ML20138M250

Monthly Operating Rept for Sept 1985

ML20138M250
Person / Time
Site:	Crane
Issue date:	09/30/1985
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	Mcdonald W NRC OFFICE OF ADMINISTRATION (ADM)
References
5211-85-2174, NUDOCS 8510310596
Download: ML20138M250 (5)

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OPERATIONS

SUMMARY

SEPTEMBER, 1985 The unit remained in hot shutdown the entire month awaiting the lifting of stays imposed first by the Third Circuit Court of Appeals and then by the U.S.

Supreme Court.

Major Safety Related Maintenance The following work was completed during the month:

Nuclear Instrumentation (NI-l) - Work continued on Source Range Nuclear Instrumentation Channel NI-1.

The preamp was replaced with spares and was swapped with Channel #2. Only after connectors between the preamp and the detector were replaced was the intermittent problem (counts dropping from about'5 to 0) solved.

CRD Electrical System - Repairs to the CRD electrical system (fire damage) were performed on transfer cabinets 2 and 7 to correct wire, transfer switch, and relative position indicator module damage. Testing was first performed in a de-energized state followed by control power only testing. The auxiliary and regulated power supplies were then energizad and the CRD system tested.

Follow-up work consisted of replacing RPI output amp modules for 1-2, 8-8 and R101 relay. The power supply terminal strips were checked to ensure operability and calibration was completed.

An unrelated CRD breaker problem (failure to close) occurred while performing a surveillance procedure. The breaker was replaced and inspected to determine the cause of the failure. The breaker was found mechanically hungup in the mid-travel position. The breaker was sent to the Vendor, G. E. Service Shop, Atlanta, Ga., for further inspection to determine the cause of the failure.

G.E. has concluded that'the failure was not a generic problem and was caused by the breaker " CRANK" ears being pulled inside the spring carrier assembly causing binding of the breaker. This finding was reported via INPO Nuclear Network.

8510310596 850930 PDR ADOCK 05000289 R

PDR

l OPERATING DATA REPORT DOCKET NO.

50-289 DATE g_an_gs COMPLETED BY C.lt Smyth

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TELEPHONE (717) 948-8551 OPERATING STATUS NOTES

1. UNIT NAME:

THREE MILE ISLAND UNIT 1

2. REPORTING PERIOD:

SEPT

,1985.

3. LICENSED THERMAL POWER (MWT) :

2535.

4. NAMEPLATE RATING (GROSS MWE) :

871.

5. DESIGN ELECTRICAL RATING (NET MWE):

819,

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :

824.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) :

776.

8. IF CHANGES OCCUR IN (ITEMS 3-7) 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 PERIOD 720.

6551.

97128.

12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 31731.8

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 838.5

14. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 0.

O.

76531071.

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.

O.

25484330

18. NET ELECTRICAL ENERGY GENERATED (;MWH) 0.

O.

23840053.

19. UNIT SERVICE FACTOR 0.0 0.0 32.1

20. UNIT AVAILABILITY FACTOR 0.0 0.0 32.1

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 31.4

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 30.0

23. UNIT FORCED OUTAGE RATE 100.0 100.0 65.3

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH w

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

4 L_.

-a(p.;.

?..

AVERAGE DAILY UNIT POWER. LEVEL DOCKET NO.

50-289 UNIT TMI-l DATE 9-30-85 COMPLETED BY C.W. Smyth TELEPHONE (717) 948-8551 r

' MONTH:

SEPT-DAY- -AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL iMWE-NET)

(MWE-NET) 1 0..

17 0.

2-0.

18 0.

3 0.

19 0.

4 0.

20 0.

5 0.

21 0.

6 0.

22 0.

7 0.

23 0.

8 0.

24 0.

9 0.

25 0.

10 0.

26 0.

11 O.

27 0.

12 0.

28 0.

13 0..

29 0.

14

.O.

30 0.

15 0.

31 N/A 16 0.

t 4

4 I.

i i

i 6

)

u.

50-289 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME TNI-I DATE 9-30-85 COMPLETED BY _ C. W. Smy_th REPORT MONTH SEPTEMBER TELEPHONE f717I 948 5551 4

w.

=

-a E c

c e.

1 5

j

-5y li' "5cc 5%

g*3 Cause & Corrective No' Date 4

5.3 0

5gx Evens 17 gL Action to Report a mo Preven Recurrence iidi g g

CO e

l c

Regulaton Restralrtt Order 1

85/09/30 F

744 D

1 N/A ZZ ZZZZZZ r

2 3

4 l-: Forced Reason:

Method:

Eshibis G -Instructions S: Sd:eduled A Equipment Fa !ure (Explain)

1. Manual for Prepar.ition of Data B-Maintenance of Tes 2-Manual Scram.

Entry Sheets for Licensee C. Refueling 3-Autunutic Scram.

Event Report (LER) File (NUREG.

D-Regulatory Restriction 4-Other ( Explain) 0161) n -Operator Training & License Exansnation F-Adnuristranne 5

nal Livor (INplain)

Exhibis I - Same Source G-Operasp'Explam t Il-Other (

F..,~

REFUELING INFORMATIOT REQUEST 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

Unknown 3

Scheduled date for restart following refueling:

Unknown b.

Will refueling or resumption of operation thereafter require a technical specification change or other license amend =ent?

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)?

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

Amendment No. 50, Cycle 5 reload, was approved on 3-16-79 5

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

N/A 6.

Important liceu-ing 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:

N/A T.

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 s:ze 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 in eeues at this time.

9 The ;roject ed date of the last refueling that can be discharged to the spent fuel pool e.asuming the present licer.ed capacity:

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

Nuclear

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Route 441 South Midd!etown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2396 Writer's Direct Dial Number:

October 15, 1985 5211-C5-2174 Office of Management Information and Program Control Attn:

W. C. Mcdonald c/o Distribution Services Branch DPC, ADM U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Mcdonald:

Thr:c Mile Island Nuclear Staticn, Unit I (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report September, 1985 Enclosed please find two (2) copies of the September,1985 Molithly Operating Report for Three Mile Island Nuclear Station Unit-1.

Sincerely, fbh u.4LX

. D. Kkill Director, THI-l HDH:JGB:spb Attachments cc:

V. Stello Dr. T. E. Murley 0015C i

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