ML20094P898

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Monthly Operating Repts for Jul 1984
ML20094P898
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 07/31/1984
From: Nix H
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
GM-84-677, NUDOCS 8408200001
Download: ML20094P898 (15)
v • d • e


Text

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NARRATIVE REPORT UNIT 1 July 8th 0107 Load reduction from rated thermal power to 689 GMWe for weekly turbine test (HNP-1-1053).

July 6th 0320 Turbine testing complete.

Returning to rated power.

July lith 2105 Load reduction to approx. 350 GM W'e to invesigate problems with 1A circ. water pump.

July 12th l

0550 1A cire. water pump problems resolved returning to rated power.

July 12th 0905 Power increase discontinued at 720 GMWe to adjust APRM gains.

July 12th 0925 APRM gains set increasing power to 730 GMWe via recirc flow.

July 12th i

0935 Power increase discontinued for P-1 run at 730 GM W'e.

July 12th 0947 Increasing to rated power via recirc flow.

July 13th 2130 Load reduction via recire flow to

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500 GMWe for weekly turbine testing and rod pattern adjustment.

July 14th 0105 Turbine testing complete.

July 14th 0233 Rod pattern adjustment complete.

July 14th 0509 Increasing power to 495 GMWe via recirc from a xenon depressed power level of 471 GMWe.

July 14th 0517 Power ascension terminated at 496 GMWe.

July 16th 0830 Process computer inop.

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NARRATIVE REPORT UNIT 1 July 16th 1613 Process computer restored to service.

July 20th 2040 Reducing power via recirc flow to 649 GMWe.

6 fans tripped on "C" cooling tower, 3 fans tripped on "B" cooling tower.

July 20th 2115 "B" cooling tower fans restarted.

July 20th 2117 "C" cooling tower fans restarted.

July 20th 2321 Increasing power via recirc flow.

July 28th 0008 Ioad reduction to 720 GMWe for weekly turbine tecting.

July 28th 0208 Turbine testing complete, increasing power via recire flow.

July 28th 0850 load reduction to. 700 G4We for control rod exercise (HNP-1-3939).

July 28th 0909 Control rod exercise complete, increasing load back to rated, w,a l

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NARRATIVE REPORT UNIT 2 July 1st 0000 Recirc Piping Outage still in progress.

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HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR July 1984 NUMBER DATE COMPLETED DESCRIPTION 84-2832 06-27-84 Rebuilt CO2 discharge valve 1Z43-F007 in cable spread and computer rooms.

Ref. DCR 84-093.

84-2826 06-28-84 Rebuilt 002 discharge valve 1X43-F011 in diesel building.

Ref. DCR 84-093.

84-2830 06-27-84 Rebuilt 002 discharge valve 1Z43-F0ll in cable spread & computer rooms.

Ref. DCR 84-093.

82-7165 05-24-83 Fabricated & installed reinforcement steel in panel pads in control bldg., el.

164'-O".

Ref.80-348.

82-6191 11-29-82 Fire alarm system control bldg., el. 164'-0" pull in and lugged cable Z43-P001-M24.

Re f. DCR 80-348.

83-7635 11-22-83 CRD vents and drains.

Replaced existing Cll-F110 A,B type NP8316 E3 6E, 125 VDC solenoid valves.

Re f.

DCR 83-3 2.

83-6027 08-13-83 Replaced inoperable Barton transmitter with Rosemont 1151-RHR "A" Loop flow.

Ref. DCR 83-157.

Z" 84-2683 05-22-84 Rebuilt 002 discharge valve 1Z43-F007, F008, F011 in cable spread and computer room.

Ref. DCR 84-093.

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HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO -BE REPORTED FOR July 1984 NUMBER

'DATE COMPLETED DESCRIPTION

~83-4935 01-13-84

. Pulled cables RPlA05C28, RPlB04C28, RP2A04C28, RP2B05C28, RPlA05C29, RP1B04C29, RP2A04C29,

'RP2B05C29 on reactor protection system / scram discharge' volume.

