ML20115B748

Monthly Operating Rept for Sept 1992 for TMI-1

ML20115B748
Person / Time
Site:	Crane
Issue date:	09/30/1992
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-92-2137, NUDOCS 9210160229
Download: ML20115B748 (8)

Text

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GPU Nuclear Corporation

}i NQgIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-8005 October 13, 1992 C311-92-2137 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 September 1992 Enclosed are two copies of the September 1992 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, 37

[A T. G. Bro hton Vice President and Director, TMI-1 WGH Attachments cc: Administrator, Regic I

TMI Senior Resident inspector 92iO'150229'920930

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OPERATIONS

SUMMARY

SEPTEMBER 1992 The plant entered the month operating at 50% power producing 372 MWe.

The power reduction initiated on August 31 was required to permit main condenser tube and water box cleaning.

In late August, fouling caused by Asiatic clams cMsed higher than normal main condenser inlet water box pressure.

Upon completion of the cleaning effort, the unit returned to full power operation on September 6.

Power remained at that level until September 18, when an automatic shutdown occurreu. The A" side circulating water pumps tripped, causing a subsequent reduction in main condenser vacuum and resulted in a-turbine generator and reactor trip. The circulating water pump trip occurred while personnel were isolating the condenser circulating water inlet water box high pressure trips. The action was taken in an effort to reduce the risk of an unnecessary shutdown caused by gradual increased fouling of the condenser tube sheets by Asiatic clam. shells.

The plant returned to full power operation on September 21.

During the brief shutdown period, the condenser tube sheets were cleaned and maintenance personnel took advantage of plant conditions to perform tasks that can be completed only while the plant is shutdown.

MAJOR SAFETY RELATED MAINTENANCE During September, the followir.g major safety related maintenance was l

performed:

1 Emeraency Diesel Generators EG-Y-1 A and B Emergency Diesel Generator EG-Y-1A was removed from service to perform the scheduled annual inspection.

Various preventative and corrective maintenance tasks were completed as well as a modification replacing the frequency transducer and the frequency, amp, and kilovolt meters.

The synchronizing l

rystem volt meter and synchronizing generator volt meters were also replaced.

All inspections / maintenance tasks were completed as scheduled and upon satisfactory completion of the two hour test run, EG-Y-1A was returned to service.

The scheduled annual inspection of EG-Y-1B was also accomplished during the month.

The maintenance tasks and meter replacement modification were performed as scheduled and EG-Y-1B was returned to service upon the l

satisfactory completion of the two hour test run.

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Off-line Safety Related Maintenance Activities The maintenance items completed while the plant was off-line following the circulating water pump / main condenser inlet water box high pressure t-ip are listed:

1) The trip function leads for the main condenser inlet water box high pressure trip (CW-PS-740A/B/C and CW-PS-741A/B/C) were lifted.

2) The Main Condenser water boxes were opened to permit cleaning of the tubesheets and tubes.

A tapered plug in the condenser's "A" side was replaced with a mechanical expansion type plug.

3) Maintenance on the "A" Main Feedwater Pump incluced adjustment of the limit switch turbine turning gear, replacement of the turbine low vacuum trip switch and the lube oil transfer valve. The turbine lube oil filter elements were also c. leaned.

4) Lug connectors associated with CRD Group 5 phase "A",

phase "8" and the "A" bus cable and a cable associated with CRD Group 7 in the interface cabinet were modified to correct " Hot Spot" conditions.

5) Valve maintenance included adjustment of the torque switch setting on the RC-V-1 limitorque operator, replacement of IA-V-1091, repair of a 4

tua. to pipe fitting leak on RC-V-1037.

6) A leaking fitting was identified and repaired on a snubber on RC-P-18.

7) A Ray-Chem connection on NI-12 was repaired.

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c OPERATING DATA REPORT DOCKET NO.

50 289 DATE.

October 13, 1992-COMPLETED BY W G HEYSEK-OPERhTING STATUS TELEPHONE (717) 948 8191--

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 l NOTES:

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2. REPORTING PERIOD:

SEPTEMBER 1992 l

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3. LICENSED THERM 71 POWER:

2568 ]

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NAMEPLATE RATING (GROSS MWo):

871 l l.

5. DESIGN ELECTRICAL RATING (NET MWe):

.819 j l'

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWo):

834 l

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7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):

786 l

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IF CHANGES OCCUR IN (ITEMS 3-7) SINCE T AST PEPORT, GIVE REASONb -

-9.

