ML19344B534

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Monthly Operating Rept for Sept 1980
ML19344B534
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 10/10/1980
From: Underwood P
GEORGIA POWER CO.
To:
Shared Package
ML19344B529 List:
References
NUDOCS 8010210421
Download: ML19344B534 (6)


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  • OPERATING DATA REPORT l

DOCKET NO.80-321 DATE 10-10-80 COSIPLETED BY Pz t undarwood TELEPHONE 112-J6/-/781 OPERATING STATUS

' latch 1 Notes I 1. Unit Name:

2. Reporting Period: 9-80 i
3. Licensed Thermal Power (Mb ti: 74'26 4'
4. Nameplate Rating (Gross SIWE): 809.3 .
5. Design Electrical Rating (Net 5tWe): 777.3
6. Maximum Dependable Capacity (Gross SIWE): 796.3
7. Staximum Dependable Capacity (Net alwe): 764.3
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
9. Power Lesel To which Restricted. If Any (Net SIWE):
10. Reasons For Restrictions.If Any:

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This Manth Yr..to.Date Cumulatise

. II. Hours in Reporting Pesiod 720 6575 41639 '

12. Number Of Hours Reactor Was Critical 703.5 _' 5593.3 31391.3
13. Reactor Resesse Shutdown Hours 0.0 O.0 0.0 4
14. Hours Generator On Line 693.0 5153.I 29421.5
15. Unit Reserve Shutdown Hours nn 0.0 0.0 j u 16. Gross Thermal Energy Generated _(MWH) 1575954 13588807 61941842-

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17. Gross Electrical Energy Gener'sted (SIWH1 509060 _ , _ ,

3784830 20055770 '

18. Net Electrical Energy Generated (5tWH) 487132 3606894 10068827
19. Unit Sersice Factor 96.2 78.4 70.7
20. Unit Availability Factor 96.? 78.4 70.7 )
21. Unit Capacity Factor IUsing SIDC Nett 88.5 71.8 s;o . g
22. Unit Capacity ' Factor IUsing DER Net) 87.0 70.6 58.9 4
23. Unit Forced Outage Rate 3.8 21. 6 _, 20.9
24. Shutdowns Scheduled Oser Next 6 Stonths (Type, Date.and Duration of Eacht: .

Refuelino and torus work, 3-1-81. 13 wks.

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25. If Shut Down At Er.J Of P.eport Period. Estimated Date of Startup:
26. Units in Test Status tPrior to Commercial Operationi: Forecast Achiesed I

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INITIA L CRITICALITY INITIA L ELECTRICITY l-i Coil \tERCIA L OPER ATION i

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8010210

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-321 (JNIT Hatch 1 DATE 10-10-80 4 C0\1PLETED BY P. R. Underwood

_ TELEPilONE 912-367-7781 C: MONTil 9-80 -

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL *

(MWe-Net) (MWe. Net i 3 746 751 17 2 744 is 753 3 741 748 19 4 447 20 743 5 429 21 391 6 574 376 22 7 635 23 691 8 622' 24 702 9 743 742 25 to -

753 26 741 11 749 27 731

"' 743 12 23 747 13 582 747 29 14 685 30 745 15 749 _

31 16 751 INSTRUCTIONS On this format. list the nerage daily unit power lese! in MWe Net for each day in the reportmg 14.inth. Compute the nearest whole megawatt.

(0177)

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DOCKETNo. 50-321 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Hatch 1 .

DATE IU-lU-W t.

COMPLETED BY P R. Underwood REPORT MONTH 9-M TELEPHONE 917-367-77H1 _ ,

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- ,$g "g' *Y3 Licensee E*, *g " . Cause & Corrective No. Daie $ Ti = g 3g& Event u A u?

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a 3 NA Hil HTEXCil Rx scram due to false high MSR level ,

80-46 800904 F 11.2 A caused by LS being grounded. 4 NA HH HTEXCH Unit on startup ramp from above shut-80-47 800904 'F 53.2 A 5 down, #80-46 12.9 D 5 NA RB CONROD ibduced load to perform rod pattern 80-48 800907 F adjustment NA RB CONROD Reduced load to perform turbine test t 80-49 800912 S 21.6 0 5 and rod pattern adjustment l 1

3 NA ZZ ZZZZZZ Rx scram due to transferring of RPS 80-50 800921 F 15.8 l

bus "B" from alt. to normal and a.

spurious trip on RPS " A" l g

3 4 i, I 2 Exhibit G-Instructions Reason: Method:

, F: Forced for Preparation of Data A liguipment Failure (Explain) 1-Manual S: Scheduled Entry Sheets for Licensee n Maintenance of Test 2 Manual Scram. .

