ML20066F811

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Monthly Operating Rept for Oct 1982
ML20066F811
Person / Time
Site: Crane Constellation icon.png
Issue date: 11/15/1982
From: Smyth C
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20066F809 List:
References
NUDOCS 8211190187
Download: ML20066F811 (12)
v • d • e


Text

. -.

4 OPERATING DATA REPORT DOCKET NO.

50-289 DATE November 15, 1982 COMPLETED BY C. W. Smyth TELEPHONE C112L-QLR Rssi i

OPERATING STATUS Three Mile Island Nuclear Station, Uni: I

1. Unit Name:

October. 1982

2. Reporting Period:

2535

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe):

019

5. Desi n Electrical Rating (Net MWe):

F 840

6. Maximum Dependable Capacity (Gross MWe):

76

7. Maximum Dependable Capacity (Net MWe):

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

i

9. Power Level To Which Restricted,if Any (Net MWe):
10. Reasons For Restrictions,if Any:

This Month Yr.. o.Date Cumulatise I1. Hours in Reporting Period 745-7296.

71569.

12. Number Of Hours Reactor Was Critical 0.0 0.0 31731.8 1.0 1.0 840.5
13. Reactor Reserve Shutdown Hours 0.0 0.0 31180.9
14. Hours Generator On-Line 0.0 0.0 0.0
15. Unit Reserve Shutdown Hours 0.-

0.0 76531071.

16. Gross Thermal Energy Generated (MWH)

O.

O.

25464330.

17. Gross Electrical Energy Generated (MWH) u.

u.

us4uun.

IS. Net Electrical Energy Generated (MWH) 0.0 0.0 43.6

19. Unit Service Factor U*U UU 43.6
20. Unit Availability Factor 0.0 0.0 42.5
21. Unit Capacity Factor (Using MDC Net) 4 0.0 0.0 40.7
22. Unit Capacity Factor (Using DER Net) 100.0 100.0 51.5
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Eacht:
25. If Shut Down At End Of Report Period. Estimated Date of Startup:

1

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

Forecast Achieved i

INITIAL CRITICALITY i

INITIAL ELECTRICITY

]

COMMERCIAL OPER ATION 8211190187 821115 (9/77i PDR ADOCK 05000289 R

PDR

' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289

-I UNIT November 15, 1982 DATE COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8552 October, 1982 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

MWe-Net i I

O 17 0

0 2

0 3g 3

0 0

19 4

0 0

20 5

0 0

21 0

6 0

7 0

0 23 8

0 0

23 i

9 25 0

0 0

10 26 0

II 27 0

32 28 0

0 13 29 0

0 I4 30 0

I5 31 0

16 0

~

s 50-289 UNIT SifUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME TML-I i

DATE November 15, 1982 REPORT MONT11 October, 1982 COMPLETED 3y C. W. Smyth l

l 11ELEPHONE (717) 948-8551 i

e.

E c

.$ E 3

j E3 Licensee 5-t,

{"l Cause & Corrective W.

Date g

g s

255 Event g?

Action to gO jE d

H I y, c Report a to u g

o Prevent Recurrence o

e d

Regulatory Restraint Order i

1 10/1/82 F

744 D

1 i

i l

i 2

3 4

f: forced Reason :

Method:

Exhibit G-Instructions S: Sc hednied A l'quipment Failure (Explain) 1 -Manual for Preparation of Data n-Maintenance or Test 2 Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Repost (LER) File (NUREG.

D-Regulatory Restriction l-Ot her ( E xplain) 0161) 1 -Operator Training A license IIxamination F Administrati'.c 5

G Operaijonal liv ror I Explain)

Exhibit I - Same Source ll Oiher ( E xplain)

OPERATING SEKMARY The Unit was shutdown the entire report period by order of the NRC. The Reactor Coolant System was partially drained to permit preparation for OTSG repairs.

Core cooling was provided by the Decay Heat Removal System.

