ML20085E295

Monthly Operating Rept for Sept 1991 for TMI-1

ML20085E295
Person / Time
Site:	Crane
Issue date:	09/30/1991
From:	Broughton T, Wells R GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-91-2125, NUDOCS 9110180147
Download: ML20085E295 (7)

Text

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OPU Nuclear Corporation Post Office Box 480 Route 441 South Middletown, Pennsylvania 170$7-0191 i

717 944-7621 i

TELEX 84 2386 rgregl Number:

i October 15, 1991 C311-91-?l25 U. 3. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

20555

Subject:

Three Mile Island Nuclear Station, Unit 1 (TMl-1)

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report September 1991 Pursuant to TM1-1 Technical Specification 6.9.1.c, attached is the September 1991 Monthly Operating Report for Three Mile Island Nuclear Station, Uni 1.

Sincerely,

/

d%d L

T. G. Broughton Vice President & Director, TM1-1 RDW:

Attachments cc:

R. Hernan - Senior Project Manager T. Martin - Regional Administrator F. Young - NRC Sr Resident inspector TMl

/

}.

9110180147 91093o I

PDR ADOCK 00000289

/

.1 R

PDR 1

GPU Nuclear Lorporanon is a subsid.ary of General F'ubhc Ubhbes Corporation

OPERATIONS

SUMMARY

-SEPTEMBER 1991 The plant entered the month operating at approximately 96% reactor power and producing =810 MWe gross electrical generation.

The Reactor Coolant Pump 1A seal leakoff flow was stable at 9.5 gpm.

The plant continued )ower operation until September 27, 1991 when the unit was shutdown for the scleduled 9R refueling outage. While activities were in progress to shutdown, the reactor tripped on high RCS pressure from 14% power during a Turbine Generator testing sequence. The heat sink protection system isolated main feed water to the OTSGs when main steam pressure decreased to <600 psig.

This caused a low steam generatcr level and resulting emergency feedwater initiation.

The imbalance between heat production and removal resulted in the reactor trip.

The event is described in further detail in LER 91-003.

The unit was cooled down and depressurized on Decay Heat Removal with the RCS partially drained at the end of the reporting period.

MAJOR SAFETY RELATED MAINTENANC[

During September, the following major Safety Related maintenance items were performed:

VENTILATION SYSTEM CHARC0AL EllTER TESTING Ventilation system charcoal filter testing was completed during the month.

The Auxiliary Building filter AH-F-28 north side filters failed the DOP test and the south side filters failed the Hallde test. The AH-F-28 charcoal filters were replaced and tested satisfactory. Auxiliary Building filter AH-F-2D north side filter passed both the Hsiide and DOP tests; however, the south side filters failed the Halide test. The south side charcoal filters were replaced and tested satisfactory.

The fuel Handling Building "ESF" filters, AH-F-14A/B were DOP and halide tested satisfactory.

MOTOR OPERATED VALVE ACTUATION TESTING (M0 VATS)

MOVATS work items completed prior to the outage included the following:

(1) MU-V-16C - Baseline and Differential Pressure (2) MU-V-16A - Differential Pressure 16LCLEAR SERVICL QL*D COOLING WATER (NSCCW) PUMP NS-P-18 NSCCW Pump NS-P-1B 'a removed from service due to high bearing temperature.

The pump was disasselated and new thrust and radial bearings were installed.

The pump was reassembled and in-service testing is scheduled for October 1991.

2

9R REFUELING ACTIVITIES The following is a summary of items accomplished since the start of the outage:

Make up pump HU-P-lO failed to start during ES testing. When the pump was started in manual, the motor tripped. Upon investigation, the pump rotating assembly was found to be seized and is scheduled to be repaired this month.

Preparations were made in the fuel Transfer Canal and on the reactor head service structure for reactor head lift.

The 'A' and 'B' OTSG upper manway and handhole covers were removed to e

support leak testing and tube ISI examination.

Scheduled Local Leak Rate testing was begun.

Scheduled MOVATS baseline and AP testing was begun, Completed 10 of 452 valve repacks.

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i OPERATING DATA REPORY DOCKET No.

