ML20097J486
| ML20097J486 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/31/1984 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | Mcdonald W NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 5211-84-2240, NUDOCS 8409210267 | |
| Download: ML20097J486 (11) | |
Text
__ _
OPERATING DATA REPORT DOCKET NO.
50-289 DATE September 17, 1984 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551
' OPERATING STATUS NOTES
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1
- 2. REPORTING PERIOD:
AUGUST
,1984.
- 3. LICENSED THERMAL _ POWER (MWT):
2535.
- 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 744.
5855.
87648.
Bl. HOURS IN REPORTING PERIOD
- 32. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8 0.0 0.0 838.5
$3. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 31180.9
- 34. HOURS GENERATOR ON-LINE 0.0 0.0 0.0 35.' UNIT PESERVE SHUTDOWN HOURS
- 36. GROSS THERMAL ENERGY GENERATED (MWH)
O.
O.
76531071.
37.. GROSS ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
25484330 B8. NET ELECTRICAL' ENERGY GENERATED (MWH)
O.
O.
23840053.
0.0 0.0 35.6
- 19. UNIT SERVICE FACTOR
- 20. UNIT AVAILABILITY FACTOR 0.0 0.0 35.6 21._ UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 34.8
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 33.2 100.0 100.0 61.2
- 23. UNIT FORCED OUTAGE RATE 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:
O s;1 a
o y
AUGUST 1984 MONTHLY OPERATING REPORT OPERATIONS
SUMMARY
'The Plant remained in cold' shutdown the entire month by order of the NRC.
Core cooling was provided by the Decay Heat Removal System. The RCS was partially drained to 10-15 inches above the cold leg center lines.
The upper and lower OTSG manways were removed to permit inspection of tube repairs.
MAJOR SAFETY RELATED MAINTENANCE The following major maintenance items were completed during the month:
0TSG RC-H-1A/B Work consisted of pull testing all Westinghouse roll-type tube plugs in both the A and B OTSGs. _A total of 1006 plugs were tested, with 728 passing the test requirements, 253 plugs showing movement, and 25 that came out during the test. Repair method evaluations are in progress and repair work will continue in the month of September,1984.
Decay Heat Removal Pump DH-P-1B Pump / motor misalignment was found during preventive maintenance. The pump / motor was realigned and tapered dowel pins were installed in the pump / motor to eliminate future misalignment during operation. All work has been completed.
Nuclear Service Closed Cooling Pump NS-P-1B A bearing failure was found in NS-P-1B through high temperature indications. The pump was disassembled, new bearings and shaft were installed; the pump was then reassembled, and test run satisfactorily.
Bearing temperature during the test phase operation was normal. All work has been completed.
Nuclear Service Closed Cooling Coolers NS-C-1A/B i
NS-C-1A/B were opened for inspection and cleaning. The end covers were removed, tubes were cleaned, and inspections were performed. Coal tar epoxy was applied on defective areas of the water boxes, and magnesium anodes were installed. Similar work will continue in September,1984, with the NS-C-lC/D coolers.
s
AVERAGE DAILY UNIT POWER LEVEL DOCKET No.
50-289 UNIT TMI-1 DATE September 17, 1934 COMPLETED BY C. W. Smyth TELEPHONE 017) 948-6351 MONTH:
AUGUST 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 0
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 0.
28 0.
13 0
29 0
14 0
30 0
15 0
31 0
16 0.
t e..
E
.s g
I 50-289 UNITSHUTDOWNS ANDPOWER REDUCTIONS DOCKET NO.
UNIT NAME TM1-1 DATE-september 1/, 1984 COWTED BY C. W. Smyth REPORT MON 1y August, 1984 1 ELEPHONE (7171 948-8551
'3 => E e
e ei Cause & Corrective b**
(.
No.
Date 8.
5_5 3 5b g]
Event g7 Action to p
5.2 0
5gx E
$5$
Report at mo Prevent Recurrence OO e
6 1
Regulatory Restraint Order 1
84/08/01 y
744 D
1 N/A zz zzzzzz l
I 2
3 4
F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Oth-8 Explain) 0161)
E-Operator Training & Ucense Examination F-Administrative 5
G-Operathmal Error (Explain)
Exhibit I-Same Source Ilother (Explain) i l
REFUELING INFORMATIO3 REQUEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling chutdown:
Unknown 3
Scheduled date for restart following refueling:
i Unknown h.
Will refueling or resumption of operation thereafter require a technical specification change or other license snendment?
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)?
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 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-load capacity (177 fuel assemblies).
(
M',:
s s
' 'n c
j OPERATING DATA REPORT
- s t
_s 4
]'
~
DOCKET NO.
50-289 DATE September 17, 1984 a
COMPLETED BY C. W. Smyth 1
TELEPHONE (717) 943-u531 s
. j
[
OPERATING STATUS NOTES
- 8. UNIT NAME:-
THREE MILE ISLAND UNIT 1
- 8. REPORTING PERIOD:
AdGUST
,1984.
& -LICENSED THERMAL POWER (MWT):
2535.
871.
O. NAMEPLATE RATING (GROSS MWE):
819.
9.-DESIGN ELECTRICAL RATING (NET MWE):
Q. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
824.
% MAXIMUM DEPENDABLE CAPACITY' (NET MWE):
776.
- z.