3-Automatic Scram. Event Report ILER) File INUREG- }

C Refueling .

D-Regulatory Restriction 4 -Continuations 0161) 1 E-Operator Training & Ucense Examination 5-Ioad Ibduction i 5

' F-AdministrasIve 9-Other (Explain) Exhibit I- Same Source G-Operational Errot (Emplain) *

(9/77) liether(Emplain)

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DOCKET NO. 50-371 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Hatch 1 .

DATE 10-10-R)

COMPLETED BY P. R. (Indervood REPORT MONTH 9-80 T1ELEPliONE 912-367-7781 "t.c c Cause & Corrective l Eg Nie. Date h

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m , se Licensee Event g,7 E3 A3"" '"

Prevent Recurrence i

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$5 a'l j4c R* Port #

5 ftA ZZ ZZZZZZ Unit on startup ramp from above shut-80-51 800921 F 14.0 down, #80-50 ,

RB C0flROD ibduced load to perform a rod pattern 80-52 800923 F 4.0 D 5 f1A adjustment ftA WA FILTER Reduced load due to debris stopping  !

80-53 800927 F 1.0 B 5 '

up PSW strainers

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3 4 I 2 Exhibit G-Instructions 1 Method:

F: Forced Reason 1-Manual for Pseparation of Data S: Scheduled A-L iui ment Failure (Explain) Entry Sheets for Licensee B4taintenance of Test 2-Manual Scram.

3 Automatic Scram. Event Repost (LER) Fde INUREG-C Refueling .

0161)

D Regulatory Restriction 4 -Continuations E-Operator Training & Ucense Examination 5-Ioad Reduction 5 t F Administrative 9-Other (Explain) Exhibit I Same Source GOperational Error (Emplain)

  • l (9/77) 11Osher(Explain)

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NARRATIVE REPORT UNIT 1 Sept. 4th Rx scram at 14:39 due to false high MSR level; scram ' caused by equipment failure of the LS on the MSR; LS was grounded Sept. 4th Startup from above shutdown, #80-46; Rx critical at 20:55, and generator on line at 01:49 on Sept. 5th.; unit -returned to 80% conditions at l

07:00 on Sept. 7th c

_q-Sept. 7th Reduced load in order to perform final rod pattern adjustment from above startup; unit returned to 80% conditions at 12:00 on Sept. 8th Sept. 12th Redu*ed load in order to perform weekly turbine tests and rod pattern adjustment; unit returned to 80% conditions at 21:30 on Sept. 13th i

Sept. 21st Rx auto scram at 12:53 due to the transferring of RPS channel "B" bus from alt to normal and a l spurtous trip on RPS channel "A"

. Sept. 21st Startup from above shutdown, #80-50; Rx critical at 23:05,- and generator on line at 04:44 on Sept. 22nd; unit returned to 80% conditions at t ;

3 18:45, Sept. 22nd ,

Sept. 23rd Reduced load in order to perform a rod pattern adjustment; unit returned to 80% conditions at 02:45 on Sapt. 24th Sept. 27th Reduced load due to debris 4

stopping up PSW strainers

There was no single ' release of radioactivity or single radiation exposure which accounts for more than 10% of the allowable annual-values during September of 1980.

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  • HATCH 1 SAFETY - RELATED MAINTENANCE REQUESTS TO BE-REPORTED FOR' SEPTEMBER 1980 NUMBER DATE COMPLETED DESCRIPTION 50-4447 6-26-80 Calibrated pressure switch on HCU 80-4188 8-28-80 Replaced CRD HCU pressure switch isolation valves; valves were suspected of leaking 80-4187 8-28-80 Replaced CRD HCU pressure switch g isolation valves; valves were suspected of leaking l 80-4186 8-28-80 Replaced CRD HCU pressure switch j isolation valves; valves were i suspected of leaking 80-4178 8-28-80 Replaced CRD HCU pressure switch isolation valves; valves were suspected of teaking j 80-4312 8-19-80 3/4" "B" core spray discharge test connection was found to have cracked between the nipple and j-the 3/4" valve. Replaced old pipe with new piece of pipe 80-4495 8-29-80 Snubber was found- to havc a seal l 1eak; replaced leaking snubber' with new snubber 80-4507 8-29-80 Snubber was found to have a seal

'g leak; removed snubber and rebuilt with all new parts; replaced snubber after being rebuilt 80-04429 8-28-80 Snubber was found- to be leaking fluid; replaced leaking snubber with new snubber l 80-4430 8-28-80 Snubber was .found to be leaking

! fluid; replaced leaking snubber j with new snubber l 80-4486 9-1-80 Replaced- fire detector and-j calibrated I

80-3988 8-29-80 Relocation of #2 fire pump controller D

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