ML20077H711

Monthly Operating Repts for June 1983

ML20077H711
Person / Time
Site:	Oconee
Issue date:	07/15/1983
From:	Reavis J, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8308110233
Download: ML20077H711 (41)

Text

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AVER.\\GE D AiLY UNIT ?CwER LEVEL 50-269 OCCKET NO.

oconee 1 LNIT 0 ATE July 15,1983 COMPLE3DBY J. A. Reavis TELEPHONE 704-373-7567 it0 NTH June. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY ?chER LEVIL iMWe-Nec t i.\\lhe Nets 296 17 2

IS 3

19 4

g S

6 2

7 3

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24 9

25 10 gg 12 23 13 29

.i 30 14 15 31 16

!NSTRUCTICNS Cn t.".:s fer: :t, list :he ner:;e 2:lly =tt ;:wer 'e.et :.1 'lWe^et Nr eseh ::. - :.e -:, :: 4.: et.. ;

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B300110233 830715 PDR ADOCK 05000269 R

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59-269 DOCK ET NO.

UNITSilUTDOWNS AND POWEllliE!)UCllONS UNIT NAME Oconee 1 nATE 7-15-83 COMPLETED nY

_J.A. Reavis ItEPOltT MONTil June, 1983 TELEPflONE 704-373-7567 c

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A CB Pumpxx Reactor coolant pump low oil level, pump isoleted.

4 83-06-01 S

704.45 C

1 RC Fueixx Normal refueling and NSM work.

I 2

1 4

F: Finced Reason:

Methoi :

Exhibit G Instructions l

S: Stheiluted A.Eiluipenent Failure (Explain) 1 Manual for Picparation oil)aia ll Maintenance of Test 2.M.anual Scrum.

Ibis) Sheeis for 1.ieensee.

C.Refocling

.l Automade Scram.

Evens Repine ll.l:lt) File INtiltEG-D. Regulatory llest ricilon 4 Other (Explain) 01 til1 E-Opeaator Training 1 Liecuse Examinailon 5

F-Administrative lhhibii ! Sanie Sousee G.Opeiational !!s tor Ilixplain) ~

19/77)

Il Oihes (lixplain) t

DOCKET NO:

50-269 UNIT:

Oconee 1 DATE:

7-15-83 NARRATIVE SIDDIARY Month:

June. 1983 Oconee unit 1 entered the month at 72% power with one reactor coolant pump isolated due to a low oil level. On June 1 the unit shutdown to begin a scheduled refueling outage. The out-age continued the remainder of the month.

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o MONTHLY REFUELING INFORMATION REQUEST 1.

Facility'name:

Oconee Unit 1 2.

Scheduled next refueling shutdown:

Currently Refueling 3.

Scheduled restart following refueling:

4.

Will refueling or resumption of operation thereafter require a' technical l

specification change or other license amendment?

Yes If yes, what will these be?

Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

N/A 5.

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

N/A 6.

Important licensing considerations (new or different design or supplier,

~

unreviewed design or performance analysis methods, significant changes 1n design or new operating procedures).

4 7.

Number of fuel assemblies (a) in the core:

177 (b) in the spent fuel pool:

998*

S.

Present licensed fuel-pool capacity:

1312*

Si-- of requested or planned increase:

. 3, Projected date of last refueling which can be accommodated by present.

licensed ~ capacity:-

DUKE POWER COMPANY Date:

July 15, 1983

!Name of

Contact:

J. A. Reavis Phone:

704-373-7567 i

• Represents-the combined total for Units 1 and=2.

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o OPERATING DATA REPORT DOCKET NO.

50-270 DATE 7/15/83 COMPLETED BY J.

A.

Reavis TELEPHONE 704-373-7567 OPERATING STATUS

1. Unit Name:

Oconce No. 2 Notes Year-to-date and cu.mlative

2. Reporting Period:

3. Licensed Thermal Power l}lW ):

2568 capacity factors are calcu-laced using a weighted

4. Nameplate Rating (Gross alwen:

934 average for maximum

5. Design Electrical Rating (Net alwe):

886 dependable capacity.

6. Ma.timum Dependable Capacity (Gross MWes:

890

7. Maximum Dependable Capacity (Net MWe):

860

3. If Changes Occur in Capacity Ratings (Items Number 3 Through 71 Since Last Report. Give Reasons:

None i

None

9. Power Level To which Restricted. !f Any INet MWe):

10. Reasons For Restrictions. If Any:

This Month Yr. to.Date Cumulative

11. Hours In Reporting Period 720.0 4 343.0 77 208.0

12. Number Of Hours Reactor Was Critical 720.0 4 002.7 54 916.4

13. Reactor Reserve Shutdown Hours I4 Hours Generator On Line 720.0 3 983.3 53 793.7

15. Unit Reserve Shutdown Hours

16. Gross Thermal EnerEy Generated (MWH) 1 853 129 10 107 695 126 771 004 17 Gross Electrical Energy Generated (MWH)

A?n ?Rn

't aA7 44n 43 174 696

13. Net Electrical Energy Generateo lMWH) 601 408 3 313 066 40 983 301 t9. Unit Service Factor 100.0 91.7 69.7

20. Umt Availability Factor 100.0 91.7 69.7

21. Unit Capacity' Factor IUsing MDC Nett 97.1 88.7 61.5

22. Unit Capacity Factor (Uning DER Net) 94.3 86.1 59.9

23. Unit Forced Outage Rate 0.0 3.7 16.8

24. Shutdowns Scheduled Over Nest 6 Months IType. Date.and Duration of Each :

Refueling - September 25,-1983 - 10 Weeks

25. If Shur Down At End Of Report Period. Estimated Date of ",tartup:

26. Units in Test Status IPrior to Commercial Operations:

Forecast Achieved INITIAL CRITICALITY INITIA L ELECTRICITY COMM ERCIA L OPER A TION lYb

AVERAGE D ALLY UNIT ?OhER LE.'IL DCCKET NO.

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ty 7 Oconee 2 D ATE July 15, 1983 COMPLZ""ED BY J. A. Reavis TELEPHONE 704-373-7567 June,1983 310NTil DAY AVERAGE DAILY POWER LEVEL 0AY AVERAGE DAILY ?OhER '. EVIL 13the-Net t i stw e. Net 836 1

834 1,

832 836 i3 3

R7a 19 836 836 4

834 g

836 836 g

3 837 836 n

838 835 7

,3 3

R1A

4 824 9

838 835

.3 837 834 10 y

837 835 1:

837 834 3

836 834 i;

y 14 836 834 3o 837 15 g

i6 835

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!NSTRUCTICNS Cn th:s ictr::t, list :he aer:;: 22:!y ;;::t ;.:wer e.,ei ;,, *,iwe.. set f..f 43,.:.,.:.,.,.,,.,.., y ;,,,, g,,.,,,,,

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UEIT SilUT!) OWNS AND POWER REDUCllONS U C ET ne 2 DATE 7-15-83 COMPLETED 11Y

-J.A. Reavis 1(EPORT AIONTII June, 1983 TELEPIl0NE 704-373-7567

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3-N' Licensee

,E r, Came & Cuencesive o

' No.

