ML20206C213
ML20206C213 | |
Person / Time | |
---|---|
Site: | Oconee |
Issue date: | 05/31/1986 |
From: | Reavis J, Tucker H DUKE POWER CO. |
To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
References | |
NUDOCS 8606190392 | |
Download: ML20206C213 (19) | |
Text
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OPERATING DATA REPORT DOCKET NO. 50-269 DATE 06/13/86 COatPLETED BY J.A. Reavis TELEPHONE 704-373-7567 OPERATING STATUS
- 1. Unit Name: Oconee 1 Notes
- 2. Reporting Period: May 1. 1986-May 31. 1986 Year-to-date and cumulative
- 3. Licensed Thermal Power (31Wr): 2568 capacity factors are calcu-
- 4. Nameplate Rating (Gross 31We): 934 lated using a weighted.
886 average for maximum
- 5. Design Electrical Rating (Net $1We): .
899 dependable capacity
- 6. Staximum Dependable Capacity (Gross alWe):
- 7. Staximum Dependable Capacity (Net 51We): 860
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
None
- 9. Power Level To Which Restricted,if Any (Net 5fWe): Now
- 10. Reasons For Restrictions,if Any:
This 51onth Yr..to.Date Cumulative
- 11. Hours In Reporting Period 744.0 3 623.0 112 872.0
- 12. Number Of Hours Reactor Was Critical 414.2 1 454.9 81 901.2
- 13. Reactor Reserve Shutdown Hours ---
- 14. Hours Generator On.Line 366.1 1 395.6 78 525.2
- 15. Unit Reserve Shutdown Hours ----
- 16. Gross Thermal Energy Generated (>lWH) 732 805 3 357 096 189 657 296
.17. Gross Electrical Energy Generated (MWH) 251 430 1 166 380 65 913 220
- 18. Net Electrical Energy Generated (31WH) 230 269 1 093 360 62 491 609
- 19. Unit Service Factor 49.2 38.5 69.6
- 20. Unit Availability Factor 49.2 38.5 69.6
- 21. Unit Capacity Factor (Using.ilDC Net) 36.0 M1 64.2 1
- 22. Unit Capacity Factor (Using DER Net) 34.9 34.1 62.5
- 23. Unit Forced Outage Rate 42.7 16.9 14.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each t: '
Mnno
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation): '
Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION k
n (0/77) e j
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-269 UNIT Oconee 1 DATE 6/13/86 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567 MONTH May. '986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Ne t) 1 17 ---
2 ---
18 ---
3 ---
19 ---
4 ---
20 ---
5 78 21 ---
6 251 22 ---
7 469 23 ---
8 487 24 ---
9 148 25 ---
10 156 26 ---
11 595 27 193 12 844 28 848 13 857 29 818 14 859 30 851 15 847 31 847 16 696 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
O
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-269 .
UNIT NAME Oconee 1 .
DATE 6/13/86 !
PAGE 1 REPORT MONTH May, 1986 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567 "s. O c o o,$ License y Cause & Corrective 87 "c v5E
- 8 Action to No. Date %
%h ES 5l E
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%5b Event h gm, 5B H o- a: zmo Report # EE mu oo Prevent Recurrence 3 86-05-01 S 104.87 A 4 HA TURBIN Outage Extension Due to Increased Scope of Turbine Inspection & Repair 4- 86-05-05 S 0.85 B -
HA TURBIN Turbine Emergency Overspeed Trip Test (Reactor Critical) 11-p 86-05-05 F --
B -
IB INSTRU Nuclear Instrumentation Calibration 12-p 86-05-06 S --
B -
RC FUELXX Low Power Physics Test 13-p 86-05-06 F -
A -
HA INSTRU Integrated Control System Rupback Due to Loss of Stator Coolant Alarm 14-p 86-05-06 F --
A -
HA INSTRU Integrated Control System Runback Due to Loss of Stator Coolant Alarm 15-P 86-05-06 F --
A -
IB INSTRU Power Range Recorder Problem 16-p 86-05-07 F -
A -
HH PUMPXX Low Condensate Booster Pump Suction i Pressure 17-P 86-05-07 S --
B -
RC FUELXX Power Escalation Testing 18-p 86-05-08 F --
A -
RC INSTRU Reactor Coolant System Leakage 1 2 3 4 FF e Reason: Method: Exhibit G - Instructions ed A-Equipnent 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 (NtREG-0161)
