ML19210A802
| ML19210A802 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/03/1978 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210A779 | List: |
| References | |
| NUDOCS 7910310688 | |
| Download: ML19210A802 (12) | |
Text
. P. AGE DAILY UNIT PC'4ER LEVEL Dceket No.
50-289 Unit TMI-1 Date 5-3-78 Cor::pleted By D. G. Mitchell Telephone (215)929-3601 Ext. 169 DAY AVERAGE DAILY PO'4ER LEVEL DAY AVERAGE DAILY P0kTR LEVEL (K4e-Net)
(Kle-Net) 1
-5 17
-6 2
-5 18
-9
-6 19
-9 3
h
-6 20
-9
-5 21
-10 5
6
-6 22
-9 7
-5 23
-9 8
-5 2h
-10
-6 9
25
-13
-6 26
-32 10
-6 11 27
-35
~5 28
-30 12
-5 29
-39 13 1h
-5 30
-39
-5 31
- .5 16
-5
}Sv' 0:0 1910s3og;jsg
OPERATING DATA REPORT Docket No.
50-239 5'3'i0 Date Cccpleted By
- D. G. Mitchell OPEPATING STATUS Telephone 215-929-3601 Ex+.
1.
Unit Name: Three Mile Island Unit 1 2.
Reporting Period:
April, 1970 3
Licensed Ther=al Power (Wt):
SM h.
Nameplate Rating (Gross We):
871 5
Design Electrical Rating (Net KJe): 019 840 6.
Max. Dependable Capacity (Gross M'Je):
7 Max. Dependable Capacity (Net We):
voo 8.
If Changes Occur in Capacity Ratings (Items No. 3 through 7) Since Last Report, Give Reasons:
9 Power Level to which Restricted. If Any (Net We):
0111 'v NRC must review letter from BY4 on Small 10.
Reasons fcr Restrictions If Any:
Break LOCA Analysis.
This Month Yr.-to-Date Cumulative 719 2879
,2_caq
- 11. Hours in Reporting Period 47 1,871 24,929.3 12.
No. of Hours Reactor was Critical 0
0 838.5 13 Reactor Reserve Shutdovn Hours 0
1824 2k,421.5 lb. Hours Generator On-Line 0
0 0
15 Unit Reserve Shutdown Hours 0
4,469,915 59,863,450
- 16. Gross Thermal Energy Generated (!GH) 17 Gror-Elect. Energ7 Generated (WH) 0 1,h91.077 19,985,779
- 18. Net Electrical Energy Generated (WH) 0 1,392,271 18.710.670 0
,;1. h 76.1 19 Unit Service Factor 0
63.h 76.1 20.
Unit Availability Factor 61.1 73.6 21.
Unit Capacity Factor (Using MDC Net) 59.0 71.o 22.
Unit Capacity Factor (Using DER Net)
~
0 0
5.2
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Mor',hs (Type, Date, and Duration of Each):
If Shut Down at End of Report Period, Estimated Date of Startup; May 2, 1973 25
- 26. Units In Test Status (Prior to Cecr.ercial Operation):
FORECAST ACHIE'E INITIAL CRITICALITY INITIAL ELECTRICITY COM'ERCIAL OPERATION 1589 OH
Docket No. 50-289 UNIT SHUTDOWNS AND POWER REDUCTAONS Unit Name TMI-1 REPORT MONTit April 1978 Date 5-3-78 Completed By D. G. Mitchell Telephongl'J-929-3601 Ext. 169 l E7 System Component Cause and Corrective No.
Date Type cu h
$g g@
Code h Code 5 Action to Prevent Recurrence 4 :r:
g ggo gpg
'S $ 8 0Ej aam m
4 h-1-78 G
719 C
1 N
r 'l O
t>
c3 L. 7 2 eason:
3
- nstrucMons 1: Forced R
Methods F
f r Preparation of Data S: scheduled A-Equipment Failure (Explain) 1-Manu al B-Maintenance or Test 2-Manual Scram.
Event Report (LER) File C-Reiheling 3-Automatic Scram.
D-Regulatory Restriction h-Other (Explain)
~
E-Operator Training & Licensee Examination F-Administrative S
G-Operational Error (Explain)
Exhibit 1 - Same Source H-Other (Explain)
OPERATING
SUMMARY
The Unit remained shutdown for the entire month for the 1978 Refueling Outage.