Date

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.s ~ 5-Event y, y 93 Attion to

<. f, g Repius sr mO 5'

Preveni Reentrence y5 5g H

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O CC Valvex Turbine valve movement test 8-P 83-06-24 S

B Y

1 l

I 2

3 4

F: Forced Reason:

Methuit:

Exhibit G Internesions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data ll Maintenance of Test 2 Manual Scram.

linisy Sheels for I.ieensee 1 Antomatic Scram.

Event Repini (i.Elt) File INLIREG.

C Refncling D.Regn!aiory Hestriellon 4 Other (lisplain)

Olbl)

E-Ope.aior Training.t. License Examinailon 5

F Administrative Eshibit ! S.une Sonsee G.Opeiational lis tor (lixplain t 19/77)

I1.Other (lixplain)

O

o 50-2ho DOCKET NO:

IniIT:

Oconee 2 DATE:

7-15-83 NARRATIVE SIRDIARY

- Month:

Jung. 19R3 Oconee unit 2 operated the entire month at near full power. June 24 the monthly-turbine valve movement test was performed requiring the. unit to reduce load for a brief period of time, f

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MONTHLY REFUELING INFORMATION REQUEST 1..

Facility name:

Oconee Unit 2 2.

Scheduled next refueling shutdown:

- September, 1983 3.

Scheduled restart following refueling:

November, 1983 I-4.

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

If yes, what will these be?

Technical Specification Revision l

l If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

N/A 5.

Scheduled date(s) for submitting proposed IJ;ensing action and supporting information:

N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in i

design or new operating procedures).

i w

177 7.

Number of fuel assemblies (a) in the core:

(b) in the spent fuel pool:

998*

8.

Present licensed fuel pool capacity:

1312*

Size of requested or planned increase:

9.

Projected-date of last refueling which can be accommodated by present licensed capacity:

DUKE POWER COMPANY Date:

July 15, 1983

~

Name of

Contact:

J. A. Reavis Phone: 704-373-7567

• Represents the combined total for Units 1 and 2.

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m k-OPERATING DATA REPORT DOCKETSO. 50-287 DATE.luly 15,1983 COMPLETED BY

3. A. Reavis TELEPHONE 704-373-7567_

OPERATING STATUS Notes Oconee No. 3 I. Unit Name:

Year-to-date and cutaulative June 1. 1983 - June 30. 1983 capacity factors are calcu-

2. Reporting Penod:

2568 laced using a weighted

3. Licensed Thermal Power Qlwt1:

934

4. Nameplate Rating (Gross MWei:

average for maximum 886 5., Design Electrical Rating (Net MWe):

dependable capacity.

899

6. Maximum Dependable Capacity (Gross MWei:

860

~. Maximum Dependable Capacity (Net MWe):

S. If Chanps Occur in Capacity Ratmas IItems Number 3 Through 7) Since Last Report. Give Reasons:

Nonc None

9. Power Level To Which Restricted. If Any (Net MWe1:

10. Ressons For Restrictions. If Any:

j 1

I This Month Yr. to.Date Cumulative 720.0 4 343.0 74 855.0

!!. Hours in Reporting Period 720.0 4 259.3 52 480.4

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 703.6 4 220.4 51 363.7

14. Hours Generator On.Line

15. Unit Reserve Shutdown Hours 1 795 105 10 693 020 124 742 081

16. Gross Thermal Energy Generated (MWH) 620 380 3 711 890 43 109 704 I

17 Gross Electrical Energy Generated (MWH) 593 565 3 556 899 41 025 000

13. Set Electrical Energy Genersted (MWH) 97.7 97.2 68.6

19. Umt Service Factor 97.7 97.2 68.6

0. Unit Availability Factor 95.9 95.2 63.5

21. Unit Capacity Factor (Using MDC Net) 93.1 92.4 61.9

22. Unit Capacity Factor (Using DER Net) 2.3 2.8 16.2

23. Unit Forced Outage Rate

. 24. Shutdowns Scheduled Over Next 6 Months (Type.Date.snd Durstion of Eachi:

None

25. If Shut Down At End Of Report Period. Estimated Date of ~,::rtup:

Forecast Achieved

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

i INITIAL CRITICALITY l

INITIAL ELECTRICITY COMMERCIAL OPER ATION l

tm-,

i

AVERAGE D riLY L$1T POWER LEVIL

~

DCCKET NO.

Oconee 3

.gg7 D 4rE July 15. 1983 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567 sicNTH June. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY ?OhER LEVEL (StWe-Neo i3lwe.yer s 859 846 g.

2 AS4 is 530 3

856 3 51 39 847 8 51 4

,g 3

858 854

,g 6

AGA

=

854 814 8 54

,3 3

All

4 851 858 842 9

,3 I

854 to 858

,3 858 853 i:

12 857 848 3

856 852 1

.9 14 857 851 30 15 A47 31 i6 856 INSTRL*CTICNS Cn t..:s fctr-:t. List :Me ner:ge f:tly.. it :wer :e.,c ;3 '.ta.v.3et (;. 23,.3...,

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50 287 D

UNITSilUT!) OWNS AND POWEll REDUCllONS Uconee 3 UNI N E

part 7-15-83 COMPLETED !!Y J.A. Reavis REPORT AIONTil June, 1983 TELEPflONE 704-373-7567

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3-N' Licensee

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L Canse & Ciotective No.

Date g

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,2 ~ 5 livent 3'g e-T Attiim to

~ f, g Report u in U Prevent Itceurtence yE d

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go 5-P h3-06-03 F

B HH Pumpxx El heater drain pump repairs 6-P 83-06-07 F

A CH Pumpxx A feedwater pump tripped due to high setting on bearing oil ressure switch.

