Install Sprinkler system 2T43130WO6.

4 Ref. DCR 83-248.

85-1635 04-10-86 Install fire protection sprinkler j

system 2T43087WO8.

Ref. DCR 83-250.

85-1636 04-09-86 Install fire i.

protection sprinkler i

system 2T43087WOl.

j '

Ref. DCR 83-250.

5

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85-2893 04-08-86 Replace CS pump bowl assembly with a SS bowl assembly-on 1

2P41-C001D.

Ref. DCR-84-060.

I 85-3172 04-14-86 Re-roof Unit 2 turbine and reactor buildings.

Ref. DCR 85-067.

1 85-3173 04-14-86 Re-roof Unit 2 Turbine j

building and Reactor building connectors.

l Ref. DCR 85-067.

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HATCH 2 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 NUMBER DATE COMPLETED DESCRIPTION 85-3174 04-14-86 Re-roof Unit 2 Radwaste building and l

Hot Machine Shop.

Ref. DCR 85-067.

85-6864 03-26-86 Replace flow transmitter X75-FT-N009 and existing flow meter X75-FE-N002 with a Veltron 7000/3 CEJNV flow transmitter and three air monitor probes.

Ref. DCR 80-157.

86-0486 04-23-86 Implement a' portion of DCR 81-139 Rev. 1 per WPS 81-139-T080.

Ref. DCR 81-139.

3

OPERATING DATA REPORT DOCKET NO.

50-366 DATE 05-10-86 COMPLETED BY: Gary Koerber TELEPHONE (912) 367-7851 x 2882 i

OPERATING STATUS

1. Unit Name: E.

I.

Hatch Nuclear Plant Unit 2 2.

Reporting Period:

04-86 i

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 i

(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 t

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 719 2879 58176

12. Number of Hours Reactor was Critical 634.7 2725.9 40297.4

13. Reactor Reserve Shutdown Hours O

O O

14. Hours Generator On-Line 605.9 2650.7 38518.8

15. Unit Reserve Shutdown Hours 0.0 0.0

0. O

16. Gross Thermal Energy Generated (MWH) 1197696 5418352 83601558

17. Gross Electrical Energy Generated (MWH) 389100 1778760 27560260 i

18. Net Electrical Energy Generated (MWH) 369101 1694283 26232937 i

19. Unit Service Factor (%)-

84.3 92.1 66.2

20. Unit Availability Factor (%)

84.3 92.1 66.2-

21. Unit Capacity Factor (% Using MDC Net) 66.1 75.7 58.0

22. Unit Capacity Factor (% Using DER Net) 65.5 75.1 57.5

23. Unit Forced Outage Rate 15.7 7.9 10.8 1

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

Refueling Outage, September 06, 1986 8 weeks j

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 4

i 4

~.

i AVERAGE DAILY UNIT POWER LEVEL e

DOCKET NO.

50-366 DATE:

05-10-86 COMPLETED BY: Gary Koerber TELEPHONE (912) 367-7851 x 2882 i

MONTH 04-86 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) l 1

645 17 645 2

645 18 646 i

3 642 19 641 l

4 638 20 7

l 5

636 21 241 6

641 22 541 7

636 23 632 8

636 24 631 9

644 25 0

10 646 26 0

l 11 647 27 0

12 547 28 102 13 634 29 538 14 640 30 635 15 640 16 645 NOTE:

Power level does not include station service used while shutdown.

.m__

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-366 UNIT NAME HATCH TWO COMPLETED BY Gary M.

Koerber TELEPHONE (912) 367-7851 (2882)

DATE MAY 10, 1986 REPORT MONTH APRIL j

I i

i l

I I

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l 1R l 1

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ZZZZZZ l Management decision l~,

I l

l l

1 I

I l

1 l to reduce power to l

l l

l l 85%.

High offgas l

l l

l l activity in Rx. and l

I l

l l

l l Turbine building l

l l

1 l

l l

l l caused by leaking fuell l

l l

l was slowing down Unit l l

1 1

I I

I l

I One Outage Work.

I I

I I 86-017 I 860412 lF i 11.55 lA l 5

l N/A l HF I

ELECON I4160 Volt bus 2A, l

l 1

I l

l l

l lrecirc pump 2A, and l'

l l

l l Circ Water pump 2A l

1 l

l l

l ltripped.

l 1

I I

I i!

I I

I l

l l

1 I

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)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-366 UNIT NAME HATCH TWO

~

COMPLETED BY Gary M.

Koerber TELEPHONE (912) 367-7851 (2882)

DhTE MAY 10, 1986 REPORT MONTH APRIL l

I I

I l

l l

l l R l l

l S l

l l

l 1

IE l l

lY l

l l

l T l l A l METHOD OF l LICENSEE l SC l l

l l

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EVENT l TO I I

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REPORT IED i COMPONENT I ACTION TO I

NO.

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

NUMBER IME I CODE I

PREVENT RECURRENCE I

i 1

1 I

I I

I l

1 I

i l

i I

I I

I l

l 86-018 l 860413 lS l 166.02 lH I 5

l N/A l ZZ l

ZZZZZZ l Management decision l

1 l

l l

l l to reduce power to l

l l

l 1

l l

l 85%.

High offgas l

l l

l activity in Rx. and l

l l

l l Turbine building l

l l

l l caused by leaking fuell l

l l

l was slowing down Unit l l

1 I

I I

I One Outage work.

l I

I I

I 86-019 I 860420 IF l 28.15 l A l 3

1 2-86-9 l IA l INSTRU l Rx Scram on erroneous !

l l

1 I

l l MSR A high level.

I I

I l

l 86-020 l 860421 l S I 10.45 i B l 5

l 2-86-9 l IA l INSTRU l Scram Recovery I'

I I

I 1 86-021 l 860421 l F l 29.38 lA l 5

l N/A l CH l TURBIN I RFPT 2B tripped l

l l

l 1

1 I

I I

I l

l 1

I l

l 1

1 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 .

l 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)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-366 UNIT NAME HATCH TWO COMPLETED BY Gary M.

Koerber TELEPHONE (912) 367-7851 (2882)

DATE MAY 10, 1986 REPORT MONTH APRIL I

I i

l I

I I

IR I I

IS I

l l

1 I

IE I l

1Y l

l l

l i

l T l l A l METHOD OF l LICENSEE l SC i i

i l

l l Y l l S l SHUTTING l

EVENT l TO I l

CAUSE & CORRECTIVE l

l l

l P I DURATION l O I DOWN l

REPORT l ED l COMPONENT l ACTION TO l

l NO.

I DATE IE i (HOURS) lN I REACTOR l

NUMBER IME l CODE PREVENT RECURRENCE I

I i

1 l

1 I

I I

l l

l 1

I l

l l

l l 86-022 l 860424 i F l 85.03 l A l 3

l 2-86-10 l HA I

GENERA I Excessive condensationl l

l l

l in the Generator i

i l

l I

I l

l l

l l Excitor caused a

'l i

l I

l l

l l Generator Field Groundl l

l l

l l and subsequent turbinel l

l l

l 1

l l trip.

Source of l

1 l

l l

l condensation was an l

l 1

l l

l approximately 18" l

l l

l rupture in the 6th l

l l

l l stage "A" extraction l

l 1

1 I

l l

1 I

I line.

l l

l 1

1 I

I I

l 1

l l

l 86-023 l

860428 l S l 29.40 lB l 5

l 2-86-10 l HA l

GENERA l Scram Recovery.

1 l

I I

I l

l 86-024 I

860429 l S l 2.9.00 l H I 5

l N/A l ZZ l

ZZZZZZ l See 86-016.

l l

1 1

I I

I l

l l

F: Forced Reason:

Method:

Events reported involve l

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

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

)

y Georgia Fbwer Company j

333 Piedmont Avenue Attarsta, Georgia 30308 Telephone 404 526-6526 l

Maihng Address:

Post Office Box 4545 Atlanta, Georgia 30302 Georgia Power L. T. Gucws l' " " "" " *I' W #" "

Manager Nuclear Safety and Licenstrig May 14,1986 Nuclear Operations NRG Monthly Operating Report File: X7GJ10-H000 Log: SL-741 Director Office of Management and Program Analysis U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Sir:

Enclosed is the NRC Monthly Operating Report for Hatch Unit 1, Docket Number 50-321, and for Hatch Unit 2, Docket Number 50-366.

This report is submitted pursuant to Technical Specifications Section 6.9.1.10 Sincerely, 1

b L. T. Gucwa y

EBS/lc Enclosure c: Mr. J. P. O'Reilly Mr. J. T. Beckham, Jr.

Mr. H. C. Nix, Jr.

