ML20207Q381

Monthly Operating Rept for Dec 1986

ML20207Q381
Person / Time
Site:	Crane
Issue date:	12/31/1986
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
0015C, 15C, 5211-87-2006, NUDOCS 8701270246
Download: ML20207Q381 (7)

Text

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OPERATIONS SlM4ARY DECEMBER, 1986 The unit entered December with the RCS in a partially drained cold shutdown condition on "A" DHR. The 6R outage work scope was in progress. On December 7,1987, the "B" decay heat removal system was placed in service while securing "A" DHR system. On December 12, the Reactor Vessel Head was removed and placed on the storage stand. The plenum was placed in the deep end of the fuel transfer canal following fill of the deep end of the canal.

On December 28, 1986, the fuel traasfer canal was filled to refueling level.

Following leakage (approximately 2 gpm) developing on the NI cover plates, the fuel transfer canal was drained to effect repairs.

At the close of the month preparations were being made to fill the fuel transfer canal following sealing of NI cover plates.

MAJOR SAFETY RELATED MAINTENANCE During the month of December, TMI-l was at cold shutdown conditions for ref ueli ng. The following major maintenance items were performed:

OTSG Inspection and Repairs - During the month of December, OTSG work activities included the completion of Eddy Current Testing (ECT) and plugging a limited number of tubes. Three tapered plugs were welded in the "A" OTSG upper tubesheet where tubes were removed. The remaining tubes to be taken out of service in the "A" & "B" 0TSG upper tubesheet were plugged with B&W rolled plugs and the lower tubesheets were plugged with B&W ribbed mechanical plugs.

A total of 39 tubes were removed from service. All tools and materials were removed from the OTSGs, tents removed, and handhole and manway covers were reinstalled.

OTSG Eddy Current related work items are now complete.

Reactor Vessel Head Removal - The Reactor Vessel Head Removal was completed in December. Work included alignment stud installation, removal of the transfer i

tube cover plates and installation of the flood line cover plate. An exclusion area was set up and the Reactor Yessel Head removed and put on the storage stand. The indexing fixture was installed and the plenum was removed and stored in the deep end of the Fuel Transfer Canal (FTC). The FTC seal plate was installed and torqued.

Equipment was installed over the vessel for ISI inspection of the RV Nozzles. After completion of the ARIS inspection, equipment was removed and cleaned. An internal vent valve inspection was then satisfactorily performed. The FTC was then filled and after a 1.5 to 2 gpm leak was detected, it was drained for repairs. The "NI" cover plates were discovered leaking and new gaskets were installed and sealed with RTV sealant. The FTC was then being prepared for refill. The fuel shuffle is scheduled to commence on January 2,1987, h

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Reactor Coolant Pump Seal Inspections - Reactor Coolant Pump Seal Inspections were completed during December to allow filling the "RCS" for fuel shuffle work. Work items completed were as follows:

The number 1, 2 and 3 seal assemblies were inspected and replaced in RC-P-lC.

The leak-off lines were reconnected and the coupling installed. The pump / motor was aligned and the coupling spool piece was installed. RC-P-1A and RC-P-lD work included the removal of the spool pieces, couplings and the number 1, 2 and 3 seals.

The seals on RC-P-1A were inspected and replaced.

On RC-P-lD, the number 1 seal was inspected and reinstalled. The nuraber 2 and 3 seals were inspected and replaced. The leak-off lines were reconnected and the couplings reinstalled. The pump / motors were aligned and the coupling spool pieces were installed.

Local Leak Rate Testing - Local Leak Rate Testing (LLRT) continued in December. Two valves failed the test and will be repaired at a later date.

In the report submitted in December 1986, one valve was reported to be repaired at a later date. This was NS-V-35 (Containment Irolation Valve).

Repairs on this valve commenced and valve seating surfaces were reconditioned. The valve was reassembled and satisfactorily LLRT tested.

Emergency Diesel Generator EG-Y-1 A - Emergency Diesel Generator "A" was removed from service to perform annual inspection work and to replace cylinder liners. The diesel was disassembled and parts cleaned and inspected.

Reassemble work to be performed in January.

