ML20040A254

Monthly Operating Rept for Dec 1981

ML20040A254
Person / Time
Site:	Crane
Issue date:	01/15/1982
From:	Smyth C GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20040A252	List: ML20040A251 ML20040A254
References
NUDOCS 8201200624
Download: ML20040A254 (10)

Text

_ _______________

OPERATING DATA REPORT DOCKET NO. _50-289 DATE Januarv 15, 1982 COMPLETED BY C. W. Savth TELEPHONE

!<2 w-e 51 OPERAT!NG STATUS Three Mile Island Nuclear Station, Uni I

1. Unit Name:

2 Reportmg Penod:

December. 1981

3. Licer2d Thermal Power (MWt):

2535 l

871

4. Nameplate Rating (Gross MWe):

019

5. Design Eiectrical Rating (Net MWe):

6. Mnimum Dependable Capacity (Gross Mwe): p0 1

1. D 7 Mnimum Dependable Capacity (Net MWe):

6. 'If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Lesel To Which Restricted.lf Any (Net MWe):

10. Reasons For Restri:tions. If Any:

This Month Yr.-to-Date Cumulathe

11. Ilours in Reporting Period 744.

8760.

64273.

12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.c 0.0 0.0 839.5 1.1. Reactor Reserve Shutdown Hours 0.0 0.0 311f,0. 9

14. Hours G:nerator On-Line 0.0 0.0 0.0

15. Unit Re e.ve Shutdown Hours 0.0 0.0 76531071.

16. Gross The-mal Energy Generated (MWH)

O.

O.

25464.53v.

I? Gres,2:ctrical Energy Generated (MWH)

O.

u.

2.m uua.:.

18. Net Electri:al Energy Gene-ated (MWH) 0.0 0.0 48.5 19 Uni! Seni:: Factor UU UU M.5

20. Urdt Adlability Fa: tor 0.0 0.0 47.2

21. U. it Capaci:y Factor (Using MDC Net)

22. Unit Ca;ccaty Factor (Using DER Net) 0.0 0.0 45.3 100.0 100.0 42.3

23. Unit F 3rced Outage Rate

24. Shutdovus Scheduled Over Next 6 Months (Type.Date,and Duration of Each1:

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

26. Ur.its In Test etatus (Prior to Commercial Operation):

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIA L OPER ATION 8201200624 820115 PDR ADOCK 05000289

("III '

R pyg J

AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. _50-289 M '1 UNIT D 47E _ January 15, 1982 CCMPLETED BY C. L'. Sevth TELEPHONE (717) 948-8551 MONTH December 15, 1982 l

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL t

(Mb e-Net)

IMwe-Net)

I o

17 0

2 0

0 18 3

0 0

19 4

0 0

20 5

0 0

23 6

o 0

22 7

0 0

23 8

0 0

24 0

9 25 0

0 10 0

26 0

11 27 0

12 0

0 0

13 29 0

14 0

30 0

15 0

31 0

16 0

=

i 50-289 DOCKETNO.

UNIT SIIU1 DOWNS AND POWER REDUCTIONS UNIT NAME 'lill-l DATE January IS, 1982 C. W. Smyth December, 1981 COMPl.E1ED BY REPORT MON HI TEl.FPIIONE (717) 948-8551 "E

i I.icensee 51, 5t, c

re 5 u. :

cause A corrective 1

-3 _g g

7gf g

"o N

.c g m Event uy

o. ]

Atgion go g,, -

m,'

oE E

jgg Repoet fr iN 0 0

Prevent Recurrence 6

Reguint ry Rentraint Order 1

12/1/81 F

744 D

1 1

2 3

4 F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A.Fquipment Failure (Explain) 1 -Manual for Preparation of Data i

fi Mainicnance of Test 2 Manual Scram.

Entry Sheets for I,icensec C. Refueling 3 Automatic Scram.

I: vent ReporI(LERIIileINtlRI G.

D.Regulato y Restriction 4 Other (Explain) 0161)

E-Operator Training & License Examination F-Adrninistrative 5

Eshibis 1 - S.ivne Source G OperatJonal Error (Explain)

II Ot her ( Explain)

4 OPERATING

SUMMARY

i The Unit was shutdown the entire report period by crder of the NRC.

Core cooling was provided by the decay heat removal system. The RCS was partially drained on 12/11 in preparation for additional inspections of the OTSG tubes.

MAJOR SAFETY RELATED MAINTENA"CE In addition to work being performed on restart modifications, the following major maintenance activities were performed on the Once Through Steam Generators. The secondary side of the Steam Gencrators were pressurized to determine the number of leaking tubes. Leaking tubes were identified and marked. The primary side of the Steam Generators were drained and the lower primary manways removed.

Preparations were made and equipment setup to remove tubes from the "B" Steam Generator. Four tubes were removed and sent for i

lab analysis by B&W and Bate 11e Labs. The 4 tubes were temporarily plugged to allow refilling the secondary side of the Steam Generators.

Eddy Current testing continued to be performed on both Generators.

l l

J i

i i

I,

REFUELING INFORMATION REQUEST 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 2.

Scheduled date for next refueling shutdown:

Unknown l

3 Scheduled date for restart following refueling:

l Unknown h.

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

Amend =ent 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 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 The number of fuel assemblies (a) in the core, and (b) in the spent fuel 7

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 l

at this time.

The projected date of the last refueling that can be discharged to the spent 9

fuel pool assuming the present licensed capacity:

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

l

\\

OPERATLNG DATA REPORT DOCKET NO.

