ML20127E458

Monthly Operating Rept for Dec 1992 for TMI-1

ML20127E458
Person / Time
Site:	Crane
Issue date:	12/31/1992
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-93-2001, NUDOCS 9301190320
Download: ML20127E458 (7)

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GPU Nuclear Corporation QQgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TEL.EX 84 2386 Writer's Direct Dial Number; (717) 948-8005 January 13, 1993 C311-93-2001 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 December 1992 Enclosed are two copies of the December 1992 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, f

W T. G. Bro hton Vice President and Director, TMI-l WGH Attachments cc: Administrator, Region I TMI Senior Resident Inspector 1 4.". ' C 2.

9301190320 921231 PDR ADOCK 05000289

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GPU Nuclear Corporation is a subsidiay of General Pubhc Utihties Corporation y

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1 OPERATIONS

SUMMARY

December 1992 The plant operated at 100% power,_ producing 860 MWe, during the majority of the month of December. On two separate occasions, an administrative power limit of 2650 MWth was in effect. This was due to the affects on the feed Water flow correction factor caused by calibration of T, and T,,ie so instrumentation. A 0.3% power reduction resulted.

MAJOR SAFETY RELATED MAINTENANCE During December, the following major safety related maintenance was performed:

Nuclear Service River Water Pumo NR-P-1B The overhaul of Nuclear Service River Water Pump NR-P-1B, begun in November,.

was completed in December. The pump was rebuilt using new shafting, bearings, and bowl assembly.

Post maintenance testing was performed after the motor was reinstalled and coupled to the reassembled pump.

The test results were satisfactory and NR-P-1B was returned to service.

Nitroaen Filter NI-F-2 Galled threads on the Core Flood Tank Nitrogen Filter NI-F-2 canister housing necessitated replacement of the unit.

A new filter housing was obtained and welded into the system.

NI-F-2 was tested satisfactorily with no leakage evident and returned to service.

Decay Heat Removal System Valve DH-V-4A Body to bonnet _ leakage on DH-V-4A, the Decay Heat Removal Pump isolation valve, was repaired. Maintenance actions included live loading and retorquing the bonnet studs to eliminate body to bonnet leakage.

Reactor Buildino Eouioment Hatch Door During performance of a scheduled surveillance, the Reactor Building Equipment Hatch inner door was-determined-to be leaking. One by one, the contributors-to the leakage were identified and eliminated.

Maintenance actions included-overhaul of the pressure equalizing ball valve, replacement of the inner door gaskets, and adjustment of-the linkage arm / operating shaft packing.- A successful surveillance test was performed after the corrective maintenance was completed'.

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j OPERATING DATA REPORT I'

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DOCKET NO.

50 289 l

DATE' COMPLETED BY W G HEYSEK j

OPERATING STATUS TELEPHONE (717) 948 8191-

1. UNIT NAMES.

THREE MILE ISLAND UNIT 1 l NOTES:

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2. REPORTING PERIOD DECEMBER _1992 l

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3. LICENSED THERMAL POWER:

2568 l l

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4. NAMEPLATE RATING (GROSS MWe):

871 l l

l S. DESIGN ELECTRICAL RATING (NET MWe):

819 l l

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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 OCCUK IN (ITEMS'3 7) SINCE LAST REPORT, GIVE REASONS:

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9. POWEa LEVEL TO WHI'H RESTRICTED,. IF ANY (NET MWe):

10. REASONS FOR RF 'ThacTIONS, IF ANY:

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THIS MONTH.YR-TO-DATE CUHMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 744.0

-8784.0 160705.0 1

12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 8745.8 85476.8

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 38.2-2283.8

14. HOURS GENERATOR'ON.LINE (HRS) 744.0 8743.0 84400.1 l

15. UNIT RESERVE SHUTDOWN HOURS (HRS)-

0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1906278 22177659

.206046704

17. GROSS ELECTRICAL-ENERGY GENERATED (MWH) 645496

7350815 69345074 4

18. NET ELECTRICAL ENERGY GENERATED

-(MWH) 609852 6935638

_65102307

'19. UNIT SERVICE FACTOR (1) 100.0:

99.5 52.5 l

20. UNIT AVAILABILITY FACTOR

_ (%)-

_100.0 99.5 52.5

21. UNIT. CAPACITY FACTOR' (USING MDC NET) 104.3 100.5 51.5

32. UNIT CAPACITY FACTOR (USING DER NET)

-100.1 96.4 49.5

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.5 41.8 I

UNIT FORCED OUTAGE HOURS (HRS) 0.0 41.0 60689.7

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

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25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPi c

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 I

UNIT THI-1 DATE COMPLETED BY W G llEYSEK TELEPHONE (717) 948-8191 I

MONTH:

DECEMBER j

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

(MWe-NET) 1 814 17 819 2

814 18 820 1

3 813 19 821 l

4 820 20 819 l

5 824 21 823 j

6 826 22 820 1

7 824 23 816 8

822 24 820 1

9 824 25 822 i

10 821 26 821 11 817 27 822 4

12 820 28 820 l

13 821 29 819 14 822 30 816 l:

15 823 31 808 16 821 f

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' UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No.

