ML20083C134

Monthly Operating Rept for April 1995 for Three Mile Island Nuclear Station

ML20083C134
Person / Time
Site:	Crane
Issue date:	04/30/1995
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-95-2235, NUDOCS 9505150132
Download: ML20083C134 (8)

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GPU Nuclear Corporation

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Route 441 South 4

P.O. Box 480 Midd etown, Pennsytvania 17057-0480 (717) 944-7621 Writer's Direct Dial Number:

(717) 948-8005 May 8,1995 C311-95-2235 U. S. Nuclear Regulatcry 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 Repon for April 1995 Enclosed are two copies of the April 1995 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, h

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T. G. Brough' ton Vice President and Director, TMI WGH Attachments i

x: Administrator, Region I I

TMI Senior Resident Inspector

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9505150132 950430 PDR ADOCK 05000289 R

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GPU Nuclear Corporation is a subsidiary of General Public Utdities Corporation g

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- OPERATIONS

SUMMARY

h April 1995 The plant entered the month operating at 100% power and remaiced at that level throughout t

the entire month. Net unit electrical output averaged approximately 815 MWe during April, The channels of the Reactor Coolant Inventory Trending System isolated after the March 7 j

Unusual Event remain isolated, rendering the system inoperable. Satisfaction of the requirement of Technical Specification section 3.24 was accomplished by including the appropriate details within the March Monthly Operating Report. No further mention will be i

made concerning the system's status until it has been returned to se vice.

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MAJOR SAFETY RFr ATED MAINTENANCE j

The following is a summary of major safety related maintenance items accomplished during l

the month.

EMERGENCY DIESEL GENERATOR EG-Y-1B i

Emergency Diesel Generator EG-Y-1B was removed from service during the week of April l

17 to perform the scheduled annual suiveillance/inspxtion. The limited scope inspection was performed with no major discrepancies found. Activities associated with completion of the surveillance included: replacement of engine jacket heaters, repair of exhaust manifold and fuel oil leaks; replacement of diesel air start piping and air stait valves; testing of relief j

valves EG-V-22B and EG-V-46B, r' pair of relief valve EG-V-76B and check valve EG-V-

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77B and inspection of check valves EG-V-10A/B and EG-V-10B/B, air tanks EG-T-1B1 and EG-T-1B2, and motors DF-P-1B and EG-P-10B; and calibration of transducers, various oil changes and breaker tests were performed. Upon completion of the inspection and satisfactory performance of post maintenance testing, EG-Y-1B was retumed to service.

EMERGENCY DIESEL GENERATOR EG-Y-I A During the week of April 24 Emergency Diesel Generator EG-Y-1A was removed from service to perform the scheduled annual surveillance!inspectiori. The limited scope inspection performed found no major discrepancies. Activities associated with this inspection included: repair of exhaust and fuel oil leaks and replacing air start piping and valves; inspection of relief valves EG-V-22A and EG-V-46A, check valves EG-V-10A/A and EG-V-10B/A, air tanks EG-T-1 A1 and EG-T-1 A2, various breakers and relay cabinets; various oil j

changes and transducer calibrations inspections were performed. It was decided to replace the existing generator outboard bearing and bearing enclosure assembly after both the oil sample wear particle count and the vibration stress nergy wave levels were found to be increasing. During the oost maintenance mn of EG-Y-1 A, the generator was operated at 2

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approximately 125% (3.4MW) of the manufacturer's continuous sted load for approximately 15 minutes. The cause of the overload condition was determined to be the failure of the generator potential transformer metering fuse (FU16). Based on recommendations from the manufacturer, a engine inspection was performed which involved removal of the scavenge air inspection covers to inspect the upper pistons, piston rings, and cylinder liners; removal of j

the control exhaust manifolds to inspect the lower pistons, piston rings, and cylinder liners; pressurization of the cooling water jacket to 50 psig to check for cylinder liner cracks and finally a check of the upper piston pin bushings with a feeler gauge. All inspections wem performed and no discrepancies found. EG-Y-1 A was retested satisfactorily and returned to service.

EMCTOR COOLANT WASTE EVAPORATOR WDL-Z-1 A Reactor Coolant Waste Evaporator WDL-Z-1 A was removed fmm service to replace a feed tank mptum disc which had failed. After the new mpture disc was installed and WDL-Z-1 A returned to service.

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OPERATING DATA REPORT DOCKET NO.

