ML20082T102

Monthly Operating Rept for Aug 1991 for TMI Nuclear Station, Unit 1

ML20082T102
Person / Time
Site:	Crane
Issue date:	08/31/1991
From:	Broughton T, Wells R GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-91-2104, NUDOCS 9109180104
Download: ML20082T102 (7)

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GPU Nuclear Cotporation c Nuclear

,o=greo Middictown, Pennsyivania 17057 0191 7'47 944 7621 (ELEX o4 2".66 ffe7 s gigtgNumber.

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Septirttrr 16, 1991 C311-91-2304 H. S. Nuclear Regulatory Commission Attn: Document Control Desk Washingto, D.C.

20555

Dear Sir:

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Subject:

Three Mile Island Nuclear Station, Unit 1 (TMI-1) i Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report August 1991 i

Pursuant to TM1-1 Technical Specification 6.9.1.c, attached is the August 199'.

Monthly Operating Report for 1hree Mile Island Nuclear Station, Unit 1.

l Sincerely,

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T. G. Brougnton L

Vice President & Director, TMI-1 RDW:

Attachtrent ec:

R. Hernan - Senior Project Manager T. Martin - Regional Administrator F. Young - NRC Sr Resident Insnector TMI l

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9109180104 910931 PDR ADOCK 05000289

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g GPU Nuclear Corporabon is a subsid,ary of Genera! Puohc Uubbes Corporabon i

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L OPERATIONS SUtHARY

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AUGUST 1991 l

The plant entered the month operating at approximately 95% reactor power

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producing 810MW electric. The plant continued at that power level for the entire month.

Reactor power level continues to be limited by the "B" OTSG operating j

range water level. Leakoff from the #1 seals of Reactor Coolant Pumps (RCP) "A" l

and "C" has remained stable at 10 and 8 gallons per minute (GPM).- respectively.

c incretses have occurred on the "B" RCP to about 5 gpm and on the "D" RCP to about 6 gpm. The seals continue to operate normally in all other aspects. Primary to secondary leakage remains unchanged from July with an August monthly average of 0.074 gpm.

The license condition change to raise the operating limit from 0.1

-to 0.2 gpm above the baseline leakage was approved by the NRC during this I

reporting period.

The NRC licensed operator initial exams were conducted for i

seven (7)' candidates; results have not yet been received..The unit closed the month operating at approximately 95% power.

h MAJOR SAFETY RELATED MAINTENANCE i

During August, the following major Safety Related maintenance items were i

performed:

RADIATION MONITOR RM-A-2

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t Radiation Monitor RM-A-2 was removed from service in August to replace the temporary heat trace and the sample prnel. The new sample panel is equipped with r

a smaller diameter tubing, more durable rotameter, and high reliability valves.

The temporary heat trace transformer, heat trace and insulation were removed.

A new heat trace transformer, along with new permanent heat trace, were installed and tested satisf actorily. The new sample panel was also tested satisf actorily.

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MAIN STEAM VALVE MS-V-10A l

-The Main Steam Gate Valve MS-V-10A bonnet-leak was repaired-by the vendor by using_ an hiected sealant. To accomplish this, the bonnet studs were replaced

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with lugcr studs. 1-iection adapter nuts were installed on the new studs. The

' bonn #t hak' ras ther. sealed by the vendor.

After two-(2) days, the-bonnet i

stat % to inak again and the vendor injected more sealant into the valve appe r 41y c.n recting the problem.

i VENTILATION SYSTEM CHARC0AL FILTERS l

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V:Entilation System Charcoal Filter testing began _ in August.

The filters for 1

Control Building ventilation fans AH-E-18A/B and Reactor Building ventilation i

' f ans AH-E-7A/B en '00P' and ' Halide' tested satisfactorily. Auxiliary Building -

l (AB) ventilat' on fl.' te r unit AH-F-2A was also _' DOP ' and ' Halide' tested satisfactorily.

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l VENTILATION SYSTEM CHARCOAL FITTERS (Cont'd) l AB ventilation filter unit AH-F-2C was 'DOP' tested satisfactorily, but failed k

the ' Halide' test. The affected filters were replaced and tested satisfactorily, AB ventilation filter AH-F-2D was ' Halide' tested. Bank-1 of the filter unit was acceptable, but Bank-2 f ailed the test. The filters on Bank-2 were replaced and

-the ' Halide' retest was acceptable. This filter unit is scheduled to be 'D0P' I

tested in September 1991. AB ventilation filter unit AH-F-2B will be 'DOP' and

' Halide' tested at that time.

