. .

OPERATING DATA REPORT

DOCKET NO. 50-321DATE 7-5-79

CO.\1PLETED BY P. B. AllenTELEPHONE 9Id-30/-/78l

OPERATING STATUS

1. Umt Nime: Hatch - 1 N ''S

2. Reporting Period: . June 1979

3. Licenssd Thermal Power (5tht): 24364. Nameplate Rating (Gross 31We): 809.35. Design Electrical Rating (Net .\lWel: 786.36. Sf aximum Dependabk Capacity (Gross SIWE): 7A4. 37. Sf aximum Dependable Capacity (Net SIWel: 73l 3S. If Chan' es Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:g

9. Power Lesel To which Restricted. If Any (Net alwe):10. Reasons For Restrictions. If Any:

This 51onth Yr..to.Date Cumulatis e

11. Hours In Reporting Period 720 4343 4204912. Number Of Hours Reactor Was Critical 0 2449.9 30897.113. Reactor Reserse Shutdown Hours 0 0 014. Hours Generator On.Line 0 2414.1 28414.815. Unit Reserve Shutdown Hours 0 0 016. Gross Thermal Energy Generated (51WH) 0 5492776 5508856117 Gross Electrical Energy Generated (5thH) O__ , _ . 1798940 178492271lb. Net Electrical Energy Generated I.\lhH) -3341 1711600 1698349319. Unit Service Factor 0 55.6 69.520. Unit Availability Factor 0 55.6 69.521. Unit Capacity Factor (Using \lDC Net) 0 53.9 56.3.

22. Unit Capacity Factor (Using DER Net) 0 50.1 52.323. Unit Forced Outage Rate 0 9.5 17.a24 Shutdowns Scheduled Oser Nest 6 \1onths (Tspe. Date.and Duration of Each):

25. If Shur Down -\t End Of Report Period. Estunated Date of Startup: 8-I-7926. Umts in Test Status (Prior to Commercial Operation p: Forecast -\chie s ed

INITI \L CRITICALITYINITI \ L ELECTRICITYCO\l\tERCIA L OPER ATION

340 062 -

7 9 0717 0 RM ._

..

AVERAGE D AILY UNIT POWER LEVEL

DOCKET NO. 50-321

UNIT Hatch - 1 _DATE 7-5-79

CON 1PLETED BY P. B. Allen

TELEPHONE 912-367-7781

stONT11 June 1979

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POhER LEVELOlbe-Net) ( .\t We-Ne t )

1 -5 17 -5

2 -418 -5

3 -5 19 -54 d 20 -55 -5 ZI -5

~

6 -

22 -57 -5 23 -5

S -5 24 -59 -5 25 -4

10 -5 26 -a!1 -5 27 _a

1: -528 d

13 -529 _4

14 -5 30 -4-

15 -33 _4

16 -5

INSTRUCTIONS

On this tormat.hst the aura;: Ja:h un.t power lese! in \tWe. Net for each by :n the repor m; nonth. C.unrute nithe r.earest whole me;2 wart.

pu- i

340 063.

.me et.bre-. =d

s

UNil SillllDOWNS AND POWEli ItEDUCllONS DOCKLTNO. 50-321.

UNil NAME H<l.tch - 125-79DA~IE

COMPLE I ED 11Y P. B. AllenItEPOlt I MON ill _dunn 1979 .l EllPilONE 912-162-Z231.

'l -

-- } h 11ctisce [ 't, Q CJuse d CorrettiseNo. Dale i 33 i j55 1: vent L] gL3 Action to

Iteport u (E U Psevent iteturienteyE 5 y jy3H = 0g u-

6

79-10 790422 S 720 C 1 ft/A ZZ FUELXX Shutdown to facilitate refueling

U44O

OON4

1 2 3 4I I onced Iteason : Method: 1.xlubit G Instiut tionsS Ss hed ulcil A Iiiuipinent Failure (Explain) 1 Maiiual fin Prepaiatio:; of Data

Italaintenance or Test 2 Manual Serain. Eni 3 Sheets foi I AenseeC-Itefuchng 3- Autonulie Sesain. Lient Itepori (l.I'It)I ile t Nilit! G-D Itegulato > itesititlion 4 Olhes (I xplani) 0161)i Operator Training & lice"w I:ror '::ationl'- Ad illillist r Jllb e bG Operat:onal 1 iros (l:xplain) Esinbii ! Saine Source

01/77) 11 Other (I splani)

!

