ML20140A774

Monthly Operating Rept for Feb 1986

ML20140A774
Person / Time
Site:	Crane
Issue date:	02/28/1986
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
5211-86-2045, NUDOCS 8603210223
Download: ML20140A774 (6)

Text

g OPERATING DATA' REPORT DOCKET NO.

50-289 DATE 2/28/86 COMPLETED BY-L.W. dmytn TELEPHONE U1/) 948-8551 s

s OPERATING. STATUS t

NOTES

1. UNIT NAME:

THREE MILE ISLAND UNIT 1,

2. REPORTING PERIOD:

FEBRUARY,1986.

3. LICENSED THERMAL POWER (MWT) :

2535.,

s

4. NAMEPLATE RATING (GROSS MWE):

871.

5. DESIGN ELECTRICAL RATING (NET MNE) :

819.

6. MAXIMUM DEPENDABLE CAPACITY.(GROSS MWE) :

824.-,

7. - MAXIMUM DEPENDABLE CAPACITY ' (NET MWE) :

776. !

's l

s

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

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

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERICI) 672.

1416.

100753.

12. NUMBER OF HOURS REACTOR NAS' CRITICAL 586.0 1190.3 35006.9

13. REACTOR RESERVE SHUTDOWN HOURS 86.0 191.3 1074.5

14. HOURS GENERATOR ON-L'INE 582.8 1178.7 34212.6

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1452251.

2925796.

82276192.

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 491292.

976657.

27368810.

18. NET ELECTRICAL ENERGY GENERATED (MWH) 461761".

'915531.

25567243.

19. UNIT SERVICE FACTOR 86.7 83.2 34.0

20. UNIT AVAILABILITY FACTOR 86.7 83.2 34.0

21. UNIT CAPACITY FACTOR (USING MDC NET) 88.5 83.3 32.5

22. UNIT CAPACITY FACTOR (USING DER NET) 83.9 78.9 31.0

23. UNIT FORCED OUTAGE RATE 13.3 14.5 63.4 24.. SHUTDOWNS SCHEDULED OVER.NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH Eddy Current Outage (Steam Generators); March 22, 1986; 35~da.ys

~ si

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

s 8603210223 %$O 89

, }h -j d

DR ADOCK PDR

e a

r -..

.i

~

l><

IAVERAGE' DAILY UNIT-POWER LEVEL.

l%v 41

/

' DOCKET NO;.

50-289

' UNIT:

TMI-l' DATE 2/28/86-

~

y COMPLETED BY-C.W. Smyth

+e..

TELEPHONE' -(717) 948-8551

MONTH:

FEBRUARY:

' DAY. AVERAGE DAILY POWER LEVEL DAY -AVERAGE DAILY POWER LEVEL 1~

~

3 L(MWE-NET)

-7..

.17 -'

.(MWE-NET)

.803.

jf' 2;

-9.

18

'804.-

~,

3

.- 2 2..

19 804.

'4 83.

20 804.

5..

.695.

21

'803.

l6 797.

22 806.

-7'

=812.

23 804.

8 1805.-

- 24

. 80 6..

e 9

806.

25 804.

f

,10-808.

26

- 80 4..

. 11 808.

. 27 8 0 4.-- 12-807.

28 804.

13' 805.

29 N/A

. 14

801.

30 N/A 15 799.-

31 N/A

~

16

'802.

1 L

?

r s

/

I-

-a 50-289 DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS IMI-I UNIT N AME DATE 2/28/8b COMPT.ETED ay C.W. Jm th S

REPORT MONTig FEBRUARY TELEPHONE ITI B 94h M T h

c ra 3 nac '4 Licensee E-r,,

n.,

Cause & Correceive

.2 e E

7

.No.

Date

{

3g g

jgg Event uT Action to

$5 E

j5g

. Report

• EG Prevent Recurrence 6

I 1/27/86 F

186 A

1 N/A HJ HT Exch.

Shutdown to repair bellows on extraction steam line I

2 3

4 F: Forced Reason:

Method:

Enlubit G -Instructions S Scheduled A fqmpment Failure (Explain) 1-Manual for Preparation of Data

~ B Maintenance of Test 2 Manual Scram.

Entr> Sheets for Licensee C Refueling 1-Automatic Scram.

Eveni Report (LE RI File (NtIREG-D. Regulator) Restriction 4-Other tINelaini 0161)

IAperator Training & Licenw INamination F-Admanistraine 5

osul 1:stur (INplaml Ihlubit I-Same Source G-Opera }Esplaml Il-Other(

6 Actually used Exhibits F & 11 NUREG 0161

REFUELING INFORMATION -REQUEST 1.

Name of Facility: Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

December.6, 1986 3.

Scheduled date for restart following refueling:

May 4, 1987 4.

Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?

Yes If answer is yes, in general, what will these be?

Conversion to 18 nonth fuel cycle with associated changes to Power Imbalance, Quadrant Tilt and Rod Insertion Li mi ts.

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?

To be determined.

5.

Scheduled date(s) for submitting proposed licensing action and supporting i nformation:

November, 1986 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) 208 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.

There are no planned increases at this time.

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).

(>

GPU Nuclear Corporation Ng gf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

March 14, 1986 5211-86-2045 Director, Office of Inspection and Enforcenent U. S. Nuclear Regulatory Connission Washington, D.C. 20555

-Attn: Document Control Desk

Dear Sir:

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

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report February, 1986 Enclosed please find two (2) copies of the February,1986 Monthly Operating Report for Three Mile Island Nuclear Station Unit-1.

Si ncerely, t

. D. Hukill Director, THI-l HDH:DVH:spb Attachments cc: Dr. T. E. Murley 0015C a

i GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

OPERATIONS SlNMARY FEBRUARY, 1986 The unit entered February in a cold shutdown condition for 8th stage extraction line bellows repairs.

All-six bellows were replaced.

On zFebruary 4,1986, the reactor was-taken critical and the~ subsequent morning -

the unit achieved 92% power (power level cutoff). The reactor reached-100%

-power on February 6,1986 with OTSG 1evels at 68% in their respective -

operating range i_nstrumentation. The' unit continued through the month with reactor power at 100%.

MAJOR SAFETY RELATED MAINTENANCE During the month of February, TMI Unit 1 performed no major maintenance on-safety related equipment.

r CORRECTION NOTE:

In the TMI-1 November,1985 Monthly Operating Report s

(letter no. 5211-85-2208), it was stated in the Major Safety Related Maintenance section that the diesel will remain inoperable (second to last line). This should have'-

t stated that the diesel will remain operable.

i l

a 1

l l

s I

r I

l

~

r-,w

,sr

+~.-,-w y

=ne, w -

m

-,---,>mw,-,,wre-~r,,vvge py,c,,

og-,m, ww--~-,--n,,w,ys+y,---

,m-g, e--

--vr g---

we w e,-,,em w--e--ee,