ML20095E074
| ML20095E074 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/31/1984 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | Mcdonald W NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 5211-84-2167, NUDOCS 8408240066 | |
| Download: ML20095E074 (11) | |
Text
OPERATING DATA REPORT 4
DOCKET NO.
50-289 DATE Aunust 16, 1984 COMPLETED BY C. W. Smvth TELEPHONE (717) 948-8551 OPERATING STATUS NOTES l
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 2.
REPORTING PERIOD:
JULY
,1984
- 3. LICENSED THERMAL POWER (MWT):
2535. l
- 4. NAMEPLATE RATING (GROSS MWE):
871.
- 5. DESIGN ELECTRICAL RATING (NET MWE):
819. !
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
824.
7 MAXIMUM DEPENDABLE CAPACITY (NET MWE):
776.
I 8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
9.
POWUM LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)
- 10. REASONS FOR RESTRICTIONS, IF ANY:
s THIS MONTH YR-TO-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.
5111.
86904.
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 838.5
- 14. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. CROSS THERMAL ENERGY GENERATED (MWH)
O.
O.
76531071.
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
25484330..
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) n.
O.
23840053.
- 19. UNIT SERVICE FACTOR 0.0 0.0 35.9 20 UNIT AVAILABILITY FACTOR 0.0 0.0 35.4
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 35.1
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 33.5
- 23. UNIT FORCED OUTAGE RATE 100.0 100.0 60,9
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH
- 25. IF 5 HUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
O R
gA
\\R
AVERACE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 DATE August 16, 1984 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 MONTH:
JULY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY DOWER LEVEL (MWE-NET)
(MWE-NET) 1 0,
17 0
2 0,
18 0
3 0
19 0
4 0
20 0
5 n.
21 0
6 0
22 n.
7 0
23 0
8 0
24 4
9 0
25 n.
10 0
26 n.
11 n.
27 n.
12 0
28 n.
13 n.
29 n.
14 n.
30 4
15 O.
31 0
4 16 n.
9
' CJ i
I I
I 50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME TML-1 DATE Aigu s t 16. 1984 COMPLETED BY C. W. Smyth REPORT MONTH July, 1984 TELEPHONE (717) 948-8551 I
5
].-o3_y e
c.
s Licensee E*
c.,
Cause & Corrective i,
.7, ?
a
=
ge Event 57 83 Action su No.
Date g
7p g g
H
&3 5
jdg Report
- N0 0
Prevent Recurrence 6
1 84-01-08 F
744 D
N/A ZZ ZZZZZZ 1
2 3
4 F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A Equipment Failure (Explain)
I-Manual for Preparation of Data B-Maintenance of Test 7-Manual Scram.
Entry Sheets for Licensee C. Refueling 3m,natic Scram.
Event ReporI (LER) File (NUREG.
D. Regulatory Restrietion 4 Osher (Explain) 016I)
E. Operator Training & I.icense Examination F-Administrative 5
G Operatjonal Error (Explain)
Exhibis 1 - Same Source i
11-0ther ( E xplain) s
~
i OPERATING
SUMMARY
The Unit was shutdown the entire month by order of the NRC. Core cooling was provided by the Decay Heat Removal System.
The RCS was partially drained the entire month to enable investigations in OTSG tube leakage.
These efforts and findings were discussed in detail in our letter to Mr. John F. Stolz, dated July 18, 1984.
MAINTENANCE
SUMMARY
Major Safety Related Maintenance l
The following major maintenance items were completed during the month:
0TSG A & B Work accomplished consisted of the completion of Eddy Current Testing, Fiberoptic Inspection of tube #148 35 ("A" 0TSG), and removal of the lower manway on the "A" 0TSG.
Repairs on the "A" 0TSG included welding plugs in the upper tubesheet in tubes #135-72 and #148-35. Repairs on the "B" 0TSG included welding plugs in the upper tubesheet in tubes #70-8, #79-41, and
- 80-45. Explosive plugs were also installed in the "B" 0TSG lower tubesheet in tubes #70-8, #77-7, #79-41, and #80-45. The upper and lower tubesheets were mapped utilizing photographs for all plugged tubes in the upper and lower tubesheets of both the "A" and "B" 0TSGs.
Further inspections and testing of plugged tubes will continue in August.
Concentrated Waste Storage Tank Pump (WDL-P12 A/B)
WDL-P-12A was removed from the system, disassembled, repaired, reassembled, and reinstalled to correct seal leakage. A section of WDL-P128 suction piping, suction valve WDL-V-175, and suction pipe flange, were replaced due to deterioration of piping. Repairs to WDL-P-12B will continue in August to correct a cracked pump casing.
Fire Service Pump Diesel (FS-P-3)
To correct oil leakage on FS-P-3 diesel engine resulting from the #4 injector adjusting screw locknut loosening and cracking the valve cover, the following corrective action was taken:
The rocker box was removed from the diesel.
The cam followers were removed and inspected.
Three cam followers were replaced, the #4 injector adjusting screen locknut was replaced,1 valve pushrod was replaced, and a new valve cover was installed. The diesel engine was satisfactorily timed and run. All work has been completed.
0061A
REFUELING INFORMATION REQUEST i
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 h.
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 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 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 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 procedures:
N/A T.
The number of fuel assemblies (a) in the core, and (b) in the spent fuel 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 nu=ber of fuel assemblies:
The present licensed capacity is 752. There are no planned increases at this' time.
9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
1988 is the last refueling discharge which allows full core off-10ad capacity (177 fuel assemblies).
