ML20066D430
| ML20066D430 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/15/1982 |
| From: | Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20066D403 | List: |
| References | |
| NUDOCS 8211110335 | |
| Download: ML20066D430 (10) | |
Text
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OPERATING DATA REPORT DOCKET NO.
50-289 DATE October 15,1982 s
COMPLETED BY C. W. Smyth TELEPHONE r n 7) wax-sssi OPERATING STATUS Three Mile Island Nuclear Station, Unit I
'1. Unit Name:
- 2. Reporting Period:
September, 1982 2535
- 3. Licensed Thermal Power (MWt):
871
- 4. Namepiste Rating (Gross MWe):
019
- 5. Design Electrical Rating (Net MWe):
840
- 6. Maximum Dependable Capacity (Gross MWe):
i/6
- 7. Maximum Dependable Capacity (Net MWe):
S. If Changes Occur in Capadty Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
- 9. PowrJ level To Which Restrkted,1f Any (Net MWe):
10.;REasins For Restrictions. lf Any:
This Month Yr.-to-Date Cumulative r
720.
6551.
70824.
- 11. Hours in Reporting Period
- 12. Number Of Hours Reactor was Critica!
0.0 0.0 31731.S 0.0 0.0 839.5
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9
- 14. Hours Generator On-Line 0.0 0.0 0.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.
l
- 16. Gross Thermal Energy Generated (MWH) 0.
O.
2 464330.
- 17. Gross Electrical Energy Generated (MWif) v.
a d4u m.
u.
IS. Net Electrical Energy Generated (MWH) 0.0 0.0 44.0
- 19. Unit Service Factor U*U UU 44.0
- 20. Unit Availability Factor 0,0 42.9 0.0
- 21. Unit Capacity Factor (Nsing MDC Net) 0.0 0.0 41.1
- 22. Unit Capacity Factor (Using DER Net) 100.0 100.0 50.9
- 23. Uni: Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Each):
s-
~
- 25. if, Shut Down At Endpf Rehrt Period. Estimated Date of Startup:
A "26. " Units in Test Status (Prior to Cominersial Oper. tion):
Fore St Achieved
- s
~
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION t
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8211110335 G21015
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AVE.. AGE DAILY UNIT POWER LEVEL
/
DOCKET NO.
50-289 THI-I m'IT October 15,'1982 DATE COMPLETED BY C. W. Smyth (717)d43-8551 TELEPHONE MONTH September 1982 DAY AVERAGE IL P WER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net I7 0
0 2
0 gg 3
0 o
,9 4
0 0
20 0
5 0
21 o
6 0
0 7
0 23 8
0 0
24 9
25 0
0 0
10 26 II 27 0
0 12 28 0
0 13 29 0
0 14 30 0
0 15 31 0
16 0
e - -
n n
w
s l
50-289 DOCKET NO.
UNIT N AME 'lill-1 DATE 10/15/82 REPORT MONT11 September 1982 COMPLETED BY C._L Smyth TELEPHONE (717) 948-8551 n.
C C
P0 3 t 3D LIC "5 e
't 4
Cause & Corrective No*
Date E
'S,E 5
g-5y
~
.c g oc Event uy al Action ein UQ n
$E 5
jdiy Report *
<$0 0
Psevent Recurrence d
4 i
1 1
820901 F
720 D
1 N/A ZZ ZZZZZZ Regulatory Reason related to T"I-2 I
2 3
4 F: l'orced Reason :
Method:
Exhibit G. instructions S: Sc hetinled A l'quipment Failure (Explain) 1-Manual for Preparation of Data II.Maintena nce e.i 'I cst 2-Manual Scra m.
Entry Sheets for Licensee C-Relueling 3-Autoniatic Scram.
Event Report (LER) File (NUREG.
D-Regulatory Restriction 4 Other IExplain) 0161)
E-Ope ator haining & Iicense lixamination F-Administrative 5
G Operatjonal I:e vor IExplain)
Exhibit I. Same Source 11 Othr IExplain)
OPERATING
SUMMARY
The Unit was shutdown the entire report period by order of the NRC.
The Reactor Coolant System was partially drained to permit preparation for OTSC repairs.
Core Cooling was provided by the Decay Heat Removal System.
MAJOR SAFETY RE1ATED MAINTENANCE During the month of September, restart modifications continued.
Additionally, the following major maintenance items were performed.
1.
