ML19344B546: Difference between revisions
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{{#Wiki_filter:, . - . . . . . - . | {{#Wiki_filter:, . - . . . . . - . | ||
AVER AGE DAILY UNIT POWER LEVEL e | |||
AVER AGE DAILY UNIT POWER LEVEL | |||
e | |||
. DOCKET NO.. 50-289 I | . DOCKET NO.. 50-289 I | ||
3.IT TMI-I i | 3.IT TMI-I i | ||
DATE October 15. 1980 CO%fPLETED BY D. G. ' ?titchell'- | DATE October 15. 1980 CO%fPLETED BY D. G. ' ?titchell'- | ||
TELEPHONE (717) 948-8553 MONTH September 1980- | TELEPHONE (717) 948-8553 MONTH September 1980-DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe Neti iMWe Net) i i O , | ||
DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe Neti iMWe Net) i i O , | |||
37 _ | 37 _ | ||
0 2 0 g3 0 3 0 - 39 0 | 0 2 0 g3 0 3 0 - 39 0 | ||
Line 41: | Line 31: | ||
0 0 25 I | 0 0 25 I | ||
10 0 26 | 10 0 26 | ||
^0 l 11 27 0 12 0 o 33 | ^0 l 11 27 0 12 0 o 33 13 29 0 14 0 0 30 15 0 3, o 16 0 i | ||
13 29 0 14 0 0 30 15 0 3, o | |||
16 0 | |||
i | |||
8010210 4 -- _ . , . . . _ -_ . . . ,. _ . , _ _ __ | 8010210 4 -- _ . , . . . _ -_ . . . ,. _ . , _ _ __ | ||
+ | + | ||
OPERATLNG DATA REPORT DOCKET NO. 50-289 DATE October 15, 1980 COMPLETED BY D. G._Mitchell TELEPHONE (717) 948-8553 OPERATING STATUS Three Mile Island Nuclear Station, Unit I | |||
OPERATLNG DATA REPORT | |||
DOCKET NO. 50-289 DATE October 15, 1980 COMPLETED BY D. G._Mitchell TELEPHONE (717) 948-8553 OPERATING STATUS Three Mile Island Nuclear Station, Unit I | |||
: 1. Unit Name: , | : 1. Unit Name: , | ||
: 2. Reporting Period: September 1980 2535 | : 2. Reporting Period: September 1980 2535 | ||
Line 88: | Line 64: | ||
: 20. Unit Availability Factor | : 20. Unit Availability Factor | ||
: 21. Unit Capacity Factor iUsing MDC Net) 0.0 0.0 56.8 | : 21. Unit Capacity Factor iUsing MDC Net) 0.0 0.0 56.8 | ||
: 22. Unit Capacity Fcetor (Using DER Net) 0.0 0.0 54.6 | : 22. Unit Capacity Fcetor (Using DER Net) 0.0 0.0 54.6 | ||
: 23. Unit Forced Outage Rate 100.0 100.0 u,1 | : 23. Unit Forced Outage Rate 100.0 100.0 u,1 | ||
Line 97: | Line 72: | ||
10/77) | 10/77) | ||
DOCKET NO. | DOCKET NO. | ||
50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS ,I.H L-1 UNIT NAME DATE 10-15-80 REPORT MONTH September COMPLETED RY D. C. Mitchell. | 50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS ,I.H L-1 UNIT NAME DATE 10-15-80 REPORT MONTH September COMPLETED RY D. C. Mitchell. | ||
TELEPHONE (717) 948d553 1 ._ | TELEPHONE (717) 948d553 1 ._ | ||
, .3 ? 3g hY Licensee ,E*, f% Cause A Corrective | , .3 ? 3g hY Licensee ,E*, f% Cause A Corrective | ||
Line 106: | Line 79: | ||
* $5 Report *r mv 5L Prevent Reuntence c2 35t | * $5 Report *r mv 5L Prevent Reuntence c2 35t | ||
< u b | < u b | ||
*#" #7 " 8 "" " '# | *#" #7 " 8 "" " '# | ||
I 9-1-80 F 720 D 1 1 2 3 4 F: Fort ed Reason: Metimd: Exhibit G -Instructions S: Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram- Entry Sheets for Licensee C Refueling 3-Automatie Scram. Event Repori t1.ERI File INURI G-D-Regulatory Restriction 4-Oiher ( Explain) 0161) | I 9-1-80 F 720 D 1 1 2 3 4 F: Fort ed Reason: Metimd: Exhibit G -Instructions S: Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram- Entry Sheets for Licensee C Refueling 3-Automatie Scram. Event Repori t1.ERI File INURI G-D-Regulatory Restriction 4-Oiher ( Explain) 0161) | ||
E-Operator Training & License INamination | E-Operator Training & License INamination F Administrative 5 G-Opergtional I.iror (INplain) E xhibit I - Same Source Il-Olher ( E xplain) | ||
F Administrative 5 G-Opergtional I.iror (INplain) E xhibit I - Same Source Il-Olher ( E xplain) | |||
_ f. | _ f. | ||
~ | ~ | ||
y , | y , | ||
+ | + | ||
OPERATING SU!e!ARY | OPERATING SU!e!ARY | ||
Line 130: | Line 91: | ||
f | f | ||
; The' Unit was shutdown the entire month as a result of 3/28/79, ? | ; The' Unit was shutdown the entire month as a result of 3/28/79, ? | ||
