ML20059J146

Monthly Operating Rept for Aug 1990 for TMI-1

ML20059J146
Person / Time
Site:	Crane
Issue date:	08/31/1990
From:	Heysek W, Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-90-2124, NUDOCS 9009190194
Download: ML20059J146 (6)

Text

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GPU Nuclear Corporation,

g f, Post Office Box 480 '

,. Route 441 South 1

"g' 17057 0191 Middletown, Pennsylvania 717 944 7621-

. TELEX 8442386..

Writer's Direct Dial Number:

Septerrber 14[1990

,C311-90-2124

[

.U. S. Nuclear. Regulatory Commission'

1

-Attna Document Control Desk Washington,.D.C.- 20555-t

,j.

Dear Sir I

'Three Mile Island Nuclear-. Station, Unit I (THIN)-

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

(

Enclosed are two copies of the August, 1990 Monthly Operating Report for Three Mile Island Nuclear Station, Unit l.

t Sincerel'y, t

Vice President:& Director,?THI-1' l

-1 4

MDH/WGH:

cca T. T. Martin, USNRC N

s F. Young,-USNRC Attachments j

0^' 000 i

^ ~ " -

9009190194 900831 PDR ADOCK 05000289 R

PDC g

GPU Nuclear Corporation is a subsidiary of General Pubkc'Utihties Corporation

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a OPERATIONS

SUMMARY

August 1990-I i

The unit entered the month operating at =96.5% power (limited by.high OTSG 1evel) producing 814 MWe gross electrical generation.

-A ATc.of -4.5'F was' input.to compensate for high OTSO level on the "B" side. The unit continued to operate.

at =96.5% power throughout the month.

MAJQR SAFETY RELATED MAINTENANCE l

During - August, the following major safety related maintenance! activity was-performed:

Screen Wash Ventilation Strainer - SW-S-2A Screen Wash Ventilation Strainer (SW-S-2A) - was. rebu lt i using L a new shaf t, j

bearings and seals.

A new drive gear unit was also installed,on the strainer

~I before the assembly was reinstalled in the housing. Post maintenance testing was i

completad satisfactorily and the unit returned to service.

Waste Evaoorator Condensate Storace Tank - WDL-T-11B A leak which developed on the recirculating piping inlet flange of the Waste Evaporator Condensate Storage Tank was repaired by replacing the existing 2"-150#

slip-on weld flange with a weld neck flange of the same size and pressure rating.

I Af ter NDE inspection found the weld antisf actory,' the-flange connection was made.

_j up and the recirculating piping returned to service.-

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OPERATING DATA' REPORT 4

' DOCKET'NO.

50-289 DATE 8-31-90 9

COMPLETED BY W.G. Heysek TELEPHONE 717-948-8191 I

i

' OPERATTNG STATUS

1. UNIT NAME:

1 NOTES-I THREE MILE ISLAND' UNIT 1 i

^

2. REPORTING PERIOD:

'l~

AUGUST-

,1990.1 1

'3.. LICENSED THERMAL POWER (MWT):.

' 2568. I l'

l4.'-NAMEPLATE RATING (GROSS MWE):

871. I 1

l

' 5. DESIGN EL ECTRICAL RATING (NET MWE):

i l

819.

l--

'6.' MAXIMUM DCPENDABLE CAPACITY-(GROSS MWE):'

.I

-l 856.- I 7.LMAXIMUM DEPENDABLE CAPACITY l(NET NWE):

l-808'. I i:

I I

O.

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

)

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)

-4

10. REAaONS FOR RESTRICTIONS, IF ANY:

i

11. HOURS IN REPORTING PERIOD THIS MONTH: YR-TO-DATE-'CUMMULATIVE 1744.

5831.-

140232;

12. NUMBER OF HOURS REACTOR WAS' CRITICAL 744.0 4236.6, E66235;27

13. REACTOR RESERVE SHUTDOWN-HOURS

14. HOURS GENERATOR ON-LINE 0.0

'242 8' 2245.6?

j 744.O'

'4194.6 65190.7 l

' 15. UNIT RESERVE SHUTDOWN HOURS

16. GROSS THERMAL ENERGY GENERATED (MWH)

. 0.0 CG Co

.O.0-

'1846495.