The Once Through Steam Generator (OTSC) Program continued with Eddy Current Testing on both the "A" and "B" generators.
All Eddy Current Test equipment was removed at the completion of testing.
Dehumidifiers were installed on both go.
ators and dehumidification tests were per-formed. Additionally, crevis dry was performed on OTSC-B.
2.
The scheduled Decay Heat (Loop "A") outage was completed with the fol-lowing work items completed.
a.
DH-P-1A Mechanical seal replacement b.
DH-P-1A 011 change "A" Decay Heat loop refilled and satisf actorily tested in ac-c.
cordance with SP 1303-11.16.
3.
Reactor Building Ventilation Fan (All-E-1)' work continued with the fol-lowing work being accomplished.
a.
All-E-1 A 1)
Balanced Fan Motor in fan unit 2)
Satisfactory Testing of motor in the fan unit b.
Spare AH-E-1 Motor 1)
Sandblasted, primed, and painted motor 2)
Disassembled motor for overhaul.
4.
Concentrated Waste Sturage Tank WDL-T-6 A/B (CWST) piping modifications commenced with the fo11cving items being acconplished.
a.
WDL-T-6A 1)
Removed insulation and heat trace 2)
Prefabricated new piping (outside cubicle) 3)
Cut out old piping.
REFUELING INFORMATION REQUEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
Unknown 3
Scheduled date for restart following refueling:
Unknown L.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
If answer is yes, in general, what vill these be?
If answer is no, has the reload fuel design and ccre configuratien been reviewed by your Plant Safety Review Con ittee te determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50 59)?
If no such review has taken place, when is it scheduled?
Amendment No. 50, Cycle 5 reload, was approved on 3-16-79 5
Scheduled date(s) for submitting proposed licensing action and supporting information:
N/A 6.
Important licensing considerations associatei vith refueling, e.g. new or different fuel design or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating procedures:
N/A T.
The number of fuel assemblies (a) in the cere, and (t) in the spent fuel stora6e pool:
(a) 177 (b) 206 6.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity th : has been requested or is planned, in number of fuel assemblies:
The present licensed capacity is 752. There are ne planned increases at this time.
9 The projected date of the las: refueling tha can be discharged to the spent fuel pool assuming the present licensed capacity:
1967 is the last refueling discharge which allevs full core eff-lead capacity (177 fuel assemblies).
j l
l OPERATING DATA REPORT DOCKET NO.
50-289 DATE october 1% 1982 COMPLETED BY C. W. Smyth TELEPHONE
'nIi
-xssi OPERATING STATUS Three Mile Island Nuclear Station, Unit I
- 1. Unit Name:
- 2. Reporting Period:
September, 1982
- 3. Licensed Thermal Power (MWt):
2535 871
- 4. Nameplate Rating (Gross MWe):
019
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe): {0 e/6
- 7. Maximum Dependable Capacity (Net MWe):
S. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:
)
- 9. Power Level To Which Restricted.lf Any (Net MWe):
- 10. Reasons For Restrictions. lf Any:
i This Month Yr to.Date Cumulative 720.
6551.
70824.
- 11. Hours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.S 0.0 0.0 839.5
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9
- 14. Hours Generator On-Line U*O 0.0 0.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.
- 16. Gross Themia! Energy Generated (MWH)
O.
O.
23454330.
- 17. Gross Electrical Energy Generated (MWH) v.
u.
m 4uusa.
- 18. Net Electrical Energy Generated (MWH) 0.0 0.0 44.0
- 19. Unit Service Factor U*O U*O 44.0
- 20. Unit Availability Factor 0.0 0.0 42.9
- 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 41.1 l
- 22. Unit Capacity Factor (Using DER Net) 100.0 100.0 50.9
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each t:
- 25. If Shut Down At Ead Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved t
INITIAL CRITICALITY l
INITIAL ELECTRICITY COMMERCIAL OPERATION (uj;;,
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 E ~I UNIT October 15, 1982 DATE COMPLETED BY C. k'. Smyth TELEPHONE (717) 948-8551 MONTH September 1982 DAY AVER AGE DAll IR LEVEL pry AVERAGE DAILY POWER LEVEL (MWe Nen I
9 17 0
2 0
0 g
3 0
o 39 4
0 0
20 5
0 0
21 6
0 0
22 7
0 0
23 8
0 0
28 0
9 25 0
0 10 26 0
II 27 0
0 12 28 0
I3 29 0
0 14
=
30 0
0 15 31 0
16 0
4 50-289 DOCKET NO.