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7-P 83-06-17 S

B CC Valvex Turbine val've movement test 6

83-06-18 F

16.40 A

1 CC Valvex Replace faulty solenoid valve in hydra-ulics of #5 reheat stop valve.

8-P 83-06-24 F

B HH Pumpxx El heater drain pump repairs HC xxxxxx Work on air ejectors 9-P 88-06-28 F

B i

2 1

4 F: Forced Reawn:

Method:

Exhibit G Instrocitons S: Stheduled A Es[uipment Failure (Explain) 1 Manual for Preparaison ofI)au ll Maintenance of Test 2 Manual Scram.

linity Sheets for 1.icensee 1 Aufomatic Scram.

livent Iteport II.Elt) Fde INtil(EG-C.Refocling D Regulatory Resiriction

-1 Other Ilisplain) 01611 II. Ope.asor Training i License lixaminatiim I: Administrative 5

G.Opeiainmal lir ror (lixplain) thhibit I - Same Source 19/77)

Il Other Ilixplain)

50-28/

DOCKET NO:

EilT:

Oconee 3 DATE:

7-15-83

~

l NARRATIVE STDIARY Month:

June, 1983 i

Oconee unit 3 operated at full power until June 3 when power was reduced 5% to permit work on the El heater drain pump. The unit returned to full load after six hours and remained at full load until June 7 when a feedwater pump tripped causing a runback to 65%. The unit returned to full load two hours later. June 17 the monthly turbine valve movement test was run and June 18 the unit was shutdown to allow replacement of a faulty solenoid valve in the hydraulics of the #5 reheat stop valve. The unit returned to full load June 19. June 25 power was reduced 5% for seven hours to permit additional work on the El heater drain pump.

Finally, June 28, power was reduced 5% for one hour to work on the air ejectors. Oconee Unit 3 ended the p nth at full load.

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MONTHLY REFUELING INFORMATION REQUEST Oconec Unit 3 1.

Facility name:

2.

Scheduled next refueling shutdown:

May, 1984 3.

Scheduled restart following refueling:

July, 1984 4.

Will refueling or resumption of operation thereaf ter require a technical Yes specification change or other license amendment?

if yes, what will these be? Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

N/A 5.

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

N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

177 7.

Number of fuel assemblies (a) in the core:

(b) in the spent fuel pool:

55 8.

Present licensed fuel pool capacity:

474 Size of requested or planned increase:

9.

Projected date of last refueling which can be accommodated by present licensed capacity:

DUKE POWER COMPANY Date:

July 15, 1983 Name of

Contact:

J. A. Reavis Phone:

704-373-7567

i OCONEE NUCLEAR STATION Operating Status Report 1.

Personnel Exposure For the month of May, no individual (s) exceeded 10 percent of their allowable annual radiation dose limit.

2.

The total station liquid release for May has been compared with the Technical Specifications annual value of 15 curies; the total release for May was less than 10 percent of this limit.

The total station gaseous release for May has been compared with the derived Technical Specifications annual value of 51,000 curies; the total release for May was less than 10 percent of this limit.

NRC 1982 CHANGES Oconee 1 Period Originally Reported Restated January, 1982 Outage No. 1-P (Forced)

(Scheduled)

Outage No. 6 (294.47 hrs.)

SA (193.52 hrs.)

(split) 5B (100.95 hrs.)

Outage No. 7 Outage No. 6 February, 1982 Outage No. 8 Outage No. 7 9

8 March, 1982 Outage No. 10 Outage No. 9 11 10 April, 1982 Outage No. 12 Outage No. 11 13 12 May, 1982 Outage No. 14 Outage No. 13-June, 1982 Outage No. 14 Outage No.13 July, 1982 Outage No. 9-P Outage No. 9 Begin Date (82-07-02)

Begin Date (82-07-06)

Outage No. 15 Outage No.14 16 15 August, 1982 Outage No. 17 Outage No. 16 September, 1982 Outage No. 18 Outage No. 17 19 18 20 19 October, 1982 Outage No. 21 Outage No. 20 22 21 December, 1982 Outage No. 12-p (Scheduled)

Outage No. 12-p (Forced)

Oconee 2 No Changes

REVISED UNil SillHDOWNS AND POWl:H HEllllCIlONS DOCKETNO. 50-269 6/15/83 UNIX NAhlE Oconee unet 1 l>A r t 2-15-82 Hl.PONT AIONTil January, 1982 COLIPLETED Hy J. A. Heavis TELLPilONE 704-171-8552 c

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j Nd Licensee En,,

j q, Canse & c.nreceive

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Ihre 9,

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jEE Event 37 93 Auion lo j5 ch 3 g j:

Report c

. uib 5b Prevent Hecurrente 6

a y

G O

82-01-01 F

11,95 A

3 IIC

'lVRBIN

}bisture separator-reheater drain tank high level. tripped turbine /

reactor.

2 H2-01-01 F

6.18 A

3 IIC

'RIRBIN ibisture separator reheater drain tank high level tripped turbine / reactor.

3 82-01-01 F

16.60 A

3 IIC

'IURBIN bbisture separator reheater drain tank high level trinned turbine / reactor.

4 8.?-01-02 F

21.07 A

3 IIA INSTRU

'hirbine/ reactor trip due to false, loss of stator coolant signal.

1-p' 8.!-(11 - 01 S-B ZZ ZZZZZZ lblding at 401 for power escalation testing.

5 82-111-06 F

276.70 A

1 IIA TilRBIN Turbine brng. 811 exceeded high vib.

limit. Shutdown for balance shot and repair generator hydrogen leak.

I 2

3

-l 11 l'orscJ Reaunc

• klethoil:

Eshibit C Instinctams

.5 L heiluleil A l'ipnpment l'ailure (Explaint I-blanual fin Pseparation of Data 18 klaintenance ni Test 2 klannal Scram.

Ensey Sheets for 1.icemee C.Reincling

.t Automatic Suam.

I!vens Report II.1:HI l'ile INtlRI G-

1) R. gul.a.ny Reste Alion

! Other Ilimplaini Olbli l' Doc.ator Tuiningi 1iccuse lixamination li,bimimit ra tive 5

G Opcianninal 1.oros IEsplaint E'7:

ll Othes I L xpl.rini Eshibit 1 - S.une Somce

Oconee 3 Period Originally Reported Restated

, March, 1982 Outage No. 1 Outage No.-1A April through Outage No. 2 (Cause)

Outage No. 2 (Cause)

September,1982 Changed Steam Generator Auxiliary Feed Ring Inspection as Primary Cause of Outage.

October, 1982 Outage No. 2 (68.42 hrs. )

Outage No. 2 (11.00 hrs.)

(82-10-01) Date started (82-10-01)- Date started Outage No. 2A (57.42 hrs.)

(82-10-01) Date started (Cause) Core Physics Testinc!

Add Outage 3-P (Scheduled)

(82-10-06) Date started Outage'Ho. 3-P Outage No. 4-P Outage No. 4-P Outage No. 5-P (82-10-25) Date started (82-10-23) Date started Outage No. 5-P Outage No. 6-P Add Outage No. 7-P (82-10-30) Date started Nosember, 1982 Outage No. 6-P Outage No. 8-P t

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REVISED tlNil slitlil OWNS AND lslWI R RI puriloNS f)OCKET NO....- 50-269 6/15/83 UNIT NAhlE _0conee Unit I l)A IE 2-15-G?