L

,

NARRATIVE REPORTUNIT I

Jur.e 1970 Cold Shutdown for Refueling

Folicwing the compilation of Health Physics Dosimetry Records for theprevious month, it was found that twenty-five employees receiveddoses exceeding 10% of our annual allowable limits. The exposureswere received as a result of cladding removal in the reactor vesseland were recorded as fo'llows:

Ecoloyee mr Employee er

1 1473 14 1609

2 1378 15 1470

3 1238 16 1357

4 1485 17 1586

5 1609 18 16t,

6 1432 19 1952

7 1266 20 12ch

8 1208 21 1451

9 1643 22 1438

10 1226 23 1300

11 1267 23 1450

12 1400 25 1986

13 1559

340 065

.-

HATCH 1 SAFETY - RELATED MAINTENANCE REOUESTSTO BE REPORTED FOR JUNE 1979

NUMBER DATE COMPLETED DESCRIPTION79-2572 6-1u-79 Cleaned and disassembled

isolation valves to C4scram level switch en1Cll-N0l?C

73-3407 6-19-79 Reinstalled T48-R/I-K080/81per DCR 77-298

70-1237 4-26-79 Fabricated gussets en MSRHangers for DCR 77-98

79-2165 6-19-70 Inspected and recaired LLRTValve on IEul-F003

79-1913 6-10-79 Replaced ring and centereddis c on RHR Pump SucttenValve

79-2675 6-14-70 Lapped gate and cleanedIsolation Valve to "D"

scram level switch, andreplaced old gasket

70-2674 6-la-79 Lapped gate and cleanedIsolation Yalve to "B"

scram level switch, and.

replaced old gasket

79-2673 6-14-79 Lapped gate and cleanedIsolation Valve to "A"scram level switch, andreplaced old gasket

79-1C80 6-10-70 Changed Inboard "B" LineMSIV B21-F0223

79-2092 6-1-70 Repaired Min. Flow CheckValve lE51-F021

79-2428 5-30-79 Installed Isolatten (2)Valve, 2 stainless steeltee's a*d tubing for testconnectiu..3 Gil-M012

79-2218 6-5-70 Changed AutomaticIsokinetic Panel 1Dil-P020

340 056

.

79-3026 6-2-79 Replaced 1" Relief Valveon air manifold block1-B21-MSIV

79-1323 6 4-79 Relocated piping as DerDCR-78-162

79-750 6-10 70 Set breakers andrecorded secoints onrelaving data sheetsLEA-R24-S013A

79-2503 6 4 79 Installed 203 VAC powercables as per DCR-79-273

79-2507 6 4-79 Installed 203 VAC per

DCR 79-239

79-2501 5-30-79 Connected temocrary

cables to 1R20-S001120/203 V DistributionPanel for core drillpower as per DCR 79-23u

79-2285 6 a 79 Restored wiring recovedfrom lE51 ?i601A&B by DCR

79-158-Rev. 0

79-2286 6-9-79 Restored wiring removedfrom 1 E41-!I601A&B bvyDCR 79-159, Rev. 0

79-2862 6- 11- 74 Changed setpoints a ceraccounting room requeston 1Dil-R619B

79-2269 6-11-79 Filed all her.d nuts andremoved indicatior.s withthe exceptions of #13and 46

78-1425 6-12-70 Welded in valves andvalves were P.T. testedby CC and welds wereHvdro tested C11-N013A-D

7?-1313 6-10-70 Checked all positions ofCentrol Rod 32-11

79-1312 6-14-79 Checked all positions ofControl Red 24 47

79-13;l 6-14 79 Checked all positions ofControl Red 22 37

340 067

..~

79-1310 6-14 79 Checked all positions ofControl Rod 10 10

79-1479 6-26-79 Performed lead dischargetest on lA Sta. Sev.

