ML20083Q421
| ML20083Q421 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 03/31/1984 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | Mcdonald W NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 5211-84-2091, NUDOCS 8404230065 | |
| Download: ML20083Q421 (13) | |
Text
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OPERATING DATA REPORT
(
DOCKET NO.
50-289
(
DATE Mu rh 15. 14R4 COMPLETED BY C.W.Smvth
( V TELEPHONE 948-8551
!Y
!22i
(
OPERATING STATUS f,
NOTES
('!,
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 2.
REPORTING PERIOD:
MARCH
,1984.
- 3. LICENSED" THERMAIF POWER-~ (MWT)~:
z535.
(GROSS MWE):
871.
- 4. NAMEPLATE RATING 5.
DESIGN ELECTRICAL RATING (NET MWE):
819.
1,,r 67 MAXIMUM DEPENDABLE CAPACITY-(GROSS MWE) :
824.
( $
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
776.
Y l
q:
(
35
(,j 8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
,b
(
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE) 10.-REASONS FOR RESTRICTIONS,~-~IF ANY:--~~-
t',,
2__.._____________.__.
i
_ _. _. _ _. _.-~ ~ THIS MONTH-- YR-TO-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD
- 744, 2184.
83977
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8
~13'.-REACTOR' RESERVE ~ SHUTDOWN HOURS 070 070 838T5 l'4. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
-16; -GROSS-THERMAL-ENERGY GENERATED ~( MWH )
0 O.
7 6 531071~.-
( i ',17.
GROSS ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
25484330 (7 18 NET ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
23840053.
L.J 19;- UNIT--S E RVICE" F ACTOR OTO CO 3 7T1-(
20 UNIT AVAILABILITY FACTOR 0.0 0.0 37.1
,, 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 36.3
'22;~ UNIT CAPACITY-FACTOR-(USING DER ~ NET) 0T1) 0.0 34;7
- 23. UNIT FORCED OUTAGE RATE 100.0 100.0 59.4
~
~
~ ~ ~
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,~~DATE,'AND DURATION OP EACH 8404230065 840331 PDR ADOCK 05000289 R
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
1
' ~ ~ ~ ~ ~ ~ '
~
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~ ~ ~ ~
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lu AVERAGE DAILY UNIT POWER LEVEL
(
DOCKET NO.
50-289
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~
UNIT TMI-1 DNTE March 15. 19R4 COMPLETED BY C.W.Rmvth
( I,'
TELEPHONE 948-8551 2
s Li
( (>\\,l MONTH:
MARCH e s'
( f.I AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL DAY (MWE; NET)
~
~(MWE-NET)
( '. '
1 0
17 0
.q
-/
2 0,
18 0.
Ir!
3 0.
19 0.
4 0
20 0,
( 3:!
2) 5 O.
21 0
2) 6 0
22 6.
i 7
0.
23 0
8 0
24 0.
(
3s n!n.'
9 0.
n u.
(W 10 0
26 0.
11 0
27 0
~ ~ ~ ~ ' 12 -
07-28-O.
( i,.
13 0
29 0
I,,
14 0.
30 0
- 15 07 31 6.
c 16 0.
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C.T
s 50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME 'DIl-1 DATE Marcti 15. 1984 COMPLETED 8Y C,W.Snifth REPORT MONTHyw+~' -'--
TELEPHONE 17171 4a9 n5;1
'no, w.
C PB 30
.E ?
E
,.s M Licensee 3%,
Cause & Corrective g""d No.
Date g
3g g
,g g 5 Event uT o
Action to
$E 5
j di j Report n (N 0 Prevent Recurrence 6
1 84-03-01 F
D 1
N/A ZZ ZZZZZZ s
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 Scr..- -
Entry Sheets for Licensee 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 Il-Other (Explain)
W
4 4
i OPERATING
SUMMARY
l The Unit was in cold shutdown the entire month by order of the NRC.
Core cooling was provided by the Decay Heat Removal System.
The Reactor Coolant System was nar-i tially drained ~during the month to enable repair work to continue on Reactor Coolant i
Pump 1B.
MAJOR SAFETY REIATED MAINTENANCE i
i Repair work continued on RC-P-1B.
The cause of the initial high vibration was found to be a crack in the pump shaft which-extended through the thermosleeve pins about 200 around the shaft. The cause remains under investigation. However, a new shaft i
has been installed. Also installed were a new radial bearing cartridge, a turning vane /difusser assembly, a new impeller, and a reinstallation of the difusser adapter.
p Also found during the disassembly was significant impeller erosion that is thought to have been a result of cavitation. The exact cause of this is unknown.
1 l
ISI inspections were completed (satisfactorily) on the pump casing, 16 of 24 main
}
flange bolts, and on 12'of 12 #1 seal housing bolts.