2 Unit 2 accident. Core cooling was provided by the' Decay Heat | 2 Unit 2 accident. Core cooling was provided by the' Decay Heat Removal System. , | ||
MAJOR SAFETY RELATED MAINTENANCE. | MAJOR SAFETY RELATED MAINTENANCE. | ||
; While'.thel Unit was in cold shutdown. condition, the following I | ; While'.thel Unit was in cold shutdown. condition, the following I | ||
major > maintenance _. item was performed. | major > maintenance _. item was performed. | ||
Diesel [ Generator "A''' (EG-Y-1A) repair and; preventive maintenance! items were completed. This included.in-spection 'and repair -of generator bearing, compressor | Diesel [ Generator "A''' (EG-Y-1A) repair and; preventive maintenance! items were completed. This included.in-spection 'and repair -of generator bearing, compressor | ||
; | ; | ||
' overhaul,-instrument calibration, oil leak repairs, and exhaust manifold leak-repcirs. All associated . | ' overhaul,-instrument calibration, oil leak repairs, and exhaust manifold leak-repcirs. All associated . | ||
work was performed with satisfactc.y: test results l and wh'ile Emergency Diesel Generator "B'' remained l | work was performed with satisfactc.y: test results l and wh'ile Emergency Diesel Generator "B'' remained l | ||
operable. .; | operable. .; | ||
Line 148: | Line 103: | ||
l , | l , | ||
f i _ | f i _ | ||
1 i | 1 i | ||
J | J | ||
Line 155: | Line 108: | ||
r l | r l | ||
g' , | g' , | ||
L4 1 | |||
L4 | |||
1 | |||
l | l | ||
.i | .i | ||
? I | ? I | ||
REFUELING'INFORMATION REOUEST | REFUELING'INFORMATION REOUEST | ||
.l .' Name of Facility: | .l .' Name of Facility: | ||
'Three Mile Island. Nuclear Station, Unit I | 'Three Mile Island. Nuclear Station, Unit I | ||
: 2. Scheduled date for next refueling shutdown: | : 2. Scheduled date for next refueling shutdown: | ||
Line 180: | Line 120: | ||
'3. Scheduled date for restart following refueling: | '3. Scheduled date for restart following refueling: | ||
Unknown | Unknown | ||
: 4. Will refueling or resumption of operation thereafter' require a technical | : 4. Will refueling or resumption of operation thereafter' require a technical specification change or other license amendment? | ||
specification change or other license amendment? | |||
;- If answer is yes, in general, what will these be? | ;- If answer is yes, in general, what will these be? | ||
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety-Review Committee to-determine whether | If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety-Review Committee to-determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)? | ||
any unreviewed safety questions are associated with the core reload | |||
(Ref. 10 CFR Section 50.59)? | |||
If no auch review has taken place, when is it scheduled? | If no auch review has taken place, when is it scheduled? | ||
l Amendment No. 50, Cycle 5 reload, was approved on 3-16-79. | l Amendment No. 50, Cycle 5 reload, was approved on 3-16-79. | ||
Line 201: | Line 135: | ||
'The present' licensed capacity is>752. There are no planned increases at this time. | 'The present' licensed capacity is>752. There are no planned increases at this time. | ||
: 9. The projected ~date ofLthe last refueling that can be discharged to the spent ufuel. pool' assuming the present licensed capacity: | : 9. The projected ~date ofLthe last refueling that can be discharged to the spent ufuel. pool' assuming the present licensed capacity: | ||
1986 is-the last refueling discharge which allows full core off-load capacity'(177 fuel assemblies). | 1986 is-the last refueling discharge which allows full core off-load capacity'(177 fuel assemblies). | ||
l 4 !}} | l 4 !}} |
Revision as of 06:59, 31 January 2020
ML19344B546 | |
Person / Time | |
---|---|
Site: | Three Mile Island ![]() |
Issue date: | 10/15/1980 |
From: | Mitchell D METROPOLITAN EDISON CO. |
To: | |
Shared Package | |
ML19344B543 | List: |
References | |
NUDOCS 8010210431 | |
Download: ML19344B546 (5) | |
Text
, . - . . . . . - .
