ML20207C722

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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)
v • d • e


Text

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j se l . NARRATIVE REPORT '

i 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.

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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.

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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.

Ref. DCR 85-120.

4 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.

1 86-1623 04-21-86 Reterminate cable "

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.

d Ref. DCR 86-058.

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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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l AVERAGE DAILY UNIT POWER LEVEL 'i j

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DOCKET NO. 50-321 1 DATE: 05-10-86 ,

COMPLETED BY
Gary Koerber j

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

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, DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I (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 4 5 0 21 0  :

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

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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 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

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. 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.

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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I HATCH 2 SAFETY-RELATED MAINTENANCE -WORK ORDERS l

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TO BE REPORTED FOR APRIL 1986 i NUMBER. DATE COMPLETED DESCRIPTION

, 83-0429 04-10-86 Install conduit 2MB0441, 2MB1356,7,8,9 l 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 4 system 2T43130WO6.

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.

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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.

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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.

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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 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.

1 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~,

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!

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

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 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

, 1 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 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 !

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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 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

! 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

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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

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

y L. T. Gucwa 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 l T

0537C I[

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