50-289 DATE - Januarv 15, 1982 COMPLETED BY C. W. Sevth i

TELEPrlONE

i') M-O 51 OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name:

December. 1981

2. Reporting I'eriod:

2535

3. Licensed Thern.al Power (Mht):

671

4. Nameplate Rating (Gross MWe):

819

5. Design Electrical Rating (Net MWe):

6. Maximum Dependab!c Capacity (Gross MWe): f0

1. D

7. Maximum Dependable Capacity (Net MWe):

6. If Changes Occur in Capacity Ratings (Items Numoer 3 Through 7) Since last Report. Give Reasons:

9. Power Level To which Restricted.lf Any (Net MWe):

10. Reasons For Restrictions. If Any:

~

This Month Yr..to-Date Cumulatne 744.

8760.

64271.

11. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.S 0.0 0.0 839.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 31160.9 14 Hours Generator On.Line 00 0.0 0.0

15. Unit Reserve Shutdown Hours 0.0 0.0

76531071,

16. Gmss The-mal Energy Generated (MWH)

O.

U.

25464330.

17. Gross Electrical Energy Generated (MWH)

O.

u.

ad uuaa.

IE. Net Electrical Energy Generated (MWH) 0.0 0.0 48.5

19. Unit Service Factor

~

46.5 UU UU

20. Unit Ava?. ability Factor 0.0 0.0 47.2

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 45.3

22. Unit Capacity Factor (Using DER Net) 100.0 100.0 45.3

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.F. w 'ted Date of Startup:

26. Units in Test Status (Prior to Commerci:; 4 3.. ation):

Forecast Acitieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPERATION to/771

I i

AVER AGE D AILY UNIT POWER LEVEL 1

DOCKET NO. 289

'I l

UNIT January 15, 1982 DATE COMPLETED BY J. W. Sevth TELEPHONE (717) 948-8551 i

I December 15, 1982 MONTH i

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL j

(Mbe Net)

(Mwe. Net s i

1 0

7 0

2 0

0 33 3

0 0

i 39 4

0 0

20 S

0 0

g 6

0 0

7 0

0 23 8

0 0

24 0

0 9

25 0

10 26 0

27 0

0 1

25 0

0 13 29 0

0 14 30 0

)

IS 31 0

16 0

1 1

i i

1

~._.___-.._.__ _._ _._ _ ___

DOCKET No. 50-289 UNIT SilUIDOWNS AND POWER RFDUC110NS 1hl-1 UNIT NAME DATE J anunty 15, 1982 C.

W. Smytti REPORT MONIll December, 1981 COMPT.F1ED RY TEI.FPfl0NE (717) 948-8551 "E

i Licensee

'E4 kg

].E 5

.$ E "e

Canse A Corre,:tive gh Event E5 E '8 Action to No.

Date h

3 ij d

fU P

$ ~d 5

jgg Report *r N0 Prevent Recurrence d

Regulatory acntrntnt Order wwma 1

2 3

4 f: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A. Equipment Failure (Explain)

1. Manual for Preparation of Data li Maintenance of Test 2-Mannal Scram.

Entry Sheets for 1.icensee C. Refueling

3. Antomatic Scram.

Event ReporiII.ER)l'ile INtIREG.

D Regulatory Restriction 4-Other (Explain)

Ol61)

E-Operator Training A License Examination F. Administ rative 5

Exhibit I. S.nne Sontce G.Operatjonal I:rror IEvplain) ll Ot he r I Explain)

l OPERATING

SUMMARY

The Unit was shutdown the entire report period by order of the NRC.

Core cooling was provided by the decay heat removal system. The RCS was partially drained on 12/11 in preparation for additional inspections of the OTSG tubes.

i MA.JOR SAFETY RELATED MAINTENANCE In addition to work being performed on restart modifications, the following major maintenance activities were performed on the Once Through Steam Generators. The secondary side of the Steam Generators were pressurized to determine the number of leaking tubes. Leaking tubes were identified and marked. The primary side of the Steam Generators were drained and the lower primary manways removed.

Preparations were made and equipment setup to remove tubes from the "B" Steam Generator.

Four tubes were removed and sent for lab analysis by B&k' and Batelle Labs. The 4 tubes were temporarily plugged to allow refilling the secondary side of the Steau Generators.

Eddy Current testing continued to be performed on both Generators.

l

REFUELIWG IliFORMATIOR REQUEST "1

1.

Name of Facility:

.i Three Mile Island Nuclear Station, Unit.1 4

2.

Scheduled date for next refueling shutdown:

i Unknown I

Scheduled date for restart following refueling:

3 Unknown L.

Will refaeling or resumption of operation thereafter require a technical 1

specification change or other license amendment?

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

If ranswer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Co==ittee to determine whether any unreviewed safety questions are associated with the core reload i

(Ref. 10 CFR Section 50.59)?

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

Amend =ent No. 50, Cycle 5 reload, was approved on 3-16-79 Schedbed date(s) for sub=itting proposed licensing action and supporting 5

information:

s N/A 6.

Important licensing considerations associated with refueling, e.g. nev or different fuel design or supplier, unreviewed design or performance l

analysis methods, significant changes in fuel design, new operating procedures:

?

N/A Tne number of fuel assemblies (a) in the core, and (b) in the spent fuel 7

storage pool:

i (a) 177 (b) 208 The present licensed spent fuel pool storage capacity and the size of 8.

any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

l The present licensed capacity is 752. There are no planned increases at this time.

The projected date of the last refueling that can be discharged to the spent 9

fuel pool assu=ing the present licensed capacity:

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

i

. _..