ML20082S502

Monthly Operating Repts for Nov 1983

ML20082S502
Person / Time
Site:	Hatch
Issue date:	12/10/1983
From:	Curtis C, Nix H GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
References
GM-83-1171, NUDOCS 8312140174
Download: ML20082S502 (12)

Text

{{#Wiki_filter:, O) f) C) G v m OPERATING L'ATA REPORT DOCKET NO. 50-321 OATE 12-10-83 COMPLETED BY: C. M. Curtis TELEPHONE (912) 367-7851 l OPERATING STATUS Notes 1. Unit Name: E. I. Hatch Nclear Plant Unit 1 2. Reporting Period: 11-83 3. Licensed Thermal Power (MWt): 2436 4. Nameplate Rating (Gross MWe): 809.3 g i J l 5. Design Electrical Rating (Net MWe): 777.3 i. 6. Maximum Dependable Capacity (Gross MWe)': 801.2 7. Maximum Dependable Capacity (Net MWe): 764.7 8. If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons: J l 9. Power Level to Which Restricted, If Any (Net MWe) ll

10. Reasons for Restrictions, if Any:

l l This Montn Yr-to-Date Cumulative

11. Hours In Reporting Period 720 8015 69383

12. Wmber of Hours Reactor was Critical 96.0 6050.5 49003.0 l

l

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 96.0 5797.7 45948.0

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 161784 12139229 96387592

17. Gross Electrical Energy Generated (MWH) 51520 3923040 31192530

18. Net Electrical Energy Generated (MWH) 44413 3722867 29609082

19. Unit Service Factor D.)

72.3 66.2

20. Unit Availability Factor 13.3 72.3 66.2

21. Unit Capacity Factor (Using MDC Net) 8.1 60.7 55.8

22. Unit Capacity Factor (Using DER Net) 7.9 59.8 54.9

23. Unit Forced Outage Rate 0.0 5.4 18.5

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

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

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

Forecast Achieved INITIAL CRITICALITY 8312140174 832210 INITIAL ELECTRICITY PDR ADOCK 05000321 COMMERCIAL CPERATION R PDR 0

O O O AVERAGE DAILY UNIT POWER LEVEL i i DOCKET NO. 50-321 i DATE: 32-10-83 l COMPLETED BY: C. M. Curtis l TELEPHONE (912) 367-7851 1 i MONTH 11-83 b DAY AVERAGE DAILY POWEk LEVEL DAY AVERAGE DAILY POWER LEVEL {- (MWe-Net) '.MWe-Net) 1 514 17 -5 { 2 514 18 -5 3 514 19 -4 l 4 485 20 -6 5 -15 1 21 -6 6 -13 22 -7 l 7 -13 23 -6 8 -9 24 -6 9 -7 25 -6 10 -7 26 -6 11 -6 27 -6 1 12 -6 28 -6 i 13 -6 29 -5 14 -6 30 -6 15 -6 31 16 -5 i l (9/77) i i I i 7, n .,m -a

^s . O .O. 50-321 UNIT SliUTDOWNS AND FOWER REDUCTIONS DOCKETNO. Hatch 1 UNIT NAME DATE 12-10-83 COMPLETED BY C X Curth REPORT MONTri Nnvombor TELEPi!ONE Q19 V7 7AR1 Fe b- 'Cause & Corrective .! E 3 .Y Licensee 5% E.% 8 Action to No. Date. g 3g g jj g 5 Event u7 5E 5 j5j Report # is 0 gO Prevent Recurrence i-6 n 83-84 831101 F 96 F 5 NA RC FUELXX Load Reduction Due to Leaking Fuel Problems. 83-85 831105 S 624 C 2 NA RC FUELXX Core Reconstitution Outage. l t I i I j I 2 3 4 F: Farced Reason: Method: Exhibit G Instructions A6 uiprn:nt'F:ilur:(Expl in) 14 Enual c for Preparation of Data S: Sch:du!ed t LJ.hintenan:e ci Test 2-Mancal Secm. Entry Sh:ets for Licensee C-Refueling 3-Autumatic Scram. Event Report (LER) File (NUREG-D Regulatory Restrictien 4 -Continuations 0161) E-Operator Training & Ucense Examination 5-Ioad Peduction ~ S F-Administrative 9-Other (Explain) Exhibit I-Same Source G Operational Error (Exp!ain) (9/77) Il Oti :r (Exp!:!=)

.... _. _ - - _. - -. - -. - - - _ ~. i NARRATIVE REPORT UNIT'l d NovemberJlst . 0000 Load held-to 65% due to leaking fuel problems. -{ i November 5th 2,10000 Manual shutdown for core l reconstitution outage. E + k e r I k .j-i i