UNIT NAME IMI-I DATE 10/15/82 REPORT MONTil September 1982 COMPl.ETED RY C._W. Smyth l
TELErff0NE (7171 948-8551 l
=
c
.! E "h
}.Y 3 Licensee 5%
c4 Cause A Corrective M'.
Date y,
5?
s
.c s E Event uT 81 Action to
$E cE j dj g Report sr N0 0
H Prevent Recurrence S
)
1 820901 F
720 D
1 N/A ZZ ZZZZZZ Regulatory Reason related to T"I-2 i
4 J
t i
2 3
4 F: Forced Reason:
Mettuid:
Exhibit G Instructions S: Scheduletl A lipiipment Failure (Explain) l-Mannal for Preparation of Data H. Maintenance e.i ~Icst 2-Manual Scram.
Enity Sheets for I.icensee C. Refueling 3-Autinuatic Scram.
Event Repose (l_ERI File (NilREG-D. Regulatory Restriction 4-Ot hes ( Explain) 0161) l
. li-Ope:atm liaining & 1.iunu Examination F Administrative 5
G.Openatjonal l'iror (lixplain)
Exhibit 1 Same Source Il-Olher ( Explain t
OPERATISC
SUMMARY
The Unit was shutdown the entire report period by order of the NRC.
The Reactor Coolant System was partially drained to permit preparation for OTSC r pairs.
Core Cooling was provided by the Decay Beat Removal System.
MAJOR SAFETY RE1XtED MAINTENANCE During the month of September, restart modifications continued.
Additionally, the following major maintenance items were performed.
1.
The Once Through Steam Generator (OTSC) Program continued with Eddy Current Testing on both the "A" and "B" generators.
All Eddy Current Test equipment was removed at the completion of testing.
Dehumidifiers were installed on both generators and dehumidification tests were per-formed.
Additionally, a crevis dry was performed on OTSG-B.
2.
The scheduled Decay Heat (Loop "A") outage was completed with the fol-lowing work items completed.
a.
DH-P-1A Mechanical seal replacement b.
DH-P-1A 011 change c.
"A" Decay Heat Loop refilled and satisfactorily tested in ac-cordance with SP 1303-11.16.
3.
Reactor Building Ventilation Fan (AH-E-1)' work continued with the fol-lowing work being accomplished, a.
AH-C-1A 1)
Balanced Fan Motor in fan unit 2)
Satisfactory Testing of motor in the fan unit b.
Spare AH-E-1 Motor 1)
Sandblasted, primed, and painted motor 2)
Disassembled motor for overhaul.
4.
Concentrated Waste Storage Tank WDL-T-6 A/B (CWST) piping modi fications commenced with the following items being accomplished.
a.
WDL-T-6A 1)
Removed insulation and heat trace 2)
Prefabricated new piping (outside cubicle) 3)
Cut out old piping.
REFUELING INFORMATION REQUEST 1.
Name of Fac'lity:
i Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
Unknown 3
Scheduled date for restart following refueling:
Unknown h.
Will refueling or resumption of operation therea'ter require a technical specification change or other license amendnent?
If answer is yes, in general, vhat vill these be?
If answer is no, has the reload fuel design and core configuratien been reviewed by your Plant Safety Review Connittee to dete:rine whether any unreviewed safety questions are assceiated with the core relcad (Ref. 10 CFR Section 50 59)?
If no such review has taken place, when is it scheduled?
Amendment No. 50, Cycle 5 reload, was ap; roved on 3-16-79 t
5 Scheduled date(s) for submitting proposed licensing action and supporting information:
N/A 6.
Important licensing considerations associatei vi h refueling, e.g. new or different fuel design or supplier, unreviewed design er perfcrmance analysis methods, cignificant changes in fuel design, new opere. ting procedures:
N/A 7
The number of fuel asseiolies (a) in the cere, e..i (t) in the spent fuel storage pool:
(a) 177 (b) 208 6.
The present licensed spent fuel pcol storage espacity and the sice of rny increase in licensed storage capacity that he.:: teen recuested or is p;.anned, in number of fuel assemblies:
The present licensed capacity is 752.
There are nc planned increases at this time.
9 The projected date of the last refueling the.: can te discharged to the spent fuel pool assuming the present licensed capacity:
1987 is the last refueling discharge which allevs full core eff-load capacity (177 fuel assemblies).
,