ML20050B291

Monthly Operating Rept for Jan 1982

ML20050B291
Person / Time
Site:	Crane
Issue date:	02/16/1982
From:	Smyth C GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20050B278	List: ML20050B277 ML20050B291
References
NUDOCS 8204050172
Download: ML20050B291 (9)

Text

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e-OPERATLNG DATA REPORT DOCKET NO.

50-289 DATE February 16, 1982 COMPLETED BY C-W.

Smyth TELEPHONE (717-948-8551)

OPERATING STATUS Three Mile Island Nuclear Station, Uni I

1. Unit Name:

2. Reporting Penod:

Januarv, 1982 2535

3. Licensed Thermal Power (MWt):

671

4. Nameplate Rating (Gross MWe):

819

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross Mhe): {0

'#D

7. Maximum Dependable Capacity (Net MWe):

E. If Changes Occur in Capacity Ratings (items Number 3 Through 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 Cumulatise 744-744.

65017.

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 O.0 0.0 31180.9

14. Hours Generator On.Line U*O 0.0 0.0

15. Urdt Reserve Shutdov.m Hours 0.0 0.0 76531071.

16. Gross Thennal Energy Generated (MWH)

U*

U-N o'* 3 30 -

17. Gross Electrical Energy Generateo lMWH) u.

u.

z;o4vas, IS. Net Electrical Energy Generated (MWH) 0.0 0.0 48.0

19. Unit Service Factor U*U U*U 48.0

20. Unit Availability Factor 0.0 0.0 4o.<

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 44,8

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 46.0

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 Operationp Forecast Achieved INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCI AL OPERATION i

8204050172

{DR ADOCK Ohh9 (4/771 PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. _50-289 M -I UNIT February 16, 1982-DATE COMPLETED BY _ C. k'.

Smyth TELEPHONE (717) 948-8551 January, 1982 MO5W DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(Mwe Net)

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OPERATING

SUMMARY

The Unit was shutdown the entire report period by order of the NRC..The RCS was at atmospheric pressure and core cooling was provided by the Decay Heat Removal System.

MAJOR SAFETY RELATED MAINTENANCE Work continued during the period on previously reported restart modifications.

Work on the OTSG tube degradation program continued with attention primarily focused on the A OTSG.

This work included eddy current testing and sample re-moval of 15 tubes in the A OTSG. Associated work included draining of the secondary side, identification of tubes from which to remove samples, instal-lation and removal of tube removal tools, performing smear sample, visual, eddy current, and microscopic ir.spection and temporary plugging of tubes.

Fol-lowing temporary tube plugging, the secondary side of the OTSG was refilled.

Tube samples were sent offsite for analysis.

Work on turbine driven emergency feedwater pump (EF-U-1) included replacing the oiler, exhaust end bearing inspection and governor valve work. Work is still progressing on the governor valve. Retesting of the pump will be scheduled at a later date.

4 I

r l

t i

1 4

PIFLII,XNG INFORv.aTION REOUEST l-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 resumption 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 Com=ittee 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=itting proposed licensing action and supporting information:

4 N/A 6.

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

N/A l

7.

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

(a) 177 l

(b) 208 8.

The present licensed spent fuel pool storage capacity and the size of l

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:

1987 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).

OPERATING DATA REPORT DOCKET NO.

50-289 DATE February 16, 1982 COMPLETED BY C. W. Smyth TELEPHONE

'717-948-8551)

OPERATING STATUS ee e sland h iear Statior., Uni: I

1. Unit Name:

2. Reporting Period:

J anuan. 1982 2535

3. Licensed Thermal Power (MWr):

871

4. Nameplate Rating (Gross MWe):

019 S. Design Electrical Rating (Net MWe):

6. Msximum Dependable Capacity (Gross MWe): {0

1. 1. D

7. Maximum Dependable Capacity (Net MWe):

6. If Changes Occur in Capacity Ratings (Items Number 3 Through 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 Cumulative

744, 744.

65017.

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 DU 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0 76531071.

16. Gross Thermal Energy Generated (MWH)

O.

O.

23'+ 64 3 30.

17. Gross Electrical Energy Generated (MWH) u.

u.

436euvas.

16. Net Electrical Energy Genera'ed (MWH) 0.0 0.0 48.0

19. Unit Service Factor U'O UU 48.0

20. Unit Availability Factor 0.0 0.0 4o.i

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 44.8

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 46.0

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Mor.ths (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 INITIA L CRITICA LID' INITIA L ELECTRICin' COMMERCI AL OPER ATION P/771

AVER AGE DAILY UNIT POWER LEVEL I

DOCKET NO.

50-289 N -I UNIT February 16, 1982 DATE COMPLETED BY C. k'.

Smvth l

(717) 948-8551 TELEPHONE January, 1982 F

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (Mb e-Net)

(MWe-Ner) 3 0

17 0

2 0

0 is 3

0 0

19 4

0 0

20 5

0 O

2; 6

n j --

22 0

7 0

0 j

23 S

0 0

24 0

25 0

9 0

0 10 26 0

11 27 0

12 0

0 0

13 29 0

14 0

30 0

15 0

31 0

16 0

w 6

OPERATING

SUMMARY

The Unit was shutdown the entire report period by order of the NRC. The RCS was at atmospheric pressure and core cooling was provided by the Decay Heat Removal System.

MAJOR SAFETY RELATED MAINTENANCE Work continued during the period on previously reported restart modifications.

Work on the OTSG tube degradation program continued with attention primarily focused on the A OTSG. This work included eddy current testing and sample re-moval of 15 tubes in the A OTSG.

Associated work included draining of the secondary side, identification of tubes from which to remove samples, instal-lation and removal of tube removal tools, performing smear sample, visual, eddy current, and microscopic inspection and temporary plugging of tubes.

Fol-lowing temporary tube plugging, the secondary side of the OTSG was refilled.

Tube samples were sent offsite for analysis.

Work on turbine driven emergency feedwater pump (EF-U-1) included replacing the oiler, exhaust end bearing inspection and governor valve work.

Work is still progressing on the governor valve.

Retesting of the pump will be scheduled at a later date.

PEtiELING DTORMATION REOLEST 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 resumption of operation thereafter require a technical specification change or other license amendment?

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

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Com=ittee 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=itting proposed licensing action and supporting inf~rmation:

o 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.

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:

1987 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).