O 4

4 + l i~ 1 1 i e { i i e-O t i L

HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR NOVEMBER 1983 - (') NUMBER DATE COMPLETED DESCRIPTION 83-7201 05-23-63 dPCI system pipe hanger: per DCR 82-75 install hanger E41-221A-H4. 83-6101 10-25-83 Plant service water pump ,4 discharge pressure gauges: remove present gauges and a' snubbers. Install Weksler compound liquid filled gauges with diaphragm seals as per GCR 83-124. 83-6661 11-03-83 PSW strainer packing: pack strainers using existing grease passage ways per leak repair procedure. 83-6955 11-30-83 RPS/ scram discharge volumet calibrate liquid level controller C11LSN660 A,B,C,D & C11LEN060 A,B,C,0 as per installation cat. 83-7999 11-29-83 Diesel generator 1A,18,1C reverse power relays: change p), \\_ set point on the ICW reverse power relays to 50 watts, per DCR 82-189. O

) [ OPERATING DATA REPORT-DOCKET NO. 50-366 DATE-12-10-83. COMPLETED BY: C. M. Curtis TELEPHONE (912) 367-7851. OPERATING STATUS Notes 1. Unit Name: E. I. Hatch Nuclear Plant Unit 2 2. Reporting Period: 11-83 3. Licensed Thermal Power (MWt): 2436 4. Nameplate Rating (Gross MWe): 817.0 L 5. Design Electrical Rating (Net MWe): 784.0 3-6. Maximum Dependable Capacity (Gross MWe): 803.9 7. Maximum Depenoable Capacity (Net MWe): 774.5 8. If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons: 9. Power Level to Which Restricted, If Any (let MWe):

10. Reasons for Restrictions, If Any:

1 Tnis Month Yr-to-Date Cumulative

11. Hours In Reporting Period 720 8016 37153

12. tOmber of Hours Reactor was Critical 720.0 5320.2 26471.3 4

l

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 720.0 5032.9 25188.0

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1691976 10201892 53807575

17. Gross Electrical Energy Generated (MWH) 568010 3420800 17697270

18. Net Electrical Energy Generated (MWH) 544922 3245429 16833755

19. Unit Service Factor 100.0 62.8 67.8

20. Unit Availability Factor 100.0 62.8 67.8 i

21. Unit Capacity Factor (Using MOC Net) 97.7 52.3 58.5

22. Unit Capacity Factor (Using DER Net) 96.5 51.6 57.8

)

23. Unit Forced Outage Rate 0.0 17.4 13.5

24. Shutdowns Scheduled Over Nex. 6 Months (Type, Date, and Duration of Each):

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

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY ~ COMMERCIAL OPERATION

/_ O-O O AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-366 ~DATE: 12-10-83 COMPLETED BY: C. M. Curtis TELEPHONE (912) 367-7851 MONTH 11-83 j DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) ) 1 770 17 730 2 777 18 762 3 731 19 763 4 686 20 777 l 5 729 1 21 766 l 6 696 22 786 7 712 23 '781 8 773 24 779 9 778 25 786 10 778 26 717 11 785 27 721 12 774 28 768 13 788 29 739 14 742 30 725 15 780 31 16 767 (9/77)

~ 'O. O O 50-366 D ET O natcn 4 UNIT SHUTDOWNS AND FOWER P. EDUCTIONS u N { DATE 12-10-83 November COMPLETED BY C_M_ Curtis REFORT MONTri - TELEPi!ONE Q12 'M7-7M1 l n. E E 'Cause & Corrective m .E q $.? 5 Lieccsec ,E -* y*3 Action to No. ~ Date - g 3g s jg5 Event p c-Prevent Recurrence yv yE 5 j@g Report # mO H z. 6 83-45 831103 F 22.3 A 5 NA HE VALVEXX Load reduction due tc turbine bypass i-valve slow opening. 83-46 831105 F 58 A 5 NA HE VALVEXX Load reduction due to turbine bypass valve slow opening. 4 83-47 831105 S 2 B 5 NA HE VALVEXX Load reduction for control valve test. 4 83-48 831105 S 2 H 5 NA RB CONROD Load reduction due to control rod exer-cise. 83-49 831111 S 4.3 8 5 NA' HA TURBIN Load reduction for weekly turbine test-ing. 83-50 831114 F 9 A 5 NA HE VALVEXX Load reduction due to turbine bypass valve opening.

83-51 831116 F

15.3 A 5 NA HE VALVEXX Load reduction due tb turbine bypass valve opening. l l I 2 ?!ethod: 4 3 Exhibit G. Instructions !4hnuel , for Prep 2 ration of Data F: Fon:d R:ason: S: S:h:duled ACn:ip.=nt'F:ilur:(Explain) 2-Manual Scr:m. Eritry Sheets for Licensee 3-Autumatic Scram. Esent Report (LERI File (NUREG-E. bir.tenance ci Test C-Refueling 4 -Continuations 0161) D Regulatory Restriction E-Operator Training & License Examination 5'-Ioad Pcduction 5 F-Administtative 9-Other (Explain) Exhibis 1-Same Source G Operation:1 Error (Explain) (9/77) Il Oth:r (Exp!:in)

