ML20058Q162

Monthly Operating Rept for Jul 1990 for TMI-1

ML20058Q162
Person / Time
Site:	Three Mile Island
Issue date:	07/31/1990
From:	Heysek W, Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-90-2111, NUDOCS 9008210125
Download: ML20058Q162 (6)

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..i GPU Nuclear Corporation i

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Middletown Pannsylvania 17057

.717 944-7621

-TELEX 84 2386 l

Writer"s Direct Dial Numberi

-f-t August 14,1990 L i

C311-90-2111-ll

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. U. S. Nuclear Regulatory Conrnission Attna Document Control Desk

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. Washington / D.C.

20555 0:ar Sir:

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

Operating License No. DPR-50 Docket No. 50-289-Monthly Operating Report July 1990

?

Enclosed are two copies of the July, 1990 Monthly Operating Report for Three Mlle Island Nuclear Station, Unit 1.

s Sincerely, e

H 6

1 Vice President.& Director, THI F I

HDH/WGH cca T. T. Martin, USNRC F. Young, USNRC Attachments 9008210125 900731 PDR ADOCK 03000289 R

PDC

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GPU Nuclear Corporation is a subsidiary of the General Pubhc U'.ihties Corporation 000:3 III

OPERATIONS

SUMMARY

JULY 1990 T'ne unit entered the month operating at -93.2% power (limited by high OTSG level) producing -790 MWe gross electrical generation.

A ATc of -4,5'F was input to compensate for the high OTSG level on - the "B"

side, on July 2,

1990 an inadvertent ESAS actuation occurred during ESAS testing.

"B" side components actuated and were subsequently secured.

Notification was made under 10 CFR 50.72.

Based on testing performed in June, reactor power was raised on July 20th until the B" side OTs0 level reached 96%.

Final reactor power was 97%.

The unit closed the month operating at 96.5% power producing -814 MWe gross

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electrical generation.

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MAJOR SAFETY RELATED MAINTENANCE i

i During July, the following major safety related maintenance _ activity was performed:

car.dox CO Fire sunoressi n system 2

The relay room Cardox CO fire suppression system compr.=ssor (FS-P-7) and motor 2

were replaced during the month.

Replacement in lieu'of repair was performed because of the obsolete design of the original equipment.

Post maintenance testing was completed satisfactorily.

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yt m ,c, y ,pr: ,8 3 {l - TW ~ ' 'f, v a g g 7 pn yy Q,WJyH }l 3; s c y g g%.. -=" ^ Y -' OPERATING' DATA 'REPORTJ M. d

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y e m .s; 4 .s w i =Q D, "f I 'g '. 4 g ? DOCKET;NO.' E50-289L jA A - + i h~'?g.' L' 'DATEi 7-31-90 % 3 T COMPLETEDi BY" W.G. Heysek - TELEPHONE (717) 948-8191f 4 3 I y, e t ~ T f U, 7b tOPERATING-STATUSI

• i

-I1 NOTES ~ IL *

1 '. L U N I T 3 N A M E :

LTHREE" MILE ISLAND-UNIT.L1 'l. Lt.

2 '... REPORTING QERIOD:

' JULY.- 1990.;I .I ^ Sf3.fLICENSED THERt1AL POWER (f1WT):- 2568; -ll l' 14.o NIMEPL ATE RATING e ( GROSS t t1WE ) :' '871.' I

lr

.:Ic fG;JDESIGN_ELECTRICALTRATING'(NET lMWE) ~

' 8 1 9.. 1. al-j&.? MAXINUM' DEPENDABLE CAPACITY (GROSS t1WE) a

856. I

. lj e $;p..' MAXIMUM = DEPENDABLE' CAPACITYd (NET' MWE) : 7 808. I 11 -/ r

i-et W m

l-s e ,A 3p M IF CHANGES OCCUR 'INl(ITEMS 3-7) SINCE AST REPORT dGIVE REASONS: J~ 3 g m = C6 POWER LEVEL 'TO WHICH RESTRICTED;~ IF ANY. (NET t1WE) 10; REASONS?FOR RESTRICTIONS,~IF ANY: - + 'THIS MONTHi YR-TO-DATE. CUMt1ULATIVEf ]

i. I '1 ; HOURS IN: REPORTING PERIOD.

