ML20247G265

Monthly Operating Rept for Aug 1989 for TMI Nuclear Station, Unit 1

ML20247G265
Person / Time
Site:	Crane
Issue date:	08/31/1989
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-89-2108, NUDOCS 8909190016
Download: ML20247G265 (6)

Text

y,w,m,-

,-n---.-

g

1. O GPU Nuclear Corporation U Nuclear

=S B 480 Middletown, Pennsylvania 17057 717 944-7621 TELEX 84-2386 Writer's Direct Dial Number.

September 13, 1989 C311-89-2108 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

20555

Dear Sir:

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

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report August 1989 Enclosed are two copies of the August 1989 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, D.

h. kill Vice President & Director, TMI-1 HDH/WGH:spb cc:

W. Rucsell, USNRC F. Young, USNRC Attachments h

' I 8909190016 890831

(.DR ADOCK 05000289 FDC I

GPU Nuclear Corporation is a subsidiary cf the General Public Utilities Corporation

OPERATIONS

SUMMARY

AUGUST 1989 The plant entered the month operating at 100% power producing approximately 870 MWe. On August 11, power was reduced to approximately 97% as a result of a motor failure on one of six operating circulating water pumps (CW-P-1F). The plant was stabilized and returned to 100% power for the duration of the month.

CW-P-1F was returned to service following the motor repairs on August 24, 1989.

MAJOR SAFETY RELATED MAINTENANCE During August, the following major maintenance activities were performed on safety-related equipment:

Primary Neutralizing Tank (WDL-T-8)

Recoating the interior surfaces of the Primary Neutralizing Tank was completed during August. Reinstallation of the mixer, WDL-M-1, t expected to be completed in September.

Waste Gas Compressor (WDG-P-1A)

The Waste Gas Compressor was removed from service, disassembled and inspected in July because of high operating noise levels.

It was reassembled using new parts as necessary and satisfactorily tested in August. The pump was returned to service.

Mrdox Fire System Pump (FS-P-7)

The Cardox Fire System Compressor was removed from service during August because of electric motor tripping on thermal overload. After being returned to service with a new motor, the compressor again tripped on thermal overload.

Pressure, temperature, and current readings are being monitored and will continue into September.

l l

l w_-__----_-_-

OPERATING DATA REPORT DOCKET NO.

50-289 DATE 08-31-89 COMPLETED BY C.W. Smyth TELCPHONE (717) 948-8551 OPERATING STATUS 4 NOTES I

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 1 I

2. REPORTING PERIOD:

AUGUST

,1989. I 1

3. LICENSED THERMAL POWER (MWT):-

2568. I I

4.. NAMEPLATE RATING (GROSS MWE):

871. I 1

5. DESIGN ELECTRICAL RATING (NET MWE):

819. I I

O. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

856. I I

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

808. I i

1 1

3.

IF CHANGES OCCUR IN CITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

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

20. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMMULATIVE-11.-HOURS IN liEPORTING PERIOD 744.

5831.

131472.

-12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 5831.0 59112.4

13. REACTOR RESERVE SHUTDOWN HOURS O.0 0.0 1960.0

14. HOURS GENERATOR ON-LINE 744.0 5831.0 58113.0

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1906894.

14946376.

142305481.

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 642261.

5131345.

47805730.

18. NET ELECTRICAL ENERGY GENERATED (MWH) 608119.

4854703.

44824413.

19. UNIT SERVICE FACTOR 100.0 100.0 44.2

20. UNIT AVAILABILITY FAL

,a 100.0 100.0 44.2

21. UNIT CAPACITY FACTOR 4.USING MDC NET) 101.2 103.0 43.6

~

22. UNIT CAPACITY FACTOR (USING DER NET) 99.8 101.7 41.6

23. UNIT FORCED OUTAGE RATE O.0 0.0 50.9

'24.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH 8R Refueling Outage 1/5/90 - 3/5/90

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

+

/ AVERAGE DAILY UNIT POWER LEVEL.

DOCKET'NO.

!50-289 UNIT TMI-1 DATE;- 08-31-89

. COMPLETED BY. L.w. dmytn TELEPHONE (11/J 946-8bb1 4

NONTHt' AUGUST DAY AVERAGE' DAILY POWER LEVEL-

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

(MWE-NET) 1 824.

'17 815.

2 818.

18.

820.

3 811.

19 '

823.

4 807..

20 816.

'S 800.

21 807.

6 810.

22 810.

7-819.

23 807.

8 830.

24 819.

9 829.-

25 827.

10 828.

26 824.

11

.824.-

27 823.

l'2 -

823.

28 817.

13.

816.

29 812.

1 14

' 816. -

30 811.

15 815.

31 821.

16 811.

p l-

[.

I r

p

}

~

,4 REFUELING'INFORMATION' REQUEST

~

1 Name.of Facility:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

January 5, 1990 (8R)

~

3.

Scheduled date for restart following refueling: March 5, 1990 (8R) 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 unreviewed 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?

October 5, 1989 5.

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

6.

Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

None 7.

The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:

(a) 177 (b) 360 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 capeity is 752.

Planning to increase licensed capacity through fuel pool reracking is in process.

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).

L_ J - _... _. _. _ - -. -.

.#. g,

+.-

I" l

I.

s ls I

I h

7q

1. h m

n(

M tf c

g 1

+r c C %4 7,

h g gg 4

7 55 M*

7m ~

4 4,e nt o 5.

mm

- no m w,,

n-u a o

8C'Y N 5

%.O s

I

• C, y

m m

,r,m ht O O'

M 8

u r

.e e

3 n ='{*

=

1c

.O.e n

a:

o, p <g,.

.:. h.

-. =

=

w m

2h#

a 9E I

YN I

q 2g

.3, N

$M W

@ U.

s- -

e'E e

g ep 'e

r. =c -v=.,..

pM

=

tr e m e n >mn L E85 L

o Mg Rc' e

m m"mmo m

d n.

t O

7 A

e' M

^

2

=

o e

- 11 oc 6& $edoC s21 m-u w

tnenopmoC m

.4..

QF 4

.e.egn mz

c e22-

.a E.o c =

a a..

n 6& edoc 2E I>O c

4 3

metsyS E -- yw ^

w C

5 2>

2o o

u 2

3 g EO m

A

=

z z

g gy o

=

3

,.. o 2

r x

E m

C z

E l

m e

rotcaeR nwoD 3

~

2 EmttuhS

=

e 4-

'lo dohteM

-d 2! ~:-

4

-k

._ - y m

3

.a >._

,nosaeR a

cM

=A 5,.-

e._

=.-

F 5 ~g~

,p, g g'C E 7

a o

x.4..

)sruoH I E

noitaruD 3 9 s.E E 5 5=

aE g2 s r=ap w &.r.c=m 7 =

"- c o s-e c.

r9 E** CACO epyT F> *OO~'O:

l at

.e e.c

_e'

=

c.c n.r,

=a r"

l m*

_