ML20024F817

Monthly Operating Rept for Nov 1990 for TMI-1

ML20024F817
Person / Time
Site:	Three Mile Island
Issue date:	11/30/1990
From:	Heysek W, Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-90-2153, NUDOCS 9012210160
Download: ML20024F817 (6)

Text

- - - _ _ _ _ _ _ _ _

s GPU Nuclear Corporation P

D Wuclear

ers:reo o

Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

Decerher 14, 1990 C311-9v-2153 U.

S.

Nuclear Regulatory Commission Attnt Document Control Desk Washington, D.C.

20555 Gentlement

Subject:

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

Operating License No. DPR-50 Docket No. 50-289 Honthly Operating Report November 1990 Enclosed are two copies of the November, 1950 Monthly Operating Report for Three Mile Ialand Nuclear Station, Unit 1.

Sincerely, p

kill Vice President & Director, TMI-1 HDH/WGH1 cc Administrator, Region I TMI Sc.tior Resident Inspector Attachmente I

9012210160 901130 PDR ADOCK 05000289 R

PDR Y

0W3

OPERATIONS

SUMMARY

NOVEMBER 1990 The unit entered the month operating at -95% power producing -820 MWe gross electrical generation.

The unit continued at this power level until November 28th, when a power reduction was commenced as a result of a degrading low pressure feedwater heater tube leak. Plant power was reduced to 75t.

The plant closed the month operating at 75% producing 600 MWe.

The "B" high pressure and low pressurs feed water heater strings were isola ed to support repairs to the "10B" low pressure feedwater heater.

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

Control Buildina chiller "A"

(AH-C-4A)

The Control Du11 ding "A"

Chiller (AH-C-4A) work performed during November included both the monthly and annual inspection activities.

The required preventative and minor corrective ma;.r.tnnance items were completed.

A Hot Gas Bypass Valve Kit was instclied as a modification to eliminate short cycling of the chillers during low-load operation.

The modification was made on the recommendation of the equipment vendor.

The chiller was run at low-load conditions to check the operation of the completed. Hot Gas Bypass Valve installation and satisfactory results were achieved.

2

=-.

M OPERATING DATA REPORT

7

+

DOCKET NO.

'50-289 r

DATE 11-30 Sh COMPLETED BY-W.G. Heysek TELEPHONE W)]8-8191 OPERATING STATUS

l. NOTES

'l

.!!.c'U N I T N A M E :

THREE MILE ISLAND UNIT-1 l'

l l2.IREPORTING PERIOD:

NOVEt1BER -,1990.

I I

3. LICENSED 1HERMAL POWER (MUT):

2568. I I

s4.' NAMEPLATE' RATING (GROSS MWE):

871 I

--I

.5.

DESIGN ELECTRICAL-RATING (NET MWE):

819. 1

-1

6. NAXIMUM2 DEPENDABLE CAPACITY (GROSS MWE):

85G. I I

.7.

MAXIMUM DEPENDADLE CAPACITY'(NET MWE):

808. I I

i

-1 l

O.

2F CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT,._GIVE REASONS:

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET f1WE )

LIOJREASONS-FOR RESTRICTIONS,.IF ANY:

L i :.9 THIS MONTH YR-TO-DATE 'CUMMULATIVE h 11'.) HOURS IN REPORTING PERIOD

-720.

8016.

142417.

T12.lNUMBERiOF HOURS REACTOR.WAS CRITICAL

- 720.0 6421.6 68420.2.

.113L'REACTORLRESERVE SHUTDOWN / HOURS.

O.O 242.8 2245.6-

, L14.:;iHOURS - GENERATOR. ON-LINE 720.O

'6379.6 67375.'7

!;10WUNIT RESERVE SHUTDOWN-HOURS-

O. 0 --

>0.0 0.0

~

fl6).a. GROSS THERMAL-ENERGY GENERATED-(MWH).

1721998.-

15142982.

164714877;

't iLit7f GROSS El.ECTRICAL ENERGY: GENERATED (MlJH )

57896~1'.

5059535.

55366204.

g 9 8. - NET / ELECTRICALi ENERGY GENERATED (MWH)-

545254.

4743349.

51929838.

