ML20214E433

From kanterella
Revision as of 16:26, 19 January 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Monthly Operating Repts for Apr 1987
ML20214E433
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 04/30/1987
From: Reavis J, Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8705220085
Download: ML20214E433 (19)


Text

_

7 l .

s DFERATIN6 DATA FEPORT DOCKET- 50-269 DATE 5-15-87 CPERATINGSTATUS .COMPLETEDBY- J. A. Reavis TELEPHONE 704/373-7567

1. Unit Name: OCONEE 1
2. Re;orting Period: APRIL 1, 1987-APRIL 30, 1987
3. Licensed Thereal Power (M t): 2568 _ . . . ......
4. Naseplate Rating (6ross Me): 934 l Notes Year-to date and- l
5. Design Electrical Rating (Net Me): 866 I cueulativecapacityfactors: I 6.MaxieueDepenfableCapacity(Gross 899 I are calculated using a weight-l
7. Maxieue Dependable Capacity (Net Me): 860_ i ed average for easinue 1
8. If Changes Occur in Capacity Ratirgs (Itees Number 3 Through 7) Since Last I dependable capacity. 1 Report. Give Reasons. ....., ._________________ l._ ___ _. _ _ _ .I
9. Power Level To Which Restricted, if Any (Net Me): ........ . _ ,_ ... _. ..............., _ ...,_ , _. ..
10. Reason For Restrictions, If any .. _ ,. _ .,_ . _ _ _ _ _ _ _ _ _ _ .. _ ,, _.__ _ , ..

This Month Yr.-to-Date Cueulative

11. Hours in Reporting Period 719.0 2,879.0 120,888.0
12. Nueber Of Hours Reactor Was Critical 719.0 2,574.5 88,969.4
13. Reactor Reserve Shutdown Hours --0-- --0-- --0--
14. Hours Senerator On-Line .719.0 2,563.0 85,565.1

~1 5. Unit Reserve Shutdown Hours - --0-- --0--

16. Gross Thereal Energy Generated ( MH) .1,610,448 6,060,264 206,986,369
17. Sross Electrical Energy Generated ( MH) 552,620 2,088,460 71,862,330
18. Net Electrical Energy 6ererated ( MH) -525,750 1,979,171 68,162,215
19. Unit Service Factor 100.0 89.0 70.9
20. Unit Availability Factor 100.0 89.0 70.8
21. Unit Capacity Factor (Using MDC Net) 85.0 79.9 65.4
22. Unit Capacity Factor (Using DER Net) 82.5 77.6 63.6
23. Unit Forced Outage Rate 0.0 0.0 14.4
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Eachit

. ....gefueling,,_Augu,s.t_y,b_1987 - 8 weeks -

25. If Shut Down At End Of Report Peried. Estiented Date of Startups....... ,_ __ _ _ _ _ _ ..___ _ .
26. Units In Test Status (Prior to Consercial Operation): Forecast Achieved INITIAL CRITICALITY ~ l INITIAL ELECTRICITY [~~~ j COMERCIAL OPERATI0li . ___-

B705220085 870430 r.-~,

'V k

PDR ADOCK 05000269 r q

'R PDR u

-- p\ \ '

AVERASE DAILY UNIT POWER LEVEL, l DOCKET NO 50-269 UNIT Oconee 1 DATE May 15, 1987 COMPLETED J. A. Reavis TELEPHONE 704-373-7567 MONTH AFRIL,1987 DAY AVERASE DAILY F0WER LEVEL DAY AVERAGE DAILY POWER LEVEL-(MWE-Net) (MWE-Net) 1 752 17 729 2 753 18 733 3 750 19 734 4 733 20 730 5 731 21 730 6 729 22 734 7 723 23 733 8 722 24 733 9 722' 25 733 10 720 26 733 11- 718 27 '733

12 727 28 732 13 721 29 732-14 727 30 732 15 727 16 729

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. _5Q:262___________

UNIT NAME __QGQNEE_1________

DATE _g5215282_________

REPORT MONTH _______6gtil_1282_ COMPLETED BY _GER@LQ_REAVIS__1_

TELEPHONE _12g41:373:2562___

(1) (2) (3) (4) (5) l R MET- (

1 E HOD [

T A OF LICENSE I N Y S SHUT EVENT SYS- CAUSE AND CORRECTIVE l 0 P DURATION O DOWN REPORT TEM COMPONENT ACTION TO {

. DATE E HOURS N R/X NO. CODE CODE PREVENT RECURRENCE l 7-p 87 1 Sl -- 1 A -- l' EA TRANSF POWER LIMITED BY SIZE OF REPLACEMENT [

l l TRANSFORMER (

l 8-p 87 3 F --

A --

WB HTEXCH REACTOR BUILDING COOLING UNITS AND (

LOW PRESSURE INJECTION COOLER PROBLEMS I

f 1 (

l I I (

(

l l

i ti) (2)

