ML20083H738

Monthly Operating Repts for Dec 1983

ML20083H738
Person / Time
Site:	Hatch
Issue date:	12/31/1983
From:	Nix H, Rafeedie D GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
GM-84-18, NUDOCS 8401130330
Download: ML20083H738 (17)

Text

- - _ _ _ _. _ _ _ _ _ _ _ _ _.

8401130330 831231

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PDR ADOCK 05000521 R

PDR OPERATING DATA REPORT DOCKET NO.

50-321 DATE 01-10-S4 COMPLETED BY: D. P. Rafeedle TELEPHONE (912) 367-7851 OPERATING STATUS Notes 1.

Unit Name: E. I. Hatch Nuclear Plant Unit 1 2.

Reporting Period: 12-83 3.

Licensed Thermal Power (MWt): 2436 4.

Nameplate Rating (Gross MWe): 809.3 5.

Design Electrical Rating (Net MWe): 777.3 6.

Maximun 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:

9.

Power Level to Which Restricted, If Any (Net NWe)

10. Reasons for Restrictions, If Any:

Inis Montn Yr-to-Date Cumulative

11. Hours In Reporting Period 744 8759

,70127

12. Number of Hours Reactor was Critical 522.2 6572.7 49525.2

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 445.0 6242.7 46393.0

15. Unit Heserve Shutdowri Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 802332 12941561 97189924

17. Gross Electrical Energy Generated (MWH) 256420 4179460 31448950

18. Net Electrical Energy Generated (MWH) 241280 3964147 29850362

19. Unit Service Factor 59.8 71.3 66.2

20. Unit Availability Factor 59.8 71.3 66.2

21. Unit Capecity Factor (Using MDC Net) 42.4 59.2 55.7

22. Unit Capacity Factor (Using DER Net) 41.7 58.2 54.8

23. Unit Forced Outage Rate 8.4 5.6 16.4

24. Shutdowns Scheduled Over Next 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 g

INITIAL CRliICALITY I

INITIAL ELECTRICITY COMMERCIAL OPERATION I

AVERAGE DAILY UNIT' POWER LEVEL DOCKET NO.

50-321 DATE:

01-10-84 COMPLETED BY: D. P. Rafeedle TELEPHONE (912) 367-7851 MONTH 12-83 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)-

~

l

-6 17 97 2

-6 18 447 3

-5 19

-529 4

-8 20 653 4

5

-6 21 707 6

-6 22 719 7

-7 23 676 8

-8 24 590 9

-13 25 681 10

-13 26 742 11 11 27 213 12 179 28 304 13 270 29 678 14 421 30 735 15 495 31 690 16 294 4

en

'2/77)

NARRATIVE REPORT UNIT 1

' December ~1st.

0000 Core reconstitution outage.

December 8th-2242 Reactor critical.

December lith 1611

' Generator tied to grid and

- increasing reactor power.

December lith 2136 Manual turbine trip for overspeed testing.

December lith 2336 Generator tied to grid increasing power to 30% thermal and holding for scram time testing to be complete.

December 13th 1038 Increasing reactor power to 50%

by pulling roos.

December 13th 1235 Power increase stopped so engineer can take data.

December.14th 0200 Power ascension in progress.

December 16th 0720 Normal reactor shutdown in progress to repair "B"

TIP machine.

December 16th 2054 Manual reactor scram.

December 16th 2056 Main turbine trip.

December 17th 0800 Reactor critical.

December 17th 1446 Generator. tied to line ano power increase started.

December 17th 1600 Power increase stopped.

December 17th 1749 Began reactor power increase by pulling rods.

December 17th 2000 Power increase stopped.

December-18th 0455 Power increase started with recirc.

December 23rd 2000 Load reouction for pattern adjustment ano main turbine test.

December 23rd 2115 Weekly turbine testing in progress.

.-.,,n, e

D;cc;bar:24th 0110 tsskly turbine test complete.

Increasing reactor power.

December 27th 0657 Reactor scram due to low H O 2

level from condensate booster pump trip.

December:27th 2321 Reactor critical.

December 28th 0553

~ Generator tied to grid. Power increase in progress.

December'3'Oth 2340 Power reduction for rod-pattern adjustment.

Decen.be r - 31s t 0300-Pattern aojustment complete.

Increase reactor power.

Q 50-321 S

[,-

K UNIT SliUTDOWNS AND FOWER REDUCTIONS i.