9998559.

159570454.

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17. GROSS ELECTRICAL ENERGY GENERATED-(MWH) 604484..

3345090.

_53651759.

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'10. NET ELECTRICAL ENERGY GENERATED (MWH)

UNIT SERVICE FACTOR 569981.--

,3129757.

-50316246.

,19.

20. UNIT AVAILABILITY FACTOR 100.O' 71.9 46.5 100.0 71.9 46.5 i

21. UNIT CAPACITY FACTOR (USING MDC NET) 94.8 66.4-45.7

22. UNIT CAPACITY FACTOR (USING-DER NET),

'93.5 65.5-

' 43.8-1

23. UNIT-FORCED OUTAGE RATE O.0-5.4 48.2 I

24.

SHUTDOWNS SCHEDULED OVER'NEXT 6 MONTHS i

(TYPE, DATE, AND DURATION!OF EACH.

25.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP :

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AVERAGE ~ DAILY. UNIT POWER LEVEL--

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. DOCKET NO.

50-299" UNIT. 31-90 TMI-1 DATE COMPLETED BY. W.G. Heysek :

1 TELEPHONE' 717-948-8191-ii

. MONTH:t AUGUST

' DAY AVERAGE DA7'"' POWER LEVEL DAY AVERAGE: DAILY: POWER' LEVEL (MWE- 'T)

'(MWE-NET) 1.

775.

17-

-761.:

+

2 774.

18

' 759.

3 770.

19 760'.

4-767.

20 776.

5 766.

- 21..

776.

,6 762.

22

- 773.

7 766. 772.

L.l 8

769.

- 24 768.'

4 9

772.

-25

-.762.

O 10 770.

26.

760.-

11 s764.

27 755.12-765.

28 755.

13 762.

29

-760.

= 14 767.

30 767.

i 15 764.

31'

768.

q

=

16 764.

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f" DOCKET Wo. 289-UNIT SHUTDOWHS AND POWER REDUCTICIIS IIIIIT EERBS TMI-1 DATE 8/31/90 REPORT 300er1T ADUUST 1990 COBrLETED BY.

W. G.'HEYSEK TERPECOBE (717)-948-8191 f'

plethod of Licensee System Component Coune & Corrective l

2 Action to 80 0 -

Date Type Duration Reeson Shutting Event Code Code (Hours)

-Down Report #

Prevent Recurrence 3

6 Reactor 5

5 6 g

j

- NONE -

b 2

3 4

1 Reason Method Exhibit G - Instructions F Forced for Properation of Date S Sciwasted A-Eqipment Felture (Explain) 1-sternset

~ Entry Sheets for Licensee 9-Maintenance or Test 2-seenuel Scram

.C-Refueling 3-Autoestic Scrom.

Event Report (LER) File (IRNEG-0161).

D-Regulatory Restriction.

4-other (Explain)

E-Operator Training & Licensing Examination F-Administrative 5 Exhibit 1 Same Source G-Operational Error (Explain) 5

- : -~

....:..-. -. - - =

REFUELING INFORMATION REQUEST

=1.

Name of Facility:

Three Nile = Island. Nuclear Station, Unit 1

2. Scheduled date for next refueling shutdowns.

October 4,11991"(9R).

3. scheduled date for-restart following current refueling: NA

4. Nill refueling or resumption of operation thereafter require a technical specification change or other license' amendment?. No. -

If answer is yesi in general,-what wil'l these be?

I If answer is no,. has the reland fuel. design and core configuration a

been reviewed by'your Plant 4 % y; Review Committee to determine j

whether any unreviewed safety.epek lons'are associated with the core--

reload (Ref.'10 CFR sec4jtn 50.59)f

.No' 1

3:

If no such review has taken place, when:is it scheduled? =6/1/91.

j

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,jnew operating; q

procedures:

-None.

-i

7. The number of fuel assemblies (a) in tho' core,Iand (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 assemblies:,

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 th6 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

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