E-Operator Training 4 License Examination F-Adninistrative 5 G-Operational Error (Explain) Exhibit I - Same Source H-Other (Explain)
(0/77) . .. .- _ .-. . . . - -
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET N0. 50-269 -
UNIT NAME Oconee 1 DATE 6/13/86 REPORT MONTH May, 1986 COMPLETED BY J. A. Reavis p '
TELEPHONE 704-373-7567 "sO c '$ en$ License y Cause & Corrective 32 "c v5E
- 8 No. Date % %h g 3g Event pr, go, Action to H
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%Sb Emo Report # E'8 mu 53 ou Prevent Recurrence l 5 86-05-09 F 11.12 A 1 RC INSTRU Reactor Coolant System Leakage Outage Due l to LenLing Pressure Transmitter 6 86-05-10 F 7.78 A 3 HH PUMPXX Loss of Condensate Booster Pump Suction Pressure 19-p 86-05-11 F --
B -
RC ZZZZZZ Record Reactor Coolant System Leakage 20-p 86-05-11 F --
B -
IB INSTRU Nuclear Instrumentation Calibration 21-p 86-05-11 F --
A -
HH PUMPXX "E" Heater Drain Pump Problems 22-p 86-05-12 F --
A -
HB PIPEXX Steam Leak on Second Stage Reheater Drain Tank Metering Run 23-p 86-05-15 S --
B -
RC ZZZZZZ Moderator Temperature Coefficient Test 24-p 86-05-16 F --
A -
RC INSTRU Reactor Limiter Problem 7 86-05-16 F 253.30 A 1 CC HTEXCH One Thru Steam Generator Tube Leak 25-p 86-05-27 F --
A -
HH VALVEX Steam Leak on Heater Drain Valve "HD-92" 26-p 86-05-29 F --
A -
HA TURBIN High Vibration on Turbine Bearing "#12" 27-p 86-05-29 F --
A -
HH PUMPXX Heater Drain Pump "lE2" Trip l 28-p 86-05-31 S --
B -
RC ZZZZZZ Reactivity Coefficients at Power Test 1 2 3 4 Reason: Method: Exhibit G - Instnictions I
S led A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensec l C-Refueling 3-Automatic Scram Event Report (LER) l D-Regulatory Restriction 4-Other (Explain) File (NUREG-0161) l E-Operator Training 6 License Examination F-Achinistrative 5 I G-Operational Error (Explain) Exhibit I - Same Source l H-Other (Explain) l(o/771
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DOCKET NO: 50-269 UNIT: Oconee 1 ,
' DATE: 6/13/86 i
NARRATIVE
SUMMARY
Month: May, 1986
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Oconee Unit I returned to service from its ReYueling and Main Turbine Outage j on May 5, 1986. The unit encountered an Unidentified Leakage problem on May 8.
This placed the unit in a Limiting Condition for Operation. The leakage was identified as coming from instrument taps on the Reactor Coolant System. This allowed the unit to close out the LCO but a shutdown was initiated to repair the a
leaks. The unit returned to service on May 9, but on May 10, the unit tripped j due to the loss of the Condensate Booster pumps. That caused the Main Feed
- pumps to trip which caused a Turbine / Reactor trip. The unit returned to service
- on May 10 and increased power to 100%. The unit was shttdown on May 16 to plug '
leaking tubes in Steam Generator "B". Tube plugging was completed on 5/21'and
{ heatup to operating temperature and pressure began on'May 22. On May 23, a i
j leaking manway was discovered on "A" Steam Generator. A cooldown was initiated
- to allow repairs. The unit returned to service on May 27 and was at 100% on i
1 May 28. On May 29, the unit reduced power after detecting a high vibration
] on the number 12 Turbine bearing. A detector was found to be faulty and was replaced. The unit returned to 100%'and operated at that level for the balance of the month.
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MONTHLY REFUELING INFORMATION REQUEST i
- 1. Facility name: Oconee, Unit 1 i
- 2. Scheduled next refueling shutdown: ---
i
- 3. Scheduled restart following refueling:
- 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 '
i If no, has reload design and core configuration been reviewed
] by Safety Review Committee regarding unreviewed safety l questions? N/A
{ i
- 5. Scheduled date(s) for submitting proposed licensing action and )
l supporting information: N/A j i !