(3) (4)

F Forced Reason:

S Scheduled Method: Exhibit G- Instructions A-Equipment Failure (Explain) 1-Manual B-Maintenance or test for Preparation of Data C-Refueling 0-Manual Scram Entry Sheets For License D-Regulatory Restriction 3-Automatic Scram Event Report (LER) 4-Other (Explain) File (NUREG-0161)

E-Operator Training & License Examination F-Administrative (5)

G-Operator Error (Explain)

H-Other (Explain) Exhibit I - Same Source

.. ; r s.

DOCKET NO: 50-269 s

UNIT: Oconee.1

' DATE: -5/15/87 NARRATIVE

SUMMARY

Month. April, 1987 Oconee Unit 1 operated at 88% during the entire month, limited in power by the I- capacity of its replacement transformer.

4 i

?

?

i f

1 4

t I

1 i

1 ja l- )

. < . , .m. + , . , ,_

MONTHLY REFUELING INFORMATION REQUEST 1.- Facility name: Oconee, Unit 1

2. Scheduled next' refueling shutdown: August, 1987
3. Scheduled restart following . refueling: October, 1987
4. Will refueling or resumption of operation thereafter require a technical 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 '

Comnittee 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).
7. Number of fuel assemblies (a) in the core: 177 (b) in the spent fuel pool: 917*
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: Augus t, 1991
DUKE POWER COMPANY DATE: May 15, 1987 l

Name of

Contact:

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

  • Represents the combined total for Units 1 and 2.

1 4

_mm.,_., _ . . . . _ . . . . , , - . ,,..-m,7 - , . _ .,,,,%-,.-y. _.

y _,.,m,,,-,r,- , . - , , - . , , , _ . , - - < -,,,,r, -

OPERATING DATA REPORT DOCKET 50-270 DATE 5-15-87 CFERAilh6 STATUS COMPLETED BY .T. A. Reavis TELEPHONE 704/373-7567

1. Ur.it Nase: OCONEE 2
2. Reporting Period: APRIL 1, 1967-APRIL 30, 1987
3. Licensed Thereal Power (Mt): 2568 _ _ .. ..,_ _ _ ____ _.
6. Naseplate Rating (Gross Me): 934 I Notes Year-to date and I 9.CesignElectricalRating(NetMWe): 886 l cueulative capacity factors l ,
6. Maxieue Dependable Capacity (Gross 899 I are calculated using a weight-l
7. Maxieue Dependable Capacity (Net Me): 660 i ed average for saxieue i
8. If Changes Occur in Capacity Ratings (! tees Number 3 Through 7) Since Last I dependable capacity.- I Report. Give Reasons: , , , _ _ _ _ _ , _ , _ _ . ._

'l.,____,___________.I

9. Power level To Which Restricted, If Any (Net Me): , , , , , . . _ _ ......... ... .... ..... .......
10. Reason For Restrictions, if any: _ . . ,_ ..._ ___ _ . _ _ _ _ _ _ _ _ . .

This Month ' Yr.-to-Date Cueulative

11. Hours In Reporting Period 719.0 2,879.0  !!0,808.0
12. Nueber Of Hours Reactor Was Critical 596.8 2,739.9 82,831.1
13. Reactor Reserve Shutdown Hours - --0-- ---0--
14. Hours Generator On-Line 587.5 2,708.6 81,434.5
15. Unit Reserve Shutdown Hours --0-- --0-- --0---
16. Gross Thereal Energy Generated (MWHI 1,246,824 6,497,856 194,786,134
17. Gross Electrical Energy Generated (MH) 432,310 2,241,080 66,374,601
18. Net Electrical Energy Generated (MH) 408,908 2,139,906 63,108,532
19. Unit Service Factor 81.7 94.1- 73.5
20. Unit Availability Factor 81.7 95.1 -73.5
21. Unit Capacity Factor (Using MDC Net) 66.1- _8e.4 66.1
22. Unit Capacity Factor (Using DER Net) 64.2 _83.9 64.3
23. Unit Forced Datage Rate _

18.3 5.9 12.6

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

.. . R 91M .... .. .....- ._ . . . . . . . - . . - - . . - - - . . . . . . . . . . -

250 if Shut Down At End Of Report Period. Estinated Date of Startups. _ , _ __ _ _ ,......., _ __.. _ ....... .,_ _ ,..