MAJOR SAFETY RELATED MAINTENANCE During the month of October, restart modification work continued and the follow-ing major maintenance items were performed.

The Once Through Steam Generator (OTSG)' repair program continued with the following items accomplished:

1.

RC-H-1A ("A" OTSG)

A.

Crevis Drying and Dehumidification B.

Installed Stops / Bladders in the Hot and Cold Legs C.

Added I=munol into the Generator D.

Installed Video Equipment into the Generator E.

Installed Candles with Detonator Cords into Tubes - First 8 Rows (Total)

F.

Bubbled Immunol Up Tubes to Coat Tubeeheet

~

G.

Explosively Expanded Tubes - Total cf 302 Tubes Expanded H.

Cleaned Tubes /Tubesheet I.

Performed Profilometry and Eddy Current Tests 2.

RC-H-1B ("B" OTSG)

A.

Crevis Drying and Dehumidification B.

Installed Stops / Bladders in the Hot and Cold Legs C.

Added Immunol into the Generator D.

Installed Video Equipment into the Generator E.

Installed Candles with Detonator Cords into Tubes - First 8 Rows (Total)

F.

Bubbled Immunol Up Tabes to Coat Tubesheet G.

Explosively Expanded Tubes - Total of 152 Tubes Expanded H.

Cleaned Tubes and Tubesheets l

I.

Performed Profilometry and Eddy Current Tests l

This work was performed primarily to test the procedures and hardware and verify suf ficient tube expansion prior to continuing with the remaining tubes.

Concentrated Waste Storage Tank (CWST) piping modifications continued with field welding new pipe on the "A" CWST.

The Pressurizer Code Safety Relief Valve modification prugressed with the following work items completed:

I l

i

1.

Fit Up Piping ("B" Valve) l 2.

Welded Piping

3. - Radiography Performed - Satisfactorily 4.

Reinstalled Missile Shield 5.

Com=ensed Insulation Reinstallation I

Local Leak Rate Testing Program commensed with the following valves testing satisfactorily:

1.

HR-V-2 A/B, 4 A/B, 22 A/B i

2.

LR-V-1, 2, 3, 4, 5, and 6 i

3.

RB-V-2A, 7 4.

IC-V-18 Repair of IC-V4 was initiated because of high leakage.

The Annual Diesel Generator Inspections on the "A" and "B" diesels were com-pleted with the following ite=s completed:

i 1.

EG-Y-1A ("A" Diesel)

A.

Ran Diesel Engine (Preinspection)

B.

Performed Various Electrical and Mechanical Inspections -

l Satisfactorily C.

Performed IC Guage Calibrations D.

Performed Post Inspection 24 Hour Run - Satisfactorily 2.

EG-Y-1B ("B" Diesel) i A.

Ran Diesel Engine (Preinspection)

B.

Performed Various Electrical and Mechanical Inspections -

Satisfactorily D.

Performed IC Guage Calibrations l

E.

Performed Post Inspection 24 Hour Run - Satisfactorily Overhaul cf Fire Service Pump (FS-P-2) commensed with the electricmotor removed and pump disassembly.

Inspection was in progress as of the end of the month.

I i

l J

REFUELING INFORMATION REQUEST l

I 1.

Name of Facility:

Three Mile Island Nuclear Station, Unit 1 1

2.

Scheduled date for next refueling shutdown:

Unknown 3

Scheduled date for restart following refueling:

Unknown L.

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?

J If answer is no, has the reload fuel design. and core configuratien teen reviewed by your Plant Safety Review Contittee te determine whether any unreviewed safety questions are assceiated 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 3-16-70 5

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

i U/A c.

Important licensing considerations associe.tei vi h refueling, e.g. nev cr different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, nev cperating procedures:

l N/A 4

7 The number cf fuel asse=tlies (a) in the cere, and (t) in the spent fuel s:crage pool:

i sa)

-,i (y) yeu.

J c.

