ML20211E623

Monthly Operating Repts for Jan 1987

ML20211E623
Person / Time
Site:	Oconee
Issue date:	01/31/1987
From:	Reavis J, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8702240363
Download: ML20211E623 (17)

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OPERATING DATA REPORT DOCKET NO. 50-269 DATE 02-16-87 COMPLETED BY J.A- Reavis TELEPHONE 704-373-7567 4

OPERATING STATUS OC "** 1 b *"

1. Unit Name:

2. Reporting Period: January 1. 1987-January 31. 1987 Year-to-date and cumulative l 2568 capacity factors are calcu-

3. Licensed Thermal Power (MWt): lated using a weighted

4. Nameplate Rating (Gross MWe):

934 886 average for maximum

5. Design Electrical Rating (Net MWe): dependable. capacity.

4 6. Maximum Dependable Capacity (Gross MWe): 899 3

7. Maximum Dependable Capacity (Net MWe): 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 MWe): M-l 10. Reasons For Restrictions,1f Any:

This Month Yr..to.Date Cumulative i1. Hours In Reporting Period 744.0 744.0 118 573.0 ;

12. Number Of Hours Reactor Was Critical 744.0 744.0 87 138.9

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! 13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Line 744.0 744.0 83 746.1

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 1 838 472 1 838 472 202 764 577

! .17. Gross Electrical Energy Generated (MWH) 636 110 636 110 70 429 980

18. Net Electrical Energy Generated (MWH) 607 430 607 430 66 790 474

19. Unit Service Factor 100.0 100.0 70.5

20. Unit Availability Factor 100.0 100.0 70.6 l 21. Unit Capacity Factor (Using MDC Net) 94.9 94.9 65.3

22. Unit Capacity Factor (Using DER Net) 92.2 92.2 63.5

23. Unit Forced Outage Rate 0.0 0.0 14.7 4

24. Shutdowns Scheduled Over Nest 6 Months (Type. Date.and Duration of Each1:

! Refueling-July 28,1987-10 weeks t

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

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

l INITIA L CRITICALITY j INITIAL ELECTRICITY CO\lMERCIAL OPERATION t.

i 8702240 AD0 0 269 (9/7;)

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. i AVEP. AGE DAILY UNIT POWER LEVEL DOCKET ND 50-269 UNIT Oconee 1 DATE ' 02-16-87 COMPLETED J. A. Reavis TELEPHONE 704-373-7567 CENTH JANUARY,1987 DAY AVERASE DAILY POWER LEVEL DAY AVERAGE IAILY POWER LEVEL (MWE-Net) (MWE-Net) 1 833 17 849 2 833 18 842 3 833 19 842 0 833 20 845 5 833 21 806 6 833 22 760 7 834 23 760 8 834 24 760 9 815 25 760 10 840 26 764 11 841 27 767 12 839 28 766 13 843 29 777 14 850 30 809 15 850 31 809 16 850

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s UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-269 UNIT NAME OCONEE 1 -

DATE 02-16-87 REPORT MONTH January. 1987 COMPLETED BY Jerel Reams.

TELEPHONE (704)-373-7567-t MET-R HDD E OF T A SHU- LICENSE N Y S TING EVENT SYS- CAUSE AND CORRECTIVE O P DURATION O DOWN REPORT TEM COMPONENT ACTION TO

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

A --

CH HTEXCH HIGH STEAM GENERATOR LEVELS 2-p 87 9 S --

B --

HB VALVEX CONTROL VALVE STOP VALVE MOVEMENT PT'S 3-p 87 9 F --

A --

CH HTEXCH HIGH STEAM GENERATOR LEVELS 4-p 87- 1-21 S --

F --

EA TRANSF HIGH ACETYLENE LEVELS IN MAIN TRANSFORMER 5-p 87- 1-29 S --

F --

EA TRANSF HIGH ACETYLENE LEVELS IN MAIN TRANSFORMER 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

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DOCKET'NO: 50-269 UNIT: Oconee 1 DATE: 02-16-87 s

NARRATIVE

SUMMARY

Month: January 1987 Oconee Unit I began the month at 98% power,' limited by high. Steam Generator levels and a feedwater flow limit on "A" Steam Generator. On 1/14, power was

• increased to 100% after the upper feed flow limit was-increased. On-1/21, power was reduced to 90% for testing due to a gassing condition on the 1A Main Transformer. The unit then increased power to 95% on 1/29, where it remained for the rest of the month.