79-3153 6-23-79 Repaired gear box andflange bearing 1L48-R64A

79-3270 6-23-70 Repaired AnnunciatorAlarm "Hp Analvter"IN62-P600

79-3357 6-24-79 Checked annunciator byhaving operator put modeswitch in test position1H11-P652

79-3253 6-23-70 Replaced bad point cardon Control RoomAnnunciator Panel Alarm1Hil-P650

79-3119 6-23 79 Cha" tad card cut anderoblem resolved itselfon panel H11-P654

79-3136 6-27-79 Tightened alarmconnection en back of

.meter relay 1-Gil-P001

79-2163 6-13-79 Recoved and repaired

steam to RCIC IsolationVa'.ves 1E51.-F007/F003

79-1256 6-22-79 Cleaned off weld withwire brush en air endgrinder 1-Eul-G001

79-2980 6-25-79 Replaced broken vanes onMain , Stack Sample Pump1Dil-P0013

79-3388 6-27-74 Tested Rod Scram Testswitch and repairedshorted wire going to

the solenoid 1C11-18-35

79-2995 6-23 79 P.T- inscecticn ofC.R.D. 1911-A001

79-1903 6-22-79 Repaired fabricatedshield plug

340 068

__ ...M

Georg:a Power CampanyPost O'f:ce Bcx 442Bax'ey Georg:a 31513Teteprone 912 367-7781

912 537-9444

mCOrga PowerEdw n 1. Hatch Nuclear Plant

rN out>m t~c c mreen

July 9, 1979

PM-79-610

PLANT E. I. HATCHNRC Monthly Reoort

Docket No. 50-366

Office of Plans and SchedulesDirectorate of LicensingU.S. Nuclear Regulatory Com:nission'4ashington, D.C. 20535

Dear Sirs:

Pursuant to Section 6.9.1.6 of the Hatch Unit 2 TechnicalSpecifications, please find attached the NRC Monthly OperatingReport.

M. Manry

Plant Manager

MM/peb

xc: C. T. MooreT. V. GreereFile

340 069

OPERATING DATA REPORT

DOCKET NC. 50-366DATE /~U-'1

CO.\tPLETED BY P. 6. nllenTELEPilONE 01'-367-7781

OPERATING STATUS

1. Unit Name: Hatch - 2 Notes

2. Reporting Period: June 19793. Licensed Thermal Power (.\lWt): 24364 Nameplate Rating (Gross 51Wel: 8l75. Design Electrical Rating INet .\lWe): 784

o. Staximum Dependable Capacity (Gross SlWe): 749

7. .\lnimum Dependable Capacity (Net .\1We): 7IO

S. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report. Cise Reasons:

9. Power Level To which Restricted. If Any (Net .N!Wel:10. Reasons For Restrictions. If Any:

This .\lonth Yr..to Date Cumularis e

11. Hours In Reporting Period 720 4343 876012. Number Of Hours Reactor Was Critical 509.7 934.9 3567.413. Reactor Resene Shutdown Hours 0 0 014. Hours Generator On Lme 260.9 544.4 193115. Unit Resene Shutdown Hours 0 0 016. Gross The mal Energy Generated . \tWH) 504955 920070 _2_92601117 Gross E!ectrical Energy Generated I.st% H) 120460 _ _ _ . 235010 77161015. Net E'ectrical Energy Generated t..\1WH) 108593 200428 69396019. Unit Senice Factor N/A N/A N/A20. Unit Asailabiiity Factor N/A N/A N/A21. Unit Capacity Factor (Using .\tDC Net) N/A N/A N/A22. Unit Capacity Factor IUsing DER Net) N/A N/A23. Unit Forced Outage Rate N/A N/A

-"!

N/A24. Shutdow n3 ScheJ.aed Oser Neu o \tonths (T)pe. Daie.and Duration of Each L

25. If Shut Down \t End Of Report Period. Estunated l> ate of Startup-26. Units in Test Status (Prior to Commercial Operation t Forecast Achies ed

INIT!T L CllTICA LITY 7-4-73INITl \L ELECTRICITY 9-22-78CO\litERCI \L OPER \ TION 8-23-79

340 070 I"'->

--

AVERAGE DAILY UN'T POWER LEVEL

DOCKET NO. 50- 366.