Re f. DCR 82-220, 83-1519 04-18-83 Install flex hose 2T48-00018 on containment purge & vent and hydrogen inerting system.

Ref. DCr 82-076.

83-2877 06-08-83 Overlayed pipe to pipe weld 2B31-IRC-12BR-E4 on recirc -

loop B, riser E.

Ref. DCR 83-083.

82-1986 04-19-82 Replaced existing recirc pump B seal water FCV with new model.

.Ref. DCR 82-5 4.

83-4126 08-05-83 Lighting in airlock el.

164'-0".

Core drilled 2" hole in SSO kitchen &

installed rigid steel sleeve, installed ALS and ground cable, receptables and lig'nts in airlock.

Ref.

DCR 80~348.

84-1234 07-12-84 Installed air piping and pipe supports for automatic operators on the manually operated valves in RWCU valve nest room for reactor water cleanup system.

Re f.

DCR 83-86.

84-1690 05-14-84 Changed out H 022 analyzer panels, bottle racks; installed cabinets, circuit breakers, tubing, raceway and cables.

Ref.

DCR 81-165.

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  • HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR July 1984 NUMBE R DATE COMPLETED DESCRIPTION 84-1681' 05-11-84 Diesel generator 2C air start sy st em.

Fabricated and installed tube support, stainless steel and copper tubi ng.

Removed existing pressure switches and installed 2 new pressure switches.

Ref. DCR 80-98.

8,3-2641 06-04-83 Revised reactor bldg.

nitrogen inerting system isolation valve actuator orie nt ation.

Ref. DCR 83-51.

83-1131 05-27-83 RHR system installed pipe support 2 Ell-RHR-H719.

Ref.

DCR 82-76.

83-2438 07-08-83 Re-installed main steam safety / relief valve 2B21-F013L hady, topworks and solen?id.

Ref. DCR 82-53,. 1R 83-25.

84-2021 05-22-84 Removed scram discharge volume level switch level element 2C11-N060C, and investigated level element and SDV tap for moisture.

Ref. DCr 82-220.

84-0375 03-27-84 Installed improved design stem / disk assembly on outboard MSIV 2B21-F022 A-D and 2B21-F028A-D.

Ref. DCR 83-4G.

84-0370 03-28-84 Installed improved design stem / disk assembly on i

inboard MSIV 2B21-F022 A-D a nd 2B21-F028 A-D.

Ref.

83-46.

84-1929 06-09-84 Filled scram discharge header 2Cll (North and south l

side) with demin water to help lower radiation exposure rates.

Ref. DCR 82-257.

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HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR July 1984 NUMBE R DATE COMPLETED DESCRIPTION 84-2420-06-09-83 Sealed target rock solenoid valves Q270-SV-F004, F005, F066, F067.

Ref. DCR 81-112.

84-1699 05-23-84 RWCU pump seal water system.

Flushed new seal water supply line.

Re f. D CR 79-96.

84-1421 04-25-84 Temporary shroud wide range level transmitter.

Disconnected the alarm functon being supplied by the temporary level transmitter.

Reconnected after the ATTS tubing work on racks 2Hil-P005 and 2Hil-P009 was complete.

Ref. DCr 81-139.

84-1351 05-08-84 Containment atmosphere control.

Installed conduit and supports 2T48-ADV-F307.

Ref.

DCR 83-168.

84-0826 05-10-84 Completed internal panel wiring on 2H11-P622, 2Hil-P601, and 2Hil-P602.

Intalled amber trip lights on valves 2T 48-ADV-F307, F308, F309, F318, F319, F320, F324, and F326.

Ref.

84-1193 03-29-84 Reactor protection system / scram discharge volume.

Calibrated level switches 2Cll-LS-N660C,D.

Ref.

DCR 82-220, Rev. 1.

83-0338 05-09-83 Performed all core drills,

and all civil & structural work to construct all pads for ATTS local rack installation.

Ref.

DCR l

81-139.

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'OPERATItG IATA IEIORT d

DOCKETf No.