Hatch 1 IT A. IE DATE 1-10-84 December

> COMPLETED BY D.P. Rafeedie REFORT MONTH J

TELEPHONE 912-367-7851 e.

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4,Y 5 Licensec

,Eg "Cause & Corrective No.

Date.

g 3g

• s ji 5 5 Event gg e.?

Action to ju Prevent Recurrence 8--

$5 5

jig Report #

mO c5 83-86 831201 S

256.2 C

2 NA RC FUELXX Core reconstitution outage.

83-87 831211.

S 5.4 H

5 NA RC FUELXX Power ascension fr'oin above cutage.

l 83-88 831211 S

2, B

9 NA HA TURBINE Manual turbine trip for overspeed testir 9 b3-89 831212 S

79.7 H

5 NA RC FUELXX Fower ascension from above outage.

1 i

83-90 8312'16 F

13.5 A

5

. NA ID INSTRU Load reduction for repair of B TIP machine.

I l 83-91 831216:

F 17.8 A

2 NA

.ID INSTRU Dutage to repair B TIP machine.

83-92 831217 S

93.2 H

5 NA ID INSTRU' Ramp from IIP outage.

83-93 831223 S

61 H

5 NA RB CONROD Load redtict' ion for pattern adjustmant &

turbine test.

l 83-94 831227 F

22.9 A

3 NA CB PUMPXX Condensate booster pump trip.

l 2

~

3 4

l F: Forced R:ason:

Plethod:

Exhibit G. Instructions S: Sch:dukd A 0;uip:n: :t'Failur:(Exp!cin) 14hnual 7for Preparation of Data B..

2 Manual Screm.

Entry Sheets for Licensee c.'hinte: ance er Test 4 -Continuations 0161)

Refueling 3-Automat'- Scram.

Event Report (LER) File (NUREG-D Regulatory Restriction E-Operator Training & Ucense Examination 5'-Ioac1 Pcduction F-Administrative 5

G Operational Error (Explain) 9--Other (Explain)

Exhibit I Same Soure:

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(9/77)

Il Oth:r (Expkir:)

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50-321 D

UNIT SHUTDOWNS AND FOWER REDUCTIONS UITN IE Hatcn i DATE 1-10-84 December COMPLETED BY D.P. Pafeedie REFORT MONT~ri TELEPHONE 912-367-7851

,E g 3

) Yh Licensec

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~ Cause & Corrective No.

Date.

g 3g s

jg g 5 Event g7 93 Action to

.ju Prevent Recurrence H

JE di jdg Report #

mO 6

83-95 831228 S

27 A

5 N.A CB PUMPXX Ramp from CB'P scram.

83-96 831230 S

8.3 H

5 NA RB CONR0D Lodd reduction for pattern adjustment I

& main turbine wee'Kly.

4

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i -

i t

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2 3

4 F: Forecd R:ason:

I!cthod:

. Exhibit G Instructions A S uiprn:nt'Feitur:(Exp!cin) 1 ?hnual

' t for Preparation of Data S: S:heduled t

B..binte. an:e of Test 2 Manual S:r:m.

Eritry Sheets for Licensee

c. Refueling 3.Auturnatic Scram.

Event Report (LER) File (NUREG-D Regulatory Restriction 4 -Continuations 0161)

E-Operator Training & Ucense Exsmination 5'-Inad Peduction i,.

9.-Otner (Explain)

-S i -3 F-Administrative G Operational Error (Exp!ain)

Exhibit I-Same Source (9/77) li Oth:r(Exp!:in)

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HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR DECEMBER 1983 NUMBER DATE COMPLETED DESCRIPTION 7635

_11-22-63 CR0 Vents ano Urains.

Replaced existing valves Cll-F110A&B (Solenoid valves) with 2 ASCO Type NP8316E36E, 125 VDC Solenoid Valves. New valves were seated as per HNP-0-6946.

Ref: 83-32.

82-4426 03-28-83 Health Physics'130 El.

(Smoke detection System).

Installed conduits, conduit hangers, & associated electrical equipment. Pulled cable tag with oppossum tails. Terminated & redline.

per sketches SE 80-484-23, 24, 25, 35, 50, 56, 61, 62, 63, 68, 69, 176, 183, 185, 189, 190, and 192.

