ML19325D425

Monthly Operating Rept for Sept 1989 for TMI-1

ML19325D425
Person / Time
Site:	Three Mile Island
Issue date:	09/30/1989
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-89-2119, NUDOCS 8910240033
Download: ML19325D425 (6)

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Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191

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717 944 7621 TELEX 84 2386

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Writer's Direct Dial Numbet:

October 13, 1989 C311-89-2119 s

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U. S. Nuclear Regulatory Connission Attne Document Control Desk Washington, D.C.

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. Dear Sir Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 i

Docket No. 50-289 Monthly. Operating Report September'1989 i

t-l Fnclosed are two copies of the September 1989 Morthly Operating Report for I.

.Three Mile' Island Nuc) ear Statioa, Unit 1.

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Sincerely,

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ill Vice President Tm Director, TMI-1 HDB/WGHispb

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cc W. Russell, USNRC L

.F. Young USNRC 1

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/ g GPU Nuclear Corporation Is a subsidiary of the General Public Utilities Corporation

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a OPERATIONS

SUMMARY

SEPTEMBER 1989 I

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j The' plant entered the month operating at 100% power producing j

approximately 870 Hwe. Da September 1, 1989 power was reduced to approximately 95% as a result of a module failure in the ICS. The plant was returned to 100% power within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and continued at tha* 1evel for the remainder of tha month.

MAJOR SAFFTY RELATED MAINTENANCE

' During the month of Septnmber, the following major maintenance activities

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were performed on safety-related equipment:

Primary Neutralizing Tank (WDL-T-8)

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Primary Neutralizing Tank (WDL-T-8) repairs were completed in September.

Work performed included completion of the recoating of the tank's internal surfaces,. repairing and reinstalling tank mixer 'JDL-M-1 and repairing the tank' discharge nozzel, flange gasket seating area. A closcout inspection WDL-T-8 has been was performed on the tank and the manway reinstalled.

returned to service.

. !jakg-up System Valve MU-V-1045 Repairs to a weld' leak at Make-up and Purification System Valve MU-V-1045 As there was no isolation for HU-V-1045, a vendor.

were completed.

Freeze Service Inc., was contracted to apply a freeze seal to the piping upstream of the valve. Liquid nitrogen-was used as the freezing agent.

With the freeze plug in place the defective area of the weld was excavated.. NDE personnel performed liquid penetrant tests and dimensional checks at the weld joint. The joint was rewelded and inspection results were satisfactory. The freeze seal was allowed to thaw and the system

.returr.ed to service.

Cardox Fire Service Pump (FS-P-7)

The Cardcx Fire System Compressor which tripped en thermal overload after repair of the same problem carlier in August was monitored during the month-of September. No additional trips occurred and no problems were identified as a result of the monitoring effort. The compressor continues a

'to operate satisfactorilly.

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' OPERAYING DATA' REPORT n

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l4 DOCKET NO..

'50-289

,V DATE' 9-30-89 s

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COMPLETED BY _C.W.

Smyth TELEPHONE (717) 948-8551-i 1

10PERATING STATUS-1 NOTES.

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'1.'UNITyNAME '

THREE MILE ISLAND UNIT l'l I

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REPORTING PERIOD:

SEPT

,1989.

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3. LICENSED THERNAL POWER (NWT):

2568.*.I l'

4. NAMEPLATE RATING (GROSS NWE):

871. I l'

5. DESIGN. ELECTRICAL-RATING (NET NWE):

819. I 1

'R3..MAXINUM DEPENDABLE CAPACITY (GROSS NWE):

856. I 1

j 7.-MAXINUN. DEPENDABLE CAPACITY (NET NWE):

808. I I:

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e3b.LIFCHANGESOCCURtIN(ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

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19k POWER LEVEL'TO WHICH. RESTRICTED, IF ANY (NET NWI)

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10. REASONS FOR RESTRICTIONS, IF ANY

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F THIS MONTH YR-TO-DATE CUMMULATIVE 4.'!!7 HOURS.IN. REPORTING PERIOD 720.

16551.

132192.

12." NUMBER.0F HOURS REACTOR WAS CRITICAL 720.0 6551.0 59002.4 c:.132 REACTOR RESERVE SHUTDOWN' HOURS 0.0 0.0 1960.0 h14. HOURS' GENERATOR ON LINE' 720.0

'6551.0

.58833.0 104 UNIT RESERVE SHUTDOWN HOURS ~

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'.10. -1 GROSS THERNAL ENERGY GENERATE 9 (NWH) 1845878.

16792255.

144151360.

[ ;'17.. GROSS. ELECTRICAL' ENERGY GENERATED-(NWH) 626899.-

5759244.

4843?929.

10.tNET ELECTRICAL ENERGY GENERATED (NWH) 593213.

5447916.

4541'.26.

10.1UNITiSERVICE FACTOR 10'O.0 100.0 44.5

. 20.DUNIT< AVAILABILITY-FACTOR 100.0 100.0 44.5 lL21'.' UNIT' CAPACITY FACTOR (USING MDC NET)

,102.0 102.9 43.9 f

i 22.' UNIT-CAPACITY FACTOR (USING DER NET)

'100.6 101.5 42.C' L 23.1 UNIT FORCED OUTAGE RATE O.0 0.0 50.6'

' 2 43 / CHUTDOWNS SCHEDULED OVER NEXT 6=NONTHS (TYPE, DATE, AND DURATION OF EACH

'8R Refuelino Outaae 1/5/90 - 3/5/90 s

- 25.' IF: SHUT DOWN AT END OF REPORT PERIOD, ESTINATED DATE OF STARTUP:

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,1 AVERAGT' DAILY UNIT POWER' LEVEL

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DOCKET NO.

50-289 iv UNIT TMI-1 6

. DATE,,. 9-30-89 L

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COMPLETED BY. _ L.W. Smyth TELEPHONE ', /1/ J 946-Ubb1 l

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' DAY-AVERAGE-DAILY POWER LEVEL DAY AVERAGE DAILY POWER. LEVEL (NWE-NET)-

(NWE-NET) i L

1.

816.

17 825.

2

.818.

18 828.

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829.-

19 827.

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829.

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4' 5-829.:

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22 808.

7 823.,

23 822.

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' 24 037.

9 815.4

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10 809.

26 B29.

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813.

27 839.

12

'821.

28 838.

'13 821.

29 832.

' 14 815.

30 834..

820.

31 N/A 15 16 ~.

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{i-REFUELING INFORMATION REQUEST

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Name of Faci 3ity:

Three Mile Island Nuclear Station, Unit 1 7,

Scheduled date for next refueling shutdown:

January 5, 1990 (8R) 3.

Scheduled date for restart following refueling: March 5, 1990 (8R)

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Will refueling or resuminion of operation thereafter require a technical specification change or other license amendment?

No If answer is yes, in general, what will these be?

If unswer 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?

December 1, 1989 5.

Scheduled date(s) for submitting proposed licensing action and sup,norting information.

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:

None 7.

The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pools (a) 177 (b) 360 8.

Tha present licensed spent fuel pool storage capacity and trie 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 752. Planning to increase licensed capacity thruugh fuel pool raracking is in process.

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 refuelin,= discharge which allows full core off-load capacity (177 f.el assemblies).

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