50-321 gj:

IATE 08-10-84 1

CDMPIRIED BY: P.J. North 3'

TEIEPIDE (912) 367-7851 l

OIERATING S'IATUS Notes 1.

Unit Name: E. I. Ilatch Ntr: lear Plant Unit 1

.j 2.

Reporting Period: 07-84

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3.

Licensed Thermal Ibwer (!Wt): 2436 3

4.

Nameplate Rating (Gross MWe): 8 09. 3

~j 5.

Design Electrical Rating (Net MWe): 777.3 6.

Maximum Deperdable Capacity (Gross MWe): 801.2 7.

Maximum Depen 3able Gpacity (Net MWe): 752.2 g

4 8.

If Changes Occur in Gpacity Ratings (Itens Number 3 throu9h 7) Since last Report, Give Reasons:

I 9.

Pbwer level to Which lbstricted, If Any (Net MWe)

10. Reasons for Restrictions, If Any:

i This Month Yr-tcH] ate Ctunulative

11. Hours In Reporting Period 744 5111 75238
12. Number of Hours Reactor was Critical 744.0 4261.8 53786.9
13. Beactor mserve Shutdown Iburs 0

0 0

14. Hours Generator On-Line 744.0 4131.3 50524.3
15. Ur.it Ibserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MI) 1641541 9315545 106533573 J7. Gross Electrical Energy Generated (IWH) 539410 2963540 34421710
18. Net Electrical Energy Generated (MWH) 514488 2820966 32680329 M. Unit Service Factor 100.0 80.8 67.2
20. thit Availability Factor 100.0 80.8 67.2
21. Unit Capacity Factor (Using MDC Net) 91.9 73.4 57.7 i
22. thit Capacity Pactor (Using DER Net) 89.0 71.0 55.9

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23. Unit Ibreed Outage Rate 00.0 17.8 18.4
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, an! Duration of Each):

Refueling 10-1-84 10 week duration

25. If Shutdown at Ih1 of Report Period, Estimated Ihte of Startup:

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26. Units in 'Ibst Status (Prior to Connercial Operation):

Ebrecast Achieved INITIAL CRITICALITY INITIAL ELDC'IRICITY 00tNERCIAL OPERATION

[ O [9 9%

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AVERNE DAILY UNIT IOWER IEVEL

. {

D00GT NO.

50-321

'I IATE:

08-10-84

~I CDMMEIED BY: P.J. North 4

TEIEPIDE (912) 367-7851

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Ll M0tmi 07-84 i,

DAY AVERAGE IAILY IOhER LEWL IAY AVERAGE IAILY POhER LEVEL 1

(MNe-Net )

-l (MWe-Net ).

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1 717 17 710 5

2 720 18 711 3

720 19 709 I

4 720 20 697 5

718 21 708 6

719 22 703 7

719 23 701 8

713 24 699 j

9 715 25 6%

10 714 26 693 11 689 27 691 12 622 28 690 13 699 29 690 14 507 30 686 15 611 31 685 16 667 i

(9/77)

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OPERATI1G IWIA IEIORF

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,4 DOGET NO.

'50-366 Q4l IATE

~ 08-10 6%

CDMPLEIED BY: P.'J. North-

'M!

'IEIEPHotE (912) 367-7851

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OPERATIN3 S'IATUS 63 3

Notes

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Unit Name: E. I. Hatch Ntriear Plant Unit 2 d

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2. - Reporting Period: 07-84 O'

l 3.

Licensed Thermal Ibwer (Mit): 2436-

, w'-

4.

Nameplate Rating (Gross Mie): 817.0 N

5.

Design Electrical Rating (Net MWe): 784.0 j

l 6.

Maximum Depen 5able Capacity (Gross MWe): 803.9 d

7.

Nximaa Deperdable Capacity (Net MWe): 747.9 R!

8.

If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Iast Report, Give Reasons:

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i 9.

Pbwer level to hhich Ibstricted, If Any (Net Mie):

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10. Reasons for Restrictions, If Any:

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'Ihis Month Yr-to-Date Ctanulative -

1

11. Hours In Reporting Period 744 5111 42864
12. Number of Hours Reactor was Critical O.0 -

308.2.