26. Units In Test Status (Prior to Coseercial Operation): Forecast Achieved INITIALCRITICALITY . . . . .

-INITIAL ELECTRICITY .. _ ... ..

COMMERCIAL O'ERATION _.. ..... ._

p 'l ,= -

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-270

' UNIT Oconee 2 DATE May 15, 1987 COMPLETED - J. A. Reavis TELEPHONE _ 704-373-7567 MONT}i AFRIL,1987

. DAY AVERAGE CAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net) (MWE-Net) 1 656 17 740 2 556- 18 - 738 3- 662 19 - 733 4 639 20 149 5 638 21 652 6 540 22 .765 7 0 23 743-6 0 24 741 9 0 25 742

. ........ . .... z.-- .....

.10 0 26 743-

~11 93 27 742 12 723 28 742 13- 733 29 - 743

. .= .......... - . . . ....

14 733 30 741

-15 733 16 732

y UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-270 Pigs 1 of 2 UNIT NAME [dhdhkh[h~~______ _

DATE _05/15/87________.

REPORT MONTH _______Agtil_1282_ COMPLETED BY _ GERALD _REAVIS____

TELEPHONE __(7_ 0__ 4 _) _ 3_ 7__ 3_ - 7 5_ 6_ 7_ _ _ _ q

, I (1) (2) -(3) (4) (5) l l R MET-( l E HOD T A , OF LICENSE N Y S l SHUT EVENT SYS- CAUSE AND CORRECTIVE O l P DURATION O DOWN REPORT TEM COMPONENT ACTION TO

,l . DATE E HOURS N R/X NO.  ; CODE CODE PREVENT RECURRENCE 8-p 87 1 F --

A --

HB HTEXCH HIGH FEEDWATER FLOW IN *2A' STEAM-GENERATOR l.

l 9-p 87 1 F --

B --

SF HTEXCH LOW PRESSURE INJECTION COOLER HEAT TRANSFER EVALUATIONS 10-p 87 1 F --

B --

l SF HTEXCH LOW PRESSURE INJECTION COOLER HEAT l TRANSFER EVALUATIONS 11-p 87 2 F --

B --

l SF HTEXCH LOW PRESSURE INJECTION' COOLER HEAT l l TRANSFER EVALUATIONS 12-p 87 3 F --

A --

SF HTEXCH -LOW PRESSURE INJECTION' COOLER AND RX BUILDING COOLING UNIT PROBLEMS 4 87 6 F 114.42 B 4 SF HTEXCH HEAT TRANSFER TEST ON 'A' LOW PRESSURE INJECTION COOLER

l i I
(1) (2) (3) (4)

F Forced- Reason: Method: Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for, Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For Licensee C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain) File (NUREG-Ol61)

E-Operator Training & License Examination F-Administrative (5)

G-Operator Error (Explain)  : Exhibit I - Same Source H-Other (Explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-270 UNIT NAMEL__QCQNEE_2________:

P:ge 2 of 2 DATE _Q5415L@2_________.

REPORT MONTH _______Agt11_12@2_ COMPLETED BY _GgRALQ_REAVI@____

TELEPHONE _12941-323-2562___

l (1) (2) ,(3) (4) (5)

R MET-E HOD T A OF LICENSE l l-N Y' S SHUT EVENT SYS- CAUSE AND CORRECTIVE D P DURATION O DOWN! REPORT TEM . COMPONENT I ACTION TO

. DATE E HOURS N R/X NO. CODE : CODE l PREVENT RECURRENCE 13-p 87- 4-12 F --

lA --

CH HTEXCH HIGH LEVEL IN *B' -STEAM GENERATOR 14-p l 87- 4-12 Fl --

A --

CH HTEXCH HIGH LEVEL IN 'B STEAM GENERATOR S 87- 4-20 F 17.12 A 3 .CH HTEXCH HIGH LEVEL IN 'B' STEAM GENERATOR' l.

I 15-p 87- 4-21 F --

A --

CH l HTEXCH HIGH LEVEL IN *B' STEAM GENERATOR l' l.

I I I i

i I i

I I

i i

I

.(1) (2)- ~ (3) (4)

F Forced Reason: Method: Exhibit G - Instructions.