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OPERATING DATA REPORT t

DOCKET NO.

50-289 DATE 12-31-86 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551

~ OPERATING STATUS NOTES

1. UNIT NAME:

THREE MILE ISLAND UNIT 1

2. REPORTING PERIOD:

DECEMBER,1986.

3.. LICENSED THERMAL POWER (MWT) :

2535.

4. NAMEPLATE RATING (GROSS MWE) :

871.

5. DESIGN ELECTRICAL RATING (NET MWE) :

819.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :

824.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

776.

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 MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD

744, 8760.

108097.

12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 6268.7 40085.3

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 990.8 1874.1

14. HOURS GENERATOR ON-LINE 0.0 6212.3 39246.2'

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (bOGI) 0.

15576865.

94927262.

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.

5126718, 31518871.

18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.

4818263.

29469975.

19. UNIT SERVICE FACTOR 0.0 70.9 36.3

20. UNIT AVAILABILITY FACTOR 0.0 70.9 36.3 21'. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 70.9 34.9

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 6".2 33.3

23. UNIT FORCED OUTAGE RATE 0.0 4.0 60.2

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH Currentiv in a Refuelino Outage

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: March ZU, 1987

-AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289.

UNIT TMI-1 DATE 12-31-86 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 MONTH:

DECEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 0.

17 0.

2 0.

18 0.

3 0.

19 0.

4 0.

20 0.

5 0.

21 0.

6.

O.

22 0.

7 0.-

23 0.

8 0.

24 0.

9 0.

25 0.

10 0.

26 0.

11 0.

27 0,

12 0.

28 0,

13 70.

29 0.

14 0.

30 0.

15 0.

31 0.

16 0.

50-289 DOCKET NO.

UNIT SilUTDOWNS AND POWER REDPitMONS UNdT NAME 'INI-I DATE Dec ember 31. 1986 December 1986 COMPLETED BY C. W. Smyth REPORT MON 1H TELEPHONE (717) cAn_qqq1 n.

c r#

3 to cr t

Cause & Correceive g*'3 s4 Licensee 2,e E

7 No.

Daic h

3g i

jg5 Event s?

a-Acima to f'

$3 E

j 65 g Reposi *

'E 0 Prevent Recurrence 6

7 861031 S

744 C

N/A N/A N/A N/A Refueling Outage 1

2 3

4 F: l'ossed Reason:

Method:

Ex!nbit G - Instruttions S. S heduled A 1 quipment Failure (Lxplam) l-Manual for Psepasarion of Data ll-Maintenance of Test 2 Manual Scram.

Entry Sheets for IAensee C-Refueling

.l Autunutic Scram.

Event Repos ILER) FileINilREG-D Regulator > Restriction 4-Othee llipl.sm) 0161) 1 -Operator liaining & licenw I umuution 5

F. Adnumsisative f sinbit I - Same S. usse G Operai unal I noi 11Tplam n lloiher INelaini 6.

Used Exhibits F & H (Actual) 6 Actually used Exhibits F & 11 NUREC 0161

REFUELING INFORMATION REQUEST 1.

Name of Facility: Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

July 1, 1988 (7R) 3.

Scheduled date for restart following refueling:

March 20, 1987 (For current 6R Outage)

September 14, 1988 (7R) 4.

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

Yes (For 6R)

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

Conversion to 18 month fuel cycle with associated changes to Power Imbalance, Quadrant Tilt and Rod Insertion Limits.

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?

To be determined.

5.

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

submitted November 3,1986.

(For 6R) 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 pool:

(a) 177 (b) 208 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 752. There are no planned increases at this time.

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 l

core off-load capacity (177 fuel assemblies).

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.s-GPU Nuclear Corporation NggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944-7621 TELEX 84 2386 Writer's Direct Dial Number:

January 15, 1987 5211-87-2006 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 December, 1986 Enclosed please find two (2) copies of the December,1986 Monthly Operating Report for Three Mile Island Nuclear Station, Unit-1.

Si ncerely, ki 1 Vice President & Director, THI-l HDH:DVH:spb cc: Dr. T. E. Murley F. I. Young Attachments 0015C 0

GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation u

.