NRC-Region II i

GO-NORMS 1

YN

b T

0537C I[

ML20207C722: Difference between revisions

Latest revision as of 23:16, 6 December 2024

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Dear Sir:

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-{{#Wiki_filter:- _             . _ _ _  ... _ _ _ .                     .    ,                           -. . _.._. _ . .-                         _ _._ . .-_ _       _ .         .     ..
+{{#Wiki_filter:- _
-j     se l         .                                                                     NARRATIVE REPORT                                                                                                                          '
+j se l
-i                                                                                     UNIT ONE April 1st                                               0000                  Unit in cold shutdown for                                                                                                     ,
+NARRATIVE REPORT i
-refueling outage.
+UNIT ONE April 1st 0000 Unit in cold shutdown for refueling outage.
-t April 30th                                               2400                 Unit in cold shutdown for i                                                                                          Refueling Outage. Expected Startup May 02, 1986.
+t April 30th 2400 Unit in cold shutdown for Refueling Outage.
+Expected i
 ]
+Startup May 02, 1986.
 5
 J i
 I 1
 i i
+L
-!                                                                                               e                                                                                                 L 8607210424 860430 PDR          ADOCK 05000321                                                                                                                 4/                    k PDR                                                                                              }
+e 8607210424 860430 4/
+. k PDR ADOCK 05000321 PDR
+} \\}
 R
-                                                                                                                                                                                        /
+/
-                                                                                                                                                                                            \}
+-y--
-    -y--          e- w..     .-p. $pr---      -e p-r, g     wa-+.*g4--g  ,-=y-r r      .--m,ps--    ..ve -
+e-w..
-                                                                                                           .y.-,---4,   e'-w,w,p,     -.9y.. - - - gpg.3,-wg-y,        +q-9g-yw e w-yg  , prg
+.-p.
-                                                                                                                                                                                              #y   w,,     ye,me.r Ww q--
+$pr---
+-e p-r, g wa-+.*g4--g
+,-=y-r r
+.--m,ps--
+..ve
+.y.-,---4, e'-w,w,p,
+-.9y.. - - -
+gpg.3,-wg-y,
+-9
++q-9g-yw e
+w-yg
+, prg
+#y w,,
+ye,me.r Ww q--
-f HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 NUMBER                     DATE COMPLETED          DESCRIPTION 82-0331                      04-05-86              Install. piping / plumbing for TSC in the Unit 2 service building.
+f HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 NUMBER DATE COMPLETED DESCRIPTION 82-0331 04-05-86 Install. piping / plumbing for TSC in the Unit 2 service building.
-.,                                                              Ref. DCR 80-157.
+Ref. DCR 80-157.
--7268                      04-08-86              Install supports for breakglass stations and conduit supports for i
+-7268 04-08-86 Install supports for breakglass stations and conduit supports for i
 Drywell personnel airlock.
 Ref. DCR 78-359.
--8486                      04-02-86              Install panels X75-P200A&B.
+-8486 04-02-86 Install panels X75-P200A&B.
 Ref. DCR 80-157.
--0103                      04-10-86             Modify TSC HVAC ductwork.
+-0103 04-10-86 Modify TSC HVAC ductwork.
 Ref. DCR 80-157.
--1348                      04-04-85             Fabricate and install packing leakage piping for B21-F016.
+-1348 04-04-85 Fabricate and install packing leakage piping for B21-F016.
 Ref. DCR 83-035.
--6022                      04-05-86              Install misc. mechanical portions required by the Emergency Response Facilities.
+-6022 04-05-86 Install misc. mechanical portions required by the Emergency Response Facilities.
 Ref. DCR 80-157.
--6023                      04-05-86              Install civil portion of the Emergency Response Facility.
+-6023 04-05-86 Install civil portion of the Emergency Response Facility.
 Ref. DCR 80-157.
--0219                      04-21-86              Install Control Room Access Barriers and gate sections.
+-0219 04-21-86 Install Control Room Access Barriers and gate sections.
 Ref. DCR 83-230.
--3052                      04-21-86              Fabricate and install all the conduit and conduit supports required to complete the ATTS modifications.
+-3052 04-21-86 Fabricate and install all the conduit and conduit supports required to complete the ATTS modifications.
 Ref. DCR 81-138.
--3756                      04-23-86              Fabricate and install all tubing
+-3756 04-23-86 Fabricate and install all tubing supports and local instruments per WPS 81-138-J001,2.
- .                                                              supports and local instruments per WPS 81-138-J001,2.
 Ref. DCR 81-138.
--4084                      04-23-86              Fabricate and install all tubing supports and local instruments per WPS 81-138-J004,5.
+-4084 04-23-86 Fabricate and install all tubing supports and local instruments per WPS 81-138-J004,5.
 Ref. DCR 81-138.
-                     , - - - , - -    -        -        ,      eey -. p.-m pr-r -r ,,.-w, y , ,-- u m -- w -- ,-v y - -
+eey -.
+p.-m pr-r
+-r
+,,.-w, y,,--
+u m -- w
+,-v y
-HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 84-4226       04-12-86               Install drain line and supports for racks H21-P036 and H21-P415A&B.
+HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 84-4226 04-12-86 Install drain line and supports for racks H21-P036 and H21-P415A&B.
-Ref. DCR 81-138, 84-4840       04-10-86               Install partial fire protection riser system.
+Ref. DCR 81-138, 84-4840 04-10-86 Install partial fire protection riser system.
 Ref. DCR 83-219.
--4884       04-21-86               Fabricate and install tubing / piping and their supports per WPS 81-138-J013,14.
+-4884 04-21-86 Fabricate and install tubing / piping and their supports per WPS 81-138-J013,14.
 Ref. DCR 81-138.
--5153       04-07-86               Redline of power supply cables to Foxboro analog isolator panels.
+-5153 04-07-86 Redline of power supply cables to Foxboro analog isolator panels.
 Ref. DCR 80-157.
--5821       04-21-86               Install ATTS panel entries associated with WPS 81-138-R016.
+-5821 04-21-86 Install ATTS panel entries associated with WPS 81-138-R016.
 Ref. DCR 81-138.
--6052       04-21-86               Fabricate and install all conduit and conduit supports associated with WPS 81-138-R018, T015.
+-6052 04-21-86 Fabricate and install all conduit and conduit supports associated with WPS 81-138-R018, T015.
 Ref. DCR 81-138.
--6178       04-25-86               Install class IF cables.from main control room panels to'ERF/SPDS panels X75-P200A,B.
+-6178 04-25-86 Install class IF cables.from main control room panels to'ERF/SPDS panels X75-P200A,B.
 Ref. DCR 80-157.
--0067       04-05-86               Install chains and break away locks on new fire protection riser isolation valves on T43 system.
+-0067 04-05-86 Install chains and break away locks on new fire protection riser isolation valves on T43 system.
 Ref. DCR 83-219.
--0665       04-05-86               Install decontamination ports for hydrolasing on Reactor building floor drains.
+-0665 04-05-86 Install decontamination ports for hydrolasing on Reactor building floor drains.
 Ref. DCR 85-196.
--1544       04-07-86               Replace motor on lEll-F004A.
+-1544 04-07-86 Replace motor on lEll-F004A.
 Ref. DCR 86-028.
--3755       04-11-86               Install sprinkler system T43185WO3.
+-3755 04-11-86 Install sprinkler system T43185WO3.
 Ref. DCR 83-246.
--4932       04-17-86               Replace scram discharge volume switches 1Cll-N013A-F.
+-4932 04-17-86 Replace scram discharge volume switches 1Cll-N013A-F.
 Ref. DCR 86-105.
-HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-4972        04-11-86               Remove RWCU piping insulation to provide access for weld overlay.
+HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-4972 04-11-86 Remove RWCU piping insulation to provide access for weld overlay.
 Reinstall when complete.
 Ref. DCR 85-120.
--4973        04-10-86               Remove Recirc piping insulation to provide access for weld overlay. Reinstall when complete.
+-4973 04-10-86 Remove Recirc piping insulation to provide access for weld overlay.
+Reinstall when complete.
 Ref. DCR 85-120.
--4974        04-07-86               Remove RHR piping insulation to provide access for weld overlay.
+-4974 04-07-86 Remove RHR piping insulation to provide access for weld overlay.
 Replace when through.
 Ref. DCR 85-120.
--5174        04-04-86               Replace unqualified MOV motors and actuators on B31 to meet the requirements of I.E.B. 79-OlB.
+-5174 04-04-86 Replace unqualified MOV motors and actuators on B31 to meet the requirements of I.E.B.
+-OlB.
 Ref. DCR 81-093.
--5176        03-24-86               Install Time Delay Relay E41-K63.
+-5176 03-24-86 Install Time Delay Relay E41-K63.
 Ref. DCR 83-214.
--5443         04-15-86              Implement a portion of DCR 81-138 Rev. 1 (ATTS) per WPS 81-138-T032 and WPS 81-138-T038.
+-5443 04-15-86 Implement a portion of DCR 81-138 Rev. 1 (ATTS) per WPS 81-138-T032 and WPS 81-138-T038.
 Ref. DCR 81-138.
--5585         04-09-86              Fabricate and install tubing supports and fittings for A70.
+-5585 04-09-86 Fabricate and install tubing supports and fittings for A70.
 Ref. DCR 81-138.
--5610         04-09-86              Complete the termination of 3 cables for X75 Emergency Response Facilities.
+-5610 04-09-86 Complete the termination of 3 cables for X75 Emergency Response Facilities.
 Ref. DCR 80-157.
--5622        04-15-86              Complete cable termination and redlining originally issued under 80-157-EC04, 07, 11 per work package 80-157-EM74A.
+-5622 04-15-86 Complete cable termination and redlining originally issued under 80-157-EC04, 07, 11 per work package 80-157-EM74A.
-Ref. DCR 80-157, 85-5768        04-14-86              Replace motor on B21-F019 per I.E.B. 79-01B.
+Ref. DCR 80-157, 85-5768 04-14-86 Replace motor on B21-F019 per I.E.B.
+-01B.
 Ref. DCR 81-113.
--5910        04-09-86              Calibrate new ATTS RTD trip units.
+-5910 04-09-86 Calibrate new ATTS RTD trip units.
 Ref. DCR 81-138.
-        ~
+~
-HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-5923         04-26-86                                 Calibrate transmitters for new
+HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-5923 04-26-86 Calibrate transmitters for new ATTS system.
-.                                                            ATTS system.
 Ref. DCR 81-138.
--5955         04-09-86                                 Calibrate new ATTS trip units per 57CP-CAL-102-lS.
+-5955 04-09-86 Calibrate new ATTS trip units per 57CP-CAL-102-lS.
 Ref. DCR 81-138.
--5993         04-09-86                                 Replace Barton transmitters with Rosemount transmitters on 1C71-N050A-D and 1 Ell-N094A-D.
+-5993 04-09-86 Replace Barton transmitters with Rosemount transmitters on 1C71-N050A-D and 1 Ell-N094A-D.
 Ref. DCR 80-138.
--6947         04-23-86                                  Implement A"Ts changes on HPCI Loop "B" T030-and RCIC Loop T025.
+-6947 04-23-86 Implement A"Ts changes on HPCI Loop "B" T030-and RCIC Loop T025.
 Ref. DCR 81-138.
--6988         03-26-86                                  Implement ATTS changes on NSSS Loop "A" T034 per 42SP-DCI-006-lS.