50-289 DATE October 15, 1991_

COMPLETED BY R D WELLS OPERATING STATUS TELEPHONE (717) 948-8693 i

a. UNIT NAME:

THREE MILE ISLAND UNIT 1 NOTES:

2. REPORTING PERIOD:

SEPTEMBER 1991

3. LICENSED THERMAL POWER:

2568

4. NAMEPLATE RATING (GROSS MWo):

871

5. DESIGN ELECTRICAL RATING (NET MWe):

819

6. MAXIMUM DEPENDABLE CAPACITY (GROSS HWe):

856

7. MAXIMUM DEPENDABLE CAPACITY (NET MWo):

808

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

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

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS HONTH YR-TO-DATE CUMMULATIVE

11. IlOURS IN REPORTING PERIOD (IIRS )

720.0 6551.0 149712.0

13. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 642.6 6427.1 75591.3

13. REACTOR RESERVE SHUTDOWN HOURS (IIRS) 0.0

-0.0 2245.6

14. HOURS GCNEMATOR ON-LINE (llRS )

642.4 6421.5 74541.2

15. UNIT RESERVE SHUTDOWN HOUR 9 (HRS) 0.0 0.0 00

16. GROSS THERMAL ENERGY GENERATED (MWil) 1566685 14694918 181165249

17. GROSS ELECTRICAL ENERGY GENERATED (HWH) 528130 5124291 61085195

18. NET ELECTRICAL ENERGY GENERATED (HWH) 496991 4819968 57309388

39. UNIT SERVICE FACTOR

(%)

89.2 98.0 49.8

20. UNIT AVAILABILITY IWCTOR

(%)

89.2 98.0 49.8 81.. UNIT CAPACITY FACTOR (U$ING MDC NET) 85.4 91.1 48.7

88. UNIT CAPACITY FACTOR (USING DER NET) 84.3 89.8 46.7

23. UNIT FORCED OUTAGE RATE

(%)

0.0 0.8 14.9

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

~

'~~~

85. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

11/13/9]

4

~

a.

AVZRAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT TMI-1 DATE October 15, 1991 COMPLETED BY R D WELLS TELEPHONE (717) 948-8693 HONTH:

SEPTEM8ER DAY-

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

(MWe-NET) 1 785 17 753 2

786 18 766 3

780 19 777 4

773 20 788 5

772 21 791 6

778 22 792 7

775 23 785 8

772 24 785 9

771 25 782 10 770 26 786 11 766 27 566 12 781 28

~28 13 777-29

-13 14 770 30

-6 15 768 31 NA 16 758 5

,. -.. -., - ~..

. UNIT SHUTDOWNS'AND' POWER REDUCTIONS DOCKET NO.

50-289

' ~ ~

UNIT NAME TMI-1 REPORT MONTH September 1991-DATE ' October 15,11991 -

COMPLETED.BY R. D. Wells TELEPHONE -(717) 948-8693 Method of Licensee' System :omponent Cause & Corrective No.

Date Type' Duration Reason' Shutting.

Event Code Code

' Action to (Muurs)

Down Report #

Prevent Recurrtr*e Reactor' 91-09/27/91 S

79.6 C

3 LER 91-03 During the shutdown'to start tte refueling i

04 outage,' after the generator had been taken i

off-line and %hile performing the turbine overspeed test, the reactor tripped from 14%

power due to'high RCS pressure. The event resulted from procedural inadequacics involving the test.

-j i

i i

'I

.I t

t

b l

1 2

3 4

F Forced Reason Method Exhibit C - Instructions for S Scheduled A-Equipment failure (Explain) 1-ftenual preparation of Data Entry Fheets 5-Maintenance or Test' 2-Manual Scram fy Licensee Event Report (LER)

C-Refueling 3-Autcoatic scram File (NUREG-0161) 0-Regulatory Restriction 4-Other (Explain)

E-operator Training & Licensing Examir-tion 5 Exhibit 1 same source F-Administrative G-Operational Error (Esplain)'

6 Actually used exhibits F & II NUREG 0161 N-Other (Explain) 6~

REFUELING INFORMATION REQUEST 1.

Name of Facility:

Three_ Mile Island Nuclear Station, Unit 1 2,

Scheduled date for next refueling shutdown:

NA 3.

Scheduled date for restart followiry current refueling: November 13, 1991 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 quest'ons are associated with the core reload (Ref. 10 CFR Section 50.59)? Yes If no such review has taken place, when 'is it scheduled?

5.

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

None planned.

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:

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

Westinghouse fuel technology will be utilized to the extent l

possible.

7.

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

(a) 177 (b) 3E 8.

The present licensed spent fuei

' v.orage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

t The present licensed capacity is 752. Planning to increase licensed l

capacity through fuel pool reracking 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).

,