ML19338D305

Monthly Operating Rept for Aug 1980

ML19338D305
Person / Time
Site:	Three Mile Island
Issue date:	09/15/1980
From:	Mitchell D METROPOLITAN EDISON CO.
To:
Shared Package
ML19338D304	List: ML19338D303 ML19338D305
References
NUDOCS 8009220291
Download: ML19338D305 (5)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 TMI-I WIT DATE September 15, 1980 COMPLETED BY D-G. Mitchell-

-TELEPHONE (215) 921-6579-MONTH August 1980-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL '

(MWe. Net)

(MWe-Net) 1 0

- 37 0

0.

2 0

gg 0

3 0

39 0

4 0

g 0-5 0

.21-O 6

0 2;

0 7

0-23 0

0 8

24 0

0 9

25 0

10 26 0-II 27.

0 0

12 28 0

13 29 0

0 14 30 0

0-15 31 0

16 0

8 0 O'.9 2.2 0 M /'

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OPERATING DATA REPORT DOCKET NO.

50-289 DATE Sept. 15. 1980 COMPLETED BY D-G. Mitchell:

TELEPHONE' (215) 921-6579 OPERATING STATUS Three Mile Island. Nuclear Station, Unit'I

1. Unit Name:

2. Reporting Periodi August 1980 2535

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe)i_

819

5. Desaga Electrical Rating (Net MWe):

840

6. Maximum Dependable Capacity (Gross MWe):

776

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

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.l 1

9. Power Level ~o Which Restricted. lf Any (Net MWe):

10. Reasons For Restrictions. If Any:

This Month

.Yr to.Date Cumulatise 744.

5855.

52584

11. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.8 0.0-0.0 839.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9

14. Hours Generator On.Line

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0.0 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.

16. Gross Thermal Energy Generated (MWH)

O.

o.

23434330.

17. Gross Electrical Energy Generated (MWH) v.

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zas4uuaa.

.18. Net Electrical Energy Generated (MWH) 0.0 0.0 59.3

19. Unit Service Factor 20.-Unit Availability Factor.

0.0 0.0 59.3 0.0 0.0 57.6

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 55.4

22. Unit Capacity Factor (Using DER Net)_

-100.0 100.0

-31.0

' 23.-Unit Forced Outage Rate.

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each)-

25.'If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status (Prior Io Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY.

COMMERCIAL OPERATION P/77)

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s 50-289 UNITSHUTDOWNS AND POWER REDUCDONS DOCKET NO.

UNIT NAME TMI-I DATE September 15, 1980 REPORT MONDI August 1980 COMPLETED BY D-C. Mitcha11 TELEPHONE (215) 921-6579

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$*o Cause & Corrective 1

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No-Date x

eo a

.c 5 a:

Event uT Action to

$E 5-j di g Repost #

c50 5

Prevent Recurrence d

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l A

E" #

.1 8-1-80 F

744

.D 1

I 2

3 4

F: Forced Reason:

Method:

. Exhibit G Instructions S: Scheduled A-Equipment Failure (Explain) l-Manual for Preparation of Data -

B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-s D-Regulatoey Restriction 4 Other (Explain) 0161)

E-Operator Training & License Examination F Administrative 5

G-Operational Error (Explain)

Exhibit 1 - Same Source Il-Other (Explain)

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SUMMARY

'? The ' Unit Lwas shutdown the entire. month as a result'of 3/28/79,

, Unit #21 accident. Core cooling was provided'by the Decay Heat LRemoval System.

MAJOR SAFETY RELATED MAINTENANCE b

'During ' the month 'of ' August, -1980, the' Unit operated in the cold

~ shutdown condition with restart ' activities in progress. The following major maintenance' activities were performed:

' 7) ' Emergency Diesel Generator "B" - the generator bearing was-inspected, repaired by.the vendor, and reinstalled.

. Also, manifold leaks,' and injector leaks were repaired.-

Leaks on. the air intake box were_ repaired during this :

schedule diesel generator work. Additionally, preventive maintenance items were completed including calibration of-megawatt meters, veltage meter, and oil changes.

All corrective maintenance and preventive maintenance items.

were performed satisfactorily.while Emergency Diesel Generator "A"~ remained operable.

2)

. The Main Steam Relief valves (MS-V-22 A/B) to the Emergency Feedwater. Pumps were. removed and sent to the vendor for set point-inspection.

3)

-The -Decay Heat ' Pump Motor "B" (DH-P-1B) was replaced

'during this month'.

The.following work was. performed

'during. the replacement of the motor:

Removal'of Decay Heat Vault "B" shield blocks.

a.

b.

Removal of. ventilation duct for access:1nto-vault.

c.

Disconnect electrical ~ power.to the. temporarily

' installed 500 EP motor.

d.

Remove motor from vault / install new motor.

e.'

Mount motor on base, connect electrical leads, thermocouples, cooling water lines.

f.

. Install oil in motor. Prechecks for running motor uncoupled.

g... Rotational check of motor, run motor uncoupled, tike readings.

f.

Alignment checks, grease,' coupling, couple motor to pump.

- 1.

Run pump / motor, perform ISI testing, operational

-checks.

All work was performed within technicalJspecification requirements fand with satisfactory results. - Pump / motor declared operational.

Weld repairs to weld #D-335 (Decay Cooler 1B Outlet to relief i

4) - valve DH-V-18B) were performed with' satisfactory _ flush and -

leak check results.- Work performed to repair the indication T

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was as follows:

!1 a'. '. Weld: cut marks, identified ~on pipe.

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.b. ? Cut:out spool piece 1(dutchmen).

c'. - Weld : preparation._--

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Id. " Cleanliness: checks.

-e...Fitup.

.f.

A ot; Hot weld pass.-

~~. _ Initial x-ray..

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g h.: Weld 'out.

-1.

Fiaal x-ray.

j. Flush / leak.' check. -

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3-REFUELING INFORMATION REOUEST

1. -Name'of Facility:

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1Three Mile Island Nuclear Station, Unit I-

=2.

Scheduled date for next refueling shutdown:

-Unknown 3.

Scheduled date for restert following refueling:

Unknown

4.,Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

~ If'answar 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?

EAmendment No.150,' 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 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:

N/A 7.

"D2e number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:

(a) 177-

^

-(b) 208

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8.

The present 1icensed spent fuel pool storage capacity and the size of I

any' increase.in licensed storage capacity that has been requested or is

.l planned Iin number of fuel ~ assemblies:

LThe present licensed capacity is 752. There ar 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-

1986 is'the.last refueling discharge which allows full core off-load

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capacity'.(177 fuel assemblies).

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