+-6988 03-26-86 Implement ATTS changes on NSSS Loop "A" T034 per 42SP-DCI-006-lS.
 Ref. DCR 81-138.
--6990         04-22-86                                  Mount alarm relay for RWCU in panel H21-P602.
+-6990 04-22-86 Mount alarm relay for RWCU in panel H21-P602.
 Ref. DCR 81-124.
--6993         04-08-86                                   Implement ATTS changes per 42SP-DCI-005-1S.                        (SLD Loop T033)
+-6993 04-08-86 Implement ATTS changes per 42SP-DCI-005-1S.
+(SLD Loop T033)
 Ref. DCR 81-138.
--7052         04-23-86                                   Implemented a portion of DCR 81-138 Rev. 1 as per WPS 81-138-T040.
+-7052 04-23-86 Implemented a portion of DCR 81-138 Rev. 1 as per WPS 81-138-T040.
 Ref. DCR 81-138.
--7095         03-11-86                                  Functional test new C71 ATTS instruments.
+-7095 03-11-86 Functional test new C71 ATTS instruments.
 Ref. DCR 81-138.
--7096         04-23-86                                   Functional test new E21 ATTS equipment.
+-7096 04-23-86 Functional test new E21 ATTS equipment.
 Ref. DCR 81-138.
--7097         04-09-86                                    Functional test new E51 ATTS Instruments.
+-7097 04-09-86 Functional test new E51 ATTS Instruments.
 Ref. DCR 81-138.
--7100         04-09-86                                    Functional test new E41 ATTS Instruments.
+-7100 04-09-86 Functional test new E41 ATTS Instruments.
 Ref. DCR 81-138.
-                - .    .,__-_,#  .   . , . _ , , , . , , _ _ _ _    ,  . _ . , . , _ , . .- _ . , _ , , , . .   ,_-..,_,s_._...., ,_. -. m,.
+,_-..,_,s_._....,
+m,.
-HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-7101         04-24-86               Functional test new RHR ATTS instruments.
+HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-7101 04-24-86 Functional test new RHR ATTS instruments.
 Ref. DCR 81-138.
--7123         04-02-86               Modified E11-F008 to meet Appendix "R" 10CFR50 "Hi-Low" requirements.
+-7123 04-02-86 Modified E11-F008 to meet Appendix "R" 10CFR50 "Hi-Low" requirements.
 Ref. DCR 85-119.
--7219          04-09-86              Implement ATTS changes on ECCS Loop "F" T036 per 42SP-DCI-008-1S, Ref. DCR 81-138.
+-7219 04-09-86 Implement ATTS changes on ECCS Loop "F" T036 per 42SP-DCI-008-1S, Ref. DCR 81-138.
--7220         04-09-86              Implement ATTS changes on Ind Loop T031 per 42SP-DCI-004-lS.
+-7220 04-09-86 Implement ATTS changes on Ind Loop T031 per 42SP-DCI-004-lS.
 Ref. DCR 81-138.
--7344        04-22-86              Replace motors and actuators on valves lE21-F004A,B and lE21-F005A,B.
+-7344 04-22-86 Replace motors and actuators on valves lE21-F004A,B and lE21-F005A,B.
 Ref. DCR 81-093.
--7401        04-05-86              Remove shim plates on recirc piping to provide access for weld overlay. Reinstall new shim plates when complete.
+-7401 04-05-86 Remove shim plates on recirc piping to provide access for weld overlay.
+Reinstall new shim plates when complete.
 Ref. DCR 85-120.
--7412        04-04-86               Removed snubber from Recirc piping clamp and reinstall after weld overlay was complete.
+-7412 04-04-86 Removed snubber from Recirc piping clamp and reinstall after weld overlay was complete.
 Ref. DCR 85-120.
--7413         03-18-86              Remove pipe clamp from RWCU piping to provide access for weld overlay.
+-7413 03-18-86 Remove pipe clamp from RWCU piping to provide access for weld overlay.
 Ref. DCR 85-120.
--7957         04-10-86              Remove drywell pneumatic system piping which interferes with the installation of weld overlay equipment. Reinstall upon completion of weld overlay.
+-7957 04-10-86 Remove drywell pneumatic system piping which interferes with the installation of weld overlay equipment.
+Reinstall upon completion of weld overlay.
 Ref. DCR 85-120.
--7958        04-05-86               Remove shim plates on recirc piping to provide access for weld overlay. Reinstall new shim plates when complete.
+-7958 04-05-86 Remove shim plates on recirc piping to provide access for weld overlay.
+Reinstall new shim plates when complete.
 Ref. DCR 85-120.
 w
-HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-7959        04-05-86               Remove beam _ angle and grating on RWCU piping which interferes with weld overlay.
+HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 85-7959 04-05-86 Remove beam _ angle and grating on RWCU piping which interferes with weld overlay.
 Ref. DCR 85-120.
--8007        04-07-86               Remove insulation below valve G31-F004 to provide access for weld overlay.
+-8007 04-07-86 Remove insulation below valve G31-F004 to provide access for weld overlay.
 Ref. DCR 85-120.
--0212        04-10-86               Open Drywell Penetration X43 to route welding cables.
+-0212 04-10-86 Open Drywell Penetration X43 to route welding cables.
 Ref. DCR 85-120.
--0322        04-22-86               Perform Flush / Hydro on E51 system.
+-0322 04-22-86 Perform Flush / Hydro on E51 system.
-:                                                  Ref. DCR 81-138.
+Ref. DCR 81-138.
--0324        04-04-86               Perform Flush / Hydro on E41 system.
+-0324 04-04-86 Perform Flush / Hydro on E41 system.
 Ref. DCR 81-138.
--0471        04-02-86               Change out breaker R22-S017 frame 1M with refurbished breaker with modified trip elements.
+-0471 04-02-86 Change out breaker R22-S017 frame 1M with refurbished breaker with modified trip elements.
 Ref. OCR 85-221.
--0602        04-04-86               Install decontamination ports for CRD 8" Scram discharge Heater for Hydrolase work.
+-0602 04-04-86 Install decontamination ports for CRD 8" Scram discharge Heater for Hydrolase work.
 Ref. DCR 85-197.
--0668        04-15-86               Remove main incoming line supply breakers (lR24-S018A,B) and install safety switches.
+-0668 04-15-86 Remove main incoming line supply breakers (lR24-S018A,B) and install safety switches.
-Ref. DCR 84-204 86-0761        04-24-86               Reworked conduit and cable per WPS 81-138-E020 and ORl-86a8.
+Ref. DCR 84-204 86-0761 04-24-86 Reworked conduit and cable per WPS 81-138-E020 and ORl-86a8.
 Ref. DCR 81-138.
--0764        04-09-86               Reinstall pipe support for P70 piping which was removed to provide access for weld overlay.     .
+-0764 04-09-86 Reinstall pipe support for P70 piping which was removed to provide access for weld overlay.
-Ref. DCR 85-120.                     !
+Ref. DCR 85-120.
--0832        04-09-86               Replace Jet Pump beam #16 (lBil-D233).
+-0832 04-09-86 Replace Jet Pump beam #16 (lBil-D233).
 Ref. DCR 86-020.
-i
-HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 86-0833                 03-26-86                   Determinate and remove 1H11-P613-E59-Cll6 from panel H21-P001. Inspect for damage from flood. Obtain new cable pull and terminate cable.
+HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 86-0833 03-26-86 Determinate and remove 1H11-P613-E59-Cll6 from panel H21-P001.
+Inspect for damage from flood.
+Obtain new cable pull and terminate cable.
 Ref. DCR 81-138.
--0837                 04-07-86                   Readjust the set points on ATTS trip units B21-N685A&B.
+-0837 04-07-86 Readjust the set points on ATTS trip units B21-N685A&B.
 Ref. DCR 85-092.
--0838                 04-09-86                   Readjust the set points of ATTS i                                                            trip units B21-N682A-D.
+-0838 04-09-86 Readjust the set points of ATTS i
+trip units B21-N682A-D.
 Ref. DCR 85-092.
--0839                 04-09-86                   Readjust the set points of ATTS trip units B21-N693A-D.
+-0839 04-09-86 Readjust the set points of ATTS trip units B21-N693A-D.
 Ref. DCR 85-092.
--0840                 04-09-86                   Readjust the set point of ATTs trip units B21-N680A-D Ref. DCR 85-092.
+-0840 04-09-86 Readjust the set point of ATTs trip units B21-N680A-D Ref. DCR 85-092.
--0841                 04-09-86                   Readjust the set points of ATTS trip units B21-N691A-D.
+-0841 04-09-86 Readjust the set points of ATTS trip units B21-N691A-D.
 Ref. DCR 85-092.
--0842                 04-09-86                   Readjust the set points of ATTS trip units B21-N681A-D.                 '
+-0842 04-09-86 Readjust the set points of ATTS trip units B21-N681A-D.
 Ref. DCR 85-092.
--0843                 04-09-86                   Readjust the set points of ATTS trip units E41-N660A,B.
+-0843 04-09-86 Readjust the set points of ATTS trip units E41-N660A,B.
 Ref. DCR 85-092.
--0844                 04-09-86                   Readjust the set points of ATTS trip units on B21-N692A-D.
+-0844 04-09-86 Readjust the set points of ATTS trip units on B21-N692A-D.
 Ref. DCR 85-092.
--0845                 04-09-86                   Readjust the set points of ATTS trip units B21-N690E,F.
+-0845 04-09-86 Readjust the set points of ATTS trip units B21-N690E,F.
 Ref. DCR 85-092.
--0846                 04-09-86                   Readjust the set points of ATTS trip units B21-N695A,B.
+-0846 04-09-86 Readjust the set points of ATTS trip units B21-N695A,B.
 Ref. DCR 85-092.
--0849                 04-09-86                    Readjust the set points of ATTS trip units B21-N641B,C.
+-0849 04-09-86 Readjust the set points of ATTS trip units B21-N641B,C.
 [
-Ref. DCR 85-092.                       ,
+Ref. DCR 85-092.
-HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 86-0850         04-09-86              Readjust the set points of ATTS trip units E41-N657A,B.
+HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 86-0850 04-09-86 Readjust the set points of ATTS trip units E41-N657A,B.
 Ref. DCR 85-092.
--0851        04-09-86              Readjust the set points of ATTS trip units B21-N690A-D.
+-0851 04-09-86 Readjust the set points of ATTS trip units B21-N690A-D.
 Ref. DCR 85-092.
--0923       19-86              Change out R23-S004 Breaker 4B with refurbished breaker equipped with modified micro versa trip device.
+-0923 19-86 Change out R23-S004 Breaker 4B with refurbished breaker equipped with modified micro versa trip device.
 Ref. DCR 85-219.
--0935        04-07-86              Remove MSIV 3/4" leakoff line piping. Weld pipe caps onto remaining IT45 drain piping.
+-0935 04-07-86 Remove MSIV 3/4" leakoff line piping.
+Weld pipe caps onto remaining IT45 drain piping.
 Ref. DCR 85-161.
--0988        04-07-86              Replace Barton transmitter with Rosemount transmitter on Ell-N055C.
+-0988 04-07-86 Replace Barton transmitter with Rosemount transmitter on Ell-N055C.
 Ref. DCR'81-138.
--1006        04-05-86              Remove pipe support and cold spring drain line for.B31-F031A to provide access for weld overlay. Reinstall after completion.
+-1006 04-05-86 Remove pipe support and cold spring drain line for.B31-F031A to provide access for weld overlay.
+Reinstall after completion.
 Ref. DCR 85-120.
--1019         04-05-86             Remove temporary startup instrumentation bracket on B31 to provide access for weld overlay.
+-1019 04-05-86 Remove temporary startup instrumentation bracket on B31 to provide access for weld overlay.
 Reinstall when complete.
 Ref. DCR 85-120.
--1056        03-26-86              Flush newly installed ATTS Tubing for E21 system.
+-1056 03-26-86 Flush newly installed ATTS Tubing for E21 system.
 Ref. DCR 81-138.
--1084        04-10-86              Remove damaged cables on E41/E51 and pull new cables.
+-1084 04-10-86 Remove damaged cables on E41/E51 and pull new cables.
 Ref. DCR 81-174.
--1085        04-05-86              Removed temporary service water and Demin water hoses and connections'and restore the systems to their normal configurations.
+-1085 04-05-86 Removed temporary service water and Demin water hoses and connections'and restore the systems to their normal configurations.
 Ref. DCR 85-120.
 l
-HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 86-1183        0,4-07-86              Restore pipe. clamp and spring can 1 Ell-RHRH-327 which was removed to provide access for weld overlay.
+HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 86-1183 0,4-07-86 Restore pipe. clamp and spring can 1 Ell-RHRH-327 which was removed to provide access for weld overlay.
 Ref. DCR 85-120.
-86-1376         04-22-86               Correct the long term pick-up for R22-S016 Fr. 1B & 3M.
+-1376 04-22-86 Correct the long term pick-up for R22-S016 Fr. 1B & 3M.
 Ref. DCR 85-221.
--1541         04-11-86               Replace lE21-F001A motor.
+-1541 04-11-86 Replace lE21-F001A motor.
 Ref. DCR 86-028.
--1542         04-01-86               Replace motor on E21-F031A.
+-1542 04-01-86 Replace motor on E21-F031A.
 Ref. DCR 86-028.
--1610         04-03-86               Rowire and relabel indicating lights ACG and ACJ on R26-M077.
+-1610 04-03-86 Rowire and relabel indicating lights ACG and ACJ on R26-M077.
 .I Ref. DCR 84-204.
-86-1623         04-21-86               Reterminate cable                     "
+-1623 04-21-86 Reterminate cable 1
 Hil-P612-ESO-C068to enable lEll-N007B.
 Ref. DCR 81-196.
--1880         04-07-86              Close Drywell penetration X43.
+-1880 04-07-86 Close Drywell penetration X43.
 Ref. DCR 85-120.
--1967         04-07-86              Disconnect cables subjected to flooding in the southeast diagonal, northeast diagonal, and i
+-1967 04-07-86 Disconnect cables subjected to flooding in the southeast diagonal, northeast diagonal, and i
 HPCI room.
 Ref. DCR 86-058.
--2042         04-16-86              Pull back cables, rework conduit, install new terminal boxes, install new conduit and supports.
+-2042 04-16-86 Pull back cables, rework conduit, install new terminal boxes, install new conduit and supports.
- !                                       pull back new cable from new terminal boxes to instruments on B31, Ell, ET.1, E41, and P41.
+pull back new cable from new terminal boxes to instruments on B31, Ell, ET.1, E41, and P41.
 Ref. DCR Bo-058.
--2281         04-10-86              Termination of circuits for E21-N001A.
+-2281 04-10-86 Termination of circuits for E21-N001A.
+Ref. DCR 86-058.
+-2290 04-09-86 Termination of circuits for Ell-R001A.
 Ref. DCR 86-058.
--2290         04-09-86              Termination of circuits for Ell-R001A.
+d 1
-d Ref. DCR 86-058.
-                                                                 .: g , - . .      !,' .
 l
+.: g
-i                                                                                ,
+i HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 i
-HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 i
+-2471 04-22-86 Perform controlled grinding on FW nozzle inspection door F51-N4B to ensure door will close without i
- ,  86-2471      04-22-86               Perform controlled grinding on FW nozzle inspection door F51-N4B to ensure door will close without i                                     striking FW pipe.
+striking FW pipe.
 Ref. DCR 86-121.
--2815      04-09-86               Perform functional test on ATTS per Special Instruction 57SP-0320861.
+-2815 04-09-86 Perform functional test on ATTS per Special Instruction 57SP-0320861.
 Ref. DCR 81-138.
--2835      04-17-86               Recalibrate P70-KR10,12,20,22 and replace the annunciator cards and
+-2835 04-17-86 Recalibrate P70-KR10,12,20,22 and replace the annunciator cards and cover gasket for pressure switch P70-N016.
-  ,                                     cover gasket for pressure switch           ,
-P70-N016.
 Ref. DCR 81-111.
--2840      04-09-86               Perform initial leak tests and pre-service calibration checks on 1P33-P001A&B.
+-2840 04-09-86 Perform initial leak tests and pre-service calibration checks on 1P33-P001A&B.
 Ref. DCR 81-132.
--2898      04-08-86               Replace 2nd Stage MSR steam flow pressure transmitter (N38-N772D) with a Rosemount Diferential transmitter.
+-2898 04-08-86 Replace 2nd Stage MSR steam flow pressure transmitter (N38-N772D) with a Rosemount Diferential transmitter.
 DCR 86-124.
 i i
 i I
 t i
-                                                                                 ,
+i
-i l
-l
-OPERATING DATA REPORT                                              .
+OPERATING DATA REPORT DOCKET NO.
-DOCKET NO. 50-321 DATE           05-10-86 COMPLETED BY: Gary Koerber TELEPHONE      (912) 367-7851 x 2882 OPERATING STATUS
+-321 DATE 05-10-86 COMPLETED BY: Gary Koerber TELEPHONE (912) 367-7851 x 2882 OPERATING STATUS 1.
-: 1. Unit Name: E. I. Hatch Nuclear Plant                           Unit 1
+Unit Name:
-: 2. Reporting Period:                                              04-86
+E.
-: 3. Licensed Thermal Power (MWt):                                  2436
+I.
-: 4. Nameplate Rating (Gross MWe):                                  809.3
+Hatch Nuclear Plant Unit 1 2.
-: 5. Design Electrical Rating (Net MWe):                            777.3
+Reporting Period:
-: 6. Maximum Dependable Capacity (Gross MWe):                       801.2
+-86 3.
-: 7. Maximum Dependable Capacity (Net MWe):                         768.0
+Licensed Thermal Power (MWt):
-: 8. If changes occur in capacity ratings (Items Number 3 through 7) since last report, give reasons:    N/A
+4.
-: 9. Power level to which restricted, if any (Net MWe):             No Restrictions
+Nameplate Rating (Gross MWe):
-: 10. Reasons for restrictions, if any:                               N/A This Month      Yr-to-Date       Cumulative
+.3 5.
-: 11. Hours In Reporting Period                                           719         2879             90550
+Design Electrical Rating (Net MWe):
-: 12. Number of Hours Reactor was Critical                                0.0          0.0           62126.2
+.3 6.
-: 13. Reactor Reserve Shutdown Hours                                        0            0                   0
+Maximum Dependable Capacity (Gross MWe):
-: 14. Hours Generator On-Line                                             0.0          0.0           58561.1
+.2 7.
-: 15. Unit Reserve Shutdown Hours                                         0.0          0.0                   0
+Maximum Dependable Capacity (Net MWe):
-: 16. Gross Thermal Energy Generated (MWH)                                  C            0        124631490
+.0 8.
-: 17. Gross Electrical Energy Generated (MWH)                               0            0         40242130
+If changes occur in capacity ratings (Items Number 3 through 7) since last report, give reasons:
-: 18. Net Electrical Energy Generated (MWH)                                 0            0         38197524*
+N/A 9.
-: 19. Unit Service Factor (%)                                             0.0          0.0              64.7
+Power level to which restricted, if any (Net MWe):
-: 20. Unit Availability Factor (%)                                        0.0          0.0              64.7
+No Restrictions
-: 21. Unit Capacity Factor (% Using MDC Net)                              0.0          0.0              54.9
+: 10. Reasons for restrictions, if any:
-: 22. Unit Capacity Factor (% Using DER Net)                              0.0          0.0              54.3
+N/A This Month Yr-to-Date Cumulative
-: 23. Unit Forced Outage Rate                                             0.0          0.0              17.5
+: 11. Hours In Reporting Period 719 2879 90550
+: 12. Number of Hours Reactor was Critical 0.0 0.0 62126.2
+: 13. Reactor Reserve Shutdown Hours 0
+0
+: 14. Hours Generator On-Line 0.0 0.0 58561.1
+: 15. Unit Reserve Shutdown Hours 0.0 0.0 0
+: 16. Gross Thermal Energy Generated (MWH)
+C 0
+124631490
+: 17. Gross Electrical Energy Generated (MWH) 0 0
+40242130
+: 18. Net Electrical Energy Generated (MWH) 0 0
+38197524*
+: 19. Unit Service Factor (%)
+.0 0.0 64.7
+: 20. Unit Availability Factor (%)
+.0 0.0 64.7
+: 21. Unit Capacity Factor (% Using MDC Net) 0.0 0.0 54.9
+: 22. Unit Capacity Factor (% Using DER Net) 0.0 0.0 54.3
+: 23. Unit Forced Outage Rate 0.0 0.0 17.5
 : 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 startup: May 11, 1986
-: 26. Units in Test Status (Prior to Commercial Operation):             N/A
+: 26. Units in Test Status (Prior to Commercial Operation):
-* NOTE:  The cummulative Net Electrical Generation includes station service used while shutdown.
+N/A
+* NOTE:
+The cummulative Net Electrical Generation includes station service used while shutdown.
-    . . _ . . . _ . . . . . . _ _ _     . . . _ . . _ _ . _ . _ _ _ . . _ . - _ _ _ . _ . . . . . _ _ . _ _ _ _ . . . _ . _ _ _ _ . . _ . _ _ . . _ . _ _ - . . _ _ _ _ _ . . . . _ . _ _ _ . _ - . _ . ~ . _ _ . _
+... _.. _ _. _. _ _ _.. _. - _ _ _. _..... _ _. _ _ _ _... _. _ _ _ _.. _. _ _.. _. _ _ -.. _ _ _ _ _.... _. _ _ _. _ -. _. ~. _ _. _
-d
+d l
-                                                                                                                                                                                                                                                   ~
+AVERAGE DAILY UNIT POWER LEVEL
-l                                                                                                            AVERAGE DAILY UNIT POWER LEVEL                                                                                                                'i j
+'i
-* i I
+~
-DOCKET NO.                  50-321 1                                                                                                                                                                                                  DATE:                       05-10-86                      ,
+j i
-;                                                                                                                                                                                                  COMPLETED BY: Gary Koerber j
+I DOCKET NO.
-TELEPHONE                   (912).367-7851 x 2882 MONTH        04-86
+-321 1
-                                                   ~
+DATE:
- ,               DAY                 AVERAGE DAILY POWER LEVEL                                                                                    DAY                                              AVERAGE DAILY POWER LEVEL                                 I (MWe-Net)                                                                                                                                                            (MWe-Net)                            I f
+-10-86 COMPLETED BY: Gary Koerber j
-                1                                                 0                                                                             17                                                                            0                            1 i                 2                                                0                                                                              18                                                                            0 i                3                                                 0                                                                             19                                                                            0 I
+TELEPHONE (912).367-7851 x 2882 MONTH 04-86
-                                                 0                                                                              20                                                                            0 4                 5                                                 0                                                                             21                                                                            0                            :
+~
-i                 6                                                0                                                                              22                                                                            0 i                 7                                                 0                                                                             23                                                                            0                            t
+I DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