] 6. Important licensing considerations (new or different design or [
j supplier, unreviewed design or performance analysis methods, j significant changes in design or new operating procedures). [
- 7. Number of fuel assemblies (a) in the core: 177
! (b) in the spent fuel pool: 967* l l -
! 8. Present licensed fuel pool capacity: 1312 Size of requested or planned increase- E l
l 9. Projected date of last refueling which can be accommodated by ;
present licensed capacity: August, 1991 i I
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t DUKE POWER COMPANY DATE: June 13, 1986 Name of
Contact:
J. A. Reavis Phone: 704-373-7567 ;
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CRepresents the combined total for Units 1 and 2. l t
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OPERATING DATA REPORT DOCKET NO. 50-270 DATE 06/13/86 CO.\lPLETED BY J.A. Reavis TELEP110NE 704-373-7567 OPERATING STATUS oc nee 2 Notes
- 1. Unit Name:
- 2. Reporting Period: May 1. 1986-May 31, 1986 Year-to-date and cumulative
- 3. Licensed Thermal Power (MWt): 2568 capacity factors are calcu-
- 4. Nameplate Rating (Gross 31We): 934 lated using a weighted
- 5. Design Electrical Rating (Net 31We): 886 average for maximum
- 6. Statimura Dependable Capacity (Gross 31We): 899 dependable capacity.
860
- 7. Maximum Dependable Capacity (Net SIWE):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
None
- 9. Power Lesel To which Restricted.lf Any (Net alWe): None
- 10. Reasons For Restrictions. If Any:
This alonth Yr..to.Date Cumulatiye i1. Ilours in Reporting Period 744.0 3 623.0 102 792.0
- 12. Number Of flours Reactor Was Critical 744.0 3 614.9 76 452.6
- 13. Reactor Reserve Shutdown flours --- ---
- 14. Ilours Generator On.Line 744.0 3 601.9 75 203.4
- 15. Unit Resene Shutdown liours --- ---
- 16. Gross Thermal Energy Generated (31WII) 1 906 894 9 194 878 179 598 781
- 17. Gross Electrical Energy Generated (31Wil) 642 200 3 131 160 61 183 501
- 18. Net Electrical Energy Generated (31Wil) 614 568 2 998 134 58 165 695
- 19. Unit Service Factor 100.0 99.4 73.2
- 20. Unit Availability Factor 100.0 99.4 73.2 96.1 96.2 65.6 '
- 21. Unit Capacity Factor (Using alDC Nety
- 22. Unit Capacity Factor (Using DER Net) 93.2 93.4 63.9
- 23. Unit Forced Outage Rate 0.0 . 0.6 13.3
- 24. Shutdowns Scheduled Oser Next 6 Months i fype. Date.and Duration of Each t:
Refueling - August 14, 1986 - 9 weeks
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status iPrior to Commercial Operation): Forecast Achiesed INITI \ L CRITICA LITY INITIAL ELECTRICITY CO\1MERCIAL OPER AIlON (9/77)
AVERAGE DAILY UNIT POWER LEUEL DOCKET NO. 50-270 UNIT Ocnnee 2 DATE 6/13/86 COMPLETED BY J.A. Reavis TELEPHONE 704-373-7567 s
MONTH. Mav. 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Ne t) 1 828 17 827 2 g2s 18 829 3 R?n 19 830 4 825 20 830 5 824 21 829 6 824 22 825 7 827 23 825 8
827 24 825 9 810 25 822 i
10 824 4
26 822 11 828 27 824 12 827 ,
28 829 13 829 29 828 14 829 30 828 4
15 829 31 829 16 827 INSTRUCTIONS On in the thisreporting format, list the average daily unit power level in MWe-Net for each day month. Compute to the nearest whole megawatt.
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET N0. 50-270 UNIT NAME oconee 2 .
DATE 6/13/86 REPORT MONTH May, 1986 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567 "s.
o e 't; o,$ License y Cause & Corrective ,
S7 "cg oSE Event "&'r E Action to NO. Date ~. #h 3g y, p, i
E H; EE o-E a:
%5b
- it m o Report # EE mo 83 uo Prevent Recurrence 24-P 86-05-01 F --
A -
HH HTEXCH Second Stage Reheater Valved Out 25-p 86-05-09 S --
B -
CC VALVEX Control & Stop Valve Movement PT's 26-p 86-05-09 F --
A -
HH HTEXCH Second Stage Reheater Valved Out i
i 1 2 3 4 .