S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For Licensee-

-C-Refueling '3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)J File (NUREG-0161)

E-Operator Training & License Examination F-Administrative (5)

G-Operator Error (Explain) Exhibit I - Same Source

~ '

H-Other (Explain)

'f .

DOCKET NO: 50-270 UNIT: Oconee 2 -

DATE: 5/15/87 NARRATIVE

SUMMARY

Month: April, 1987 Oconee Unit 2 began the month at 86% power. On 4/06 at 2230, the unit.was taken off line to test its Reactor Building Cooling units. The unit returned to service on 4/11 at 1655 and operated at 86%~until it tripped on 4/20 at 0533.

The trip was due to the failure of a control module associated with the Steam Generators. The unit was placed on line at 2240 on 4/20 and returned'to 86%

power.

l r

. l l

t i

MONTHLY REFUELING INFORMATION REQUEST

1. Facility name
Oconee, Unit 2
2. Scheduled next refueling shutdown: January, 1988 j 3. Scheduled res' tart following refueling: March, 1988-l .
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes

}

! If yes, what will these be? Technical Specification Revision 1

-If no, has. reload design and core configuration been reviewed by Safety Review f

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.

I unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

i i

i 7. Number of fuel assemblies (a) in the core: 177 '

j (b) in the spent fuel pool: '917*

j

, 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 j capacity
August, 1991 1

b b

i.

I i

i i

I l

t i

i

DUKE POWER COMPANY DATE
May 15, 1987 li Name of

Contact:

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

,

  • Represents the combined total for Units 1 and 2.

l l

- , _ . , , ~ . . , _ _ , . . . _ - _ _ . . - - - _ _ _ , . - , _ _ . . . . . _ _ , . , , _ , . . _ - _ . . - , _ , - , . . _ _ .

rr-OPERATING DATA REPORT DOCKET 50-287 DATE S-15-87 OPERai!NS STATUS COMPLETED BY J. A. Reavis TELEPHONE 704/373-7567

1. Unit Nase: OCONEE 3 -------------
2. Reportirg Period: APRIL 1, 1987-APRIL 30, 1987
3. Licensed Thereal Power (Mt): 2568 . ..._ ._ _ .. _ .. _ _ _,_
4. Naseplate Rating (6ross Me): 934 i Notes Year-to date and i
5. Design Electrical Rating (Net Me): 886 l cueulative capacity factors 1
6. Maxicas Dependable rapacity (Gross 899 i are calculated using a neight-i ,
7. Marleue Dependable Capacity (Net Me): 260 I ed average for easieue 1
8. If Changes Occur in Capacity Ratings (! tees husber 3 Through 7) Since Last. I dependable capacity. I Report. Give Reasons _ . . . . . . . . , _ , , , _ , , , _ _ _ , _ _ _ _ _ , , , _ _ _ _ _ _ , . 1,____,,,,_ __ ... . ....., _ I
9. Power Level To Which Restricted, if Any (Net Me): , , , , , , , , , , , , . . . . , _ , _ _ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , , , , , , _ , _
10. Reason For Restrictions, if ary: _ ,,_ _ _ _ ,,_ ,,_ _ _ _ _ , _ ,_ ,_,_ _ ,,,,_ _ _ ,,,,,,,_ ,, _ _ _ _ _ , _ ,,,

This Month Yr.-to-Date. CueulatlYe

!!. Hours In Reporting Period 719.0 2,879.0 108,455.0

12. Nueber Of Hours Reactor Was Critical 252.8 304.7 77,511.4
13. Reactor Reserve Shutdown Hours - --

0-

14. riours Generator On-Line 234.6 235.3 76,150.5 19.UnitReserveShutdow, Hours - - -

0--

16. Gross Thereal Energy 6ererated ( MH) 480,720 483,192 185,930,302
17. Gross Electrical Energy Generated ( M ) 165,906 166,266 64,047,340
18. Net Electrical Energy Generated ( MH) 152,133 142,678 60,986,341
19. Unit Service Factor 32.6 8.2 70.2 20.iinitAvailabilityFactor 32.6 8.2 70.2
21. Unit Capacity Factor (Using NOC Net) 24.6 5.8 . 65.3
22. Unit Capacity Factor (Using DER Net) 23.9 5.6 63.5
23. Unit Forced Outage Rate 43.2 43.2 14.0
24. Shutdowns Scheduled Over Heat 6 Months (Type, Date, and Duration of Each):

.......KQDq................................................................

