ML20039B322

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Monthly Operating Rept for Nov 1981
ML20039B322
Person / Time
Site: Crane Constellation icon.png
Issue date: 12/16/1981
From: Smyth C
METROPOLITAN EDISON CO.
To:
Shared Package
ML20039B321 List:
References
NUDOCS 8112220522
Download: ML20039B322 (10)
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Text

.

OPERATING DATA REPORT DOCKET NO.

50-289 DATE December 16, 1981 COMPLETED BY C. W. Smyth TELEPHONE (717) 469-9551 OPERATING STATUS Three Mile Island Neelear Station, Unit I j

1. Unit Name:

N ve=ber, 1981

2. Reporting Period:

2535

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe):

i 019

5. Design Electrical Rating (Net MWe):

840

6. Masimum Dependable Capacity (Gross MWe):

/76

7. Mnimum Dependable Capacity (Net MWe):

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

9. Power Level To which Restricted.1f Any (Net MWe):
10. R

'ss For Restrictions,If Any:

4

~ ~

This Month Yr to.Date Cumulatise 720.

8016.

63529.

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 U*U 0.0 0.0
15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.
16. Gross Thermal Energy Generated (MWH)

U*

0.

mbow.

17. Gross Electrical Energy Generated (MWH) u.

u.

23devu23.

18. Net Electrical Energy Generated (MWH) 0.0 0.0 49,i
19. Unit Service Factor _

0.0 0.0 49.1

20. Unit Availability Factor 0.0 0.0 47.8
21. Unit Capacity Factor (Using MDC Net) 0.0 0.0

.45.8

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 44.5 t
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each t:
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8112220522 811216'

{DRADOCK 05000289

("/771 PDR

6

' AVER AGE D ALLY UNIT POWER LEVEL DOCKET NO. _50-289 THI-I UNIT December 16, 1981 DATE COMPLETED BY C. k'.

Smy th TELEPHONE (717) 948-8551 MONTH N vember, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (Mbe Net)

(Mh e-Neti 1

0 17 0

0 0

13 3

0 0

19 4

0 0

20 5

0 0

21 0

6 0

22 0

23 s

0 0

24 0

0 9

25 0

0 lo 26 27 0

0 la 25 0

0 13 29 0

0 14 30 0

0 15 31 O

16 0

4 i

t I

50-289 DOCKET NO.

UNIT SilU1 DOWNS AND POWER REDUCllONS

'llil-I UNIT N AME DATE December 16, 1981 COMPI F1ED RY C. W.

Smytli REPORT MONilg November TEl.EPIIONE (717) 948-8551 4 no 5 3

e ri No.

Date E.

k _b 35b

h.,*2

&8 Attion go

'" A I""' I' '

n

.c 2 e Event 3

yo N

fisg Report #

N0 ju Ob p, event Recurrence 8

Itmulatory itentraint Order 1

11/1/81 F

720 D

1 i

i I

2 3

4 F: Forced Reason:

Metimd:

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

2. Manual Scram.

I:ntey Sheets for Licensee C. Refueling 3-Automatic Scram.

Event Repori 11.E R) File INUREG-i D. Regulatory Restsiction 4 Other (Explain) 0161)

E Opesator Training & l.icense Examination F-Administ rative 5

G.Operathmal Error (Explain) talnint I Same Source ll Other (Explain) e 1

OPERATING SUIC4ARY The Unit was in cold shutdown the entire report period by order of the NRC.

Core cooling was provided by the decay heat removal system. During testing that required pressurization of the Reactor Coolant System, leaking Steam Generator Tubes were discovered in the "B" generator.

Investigation of tube integrity in the "A" generator revealed additional leaks. These discoveries and related details have been reported in LER #81-13.

SAFETY RELATED MAINTENANCE Work continued on Restart Modifications.

Work on Reactor Coolant Pump "C" (RCP-1C) was performed in October and reported in the October Monthly Operating Report. Alignment of the pump-l to-motor was completed during November. All instrumentation (speed switches, vibration equipment, etc.) was reconnected and the oil drip shields were installed. A rotational check was performed with satisfactory results.

The annual inspection on the Em 7ency Diesel Generators (EG-Y-1A/B) were perf ormed. Mechanical, Electrical and Instrumentation checks were performed as part of this inspection program.