The Refueling Outage Milestones rhich were completed this month are as follows:
04/04/78 Replaced Reactor Vessel Head 04/10/78 Completed Local Leak Rate Testing 04/16/78 Completed Integrated Leak Rate Testing 04/24/78 Vacuum on Main Condenser 1507 033
MAINTENANCE
SUMMARY
The refueling outage continued throughout the month with breakers beino closed on May 2,1978. The refueling outage work performed included:
(1)
Fuel transfer canal drained and decantaminated (2) Upper plenum installed (3) Reactor vessel head installed (4) New incores installed (5) CRDM's and APSR's coupled (6) Reactor vessel head tensioned (7) Reactor vessel head cables connected (8) Reactor vessel head fans installed Other maintenance activities performed during the refueling outage are outlined below:
Local leak rate testing of containment isolation valves was narformed satisfactorily with the t6i;ai leakage below the acceptance level.
Integrated leak rate test of the reactor building was performed with satisfactory results.
Eddy current inspection of OTSG "A" and "B" resulted in the tube plugging of one (1) tube in OTSG "A" and one (1) tube in OTSG "B" as preventive measures only.
RC-p-1B #2 and #3 seal inspection was completed with the installation of these seals and the coupling of motor to pump.
RC-P-lC #1, #2, and #3 seals were installed and the motor and pump coupled.
Attempts to rotate the pump and motor by hand, after the satisfactory completion of the Integrated Leak Rate test of the reactor building, failed. The RC-P-lC was again disassembled. A bolt (5/8" diameter x 4" long) was found on top of the pump radial bearing. The following precautions were.taken:
(1) pump shaft was lifted approximately 1" off of backseat to verify that no other foreign material was lodged in the pump cavity, (2) the shaft alley was flushed witn demineralized water. The pump was assembled with no problems noted.
The Decay Heat pumps lA and 1B were disassembled, one at a time, to replace the pump shafts. Disassembly of pumps included:
(1) Uncoupling of motor from pump (2) Disassembly of pump parts (3)
Inspection and cleanup of pump parts (4) Replacement of pump shaft and worn parts (5) Reassembly of pump parts (6) Modification to pump stuffing box cooling water lines and drain water lines (7) Alignment of motor to pump (8)
Inrtallation of coupling (9) Satisfactory testing of pump The pump shaft replacement completed an NRC committment.
1539 034
CA-V-13 was inspected, after an initial leak rate test of the valve passed satisfacorily, to fulfill a NRC comittment. The valve was disassembled, valve parts inspected / cleaned, worn parts replaced, and reassembled. After the valve was reassembled, another leak rate test was performed satis-factorily.
The snubber test program was performed satisfactorily during the month.
Snu5ber work included:
Removal, testing, repair / adjustment of bleed rates, installation, and Tech.
Spec. surveillance MU-V-74A&B repacks were performed to complete an NRC committment. Valves were repacked and tested satisfactorily.
15;;
035
AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-289 Unit TMI-1 Date 5-3-78 Co=pleted By D. G. Mitchell Telephone (215)929-3601 Ext. 169 MONTH April DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (KJe-Net)
(Kle-Net) 1
-5 17
-6 2
-5 18
-9
-6 19
-9 3
h
-6 20
-9 5
-5 21
-10 6
-6 22
-9 7
-5 23
-9 8
-5 24
-10
-6 9
25
-13
-6 26
-32 10
-6 11 27
-35
-5 28
-38 12
-5 29
-39 13 1h
-5 30
-39
-5 31 15 16
-5
- c. - '
IJ /
OPERATING DATA REPORT Docket No.
50-289 5-3-70 Date Completed By.
D. G. Mitchell OPERATING STATUS Telephone 215-929-3601 Dct.I 1.
Unit Name: Three Mile Island Unit 1 2.
Reporting Period:
April, 1976 3
Licensed Thermal Power (K4t):
m k.
Na eplate Rating (Gross Kle):
871 5
Design Electrical Rating (Net MWe): 819 6.
Max. Dependable Capacity (Gross XJe):840 7
Max. Dependable capacity (Net Kle):
voo 8.
If Changes occur in Capacity Ratings (Items No. 3 through 7) Since Last Report, Give Reasons:
9 Power Level to which Restricted. If Any (Net KJe):
2711 v +
v 10.
Reasons for Restrictions, If Any:
NRC tust review letter from B&W on S=all Break LOCA Analysis.
This Month _
Yr.-to-Date Cumulative 719 2870 19_nAA 11.
Hours in Reporting Period 47 1,871 24,929 3 12.
No. of Hours Reactor was Critical 13 Reactor Reserve Shutdown Hou s 0
0 838.5 0
1824 24,h21.5 1k.