- ;               8                                                 0                                                                              24                                                                            0 9                                                 0                                                                             25                                                                            0 10                                               0                                                                              26                                                                            0                            !
+(MWe-Net)
-                                               0                                                                             27                                                                            0
+I f
- ,                12                                               0                                                                              28                                                                            0 l                 13                                               0                                                                              29                                                                            0 14                                               0                                                                              30                                                                            0 15                                               0                                                                              31                                                                            0 l                16                                               0 1
+1
-I i
+17 0
-k i                                                                                                                                                                                                                                                             ;
+i
-  ;                                                                                                                                                                                                                                                          i i
+0
+0
+i 3
+19 0
+I 4
+20 0
+0
+0
+i
+0
+0
+i 7
+23 0
+t 8
+24 0
+0
+0
+0
+0
+0
+0
+0
+0
+l 13 0
+0
+0
+0
+0
+0
+l 16 0
+I
+i k
+i i
+i i
 i i
-i
-UNIT SHUTDOWNS AND POWER REDUCTIONS                                          -
+UNIT SHUTDOWNS AND POWER REDUCTIONS l
-l DOCKET NO.                        50-321                                UNIT NAME     HATCH ONE COMPLETED BY                      Gary M. Koerber               TELEPHONE (912) 367-7851 (2882)      DATE    MAY 10,1986 REPORT MONTH APRIL i          i                              i     i        l     I             I          I       I            I                            I I          I                               I     I       IR I                 I          IS      I            I                            I I          l                               l     1       IE I                 I          IY     I             I                            I I          I                               IT l          l A I METHOD OF I LICENSEE ISC l                     I                            I I          I                               l Y I         IS I SHUTTING I          EVENT  ITO I                l   CAUSE & CORRECTIVE I          I                               l P l DURATION IO I       DCWN     I  REPORT  IED l COMPONENT I            ACTION TO I   NO. I                     DATE     IE l (HOURS) i N l REACTOR I NUMBER IME I                 CODE     I   PREVENT RECURRENCE       I I          I                              I      I       I      I             I          I       I            I                            I I          i                              i      i       i      i             i          i       i            i                            l I 86-004   l 860401                        1S I 719      iC I      4          l N/A      I RC     i FUELXX    l Refueling Outage           !
+DOCKET NO.
-I          I                              I      l       l      l             1          I                    I Continues                   '
+-321 UNIT NAME HATCH ONE COMPLETED BY Gary M.
-I          i                              i     l        i      I             i          I      ,
+Koerber TELEPHONE (912) 367-7851 (2882)
-I I          I                              I      I       I      I             I          I        I           I                            I I          I                              I     I        I      I             I          I       I            I                            I I          I                              I     I        I      I             I          I       I            I                            I I          I                              I      I       I      I             I          I        I           I                            I I          I                              I     I        I      I             I          I        I           I                            I I          I                              I     I        I      I             I          I       I            I                            I I          I                              I     I        I      I             I          I        I           I                            I I          I                              I     I        I     I              I          I      I             I                            I I          I                              I     I        I     I              I          I        I           I                            I I          i                              l     l        I     I              I          I       I            I                            I I          i                              I     I        I     I              I          I        I           I                            l 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 hours.
+DATE MAY 10,1986 REPORT MONTH APRIL i
-D-Regulatory Restriciton             4-Continuations E-Operator Training & License        5-Load Reduction Examination                        9-Other (Explain)
+i i
+i l
+I I
+I I
+I I
+I I
+I I
+IR I I
+IS I
+I I
+I l
+l 1
+IE I I
+IY I
+I I
+I I
+IT l l A I METHOD OF I LICENSEE ISC l I
+I I
+I l Y I IS I SHUTTING I
+EVENT ITO I l
+CAUSE & CORRECTIVE I
+I l P l DURATION IO I DCWN I
+REPORT IED l COMPONENT I ACTION TO I
+NO.
+I DATE IE l (HOURS) i N l REACTOR I
+NUMBER IME I CODE I
+PREVENT RECURRENCE I
+I I
+I I
+I I
+I I
+I I
+I I
+i i
+i i
+i i
+i i
+i l
+I 86-004 l 860401 1S I 719 iC I 4
+l N/A I RC i
+FUELXX l Refueling Outage I
+I I
+l l
+l 1
+I I Continues I
+i i
+l i
+I i
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+i l
+l I
+I I
+I I
+I I
+I i
+I I
+I I
+I I
+I I
+l 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 hours.
+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 l
+l NARRATIVE REPORT UNIT TWO April 1st 0000 Unit at 85% power with no major equipment problems.
-                                       .                                                                      NARRATIVE REPORT                                                                                                                          l UNIT TWO April 1st                                                0000           Unit at 85% power with no major equipment problems. Holding                                                                                                     l power per management decision to help relieve offgas activity in reactor and turbine buildings.
+Holding power per management decision to help relieve offgas activity in reactor and turbine buildings.
-April 12th                                               0227           4160 Volt bus 2A, Recirc pump 2A, and Circ water pump 2A all tripped.                Recovery in progress.
+April 12th 0227 4160 Volt bus 2A, Recirc pump 2A, and Circ water pump 2A all tripped.
-          Back at 85% power.
+Recovery in progress.
-l                                                                                                        2330           Reducing power for weekly turbine j                                                                                                                       testing.
+Back at 85% power.
-April 13th                                              0300           Back at 85% power.
+l 2330 Reducing power for weekly turbine j
-April 20th                                              0101           Rx Scram Turbine trip on
+testing.
- !                                                                                                                      erroneous MSR A high level.
+April 13th 0300 Back at 85% power.
-          Scram Recovery in progress.
+April 20th 0101 Rx Scram Turbine trip on erroneous MSR A high level.
-!                                                April 21st                                              1537           Reducing to 55% rated power to j                                                                                                                       remove RFPT 2B from service.
+Scram Recovery in progress.
-April 22nd                                             0520           RFPT 2B back in service.
+April 21st 1537 Reducing to 55% rated power to j
-          Back at 85% power.
+remove RFPT 2B from service.
-April 24th                                             2334           Rx Scram. Excessive condensation in the Generator Exciter caused a Generator Field Ground and subsequent turbine trip. Source of condensation was an approximately 18" rupture in the 6th~ stage "A" extraction line.
+April 22nd 0520 RFPT 2B back in service.
-April 28th                                              1336           Scram Recovery in progress.
+Back at 85% power.
-April 29th                                              1900           Back at 85% power.
+April 24th 2334 Rx Scram.
-April 30th                                              2400           Unit at 85% power with no major equipment problems.
+Excessive condensation in the Generator Exciter caused a Generator Field Ground and subsequent turbine trip.
+Source of condensation was an approximately 18" rupture in the 6th~ stage "A" extraction line.
+April 28th 1336 Scram Recovery in progress.
+April 29th 1900 Back at 85% power.
+April 30th 2400 Unit at 85% power with no major equipment problems.
 I
-i                                                  .
+i i
-i 4
+I
-I                                                       HATCH 2 SAFETY-RELATED MAINTENANCE -WORK ORDERS                                                                                                                                                                                                    l
+HATCH 2 SAFETY-RELATED MAINTENANCE -WORK ORDERS
 ]
-TO BE REPORTED FOR APRIL 1986 i                                      NUMBER.                       DATE COMPLETED                                                                                  DESCRIPTION
+TO BE REPORTED FOR APRIL 1986 i
-,                                        83-0429                       04-10-86                                                                                     Install conduit 2MB0441, 2MB1356,7,8,9 l                                                                                                                                                                   and supports.
+NUMBER.
-!                                                                                                                                                                   Ref. DCR 80-157.
+DATE COMPLETED DESCRIPTION 83-0429 04-10-86 Install conduit l
+MB0441, 2MB1356,7,8,9 and supports.
+Ref. DCR 80-157.
 [
-I                                        83-1348                       04-12-86                                                                                     Install panels.
+I 83-1348 04-12-86 Install panels.
-I                                                                                                                                                                   2X75-P200A&B.
