ML20132D543
| ML20132D543 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/30/1996 |
| From: | Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 6710-96-2397, NUDOCS 9612190428 | |
| Download: ML20132D543 (7) | |
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GPU Nuclear, Inc.
(
Route 441 South NUCLEAR Post Office Box 480 Middletown, PA 17057 0480 Tel 717-944 7621 i
December 12, 1996 6710-96-2397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 i
Gentlemen-
Subject:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for November 1996 Enclosed are two copies of the November 1996 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, j
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J. Knubel Vice President and Director, TMI WGH i
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cc: Administrator, Region I
/
TMI Senior Resident Inspector 96001 9612190428 961130 PDR ADOCK 05000289 R
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L OPERATIONS
SUMMARY
November 1996 The plant entered the month operating at 100% power and remained at that power level for the l
. remainder of the month. Net unit electrical output averaged approximately 820 MWe during November.
MAJOR SAFETY RELATED MAINTENANCE The major safety related maintenance items completed during the month involved the following equipment:
Nuclear Services Closed Cooler NS-C-1 A l
Nuclear Services Closed Cooler NS-C-1 A which was removed from service for scheduled maintenance during October. The leak test of the tubes was completed and no leaking tubes 1
identified. However, subsequent Eddy Current testing identified one tube which will be plugged.
Sacrificial magnesium anode installation work is in progress and will also continue on into December.
Miscellaneous Waste Transfer Pumo WDL-P-7A Miscellaneous Waste Transfer Pump WDL-P-7A was removed from service because ofincreased mechanical sealleakage. The pump was disassembled and the mechanical seal replaced. The l
reassembled pump was tested and and after it was found to perform satisfactorily, it was returned to service.
i Integrated Control System Tristable Relav Module 8-5-8 Integrated Control System tristable relay module 8-5-8 was replaced after sporadic spiking was observed. The failed module will be bench tested to determine the cause of failure.
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~ Control Rod Drive Cabinet Cooline Fan A cooling fan in the CRD cabinet for CRD Group 5 failed. The cause of the failure was determined to be bearing failure. A new fan assembly was installed in the cabinet.
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OPERATING DATA REPORT DOCKET NO.
50-289 DATE December 12, 1996 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191 i
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 NOTES:
- 2. REPORTING PERIOD:
NOVEMB 1996
- 3. LICENSED THERMAL POWER:
2568
- 4. NAMEPLATE RATING (GROSS MWe):
872
- 5. DESIGN ELECTRICAL RATING (NET MWe):
819
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe) 834
- 7. MAXIMUM DEPENDABLE CAPAC ITY (NET MWe):
786
)
- 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:
j THIS MONTH YR-TO-DATE CUMMULATIVE I
- 11. HOURS IN REPORTING PERIOD (HRS) 720.0 8040.0 195025.0
- 12. F"JMBER OF HOURS REACTOR WAS CRITICAL (HRS) 720.0 8040.0 117583.1
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0f 2284.0
- 14. HOURS GENERATOR ON-LINE (HRS) 720.0 804G.
116421.3
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0<
0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,847,111.0 20,582,006.4 286,696,932.4
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 624,711.0 6,864,929.0 96,318,403.1
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 590,882.0 6,489,087.0 90,532,491.1
- 19. UNIT SERVICE FACTOR
(%)
100.0 100.0 59.7
- 20. UNIT AVAILABILITY FACTOR
(%)
100.0 100.0 59.7
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 104.4 102.7 59.1
- 22. UNIT CAPACITY FACTOR (USING DER NET) 100.2 98.5 56.7
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 0.0 34.2 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60761.2-
- 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:
2
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 DATE December 12, 1996 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191
. MONTH:
NOVEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)
(MWe-NET) 1 821 17 822 2
823 18 820 3
824 19 818 4
821 20 821 5
.820 21 822 6
815 22 820 7-804 23 822 8
803 24 820 9
819 25 819 10 823 26 818 11 824 27 824
-12 824 28 825 i
13 825 29 825 I
14 824 30 824 l
15 825 31
- N/A j
l 16 825 i
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t DOCKET No.
50-289 UNIT NAME TMI-1 DATE December 12, 1996 REPORT MONTH November 1996 COMPLETED BY W. G..Heysek TELEPHONE (717) 948-8191 4
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1 REFUELING INFORMATION REOUEST
- 1. Name of Facility: Three. Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown: September 5,1997 j
4 3.
Scheduled date for restart following current refueling: NA
- 4. Will refueling or resumption of operation thereafter require a technical l
specification change or other license amendment? Yes. To support GPU j
Nuclear's independent reload analyses for Cycle 12 as discussed in response to Question 6 below, T.S. 6.9.5.2 will require revision to include references to the GPU Nuclear analysis methods applied to the reload.
l 5.
Scheduled date(s) for submitting proposed licensing action and supporting information: A Technical Specification Change Request for the changes as discussed above will be submitted once the GPU Nuclear topicals are approved.
5.
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:
a) GPU Nuclear Letter 6710-96-2092, dated March 28,1996 confirmed plans to perform independent reload design evaluations for Cycle 12, the next operation cycle, based on NRC approved methods described in GPU Nuclear Topical Reports TR-091 A (core physics), TR-087 (core thermal j
hydraulics), TR-078 (FSAR safety analyses) and TR-092P (design and setpoints methodoNgy) submitted to the NRC. The latter three are in the final NRC approval stage. Issuance of NRC SERs is expected soon.
The GPU Nuclear Cycle 12 reload program and results are expected to be j
available for NRC review in the March to April 1997 time frame.
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i b) Cycle 12 fuel rod performance calculations (e.g. internal pin pressure) will be performed by Framatome Cogema Fuels Company (FCF) using the approved TACO 3 (BAW-10162P-A) and GDTACO (BAW-10184P-A) fuel codes. Results require minor changes to the Mark B9 fuel rod design (lower I
fill gas prepressure, increased plenum volume). The new design will meet all fuel criteria in the latest approved revision of BAW-10179P-A, Safety 4
Criteria and Methodology for Acceptable Cycle Reload Analyses. Fuel rod cladding corrosion calculations for all Cycle 12 fuel are being done by FCF
]
using the COROS2 methodology now under review by the NRC. Approval 1
is expected soon. The TACO calculations are being done using power j
histories generated with the GPU Nuclear approved core physics codes CASMO-3/ SIMULATE-3 (TR-091 A). Use of the SIMULATE-3 power peaking uncertainty of 5.5% with the TACO methodologies, rather than the current FCF NEMO physics code (BAW-10180A, Rev 1) uncertainty of 4.8%, was approved by NRC on October 4,1995 for application to TMI-1 only.
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- 7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 864 l
- 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:
l The present licensed capacity is 1990. Phase I of the reracking project to increase spent fuel pool storage capacity permits storage of 1342 assemblies, Upon completion of Phase II of the reracking project, the fulllicensed i
capacity will be attained. Phase II is expected to be started in 2002.
- 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Completion of Phase I of the reracking project permits full core off-load (177 fuel assemblies) through the end of Cycle 14 and on completion of the rerack project full core off-load is assured through and beyond the end of the current operating license.
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