23. If Shut Down At End Of Report Period. Estiested Date r,f Startups... Jjay,L ,M7,,,____,,,,,,,,,__,,,,,_,,,,
26. Units in Test Status (Prior to Coseercial Operation): Forecast Achieved INit!AL CRITICALITY _ ,,,, . , , , , _ , ,

INITIAL ELECTRICliY ,__... _ , _ , ,

COPMERCIAL OPERATION ____. , _ , _ ,

i

)

i L ..______._______._____________._______._____.____________________.._____

y AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-287 UNIT Cconee 3 DATE May15,1987 COMPLETED J. A. Reavis TELEPHONE 704-373-7567 MCNTH APRIL,1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERASE DAILY F0WER LEVEL (MWE-Net) (MWE-Net) 1 0 17 675 2 0 18 850 3 0 19 854 0 0 20 856 5 0 21 858 ~

6 0 22 854 7 0 23 639 8 0 24- 0 9 0 25 0 10 0 26 0 I1 0 27 0 12 0 28 0 13 0 29 0 14 208 30 0 15 110 16 550 I

A _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ . _ . _ . _ _ _ _ _ _ _ _ . . _ . _ _ . _ . _ _ _ _ _ . . _ . __ m _ _. _. _ _ _

4.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-287 UNIT NAME __QGQNgg_3________

l Pa8i i cf 2 DATE 05/15/87 -

r

( REPORT MONTH _______Agt11_1282_ COMPLETED BY [hhhh(h_hhh5[h_ ~~_ _

j TELEPHONE _1704),--373-7567___ g 1 . . . . .

'l l l(1)l l(2) (3) l i (4) (5) .l lR MET-l l l l l -l l l l l lE HOD l i ' l-

,l l lT l lA OF LICENSE l 'l l N l lY l lS SHUT EVENT l SYS-l CAUSE AND CORRECTIVE l l 0 l P ! DURATION l'O DOWNl REPORT ,

TEM l COMPONENT , ACTION TO - l-ll . l DATE E HOURS 'N R/X l NO. l CODE CODE PREVENT RECURRENCE

!l 2 87 1 lS l 300.93 lB 4 HA GENERA GENERATOR BEARING VIBRATION l l l l l (ll 3' l 87- 4-13 lS l 4.78 lB 4 HA TURBIN TURBINE OVERSPEED TRIP TEST l l l  !

1-p l 87- 4-14 lS l --

lB l -- IE INSTRU NI CALIBRATION

'l l l l l l l

'l2-p l 87- 4-14 lF l --

lA -- , HA INSTRU POWER INCREASE HELD'DUE TO Z-PHASE l l l l l l CAPACITOR PROBLEMS l l l 'l 4 l 87- 4-15 F 8.38 A 4 HA INSTRU l Z-PHASE CAPACITOR PROBLEMS (RX l l l l CRITICAL) -l l l l l I l l l l l l3-P l 87- 4-15 lF l --

lA l -- l l HH PIPEXX l FEEDWATER LINE. WELDING WORK l l l l l l l l l 4-p l 87- 4-16 Sl --

lB l -- l IE INSTRU NI CALIBRATION l-l l l l l l l l 5-p l 87- 4-16 S --

lB l -- RC ZZZZZZ FLOW MEASUREMENTS l l l l l l l l l l l l l I i

'(1) (2) (3) (4)

F Forced ' Reason: Method: Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For LicenseG C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain) File (NUREG-Ol61)~

E-Operator Training & License Examination F-Administrative (5)

G-Operator Error (Explain) Exhibit I - Same Source:

H-Other (Explain)

J M-i .

UMIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-287 -

UNIT NAME __QCQNEE_3___

Page 2 of 2 DATE _Q5415f@2________L REPORT MONTH _______Agri_1_1997_ COMPLETED BY _GERALQ_REAVIg____q TELEPHONE _1294 )--323-2562___ ]

l I i(1): i(2)l(3) i i(4) . (5) i I I L IR IMET-l' I l 1 I I I E l HOD I i i iT I A OF LICENSE I N I IY I IS SHUT EVENT SYS- CAUSE AND CORRECTIVE O I IP I DURATION 10 IDOWN REPORT TEM COMPONENT ACTION.TO

