ML20116N657

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

ML20116N657
Person / Time
Site:	Crane
Issue date:	07/31/1996
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-96-2274, NUDOCS 9608220225
Download: ML20116N657 (7)

Text

.

2 4

l GPU Nuclear,Inc.

(

Route 441 South NUCLEAR Post Office Box 480 Middletown, PA 17057-0480 Tel 717-944 762) i

}

August 14, 1996 6710-96-2274 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 July 1996 Enclosed are two copies of the July 1996 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely,

.[

J.Knubel Vice President and Director, TMI WGH 9608220225 960731 PDR ADOCK 05000289

/

cc: Administrator, Region I

^ gt[ /g R

PDR TMI Senior Resident Inspector 96001 212038 i

OPERATIONS

SUMMARY

July 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 796 MWe during July.

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

NR-V-13C Piping R_epairs A pin hole leak was found and repaired in the piping near NR-V-13C, a Nuclear Service Closed Cooler backwash valve. The repair involved welding a half coupling over the area of the leak and installing a pipe plug in the half coupling. The results of post-maintanance inspection were satisfactory and NR-V-13C and its associated piping were returned to service.

1 l

1 l

l

OPERATING DATA REPORT DOCKET NO.

50-289 DATE August 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:

JULY 1996

3. LICENSED THERMAL POWER:

256C

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) 744.0 5111.0 192006.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 5111.0 114654.1

)

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

14. HOURS GENERATOR ON-LINE (HRS) 744.0 5111.0 113492.3

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,907,510.4 13.067,216.6 279,182,142.6

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 626,781.0 4,363,570.0 93,817.044.1

18. NET ELECTRICAL ENERGY GENERATED (MWH) 502,582.0 4,123,392.0 88,166,796.1

19. UNIT SERVICE FACTOR

(%)

100.0 100.0 59.1

20. UNIT AVAILABILITY FACTOR

(%)

100.0 100.0 59.1

21. UNIT CAPACITY FACTOR (USING MDC NET) 101.3 102.6 58.4

22. UNIT CAPACITY FACTOR (USING DER NET) 97.3 98.5 56 0

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.0 34 8 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 s.

DOCKET NO.-

50-289 UNIT TMi-1 DATE August 14, 1996 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:

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

(MWe-NET) 1 791 17 792 2

795 18 793 3

802 19 790 4

804 20 801 5

803 21 800 6

799 22 803 7

794 23 800 8

789 24 795 9

791 25 791 10 802 26 794 11 804 27 801 12 802 28 800 13 794 29 799 14 789 30 798 15 788.

31 795 16 791 i

S e

3

DOCKET NO.

50-289.-

I tiNIT NAME TMI-l I

DATE August 14,-1996 -

REPORT MONTH July 1996 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 Method of Izcmce system Component Came & Comsnw Shumns Everit Code code ACO'm h

Date Type Durunen Remmn1 Down Reports tHoum)

Reecew

'A' 2

,g.

None 1

2 3

4 r ro.cea R"

exa,b G.huoucnom rw S kheduled A Equipment Falure Explam) g_y

,,g preparabon ofDa Enuy Sheen B Mamtanens*orTea 2-M M h fwIxennes Event Report (LER)

LAhkh Fde(NUREG-0161)

D egulatory Restnenea

• • EN

,x.,c,.,_1r m. A - E,_

5,- i

m. _

F Adrmnstrauw G(mersnonal Emu (Explam)

IMW(Explums

() A% used exhibits F A E NL1tEG 0161 4

=

REFUELING INFORMATION REOUEST 1

1.

Name of Facility: Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown: September 5,1997 j

3.

Scheduled date for restart following current refueling: NA l

4

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

specification change or other license amendment? Yes. To support GPU 4

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 references to the GPU Nuclear analysis methods applied to the reload.

s 1

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.

l i

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:

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 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 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 March to April 1997 time frame.

5

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-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 with approval expected about September 1996. The TACO calculations are being done using power histories generated with the GPU Nuclear approved core physics codes CASMO-3/SIMULAT E-3 (TR-091 A). A letter requesting 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-10180A, Rev 1) uncertainty of 4.8%. will be submitted in August 1996 with approval requested in September 1996.

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.

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 assembiies) through the end of Cycle 14 and on completion of the scrack project full core off-load is assured through and beyond the end of the current operating license.

6