ML20129B662

Monthly Operating Rept for Sept 1996 for Three Mile Island Nuclear Station Unit 1 (TMI-1)

ML20129B662
Person / Time
Site:	Three Mile Island
Issue date:	09/30/1996
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-96-2339, NUDOCS 9610230081
Download: ML20129B662 (7)

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GPU Nuclear, Inc.

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Route 441 south NUCLEAg Post Office Box 480 Middletown, PA 17057 0480 Tel 717-044-7621 October 14, 1996 6710-96-2339

)

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for September 1996 Enclosed are two copies of the September 1996 Monthly Operating Report for Three Mile Island i

Nuclear Station, Unit 1.

Sincerely, i

y J. Knubel Vice President and Director, TMI WGH 9610230001 960930 PDR ADOCK 05000289 R

PDR a 1bY g cc: Administrator, Region I TMI Senior Resident Inspector

/l 96001 230073

l OPERATIONS

SUMMARY

September 1996 The plant entered the month operating at 100% power and remained at that power level for the remainder of the month. Net unit electrical output averaged approximately 801 MWe during September.

2 i

MAJOR SAFETY RELATED MAINTENANCE 1

The major safety related maintenance items completed during the month involved the following l

eqmpment.

Nuclear Services Closed Cooler NS-C-lD Nuclear Services Closed Cooler NS-C-lD was removed from service for scheduled maintenance.

Work accomplished included leaking check of the tubes (no leaks identified), installation of sacrificial anodes, coating of the water boxes, perfomiing and Eddy Current Testing. Based on Eddy Current Testing results, one (1) tube was removed from service by installing a stabilizer and plugging.

Core Flood Valves CF-V-83 A/B Core Flood System Sample valves CF-V-83A/B were removed from service because of seat leakage. The existing valves were replaced with new compression fitting tubing valves.

Reactor Coolant Pump Bearing Oil Level Indicator RC-61-LI7 3

Reactor Coolant Pump RC-P-lD lower bearing oil level indicator RC-61-LI7 was removed from service afler the instrument failed down scale. Troubleshooting identified a blown fuse and a failed power supply. Following installation of a new power supply and fuse, the fuse blew again when the unit was repowered. The failure was attributed to a failed step-down transformer. The transformer and fuse were replaced. Afler post maintenance testing was satisfactorily completed, the instrument was returned to service.

Nuclear Services River Water Pump NR-P-lC Nuclear Services River Water Pump NR-P-lC was removed from service due to high column vibrations. After the motor was removed, the pump was pulled and disassembly started. A new replacement pump bowl assembly was obtained from warehouse stock, disassembled, balanced, reassembled and set aside for installation later. Pump disassembly is still in progress and re-assembly is expected to be complete in October.

1

OPERATING DATA REPORT DOCKET NO.

50-289 DATE October 14, 1996 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 NOTES:

2. REPORTING PERIOD:

SEPTEM 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 CAPACITY (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:

THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 720.0 6575.0 193565 0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 720.0 6575.0 116118.1

- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2284.0

14. HOURS GENERATOR ON-LINE (HRS) 720.0 6575.0 114956.3

15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,847,727.4 16,823,687.0 282,938,613.0 l

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 610,101.0 5,600,405.0 95,053,879.1 j

18. NET ELECTRICAL ENERGY GENERATED (MWH) 576,900.0 5,292,770.0 89,336,174.1

19. UNIT SERVICE FACTOR

(%)

100.0 100.0 59.4

20. UNIT AVAILABILITY FACTOR

(%)

100.0 100.0 59.4

21. UNIT CAPACITY FACTOR (USING MDC NET) 101.9 102.4 58.7

22. UNIT CAPACITY FACTOR (USING DER NET) 97.8 98.3 56.4

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 34.5 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:

3 2

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 i

DATE 10/14/96 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191

]

MONTH:

SEPTEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j

(MWe-NET)

(MWe-NET) 1 797 17 804 2

797 18 805 3

795 19 805 4

795 20 808 5

789 21 807 6

791 22 806 7

789 23 808 8

791 24 811 9

792 25 809 10 792 26 811 11 796 27 803 12 797 28 800 13 801 29 810 14 808 30 809 15 806 31

1. N/A 16 805 3

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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 3.

Scheduled date for restart following current refueling: NA j

l

4. Will refueling or resumption of operation thereafter require a technical i

specification change or other licensa amendment? Yes. To support GPU 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.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information: A Technical Specification Change Request for the changes as l

discussed above will be submitted once the GPU Nuclear topicals are approved.

j 6.

Important lic.ensing 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:

]

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a) GPU Nuclear Letter 6710-96-2092, dated March 28,1996 confirmed i

plans to perform independent reload design evaluations for Cycle 12, the next operation cycle, based on NRC approved metheds 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 methodology) submitted to the NRC. The latter three are in the NRC review and approval stage.

At this time, completion of the NRC review and issuance of NRC SERs is i

active. We have received questions on all reports and are in the process of I

providing answers. All remaining reports are expected to be approved in an acceptable time frame to support our reload design activities.

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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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 fill gas prepressure, increased plenum volume). The new design will meet all fuel criteria in the latest approved revision of BAW-19179P-A, Safety Criteria and Methodology for Acceptable Cycle Reload Analyses. Fuel rod cladding corrosion calculations for all Cycle 12 fuel are being done by FCF using tb COROS2 methodology now under review by the NRC with i

approval expected about September 1996. The TACO calculations are being done using power histories generated with the GPU Nuclear approved l

core physics codes CASMO-3/ SIMULATE-3 (TR-091 A). A letter l

requesting approval for use of the SIMULATE-3 power peaking l

uncertainty of 5.5% with the TACO methodologies, rather than the current l

FCF NEMO physics code (BAW-10180A, Rev 1) uncertainty of 4.8%, was l

submitted by FCF in August 1996 with approval requested by September l

30,1996 to support the Cycle 12 reload design schedule requirernents.

I l

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage l

pool: (a) 177 (b) 864 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:

I j

The present licensed capacity is 1990. Phase I of the reracking project to l

increase spent fuel pool storage capacity permits storage of 1342 assemblies.

Upon completion of Phase II of the reracking project, the full licensed l

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:

l Completion of Phase I of the reracking project permits full core off-load l

(177 fuel assemblies) through the end of Cycle 14 and on completion of the l

rerack project full core off-load is assured through and beyond the end of the current operating license.

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