Hl.rORI AlONill January. 1982 COWLETEI) g J. A. R m is 1ELEl'110NE 704-373 /bb/

c.

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2, N* i lxce.wc j -e,,

f'l.

Cause & Curreceive

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18 de

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4 isy 1:vcos ay EE Action su fE d

F 3i ;=,, g Itcpuso u no E'

Pacvens Recunense c

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O 5A 82-01-17 F

193.52 A

CH HTEXCH Outage extended due to leaks in the high pressure feedwater heaters IA1 and 1A2.

5B 8h-01-26 F

100.95 A

CH HTEXCH HP-25 repairs - valve disc and stem damaged.

6 82-01-30 F

4.13 A

1 HA TURBIN Removed unit from service for turbine balance shot. Reactor remained critical.

I 2

.I 1

I I. s.cil Reasine blesliini:

Enliil>it G - Insinadiinis S

5. i.ninicil A l'ipnpincos I ailine fI splaint I kineual l'os Psepasation ol' Data II Al.nnienini e us l'c>l 2 hjannal Sceain.

1:nt:) Slicets lin 1.itcusec

( Helucinig 1 A ui.n n itic Sse.u n.

I: vent Repost il l'H i l'elc lNilRI.G.

In Res;ul.nin) He>in. nun 1 Osive ll.npl.nni ot till l Opc..si... i s.unner A l C"w l unun.in..n l' A.lnusitalsative 5

(; i) pes.sinen.il I n..: liipl.nni lislailut I - Saine Sontce s'8/1/1 11 Ollies ll:apl.sen t

1 50-269 REVISED t Nil SiluTDOtt':0 2 Nill' owl:lt ItEDUCilONS DOCKET 6/15/83 93gg 3/15/82 ul:polt~1. AION. fit February, 1982 CO.\\lpi.ETEli nY J.A. Reavis TELEPilONE (704) 373-8552 E

F.

!E 3

$E'S l.icensee

,E s,

{*^o C. nase & Coircuive-Na.

Dale i

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i j55 livent 3, y 9?

Auson tu yE

[= 5 g itepine se mO 5'

Psevent Reentrente 6

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2-p 82-02-01 F

A Cil PIPEXX Reduced to 55% power to secure "A" feed-water pump for repair of a leak in the recirculation line.,

7 82-02-01 F-31.80 A

1 IIA TURBIN Turbine off for a -balance shot. Reactoi remained critical.

8 82-02-09 F:

417.65 A

1 CB llTEXCil Removed unit from service to repair tubi leak in the l A steam generator.

I 2

.I

-1 l~: Fin.ed Iteaun,:

Alcatiosl:

Exhibit G - lossentlions S - S t.c.inted ~

A.l!.pninnen Failure (laplain)

I 4lanual for Picp.uainin os liaia 11 hiaintenance or Test 241 annal Scrani.

Ensiy Sheets for 1.ieense.-

C It.:l'echng 1 Antuniatic Leaan.

!!ven Itepost (1.1.R1 I? le INtlRI.G.

i D.R.:gulatory itesiniction 1 Other (fixphin) 01bl)

I? ope aiin Trainingi 1.icenne li.tainin.iiinn I.A.hnim>iraisve 5

G Opes.inun I listor (lisplain) ihhibil 1 S.une Sonoce l's/77 ).

11 Dihes llispl.iini

=

50-269 DOCK ET NO.

t[ Nil SilOTDOWNS ANI) POWER REDUCTIONS UNil NAME Oconee 1 REVISED 6/15/83 DATE COMPLETED nY March, 1982 RI.00RT.sIONTil TELEPilONE a..

Litensee

,E s _

f4 15 I

'k

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Cane A Coerestive j

jE freed E?

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=

rN U Preveni Recurrente c5 _

~5; Rep.n t e

o 5o A

HA TURSITI Power was reduced per tech. spec. due tt: P-82-03-04 F

a turbine control (EHC) oil leak.

The leak was repaired and the unit returned to near rated power.

~

9-

'82-03-06 F.

432.25 A

1 CB HTEXCH IB steam generator tube leak repair.

^10 82-03-24' F

3.15 A

3 CB Ifl5TRU Reactor tripped on high reactor coolant system pressure due.to a feedwater control problem causing a swing in' flow.

\\

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2 Esta5 t C.Insiractn.ns

'I.

~~ Finiej Reaso:t los Picparatiini of Ibra Merin >J:

l':

1. Manual S.. Si,t.e.itdet!

A.F.gnspment Failure (Espla:n) n Maintenance of Test 241. nual Seram.

Entiy Slieers for I.aensee

.:. Autematic Scr;nn.

F.s en: Rep nt (l.l.R1 file INL:R!,C.

, C.Refs. cling 4.Oilie: (ib. plain i 01bl1 D.Rgul;nory Restin. tion

' l Ops *.J!Df I:JifMng 1 LN'Jnie I5UntinJitun 5

F.Adernevi> rative

[NlnhisI.S.nne$ optic C C;WJilun.d l3!uf (E%plJin) rs/77)

.11 Diiier ( Explaial L-m f'

. _ _ _ _ _ _. ~ _ _ _.

=

50-269 REVISED 1:Nir Silu1 DOWNS AND l'0WI.R REDUCllONS DOCKET NO.

6/15/83.

UNil NAhlE Oconee 41 DATE April, 1982 costPLETED fly lit. PORT Af 0N.fil TEMPHONE i

t

~.

E 2

i

.]E 3

$ 5' ~j l.icensee

,E,

{ 9, Cause & C ureceive D oe

.i 3g i

is@

Etens 37 E- ?

Aoian in i

H.

fE d

3 ;p, g Itcport a viU SU Prevent itecurre:4e g

u C

11

.82-04-02 F-36.33 A

3 RB CRDRVE Reactor tripped when a control problem allowed the group #6 rods to drop into Core.

4-P 82-04-19 F

A CB MOTORX The lAl RCP (reactor coolant pump)

I was--removed from service due to oil level low alarm on the motor lower bearing oil pot.

12 82-04-20 F

9.72 A

1 CB MOTORX Unit was removed from service and reactor at hot shutdown. to add oil to the lAl RCP motor lower oil pot.

i 1

-1 2

.I 4

IE fenced.

Reaune kleilniil:

thliibit G Instructions S. S61.cif uleil A l.gnipineri Failure (Lipl.rin) 141.enual for Preparation ofI);u Il4taintenance of Test 241 annal Serain.

I:ntry St.eets for 1.icemec C.Refue!ing

.t Autoniatic Saain.

Ewn Report (1.Elt) file INllRI.G-I).He5ulatory itesteiction

-! Oiher (thplaisil 01611

'~

INOpe.asin Training 1 Lrce.ne !!.siinin.ition I"~ AtIllif fent rJlive S

j,

C Ope JfiustJI 1.g e'est (l'.\\plJtta)

Estilbil 1 S.silit* Settleie t's/77)

Il Oslier ( thplain) l i.