\\
- 8. IF CHANGES OCCUR IN-(ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
9.. POWER LEVEL TO WHICH RESTRICTED, IF. ANT (NET MWE) 0.-REASONS'FOR RESTRICTIONS, IF ANY:
..s t
w THIS MONTH YR-TO-DATE CUMMULATIVE
- 1. HOURS IN REPORTING PERIOD 744.
5855.-
87648.
- 2. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.R
- 3. REACTOR RESE$"/E- ~ SHUTDOWN HOURS 0.0 0.0 838.5 4.. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9 5.-UNIT' RESERVE SHUTDOWH: HOURS 0.0 0.0 0,0 6.= GROSS THERMAL' ENERGY GENERATED (MWH)
O.
O.
76531071.
- 7. GROSS ELECTRICAL ENERGY GENERATED (MWH)'
O.
O.
- 25484330,
- 8. NET ELECTRICAL' ENERGY GENERATED ~(MWH).
O.
O.
23840053.
- 9. UNIT SERVICE FACTOR s
0.0 0.0 35.6
'O. UNIT. AVAILABILITY FACTOR 0.0 0.0 35.6
- 1.-UNIT CAPACITY FACTOR (USING'MDC. NET) 0.0 0.0 34.8 O.0 0.0 33.2
'2.. UNIT CAPACITY FACTOR (USING DER NET) 100.0 100.0 61.2
'3.. UNIT FORCED OUTAGE RATE
$4.LSHUTDOWNSSCHEDULED=OVER,NEXT\\6 MONTHS (TYPE, DATE, AND DURATION OF EACH
'j5.:IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
f
. _... _ - _ - - -...., _.. -. _ _ _ _., _ _ ~
.. _ _ _. -. -. _ _... - - _.,,,,. _. -. _ _ _.. ~ -, _ -..
7
- AUGUST 1984 MONTHLY OPERATING REPORT.
OPERATIONS
SUMMARY
.The Plant remained in cold shutdown the entire month by order of the NRC.
Core cooling was provided by the Decay Heat Removal System. The RCS was partially drained to 10-15 inches above the cold leg center lines. The upper and lower ~0TSG manways were removed to permit inspection of tube repairs.
MAJOR SAFETY RELATED MAINTENANCE The following major maintenance items were completed during the month:
OTSG RC-H-1A/B' Work consisted of pull testing all Westinghouse roll-type tube plugs in both the A and B OTSGs. A total of 1006 plugs were tested, with 728 passing the test requirements, 253 plugs showing movement, and 25 that came out during the test.
Repair method evaluations are in progress and repair work will continue in the month of September,1984.
Decay Heat Removal Pump DH-P-1B
- Pump / motor misalignment was found during preventive maintenance. The
- pump / motor was realigned and tapered dowel pins were installed in the pump / motor to eliminate future misalignment during operation. All work a
has been completed.
Nuclear Service Closed Cooling Pump NS-P-1B
-A bearing failure was found in NS-P-1B through high temperature indications. The pump was disassembled, new bearings and shaft were installed; the pump was then reassembled, and test run satisfactorily.
Bearing temperature during the test phase operation was normal. All work
- has been completed.
Nuclear Service Closed Cooling Coolers NS-C-1A/B-
- NS-C-1A/B were opened for inspection and cleaning. The end covers were t'
removed, tubes were cleaned, and inspections were perfomed. Coal tar epoxy was applied on defective areas of the water boxes, and magnesium
. anodes were installed. Similar work will continue in September,1984, with the NS-C-lC/D coolers.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 DATE Seotember 17, 1934 COMPLETED BY C. W. Smyth TELEPHONE ( ~il 7 ) 94c-6531 MONTH:. AUGUST 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 n.
5 0
21 0
6 0.
22 0
7 0
23 0,
8 0,
24 0
3 0
25 0
in-O.
26 0
11 0
27 0,
12 0.
28 0.
13 0
29 0
-14 0
30 0
15 0
31 0
16 0.
i i
h i
i 1
50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME TML-1 DATE september 1/, 1984 COMPLETED BY C. W. Smyth REPORT MONTH August, 1984 TELEPHONE (7171 948-3551 "s
.! ?
3
.Y~h Licensee E*
Cause & Corrective No.
Date k
3g g
,g g 5 Event 55 k%
l Action to H
$E 5
3 ;5 c:
Report 2r
<N 0
$U Prevent Recurrence e-O 6
Regulatory Restraint Order 1
84/08/01 F
744 D
1 N/A ZZ ZZZZZZ f
i 1
l 1
2 3
4 F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee i
C Refueling 3 Automatic Scram.
Event ReporI(LER) File (NUREG-D Regulatory Restriction 4-Of her (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G Operatjonal Error (Explain)
Exhibit 1 - Same Source Il-Other (Explain) i
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 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)?
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 r
analysis methods, significant changes in fuel design, new operating procedures:
N/A 7
The number of fuel assembliec (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 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 vhich allows full core off-load capacity (177 fuel assemblies).
GPU Nuclear Corporation NU 98 Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944-7621 TELEX 84-2386 Writer's Direct Dial Number:
September 17, 1984 5211-84-2240 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 Monthly Operating Report - August 1984 Enclosed please find two (2) copies of the August 1984 Monthly Operating Report for Three Mile Island Nuclear Station Unit-1.
Sincerely,
- b. D. Hu ill, Director, THI-1 HDH:JGB:vjf Attachments cc:
V. Stello 1
Dr. T. E. Murley 0015C 4
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation g
-