27379.4-4

13. Reactor-Ibserve Shutdown Hours 0.0 0

0

. 14. Hours Generator On-Line 0.0 308.2 26096.1

15. Unit Ibserve Shutdown Hours 0.0 0

0 3'

16. Gross Thermal Energy Generated (MGH)

O 726912 55943167 l

17. Gross Electrical Energy Generated (MfH) 0 242640 18414420
18. Net Electrical Energy Generated (MdH)

-3414.

215860 17504967.

19. Uhit Service Emetor 0.0 6.0 60.9 i
20. thit Availability Factor 0.0 6.0 60.9
21. Unit Capacity Factor (Using 10C Net)

-0.6 5.6 54.6

22. Unit Capacity Factor (Using DER Net)

-0.6 5.4 52.1 1

23. Unit Ebrced Ottage Rate 0.0 0.0 13.1 i
24. Stutdowns Scheduled Over Next 6 Months (Type, Date, an! Duration of Each):

Recirc piping outage still in progress.

25. If Shutdown at End of Report Period, Estimated Date of Startup:

8/19/84

26. lhits in 'Ibst Status (Prior to (buunercial Operation):

Ebrecast Achieved I

INITIAL CRITICALITY

]

INITIAL ELBC'IRICITY COMERCIAL OEERATION 4

9

- (9/77).

AVEREE DAILY UNIT IOWER LEVEL

!*M

.:+.

DOQET NO.

50-366 IA'IE:

08-10-84

't (DMPLEIED BY: P. J. Nxth TELEPHOtE (912) 367-7851 i

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MONHi 07-84 DAY AVERAGE IAILY POWER LEVEL IRY AVERAGE IRILY POWER LEVEL (MWe-Net)

(MWe-Net )

1

-7 17

-4 2

-6 18

-4 3

-6 19

-4 4

-6 20

-4 5

-5 21

-4 6

-3 22

-5 7

-3 23

-5 8

-4 24

-4 9

-4 25

-5 10

-4 26

-5 11

-4 27

-4 12

-5 28

-6 13

-3 29

-6 14

-4 30

-6 15

-5 31

-6 16

-4 (9/77)

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50-32 d UNIT SI:UTDOWNS A POWER REDUCTIONS DOCKET NO.

UNIT N/OIE Hatch 1 DATE 8-1-84 REPORT MONTil July COMPLETED BY Philip J. North TELEPilONE. 912-367-7851 x-2882 i

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f,.YE Licensee

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"Cause & Corrective No.

Date g

3g r,

ygs Event p

Q Action to ?

H dE j ;jj g Report #

mO Prevent Recurrencc g

84-49 84-07-01 F

744 A

5 N/A HA TURBIN 13th stage buckets were damaged and out for the duration of July.

84-50 84-07-08 S

2.2 B

5 N/A HA TURBIN Load reduction for weekly turbine testin J.

t 84-51 84-07-11 F

8.75 A

5 N/A HF

PUMPXX, Load reduction to investigate problems with1Acircwaterpump.}

l 84-52 84-07-12 S

.33 H

5 N/A IB INSTRU Power increase discontinued to adjust APRi1 Gains.

84-53 84-07-12 S

.20 H

5 N/A IF INSTRU Power increase discontirued for P-1 run.

f 84-54 84-07-13 S

3.58 B

5 N/A HA TURBIN Load reduction for weekTy turbine testint and rod pattern adjustmc nt.

84-55 84-07-14 S

1.46 H

5 N/A RB CONROD Rod pattern adjustment.

1 2

3 4

F: Forced Reason:

Method:

Exhibit G-11,structions S: Schedu!cd A Equipment' Failure (Explain)

I Manual for Preparati6n of Data l'

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B Maintenance of Test

2. Manual Scram.

Entry Sheets'for Licensee. -

C-R:fueline,

3. Automatic Scram.

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Event Report (LER) File (!JUREG-:

i D Regulatoiy Rest:.c; ion 4 -Continuations l

0161)

E. Operator 't raining & License Examination 4

5-Ioad Iteduction F Adsninis ra:ive G.Operaticua! Erret (cxplain) 9-Other (Explain) 5 g

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Exhibit I Same Source,.