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MONTHLY REFUELING INFORMATION REQUEST i

1. Facility name: Oconee, Unit 1

2. Scheduled next refueling shutdown: July, 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 Committee regarding unreviewed safety questions? N/A

5. Scheduled date(s) for submitting proposed licensing action and supporting informatioa: 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: 971*

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8. Present licensed fuel pool capacity: 1312

Size of requested or planned increase

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9. Projected date of last refueling which can be accommodated by present licensed capacity: August, 1991 i

i i DUKE POWER COMPANY DATE: February 16, 1987 Name of

Contact:

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

• Represents the combined total for Units 1 and 2.

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OPERATING DATA REPORT DOCKET NO. 50-270

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DATE 02-16-87 COMPLETED BY J.A. Reavis TELEPHONE 704-373-7567 OPERATING STATUS Oconee 2 Notes

1. Unit Name:

2. Reporting Period: Janunrv 1. 198 7- Tanua rv *11. 1987 Year-to-date and cumulative

3. Licensed Thermal Power (MWt): 2568 capacity factors are calcu-

4. Nameplate Rating (Gross MWe): 934 lated using a weighted

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

6. Maximum Dependable Capacity (Gross MWe): 899 dependable capacity.

7. Maximum Dependable Capacity (Net MWe): 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 MWe): None

10. Reasons For Restrictions.If Any:

This Month Yr. to-Date Cumulative

11. Hours la Reporting Period 744.0 744.0 108 673.0

12. Number Of Hours Reactor Was Critical 731.1 731.1 80 822.3

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13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Line 717.5 717.5 79 443.5

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 1 792 872 -1 792 872 190 081 150

17. Gross Electrical Energy Generated (MWH) 607 110 607 110 64 740 631

18. Net Electrical Energy Generated (MWH) 580 460 580 460 61 549 086

19. Unit Service Factor 96.4 96.4 73.1

20. Unit Availability Factor 96.4 96.4 73.1

21. Unit Capacity Factor (Using MDC Net) 90.7 90.7 65.7

22. Unit Capacity Factor (Using DER Net) 88.1 88.1 63.9

23. Unit Forced Outage Rate 3.6 -

3.6 12.8

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date, and Duration of Each1:

.None

25. If Shut Down At End Of Report Period. Estimated Date of Startup: March 20, 1987

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIA L ELECTRICITY COMM ERCIAL OPER ATION (9/77)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-270 UNIT NAME OCONEE 2 -

DATE 7 2-16-87 REPORT MONTH Januarv. 1987 COMPLETED BY Jerel_Reavis TELEPHONE (704)-373-7567.

MET-R HOD E OF T A SHU- LICENSE N Y S TING EVENT SYS- CAUSE AND CORRECTIVE O P DURATION O DOWN REPORT TEM COMPONENT ACTION TO

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

A --

CH HTEXCH HIGH STEAM GENERATOR LEVEL 1 87- 1-18 F 14.93 A 1 CH HTEXCH LOOSE PARTS MONITOR NOISE INVESTIGA-TION AT TOP OF STEAM GENERATOR 2 87- 1-18 F 11.55 H 3 HB TURBIN FEEDWATER SWING & TURBINE CONTACT BUFFER HAD NOT BEEN RESET 2-p 87- 1-19 F --

F --

RB CONROD HOLD AT 63% POWER DUE TO ROD WITHDRAWAL LIMITS 3-p 87- 1-19 F --

A --

CH HTEXCH HIGH STEAM GENERATOR LEVEL 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)

AVERAGE DAILY UNIT POWER LEVEL DCCKET NO 50-270 UNIT Oconee 2 DATE 02-16-87 COMPLETED J. A. Reavis TELEPHONE 704-373-7567 MONTH JANUARY, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERASE DAILY POWER LEVEL (MWE-Net) ---