83-5714 10-06-83 HPCI Sprinkler System (Fire Protection). Installed caule, raceway, & terminal box for new HPCI sprinkler system per DCR 80-322.

Installed conduits &

raceways per HNP-6921, Ref:

DCR 80-322.

83-6985 12-06-83 CRD SDV Vents & Drains.

Removed existing supports &

piping. Installed new valves Cll-F035A&B, F037; piping &

support per sketches on continuation sheets. Also hydrostatically tested the new installation. Ref. DCR 83-32,82-204.

l 83-6950 12-05-83 Reactor Protection l

System / Scram Discharge Volume. Revised internal wiring in panels H11-P609 &

Hll-P611 & terminated cables as per attached sketches.

Ref. DCR 82-219.

6 j

HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR DECEMBER 1983 82-8473 10-12-83 Turbine / Generator Bearing Fire Annunciation. Revised the annunciation logic for the 8 Unit 1 Turbine / Generator Fire alarms per sketches SE-82-134-(1,2,3,4) Rev. A &

SM 82-134-1 Rev. A per DCR 82-134.

Tapeo and stowed spare conductors. Ref. DCR 82-134.

83-8427 12-08-83 Reversed Thermocouple lead on G31-N602A-D. Ref. DCR 83-270.

83-8426 12-08-83 Leak Detection Thermocouple Selection Switch. Heversed wiring on switch B21-52 from thermocouples G31-N023A-D &

G31-NO22A-D per DCR 83-270.

Ref.83-270.

83-8083 12-21-83 Repaired leaks in valve Cll-F035A. Ref. DCH 83-032.

83-7507 11-28-83 Reactor Protection System / Scram Discharge Volume attacheo new nameplates. Ref. DCR 82-219.

83-7394 12-01-83 Cll-F035 Isolation Valve for the CHD Scram Discharge Volume. Disassemoled Valve Cll-F035 per SX-19950.

Removed rust on valve parts.

Reassembled valve & paintc d.

Ref. DCR 83-032.

83-8123 11-30-83 Terminal boxes for Radiation Monitoring System. Installed TB1-1519 in West Cableway near cable tray support #9.

Installed TB1-1520 in West Cableway near caule tray support #24. Installed boxes on tray TAA7-4. Ref. FDR 83-213-2, DCR 83-213.

.82-7498 12-05-83 Solenoid Valves. Lubricateo ASCO Solenoid Valves. Used Lubrication Kit N-220-457.

Ref. DCR 79-459.

4

. HATCH'l SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR DECEMBER 1983 6952 11-22-83 Reactor Protection System / Scram Discharge Volume. Installed level elements Cll-LE-N060A,B,C,D

& level switches Cll-LS-N660A-D as per attached sketches & work instructions. Ref. DCR 82-219.

83-7817.

11-11-83 1Lil, CRD Vents & Drains, core drills for DCR 83-032.

83-6956 11-30-83 1Cll pullec 8 new cables for DCR 82-219.

83-8031 12-05-83 C11-F110A&B Install hign energy line break barriers for solenoid valves.

C11-F110A&b. Ref. DCR 83-032.

83-7718 12-03-83 1Hll-P607 TIP monitoring &

centrol panel implement DCR 83-21.

83-7667 11-30-83 C11-F035A&B installed conduit support & conduit.

Ret.83-032.

83-6951 12-01-83 C11 reactor protection system / scram discharge volume installed raceways &

fabricateo supports. Ref.

DCR 82-219.

83-6964 11-18-83 1C11 Install indication lights for valves.

Cll-F035A&B on panel H11-P603 relocate nameplates. Ref DCR 83-032.

83-6986 12-05-83 1C11-F035A&B pulled cables for DCR 83-032.

83-7717 12-02-83 1Cll-F040 Installed tubing

?ittings, supports, valves.

C11-F045, Cll-F080, Cll-F081, Cll-F086, supplying AIV to Cll-F035A-B

& Cll-F037. Re f. DCR 83-032.

83-6962 12-02-03 C11-F035A&B, Cll-F037, provide internal wiring for new valves & circuits. Ref.

DCR 83-032.

HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR DECEMBER 1983 83-7936-12-03-83 R33 cable trays in U1 drywell restore cable trays.

Ref. DCR 83-53.-

83-7937 12-03-83 1R33 U1 steam chase cable trays restored. Ref. UCR 83-53.

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OPERATING' DATA REPORT'

. DOCKET NO.

