ML20086L853

Monthly Operating Rept for Nov 1991 for TMI-1

ML20086L853
Person / Time
Site:	Three Mile Island
Issue date:	11/30/1991
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-91-2161, NUDOCS 9112170109
Download: ML20086L853 (7)

Text

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e GPU Nuclear Co#poration u Nuclear ren4rsgr8o Middletown, Pennfiylvania 17057 0191 717 944 7621 TELEX 84 2386 Writet's Direct Dial Number:

(717) 948-8005 December 13, 1991 C311-91-2161 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

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

Operating License No. OPR-50 Docket No. 50-289 Monthly Operating Report for November 1991 Enclosed are two copies of the November, 1991 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, ps (J.g T. G. ughton Vice President and Director, 1MI-l WCH Attachments cc: Administrator, Region 1 TMI Senior Resident Inspector b Y'1 1 1 1 0 1 h 9 9 1 1 1 3 0 PbR f. DOCK OGOOO.M 0 R FDR GPU Nuclear Corporation is a subsdiary of General Pubhc Utoties Corporation

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OPERATIONS

SUMMARY

NOVEMB1R 1991 The unit entered the month shutdown and in a drained down state on decay heat removal- for the 9R outage. The plant proceeded to heatup on 11/12/91 following completion of the 9R outage. During the heatup while trip testing '

main feedwater pump 18, an EfW actuation occurred on loss of MFW pumps. EFW was secured within 40 seconds. This event was classified as 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> reportable and is detailed in LER 91-007. The unit achieved initial criticality following the 9R outage at 1222 on 11/14/91. 100% Power was achieved on 11/17/91 with normal OTSG operating levels following chemical cleaning. The unit continued at 100% power until 11/25/91.

At 0408 on 11/25/91 a power reduction to 43% occurred as a result of an elevated and increasing CRDM stator temperature apparently initiated by debris stirred up during the backwash of the heat exchanger that cools the stator supply. A second Intermediate Closed Cooling Water (ICCW) pump was started to increase flow to the CRDM stators. The desired effect was obtained on CRDM stator mechanism 15 since temperature was observed to decrease. However, the temperature of mechanism 12 continued to rise. Reactor power was decreased to 43% power to permit insertion of the CRDM 12 control rod into the reactor core. The effected mechanism was de-energized and its fuses were pulled to prevent permanent damage to the stator windings. After troubleshooting, corrective maintenance actios cleared flow impediments as described in the report on CRDM Stator Cooling Water maintenance that follows. The unit was returned to and completed the month at 100% power.

MAJOR SAFETY R((ATED MAINTENANCE During November, the following major safety related maintenance activity was performed:

Egiuelina Activities (Reactor Vessel RC-T-ll As reported previously, the core reload was completed in October. Work on the reactor head support skirt access ports continued into November. The RV head was reinstalled and the instrumentation, power and cooling water lines were reconnected. RV work was completed with the reinsta11ation of the head cooling fans and insulation.

Make-Vo Pumn MU-P-lC Hake-up pump MU-P-1C repair werk continued into November. Pump coupling alignment and reinsta11ation of the vent and drain piping was completed and testing was performed. All testing was performed satisfactorily.

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CRDM Stator Co.g_ lina F31n During inspections performed in response to the increased CRDH stator temperatures on mechanisms 12 and 15, an 0-ring was found restricting flow at the quick-disconnect fitting in the ICCW flexible hoses connected to CRDM 12.

This mechanism was one of 18 fitted with new cooling water hoses during the 9R outage.

Further investigation revealed that flow had bypassed the filter in the cooling supply line due to the displacement of the filters in the housing.

During changeout of filters on IC-F-1B, the filter housing internals were found to be deteriorated which resulted in the installation of a replacement housing.

Subsequent to these actions, the stator temperature on CRDM 15 began to rise and inspection revealel an o-ring at its quick-disconnect fitting restricting stator cooling water flow. That o-ring was also removed, lhe origin of the two o-rings removed from the flexible hose quick-disconnect fittings is unknown and the inquiry continues.

Electrical Bus Inspections and Cleaning Electrical bus inspections and cleaning were performed on the "B","C" and "D" Inverters and the "ATB" instrumentation bus.

Q1her Maintenance Activities After plant start-up and while on line, a leak an a bonnet of liS-V-2A, a pivot shaft cover leak on EX-V-28 and an outboard seal gland plate leak on HD-P-1A were repaired by injection of Atlantic-Colt compounds.

Tha following is a summary of various refueling outage activities accomplished: 457 Valve repacks,110 welded camponent replacements, 97 Local Leak Rate Tests, and 43 Baseline and 16 D/P M0 VATS Valve Operator lests.

