ML20129C266

Monthly Operating Rept for Aug 1996 for Three Mile Island Nuclear Station,Unit 1

ML20129C266
Person / Time
Site:	Crane
Issue date:	08/31/1996
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-96-2294, NUDOCS 9609240187
Download: ML20129C266 (7)

Text

i GPU Nuclear, Inc.

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Route 441 south NUCLEAR Post Office Box 480 Middletown, PA 17057 0480 Tel 717-944 7621 September 13, 1996 6710-96-2294 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

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Monthly Operating Report for August 1996 i

Enclosed are two copies of the August 1996 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely,

. Knubel Vice President and Director, TMI WGH I

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cc: Administrator, Region I (k

TMI Senior Resident Inspector 96001 9609240187 960831 PDR ADOCK 05000289 R

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l OPERATIONS

SUMMARY

l August 1996 l

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 796 MWe during August.

i MAJOR SAFETY RELATED MAINTENANCE The major safety related maintenance items completed during the month involved the following equipment:

Pressurizer Pilot Ooerated Relief Valve RC-RV-2 The fuse clips for control circuit fuses FD-73 and FD-74 associated with the Pressurizer Pilot Operated Relief Valve (PORV) RC-RV-2 were replaced because the installed fuse clips were found bent.

Emergency Light Repairs Repairs to Relay Room Emergency Light EL-L-19 and Reactor Building Personnel Access Hatch Emergency Light EL-L-102 were completed 1

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OPERATING DATA REPORT i

DOCKET NO.

50-289 DATE September 13, 1996 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 NOTES:

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2. REPORTING PERIOD:

AUGUST 1996 l

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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 l

8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE L^ST 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) 744.0 5855.0 1928,40.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 5855.0 115398.1

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

14. HOURS GENERATOR ON-LINE (HRS) 744.0 5855.0 114236.3

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,908,743.0 14,975,959.7 281,090,885.7

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 626,734.0 4,990,364.0 94,443,778.1

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18. NET ELECTRICAL ENERGY GENERATED (MWH) 592,470.0 4,715,870.0 88,759,274.1

19. UNIT SERVICE FACTOR

(%)

'100.0 100.0 59.2

20. UNIT AVAILABILITY FACTOR

(%)

100.0 100.0 59.2

21. UNIT CAPACITY FACTOR (USING MDC NET) 101.3 102.5 58.6

22. UNIT CAPACITY FACTOR (USING DER NET) 37.2 98.3 56.2

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 34.7 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60761.2

24. SHUTDOWNS SCHEDULED OVER NEXT B MONTHS (TYPE, DATE AND DURATION OF EACH):

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25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE Se 1N COMPLETEbtembe" l'kYSEK BY W G H t

TELEPHONE (717) 948-8191

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MONTH:

AUGUST i

i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)

(MWe-NET) 1 797 17 798 2

798 18 796 3

798 19 796 4

795 20 794 5

795 21 793 l

6 793 22 790 7

794 23 790 i

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793 24 793 I

9 796 25 794 10 800 26 797 11 803 27 796 12 803 28 796 13 803 29 797 14

, 798 30 799 15 795 31 799 16 798 1

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DOCKET NO.

50-289 UNIT NAME TMI-l W. ptember 13, 1996 '

DATE Se REPORT MONTH August 1996 G. Heysek COMPLETED BY TELEPHONE (717) 948-8191 7

Method cf Imensee Systmen Camponent Cause & Cor ective Shurtmg Emmt Code Code Action to Dus Type' Duranon Reason a

Down ReponW Prevent Recurrence (Hours)

Reacter' P

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REFUELING INFORMATION REOUEST

1. Name ofFacility: 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

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes. To support GPU Nuclear plans to do independent reload analyses for Cycle 12 as discussed in response to question 6 below, T.S. 6.9.5.2 would require revision to include l

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.

l 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:

1 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 hydraulics), TR-078 (FSAR safety analyses) and TR-092P (design and setpoints methodology) submitted to the NRC. The latter three are in the l

NRC review and approval stage.

i At this time, completion of the NRC review and issuance of NRC SERs is active. We have received questions on all reports and are in the process of 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 available for NRC review in the Marcia to April 1997 time frame, i

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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 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 the COROS2 methodology now under review by the NRC with approval expected about September 1996. The TACO calculations are being done J

using power histories generated with the GPU Nuclear approved core physics codes CASMO-3/ SIMULATE-3 (TR-091 A). A letter requesting i

approval for use of the SIMULATE-3 power peaking uncertainty of 5.5%

with the TACO methodologies, rather than the current FCF NEMO physics code (BAW-19180A, Rev 1) uncertainty of 4.8%, was submitted by FCF in August 1996 with approval requested by September 30,1996 to supportthe Cycle 12 reload design schedule requirements.

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 864

8. The present licensed spent fuel pool storage capacity and the size of any increase l

in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

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 full licensed 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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