Upon completion of these inspections, a twenty-four (24) hour run was performed satisfactorily. Diesel Generator "1B" was found to exhibit high vibration and work is in progress to identify and solve the cause.

h -

REFLTE2.ING INFORMATION REOTTEST -

1.

Name of Facility:

Three Mile Island Nuclear Station, Unit I 2.

Scheduled date for next refueling shutdown:

Unknown 3.

Scheduled date for restart following refueling:

Unknown 4.

Will refueling or-resu=ption of operation thereafter require a technical specification change or other license amendment?

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

If answer is no, has the rr'oad fuel design and core configuration been reviewed by your Plant Satery Keview 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 sub=1tting 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 ane. lysis methods, significant changes in fuel design, new operating procedures:

N/A 7.

The number of fuel asszmblies (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 sice of any increase in licensed storage capacity that has been requested or is planned, in number of fuel asse=blies:

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:

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

~

capacity (177 fuel assemblies).

OPERATING DATA REPORT DOCKET NO.

50-289 DATE DecembeF 16, 1981 COMPLETED BY C. W. Scyth TELEPHONE "1m oas-8ss1 OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name:

November, 1981

2. Reporting Period:

2535

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe):

019

5. Design Electrical Rating (Net MWe):
6. Maximum Dependable Capacity (Gross MWe): f0

'ID

7. Maximum Dependable Capacity (Net MW():

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

9. Power Level To Which Restricted. lf Any (Ni MWe):
10. Reasons For Restrictions. If Any:

This Month Yr.-to-Date Cumulatise 720.

8016.

63529.

i1. Hours in Reporting Period 0.0 0.0 31731.8

12. Number Of Hours Reactor Was Critica!

0.0 0.0 839.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9
14. Hours Generator On-Line 0.0 0.o o,o
15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.
16. Gross Thermal Energy Generated (MWH)

O.

O.

m y330.

17. Gross Electrical Energy Generated (MWH) u.

u.

m <4u m.

18. Net Electrical Energy Generated (MWH) 0.0 0.0 49.1
19. Unit Service Factor U*U U*U 49.1
20. Unit Availability Factor 0.0 0.0 47,g
21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 AS.8 l
22. Unit Capacity Factor (Using DER Net)

~

100.0 100.0 44.5

23. Unit Forced Outage Rate l
24. Shutdowns Scheduled Over Next 6 Months (Type, Date,and Duration of Eachh

~:*

\\

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

5

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

Forecast A(hieved INITIAL CRITICALITY f

INITIAL ELECTRICITY l

COMMERCIAL OPERATION i

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~. OPERATING

SUMMARY

The Unit was in cold shutdown the entire report period by order of the NRC. Core cooling was provided by the decay heat removal system. During testing that required pressurization of the Reactor Coolant System, leaking Steam Generator Tubes were discovered in the'"B" generator. Investigation of tube integrity in the "A" generator revealed additional leaks. These discoveries and related details have been reported in LER #81-13. SAFETY RELATED MAINTENA';CE Work continued on Restart Modifications. Work on Reactor Coolant Pump "C" (RCP-lC) was performed in October and reported in the October Monthly Operating Report. Alignment of the pump-to-motor was completed during November. All instrumentation (speed switches, vibration equipment, etc.) was reconnected and the oil drip shields were installed. A rotational check was performed with satisfactory results. The annual inspection on the Emergency Diesel Generators (EG-Y-1A/B) were performed. Mechanical, Electrical and Instrumentation checks were performed as part of this inspection program. Upon completion of these inspections, a twenty-four (24) hour run was performed satisfactorily. Diesel Generator "1B" was found to exhibit high vibration and work is in progress to identify and solve the cause.

~ REFUELING INFORMATION REOCEST 1. Name of Facility: Three Mile Island Nuclear Station, Unit I 2. Scheduled date for next refueling shutdown: Unknown 3. Scheduled date for restart following refueling: Unknown 4. Will refueling or resu=ption of operation thereafter require a technical specification change or other license amendment? 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. I=portant 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. 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 license? 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: 1986 is the last refueling discharge which allows full core off-load eapacity (177 fuel assemblies).}}

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