+I 2X75-P200A&B.
 Ref.'DCR 80-157.
-]                                          83-1432                     04-12-86                                                                                     Pour concrete pads for 2Rll-S100, 2R25-S133, and 2R44-S005.
+]
-I                                                                                                                                                                   Ref. DCR 80-157.
+-1432 04-12-86 Pour concrete pads for 2Rll-S100, 2R25-S133, and 2R44-S005.
-!                                          83-2238                     04-12-86                                                                                     Install panels 2R25-S133 and-
+I Ref. DCR 80-157.
-!                                                                                                                                                                   R25-S0108 in vital AC
+-2238 04-12-86 Install panels 2R25-S133 and-R25-S0108 in vital AC room Units 1 & 2.
-.                                                                                                                                                                   room Units 1 & 2.
 Ref. DCR 80-157.
-I                                           85-1265                    04-11-86                                                                                     Install Sprinkler 4                                                                                                                                                                   system 2T43130WO6.
+I 85-1265 04-11-86 Install Sprinkler system 2T43130WO6.
 Ref. DCR 83-248.
--1635                    04-10-86                                                                                     Install fire protection sprinkler j                                                                                                                                                                   system 2T43087WO8.                                                                                                                    ;
+-1635 04-10-86 Install fire protection sprinkler j
+system 2T43087WO8.
+Ref. DCR 83-250.
+-1636 04-09-86 Install fire i.
+protection sprinkler i
+system 2T43087WOl.
+j '
 Ref. DCR 83-250.
-!                                            85-1636                   04-09-86                                                                                     Install fire                                                                                                                          ,
-: i.                                                                                                                                                                  protection sprinkler i                                                                                                                                                                  system 2T43087WOl.
-j'                                                                                                                                                                  Ref. DCR 83-250.
-)                                            85-2893                   04-08-86                                                                                     Replace CS pump bowl
+)
-;                                                                                                                                                                   assembly with a SS
+-2893 04-08-86 Replace CS pump bowl assembly with a SS bowl assembly-on 1
-:                                                                                                                                                                   bowl assembly-on 1                                                                                                                                                                   2P41-C001D.                                                                                                                           ,
+P41-C001D.
-!                                                                                                                                                                   Ref. DCR-84-060.
+Ref. DCR-84-060.
-I                                             85-3172                   04-14-86                                                                                    Re-roof Unit 2 turbine
+I 85-3172 04-14-86 Re-roof Unit 2 turbine and reactor buildings.
-,                                                                                                                                                                   and reactor buildings.
+Ref. DCR 85-067.
-;                                                                                                                                                                   Ref. DCR 85-067.
+85-3173 04-14-86 Re-roof Unit 2 Turbine j
+building and Reactor building connectors.
-;                                              85-3173                  04-14-86                                                                                    Re-roof Unit 2 Turbine                                                                                                                ,
+l Ref. DCR 85-067.
-j                                                                                                                                                                   building and Reactor
-;                                                                                                                                                                   building connectors.                                                                                                                   '
-l Ref. DCR 85-067.                                                                                                                     !
 l t
 i i
-l
+HATCH 2 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR APRIL 1986 NUMBER DATE COMPLETED DESCRIPTION 85-3174 04-14-86 Re-roof Unit 2 Radwaste building and l
-                    ..                                                                      1 l
+Hot Machine Shop.
-HATCH 2 SAFETY-RELATED MAINTENANCE WORK ORDERS                    !
-TO BE REPORTED FOR APRIL 1986
-:      NUMBER                     DATE COMPLETED          DESCRIPTION
-!       85-3174                      04-14-86             Re-roof Unit 2 Radwaste building and           l Hot Machine Shop.
 Ref. DCR 85-067.
--6864                      03-26-86             Replace flow transmitter X75-FT-N009 and existing flow meter X75-FE-N002 with a Veltron 7000/3 CEJNV flow transmitter and three air monitor probes.
+-6864 03-26-86 Replace flow transmitter X75-FT-N009 and existing flow meter X75-FE-N002 with a Veltron 7000/3 CEJNV flow transmitter and three air monitor probes.
 Ref. DCR 80-157.
--0486                      04-23-86             Implement a' portion of DCR 81-139 Rev. 1 per WPS 81-139-T080.
+-0486 04-23-86 Implement a' portion of DCR 81-139 Rev. 1 per WPS 81-139-T080.
 Ref. DCR 81-139.
-OPERATING DATA REPORT                                                                                        .
+OPERATING DATA REPORT DOCKET NO.
-DOCKET NO.                 50-366 DATE                       05-10-86                                 .
+-366 DATE 05-10-86 COMPLETED BY: Gary Koerber TELEPHONE (912) 367-7851 x 2882 i
-COMPLETED BY: Gary Koerber TELEPHONE                   (912) 367-7851 x 2882 i
 OPERATING STATUS
-: 1. Unit Name: E. I. Hatch Nuclear Plant                                                        Unit 2
+: 1. Unit Name: E.
-: 2. Reporting Period:                                                                           04-86 i          3. Licensed Thermal Power (MWt):                                                                2436
+I.
-;           4. Nameplate Rating (Gross MWe):                                                                817.0
+Hatch Nuclear Plant Unit 2 2.
-: 5. Design Electrical Rating (Net MWe):                                                          784.0                                                                   '
+Reporting Period:
-;           6. Maximum Dependable Capacity (Gross MWe):                                                     803.9
+-86 i
-: 7. Maximum Dependable Capacity (Net MWe):                                                       777.0
+: 3. Licensed Thermal Power (MWt):
-: 8. If changes occur in capacity ratings                                                                                                                                '
-i               (Items Number 3 through 7) since last report, give reasons:                                N/A
+: 4. Nameplate Rating (Gross MWe):
-: 9. Power level to which restricted, if any (Net MWe)                                           No Restrictions
+.0
-: 10. Reasons for restrictions, if any:                                                            N/A t
+: 5. Design Electrical Rating (Net MWe):
-This Month                    Yr-to-Date                     Cumulative
+.0
-: 11. Hours In Reporting Period                                                                        719                        2879                          58176
+: 6. Maximum Dependable Capacity (Gross MWe):
-: 12. Number of Hours Reactor was Critical                                                          634.7                    2725.9                          40297.4
+.9
-: 13. Reactor Reserve Shutdown Hours                                                                         O                             O                            O
+: 7. Maximum Dependable Capacity (Net MWe):
-: 14. Hours Generator On-Line                                                                       605.9                    2650.7                          38518.8
+.0 8.
-: 15. Unit Reserve Shutdown Hours                                                                      0.0                           0.0                          0. O
+If changes occur in capacity ratings i
-: 16. Gross Thermal Energy Generated (MWH)                                                        1197696                 5418352                      83601558
+(Items Number 3 through 7) since last report, give reasons:
-: 17. Gross Electrical Energy Generated (MWH)                                                      389100                 1778760                      27560260 i
+N/A
-: 18. Net Electrical Energy Generated (MWH)                                                        369101                 1694283                      26232937 i
+: 9. Power level to which restricted, if any (Net MWe)
-: 19. Unit Service Factor (%)-                                                                         84.3                        92.1                            66.2
+No Restrictions
-: 20. Unit Availability Factor (%)                                                                     84.3                         92.1                           66.2-
+: 10. Reasons for restrictions, if any:
-: 21. Unit Capacity Factor (% Using MDC Net)                                                          66.1                         75.7                           58.0
+N/A t
-: 22. Unit Capacity Factor (% Using DER Net)                                                          65.5                         75.1                           57.5
+This Month Yr-to-Date Cumulative
-: 23. Unit Forced Outage Rate                                                                         15.7                           7.9                          10.8 1          24. Shutdowns scheduled over next 6 months (Type, Date, and Duration of Each):
+: 11. Hours In Reporting Period 719 2879 58176
-Refueling Outage, September 06, 1986                            8 weeks j          25. If shutdown at end of report period, estimated date of startup: N/A
+: 12. Number of Hours Reactor was Critical 634.7 2725.9 40297.4
-: 26. Units in Test Status (Prior to Commercial Operation):                                        N/A 4