The present licensed spen; fuel pool stcrage capacity and the cice cf any increase in licensed storage capacity thE: has been requested er is planned, in nu=ber of fuel assemblies:

The present licensed capacity is 752.

There are nc planned increases at this time.

9 The prcjected date of the las: refueling tha; es: te discharged tc the spent fuel pool assuring the presen licensed capa:ity.

198 7 is the last refueling discharge whi:h allers full ccre eff-lead

{

capacity (177 fuel assentlies).

4 e

e OPERATING DATA REPORT DOCKET NO.

50-289 DATE November 15, 1982 COMPLETED BY C. W. Smyth TELEPHONE / 71'T o/m ussi i

OPERATING STATUS Three Mile Island Nuclear Station, Unit I

1. Unit Name:
2. Reporting Period:

October. 1982 2535

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe):

819

5. Desi n Electrical Rating (Net MWe):

F 840 i

6. Maximum Dependable Capacity (Gross MWe):

//6

"/. Maximum Dependable Capacity (Net MWe):

8. If ChanFes 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:

l 4

This Month Yr..:o.Date Cumulatise I1. Hours in Reporting Period 745.

7296.

71569.

12. Number Of Houn Reactor was Critical 0.0 0.0 31731.S 1.0 1.0 840.5
13. Reactor Reserve Shutdown Hours 0.0 0.0 31150.9
14. Hours Generator On.Line 0.0 0.0 0.0
15. Unit Reserve Shutdown Hours 0.

0.0 76531071.

16. Gross Thennal Energy Generated (MWH)

O.

O.

b<.6%330.

17. Gross Electrical Energy Generated (MWH) u.

v.

23 d4.u c a.

18. Net Electrical Energy Generated (MWH) 0.0 0.0 43.6
19. Unit Service Factor i

0.0 U.0 43.6 j

20. Unit Availability Factor 0.0 0.0 42.5
21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 40.7
22. Unit Capacity Factor (Using DER Net) l 100.0 100.0 51.5
23. Unit Forced Outage Rate
24. Shutdowns SchedulcJ Over Next 6 Months (Type.Date.and Duration of Eachi:
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

("l771 1

l

. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 TMI-I WIT November 15, 1982 DATE COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8552 October, 1982 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe Net t 1

0 17 0

0 2

0 jg 3

0 0

g9 4

0 0

20 0

0 33 0

6 0

23 7

0 0

23 8

0 O

7,;

0 o

9 25 l

0 0

10 26 l

0 11 27 0

0 12 28 0

0 13 29 0

0 14 30 9

o 1S 31 0

l 16 0

l

s 50-289 UNIT SilOTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT N AME El-1 DATE November 15, 1982 REPORT MONT11 October, 1982 COMPLETED BY C. W. Smyth TELEPilONE (717) 948-8551 e.

r c

3 -, e g"

~.

Ic E

7sX Licensec E-'

Cause A Corrective c

M'-

I)J'c R

E?

4 255 Event u?

83 Action to

$E E

j;5g Report sr

'N 0 0

Prevent Recurrence 3

Regulatory Restraint Order 1

10/1/82 F

744 D

1 i

2 1

4 I~: Fort eil

__ _ Itcason:

Mettuul:

Exhibit G -Instructions S: Sc heiluleil A.I quipment Failnre t fixplain) 1-Manual for Pseparation of Data ll Mainter. ant c or 'Icst -

2. Manual Scram.

Entry Sheets for Licensee C. Refueling

.l. Antenn.itic Scram.

livent Repost (1.ER) File INUREG.

D.Itegul.itos) ltestsiction l.Othee (lisplain) 0161) li-Opciator haining & Iitense I samination l'. Ad minist rat i.c 5

G Operatjottal l esos ll'.splain)

Exhibit !- S.nne Sontcc 110:hre iINplain)

.s r

k l

OPERATING

SUMMARY

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

The Reactor

- Coolant System was partially drained to permit preparation for OTSG repairs.