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FUEL RECEIPT j

Fuel Receipt activities accomplished in August included receiving, inspectirig and storing: thirty-six (36) fuel assemblies with burnable poison rods; nine (9) control rods; and five (5) burnable poison rod assemblies.

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e OPERATING DATA REPORT DOCKET NO.

50-289 DATE P &tfrfer I b 3001 COMPLETED BY R D WELLS OPERATING STATUS TELEPHONE (717) 948-8693

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 NOTES:

3. REPORTING PERIOD AUGUST 1991

3. LICENSED THERMAL POWER:

2568

4. NAMEPLATE RATING (GROSS MWe):

873

$. DESIGN ELECTRICAL RATING (NET MWe):

819

6. MAXIMUM DtPENDABLE CAPACITY (GROSS MWe):

856

7. KAXIMUM DEPENDABLE CAPACITY (NET MWe):

808

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

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

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 744.0 5831.0 148992.0

13. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 744.0 5 *, ' 4. 5 74948.7

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2245.6

14. HOURS GENERATOR ON-LINE (HRS) 744.0 5779.1 73898.8

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

16. CROSS THERMAL ENERGY GENERATED (MWH) 1812597 13128232 179598564

17. CROSS ELECTRICAL ENERGY GEN 3ATED (KWH) 607891 4596161 60557065 I

18. NET ELECTRICAL RNERGY GENERATED (HWH) 573460 4322977 56812397

19. UNIT SERVICE FACTOR

(%)

100.0 99.1 49.6

30. UNIT AVAILABILITY FACTOR

(%)

100.0 99.1 49.6

33. UNIT CAPACITY FACTOR (USING MDC NET) 95.4 91.8 48.5

33. UNIT CAPACITY FACTOR (USING DER NET) 94.1 90.5 46.6 33.' UNIT FORCED OUTAGE RATE

(%)

0.0 0.9 45.1

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

Cycle 9 Refueling Outage. scheduled to begin 9/27/91, with a nominal 7 to 10 week duration.

35. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF LTARTUP:

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AVERACE DAILY UNIT POWER LEVEL DOCKET No.

50-289 UNIT THI-1 DATE Scotcrier 16, 1901 COMPLETED 8Y R D WELLS

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TELEPHONE (717) 948-8693-MONTH:

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

(MWe-NET) 1 1

763 17 770 2

760 18 769 3

764 19 770 4

764 20' 774

-5 774

.21 777 6

777 22 775 7

778 23 769 8

770 24 770 i

-9 769 25 775-

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10 777 26 777 11 779 27 768 12 778 28 761 13 776 29 761 14 774 30 761 15 775 31 764 16 773 f

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET 300.

50-289 UNIT hAME TMI-1 REPORT MONTH Aucust 1991

-DAIT Setsi T 16, 1991 COMPLETED BY R. D. Wells TELEPHONE (717) 948-8693 9tethod of Licensee System Component Cause & Corrective 88 0 -

Date Type Duratien Reason 2. Shutting Event Code Code Action to I

(Mours',

Down Reporti Prevest Recurrerre ReactoN 5 6 g

NONE t

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4 F Forced Reason Method Exhibit G - Instructioris for S Scheduled A-Equipment Feiture (Explain) 1-Manuet preperation cf Cate Entry Sheets B-Mainte m e er Test 2-maust Scree for Licensee Event Report (LER)

C-Refueling 3-Automatic Scram File (NUREG-0161)

D-Regulatory Restriction 4-Other (Explain)

E-Operater Training & Licensing Examination 5 Exhibit 1 same sou-te F-A$tinistrative G Operational Error (Emptein) 6 Actuelty used exh; bits F & II utFEG C161 5-Other (Explain) 6

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REFUELINGINFORMA110t1RguEST 1.

Name of facility:

Three Mile Island Nucicar Station, Unit 1 2.

Scheduled date for next refueling shutdown:

September 27, 1991 (9R) 3.

Scheduled date for iestart following current refualing: NA 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? No.

If answer is yes, in general, what will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)? No.

If no such review has taken place, when is it scheduled? 9/91.

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Scheduled date(s) for suk ;tting proposed licensing action and supporting information:

None planned.

6.

Important licensing considerations associated with refueling,1.g. new or different fuel design or supplier, unreviewed desiga or performance i

analysis methods, significant changes in fuel design, new operating procedures:

GPU Nuclear plans to install four Westinghouse Lead Test Assemblies during the reload of the TM1-1 core for cycin 9 operation.

Westinghouse fuel technology will be utilized to the extent possible.

7.

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

(a) 177 (b) 441 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 capar.ity is 752. Planning to increase licensed capacity through fuel pool teracking is in progress.

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1991 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).

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