'5'd-269 U

REVISED UNITsitu1 DOWNS AND POWI:lt REDUCllONS U! NAIE Oconee 1 6/15/83 ng, g.

ttay, 1982 COMPLETED llY RI: PORT MONTli TELLPIIONE

.I E

E

.5E 3

$ 5' E Licensee E -r, f,

C.nise A Ciurei.tive h

Dae 3.

5g ji isJ Even g,7

e. ?

Atti..n n.

y~

d 5 ;f, -

'Icpin t e to L E'

Prevent itecurren,e H

o 5o CH HTEXCH Tube leak in 1B1 feedwater heater 5-P 82-05-05 F

A necessitated a power reduction for isolation of heater.

6-P 82-05-07 F

A CH HTEXCH Operating at 95-96% power due to 181 FWH not isolating completely.

13 82-05-21 F

241.70 A

3 RB CRDRUE During control rod movement test, the

1. 8 rod on gp. #1 dropped due to a shorted stator and resulted in a reactor / turbine trip.

l.

2 1

4 la rince.!

Itcasin :

P.leiln.J :

Ex!nbei G. Instructions S. Sslieilu'.tl A l'ip:spment f.ti!ure (LxplJin) i 4*lJ n u.!!

for Prep.trJIi..n Of NJIJ li.M;intenance of Test 2.\\ lana.! Scram.

1.ni 3 Slicens f or 1.isensee C.R. fn::!,ng

.l Autunutic Sts.un.

INent Iteport (I.I.lti file INtiltEC.

D.R.:gniatorr D : yricriini 4.Ot her (1:spl iin) 0101)

' fig 1 ! leCil>C 15 %J111iffJt fil!!

I Ope.JIO' i'

F.Adminni 5

G Opearia a rut (E splain t Estntui ! S.nne Sousee pJf77)

Il Other (I:xplain) 9 L__

5d-269 REVISED 1: Nil si:uitiowNs ann rowl.It HEl>Uc1 tons DOCKET NO, 6/15/83 UNil NAhlE -

, OcD.!!Re I 11 A I t'.

7-15-82 CO&H't.EIED HY I A R N I8 Hl.I'ORI AIONI. _ June' 1982 TEl.E!*ll0NE 704-373-8552 I

1.

?

1*

!E 3

$ $ "j l.icensce

,E-+

{'a.

Cause A Cenectaire No.

Date i

3g j

jy Even:

{y py Atenni en y5 s

3gg iteguns e in O E'

l*revent Hecurrente u

e g

O 13 82-06-01 F

331.20 A

RB CRDRVE Continuation of outage. Cleaning and inspection of control rod drive stators; repair of feedwater heater leaks; repair of pressurizer relief valve (RC-66); inspection of icactor building secondary shielding wall tendons in progress.

7-p 82-06-24 F

II RA INSTRU Power reduced to 95% to evaluate noise on reactor loose parts monitor.

h 1

I 2

4

.I l'

l'in ced Iteason:

kicilnnl:

Exhibit G-Insientse.wis S.% lee Inleil A l'ignepment Emifure(laplaint i Alannat f n Picparainm ol Data It Alaintenance or Test 2 Alaniial Scram.

1:nisy Slieces Ine I.scusec C.Hes'ncling 1 Antumatie Stsam.

Event Report ll.l.Ri l ilc lNtlRI.G.

H-R.7nlainry Hessiiction LOilies llisplaini 01blI I Ope.ai.. Training A l.icense Exainination E. A.lininne ralise S

G Opciaen nal lator IEsplaint l'.shibil I. S.nue Sumic rs/17) lithheilExplain).

' ' ~ ' " ' " ~ ' ' ' ' ' '

- ~ -

U REVISED

.UNITSillJrDOWNS ANi>l>0 Welt liEDUC110NS U!

, if oconte 1 6/15/83

- gfgjg2 gg, g Iti:POltT A10NTil August. 1982 Coat! trTED I Y h,

.5 E 3

, 3*

1.ieensee

,E%

Cause & Co.rective N".

Date i

~?

4 isd liven:

3,7

c. ?

Acisonin y5 5

3 ;5 g Repost e u) U 5'

Prevent itecurrence H

o gc 16 82-08-06 F

3.17 11 3

EB CKTBRK Reactor trip due to CRD group 6 drop when power f rom auxiliary -

power supply was lost.

10-P

'82-08-20 F

D

?.C BATTRY Control batteries specific gravity out of spec. Commenced Rx shutdown per tech. spec. Power decrease stopped at 42% when batteries declared operable.

l 4

1 2

.l

.h!cthost:

Exhibit G -Instruttowis 4

1: f uced.

Iteaun.:

~

S. Lheiluteil A l'.pnpment Failure (laptain) l4tainsal l'or Preinsation ni Data 1:4tainicnance or Test 241anual Serain.

C.iterneling

.l Automatic Scram.

Enity Sheets l'or 1.i.:ensee livent f(ep.u s (1.Elt! Fi!c INtiltLG-D-It. gol.iiory itestiiction.

-l Other llaplaint Ultil l t

i Ope.aro Tsaining A License lixamination I. Administrative 5

G.Opeia tional la ror ( Esplain)

Estabit I - Same Somee 07/77)

I;i)iher IExplain).

---.e.,

-.m

50-269 DOCKET NO.

REVISED t? Nil silul') OWNS AN:

UCTIONS UNil NASIE._Oconee I 6/15/83 IIATE CONipLEll:D itY

'Itl.I'OltT alONTil July, 1982 TELEIIIONE c.

=

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{ 9, raine & rinnetiive 1).de

-3 4

2g4 Iheni

?7

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A.m..n in Pievent itecuerci se f I.

d jsy ltepnet e iE L j'

H

O HE TURBlfi Power reduced during UT (ultrasonic 8-p 82-07-01 F

B testing) of turbine extraction piping

("C" - bleed).

HE TURBill Holding at 79% power until a 9-p 82-07-06 F

H reinforcement patch is added to "C"-

bleed line.

14 82-07-06 F

7.62 B

1 HE TUR81ft Unit off and reactor at hot shutdown to weld patch on "C"-bleed line.

15 82-07-2S F

9.23 A

3 ZZ ZZZZZ Reactor / turbine trip caused by lightning.

1 4

I 2

' h!cibuti:

Eshibit G. Instantti.un li l'inced Iteavnc i 41;n o.il l'or Psepautnin.it 1).na S. St hes!ntet!

A lignipment Ibifore(L.splaint ll41aintenance ni Test 2Alanual Scram.

Entey Sliceis l' n 1.isensee

.i Aulonutie Ste.nn.