Hours Generator On-Line 0
0 0
15 Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (M4H) 0 4,469,915 59,863,450 17 Gross Elect. Energy Generated (F4H) 0 1,h91.977 19,985,779
- 18. Net Electrical Energy Generated (V4H) 0 1,392,271 18,710.670 0
62.L 76.1 19 Unit Service Factor 0
63.4 76.1 20.
Unit Availability Factor 21.
Unit Capacity Factor (Using MDC Net) 61.1 73.6 22.
Unit Capacity Factor (Using DER Net) 59.0 71.o 0
0 5.2 23.
Unit Forced Outage Rate 2h.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25 If Shut Down at End of Report Period, Estimated Date of Startupt May 2, 1978
'6.
Units In Test Status (Prior to Co=mercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL C 3 RATION
, m 077 N
\\JUr
OPERATING
SUMMARY
The Unit remained shutdown for the entire month for the 1978 Refueling Outage.
The Refueling Outage Milestones which were completed this month are as follows:
04/Os eplaced Reactor Vessel Head 34/10/78 impleted Local Leak Rate Testing 04/16f78 Completed Integrated Leak Rate Testing 0A'24/78 Vacuum on Main Condenser 509 0
o
Docket No. 50-289 UNIT SHUTD3WNS AND POWER REDUCTIONS Unit Name'fMI-l REPORT MONTH April 1978 Dste 5-3-7fl Completed L/
D. G. Mitchell Telephont.jl5-929-3601 Ext,. 169 l E7 System Component Cause and Corrective No.
Date Type a>
h
$g g'
Code h Code 5 Action to O
Prevent Recurrence g
ggo g
g fi 5 8 8Ej o
M 6lE n ii n m
co 4
h-1-78 s
719 e
i un 6
2 eason; 3
- nstruedons 1F: Forced R
Methods f r Preparation of Data S: Eicheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.
Event Report (LER) File C-Re fueling 3-Automatic Scram.
D-Regulatory Restriction h-Other (Explain)
E-Operator Training & Licensee Examination F-Administrative G-Operational Error (Explain)
Exhibit 1 - Same Source H-Other (Explain)
MAINTENANCE
SUMMARY
The refueling outage continued throughout the month with breakers being closed on May 2, 1978. The refueling outage work performed included:
(1)
Fuel transfer canal drained and decontaminated (2) Upper plenum installed (3) Reactor vessel head installed (4) New incores installed (5) CRDM's and APSR's coupled (6)
Reactor vessel head tensioned (7)
Reactor vessel head cables connected (8) Reactor vessel head fans installed Other maintenance activities performed during the refueling outage are outlined below:
Local leak rate testing of containment isolation valves was performed satisfactorily with the total leakage below the acceptance level.
Integrated leak rate test of the reactor building was performed with satisfactory results.
Eddy current inspection of OTSG "A" and "B" resulted in the tube plugging of one (1) tube in OTSG "A" and one (1) tube in OTSG "B" as preventive measures only.
RC-P-1B #2 and #3 seal inspection was completed with the installation of these seals and the coupling of motor to pump.
t RC-P-1C #1, #2, and #3 seals were installed and the motor and pump cnupled.
Attempts to rotate the pump and motor by hand, after the satisfactory completion of the Integrated Leak Rate test of the reactor building, failed. The RC-P-lC was again disassembled. A bolt (5/8" diameter x 4" long) was found on top of the pump radial bearing. The following precautions were taken:
(1) pump shaft was lifted approximately 1" off of backseat to verify that no other foreign material was lodged in the pump cavity, (2) the shaft alley was flushed with demineralized water. The pump was assembled with no problems noted.
The Decay Heat pumps lA and 1B were disassembled, one at a time, to replace the pump shafts. Disassembly of pumps included:
(1) Uncoupling of motor from pump (2) Disassembly of pump parts (3)
Inspection and cleanup of pump parts (4) Replacement of pump shaft and worn parts (5) Reassembly of pump parts (6) Modification to pump stuffing box cooling water lines and drain water lines (7) Alignment of motor to pump (8)
Installation of coupling (9) Satisfactory testing of pump The pump shaft replacement completed an NRC committment.
}bu]
b
CA-V-13 was inspected, after an initial leak rate test of the valve passed satisfacorily, to fulfill a NRC connittment. The valve was disasse'mbled,,
valve parts inspected / cleaned, worn parts replaced, and reassembled. After valve was reassembled, another leak rate test was performed satis-the factorily.
The snubber test program was performed satisfactorily during the month.
Snubber work included:
Removal, testing, repair / adjustment of bleed rates, installation, and Tech.
Spec. surveillance MU-V-74A&B repacks were performed to complete an NRC committment. Valves were repacked and tested satisfactorily.
15C9 04i i
l s
I