ML20012C149

Monthly Operating Rept for Feb 1990 for TMI-1.W/900314 Ltr

ML20012C149
Person / Time
Site:	Three Mile Island
Issue date:	02/28/1990
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-90-2033, NUDOCS 9003200189
Download: ML20012C149 (7)

Text

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GPU Nuclear Corporation Nuclear.  :::,orrs:reo Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 l-Writer's Direct Dlal Number: ,

March 14, 1990 C311-90-2033 U. S. Nuclear Regulatory nr=niacion Attn: Document Control Desk Washington, D.C. 20555 ,

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Dear Sir:

'three Mile Island Nuclear Station, Unit I ('IMI-1)

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report February 1990 Enclosed are two copies of the February 1990 Monthly Operating Report for

'Ihree Mile Island Nuclear Station,. Unit 1.

Sincerely, i

. . 1 Vice President & Director, 'IMI-1 HDH/WGH:2033 l

I oc: T. T. Martin, USNRC F. Young, USNRC Attachments t

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GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation

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OPERATICES SLPMARY FEBRUARY 1990

'Ihe unit entered the month in a refueling shutdown coniiticn with reactor refueling in p u,yass. Fuel loading was coupleted on 2/6/90. N plant

h. ar xml a heatup followirg the 8R outage on 2/26/90 and achieved hot shutdown on 2/27/90. N unit ended the nanth at hot shutdown with modification testing in r ujiass.

MILTOR SAFEIY REIATED MAINTENANCE Major safety related maintenance activities performed during the month of February include:

Control Rod Drive Mechanisms (CRIM)

As reported in January, CRIE repairs continued into February, h work included nozzle flange face gasket and split nut ring replacement. Repairs are ocuplete.

Reactor Vessel (RC-T-1)

Personnel ocupleted preventative maintenance activities in preparation for head installation. h se activities included head o-ring groove cleaning and inspection, installation of new o-rirgs, reactor vessel stud, nut and washer cleaning, NDE inspection of twenty studs, and stud lubrication.

h modification installirg permanent lifting pendants to the reactor vessel head was ocupleted with the head on the head stand.

Upon ocmpletirg fuel movement activities, the vessel raaaambly process was begun (plenum installation, canal drain down and decuduunination, and head installation). Following installation of the head superstructure cable i platforms and rod position indicator (PI) tubes, the PI tube cable and l thtu.uuxiuple connections were made. Recoupling of the QMs and ASPRs was ccmpleted later.

During an inspection of the reactor head dame for boron, the inspectors found baron deposits located within the-head superstructure. h deposits were attributed to leak.ing cas as di_-ai in the January report. Personnel removed several deposits by working through an access hole. Visual reinspection and ultrasonic testing verified that there was no deterioration in the area of these deposits.

Once 'Ihrotnh Steam Generator (RC-H-1 A/B)

Inspectors empleted the inservice inspection program eddy current testirg of tubes in both CTISGs during the final days of January. Evaluation of data obtained as a result of the inspection led to the determination that 5 tubes in

, the A OTSG ard 3 tubes in the B orSG should be plugged. On completion of the l plugging, the OPSGs were closed out and prepared for power operation.

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Prammirizer Relief Valve

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'Ibe Pilot Operated Relief Valve (PGN) was removed frun the pressurizer and replaced with a testad spare. 'Ihe valve whicts was removed was sent to Wyle laboratories for testing and inspection.

Miar=11arw=1= Work I&m==

Following is a sunnary/ status of various other work itens being performed during the BR outage:

1. Valve rapacks - 409 of 427

2. Valve replacanents - 174 of 175

3. Large valve seat repairs - 8 of 13 sdadaled - 5 nonscheduled

4. Incal leak rate tests - 115 of 115

5. MWATS valve operator tests - 33 of 52

6. Conex wire inspections - 53 of 53

7. Molded case breaker tests - 145 of 145,

8. 4160V breaker tests - 8 of 8 '

9. 480V breaker tests - 44 of 44

10. Tedi Spec smhr seal replacements - 37 of 37

11. %cti Spec smhr functional tests - 20 of 20

12. Non-Tecti Spec aruihr functional tests - 38 of 38 previously reported as 154 due to transposition of digits.

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MONTH: FEDRUARY. l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-

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p-E UNIT SHUTDOWNS ANDF0WER REDUCDONS - Tyg _

DATE 02/28/90 -

FEBRUARY 1990*

toBWE.ETED W C. W. Smyth

- REFORT BBONDE m nrn gan-nssi e e Ibec

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uY Caisse & C.*,edeve Adminen N. . .

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thit shutdown for Refueling Outage.

02/01/90 S 672 C 1 Outage unmacx3 01/05/90. 'Ibtal 90-01 i number of outage hours as of this

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report period is 1298.87.

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2. Manual Scram. Entry Sheets los Leicence i C Refueling 3 Awooniasse S.eam. Evens Repose ILERI FdeINtfREG-D Regulaeus) Resessee.in 4 Oohee il splawil 01611' I Orc asin Tr.iining & I stevisc I sanuarassim I1Adnunnesaseve $

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Actually used Exhibits F & H NUREG 0161

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REIELING INPEROLTICH REQUEETF

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1. Name of Facility: 'Ihree Mile Islard Nuclear Statim, Unit 1

2. S&eduled date for next refueling shutdown: OcMhar 4,1991 (9R)

3. Scheduled date for restart following current refueling: March 3,1990 (8R)

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4. Will refueling or resunption 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 Ocunittee to determine whether any unreviewed safety questions are aa w iated with the core reload (Ref. 10 CFR Section 50.59)? No.

If no such review has taken place, when is it scheduled?

'Ihe review was ocupleted on February 23,1990.

5. Scheduled date(s) for subnitting reoposed licensing action and supporting information: None planned.

6. Inportant licensing considerations anwiated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant charges in fuel design, new operating s ucedures: None.

7. h number of fuel assemblies (a) _ in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 441

8. 'Ibe present licensed spent fuel pool.sb age capacity and the size of any E increase in licensed storage capacity that has been requested or is l planned, in number of fuel assemblies:

h present licensed capacity is 752. Planning to increase licensed capacity through fuel pool reracking is in r w.

9. h projected date of the last refueling that can be dis &arged to the

! spent fuel pool a===ing the present licensod capacity:

1991 is the last refueling discharge which allows full core off-load capacity (177 fuel assenblies) .

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