The pump was rotated in the pump handling frame and the seals were reinstalled using a new #1 seal ring and runner.;
a new #2 seal ring, a new upper seal housing, and new #3 seal ring and runner.
Preventive maintenance inspections on RC-P-1B motor continued in March with the 1
overhaul and reinstallation of AC and DC lift pumps / motors and backstop oil numps/
j motors.
The upper and lower guide bearings were removed and disassembled and insula-tion checks were performed on the motor.
ISI inspections on the motor flywheel were i
satisfactorily performed and new upper and lower guide bearings.were installed. The oil system was refilled and temporary power was suonlied to the lift pumos while the
]
pump was rotated.
Motor to pump alignment and UT inspections on RCP-1A, C, and D were commenced.
No' UT indications were found on the three pump shafts and only the C ouma required minor 4
alignment.
Inspections of the remaining three pumps using fiber optics through 30 foot sections of the pump cold legs has resulted in concluding there is no degredation j
of the other impe11ers.
Reassembly of RC-P-1B is currently in progress with completion and testing e.:pected l
during April.
i i
Incal Leak Rate Testing continued during the month of March with the east and west fuel transfer tubes, reactor building equipment hatch, three penetrations,_and sixty-four valves satisfactorily tested.
l Core Flood valve CF-V-1B (pressure seal leak) completed during the month.with the re-assembly of the valve and reinstallation of the operator.
Testing will be nerformed l
at a later date.
l l
i
.-..~_,,x.
m
- ~.,
Once Through Steam Generator RC-H-1A/B manway/ handle hole backing olate flatness inspections commensed in March with the removal of manways and handhole covers.
Flatness checks, cleaning, etc. are in progress and will be completed in April.
Decay Heat Valve DH-V-22A repairs (not seating) were completed in March with dis-assembly, inspection, cleaning, replacement of disc assembly lockplate keepers and reassembly of the valve.
Testing will be completed when plant operation permits.
i 1
c
-3_
REFUELING INFORMATION REQUEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
1 4
Unknown 3
Scheduled date for restart following refueling:
r Unknown j
h.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
4 1
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)?
l i
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 supportin6 I
information:
s 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 i
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 which allows full core off-load.
capacity (177 fuel assemblies).
e,_s.
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9__7
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(
h OPERATING DATA REPORT r
DOCKET NO.
50-289 g
DATE March lei. 1994 y
COMPLETED BY CKRnuth 9
( t,-
TELEPHONE 948-8551 OPERATING STATUS
('
7 5
NOTES
( ' h,
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 2.
REPORTING PERIOD:
MARCH
,1984.
- 3. LICENSED ^ THERMAL POWER ~(MWT)1 "2 5 3 5---
- 4. NAMEPLATE RATING (GROSS MWE):
871.
- 5. DESIGN ELECTRICAL RATING (NET MWE):
819.
!3.F~6TMAXIMUM-DEPENDABLE CAPACITY 1 GROSS MWE) :
82'4.
I %' 7 MAXIMUM DEPENDABLE CAPACITY (NET MWE):
776.
W l
L
(' W 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.
2184.
83977
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8
~13r REACTOR ~ RESERVE" SHUTDOWN HOURS ~
0;0 0:0 838I5'
- 14. HOURS GENERATOR ON-LINE 0.0
-0.0 31180.9
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 L16r GROSS-THERMAL-ENERGY ~ GENERATED ~(MWM)
O.
D.
16531071.
( gl7. GROSS ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
25484330 L 18. NET ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
23840053.
V19.-UNIT SERVICE-FACTOR 07f) 0:0 3771-('
20 UNIT AVAILABILITY FACTOR 0.0 0.0 37.1,
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 36.3
-22.' UNIT CAPACITY ~ FACTOR ~(USING-DER NET)
Os0 0:0 34;7
- 23. UNIT FORCCD OUTAGE RATE 100.0 100.0 59.4
~
~
- 24. SilUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE,~ AMD DURATION OF EACH ESTIMATED DATE OF STARTUP-
- 25. IF SHUf DOWN AT;END OF REPORT PERIOD,.
j
f'~
s Y'
AVERAGE DAILY UNIT PONER LEVEL
(
DOCKET NO.
50-289
(
UNIT TMI-1 DKTE March 15.19R4 I
COMPLETED BY C.W. Smvt h
,.- )
TELEPHONE 948._8551. _. _
- il py y:
f!
MONTH:
MARCH us DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
(
(MWEWET)
. WE M E O'-
e 1
0 17 0
2 0
18 0
(i 3--
0.
19 6.
i 4
0 20 0
( h.:)!
5 0,
21 0.
[J 6
-~0 22 6.
1 (Q
7 0
23 0
k.
8 0.
24 0.
f; 9
0.
25 u.
(
10 0
26 0
r 11 0
27 0
~
12
~ ~ ~ ~ ~
~~-O.
-- - - - - - ~ ~ - - - --
- 0.
