ML20134Q207

Monthly Operating Rept for Jan 1997 for TMI-1

ML20134Q207
Person / Time
Site:	Three Mile Island
Issue date:	01/31/1997
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-97-2053, NUDOCS 9702260321
Download: ML20134Q207 (7)

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( GPU Nuclear. inc.

( . Route 141 South NUCLEAR P**'0"ic' B*****

Middletown. PA 17057-0480 l Tel 717 944 7621 February 17, 1997 6710-97-2053 U. S. Nuclear Regulatoly 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 January 1997 Enclosed are two copies of the January 1997 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.  !

1 Sincerely, J. Knubel Vice President and Director, TMI WGH

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cc: Administrator, Region I TMI Senior Resident Inspector 97001

[} ['I 9702260321 970131 PDR ADOCK 050002G9 R PDR l

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OPERATIONS

SUMMARY

January 1997 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 822 MWe during January.

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

Nuclear Services Closed Cooling Water Valve NS-V-47 Nuclear Services Closed Cooling Water Surge Tank relief valve NS-V-47 was removed from service and replaced due to obsolescence. A new valve was installed, tested, and placed in service.

Nuclear Seivices River Water Valve NR-V-44B Piping A section of Nuclear Services River Water piping was removed due to a through wall leak. The pipe section involved, between the NR header and valve NR-V-44B, was no longer used and capped off up stream of the valve. Ultrasonic inspection was used to determine the extent of_ wall thinning and identify a location to cut the pipe. The piping upstream of the leak at the NR header was isolated using a freeze seal while the pipe section between the freeze seal and NR-V-44B removed. A pipe cap was welded on the upstream pipe end and valve NR-V-44B and the remaining downstream piping were abandoned in place. All results of NDE inspections were satisfactory including that of a post freeze inspection of the seal area.

Main Feedwater Valves FW-V-92A/B Due to a review of GL 89-10 requirements, it was determined that the limitorque operators on Main Feedwater System Isolation Valves FW-V-92A and 92B required torque switch adjustments. The torque switch settings were increased on both operators and tested by closing the valves manually to the 90% open position and then opening using the operator. Additional testing will be performed during the 12R outage.

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OPERATING DATA REPORT  !

i DOCKET NO. 50-289 DATE 02/17/97 COMPLETED BY W. HEYSEK TELEPHONE (717) 948-8191 j OPERATING STATUS I NOTES:

UNIT NAME

THREE MILE ISLAND UNIT 1 1.

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2. REPORTING PERIOD: JANUARY 1997

3. LICENSED THERMAL POWER: 2568 I

4. NAMEPLATE RATING (GROSS MWe): 872 l

5. 819 6.

- DESIGN ELECTRICAL RATING (NET MWe):

834

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MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): i

!- 7. ' MAXIMUM DEPENDABLE CAPACITY (NET MWe): 786 I

8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

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, :9 POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):

10. REASONS FOR RESTRICTIONS,IF ANY:

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TIIIS MONTil YR.TO-DATE CUMMUIATIVE e 11.- HOURS IN REPORTING PERIOD:

(HRS) 744.0 744.0 1 % ,5.83.0 l

,l 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 744.0 119,071.0

+

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2,284.0 f 14. HOURS GENERATOR ON LINE (HRS) 744.0 744.0 117,909.3

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

,. 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,908,743.0 1,908,743.0 290,514,418.4

17. ~ GROSS ELECTRICAL ENERGY GENERATED (MWH) 647,123.0 647,123.0 97,611,669.1  !

18. NET ELECTRICAL ENERGY GENERATED - (MWH) 611,770.0 611,770.0 91,755,434.1 4

19. UNIT SERVICE FACTOR - (%) 100.0 100.0 60.0

20. UNIT AVAILABILITY FACTOR (%) 100.0 100.0 60.0

21. UNIT CAPACITY FACTOR (USING MDC NET) 104.6 104.6 59.4-22.. UNIT CAPACITY FACTOR (USING DER NET) 100.4 100.4 57.0

-23. UNIT FORCED OUTAGE RATE (%) 0.0 0.0 34.0 '

UNIT FORCED OUTAGE HOURS (HRS) .

0.0 0.0 60,761.2 l 24. ' SHUTDOWNS SCHEDULED OVER THE NEXT SIX MONTHS (TYPE, DATE AND DURATION OF EACH):

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25. IF SHUTDOWN AT THE END OF THE REPORT PERIOD, ESTIMATE DATE OF STARTUP:

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AVERAGE DAILY UNIT POWER LEVEL l

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l DOCKETNO. 50-289 DATE 02/17/97-  ;

COMPLETED BY W. HEYSEK -

TELEPHONE (717)948-8191 ,

MONTH: JANUARY j DAY- AVERAGE D AILY POWER DAY AVERAGE DAILY POWER LEVEL (MWe NET) LEVEL (MWe NET) 1 827 16 823 2 824 17 827 1 3 815 18 821 l 4 815 19 816 5 815 20 818

-6 819 21 824 7 824 22 821 8 824 23 819 9 825 24 825 10 824 25 822 11 826 26 826 12 825 27 825 13 822 28 822 14 819 29 827 15 819 30 825 I 31 824 i

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~ DOCKET No. 50-289 . t UNIT NAME .TMI-l

• I January 1997 DATE 02/17/97

• REPORT MONTH COMPLETED BY~ W. G. Heysek~

TELEPHONE (717) 948-8191 i

Method of larensee Svsten Cosmponent Cause & Corrective Shuteng Event Code Code Acean to

• Due Type' Diranan Rm' Down Repat# c Prewer Reowrence N) Remer' *a' , ,

5 None  ;

i I 2 3 4 I

F Farced Reesca Method Extubst G-Insawtons for

- S Scheduled A-Eqtupment Fahre G.xphur0 t-Manent preparueon o(Dean Eney Sheets B-Mameenance a Test 3-Manumi Scruo En Iacensee Event Report (LER) [

C-Refhehms 3.Automanc Scrurn Fine (NUREG-0161)

IMteguinery E.esenconn 4cher(ExplurJ .

Ew Tranes & tacenans " 5 Exhami s.me ee  !

F-Adminstrieve W Error (Expiesn)

Hoher(Explun) 6 Acusally used extatuts F & D NUREG 6161 I

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REFUELING INFORMATION REOUEST

1. Name of Facility: Three Mile Island Nuclear Station, Unit I

! 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

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

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:

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

plans to perform independent reload design evaluations for Cycle 12, the l next operation cycle, based on NRC approved methods described in GPU Nuclear Topical Reports TR-091 A (core physics), TR-087A (core thermal .

hydraulics), TR-078 (FSAR safety analyses) and TR-092P (design and

setpoints methodology) submitted to the NRC. The latter two are in the

, final NRC approval stage.

The GPU Nuclear Cycle 12 reload program and results are expected to be  !

available for NRC r ew in the March to April 1997 time frame.

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) b) Cycle 12 fuel rod performance calculations (e.g. internal pin pressure) j will be performed by Framatome Cogema Fuels Company (FCF) using the j 4

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  !

4 fuel criteria in the latest approved revision of BAW-10179P-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. Approval is expected soon. The TACO calculations are being done using power ]

histories generated with the GPU Nuclear approved core physics codes i CASMO-3/ SIMULATE-3 (TR-091A). 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 j 4.8%, was approved by NRC on October 4,1995 for application to TMI-1 i only.

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l 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 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. l Upon completion of Phase II of the reracking project, the fulllicensed

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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