ISent Iter.us (I.Litt l'ile INtiltl G.

C.itel'ucting 4 0ilier(lisplaini Ot til l D It.:sulatory itestinction l'-Ope.ator Training A lasense lixamination 5

!! Adminaisalive Estubit I. S.une S.i.nce G Opeuiional I.isne (l:splainI I's/77 )

Il-Other ( thplaini

U UNU SHUIDWNS AND l'WI:lt IM:DUCHO.*G REVISED x

A g

t.

j 6/15/83 nA7. 10-1s-82 S

W"'l EIED ny J.A_

R an H _ __

fu rottIaloNnt eptember,1982 TELLPilONE 70".-373-7411 l

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i 1.sycnwe

j-a, C.nise & c..ncoive N-Oase i,

5?

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$5 5

5 ;f, =

f(epeni e

<Ti G S'

l' event itecnerente O

C 17 82-09-10 F

11.62 11 3

ilA IllSTRU Low EllC pressure trip. Pressure switch activating above setpoint 18 82-09-11 F

6.33 G

3 Cll ZZZZZZ Reactor trip due to a feedwater transient result,ing from an operator error.

S 19 82-09-11 F

9.73 A

3 IIA CKTBRK Turbine trip on loss of stator cooling Loss of power to stator cooling pump caused by faulty breaier in load center feeding the pump.

I i

.i i

l'os cc.!

l(c. iso..

l:sigt.o (,. Insi,nce n.n.,

N

.% l.c.i nic.!

A-l.pninncia l'.ninie (i.spla;n)

[..i Ps ep.u a ti..n.it D o.

le r. bit:n n n:ce ai icit in.inoal S. r.ini.

I,ning Slices,i.n I. gen.cc r It.:f'ue! sng 1 Autuinatic Su.nn.

1% ni l<epin g (i.l 10 l' ele (Ntil(1 C.

D.It. gulatory Itcsnicainn

.l.Oitier (lisplain) oi g,13 i Ope.al.u Ts.sining A l.itense 1:.sanun.itann 11.blinir:nt r.itive 5

G Opeaateini.il I.orut (lispl.nn) l,gintne l. S,nne S.unce r8/17 )

Il Oilies llispl.iin)

L REVISED U. T SHU IDOWNS AND l OWI.it liElluCTIONS DOCKET NO. 269-M 6/15/83 llNil NAtti' Oconee #1 _

DA TU 7IN~

Hl.TOHT AIONfl1 ctober,1982 CO.\\ll't. Ell.D ny

.I. E Reavis_

0 TELI.I'llONE 704-373-7433

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$~

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6

.ll-P 82-10-07 F-11 u

Pur1PXX Reduced load to isolate 'lAl' RCP due

[

to low oil level alarm.

t

~

20 82-10-07 F

34.07 11 1

CB PUMPXX Reactor shu.tdown to add oil to 'lAl' t

RCP.

21 82-10-22 5

203.55 8

1 CB VALVEX Unit shutdown to adjust internal ring settings of pressurizer code relief valves.

1 b

4

'l' 2

'i I l'osced Itr.s,.. :

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g,,jg,g, g ;, g, s,3,,,,,,,,,

n 5 % licif ute.1 A.I.png.n,rio I,n;.n.- (1 sl>l.;;n t I.,sl in,,. I

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1841nulenance or Ic t j.sl.nn,.,e 3(..un, g,, n, 3.,.;,.,. 3,,,,,,,,,,3,.,.

( Rele. tin.i,.

.t.Anhnn.itic Sce.nn.

lg,o 3 ep,yggg,g;ggg,geg g ggg3.

D Regul.nory Itesinction 1 Otti.n (ghplainn gigg3 1: Ope. ant 1s.sining A lasense Eunun.inon 1; Ailn:innis.iiise G Opei.irnen.it i er.n llSpl.nn)

'5 thinba 1 - S. nae S..us e l'8/17)

_11 (lalie: (INpl.in )

1 m

e REVISED 1:NITSIllllDOWNS ANill'OWElt IIEDUCllONS DOCKET NO. _50-269 6/15/83 UNil NAtIC _0conee g ___

llAIC Ill !'OltT AION.filOctober' 1982 CO\\lPLElliD 35y

.I. A. Reavis I ELt.I'1!ONE 704-373-7433 t

c..

53, 4 N' E I.icensee E.

f'r.

C.nne A C..necin e

=

Dae E. y 4

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Il-P 82-10-07 F

11 ou PU!!PXX Reduced load to isolate 'lAl' RCP due to low oil level alarm.

20 82-10-07 F

34.07 11 1

CB PUMPXX Reactor shutdown to add oil to 'lAl' RCP.

21 82-10-22 S

203.55 B

1 CB VALVEX Unit shutdown to adjust internal ring settings of pressurizer code relief valves.

l

.I l

l l' n ccil lir.s...r :

tn l.

l..Intne t;. l. win. e..

S. I.citute.1 A 1.p.g.n.cne f.n!.n. fI spt ;nt i.\\i.n..

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.t. Antunutic Sci.nn.

I seni 1;cp.n (1.1.l() l'ile INtil:1.t;-

D 1(.:gul.nney Itesincliini Ollies (limplaini ultill 110pe.a li. 'lsarmng A l.,cuse I.ununato n i; Ailn;innisaine a

5

(; ilpeiainnul I sen II.splanil lhinini 1 S.nne S..ui.e l'8/ / 7 )

11 Oilies ll spian.)

i

REVISED llNil SilillllOWNS AND PalWI R Hi DI;ciloss DOCKET NO.

50-269 UNIT NAhlE Oconee 1 6/15/83 IIA IE l-14-82 NI:POHI AIONrII December, 1982 COMPLETED ay J. A. Reavis TELEl'ilONE 704-373-7567 e

1. I "8**

=

p.

U a E ~4 I s.tensec g e.,

i :-

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Cauw & Curreceive

$ :g, N' '-

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5-4 5s5 E.cne p?

Aoion so dE d

Reposi e a8 0 Eb Psevent Recuticosc 5 if, {c e

v o

l 12-P d2-12-03 F

B CA CRDRVE 87% power for CRD movement PT.

l l

J l

i

.I 1

l I.n. cil Reauni Alcolonl; Esinibit G - leisessisliinis S

S. I.. ilnic.I A l'ipnpmens I.nluie il splanal 1 Alanual l'os Psep. stations i l' Dala 11 hiaintenanic ne les

.? Alanual Scsaan.

I:nts) Slicess fus 1.scensee r Helucinig

.l Aus.nnalic Si s.sm.