(
13 0
29 0
f.
14 0
30 0
15 -
O.
31 6
16 0
......,.e.Am_ces.,
.s
=
.mwe.p.
...e,ggpnw--+
sw-4
--.--i-I L.
s
.s
(.
V, h
i C":
50-289 DOCKET NO, UNITSIIUTDOWNS AND POWER REDUCTIONS UNIT NAME MI-l DATE hhrdi 15. los4 COMPLETED llY 11SprLth REPORT MONTituwas ino, TELEPIIONE r71 m q a n_pe,e i s
'-~-~-
"s S*
c c.
3 r.o 2 _e E
,.s ~4 Licensee 5 *,
c.
Causc a Corrective No.
Date g
3g g
,g g 5 Event u?
E3 Action to o
c5 E 5
j dj g Report n
- G u
Prevent Recurrence d
I 84-03-01 F
D 1
N/A ZZ ZZZZZZ 9
s 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 o(Test 2-Manual Scram.
Entry Sheets for Licensee C. Refueling 3 Automstic Scram.
Event Report (LER) File (NllREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
onal Error (Explain)
Exhibit I - Same Source G-Operat} Explain)
II-Other (
O e
e
J
+
OPERATING
SUMMARY
The Unit was in cold shutdown the entire month by order of the NRC.
Core cooling was provided by the Decay Heat Removal System.
The Reactor Coolant System was par-tially drained during the mor.th to enable renair work to continue on Reactor Coolant Pump 1B.
MAJOR SAFETY RELATED MAINTENANCE Repair work continued on RC-P-1B.
The cause of the initial high vibration was found to be a crack in the pump shaft which extended through the thermosleeve pins about 200 around the shaft.
The cause remains under investigation. However, a new shaft has been installed. Also installed were a new radial bearing cartridge, a turning vane /difusser assembly, a new impeller, and a reinstallation of the difusser adapter.
Also found during the disassembly was significant impeller erosion that is thought to have been a result of cavitation.
The exact cause of this is unknown.
ISI inspections were completed (satisfactorily) on the pump casing, 16 of 24 main flange bolts, and on 12 of 12 #1 seal housing bolts.
The pump was rotated in the pump handling frame and the seals were reinstalled using a new #1 seal ring and runner a new #2 seal ring, a new upper seal housing, and new #3 seal ring and runner.
Preventive maintenance inspections on RC-P-1B motor continued in March with the overhaul and reinstallation of AC and DC lift pumps / motors and backstop oil numps/
motors.
The upper and lower guide bearings were removed and disassembled and insula-tion checks were performed on the motor.
ISI inspections on the motor flywheel were satisfactorily performed and new upper and lower guide bearings were installed.
The oil system was refilled and temporary power was suonlied to the lift pumps while the pump was rotated.
Motor to pump alignment and UT inspections on RCP-1A, C, and D were commenced. No UT indications were found on the three pump shafts and only the C ouno required minor alignment.
Inspections of the remaining three pumps using fiber optics through 30 l'
foot sections of the pump cold legs has resulted in concluding there is no degredation of the other impellers.
Reassembly of RC-P-1B is currently in progress with completion and testing expected during April.
Local Leak Rate Testing continued during the month of March with the east and west fuel transfer tubes, reactor building equipment hatch, three penetrations, and sixty-four valves satisfactorily tested.
Core Flood valve CF-V-1B (pressure seal leak) completed during the month with the re-assembly of the valve and.einstallation of the operator.
Testing vill be nerformed at a later date.
Once Through Steam Generator RC-H-1A/B manway/ handle hole backine,olate flatness inspections commensed in March with the removal of manways and handhole covers.
Flatness checks, cleaning, etc. are in progress and vill be comoleted in April.
Decay Heat Valve DH-V-22A repairs (not seating) were completed in March with dis-assembly, inspection, cleaning, replacement of disc assembly lockplate keeners and reassembly of the valve., Testing will be completed when plant operation permits.
v
~
l U
t I
\\
EEFUELING INFORMATION EECUIIT 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 i
2.
Scheduled date for next refueling shutdown:
Unknown 3
Scheduled date for restart following refueling:
i Unknown h.
Will refueling or resumption of operation thereafter require a technical specification.bange 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 Co=mittee 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?
,1 Amendment No. 50, Cycle 5 reload, was a; proved 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 asse=blies (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 which allows full core off-load capacity (177 fuel assemblies).
GPU Nuclear Corporation NuCIMr Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944-7621 TELEX 84 2386 Writer's Direct Dial Number:
April 16, 1984 5211-84-2091 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 March Monthly Operating Report Enclosed please find two (2) copies of the March Operating Report for Three Mile Island Nuclear Station Unit.
Sincerely,
. D.
11, Director, TMI-l HDH:mle Attachments cc:
V. Stello Dr. E. T. Murley rE-2.L/
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation f