ML20207N643

Monthly Operating Rept for Sept 1988 for TMI-1

ML20207N643
Person / Time
Site:	Crane
Issue date:	09/30/1988
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
C311-88-2142, NUDOCS 8810190273
Download: ML20207N643 (7)

Text

_ _ _____ _ __

OPERATIONS

SUMMARY

SEPTEMBER 1988 The unit entered September operating at 100% power producing approximately 880 MWe, A forced outage commenced on September 17, 1988. The plant was shutdown and cooled down to repair RC-P-1D seals. The reactor was critical on September 26, 1988 with the Turbine Generator back in service. The urit completed the month operating at 100% power.

Mt10R SAFETY RELATED MAINTENANCE During September, the following major maintenance activities were performed on safety-related equipment:

Reactor Coolant Pums RC-P-ID - Work was performed on Westinghouse Reactor coolant Pump RC-P-lD due to excessive seal leak-off.

The three seal package assemblies were removed from the pump and inspected.

The inspection revealed that the #1 seal runner / shaft 0-ring had failed and the #1 retainer ring /shaf t 0-ring was cut. A new #1 seal ring / runner assen61y with new 0-rings was obtained and installed in the pump. The #2 and #3 seal packages were reassembled and installed.

The radial bearing thermocouple was found damaged during reinsta11ation.

Attempts to repair the thermocouple failed and a replacenent thernocouple could not be located.

Westinghouse indicated the radial bearing thermocouple was redundant to the #1 seal water thermocouple and the pump could safely operate without it.

Pressurizer Code Safety Valve RCAV-1 A - Pressurizer Code Safety Valve RC-RV-1 A was replaced due to leakage when the plant was shutdown.

The valve was removed, packaged and shipped off-site for inspection and repair.

A rebuit/ tested valve was received and prepared fcr installation. The pressurizer mounting flange (inlet) was then found to have indications outside the gasket seating area.

The indications were removed by grinding and inspections deemed the flange satisfactory.

The valve was then installed on the pressurizer.

Makeup Pump MU-P Makeup Pump MU-P-1B was disassembled to repair an inboard seal leak. The coupling and inboard bearing assembly were removed.

The inboard mechanical seal assembly was removed, disassembled, and inspected.

Inspections revealed the seal faces were glazed and the seal was rebuilt using a new stationary and rotating assembly.

The seal was reinstalled in the punp and the inboard bearing assembly reassembled and installed.

The pump / motor coupling was reinstalled and aligned. The pump was test run satisfactorily, se10190273 880930 E

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e Source Range Neutron Flux Detector NI Repairs to source range detector NI-2 consisted of replacing the preamp.

Plateau checks and source curve checks were performed and the system returned to normal.

Temperature Element TE-960 - Repairs to Temperature Element TE-960 (T-hot) consisted of replacing the RTD. Loop calibrations were performad and TE-960 returned to service.

Intermediate Closed Cooling Pump IC-P-1B - Repairs to Intermediate Closed Cooling Water Pump IC-P-1B included removal and disassembly of the motor.

New upper and lower motor bearings were installed and the motor reassembled.

The punp was disassembled, inspected and reassembled using a new mechanical seal.

The pump / motor was reinstalled in the system and tested.

OPERATING DATA REPORT i,

DOCKET NO.

50-289 DATE 09/30/B8 i

COMPLETED BY C.

W.

SNYTH TELEPHONE 717-949-8551 OPERATING STATUS rg I NOTES I

.3.

UNIT NAME:

THREE MILE ISLAND UNIT 1 1 I

2e REPORTING PERIOD:

SEPT 1998. I 1

0.

LICENSED THERNAL POWER CNUT):

2568. l l

+

4. MANEPLATE RATING CGROSS NWE):

972. I I

.O. DESIGN ELECTRICAL RATINGCNET NWE):

819. l l

6 NAMINUN DEPENDABLE CAPACITY CGROSS MWE):

824. 1 I

P NAMINUM DEPENDABLE CAPACITY CNET MWE):

776. I i

1 1

1 C.

IF CHANGES OCCUR IN CITEMS 3-7) SINCE LAST REPORT. GIVE REASONS:

O. POWER LEVEL TO WHICH RESTRICTED, IF ANY CNET NWE) t

10. REASONS FOR RESTRICTIONS. IF ANY:

l THIS NONTH YR-TO-DATE CUNNULATIVE

11. HOURS IN REPORTING PERIOD 720.

6575.

123432.

L

12. NUMBER OF HOURS REACTOR WAS CRITICAL 514.4 4923.6 51 14.0

10. REACTOR RESERVE SHUTDOWN HOURS O.0 61.6 1147.7

14. HOURS GENERATOR ON-LINE 509.7 4864.2 50464.0

10. UNIT RESERVE SHUTDOWN HOURS O.O O.O O.O i

10. GROSS THERMAL ENERGY GENERATED CNWH) 1292423.

12230530.

122726229.

17. GROSS ELECTRICAL ENERGY GENERATED CNWH) 445964.

4200229.

41068450.

10. NET ELECTRICAL ENERGY GENERATED CNWH) 417611.

3953650.

38457932.

10. UNIT SERVICE FACTOR 70.8 74.0 40.9

20. UNIT AVAILABILITY FACTOR 70.8 74.0 40.9

, 21. UNIT CAPACITY FACTOR CUSING MDC NET) 74.7 77.5 39.9

22. UNIT CAPACITY FACTOR CUSING DER NET) 70.8 73.4 38.0 2D. UNIT FORCED OUTAGE RATE 29.2 5.3 54.3

24. CHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS CTYPE. DATE. AND DURATION OF EACH

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

(

)

l i

l 1

l l

l t

I

(

i.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE 9-30-88 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 NONTH:

SEPT DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWE-NET)

(NWE-NET) 1 835.

17 543.

2 834.

18

-21.

3 833.

19

-17.

4 828.

20

-16.

5 832.

21

-17.

6 843.

22

-17.

7 841.

23

-17.

8 838.

24

-17.

9 835.

25

-29.

10 832.

26 307.

11 837.

27 832.

12 837.

28 836.

13 824.

29 837.

14 835.

30 831.

15 039.

31 N/A 16 842.

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50-289 UNITSHUTDOWNS ANDPOWER AEDUCTIONS DOcKETNO.

UNIT NARGE MI-I DATE 09-30-88 SEPTEMBER 1988 comePLETEDsY C.W. Smyth REroaT a40 NTH TELErtIONE f71Il 948-8551 e.

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88-03 09/17/88 F

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1 Unit shutdown due to equipment failure on RC-P-ID Seal.

Resumed unit operations 09-26-88.

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Eaktns G - Instrus sanis S Sitrduled A l'.guapmen F4 dure Itmplanal 1 Manual f.w Facpasatiusi.nl Data B Mainsenance oi Tess 244anual Scram.

ass > Stieces to Lmcensee i

C-Ref ueling

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Evene Neema ILERI FdeiNilREG.

D Regulasiny Resaswen.se 44hlees il splass) 04611 8 Opesasos Tsaining A i s cinw I ununasmun F AJrinnessiasaw 5

d isinin I Sanw S. mise G OpesasymalIes..etisi aint ilihlws IL splamil Actually used Exhibits F & 11 NUREC 0161

l-REFUELING INFORMATION REQUEST 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 j

2.

Scheduled date for next refueling shutdown:

January 5, 1990 (8R) 3.

Scheduled date for restart following refueling: March 1,1990 (8R) 4 Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes j

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

Basic Refueling Report.

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)?

If no such review has taken place, when is it scheduled?

5.

Scheduled date(s) for submitting proposed licensing action and supporting information: October 1,1989 (estimate).

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 assembif es (a) in the core, and (b) in the spent fuel 1

storage pool:

(a) 177 (b) 360 i

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:

r The present licensed capacity is 752.

Preliminary planning to increase licensed capacity through fuel pool reracking 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:

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

j i

t 1

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r-GPU Nuclear Corporation Nuclear

,oma=

Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

October 14, 1988 C311 2142 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C.

20555

Dear Sir:

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

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report September 1988 Enclosed are two copies of the September 1988 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, g,

H. D. Hukill Vice President & Director, Tli!-1 HDH/SM0:spb cc:

W. Russell, USNRC l

R. Conte, USNRC Attachrnents 0015C l

$5A GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation g

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