Event Repius ll l'HIl'ile INilRI.G-la Hegul.a.n) ltr>in.n.m 1 Oslice ll.=plaml 016lI I (ppcias.n le einmr A I h e nv i unun.in.m 1 A.imanssaanvc 5

G Opcs.sinnial i es.. Il spl.un)

E.sliilus I Same Source s's! / / )

11 Ollies ll:npl un i J

50-287 DOCKET NO.

Oconen 3

' UNIT SifUTilOWNS AND POWCit REDUCTIONS UNil N A%tE _

DATE REVISED 6/15/83 COMPLETEDHY _

liarch, 1982 TELLPIIONC RI:PortT MONTit Catiu J Curres ivo-n.

c s

Literisce

{ t,

{g Action in

=

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e 's D.cr e y

3s g

jgg ggen Psevent fleeurrense

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. ;f, g Regunt r o

e

o Maintenahce to the high pressure SF PIPEXX IA 82-03-01 F

704.95 A

injection (HPI) nozzles.

4 3

Es!nbit C. Ins:rn,tio a 2

M et hoJ -

for Preparatin:t ut Data Itca..n.,

1 Manual 1:nt > Sheets for 1.nien>ce R! C-1 F FusceJ A l.jn pinent Fai!u:c (Esp!Jin) 2 M.inual Scrarn.

INent Iteport (1.1.Rl IMe (Nt:

S. SJiednied 11.muitenan.:e u( Test 1 Autout.itic St arit.

0101)

C Refuctin;;

-I Oth: (Espf ain t DM pbrory llevri. tion S

I: Ope.ator Training J License lisaniin.irion Esinbet I S.une S uice F-Ad ua n:>t r air.e G.Opei ation..! i i rnr (1: spl.nn i Il Galier (I: spbin )

I'll77 )

REVISED flNil Silll'IDOWNS AND POWI R Hl'DilCllONS DOCK ET NO.

50-287 6/15/83 UNIT NAhlE Oconee 3 DAIE 5-15-82 Hl.r O R I h! O N ill APFl'l' 1982 COMPLETED BY J. A. Reavis lELEl'II0NE 704-373-7567 C

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,E-e,

{ ;.

Causc & Currective Disc 5?

4 is5 Even 3, y e?

Attion su fE d

3 ;f, c Hrpos e 8:

vi O E'

Prevent Hecunw.c F

O 6

2 82-04-24 S

163.73 8

1 ZZ ZZZZZZ Steam generator auxiliary feed ring inspection.

End of cycle outage.

NRC NSM's/10 yr.

ISI/ refueling.

l J

.I l

l l.n. cil H ea,..n bicihinl:

Eshibit G. Imtinssiinis S

S. lioli.le.1 A l'quipmeni 12.nhne il splaml I kl.mnal for Pseparation of Dal.a 11 hiaintenm.c in l'es

.t hlan nal Scsa m.

I:nts) Sheels fin I.itcusee r 1(cincluy; 1 Antoin.itw Ss s.un.

Evens Repin g il l'HI file INilRI.G-le Regnl.nin) Itesen.non l Olhes ll.nplahil 011 11 I ( spci.si.n le.unny A 1 iim. I unun. sis. n I A.Inamissanic 5

G 0 vs.in.ui.il 1.nos li spl.nn t E.shihis I Same Sousic r?'ill II Othe II:xplas.i t

~

REVISED llNil Silull) OWNS AND Powlit itElstriloNs DOCKET NO.

50-287 6/15/83 UNIT NAME Oconee 3 isA TE 6-15-82 Itl.rul(I AIONill May, 1982 COMPLETEp ily J. A.

Reavis IELEPIIONE 704-373-7567 1

D

=-

ee

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Et

' c'8 cc E"T' E

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N.. '

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7.

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iS 0 l'acvent llecinsentc d

2 82-05-01 S

.744.00 8

ZZ ZZZZZZ Steam generator auxiliary feed ring modification is in progress.

Er.d of cycle outage continues.

NRC NSM'c/10 yr.

I ISI/ refueling.

I l

2

.I l

i

1. n i c al ite. nun-Mellioil:

Esliibit G-Instruclienn S

S. In ilnie.1 A lipnpanen 1 ailnie Il splaint i M.unut l'os Pacp.uariun iil Data 11 Mainien.ince ne l'est 2-M.a riual Sesa ni.

I:nt:) Slicess lin I.icensee r f(cineling

.l Autoniitic Sisam.

livent Itepint ll l'lti I? le INiliti G-i li itegulatin) Itesen. unn

.l.Othes il.xplain t Oltil l i e spceanos is.unner.t i sirme 1 xanunati..n I d.llnillibl4JilWL' b

G t Ipciation.il I s e..: llipl.nni lisliilus I. Same Sousee l's/ / / l II Olhes Ilimplanel

REVISED UNil SHulDOWNS AND l'UWlit RfuUCHONS NMO-UNil NAhlE Oconee 3 6/15/83 DAIE 7-15-82 Iu.ro n i alo N HI gune, 1982 COSIPLET ED llY J. A. Reavis 1El.ErtlONE 704-373-7567 l

u. 2 S

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F 5 afi g=

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Peeven Itecuncate u

C 2

82-06-01 5

720.00 B

ZZ ZZZZZZ Steam generator auxiliary feed ring modification. Refueling in progress.

End of cycle outage. continues. NRC NSM's; 10 yr. ISI (in service inspec-tion); CSA (core support assembly) bolt replacement.

l l

l I

l l

2

.I

.I I I osi cil Itcainn-Alcolonl:

Egliitne c. Insisucelons S

S. I.uinic.l A l~iinipsnene F.ninie il splain) l M.innal for P,cparasien,og pai,,

i 11 AI.sinienint e os Ics:

,2 A1.sunal Sceaan.

Ents) Slicens fin I.scensee C ltelnclung 5 Ansuntitic Sir.sna.

liveni l<cpini ll f RI l' ele INtlRI G.

la Regnl.is.n> ltesen.ason

.l.oilice ll.n pl.nn i o f geli

~

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G )penassini.il I n..: ll spl.nni Egliiln I.Saine Sontce C'li1)

II Ollieslib pl.su )

E 11 Nil SillllllOWNS AND H)WIIt IlfilUrilONS D

U e 3 DA TE 8-15-82 I 1.roitI blo N ill July, 1982 COSIPLElED llY J. A. Reavis lELErl10NE 704-373-7567 c:

53

'h

_$5'i 1.itensce 3-s, D,

Cause & Curreceive N..

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is&

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fE d

~ y, c Itcpose n in' U E'

Psevent itecunicnce 3

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2 82-07-01 S

744.00 B

ZZ ZZZZZZ Steam generator auxiliary feed ring modification.

Refueling in progress.

End of cycle outage continues. NRC NSM's.

1.0 yr.

ISI (in service inspection) and -CSA (core support assembly) bolt replace-ment have been completed.