. I DATE IE HOURS IN R/X NO. CODE CODE PREVENT RECURRENCE l  ! l I 6-p I 87- 4-16 SI --

B . -- I l RC INSTRU l POWER ESCALATION TESTING I I I I i 7-p i 87- 4-17 . SI --

B l -- IE INSTRU NI CALIBRATION l l 1 8-p 87- 4-17 S --

B --

RC 222222 REACTOR COOLANT SYSTEM FLOW DATA I I l1 9-p I 87- 4-23 iF . I --

LA --

CH HTEXCH I STEAM GENERATOR TUDE. LEAK I ll l 1 I I I ll 5 I 87- 4-23 iF i 170.2B Ai 1 CH HTEXCH STEAM GENERATOR TUBE LEAK

!I I I I i i i i i i l i l i i I i i i i II i L i ii l i I I l l l 1 1 I I I I I i l-

'I I I I I I I I I I .I I I I I I I l il i i I i i i I ll l l I I I I I l (1) (2) (3) (4) l F Forced Reason: Method: Exhibit G - Instructions l S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data l B-Maintenance or test 2-Manual Scram Entry Sheets For Licensec l C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain; File (NUREG-0161)

E-Operator Training & License Examination F-Administrative (5)

G-Operator Error (Explain) Exhibit.I Same Source H-Other (Explain) l L

, _, ,=--

s i-DOCKET NO: 50-287 UNIT: Oconee 3 DATE: 5/15/87' i

NARRATIVE

SUMMARY

Months' Apr11, 1987 i

I Oconee Unit 3 began the month in an outage to correct vibratiion problems with 4 the electrical generator. The unit was placed on line oit 4/13 at'1356, but was shutdown at.0144 on 4/15 when problems developed on the Z-phase of the

j. electrical generator. The unit returned to service on 4/15 at 1009 and held power while repairs were made to a feedwater line. Full power was attained at j 0400 on 4/17 and the unit operated at that level until 4/23'at-2143.when the 4

j .

unit was shutdown to repair a Steam Generator tube leak. The unit remained off line for the rest of the month.

i

f 1

t S

1 I

t

~

a MONTHLY REFUELING INFORMATION REQUEST 1.- Facility name: Oconee, Unit 3

2. Scheduled next refueling shutdown: August, 1988
3. Scheduled restart following refueling: November, 1988
4. Will refueling or resumption of operation thereafter require a technical 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 in design or new operating procedures).
7. Number of fuel assemblies (a) in the core: 177 (b) in the spent fuel pool: 529
8. Present licensed fuel pool capacity: 875 Size of requested or planned increase: ---
9. Projected date of last refueling which can be accommodated by present licensed capacity: August, 1991 i DUKE POWER COMPANY DATE: May 15, 1987 Name of

Contact:

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

, - e i

OCONEE~ NUCLEAR. STATION MONTHLY OPERAUNG STATUS REPORT

1. Personnel Exposure For the month of March, no individual (s) exceeded 10 percent of their allowable annual radiation dose limit.
2. The total station liquid releare for March has been compared with the Technical Specifications maxinna annual dose commitment and was less than 10 percent of this limit.

The total station gaseous release for March has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

4 4

I I

7 s

i

?: . . ,

I e

DUKE POWER COMPANY P.O. box 33189 CHARLOTTE, N.C. 28242 HAL B. TUCKER TELEPHONE ma rammanent. (704) amp 4 sat swetsaa ruonecreen May 15, 1987'"

U. S. Nuclear. Regulatory Commaission Atte_ntion: ' Document Control Desk Washington, D. C. 20555 ,

Re:',Oconee Nuclear Station ,

' Docket No. 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 April,1987.

Very truly yours, W

Ha1 B. Tucker JAR /20/sbn Attachment-xc: Dr. J. Nelson Grace, Regional Administrator American' Nuclear Insurers ,

U. .S. Nuclear Regulatory Coussission c/o Dottie Sherman, ANI Library -I Region II The Exchange, Suite 245 101 Marietta Street, NW, Suite 2900 270 Farmington Avenue Atlanta, Georgia 30323 Farmington, CT 06032 Mr. Phil Ross -INPO Records Center U. S. Nuclear Regulatory Commission Suite 1500 MNBB-5715 1100 circle 75 Parkway.

Washington, D. C. 20555 Atlanta, Georgia 30323' Ms. Helen Pastis, Project Manager . Ms.-Judy Dovers-Office of Nuclear Reactor Regulation- Nuclear. Assurance Corporation U. S. Nuclear: Regulatory Commission 5720 Peachtree Parkway Washington, D. C. -20555 Norcross, Georgia 30092 Mr. J. C. Bryant NRC Resident Inspector Oconee Nuclear Station

- t

.