ML19344B534
| ML19344B534 | |
| Person / Time | |
|---|---|
| Site: | Hatch |
| Issue date: | 10/10/1980 |
| From: | Underwood P GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML19344B529 | List: |
| References | |
| NUDOCS 8010210421 | |
| Download: ML19344B534 (6) | |
Text
(.
G OPERATING DATA REPORT l
DOCKET NO.80-321 DATE 10-10-80 COSIPLETED BY Pz t undarwood TELEPHONE 112-J6/-/781 OPERATING STATUS Notes I
- 1. Unit Name:
' latch 1
- 2. Reporting Period:
9-80
- 3. Licensed Thermal Power (Mb ti:
74'26 i
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:
i 4
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
- 14. Hours Generator On Line 693.0 5153.I 29421.5 4
- 15. Unit Reserve Shutdown Hours nn 0.0 0.0 j
- 16. Gross Thermal Energy Generated _(MWH) 1575954 13588807 61941842-u
- 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
- 23. Unit Forced Outage Rate 3.8
- 21. 6 _,
20.9 4
- 24. Shutdowns Scheduled Oser Next 6 Stonths (Type, Date.and Duration of Eacht:
Refuelino and torus work, 3-1-81. 13 wks.
l'
- 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 l-INITIA L ELECTRICITY Coil \\tERCIA L OPER ATION i
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8010210 4 2... f a-
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-321 (JNIT Hatch 1 DATE 10-10-80 C0\\1PLETED BY P. R. Underwood 4
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 17 751 2
744 is 753 3
741 19 748 4
447 20 743 5
429 21 391 6
574 22 376 7
635 23 691 8
622' 24 702 9
743 25 742 to 753 26 741 11 749 27 731 12 743 23 747 13 582 29 747 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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50-321 DOCKETNo.
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Hatch 1 IU-lU-W DATE COMPLETED BY P R. Underwood REPORT MONTH 9-M t.
TELEPHONE 917-367-77H1 _,
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Cause & Corrective
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- Y3 Licensee E*
g Ti =
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Event u
9 Action to No.
Daie A u?
2 j #5 c Repori #
u p,,,,,,g,,,,,,,c, a
80-46 800904 F
11.2 A
3 NA Hil HTEXCil Rx scram due to false high MSR level caused by LS being grounded.
4 80-47 800904
'F 53.2 A
5 NA HH HTEXCH Unit on startup ramp from above shut-down, #80-46 80-48 800907 F
12.9 D
5 NA RB CONROD ibduced load to perform rod pattern adjustment 80-49 800912 S
21.6 0
5 NA RB CONROD Reduced load to perform turbine test t
and rod pattern adjustment l
1 l
80-50 800921 F
15.8 3
NA ZZ ZZZZZZ Rx scram due to transferring of RPS bus "B" from alt. to normal and a.
spurious trip on RPS " A" l
g I
2 3
4 i,
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A liguipment Failure (Explain) 1-Manual for Preparation of Data n Maintenance of Test 2 Manual Scram.
Entry Sheets for Licensee 3-Automatic Scram.
Event Report ILER) File INUREG-
}
C Refueling 4 -Continuations 0161) 1 D-Regulatory Restriction i
E-Operator Training & Ucense Examination 5-Ioad Ibduction 5
F-AdministrasIve 9-Other (Explain)
Exhibit I-Same Source G-Operational Errot (Emplain)
(9/77) liether(Emplain) j 1
i w
y
50-371 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Hatch 1 10-10-R)
DATE COMPLETED BY P. R. (Indervood REPORT MONTH 9-80 T1ELEPliONE 912-367-7781 "t.
Licensee Eg Cause & Corrective l
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Date h
38
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m, se Event g,7 E3
$5 a'l j4c R* Port #
mE' Prevent Recurrence g
H 80-51 800921 F
14.0 5
ftA ZZ ZZZZZZ Unit on startup ramp from above shut-down, #80-50 80-52 800923 F
4.0 D
5 f1A RB C0flROD ibduced load to perform a rod pattern adjustment 80-53 800927 F
1.0 B
5 ftA WA FILTER Reduced load due to debris stopping up PSW strainers
[
1 l
j i
i I
2 3
4 Method:
Exhibit G-Instructions 1
F: Forced Reason A-L ui ment Failure (Explain) 1-Manual for Pseparation of Data S: Scheduled i
B4taintenance of Test 2-Manual Scram.
Entry Sheets for Licensee 3 Automatic Scram.
Event Repost (LER) Fde INUREG-C Refueling D Regulatory Restriction 4 -Continuations 0161)
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) a 1
3
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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 3
18:45, Sept. 22nd t ;
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 stopping up PSW 4
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 suspected of leaking i
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 the 3/4" valve.
Replaced old j-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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