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

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR.TO.DATE CUMMULATIVE 11, HOURS IN REPORTING PERIOD (HRS) 720.0 6575,0 158496.0

'12. NUMBER OF' HOURS REACTOR WAS CRITICAL (HRS) 661.8-6536.8 87767.8

13. REACTOR RESERVE SHUTDOWN HOURS.

(HRS) 38.2 38.'2 2283.8

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14. HOURS GENERATOR ON.LINE (HRS) 679.0 6534.0

-82190.2

15. UNIT RESERVE. SHUTDOWN HOURS.

(HRS) 0.0 0.0 0.0

16. GROSS THERMAL-ENERGY GENERATED (MWH) 1591955-

-166073a9-200476404

17. GROSS' ELECTRICAL ENERGY GENERATED (MWH) 517272' 5489451

'67483710-

19. NETEELECTRICAL ENERGY GENERATED (MWH).

484577 5179107 63336432J

19. UNIT-SERVICE _ FACTOR

(%)

94J3 95.4

.51.9

20. UNIT AVAILABILITY FACTOR

(%)

94.3 99.4 51.9-

21. UNIT CAPACITY FACTOR (USING MDC NET).

85.6 100.2

50.8--

22. UNIT CAPACITY FACTOR (USING DER NET)-

.82.2-96.2 48.8.

'23. UNIT FORCED OUTAGE FUkTIL

(%)

5.7 0'6 42.5 UNIT FORCED OUTAGE. HOURS (HRS) 41,0 41.0 60689~.7.

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

25. IF SHUT.DOWN AT END OF REPORT PERIOD, ESTIMATF0 DATE OF STARTUP:

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AVERACE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNIT THI-1 DATE October 13, 1992 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:

SEPTEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-NET)

(MWe-NET) 1 334 17 776 2

340 18 b55 3

378 19

-39 4

344 20 160 5

688 21 782 6

791 22 787 7

788 23 804 8

783 24 809 9

783 25 807 10 776 26 800 11 789 27 793 12 797 28 799 13 795 29 804 14 793 30 809 15 788 31 NA 16 779 5

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c UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-289 UNIT NAME TMI-l REPORT MONTH September 1992 DATE October 13, 1997-COMPLETED BY W. G. Heysek' TELEPHONE (717) 948-8191 j..

1 Method of Licensee System :osponent '

Cause & Corrective

.Date Type' Duration Reas W Shutting Event Code Code Action to No.

i (Hours)

Down Report #

Prevent Recurrence l

Reactor'

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92-8/31/92 F

0 B

4 NONE HF HTEXCH Condenser macrofouling (Asiatic clams) led to 01 a 50s power reduction fot nearly five days beginning 8/31/92. to accomplish tube and

water box cleaning. The subsequent preventative actions include installation of smaller scesh screens in the cooling water system and increased frequency of " clam kill" chemistry treatment of the system. The unit returned to full power operation on 9/6/92.

92-9/18/92 F

41.0 B

3 92-002 HF INSTRU While isolating the condenser circulating 02 water inlet water box high pressure trips, they actuated, causing three of six circulating water pumps to trip. The resulting low vacuum condition caused an immediate turbine / reactor trip.

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4 F forced

!!esson

' Method Exhibit G - Instructions for

't S Schedated A-Equipment Failure (Explain) 1-Manual preparation of Data Entry Sheets.

8-Maintenance or Test.

2-panuel Scram for Licensee Event Report (LER)

C-Refueling 3-Automatic Scram File (NUREG-0161) 0-Regulatory Restriction 4-Other (Emplain)

E-Operator Training & Licensing Examination 5 Exhibit 1 same source F-Administrative

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G-operational Error (Explain)-

6 Actually used exhibits F & 11 MUREG 0161 '

i N-Other (Explain)

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9 REFUEllNG 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? NA 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)?

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:

B&W Fuel Company (BWFC) and GPUN are now performing the fuel cycle design for cycle 10, which is scheduled for startup in October 1993.

This design incorporates reload fuel that contains urania-gadolinia, use of this type of fuel will require changes to the plant Technical Specifications. These changes will need to be supported by approval of BWFC topical reports on reload design methods revisions that account for the Gd effects in the analyses; i.e., BAW-101BO, Rev 1, "NEM0 - Nodal Expansion Method Optimized" and BAW-0184P, "GDTACO -

Urania Gadolinia Fuel pin Thermal Analysis Code." To ensure that no delays occur to reload analyses, fuel manufacturing and plant startup schedules, approval of these topicals is needed by April 1,1993.

7.

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

(a) 177 (b) 521 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 capacity is 1496.

Reracking of spent fuel pool

'A' to attain the licensed capacity is in progress.

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The projected date of thd last refueling that can be discharged t'o the;

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spentfuell pool _ assuming-thepresent_ licensed-capacity:

The 9R (1991) refueling discharge was the last to allow full core -

off-load capacity (177 fuel-assemblies). Upon completion of the _

reracking project, full core.off-load is assured through.the end of the current operating. license and beyond.

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