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OPERATING DATA REPORT DOCKET NO. 50-289 DATE De C C,mbe r 13, 1991 COMPLETFD BY W G llEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME: Ti!REE MILE ISLAND UNIT 1 NOTES:

2. REPORTING PERIOD: NOVEMBER 1991

3. LICENSED THERMAL POWER: 2568

4. NAMEPLATE RATING (GROSS MWe): 871

5. DESIGN ELECTRICAL RA" J'IG (NET MWe): 819

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWo): 856

7. KAXIMUM DEPENDABLE CAPACITY (NET MWe): 808

8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REf0RT, GIVE REASONS:

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

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTil YR-TO-DATE COMMULATIVE

21. IlOURS IN REPORTING PERIOD (!!RS ) 720.0 8016.0 151177.0

12. NUMBER OF llOURS REACTOR WAS CRITICAL (IIRS ) 395.6 6822.F 75987.0

13. REACTOR RESERVE SHUTDOWN liOURS (HLS) 0.0 -0.0 2245.6

14. HOURS GENERATOR ON-LINE (HRS) 371.1 6792.5 74912.2

15. UNIT RESERVE EMUTDOWN HOURS (HRS) 0.0 0.0 0.0

16. GROSS TIIERMAL ENERGY GENE! ATED (MWil) C51138 32209500 11120163 B7 17 GROSS ELECTRICAL ENERGY GedERATED (MWil) 2849"/6 5409267 61370171

18. NET EL CTRICAL ENERGY GENERATED (MWH) 262446 5078972 57560508

19. UNIT SERVICE FACTOR (%) 51.5 84.) 49.0

20. UNIT AVAILABILITY FACTOR (t) 51.5 84.7 49.6

21. UNIT CAPACITY FACTOR (USING MDC NET) 45.1 78.4 48.4

22. UNIT CAPACITY FACTOR (USING DER NET) 44.5 77.4 46.5

23. UNIT FORCED OUTAGE RATE (t) 0.0 0.8 44.7

24. SHUTDOWNS SCHEDULED OVLA NEXT 6 MONTilS (TYPh, DATE AND DURAT.ON OF EACH):

~

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP _ _

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._ - _ .....-._..____m...~ . . - . - . . - _ . _ . . - . ~ . _ _ _ _ _ - - _ = . _ _ - - _ _ . ~ . . _ _ . - . . . _ -

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t AVERAGE DAILY UNIT POWER LEVRI.  ;

i DOCKET Ho. 50-209  !

UNIT THI-1 '

DATE Decemtier 13, 1991 COMPLETED BY W G HEYSEK TELEPil0NE (717) 940-8191 ,

HONTH: NOVEMBER f AVERAGE DAILY POWER LEVEL I DAY DAY AVERAGE DAILY POWEH LEVEL (HWe-NET) (MWe-NET) ,

t 1 ~5 17 705 i 2 -5 18 015 3 -b 19 814 l

-5 20 -800 5 ~6 21 005 6 -5 22 805 7 -6 23 010 i 8 -9 24 015  ;

9 -8 25 403  :

10 -10 26 402 11 -20 27 802 12 -26 28 020  !

13 -33 29 614 .!

14- -44 30 007 i 15 107 31 NA )

16- 569 ,

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4 UNIT SHUTDOWNS AND PO ER REDUCTIONS DOCKET Nc. 50-239 UNIT NAME TMI-I OATE December 13, 1991.

REPORT MONTH Fo rearer 1991 COMPLETED BY W. G. Heysek .

TELE: HONE (717) 948-8191 I

method of License- 'Systan ~omponent cause & Corrm:ttwe Event Lode cme Action to No. Date Type' Durstion Peeson' ftetting Prevent securr-re (Rours) cown Report #

Reactor' *1* *g*

y 349 C NA NA FA NA Continued refueling outage which coemenced on 91- 11/01/91 S 09/27/91. l 04 A NA NA NA 91- 11/05/91 F 50 MA liteduced repairs topower to approximately the control rod drive50s to perfore motor l 05 ,

l cooling system.

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3 4 1 2 Exhibit G - Instructions for F Forced reason Method 1-Manue; preceration of Data Entry Sh-ets S Scheduled A-Equfpment Failure (Explain) for Licemee Event Report (LIR) 5-8taintenarre or Te<t 2-#srual Serse 3 Automatic Scram Flic (wuREG n161)

C-Refueling D-Regulatory Restriction 4-Cther (Exz:lein)

E-operator Training & Licenst.w Eneminaticn 5 Emhibit ! sane source F- Admin (Strative 6 Actuelty used ethibits F & II WLWEG 0161 C-Operational Error (Explain)

E-Other (Emplain) f 6

. - -. ~ - - --- - . ~ - - - . .. .

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, ,, .* i fi[G[1J11L1!([0RMA110N RE00E11

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 amen 6 ment? 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)7 If no such review has taken place, when is it scheduled?

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

Nor,e planned.

6. Impo, Tant licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methoa's, significant changes in fuel design, new optrating procedures:

GPU Nuclear has installed 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 possible. t

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 licent.ed spent fuel pool storage capacity and the size of any t

increase in licensed storage capacity that has been requested or is

planned, in number of fuel assemblies

l The present licensed capacity is 752. Planning to increase licensed capacity through fuel pool reracking is in progress.

9. The projected date of the last refueling that can be discharged to the l spent fuel pool assuming the present licensed capacity:

l l The 9R (1991) refueling discharge is the last which allows full core off-load capacity (177 fuel assemblies).

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