Reason: Method: Exhibit G - Instructions S led 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-0161)
E-Operator Training 4 License Examination F-Adninistrative 5 G-Operational Error (Explain) Exhibit I - Same Source H-Other (Explain)
' (4 /7 71
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DOCKET NO: 50-270 UNIT: Oconee 2 DATE: 6/13/86 NARRATIVE
SUMMARY
Month: May, 1986 Oconee Unit 2 operated at 100% all month except for a reduction to test its Control and Stop valves and Control Rod Drives. The unit operated at a 2
slightly reduced megawatt output throughout the month due to Moisture-Separator j Reheater problems.
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MONTHLY REFUELING INFORMATION REQUEST
- 1. Facility name: Oconee, Unit 2
- 2. Scheduled next refueling shutdown: August, 1986
- 3. Scheduled restart following refueling: October, 1986
- 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: 967*
- 8. Present licensed fuel pool capacity: 1,312 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: June 13, 1986 Name of
Contact:
J. A. Reavis Phone: 704-373-7567 CRepresents the combined totals for Units 1 and 2.
4
t OPERATING DATA REPORT DOCKET NO. 50-287 DATE 06/13/86 CO5IPLETED BY J.A. Reavis TELEPHONE 704-373-7567 OPERATING STATUS
- 1. Unit Name: oconee 3 *W te5
- 2. Reporting Period: .May 1, 1986-May 31, 1986 Year-to-date and cumulative
- 3. Licensed Thermal Power (31Wt): 2568 capacity factors are calcu-
- 4. Nameplate Rating (Gross SIWE): 934 1ited using a weighted _
- 5. Design Electrical Rating (Net SIWE): 886 a. wage for masum
- 6. Staximum Dependable Capacity IGross alWe): 899 dependable capacity.
- 7. 5faximum Dependable Capacity (Net SlWe): 860 i
S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
None l
1 None
- 9. Power Level To which Restricted. If Any (Net alWe):
1 10. Reasons For Restrictions,if Any:
4 l
l This .\lonth Yr. to.Date Cumulative II. Hours In Reporting Period 744.0 3 623.0 100 439.0
- 12. Number Of Hours Reactor Was Critical 744.0 3 619.8 72 991.2
- 13. Reactor Reserve Shutdown Hours --- --- ---
- 14. Hours Generator On Line 744.0 3 599.3 71 731.8
- 15. Unit Rewie Shutdown Hours --- --- ---
- 16. Gross Thermal Energy Generated (51WH) 1 849 576 9 104 895 175 773 341
- 17. Gross Electrical Energy Generated (SIWH) 631 820 3 146 510 60 674 564
' 18. Net Electrical Energy Generated (SIWH) 604 412 3 016 352 57 795 709
- 19. Unit Service Factor 100.0 99.4 71.4 l
- 20. Unit Availability Factor 100.0 99.4 71.4
- 21. Unit Capacity Factor (Using .\tDC Net) 94.5 96.8 66.8
- 22. Unit Capacity Factor (Using DER Net) 91.7 94.0 65.0 l~ 23. Unit Forced Outage Rate 0.0 0.7 13.9 ;
- 24. Shutdowns Scheduled Over Next 6.\lonths (Type. Date.and Duration of Eacht:
None i
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior o Commercial Operation): Forecast '
Achieved INITIA L CRITICALITY INITIAL ELECTRICITY CO\l.\lERCIAL OPERATION i
1 (9[771 l
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. i AVERAGE DAILY UNIT POWER LEVEL s
DOCKET NO. 50-287 UNIT oconee 3 DATE 6/13/86 COMPLETED BY J.A. Reavis TELEPHONE 704-373-7567 MONTH May, 1986 i
DAY AVERAGE DAILY PCWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t) (MWe-Ne t) 1 851 17 840 2 773 18 839 3 266 19 838 4 842 20 839 5 852 21 838 6 851 22 837 7 852 23 816
, 8 852 24 831 9 851 25 830 10 852 26 829 11 851 27 830 12 850 28 730 l
13 848 29 776 14 845 30 827 15 843 31 767 16 842 l
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i INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
1
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. so_287 -
UNIT NAME oconee 3 .
