ML20092F440

Monthly Operating Rept for Aug 1995 for TMI-1

ML20092F440
Person / Time
Site:	Three Mile Island
Issue date:	08/31/1995
From:	Heysek W, James Knubel GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-95-2379, NUDOCS 9509180183
Download: ML20092F440 (8)

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GPU Nuclear Corporation Nuclear s - 44' sea P.O. Box 480 Middletown, Pennsylvania 170574480 (717)944 7621 Writer's Direct Dial Number:

(717) 948-8005 September 12, 1995 C311-95-2379 U. S. Nuclear Regulatory Commisston 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 August 1995 Enclosed are two copies of the August 1995 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, n vp 6

,J. Knubel

' Vice President and Director, TMI WGH 4

Attachments cc: Administrator, Region I TMI Senior Resident Inspector T95001 2SC13G 9509180183 950831 /

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OPERATIONS

SUMMARY

August 1995 The plant entered the month operating at 100% power and remained at that level for the entire month. Net unit electrical output averaged approximately 789 MWe during August.

MAJOR SAFETY RELATED MAINTENANCE The following is a summary of major safety related maintenance items ,

accomplished during the month. '

Fuel Receipt Activities 4

Fuel receipt activities were completed in August. A total of seventy-two fuel assemblies were received and stored in preparation for refueling.

] Boric Acid Pumps CA-P-1A/B The pulsation dampener diaphragms on Boric Acid Injection Pumps CA-P-1A/B were replaced. Failure of the diaphragms was found to result from heat trace

maintaining piping temperature at 286*F instead of 100*F. The temperature  ;

variance was caused by improperly wrapping the heat trace such that the i temperature control capillary was isolated from the trace. The heat trace was reinstalled and correctly reinsulated.

Sodium Hydroxide Recirculation Pump BS-P-2

! Sodium Hydroxide Recirculation Pump BS-P-2 was removed from service due to i packing leakage. The pump was repacked with 'Slade' leakless packing and adjusted per the manufacturer's instruction. Packing leakoff is being monitored until "run-in" is complete.

Reactor Building Ventilation Fans AH-E-1A/B/C l During Engineered Safeguards (ES) testing, Reactor Building Ventilation Fan AH-E-1A failed. Troubleshooting revealed failure of fast speed relay 24FX due to age. Both the fast and slow speed (24SX) relays were replaced on AH-E-1A.

When the fast speed relay on AH-E-1B failed during subsequent ES testing, the ,

fast speed and slow speed reiays t'n fans AH-E-1B and AH-E-lc were replaced. l Results of fan testing following the replacement of the components was l satisfactory.

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. .- r 11R Refuelino Outace Rampup Work The following activities were completed in preparation for the 11R Outage:

1. Main Steam and Feedwater Heater Safety Valve testing.

2. Preventative maintenance on Reactor Building hoists MIS-A-40A/B and MIS-A-41.

3. Rebuilding of the Reactor Coolant Pump cartridge seals and performance of flow testing.

4. Desilting the Natural Draft Cooling Tower settling basin.

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OPERATING DATA REPORT DOCKET NO. 50-289 DATE l

COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME: THREE MILE ISLAND UNIT 1 l NOTES: l

2. REPORTING PERIOD: AUGUST 1995 l l

3. LICENSED THERMAL POWER

2568 l l

4. NAMEPLATE RATING (GROSS MWe): 872 l l S. DESIGN ELECTRICAL RATING (NET MWe): 819 l l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 834 l l l 7. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 786 l l J l I j 8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

j 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 5831.0 184056.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 5831.0 107419.7

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

14. HOURS GENERATOR ON-LINE (HRS) 744.0 5831.0 106286.1

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1827389 14873651 260789921

! 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 621282 4978820 87662074 I

18. NET ELECTRICAL ENERGY GENERATED (MWH) 586748 4703555 82358973

19. UNIT SERVICE FACTOR (%) 100.0 100.0 57.7

20. UNIT AVAILABILITY FACTOR (%) 100.0 100.0 57.7

21. UNIT CAPACITY FACTOR (USING MDC NET) 100.3 102.6 56.9 j 22. UNIT CAPACITY FACTOR (USING DER NET) 96.3 98.5 54.6

23. UNIT FORCED OUTAGE RATE (%) 0.0 0.0 36.3 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60761.2 i

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):

Re-fueling outage / September 8, 1995 / 45 days

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 Uh1T TMI-1 DATE COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH: AUGUST DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) (MWe-NET) 1 777 17 778 2 766 18 786 3 770 19 793 4 775 20 799 5 783 21 790 6 787 22 793 7 797 23 799 8 800 24 792 9 798 25 802 10 790 26 800 11 790 27 793 12 786 28 795 13 788 29 794 14 782 30 792 15 782 31 789 16 783 4

e DOCKET NO. 50-289 '

UNIT NAME TMI-l REPORT MONTH August 1995 DATE COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 ,

Licensee System cause a correutve No. Method of Event Code Component Action to Type' Duration Reason

• Shutting Reportf Code Prevent Recurrence Date (%urs) > *&*

Reactor" a ,

None 1 2 3 4 F Forced Exhibit G - Instructions for Reason Method preparation of Data Entry Sheets S Scheduled A-Equipment Failure (Emplain) 1-Manual for Licensee Event Report (LER)

B-Maintenance er Test 2-Manuel Scram File (NUREG-0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Other (Emplain) t E-Operator Training & Licensing Enemination J Exhibit I same soerce F. Administrative H- er pa Actually used exhibits F & !! NUREG 0161 5

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v REFUELING INFORMATION REQUEST

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

2. Scheduled date for next refueling shutdown: September 8, 1995 j l

3. Scheduled date for restart following current refueling: NA l

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? YES. See 6.c and d below.

5. Scheduled date(s) for submitting proposed licensing action and supporting information: NA

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) TMI will use the new Mark B10 fuel assembly in the Cycle 11 reload batch which is an upgraded design of the Mark B9 assembly used in Cycle

10. The Mark B10 provides a leaf-type cruciform assembly holddown spring to replace the previous coil spring design which has experienced random failures during operation and requires visual inspection each outage. The Mark B10 design meets all current BWFC fuel design criteria and is in use at other B&W 177 FA plants.

b) TMI also will use four new Westinghouse Lead Test Assemblies (LTA) in the Cycle 11 reload batch. Their planned operation is for three consecutive cycles with discharge at end-of-Cycle 13.

The four W LTAs inserted in Cycle 9 were discharged at E0C-9 due to detection of fuel rod failures caused by grid-to-rod fretting similar to that seen in W Vantage 5H fuel designs. The Cycle 11 LTAs will use the generic W recommended design fix of rotated intermediate spacer grids to minimize flow-induced fuel vibrations and thus eliminate fretting. A prototype LTA was flow-tested to demonstrate the effectiveness of the fix. The production LTA will use ZIRLO fuel rod cladding, guide tubes and instrumentation tube and intermediate grids in place of Zircaloy 4 materials used for the Cycle 9 LTAs. Otherwise, the Cycle 11 LTA design is basically the same as the Cycle 9 design.

The LTAs will meet current W fuel design criteria while operating within TMI core operating limits. LTA enrichment and core location will ensure that an LTA will not be the lead (hot) assembly at any time during the cycle and will not set any safety or operating limits. The LTAs will remain bounded by existing UFSAR safety analyses results.

c) GPUN will to place two types of BWFC advanced non-zircaloy cladding in TMI-1 Cycle 11; eight rods each. The two types will be equally distributed in two Mark B10 fuel assemblies; one rod of each material 6

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in each of the four peripheral rows per assembly. These cladding

, materials are also being irradiated in the McGuire reactor and other international reactors with no negative performance observed.

Amendment 194 responding to TSCR 251 was issued on July 24, 1995 for the use of those advanced claddings. An exemption to 10CFR50.44 and 10CFR50.46 and Appendix K was determined by the NRC to be unnecessary.

d) GPUN submitted a revised Technical Specification (TS) Change Request No. 252, Rev 1 to eliminate TS 3.2 requirements and bases from the TS.

The change precludes the need for changes to the boron storage volume i and boron concentration limits for the boric acid mix tank and the

reclaimed boric acid storage tanks to meet the requirements of the

Cycle 11 reload evaluation before cycle startup. Issuance was requested on or before September 22, 1995.

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7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel l storage pool: (a) 177 (b) 673

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 1 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 l spent fuel pool assuming the present licensed capacity:

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

(177 fuel assemblies) through the end of cycle 14 and on completion of the l rerack project full core off-load is assured through the end of the current operating license and beyond.

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