O o D ET r. UNIT SliUTDOWNS AND FOWER REDUCTIONS t 2 DitTE 12-10-83 November COMPLETED BY C.M. Curtis REPORT MONTri TELEPilONE 912-367-7851 .5 ? 3 .'I g Licensee E-- vi, - 'Cause & Corrective ~ o o s" Action to y No. Date - g; 3g s ,g g 5 Event p y5 Prevent Recurrence i H $Ei 5 jd Report # mO a ]. 2 83-52 831117 F 8.5 A 5 NA EE ENGINE Load reduction due'to 2C & B dies.el generator inop. 83-53 831120 S 2 B 5 NA HA TURBIN Load reduction for weekly turbine test-ing. {TURBIN Load' reduction for weekly turbine test-t 83-54 831126 S 3.7 B 5 NA HA ing. l 83-55 831126 S 9 H 5 NA RB CONROD Load reduction due to control rod exer-CISe. 83-56 831129 F 10 B 5 NA 'HJ PIPEXX Load reduction to repair leaks in con-denser bay. f I l I 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Sch:duled A E;uipm:ntTaitur:(Expkin) 14bnu:1 . for Preparation of Data E.'.hintenance of Test 2-Manu:1 S:am. Entry Sheets for Li ensee C Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4 -Continuations 0160 E Operator Training & Ucense Examination 5--Ioad Pcduction S F Administtative 9--Other (Explain) Exhibit I-Same Source G Operational Error (Exphin) (9/77) Il O h:r(Exphin) ~ e a

NARRATIVE REPORT UNIT 2 () November 3rd 1845 Load reduction due to turbine bypass valve slow opening. November 3rd 1912 Began increasing reactor power. November 5th a1406 Load reduction due to turbine bypass valve opening. November 5th ~1502 Load reduction for control valve test. November 5th 1554 Load reouction due to control rod exercise. November 5th 1635 Increasing reactor power with recirc. November lith 2348 Load reduction for weekly turbine testing. November 12th 0412 Testing Comp. November 14th 0700 Load reduction due to turbine bypass valve opening. ('S November 14tn 1347 Increasing reactor power via recirc. November 16th 2044 Load reduction due to #2 control valve closure. November 17th 1208 Increasing reactor power. November 17th 2244 Load reduction in progress due to "B" & 2C diesel generator inop. November 18th 0816 Increasing reactor power. November 20th 0030 Load reduction for weekly turbine testing. November 20th 0240 Testing completed. November 26th 1843 Load reduction for weekly turbine testing. Novemoer 26th 2105 Load reduction due to contro roo exercise. November 26th 2228 Weekly turbine testing completed. () November 29tn 1900 Load reduction to repair leaks in concenser bay. November 30th 0209 Increasing reactor power.

~ HATCH 2 SAFETY-RELATED MNINTENANCE REQUEbTS Tu oE REPORTED FOR NUVEMBER 1963 NUMBER DATE COMPLETE DESCRIPTION es (_) B2-1378 09-09-63 Hot machine shop floor drain piping; Cut out & remove concrete in floor per sketch B-C-79-476-1. Repour concrete & fit necessary a. joint. Ref. DCR 79-476. 82-2572 10-06-83 Drywell Pneumatic System: Change setpoint of 2?70-PS-N003 from 75 psig to 9K1.'5 psig & 2P70-F103A,B 3 1 from 90 psig to 97 2.0 psig. 1 82-2785 05-19-83 Drywell pneumatic system supply line high pressure switch: calibrate 2P70-N017. 63-1967 Process computer: install circuit breaker 2R26-M062. Ref. DCR 82-172. 83-2177 11-09-83 Distribution panels: Fabricate & place steel members, reinforcing bars, & embedded concuit per FDR-(~; 82-172-4. Pour concrete pads \\_/ for panels. def. DCR 82-172. 83-2865 07-12-83 States block TB-AA: Replace per DCR 81-139. 83-4632 10-11-83 PASS Baron & chloride analyzer: Install 2 pressure gauges upstream & downstream of analyzers per DCR 79-476. 83-6002 11-29-83 Diesel generator 2A & 2C reverse power relays: change setpoints on ICW relays to 50 watts per data sheets. Ref. DCR 82-110. o I Y< 'r k l l

4 Georgia Power Company Post Office Box 439 Baxley, Georgl3 31513 Telephcre 912 367-7781 , 912 537-9444 \\ Edwin I. Hetsh Nucieer Plant December 10, 1983 GM-83-1171 PLANT E. I. HATCH NRC Monthly Operating Report Office of Plans and Schedules Directorate of Licensing United States Nuclear Regulatory Commission Washington, D. C. 20545

Dear Sir:

Per Tech Specs section 6.9.1.6 please find attached the NRC Monthly Operating Report for Hatch Unit 1,3 Docket #50-321, and for Hatch Unit 2, Docket #50-366. 2._ H. C. Nix / General Manager d \\ f J' k t ZE-1 V 9 ll' l _}}