50-366

[

DATE 01-10 COMPL_TED BY:.D. P. Rafeedle.

TELEPHONE

. (912) 367-7851 OPERATING STATUS.

Notes 1.

Unit Name: E..I. Hatch Nuclear Plant Unit 2 2.

Reporting Period: 12-83 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): 8G2.9 i

7.

Maximum Dependable Capacity-(Net MWe): 774.5 8.

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

1 9.

Power Level to Which Restricted, If Any (Net MWe):

i l

10. Reasons for Restrictions, If Any:

This Month Yr-to-Date Cumulative j

11. Hours In Reporting Period 744 8760 37897

12. Number of Hours Reactor was Critical 744.0 6064.2 27215.3-

13. Reactor Reserve Shutdown Hours 0

0-0

14. Hours Generator On-Line 744.0 5776.9

.25932.0

15. Unit Reserve Shutdown Hours 0

-0 0

i

16. Gross Thermal Energy Generated (MWH) 1746696 11948588.

55554271i

17. Gross Electrical Energy Generated (MWH) 587620 4008420

.18284890.

18. Net Electrical Energy Generated (MWH) 564027 3809456 17397782' I

19. Unit Service Factor 100.0 65.9 68.4

20. Unit Availability Factor 100.0 65.9 68.4

21. Unit Capacity Factor (Using MOC Net) 97.9 56.1 59.3

)

22. Unit Capacity Factor (Using DER Net) 96.7 55.5 58.6

23. Unit Forced Outage Rate 0.0 15.5 13.2 l

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

1 Retat. Pws ReucxmsnT, \\-r5-8%, (oMcmms 4

4

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

j

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

Forecast Achieved i

i INITIAL CRITICALITY i

INITIAL ELECTRICITY COMMERCIAL OPEO.ATION

~

AVERAGE DAILY. UNIT POWER LEVEL DOCKET NO.

50-366 DATE:

01-10-84' COMPLETED BY: D. P. Rafeedle TELEPHONE (912) 367-7851 MONTH 12-83 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I

(MWe-Net)

(MWe-Net) i 1

763 17 764-2 744 18.

640 3

676 19 7 71 4

779 20 785 5

784 21 791 6

779 22 791 7

791 23 791 8

792 24 789 i

9 793 25 784 10 784 26 780 11 785 27 765 12 615 28 780 13 650 29 780 14 762 30 788-l 15 786 31 614 j

16 786 (9/77) 1 M

1 J

L

. NARRATIVE' REPORT =

.O UNIT 2

. December 'I s't:

~1416-Load reduction due to feedwater conouctivity increasing.

December 1st 1715 Increasing' reactor power.

December 2nd 2110

? Load reduction to fix steam leaks in condenser bay.

December.3rd-0350 Increasing reactor power with recirc.

Deceraber 10tn

'2209-Load ~ reduction for weekly turbine testing.

December llth 0307 Weekly turbine testing complete.

Load increaseo.

December 12th 1300 Loao reduction to repair leaks in steam chase.

December'13th 0321 Increasing reactor power.

December 17th 2230 Loao recuction to repair feedwater line crain valve.

December 18th 0215 Increasing-reactor power.

December 31st 1318 Load reduction due to 4160 "A"

buss trip with a recirc pump ano circ water ^ pump trip.

-December 31st 1500 Increasing reactor power.

c w

50-366 UNIT SliUTDOWNS AND POWER P. EDUCTIONS

/.

K IT N !E DATE l-10-84 December COMPLETED BY ' D.P. Rafeedie REFORT MONT~ri TELEPHONE 912-367-7R51 m

E i'

m

,E g 3

$.Y h Licensee

,Ee,

$"1

'Cause & Corrective f

e-Action to No.

Date -

g Eg s

Jg5 Event g

yU Prevent Recurrence H

g5 5

jg Report #

mu 6

l 83-57 831201 F

6.7 H

5 NA CH ZZZZZZZ Load reduction due to feedwater cbnduc-

~

tivity increasing.

l 83-58 831202 F

10.9 A

5 NA CB HTEXCH Load reduc' tion to fix steam leaks in condensate bay.

a 83-59 831210 S

1 B

5 NA HA TURBIN Load redu'ction for weekly turbine test.

83-60 831212 S

18 A

5 NA HB PIPEXX Load reduction to fix. steam leaks in steam chase.

83-61 831217 S

13.5 A

5 N

CH VALVEX Load reduction to fix F/W drain valve 2N21-F154.