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Il-Other (Explain) i.-

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lt 0-32 W UNIT SI:UTDOWNS AND POWER REDUC 110NS DOCKET NO.

UNIT N A*.!E Hatch 1 g

DATE 8-1-84 COMPLETED BY, Philip J. North REPORT MONTil Julv TELEPllONE, _912-367-7851 X-2882 ;

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'Cause & Corrective Nii.

Date g

3g g

.g g 5 Event u?

O Action to -

[g dE 5

jgg Report #

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Prevent Recurreticc 7

84;56 84-07-20 F

.62 A

5 N/A HF HTEXCH Power reduction to compensate for 6 fans tripped on "C" cooling tower, 3 fans tripped on "B" cooling tower.

84-57 84-07-28 S

2.0 B

5 N/A HA TURBIN Load. reduction for weekly turbine testin g.

j 84-58 84-07-28 S

.32 B

5 N/A RB CONROD' Load reduction for cont ol rod exercise.

o 74 U

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2 3

4 F: Forced Reason:

Method:

Exhibit G. Instructions T.

5: Scheduled A Equipment'F:ilure(Explain) 1 Manual for Pseparati9n of Data C

B41aintenance of Test 2-Manual Scram.

Entry Sheets *for Licensee. -

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C Refueling 3.Automstic Scram.

j Event Rcport (LER) File (NUREG-:

D Regulatony Rest:.c; ion 4 -Continuations 01611 j

E Operator 't raining & Ucense Examination

'i 5-Icad Reduction G Operaticual Erret(Explain) -

9 --Oh (@h) 3 F-Acrainis.ra:he p' *.

l Exhibit !.Same Source,.

(0177)

Il-Other (Explain) i.-

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50-36 b I UNITSilUTDOWNS AND POWER REDUCTIONS D

UITN IE. Hatch 2 DATE 8-1-84 REPORTMONill _ July COMPLETED BY,Philio J.

North TELEPl10NE.912-367-7851 y-2882 l

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.EE Licensee E v.,

$"3 c

'Cause & Curreclive No.

Date E

E Ej

,55 Event u '3 N

o-Action to *

$E c2 jgg Report #

AU

[U Prevent Recurscrice d

84-5 84-07-01 S

744.0 H

2 ft/A CB PIPEXX Recirc Pipe Replacement outage.

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3 F: l'orce d Reason:

4

$1cthod:

5: Scheduled A Equipment *Fallure (Explain) 141anual Exhibit C-Itstructions for Preparatlyn of Data Il41aintenance of Test 24!anual Scram.

Entry Sheets for I.ieensee. -

C Refueling:

3 Automatic Scram.

D Regulatuiy siest:.etion 4 -Continuations 3

Event Rcpurt (LER) Fife (!JUREG-:

q 0161)

E Operaint italning & Ucense Examination p

F Adrainis ra::ve 5-Ioad Reduction G Opera !vnal Errer(;ixplain) 9-Oh (@s) 3 g

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II Other (Laplain)

,..g Exhibit ! Same Sourec,*,,

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i Georgia Power Company l

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Post Office Box 439 (g9 Baxley, Georgia 31513

  1. Telephone 912 367-7781 A

912 537-9444 g

m Georgia Power Edwin 1. Hatch Nuclear Plant August 2, 1984 GM-84-677 p

PLANT E.

I. HATCH NRC Monthly Operating Report f

Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, D. C.

20555

Dear Sir:

Per Tech Specs section 6.9.1.6 pleas _e_f_ind attached the NRC

' Monthly Operating Report for45atcEEUnit;;1,, Docket #50-321, and for Hatch Unit 2, Docket #50-366, e

H.

C.

Nix General Manager JAB /sw

_TE 2.1 ij,

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