LWIT Hatch - 2

DATE 7-5-79

CO\tPLETED BY P. B. Allen

TELEPHONE 912-367-778l

.Nf0 NTH d '1'"2 1979

DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE D\lLY POWER LEVEL(\1he-Net) i SIWE-Net )

1 211i- 374

2 459is 576

3 48019 27

4 -14 20 -18s _ -11

21 -176 -Il

22 8l7 19

23 -178 73 24 11

9 -I25 471

10 2626 708

11 -10 27 369

12 -122s -10

13 46 :9 -11

14 29739 -11

15 52733

to 42

INSTRUCTIONS

On uns :ornut. ia: he a. ' rage a :. urn: pow er .e.m ;.; it '\ e '- :.;r uh Ls.>tht * pemn: m h.Co m;' ' 'oth0 r;CJICSI A hU!e ;":' TAat t_

n -i

340 071

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-

.

NARR ATI'E REPCRTUNIT II

June 3 Startup Testing

June 6 Rx Scram en Low Water Level 1947 CST

June 10 On Line 0502 CST

June 10 Turbine Trip en Low Vacuum 1106 CST

June il On Line 13hl CST

June 15 Ex Seaam en APRM Upscale Trio 2113 CST

June 16 Cn line 1608 CST

June 19 Rx Scram on TCV Fast Closure Load Rejection Test

June 22 on line 0535 CST

June 22 Rx Scram Due to Gen. Diff. Aux. Lockout Relays1403 CST

June 24 On Line 1735 CST

June 27 Rx Scram on MSI7 test 1210 CST

There was no single release of radioactivity or single radiationexposure which accounts fer more than 10 percent of the allowableannual values during the previous acnth of 19"9.

.

340 073

. _ _ _ . . - . . -

.:a -a ?. an::a. - :. u ., . . . a .a - . . . . . , . . ~ .n-. .

TO BE REPORTED F0h JUNE l'17o

NUMBER DATE COMPLETED DESCRIPTION

70-2462 9-20-70 Reolaced GE 130 meteaswith Sigma meters andcalibrated instrumentsR612A'c3

70-2603 5-20-70 Vented MSIV LC P-essuretransmitters during mainsteam line

pressurization

2332-N061B

79-2511 6-1 70 Replaced two Impellers2 Ell-C001D

79-2430 5-25-70 Removed H anger "od andpositioned clamp to a

vertical position andreassembled Hanger2E11-RHR-H178

79-2473 5-31-79 Installed resistors asper DCR 79-227

79-2463 5-29-79 Replaced GE 180 meterswith Sigma meters andcalibrated 2 Ell-P071

79-2238 5-30-70 Recalibrated 2C32-N004Cin accordance to

H'IP-2-9210 and DCR

79-130 2C32-N003C

79-2091 5-25-70 Installed thermocouoleand hooked up 2B21-F011A

79-1794 5-30 79 Replaced Pilot CartridgeAssembly after benchtesting of CartridgeAssembly was comoleted

2-321-70133

79-2379 5-30-70 Removed temporary cablesfrom panel 2R25-S037

70-25c5 6-7-77 Recolled paper to

Multiorint VentilationTemperature recorder andreseated it properly

2T47-R612

70-2336 6 4-79 Checked line voltage on

cables (203) volts

2R~5-S035

79-2326 5-30 71 Tenocrarily ran two

cables (908vi feca

2R25-309" braakers 7 's oand 10 5 12 as per DCR

k 79-l09

- -. . . _. .

79-290' 4 4-70 Built two DQttal to Analog- -

Converters 2F-1-2331-C001

vo_1391 6-12-79 '< ounted Terocrary Optical

Detectors to Rectrc. Pumps A%B per DCR 7') 84

79-2621 A-11 79 HPCI condenser vacuun pumu2E41-C002

79-2090 6-3-79 Disassembled RHR/C.S. JockeyPu=o, "eplaced worn parts,reasembled outo and returnedto service 2E21-00033

79-2513 6-9-79 Replaced RER Flow transmittersper DCR 79-215

79 434 6-3 79 Replaced RPIS probe, checkedall logic in RPIS Cabinet bysimulating inputs at rear ofpanel for 2Cll-26-15

70-2007 6-9-79 Changed out Columbia DS 3000LVDTS with 500 seriesSchaevit: L7DTS per temp. DCR78-442

79-2313 5-30-79 Installed 3 each 2-oole 20 ampcircuit breakers and rancable? per DCR 70-103