83-62 831231 F

10.6 A

5 NA CB ELECON Load reduction due to "A" recirc pump trip from '4160 bus '.'A" tripping.

l l

I 2

3 4

F: Forced R:ason:

Plethod:

Exhibit G Instructions S: Schedufed A E:;uip.m.:nt'Failur:(Expkin) 14bnuel cfor P;cparation of Dats B..!:intenance ciTest 2 Manual Su:m.

Eritry Sh:ets for Licensee c.' Refueling 3.Auturnatic Scram.

Event Report (LER) File (NUREG-D. Regulatory Restriction 4 -Continuations 0161)

E Operator Training & License Examination 5'-Ioad Ibduction 5

F-Administrative G. Operational Error (Exp!. tin) 9-Other (Explain)

Exhibit 1.Same Source (9/77)

Il Oth:r (Exp!:in)

• I [

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z f k;!'e%. c D

HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE. REPORTED FOR DECEMBER 1983 NUMBER' DATE COMPLETE DESCRIPTION 83-2574 05-25-83 MPL # 2Cll-F090A, F092A CRD Vents & Drains. Repaired the leaking valves 2Cll-F090A &

2Cll-F092A. Ref. DCR 82-206.

183-8358~

12-06-83' MPL # 1831-N007A&B.

Installed a new recirculation flow switen.

Ref. DCR 83-254.

82-1378 05-31-83 MPL 2X45 Hot Machine Shop Flow Drain Piping Cut Out &

removed concrete in floor of hot machine shop. Repoured the concrete & fitted in the necessary expansion joint.

Engineering sketches B-C-79-476-1 Rev. A, b-P-79-476-22-Rev. A &

P-P-79-476-18-Rev. A were used. Ref. DCR 79-476.

82-2572 09-16-83 MPL # 2P70-F103A&B Drywell Pneumatic System. Changed the setpoint of 2P70-PS-N003 from 75 psig to 92 + 1.5 psig & _ changed setpoint of 1

2P70-F103A&B from 90 psig to 97 + 2.0 psig. Ref. DCR 81-Il2, FDR 81-112-1.

82-2785 09-16-83 MPL 2P70-N017 Drywell Pneumatic System Supply Line High Pressure Switch.

Calibrated 2P70-N017. Ref.

DCR 81-112.

83-1967 06-15-83 Process Computer. Installed the circuit breaker 2R26-M062 in AC inverter room Unit 2 as per attached sheet. Ref. DCR 82-172.

83-2865 07-11-83 MPL 2TE-2534, states block T.B.-AA replaced states block and cable associated with it (2821-N301A) Ref.81-139.

83-4362 08-31-83 MPL 2P33-N054, N055 Post Accident boron and Chloride Analyzer. Installed two pressure gauges upstream &

downstream of analyzers.

Ref. FDR 79-476-102, DCR 79-476.

e

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HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR DECEMBER 1983 83-6002 11-21-83 Diesel Generators 2A & 2C Reverse Power Relays, Changed setpoint on the ICW reverse power relays to 50 watts per attached relay

-data sheets. Re f. DCR 82-110.

83-2177 09-07-83 Distribution panels fabricated & placed steel numbers, reinforcing borg, &

embedded conouit as shown on FDR 82-172-4. Framed &

poured concrete pad for panels R25-50107 &

2R25-5132. Ref. DCR 82-172.

83-2323 11-01-83 CRD Vents & Drains.

Installed indication lights for valves 2C11-F235A&B &

2C11-F037 on panel 2Hil-P603. Also relocated nameplate 428 & installed nameplates 651, 652, 653, &

654 per sketches B-J-82-206-S, Rev. A &

B-J-82-206-6-Rev.

A. Ref.

DCR 82-206.

7.-

• Georgi 3 Power Company

=

Post Office Box 439

,e Baxley, Georgia 31513 Telephone 912 367-7781 912 537-9444 Edwin I. Hatch Nuclear Plant Januar-/ 10, 1984 GM-84-18

' PLANT E.

I. HATCH NRC Monthly Operating Report

' 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 please find attached the NRC Monthly Operating Report for Hatch Unit 1, Docket #50-321, and for. Hatch Unit 2, Docket #50-366.

VW M

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C.

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Ganeral Man (ager HLS/hh i

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