+: 13. Reactor Reserve Shutdown Hours O
+O O
+: 14. Hours Generator On-Line 605.9 2650.7 38518.8
+: 15. Unit Reserve Shutdown Hours 0.0 0.0
+: 0. O
+: 16. Gross Thermal Energy Generated (MWH) 1197696 5418352 83601558
+: 17. Gross Electrical Energy Generated (MWH) 389100 1778760 27560260 i
+: 18. Net Electrical Energy Generated (MWH) 369101 1694283 26232937 i
+: 19. Unit Service Factor (%)-
+.3 92.1 66.2
+: 20. Unit Availability Factor (%)
+.3 92.1 66.2-
+: 21. Unit Capacity Factor (% Using MDC Net) 66.1 75.7 58.0
+: 22. Unit Capacity Factor (% Using DER Net) 65.5 75.1 57.5
+: 23. Unit Forced Outage Rate 15.7 7.9 10.8 1
+: 24. Shutdowns scheduled over next 6 months (Type, Date, and Duration of Each):
+Refueling Outage, September 06, 1986 8 weeks j
+: 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 4
 i 4
-                                                       ~.                       -                                                        -                          , , .
+~.
-i AVERAGE DAILY UNIT POWER LEVEL                                        -
+i AVERAGE DAILY UNIT POWER LEVEL e
-e DOCKET NO. 50-366 DATE:         05-10-86 COMPLETED BY: Gary Koerber TELEPHONE      (912) 367-7851 x 2882 i
+DOCKET NO.
-MONTH 04-86 DAY     AVERAGE DAILY POWER LEVEL               DAY              AVERAGE DAILY POWER LEVEL (MWe-Net)                                                     (MWe-Net) l 1                 645                            17                            645
+-366 DATE:
-! 2                 645                            18                            646 i 3                 642                            19                            641 l 4                 638                           20                               7 l 5                 636                            21                            241 6                 641                           22                             541 7                 636                            23                            632 8                 636                           24                   -
+-10-86 COMPLETED BY: Gary Koerber TELEPHONE (912) 367-7851 x 2882 i
-9                 644                            25                              0 10                646                           26                               0 l 11                647                            27                              0 12                547                           28                             102 13                634                           29                             538 14                640                           30                             635 15                640 16                645 NOTE: Power level does not include station service used while shutdown.
+MONTH 04-86 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
+(MWe-Net) l 1
+17 645 2
+18 646 i
+642 19 641 l
+638 20 7
+l 5
+21 241 6
+22 541 7
+23 632 8
+24 631 9
+25 0
+646 26 0
+l 11 647 27 0
+547 28 102 13 634 29 538 14 640 30 635 15 640 16 645 NOTE:
+Power level does not include station service used while shutdown.
-_ _ _ _ _ . ..                           .m__     _ _ _ _ _ _       ._- _ _
+.m__
-UNIT SHUTDOWNS AND POWER REDUCTIONS
+UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
-* DOCKET NO.                            50-366                                                      UNIT NAME                       HATCH TWO COMPLETED BY                         Gary M.             Koerber                    TELEPHONE (912) 367-7851 (2882)                                        DATE      MAY 10, 1986 REPORT MONTH                       APRIL I                             i                      i    l             I     I                             I                            I       I                  I                                                l, I                             I                      l    l             1R l                                1                            iS      l                  l                                                l 1                             I                      I    I             IE I                                I                            lY      I                  l                                                l l                             l                      l T l              lA l METHOD OF l LICENSEE ISC l                                                             l                                                l.
+-366 UNIT NAME HATCH TWO COMPLETED BY Gary M.
-                            l                      lY I               IS l SHUTTING l                               EVENT              lTO l                      l      CAUSE & CORRECTIVE I                             I                      IP l DURATION lO I                DOWN                 l      REPORT                l ED l COMPONENT l                          ACTION TO I         NO.                 I    DATE              l E I     (HOURS) l N I         REACTOR                I      NUMBER                l ME l       CODE          I      PREVENT RECURRENCE                        l l                             l                      l    1             1     I                             I                            I       l                  l                                                l l                             1                      l    l             I     I                             I                            l       l                  l                                                l' I 86-016                      l 860401               iS l 266.45        lH I         5                      l N/A                        l ZZ    l   ZZZZZZ         l Management decision                            l~,
+Koerber TELEPHONE (912) 367-7851 (2882)
-I                             l                      l    l             1     I                             I                            l       1                  l to reduce power to                             l l                             l                      l    l             l     l                             l                            l       l                  l 85%.             High offgas                   l l                             l                      l    l             l    l                              l                            l       l                  l activity in Rx. and                            l I                              l                     l     l             l     l                             l                            l       l                  l Turbine building                               l l                             l                      1    l             l     l                             l                            l       l                  l caused by leaking fuell l                             l                      l    l             l     l                             l                            l       l                  l was slowing down Unit l l                             1                      1    I             I     I                             I                            I       l                  I One Outage Work.                               I I                              I                     I     I             I    I                              I                            I       I                  I                                                I I                              I                     I     I             I    I                              I                            I       I                  I                                                I I 86-017                      I 860412               lF i 11.55         lA l         5                      l N/A                        l HF    I   ELECON         I4160 Volt bus 2A,                               l l                             1                      I    l             l     l                             l                            l       l                  lrecirc pump 2A, and                             l' l                              l                      l    l             l     l                             l                            l       l                  l Circ Water pump 2A                             l 1                             l                     l     l             l     l                             l                            l       l                  ltripped.                                        l 1                              I                     I     I             I     I                             I                            I       I                  I                                                i!
+DATE MAY 10, 1986 REPORT MONTH APRIL j
-I                             I                     I     l             l     l                             1                            I       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 hours.
+I i
-D-Regulatory Restriciton                                4-Continuations E-Operator Training & License                            5-Load Reduction Examination                                            9-Other (Explain)
+i l
+I I
+I I
+I I
+l, I
+I l
+l 1R l 1
+iS l
+l l
+I
+I I
+IE I I
+lY I
+l l
+l l
+l T l lA l METHOD OF l LICENSEE ISC l l
+l.
+l
+lY I IS l SHUTTING l
+EVENT lTO l l
+CAUSE & CORRECTIVE I
+I IP l DURATION lO I DOWN l
+REPORT l ED l COMPONENT l ACTION TO I
+NO.
+I DATE l E I (HOURS) l N I REACTOR I
+NUMBER l ME l CODE I
+PREVENT RECURRENCE l
+l l
+l 1
+I
+I I
+l l
+l l
+l
+l I
+I I
+l l
+l l'
+I 86-016 l 860401 iS l 266.45 lH I 5
+l N/A l ZZ l
+ZZZZZZ l Management decision l~,
+I l
+l l
+I
+I l
+l to reduce power to l
+l l
+l l
+l l
+l l
+l l 85%.
+High offgas l
+l l
+l l
+l l
+l l
+l l activity in Rx. and l
+I l
+l l
+l l
+l l
+l l Turbine building l
+l l
+l
+l l
+l l
+l l caused by leaking fuell l
+l l
+l l
+l l
+l l
+l was slowing down Unit l l
+1
+I I
+I I
+I l
+I One Outage Work.
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I
+I I 86-017 I 860412 lF i 11.55 lA l 5
+l N/A l HF I
+ELECON I4160 Volt bus 2A, l
+l 1
+I l
+l l
+l l
+l lrecirc pump 2A, and l'
+l l
+l l
+l l
+l l
+l l Circ Water pump 2A l
+l
+l l
+l l
+l l
+l ltripped.
+l 1
+I I
+I I
+I I
+I I
+I i!
+I I
+I l
+l l
+I
+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 hours.
+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)
-UNIT SHUTDOWNS AND POWER REDUCTIONS                                                 -
+UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
-DOCKET NO.      50-366                                   UNIT NAME      HATCH TWO                                          ~
+-366 UNIT NAME HATCH TWO
-COMPLETED BY Gary M.      Koerber               TELEPHONE (912) 367-7851 (2882)           DhTE   MAY 10, 1986 REPORT MONTH        APRIL l
+~
-I          I            I     I         I     I                I           I      I              I                           I l          l            l     l         l R l                  l           lS     l              l                           l l          l            l    1          IE l                   l           lY     l              l                           l l          l            l T l           l A l METHOD OF l LICENSEE l SC l                        l                           l l          l            1Y l            l S l SHUTTING         l    EVENT  l TO I                I   CAUSE & CORRECTIVE l          l            l P l DURATION IO I          DOWN      l   REPORT  IED i COMPONENT I             ACTION TO I   NO. I    DATE    l E l    (HOURS) l N l   REACTOR       l  NUMBER   IME I        CODE     I   PREVENT RECURRENCE      I i          1            1     I         I     I                I           I      I              I                           I l          1            I     i         l     i                I           I      I              I                           l l 86-018   l 860413     lS l 166.02     lH I     5             l N/A       l ZZ   l    ZZZZZZ    l Management decision       l
+COMPLETED BY Gary M.