DATE 6/13/86 REPORT MONTH May. 1986 COMPLETED BY J. A. Reais TELEPHONE 704-373-7567 "sO c O cnj License y Cause & Corrective S7 "co v5E "'
3 Action to N3. Date % %h jg Event ,Be, go,
$ o~
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%5o Emo Report # EB mo 8B oo Prevent Recurrence 9-p 86-05-02 F --
A -
HB PIPEXX Repair Moisture Separator Drain Tank Drain Line Leak 10-p 86-05-03 F --
A -
RC FUELXX Imbalance Problems 11-p 86-05-04 F --
B -
IB INSTRU Nuclear Instrumentation Calibration 12-p 86-05-23 S --
B -
CC VALVEX Turbine Valve PT's 13-p 86-05-28 F --
A -
HC HTEXCH Condenser Tube Leak 14-p 86-05-29 F -
A -
RB CONROD Control Rod Imbalance 15-p 86-05-31 F -
A -
HH PUMPXX "3D1" Heater Drain Pump Trip Due to Valve "3HD-218" Not Fully Closing 1 2 3 4 Reason: Method: Exhibit G - Instructions S led A-Equipment Failure (Explain) 1-Manual for Pre wration of Data B-Maintenance or Test 2-Manual Scram Entry Swets for Licensee C-Refueling 3-Automatic Scram Event Report (LER)
D-Regulatory Restriction 4-Other (Explain) File (NUREG-0161)
E-Operator Training 6 License Examination F-Ahinistrative 5 G-Operational Error (Explain) Exhibit I - Same Source H-Other (Explain)
(0177)
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DOCKET NO: 50-287 i UNIT: Oconee 3 DATE: 6/13/86 NARRATIVE
SUMMARY
Month: May, 1986 Oconee Unit 3 began the month at 100% power. On May 2, the unit reduced power to 20% so that a moisture separator drain tank line could be repaired. The unit returned to 100% on May 4. On May 28, the unit reduced power to 75% because of Main Condenser tube leaks which caused Secondary Chemistry to exceed specifications.
The leak was plugged and the unit returned to 100% on May 29. The unit operated at 100% for the balance of the month.
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MONTHLY REFUELING INFORMATION REQUEST l
- 1. Facility name: Oconee, Unit 3
- 2. Scheduled next refueling shutdown: February, 1937
- 3. Scheduled restart following refueling: April, 1987
- 4. Will refueling or resumption of operation thereafter require a i technical specification change or other license amendment? Yes 1 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: 458
- 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: Augus t , 1991 DUKE POWER COMPANY DATE: June 13, 1986 Name of
Contact:
J. A. Reavis Phone: 704-373-7567
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OCONEE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT
- 1. Personnel Exposure For the month of April, no individuals exceeded 10 percent of their allowable annual radiation dose limit.
- 2. The total station liquid release for April has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.
The total station gaseous release for April has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 perc,ent of this limit.
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-DUKE PbWER GOMPANY
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P.O. Isox 33189 CHAHLOTTE, N.C. 28242 wwe rarssonar (704) Oh4531 NVOLBAm PEOpt;CTION June 13, 1986 1
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/ ,a, Director ,
Office of eInspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk Re: Oconee Nuclear Station a
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 May, 1986. ,
Very truly yours,
$m -lhk. '
Hal B. Tucker JAR: sib . .
Attachment I
xc: Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW,-Suite 2900 Atlanta, Georgia 30323 Mr. Phil Ross U. S. Nuclear Regulatory Commission MNBB-5715 Washington, D. C. 20555 American Nuclear Insurers e/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Faraington, CT 06032 Y
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- Dirsctar !
June 13, 1986 Page Two xc: INPO Records Center Suite 1500 1100 Circle 75 Parkway ,
Atlanta, Georgia 30323 3
Ms. Judy Dovers
- Nuclear Assurance Corporation 5720 Peachtree Parkway Norcross, Georgia 30092 i Ms. Helen Pastis, Project Manager l Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. J. C. Bryant NRC Senior Resident Inspector Oconee Nuclear Station P
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