ML20062C329
| ML20062C329 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/30/1990 |
| From: | Heysek W, Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-90-2134, NUDOCS 9010310093 | |
| Download: ML20062C329 (6) | |
Text
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dPU Nuclear Corporation -
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Post Office Box 480 i
I Route 441 South Middletown, Pennsylvania 17057 0191
~ 717 944 7621 i
TELEX 84 2386 Writer's Direct Olal Number:
i October 12, 1990 C311-90-2134-U. S. Nuclear Regulatory Commissio'n Attn: Document Control Desk Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit I.(TMI-l')
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report September J"03-t Enclosed are two copies of the September, 1990-Honthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
'1 sincerely, r
-l D.
ill Vice-President & Director, TMI-1E HDH/WGH cca T. T. Martin, USNRC F. Young, USNRC Attachments 9010310093 901012 PDR ADOCK 05000289 R
PNV V b J.3 t,ao e,--
[ II GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation I-
- i
OPERATIONS
SUMMARY
SEPTEMBER 1990 The unit entered the month operating at -96% reactor power (limited by high OTSG level) producing ~820 MWe gross electrical generation. A aTc of -4.5'F was input to compensate for the high OTSG level on the "B" side. The unit continued at 96%
reactor power until September 28th when a reduction to 50% power was executed to support identification and repair of main condenser tube leaks. The unit closed the month operating at 50% reactor power producing 360 MW gross electrical generation. The "A" side of the main condenser was out of service with a aTc of
-2.5'F Anput to offset fouling in the "B" OTSG.
MAJOR SAFETY RELATED MAINTENANCI During September, the following major safety related maintenance activities were performed:
Hydrocen Recombiner HR-R-1B Efforts to replace the Hydrogen Recombiner HR-R-1B expansion joints were begun in September.
Holes were located in the existing bellows ir June and since replacement bellows could not be procured, a modification to the existing configuration was planned and approved to replace the failed hellows with hard piping.
Welding of flanges and pipe comprising the replacenent sections was complet9d and x-rays of the joints were satisfactory.
The cellows have been removed and the inlet and outlet piping prepped to accomnadate welding in the new sections during October.
l l
Primary Sample Valves CA-V30 A/B and CA-V31 A/B l
l The four Primary sample Valves (CA-V30 A/B and CA-V31 A/B) were replaced during September.
The valve packing gland bushing was found damaged on CA-V30A and l
since no repair part was available in the stores system, Plant Engineering authorized replacing the existing Autoclave valves with Parker-Hannifin l
compression end valves.
The results of post-installation testing were satisfactory.
l l
2
- ~
OPERATING DATA REPORT i
DOCKET NO.
50-289
.DATE 9-30-90 COMPLETED BY W.G. Heysek t
E TELEPHONE (717) 948-8191 4
OPERATING STATUS i
I i NOTES I
1.
UNIT NAME:
THREE MILE = ISLAND UNIT 1 I l
- 2. REPORTING PERIOD:
SEPT
,1990. I l
l
- 3. LICENSED THERMAL POWER (MWT):
2568. I 1
4.
NAMEPLATE RATING (GROSS MWE):
871. I i
j
- 5. DESIGN ELECTRICAL RATING (NET MWE):
819. 1 I
r
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
856.- 1 I
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
808. I I
I l
8.
IF CHANCES DCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONG:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY-- (NET MWE)
- 10. REASONS FOR RESTRICTIONS, IF ANY:
i
{
THIS MONTH YR-TO-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD 720.'
-.6551.
140952.
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0
-4956.6 66955.2
- 13. REACTOR RESERVE SHUTDOWN' HOURS 0.0-
'242.8.
2245.6
- 14. HOURS GENERATOR ON-LINE 720.0-4914.6 65910.7
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED-(MWH)
<1695496.
11694056.
161265950.
- 17. GROSS ELECTRICAL ENERGY GENERATED ~(NWH) 560456.s 3905546.
54212215.
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 527403;
~3657160.
50843649.
- 19. UNIT SERVICE FACTOR' 100.0 75.0 46.8
- 20. UNIT AVAILABILITY FACTOR 100.0-75.0
' 4 6. 8:
- 21. UNIT CAPACITY' FACTOR (USING MDC' NET) 90.7.
69;1 46.0
- 22. UNIT CAPACITY FACTOR (USING DER' NET) 89;4' 68.2.
44~.0
- 23. UNIT FORCED OUTAGE RATE
-0.0 4.6 47.9 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:
r
r i
AVECAGE DAILY UNIT POWEO. LEVEL
{
1
-DOCKET'NO.
50-289-UNIT.
TMI-1
'DATE 9 30 '
COMPLETED BY-W.G. Heysek TELEPHONE '- (717 ) 948-3191
'L l
. MONTH:
SEPT
.I i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER' LEVEL' (MWE-NET)
,(MWE-NET) 1 767.
17 775.
'I 2
758.
l 3
764.
-19
=773.
4 768.-
20:
768.
l 5
762.
21 772.
l 6
758.
22 768.
7-755.
~23 772.
B
.767.
24-
~774. -
9 771.,
25 771.-
10:
761.
26-
.771..
11 761.
27 767.12-757.
28 648.'
13 757.
29 319.
14 760.
30 322.
l 15 762.
31
'N/A' 4
l-16 773.
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- 4
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UNIT SHUTDOWNS AND POWER REDUCTIONS
~
DOCKET NO.
50-289 UNIT NAME TMI-1 REPORT MONTH September 1990 DATE 10/15/90 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 Method of Licensee system Component Cause & Corrective l
2 NO-Date Type Duration Reason Shutting Event Code Code Action to (Hours)
Down Report #
P**"I R* ""'"
3 4 6 Reactor 5 6 g
90-9/28 -
S 55 B
4 NA SG HTEXCH The unit was reduced to 50% reactor power 04 9/30/90 to locate and repair main condenser tube leaks.
1-2 3'.
4 F Forced Reason Method Exhibit G - Instructions S Scheduled A-Eqipment Falture (Explain) 1-Manual for Preperation of Data B-Maintenance or Test 2-Manuel Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4-Other (Explain)'
E-Operator Training & Licensing Examination F-Administrative 5 Exhibit 1 Same Source G-Operational Error (Explain)
N-Other (Explain) 6 Actuelty used Exhibits F & II NUREG 0161 5
1
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l REFUELING INFORMATION REQUEST 1.
Name of Facility:
Three Nile Island Nuclear Station, Unit 1
(
- 2. Scheduled date for next refueling shutdown:
October 4, 1991 (9R) l
- 3. Scheduled date for restart following current refueling: NA 1
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No.
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 l
whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
No.
If no such review has taken place, when is-it scheduled? 6/1/91.
- 5. Scheduled date(s) for submitting proposed licensing action and supporting information: None planned.
6.
Important liceneing considerations associated with refueling, e.g. new or differtat fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures None.
- 7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pools (a) 177 (b) 441 l
- 8. The present licensed spent fuel poc>l storage capacity and the size of any increase in licensed storage capacAty that has been requested or is planned, in number of fuel assembiies:
The present licensed capacity is 752. Planning to increase licensed capacity through fuel pool raracking is in progress.
- 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
l 1991 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
'l 6
.