50-289

-DATE Mav 8.1995 COMPL_ LEU BY W.G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 l NOTES:

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2. REPORTING PERIOD:

APRIL 1995 l

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3. LICENSED THERMAL POWER:

2568 l l

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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

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7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

786 l l

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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:

r THIS MONTH YR-TO-DATE CUMMULATIVE

11. HCURS IN REPORTING PERIOD (HRS) 719.0 2879.0 181104.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 719.0 2879.0 104467.7

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

14. HOURS GENERATOR ON-LINE (HRS) 719.0 2879.0 103334.1

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

16. GROSS THERMAL ENERGY GENERATED (MWH) 1845262 7387212 253303482

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 620200 2496942 85180196

18. NET ELECTRICAL ENERGY GENERATED (MWH) 586278 2359034 80014452

19. UNIT SERVICE FACTOR

(%)

100.0 100.0 57.1

20. UNIT AVAILABILITY FACTOR

(%)

100.0 100.0 57.1

21. UNIT CAPACITY FACTOR (USING MDC NET) 103.7 104.2 56.2

22. UNIT CAPACITY FACTOR (USING DER NET) 99.6 100.0 53.9

23. UNIT FORCED OUTAGE RATE

(%)

0,0 0.0 37.O UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60761.2

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

Re_ fueling outage / September 8, 1995 / 45 days

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

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'4 7"

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AVERAGE DAILY UNIT POWER LEVEL.

DOCKET NO'.

50-289' UNIT TMI DATE-Pa_v R; 1 QQci COMPLETED BY W G HEYSEK :.

TELEPHONE (717) 948-8191 1

MONTH:

APRIL I

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

(MWe-NET) 1 821 17.

818 2

821 18 814

-3 819 19 804 4

816

'20 811 5

824 21.

810 6

820 22 809 7-818 23 816 8

820 24 816 9-814 25 813 10 820 26-812 11 817 27 808 12

.813 28 811 13 816 29 812 14 819 30-813 15 818 31 NA 16 818 e

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DOCKET NO. 50-289 UNIT NAME TMI REPORT MONTH April 1995 DATE May 8.-1995 COMPLETED BY W. G. Heysek TELEPfiONE (717) 948-8191 Imennee System

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Method of No.

Code ge,,,,,,

Type' Duration Reason' Shutung Date N

Prevent Recurrence Olours)

Down 8

Reactor None 1

2 3

4 F Forced Exhibit G. Instructanas for Reastm Method preparation of Data Entry Sheets 8N A-Equipment Faihare (Explain) 3.yano,g for Imensee Event Report (LER)

B-Mamtenance er Test 2-Manual Seren Fils (NUREG-0161)

C-Refueling 3_gm %

D-Regulatory Restrwtum

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- 5 Exhw i.ame.o.,ce

% Training & Licensing Ex nmahan F-Administrative

% Error (Explain).

6 ActuaDy used exhHs F & H NUREO 0161 HW (Explain) 6-

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REFUEllNG INFORMATION REOUEST l

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

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

3. Scheduled date for restan following curmnt mfueling: NA l

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4.

Will refueling or resumption of operation thereafter mquire a technical specification change j

or other license amendment? YES. See 6.c and d below, l

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

NA

6. Impodant licensing considerations associated with refueling, e.g. new or diffemnt fuel

.i design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

i a) TMI will use the new Mark B10 fuel assembly in the Cycle 11 reload batch unich N

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 failums during operation and

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requires visual inspection each outage. The Mark B10 design meets r3 current BWFC fuel design criteria and is in use at other B&W 177 FA plants.

t 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.

i The four E LTAs inserted in Cycle 9 were discharged at EOC-9 due to detection of fuel rod failures caused by grid-to-rod fretting similar to that seen in H Vantage 5H fuel designs. The Cycle 11 LTAs will use the generic E 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 red 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 E 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.

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c) GPUN is planning to place two types of BWFC advanced non-zircaloy cladding in TMI-1 Cycle 11; eight rods each. 'Ihe two types will be equally distributed in two Mark B10 fuel assemblies; one rod of each material in each of the four peripheral j

rows per assembly. -These cladding materials are also being irradiated in the -

McGuire nactor and other international reactors with no negative performance observed. Use of the cladding requires NRC acceptance of an exemption request mgarding 10CFR50.46 which will be submitted in May 1995.

l d) GPUN will be submitting Technical Specification Change Request number 252 to relocate the volume and boron concentration mquirements of TS section 2.3 for the 3

chemical addition system boric acid mix tank and reclaimed boric acid storage tanks to the existing TMI-1 Core Operating Limits Report (COLR). The proposed change is consistent with the intent of NRC Generic I4tter 88-16 guidance. The change will preclude the need for a TSCR to mvise the parameters to meet Cycle j

11 specific requirements.

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 601

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 Itfueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Completion of Phase I of the reracking projec+ 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 the end of the current operating license and beyond.

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