AVER AGE DAILY UNIT POWER LEVEL e
. DOCKET NO.. 50-289 I
3.IT TMI-I i
DATE October 15. 1980 CO%fPLETED BY D. G. ' ?titchell'-
TELEPHONE (717) 948-8553 MONTH September 1980-DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe Neti iMWe Net) i i O ,
37 _
0 2 0 g3 0 3 0 - 39 0
- 4- 0 20 0
- 5 0 ::
- 6- 0 22 0 i
7 0 23 0 8 0 2.g 0 9
0 0 25 I
10 0 26
^0 l 11 27 0 12 0 o 33 13 29 0 14 0 0 30 15 0 3, o 16 0 i
8010210 4 -- _ . , . . . _ -_ . . . ,. _ . , _ _ __
+
OPERATLNG DATA REPORT DOCKET NO. 50-289 DATE October 15, 1980 COMPLETED BY D. G._Mitchell TELEPHONE (717) 948-8553 OPERATING STATUS Three Mile Island Nuclear Station, Unit I
- 1. Unit Name: ,
- 2. Reporting Period: September 1980 2535
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
871 019
- 5. Design Electrical Rating (Net MWe):
840
- 6. Maximum Dependable Capacity (Gross MWe):
776
- 7. Maximum Dependable Capacity (Net MWe):
- 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 MWe):
- 10. Reasons For Restrictions.If Any:-
j
- This Month Yr..to.Date Cumularise I 11. Hours In Reporting Period 720. 6575. s1104.
- 12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.8
- 13. Reactor Reserve Shutdown Hours
- 0. O. 839.5 0.0 0.0 31180.9
- 14. Hours Generator On.Line U*U 0.0 0.0
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH) 0.0 0.0 76531071.
O. O. 25464330.
- 17. Gross Electrical Energy Generated (MWH)
- u. u. zJd40us).
- 18. Net Electrical Energy Generated (MWH) 0.0 0.0 58.5
- 19. Unit Service Factor U*U U*U 58.5
- 20. Unit Availability Factor
- 21. Unit Capacity Factor iUsing MDC Net) 0.0 0.0 56.8
- 22. Unit Capacity Fcetor (Using DER Net) 0.0 0.0 54.6
- 23. Unit Forced Outage Rate 100.0 100.0 u,1
- 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Destion of Each):
I
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
'26. Units In Test Status (Prior to Commercial Operation): Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION I l
10/77)
DOCKET NO.
50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS ,I.H L-1 UNIT NAME DATE 10-15-80 REPORT MONTH September COMPLETED RY D. C. Mitchell.
TELEPHONE (717) 948d553 1 ._
, .3 ? 3g hY Licensee ,E*, f% Cause A Corrective
' No. Date g 3g jg5 Event -7 g o.3 Action to
- $5 Report *r mv 5L Prevent Reuntence c2 35t
< u b
- " #7 " 8 "" " '#
I 9-1-80 F 720 D 1 1 2 3 4 F: Fort ed Reason: Metimd: Exhibit G -Instructions S: Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram- Entry Sheets for Licensee C Refueling 3-Automatie Scram. Event Repori t1.ERI File INURI G-D-Regulatory Restriction 4-Oiher ( Explain) 0161)
E-Operator Training & License INamination F Administrative 5 G-Opergtional I.iror (INplain) E xhibit I - Same Source Il-Olher ( E xplain)
_ f.
~
y ,
+
OPERATING SU!e!ARY
?
f
- The' Unit was shutdown the entire month as a result of 3/28/79, ?
2 Unit 2 accident. Core cooling was provided by the' Decay Heat Removal System. ,
MAJOR SAFETY RELATED MAINTENANCE.
- While'.thel Unit was in cold shutdown. condition, the following I
major > maintenance _. item was performed.
Diesel [ Generator "A (EG-Y-1A) repair and; preventive maintenance! items were completed. This included.in-spection 'and repair -of generator bearing, compressor
' overhaul,-instrument calibration, oil leak repairs, and exhaust manifold leak-repcirs. All associated .
work was performed with satisfactc.y: test results l and wh'ile Emergency Diesel Generator "B remained l
operable. .;
1 i
l ,
f i _
1 i
J
( .!
r l
g' ,
L4 1
l
.i
? I
REFUELING'INFORMATION REOUEST
.l .' Name of Facility:
'Three Mile Island. Nuclear Station, Unit I
- 2. Scheduled date for next refueling shutdown:
Unknown
'3. Scheduled date for restart following refueling:
Unknown
- 4. Will refueling or resumption of operation thereafter' require a technical specification change or other license amendment?
- - If answer is yes, in general, what will these be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety-Review Committee to-determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
If no auch review has taken place, when is it scheduled?
l Amendment No. 50, Cycle 5 reload, was approved on 3-16-79.
l
- 5. Scheduled date (s) for submitting proposed. licensing action and supporting information:
! N/A l 6. Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating .
l' procedures:
l N/A 1
l 7. .The ~ number of fuel assemblies (a) in the core, and (b) in the spent fuel l storage pool:
(a). 177-(b) 208' *
- 8. The present licensed spent fuel pool storage capacity and.the size of any increase in licensed storage capacity that-has been requested or is planned,'in numberfof fuel assemblies:
'The present' licensed capacity is>752. There are no planned increases at this time.
- 9. The projected ~date ofLthe last refueling that can be discharged to the spent ufuel. pool' assuming the present licensed capacity:
1986 is-the last refueling discharge which allows full core off-load capacity'(177 fuel assemblies).
l 4 !