~
OPERATING DATA REPORT DOCKET NO.
50-289 DATE Aunust 16, 1984 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 OPERATING STATUS NOTES
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 2.
REPORTING PERIOD:
JULY
,1984
- 3. LICENSED THERMAL POWER (MWT):
2535. l
- 4. NAMEPLATE RATING (GROSS MWE):
871.
- 5. DESIGN ELECTRICAL RATING (NET MWE):
819.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
824.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
776.
I 8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
9.
POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR-TO-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.
5111.
86904.
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.n 0.0 31731.8
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 838.5
- 14. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. CROSS THERMAL ENERGY GENERATED (MWH)
O.
O.
76531071.
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) n.
O.
25484330
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
23840053.
- 19. UNIT SERVICE FACTOR 0.0 0.0 35.9 20 UNIT AVAILABILITY FACTOR 0.0 0.0 35.9
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 35.1
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 33.5
- 23. UNIT FORCED OUTAGE RATE 100.0 100.0 60,9
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
1
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-l DATE August 16, 1984 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 MONTH:
JULY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 0.
17 0
2 0.
18 0
3 0.
19 0
4 0.
20 0
5 O.
21 0
6 0.
22 0
7 0
23 0
8 0.
24 0
9 0
25 O.
10 0.
26 0
11 0,
27 0
12
'O.
28 0,
13 0
29 0
14 0
30 0
15 0
31 0
16 0
6 i
-my g.
r v~+-
r
J A.
DOCKETNO. 50-289 UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME TM1-1 DATE A' gust 16, 1984 REPORT MONTH July, 1984 COMPLETED BY._ _C. W. Smyth
~
- TELEPHONE (717) 948-8551' "i
e c.
.5 so :
5" Licensee c.
Cause & Corrective
.2 _e g.s x No.
Date g
gg g
,cg5 Event t: T E.1 Action to H
$E j ;f; g Report #
iRG u
Prevent Recurrence 6
1 84-01-08 F
744 D
1 N/A ZZ ZZZZZZ 4
\\
l 2
3 4
F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A b :vment Failure (Explain) 1-Manual for Preparation of Data B-Mainivance of Test 2-Manual Scram.
Entry Sheets for Licensee l
C Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G Operatjonal Error (Explain)
Exhibit I - Same Source II-Other (Explain)
OPERATING
SUMMARY
The Unit was shutdown the entire month by order of the NRC. Core cooling was provided by the Decay Heat Removal System. The RCS was partially drained the entire month to enable investigations in OTSG tube leakage. These efforts and findings were discussed in detail in our letter to Mr. John F. Stolz, dated July 18, 1984.
MAINTENANCE
SUMMARY
Major Safety Related Maintenance The following major maintenance items were completed during the month:
OTSG A & B Work accomplished consisted of the completion of Eddy Current Testing, Fiberoptic Inspection of tube #148-35 ("A" 0TSG), and removal of the lower manway on the "A" OTSG. Repairs on the "A" 0TSG included welding plugs in the upper tubesheet in tubes #135-72 and #148-35. Repairs on the "B" 0TSG included welding plugs in the upper tubesheet in tubes #70-8, #79-41, and
- 80-45. Explosive plugs were also installed in the "B" 0TSG lower tubesheet in tubes #70-8, #77-7, #79-41, and #80-45. The upper and lower tubesheets were mapoed utilizing photographs for all plugged tubes in the upper and lower tubesheets of both the "A" and "B" 0TSGs. Further inspections and testing of plugged tubes will continue in August.
Concentrated Waste Storage Tank Pump (WDL-P12 A/B)
WDL-P-12A was removed from the system, disassembled, repaired, reassembled, and reinstalled to correct seal leakage. A section of WDL-P128 suction piping, suction valve WDL-V-175, and suction pipe flange, were replaced due to deterioration of piping.
Repairs to WDL-P-12B will continue in August to correct a cracked pump casing.
Fire Service Pump Diesel (FS-P-3)
To correct oil leakage on FS-P-3 diesel engine resulting from 9e #4 injector adjusting screw locknut loosening and cracking the valve cover, the following corrective action was taken:
The rocker box was removed from the diesel. The cam followers were removed and inspected. Three cam followers were replaced, the #4 injector adjusting screen locknut was replaced, 1 valve pushrod was replaced, and a new valve cover was installed. The diesel engine was satisfactorily timed and run. All work has been complsted.
0061A
.c RENELING INFORMATION REQUEST 11.
Name of Facility:
ThreeMileIslandNuclearb'tation, 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 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)?
I If no such review has taken place, when is it scheduled?
l 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 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 procedures:
N/A 7
The number of fuel assemblies (a) in the core, and (b) in the spent fuel 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 number of fuel assemblies:
The present licensed capacity is 732. There are no plannca incrcasca at this time.
9 The projected date of the last refueling that can be discharged to the spent I
fuel pool assuming the present licensed capacity:
1988 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
GPU Nuclear Corporation Nuclear
- ,omea 48o s
Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
August 16, 1984 5211-84-2167 Office of Management Information and Program Control Attn:
W. C. Mcdonald c/o Distribution Services Branch DPC, ADM U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Mcdonald:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 July Monthly Operating Report Enclosed please find two (2) copies of the July Operating Report for Three Mile Island Nuclear Station Unit.
Sincerely, a
H. D.
- ukill, Director, THI-1 HDH:vjf Attachments cc:
V. Stello Dr. T. E. Murley 0015C rE 1+
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation g
e