-, 1          l            l     l         l     l                l           l      l              l to reduce power to        l l
+Koerber TELEPHONE (912) 367-7851 (2882)
-l          l            l    l          l     l                1           l      l              l 85%. High offgas          l l l          l            l     l         l     l                l           l      l              l activity in Rx. and       l l l          l            l     l         l     l                l           l      l              l Turbine building          l l l          l            l     l         l     l                l           l      l              l caused by leaking fuell l          l            l    l          l     l                l           l      l              l was slowing down Unit l l          1            I    I          I     I                I           I      I              I One Outage work.          l I          I            I    I          I     I                I           I      I              I                           I I 86-019   I 860420     IF l 28.15      l A l          3       1 2-86-9    l IA   l INSTRU        l Rx Scram on erroneous !
+DhTE MAY 10, 1986 REPORT MONTH APRIL l
-l          l            l    l          l     l                1           I      l              l MSR A high level.         I I          I            I    I         I      I                I           I      I              I                           l l 86-020   l 860421     l S I 10.45     i B l          5       l 2-86-9    l IA    l INSTRU       l Scram Recovery           I' I          I            I    I          I     I                I           I      I               I                          I 1 86-021   l 860421     l F l 29.38     lA l           5       l    N/A    l CH   l TURBIN       I RFPT 2B tripped           l l          l            l    1          1     I                I           I      I               I                          I l          l            1    I          l     l                1           1      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 hours.
+I I
-l                  D-Regulatory Restriction                4-Continuations E-Operator Training & License           5-Load Reduction Examination                           9-Other (Explain)
+I I
+I I
+I I
+I I
+I l
+l l
+l l R l l
+l S l
+l l
+l l
+l 1
+IE l l
+lY l
+l l
+l l
+l T l l A l METHOD OF l LICENSEE l SC l l
+l l
+l 1Y l l S l SHUTTING l
+EVENT l TO I I
+CAUSE & CORRECTIVE l
+l l P l DURATION IO I DOWN l
+REPORT IED i COMPONENT I ACTION TO I
+NO.
+I DATE l E l (HOURS) l N l REACTOR l
+NUMBER IME I CODE I
+PREVENT RECURRENCE I
+i 1
+I
+I I
+I I
+I I
+I l
+I
+i l
+i I
+I I
+I l
+l 86-018 l 860413 lS l 166.02 lH I 5
+l N/A l ZZ l
+ZZZZZZ l Management decision l
+l
+l l
+l l
+l l
+l l to reduce power to l
+l l
+l l
+l l
+l 1
+l l
+l 85%.
+High offgas l
+l l
+l l
+l l
+l l
+l l
+l activity in Rx. and l
+l l
+l l
+l l
+l l
+l l Turbine building l
+l l
+l l
+l l
+l l
+l l
+l l caused by leaking fuell l
+l l
+l l
+l l
+l l
+l was slowing down Unit l l
+I
+I I
+I I
+I I
+I One Outage work.
+l I
+I I
+I I
+I I
+I I
+I I
+I 86-019 I 860420 IF l 28.15 l A l 3
+2-86-9 l IA l INSTRU l Rx Scram on erroneous !
+l l
+l l
+l l
+I
+l l MSR A high level.
+I I
+I I
+I I
+I I
+I I
+I l
+l 86-020 l 860421 l S I 10.45 i B l 5
+l 2-86-9 l IA l INSTRU l Scram Recovery I'
+I I
+I I
+I I
+I I
+I I
+I 1 86-021 l 860421 l F l 29.38 lA l 5
+l N/A l CH l TURBIN I RFPT 2B tripped l
+l l
+l 1
+I
+I I
+I I
+I l
+l 1
+I l
+l 1
+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 hours.
+l 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)
-UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.      50-366                                                   UNIT NAME             HATCH TWO                                               '
+UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
-COMPLETED BY Gary M.       Koerber                              TELEPHONE (912) 367-7851 (2882)                DATE    MAY 10, 1986 REPORT MONTH       APRIL I          I             i      l                   I     I                      I                I       I            I                                     I I          I             I      I                   IR I                         I                IS      I            l                                     l l          l             1      I                   IE I                         l                1Y      l            l                                     l l          i             l T l                      l A l METHOD OF l LICENSEE l SC i                                  i                                     i l          l             l Y l                      l S l SHUTTING               l    EVENT       l TO I               l   CAUSE & CORRECTIVE                l l          l             l P I DURATION l O I                         DOWN       l   REPORT       l ED l COMPONENT l             ACTION TO                   l l   NO. I   DATE      IE i (HOURS) lN I                          REACTOR      l   NUMBER       IME l      CODE          PREVENT RECURRENCE                I I          i             1      l                   1     I                      I                I       l                                                  l l          1             I      l                   l     l                      l                l       l            l                                     l l 86-022   l 860424      i F l     85.03            l A l           3            l 2-86-10        l HA    I GENERA     I Excessive condensationl l          l             l      l                   l     l                      l                l       l            l in the Generator                    i i i          l             l      I                   I     l                      l                l       l            l Excitor caused a                  'l
+-366 UNIT NAME HATCH TWO COMPLETED BY Gary M.
-! l          I             l      l                   l     l                      l                l       l            l Generator Field Groundl l l          l             l      l                   l     l                      l                l       l            l and subsequent turbinel l l          l             l      l                   l     l                      l                1       l            l trip. Source of                 l 1 l          l             l      l                   l     l                      l                l       l            l condensation was an                 l l 1          l             l      l                   l     l                      l                l       l            l approximately 18"                   l l l          l             l      l                   l     l                      l                l       l            l rupture in the 6th                  l l          l             l      l                   l     l                      l                l       l            l stage "A" extraction                l l 1          1             I      l                   l     l                      l                1       I            I line.                               l l l          l             l      1                   1     I                      I                I       l            1                                     l l
+Koerber TELEPHONE (912) 367-7851 (2882)
-l 86-023   l  860428     l S l     29.40            lB l               5         l 2-86-10        l HA    l GENERA     l Scram Recovery.                     1 l          I             I      I                   I     I                      I                I       I            I                                     l l 86-024   I  860429     l S l     2.9.00           l H I              5         l    N/A         l ZZ    l ZZZZZZ      l See 86-016.                        l l          l             l      1                   1     I                      I                I       l             l                                    l F: Forced        Reason:                                                 Method:                                   Events reported involve l 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 hours.
+DATE MAY 10, 1986 REPORT MONTH APRIL I
-D-Regulatory Restriction                                4-Continuations E-Operator Training & License                           5-Load Reduction Examination                                           9-Other (Explain)
+I i
+l I
+I I
+I I
+I I
+I I
+I I
+IR I I
+IS I
+l l
+l l
+I
+IE I l
+Y l
+l l
+l i
+l T l l A l METHOD OF l LICENSEE l SC i i
+i l
+l l Y l l S l SHUTTING l
+EVENT l TO I l
+CAUSE & CORRECTIVE l
+l l
+l P I DURATION l O I DOWN l
+REPORT l ED l COMPONENT l ACTION TO l
+l NO.
+I DATE IE i (HOURS) lN I REACTOR l
+NUMBER IME l CODE PREVENT RECURRENCE I
+I i
+l
+I
+I I
+l l
+l 1
+I l
+l l
+l l
+l l
+l l 86-022 l 860424 i F l 85.03 l A l 3
+l 2-86-10 l HA I
+GENERA I Excessive condensationl l
+l l
+l l
+l l
+l l
+l in the Generator i
+i l
+l I
+I l
+l l
+l l Excitor caused a
+'l i
+l I
+l l
+l l
+l l
+l l Generator Field Groundl l
+l l
+l l
+l l
+l l
+l l and subsequent turbinel l
+l l
+l l
+l l
+l 1
+l l trip.
+Source of l
+l
+l l
+l l
+l l
+l l
+l condensation was an l
+l 1
+l l
+l l
+l l
+l l
+l approximately 18" l
+l l
+l l
+l l
+l l
+l l
+l rupture in the 6th l
+l l
+l l
+l l
+l l
+l l stage "A" extraction l
+l 1
+I
+l l
+l l
+I
+I line.
+l l
+l l
+l 1
+I
+I I
+l 1
+l l
+l 86-023 l
+l S l 29.40 lB l 5
+l 2-86-10 l HA l
+GENERA l Scram Recovery.
+l
+I I
+I I
+I I
+I I
+I l
+l 86-024 I
+l S l 2.9.00 l H I 5
+l N/A l ZZ l
+ZZZZZZ l See 86-016.
+l l
+l l
+1
+I I
+I l
+l l
+F: Forced Reason:
+Method:
+Events reported involve l
+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 hours.
+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)
-y                                                                                                  )
+)
-          , Georgia Fbwer Company
+y Georgia Fbwer Company j
-* j
+Piedmont Avenue Attarsta, Georgia 30308 Telephone 404 526-6526 l
-,-          333 Piedmont Avenue
+Maihng Address:
-   .        Attarsta, Georgia 30308 Telephone 404 526-6526                                                                     l Maihng Address:
+Post Office Box 4545 Atlanta, Georgia 30302 Georgia Power L. T. Gucws l' " "''' "" " *I' W #" "
-Post Office Box 4545 Atlanta, Georgia 30302 Georgia Power L. T. Gucws                                                      l' " "''' "" " *I' W #" "
+Manager Nuclear Safety and Licenstrig May 14,1986 Nuclear Operations NRG Monthly Operating Report File: X7GJ10-H000 Log: SL-741 Director Office of Management and Program Analysis U. S. Nuclear Regulatory Commission Washington, D. C.
-Manager Nuclear Safety and Licenstrig May 14,1986 Nuclear Operations NRG Monthly Operating Report File: X7GJ10-H000 Log: SL-741 Director Office of Management and Program Analysis U. S. Nuclear Regulatory Commission Washington, D. C. 20555
 ==Dear Sir:==
+Enclosed is the NRC Monthly Operating Report for Hatch Unit 1, Docket Number 50-321, and for Hatch Unit 2, Docket Number 50-366.
-Enclosed is the NRC Monthly Operating Report for Hatch Unit 1, Docket Number 50-321, and for Hatch Unit 2, Docket Number 50-366. This report is submitted pursuant to Technical Specifications Section 6.9.1.10 Sincerely,                                1 b
+This report is submitted pursuant to Technical Specifications Section 6.9.1.10 Sincerely, 1
-y    L. T. Gucwa EBS/lc Enclosure c: Mr. J. P. O'Reilly Mr. J. T. Beckham, Jr.
+b L. T. Gucwa y
+EBS/lc Enclosure c: Mr. J. P. O'Reilly Mr. J. T. Beckham, Jr.
 Mr. H. C. Nix, Jr.
-NRC-Region II                                                                    i GO-NORMS                                                                         1 YN
+NRC-Region II i
-                                                                                                  *b    l T
+GO-NORMS 1
-C                                                                                 I[}}
+YN
+*b T
+C I[}}

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