50-289 UNIT NANE TMI-l f

REPORT MONTH December 1992 DATE COMPLETED BY W. G.

Heysek TELEPEONE (717) 948-8191 1

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. Method of Licensee System :omponent Cause & Corrective l

No.

Date Type' Duration Reasorf Shutting Event Code Code Action to I

(Hours)

Down Report #

Prevent Recurrene.

Reactor *

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NONE i

1 2

3 4

F Forced Reason Method Exhibit G - Instructions for S SchedJted A-Equipment Failure (Explain) 1-Manuel preperation of Data Entry Sheets B-Maintenance or Test 2-Manual scram for Licensee Event Report (LER)

C-Refueling.

3-Automatic Scram File (NUREG-0161)

D-Regulatory Restriction 4-Other (Explain) l E-Operator Training & Licensing Examination

. 5 Exhibit 1 s.me source i

F-Administrative

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G-Operational Error (Explain) 6 Actuelty used exhibits F & II NUREG 0161 N-Other (Explain)

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REFUELING INFORMATION RE0 VEST 1.

Name of facility:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

September 17, 1993 (10R) 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 In general, these will be:

a)

Technical Specif' cation Change Request (TSCR) No. 212 requesting"an increase of the allowable enrichment of fresh fuel to 5.0 wt/o U was submitted August 25, 1992, b)

TSCR No. 220 requesting approval to move the Maximum Allowable LOCA Linear Heat Rate Limits (T.S. Figure 3.5-2M) to the Core Operating Limits Report was submitted on October 29, 1992.

c)

Use of urania-gadolinia fuel and B&W Fuel Corporation (BWFC) changes in core physics methods may require change to T.S. 6.9.5.2 which lists approved analytical methods references to support the Core Operating Limits Report values.

Changes to T.S. 6.9.5.2 could include reference to BAW-10180, Rev a, NEMO and BAW-10184P, GDTACO methods (see #6a below). Use of the gadolinium integral burnable poison ray also require changes to the Reactor Core fuel descriptions in T.S. 5.3.1.

d)

Consistent with the higher fuel loadings planned for Cycle 10 and beyond, the borated water storage requirements of T.S. 3.2 will need to be increased.

5.

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

Submittals made to date are described in 4a and b above. The TSCR submittal schedule for use of the urania-gadolinia fuel and for increased boron requirements will depend on completion of the USNRC review of the applicable BWFC methods addressed in 4c above and the BWFC boron analysis results addressed in 4d above.

Per recent discussions, NEMO, Rev. I approval is expected in the near term.

BWFC boron preliminary results indicate that no change is necessary.

Final results are expected in March 1993.

Based on this date, if a change is necessary, the GPUN TSCR would be submitted in April 1993.

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:

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BWFC and GPUN are now performing the fuel-cycle design for cycle 10, which is scheduled for startup ' n October.1993. This design i

incorporates reload fuel that contains urania-gadolinia.

Use of-L this type of fuel may require changes _ to the plant Technical-Specifications as noted in 4c above.

These changes would need to be supported by approval of BWFC topical reports on reload design 3 i

- methods-revisions:that account for the Gd offacts-in the ana'yses;-'

the NEM0 physics code was noted in 5.above. Approval-of BAW-10184P, i

GDTAC0 is also required to support fuel thermal analysis. To ensure that no delays occur to reload analyses, fuel manufacturing and plant startup schedules, approval of these topicals. has been:

i requested for April-1,1993.

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b)

TMI-1 will use the new Mark B9 fuel assembly in the Cycle 10 reload' l

batch. This design is an upgrade of _the Mark B8 assembly used-in

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Cycles 8 and 9..

The Mark B9.provides improved fuel thermal limits j

(LOCA, DNBR, CFM).and repair capabilities. The Mark B9 design meets current BWFC fuel design criteria and'has been used previously at I

other B&W 177 FA plants.

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BWFC has a licensing. change-under USNRC review-for certification of-4 the Siemens fuel assembly shipping container desi twoBWFCMarkBfuelassembliesupto5.0wt/oU'gnforshipmentof-This change is necessary to support the TMI-1 Cycle 10 fresh fuel receipt'by j

reducing the number of fuel shipments and fuel hand'ng activities.

i The risk of fuel damage is also minimized.

Based 4. the 12/3/93 BWFC/NRC meeting on this issue, approval _is expected by March 1993.

Cycle 10 fuel shipments will start in June 1993.

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7.

The number of-fuel assemblies (a) in the core, and (b)-in the spent fuel storage pool:

(a) 177 (b).521 i

8.

The present licensed spent fuel pool storage capacity and the size of _any 1

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

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The present-licensed capacity is 1990. -Phase 1 of the reracking-1 project to increase spent fuel pool storage capacity permits storage I

of 1342 assemblies. Upon completion;of Phase II'of.the reracking-

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project,1the full licensed capacity will be attained.

b 9.

_The projected date of the last refueling that can be discharged to the--

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spent fuel pool assuming the present -licensed capacity:

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of Phase I of the reracking project permits full core

- off-loaa (177 fuel assemblies) through the:end of Cycle:14 and on i

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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