2744;; 5087. (139488. --12..f NUMBER OF'HOURSD REACTOR WAS' CRITICAL- '744.O' 1349216' 65491.2 "7 /13..' REACTOR RESERVE SHUTDOWN HOURS LO.O/ 24248: f2245.6s 1 14W HOURSLGENERATOR DN-LINE 1744.O.; 13450.6: 64446.7A b- ~ 15.1 UNIT-RESERVE: SHUTDOWN: HOURS O;Oi 'O.O' - O.Oj <

10. GROSS 0 THERMAL ENERGY. GENERATED-(MWH)'

~1809516.. O'1'52065i 4157723959.* W17. J GROSS ELECTRICAL : ENERGY GENERATED (t1WH) 593079. =2740606l. 1530.47275.- c18h NET ELECTRICAL 1 ENERGYJ GENERATED - (t1WH)i ' 558573.cy 2559776'.- ; 1497462652 /190 UNIT SERVICE FACTOR ~ ' l OO. O f ' 67. 8 ' ' H 4612 J d 2 L20./ UNIT. AVAILABILITY FACTORI -100.0- '67.8 7 1 f46.2.~ d [21.1 UNIT;CAPACITYEFACTOR1(USING'MDC1 NET) 2 6213 45i5 /9229. + ; ta

22.; UNIT

CAPACsTYLFACTOR:(USING'DERnNET):

,91.7 61;41 - 4 3 '. 5, J 23i:f UNIL FORCED 10UTAGE RATE 10.0 161 48.5l J ? r 724.1 SHUTDOWNS ? SCHEDULED 'OVER MEXT 6 f10' NTH'Sl (TYPE,4 DATE, l AND DURATIONIOF EACH I Y ~ i s s y ' 1 s h5);IFSHUTDOWN'ATEND.0FREPORTPERIOD,-ESTIMATEDDATE(OF.STARTUP: i f. 1 i .] m }E,, ":3; ' ^ s t .[. y N w 1 s w - +. ~. UNIT SEUTDOWNS AND POWER REDUCTIONS DOCRET No. 50-289 UNIT M TMI-1 DETE 07-31-90 ^ REPORT HONTE JULY 1990 00gE'IATED BY W.~G. HEYSEK-TELEPEONE (717) 948-8191 i ? I 4 Method of Licensee system Component . Camse & Corrective l 2 No-Date Type Duration Reason Shutting Event Code . Code Action to (Nours) Doun Report # - Prevent Recurrence Reector 5 6 g - NONE - .l i 4 l i i r 1 2 -3 4 F Forced Reeson Method Exhibit G - Instructions ~ 'S Scheduled - A-Eqipment Failure (Explain)

1-Manuel for Properation of Data 0-Meintenance or Test 2-Manuel Scram Entry sheets.for Licensee C-Refueling

3-Automatic Scram Event Reiport (LER) File (NUREG-0161) j 3-Regulatory kestriction' 4-Other (Explain)

- E-Operator Training & Licersing Examinetton F-Administrative. 5 Exhibit 1 same Source G-Operationet Error (Explain) N-Other (Explain). 6 Actuelty used Exhibits F & II WUREG 0161 L i-1 ~. . -. - ~. .c. *:e* e REFUELING INFORMATION REQUEST

1. Name of Facility:

Three Nile Island Nuclear Station, Unit 1 l 2.. scheduled date for next refueling shutdown: October 4, 1991 (9R)

3. Scheduled date for restart following current refueling: NA

4. Nill refueling or resumption of operation thereafter require a technical j

specification change or other license amendment?- No. d If answer is yes, in general, what will these be? If answer is no, has the reload fuel design:and coro configuration been reviewed by your Plant safety Review Committee to determine. whether any unreviewed safety questions are associated with the core i reload (Ref. 10 CFR Section 50.59)? No. If no such review has taken place, when is it scheduled? 6/1/91.

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 i analysis methods, significant changes in fuel design, new operating l procedures None.

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pools (a) 177 (b) 441

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 assemblios:

~ The present licensed capacity is 752. Planning to increas's licensed capacity through fuel pool raracking is in process. 1 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). 6 -