79-2317 5-?0 77 Installed 40 amp 2-polebreaker and ran cable per DCR70-192

79-1492 6-14-79 Completed wiring as shown onDCR 78-110

79-2866 6-8-79 Welded nut to disc andinstalled disc: valve didn'tpass LLRT, therefore,disassenbled valve, lapped

-

seat and reassembled valvepassed test 2F51-F040

79-1363 5-6-71 Recoved re is tors andfabricated limiter andadjusted per DCR 79-80 andFDDRHT-2-3SS, Rev.1

79-2024 6-14-70 Replaced breaker en HPCI PumpSuction frca SucpressicnChamber and repaired looseconnection at motor 2Eul-F041

79-2015 6-13-70 Replaced motor to SucticnValve fren Torus 2E21-F041

340 0/5. .___ - - . _. ._d

70-2310 6-21 77 Welded vent line valve back inplace 2E11-FV003

79-1362 5-29 70 Removed 100 Ch7 resistors andclosed B355 and BB56 in2HH-?612. Fabricated andinstalled limiter on controlamplifier. 2Eul-K615

79-546 6-2-70 Replaced Seal Water InletLine, and fittings 2 Ell-C001 D

79-2420 6-12-79 Terminated wire at braaker#24 2R25-S106

79-611 6-11-70 Implemented DCR 2-77-221

79-2885 6-11-70 Reolaced field Oinding of HPCIVacuum Tank Condensate Pump2Ehl-C002-1

79-2327 6-6-79 Assembled R?3/MG Set BreakerPanels and wired per DCR 78-410

78-5351 6-12-79 Implemented DCR 78 48?, cutcut res tra int No. 153,grinded down smooth andrawelded assembly per Bechtelprocedure 2B11-G003

79-2350 6-12-79 Temporary instrumentsinstalled and calibrated perDCR 70-130

79-1204 6-13-70 Implemented temocrary DCR70-117 which installs paessuretranducers on the SR7Tailpipes 2B21-F013A-K, K-M

78-2867 6-25-77 Installed a T/Cs in Drywell 2on Rx Insulation at

Sacrificial Shield and 2 inair cap 1800 apart andrelocated 2T47-N002 and N0102T47-N001A&K

79-3059 6-2a-79 D isa sse=bl ed standby PSW PumpDischarge Strainer InletIsolation Valve and turnedo"e= 2?41-F 335 A

70-3053 6-24-70 Dicassembled Standaby PSW PunoDischarge Strainer OutletIsolation 7alve and turnedover 2?41-F136A

340 076, -. -- ._

.

70-3033 6-24 79 Reversed standby PSW PunoDisch. Strainer OutletIsolation 7alve position is

clossed when showing closed2P41-F336A

70-3012 6-24-70 Reversed Standbv PSW PunoDisch. Strainer InletIsolation Valve position is

closed when showing closed2Pul-P775A

70-2896 6-24-79 Retacoed indicator holes ofDIV1 PSW Strainer Back WashValve and placed indicator inright position 2P41-F313D

79-3003 6-27-70 Fixed contacts and alarmwi"ing on Recombiner Tenp Hiand Low Annunciator 2N62-P600

79 423 6-26-70 R ecalib ra ted HPCI Aux. OilPump-Auto Start PressureSwitch PS-1

79-3031 6-22-79 Changed setpoints on MainSteam Line Rad. Monitor A perHNP-2-5100

79-2950 6-22-70 Calib rated MSL Hi and HiHi tonew setoonts 2DilK603A,9,C,and D

70-2962 6-23-70 ILnstalled 120 VAC outlet with19 AMP fuses as per DCR 79-100

79-3052 6-23-79 Investigated and repaired MSIVLCS Inboard Depresurization

Valve 2E32-F0033

79-2''75 6-22 70 Changed Oil and filters,flushed lines, visuall.vinspected bearings and gea"reducer and repaired waterlines in HPCI turbine E41-C002

79-2882 6-22-79 Investigated and repaired HPCIVacuum Pump; found looseconnection on shunt field2Eul-0002-2

70-2998 6-26 79 Inspected lube oil system onHPCI turbine and added 110enllons of oil to resevoir

340 077..- .. - __ _ ..

.