Q 119.juNIT, SERVICE. FACTOR 5100.O~

79.6 47.3 ii 20.' UNIT AVAILABILITY FACTOR:

100.0 79.6

.47.3

'21.SUNIT' CAPACITY FACTOR-(USING'MDC NET) 93.7 73.2 46.5c

,l22M UNIT CAPACITY? FACTOR: (USING DER' NET) 92.5-72.3

-44.5/

23..UNITiFORCED 00TAGE. RATE-

-0.0 3.6 247.4 L 24.. SHUTDOWNS SCHEDULED OVER NEXT 6. MONTHS.(TYPE, DATE,-AND DURATION OF EACH

\\

t, i

h 25. IFJSHUT DOWN AT END OF REEORT PERIOD, ESTIMATED DATE OF STARTUP:>.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO..

50-289 UNIT THI-1 DATE 11-30-90 q

COMPLETED-iDY W.G. Heysek TELEPHONE 7)/-948-8191 MONTH:

NOVEMDFR DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY' POWER LEVEL (MWE-NET')

(MWE-NET) 1 768.

17 774.

l 2

'768.

18 777.

- L 13 -

770.

19 777.

, 4 '-

772.

20 773.

5 768.

21 773.

4 6-

'771.22-776.

'7.

779.

-23 775.

'8L 770.

24 774. 779.

25 771.

101 775.

.26 768.

11 775.

27'-

767.

12i

-777.

28 722.

' 13'

'777.

29 555.

't4 779.

30 555.

15.

.775.

3i N/A

. I6,

.769.

1

,1 m

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l

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e

}',

ImIT SHUTDOWNS AND POWER U2EDUCTYONS DOCKET NO.

50-289

.~

UNIT NAME

'IMI-l REPORT MONTH Nove ber 1990 DATE 12/15/90 COMPLETED BY W.

G. Heysek TEI.EPHONE (717) 948-8191 l.

Method of Licensee System :wt Cause & Corrective I

80-Date Type Duration Reasor' Shutting Event Code Code Action to (Hours) com Report #

Prevent Recurrence 3

4 6 Reactor 5 6 g

' 90-11/28 -

F 52.8 B

4 NA SD HTEXCH Power was reduced due to high level in the 05 11/30/90 LOB feedwater heater. The "B"

side high/ low pressure feedwater strings were isolated to perform repairs.

18 tubes were identified as damaged and 13 of these tubes were found to be complete breaks.

(

i 1

2 3

4 F Forced Reason Method Exhibit G - Instructions for S Scheduled A-Equim ent Failure (Explain) 1-Manust preparation of Data Entry Sheets

. B-Maintenance or Test 2-Manua? icram for Licensee Event Report (LER)

C-Refueling 3-Autormiic Scram File (NUREG-0161) 0-Regulatory Restriction 4-Other (Explain)

E-Operator Training & Licensing Examination 5 Exhibit 1 same source F-Administrative G-Operational Error (Explain) 6 Actually used exhibits F S 11 rJREG 0161 N-Other (Explain) 5

- -.. - - - -. ~ ~ _ _ - - _ - - -.

__.__m.. m,

i 4

.h.

w EEEUFLING INFORMATION REQUEST 1..Name of Facil'ityt

.Three Mile-' Island Nuclear Station, Unit'l 2.

Scheduled date for next refueling shutdown:

' october 4, 1991 (9R) 3.

Scheduled date for restart following current refueling: NA

g.,

4.-Will refueling or. resumption 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 Committee to determine whether any unroviewed 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? 6/1/91.

5.

Scheduled date(s),for submitting-proposed licensing action and supporting-

-information: None planned.,

l 6.fImportant licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed. design or performance

, r analysis methods, significant changes in fuel design, new operating procedures OPU Nuclear intends-to install four Westinghouse Lead Test Assemblies during the reload of the'TMI-1 core for cycle 9 oper-ation..' Westinghouse fuel technology.will be utilized'to the extent possible..

U l

=

7. The number of' fuel ~ assemblies (a)Jin the core, and-(b) in.the: spent fuel storage 1 pools (a).177 (b):441 it

' 8.;The.present licensed spent fuel pool storage capacity and the size of any

[>

increase in licensed l storage capacity that=has been requested.or is L

planned, in number of fuel assemblies:

l T

' ?; m The present licensed. capacity is 752.

Planning-tc' increase licensed ocapacity through fuel:pocl reracking is in progress.

1 p

9. The projected'date of the.last refuuling that can be discharged to!the.

sp'ent fuel pool assuming the present licensed crepacity:

gr'.

1991-is the.last refueling dischargo which allows full core

'off-load capacity (177 fuel assemblies).

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