I

.I

.I i

1.... cil Itcasun -

hiethuil:

E shibit G - Instanttions S

S. l nh.ic.I A lipnpanen I!.nhne ti sl.lan:)

I hiannal for Psep.uation sil' Data 11 bl.iinienans e in l'es 2-ht.nni.it Sciam.

Ents) Sheets lin 1.icensee C ltes ucimi; 1 Autonolic S(sans.

livent f(cpint ll l'ltil'ile INilitt G-D.Ites;nt.oin) Itc>ns non 1 Othee Ihaplaint ultili I ( spce.stin le.nnmi.i l h imc 1.sannn.ses..n l' A inunisseative 5

G Opcs. :.nial i eine 11Tpl.nni e

E.shilus 1 Same Sontcc l'8/ / / l ll Othei ll.S il.nni t

50-287 DOCK ET NO.

UNITSilull) OWNS AND POWEit REDUCTIONS UNil NA.\\lE oconee 3 DATt 9/9/82 REVISED CO.\\tPLETED ltY 6/15/83 1(1:PO!1T A10NTil August, 1982 EMPl!ONE 9*.::

=

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ch 55:

!(eport :

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g C

2 82-08-01 S

744.00 B

ZZ ZZZZZZ Steam generator auxiliary feed ring modification in progress. End of cycle outage continues. NRC NSM's.

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linery Sliceis l'or I.ieensee C.!t.:(ucting

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I:sent Repos (i.l'It)l de (Ntflit.C.

D. Regulatory itesitiction

-l Ottier (lisplain) 0161) l'-Ope:ator Training & l.rcense lixainination I.Ad.uirnst rative

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0-287 REVISED UN!! Silu1 DOWNS AND POWEll I?EI)UCilONS DOCK!:T NO.

Conee 3 6/15/83 UNil NAMg!

DATg 10-15-82 Rt v 18 8 pol (T.\\lONTis September, 1932 COMI IllIII Y i

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82-09-01 S

720.00 B

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REVISED llNil SisHIDOWNS AND l OWIIt Iti:liucilons DOCKET NO.

50-287 UNIT NAME Oconee 3 6/15/83 DAIE 11/15/82 fil;roit s AIONis, October, 1982 COMI'LETED Igy J. A. Reavis TELEril0NE 704-373-7567

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2 82-10-01 S

11.00 B

ZZ ZZZZZZ End of cycle outage and auxiliary feedwater header work completed.

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-2A 82-10-01 S

57.42 B

ZZ ZZZZZZ Core Physics Testing.

2-P 82-10-04 S

B ZZ ZZZZZZ Power Escalation testing.

l 3-P 82-10-06 S

B ZZ ZZZZZZ Power Escalation testing.

3 82-10-10 F

267.08 A

1 CB HTEXCH Unit shutdown to attempt' to locate steam generator tube leak. Work also completed on pressurizer code relief.

4-P 82-10 F A

CB HTEXCH Holding at various power levels to monitor steam generator tube leak.

5-P 82-10-23 F

A HH PUMPXX 302 heater drain pump out of service.

6-P 82-10-25 F

A HH PUMPXX Ccndensate booster pump out of service for repair of discharge valve.

7-P 82-10-30 F

A CB HTEXCH Reduced power to monitor steam generator tube leak rate.

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A. Re.svis N

lELLPil0NE 704-371-75fe7

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A CB llTEXCH Operating at reduced power levels due to steam generator tube leak.

4 82-11-17 F

313.02 A

1 CB HTEXCH Unit shutdown to-repair steam generator tube leaks.

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OPERATING DATA REPORT DOCKETSO 50-269 DATE 7/I5/83 CONIPLETED BY 3.

3.

h.wis TELEPHONE 70a-373-7567 OPERATING STATUS

1. Unit Name:

Oconce No. I Notes

2. Reporting Period: June 1, 1983 - June 30, 1983 Year-to-date and cumulative

3. Licensed Thermal Power QtW:::

25Ag capacity factors are calcu-laced using a weighted

4. Nameplate Rating (Gross StWep:

934 average for ma:cimum

5. Design Electrical Rating iNec stWe):

886 dependable capacity.

6. Sluimum Dependable C.spacity-(Gross atWep:

800

7. Staximum Dependable Capacity (Net atWe):

860 l

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

None 4

None

9. Power Level To which Restricted. lf Any INet SIWE):

10. Reasons For Restnctions. If Any:

This Stonth Yr..to Date Cumulative

11. Hours In Reporting Period 720.0 4 343.0 87 288.0

12. Number Of Hours Reactor was Critical 15.7 3 633.9 61 300:9

13. Reactor Reserve Shutdown Hours

14. Hours Generstor On.Line 15.6 3 608.5

. -58 191 5

15. Unit Reserve Shutdown Hours 23 343 9 155 900 138 275 587

16. Gross Thermal Energy Cenerated (StWH) 17 Gross Electrical Energy Generated (StWH) 7 810 3 181 070 48 098 980 Is. Set Electrical Energy Genetuted (31WH) 2 790

.3 037 793 45 534 719

19. Unit Service Factor 2.2 83.1 66.7

20. Unit Andsbdity Factor 2.2 83.1 66.7 i

0.5 81.3 60.5

21. Unit Capacity Factor IUsing SIDC Neri

22. Unit Capacity FactorIUning DER Net) 0.4 79.0 58.9

23. Uni Forced Outage Rate 0.0 0.8 18.2-

24. Shutdowns Scheduled Over Next o alonths tType. Date.snd Duration of Eache Currently Refueling 1

l

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

August '18, 1983

26. Units in Test Status Prior to Commereist Operations:

Forecast Achieved.

INITIAL CRITICALITY INITIA L ELECTRICITY.

CO31%t ERCIA L OPER A TION to.-,

o DUKE POWElt Godinuxv l'.O. ISOX !!!!!!!D Cal A14I,OTTE, N.(1. ' il*J 1*J J

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July 15, 1983 g[E((ECIsn Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Document Control Desk Re: Oconee Nuclear Station Docket Nos.

50-269

-270, -287

Dear Sir:

Please find attached information concerning the performance and operating status of the Oconee Nuclear Station for the month of June, 1983.

Also, attached are revised copies of the 1982 unit shutdowns and power reduction sheets.

Very truly yours, C

r /

L

~

Hal B. Tucker JAR:ses Attachments cc: Regional Administrator Mr. J. F. Suermann, Project Manager U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Washington, D. C.

20555 Atlanta, Georgia 30303

/ Mr. Phill Ross INPO Records Center U. S. Nuclear Regulatory Commission Suite 1500 MNBB-5715 1100 Circle 75 Parkway Washington, D. C.

20555 Atlanta, Georgia 30339 g)

Senior Resident Inspector g OB10l g 8

Oconee Nuclear Station gSIG

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