Core cooling was provided by the Decay Heat Removal System.

MAJOR SAFETY RELATED MAINTENANCE During the month of October, restart modification work continued and the follow-ing major maintenance items were performed.

The Once Through Steam Generator (OTSG)' repair program continued with the following items accomplished:

1.

RC-H-1A ("A" OTSG)

A.

Crevis Drying and Dehumidification B.

Installed Stops / Bladders in the Hot and Cold Legs C.

Added Immunol into the Generator D.

Installed Video Equipment into the Generator l

E.

Installed Candles with Detonator Cords into Tubes - First 8 Rows (Total)

F.

Bubbled Immunol Up Tubes to Coat Tubesheet

~

G.

Explosively Expanded Tubes - Total of' 302 Tubes Expanded H.

Cleaned Tubes /Tubesheet I.

Performed Profilemetry and Eddy Current Tests 2.

RC-H-1B ("B" OTSG)

A.

Crevis Drying and Dehumidification B.

Installed Stops / Bladders in the Hot and Cold Legs C.

Added I==unol into the Generator D.

Installed Video Equipment into the Generator E.

Installed Candles with Detonator Cords into Tubes - First 8 Rows (Total)

F.

Bubbled Immunol Up Tabes to Coat Tubesheet l

G.

Explosively Expanded Tubes - Total of 152 Tubes Expanded H.

Cleaned Tubes and Tubesheets l

l m Performed Profilcmetry and Eddy Current Tests I.

This work was performed primarily to test the procedures and hardware and verify sufficient tube expansion prior to centinuing with the remaining tubes.

Concentrated Waste Storage Tank (CWST) piping modifications continued with field welding new pipe on the "A" CWST.

The Pressurizer Code Safety Relief Valve modificarica progressed with the following work ite s completed:

1.

Pit L'p Piping ("B" Valve) 2.

Welded Piping 3.

Radiography Performed - Satisfactorily 4.

Reinstalled Missile Shield 5.

Commensed Insulation Reinstallation Local Leak Rate Testing Program co=mensed with the following valves testing satisfactorily:

1.

HR-V-2 A/B, 4 A/B, 22 A/B 2.

LR-V-1, 2, 3, 4, 5, and 6 3.

RB-V-2A, 7 4.

IC-V-18 Repair of IC-V4 was initiated because of high leakage.

1 The Annual Diesel Generator Inspections on the "A" and "B" diesels were com-pleted with the following items completed:

1.

EG-Y-1A ("A" Diesel)

A.

Ran Diesel Engine (Preinspection) 3.

Perforced Various Electrical and Mechanical Inspections -

Satisfactorily C.

Performed IC Guage Calibrations D.

Perforced Post Inspection 24 Hour Run - Satisfactorily 2.

EG-Y-1B ("B" Diesel)

A.

Ran Diesel Engine (Preinspectien) 3.

Performed Various Electrical and echanical Inspections -

Satisfactorily D.

Perforced IC Guage Calibraticas E.

Perforced Post Inspection 2' E:ur Eun - Satisfactorily Overhaul cf Fire Service Pump (PS-P-2) ccamensed with the electric rotor removed and pump disassenbly.

Inspection was in pregress as of the end of the centh.

a

Em~'UELING INFOR!/JsTIOE Pr.~ DST 1.

Na::2e of Facility:

Three Mile Island Nuclear Station, Unit i 2.

Scheduled date for next refueling shutdown:

Unknown 3

Scheduled date for resta-t following refueling:

Unknovn L.

Will refueling or resu=ption of opera-ic: therea'ter require e. technical specification change or other license amendnent?

If e.nsver is yes, in general, what vill '.hese be?

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anc unreviewed se.fety questions are assceiatei -ith the core relcad (Ref. 10 CFR Section 50.59)?

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

Arendment Ec. 50, Cycle 5 reload, vu ap:revei en 3-16-79

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