(NWE-Net) 1 811 17 809 2 811 18 135 3 812 19 366 4 811 20 814 5 811 21 825 6 811 22 826 7 811 23 826 8 811 24 825 9 811 25 826 10 811 26 827 11 811 27 829 12 810 28 826 13 811 29 827 14 810 30 826 15 811 31 826 16 809

DOCKET NO: 50-270 UNIT: Oconee 2 DATE: 02-16-87 NARRATIVE

SUMMARY

Month: January, 1987 Oconee Unit 2 began the month at 94% power, limited by high Steam Generator levels. 10n 1/18, the unit shut down to investigate the cause of a Loose Parts Monitor Alarm. The unit returned to service later that day, but tripped after a feedwater surge caused a power surge. The unit returned to service on 1/19, and increased power to 94%. Power was increased ~to 96% on 1/22 following a change to control circuitry which allowed the levels in the Steam Generators to equalize. The unit was able to increase

power to 97% on 1/27. It remained at that level for the rest of the month.

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MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee, Unit 2

2. Scheduled next refueling shutdown: December, 1987

3. Scheduled restart following refueling: March, 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: 971*

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: August, 1991 DUKE POWER COMPANY DATE: February 16, 1987 Name of

Contact:

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

• Represents the combined total for Units 1 and 2.

OPERATING DATA REPORT DOCKET NO. 50-287 DATE 02-16-6/

COSIPLETED BY J.A. Reavis TELEPHONE 704-373-7567 OPERATING STATUS

1. Unit Name: oconee 3 Notes

2. Reporting Period: January 1. 1987-January 31. 1987 Year-to-date and cumulative

3. Licensed Thermal Power (51Wt): 2568 capacity factors are calcu-

4. Nameplate Rating (Gross SIWE): 934 lated using a weighted

5. Design Electrical Rating (Net 31We): 886 average for maximum

6. Staximum Dependable Capacity (Gross SIWE): 899 dependable capacity.

7. Sfaximum Dependable Capacity (Net alwe): 860 S. 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 51We):

10. Reasons For Restrictions. If Any:

This 5fonth Yr. to.Date Cumulative I1. Hours In Reporting Period 744.0 744.0 106 320.0

12. Number Of Hours Reactor Was Critica! 0.0 0.0 77 206.7

13. Reactor Reserve Shutdown Hours --- ---

14. Hours Generator On.Line 0.0 0.0 75 915.3

15. Unit Reserve Shutdown Hours --- --- ---

16. Gross Thermal Energy Generated (51WH) 185 447 110

.17. Gross Electrical Energy Generated (.\lWH) 63 881 074

18. Net Electrical Energy Generated (51WH) -1 498 -1 498 60 842 165

19. Unit Service Factor 0.0 0.0 71.4

20. Unit Availability Factor 0.0 0.0 71.4

21. Unit Capacity Factor (Using SIDC Net) 0.0 0.0 66.4

22. Unit Capacity Factor (Using DER Net) --

0.0 0.0 64.6

23. Unit Forced Outage Rate 0.0 0.0 13.9

24. Shutdowns Scheduled Over Next 6 Stonths (Type. Date,and Duration of Eacht:

Currently Refueling

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25. If Shut Down At End Of Report Period. Estimated Date of Startup: March 20,1987

26. Units In Test Status IPrior to Commercial Operationi: Forecast '

Achieved INITIA L CRITICALITY INITIAL ELECTRICITY Coll %!ERCIAL OPERATION (0/77i

AVERAGE CAILY UNIT POWER LEVEL D03ET N3 50-287 UNIT Oconee 3

_10_2--16-87 COMPLETED J. A. Reavis TELEFHONE 704-373-7567 J

MONTH JANUARY,1967 DAY AVERAGE DAILY POWER LEVEL DAY AVERABE DAILY POWER LEVEL (MWE-Net) ---

(M'JE-Net i

! 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 2J 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0

UNIT SHUTDOWNS'AND POWER REDUCTIONS DOCKET NO. 50-287 UNIT NAME OCONEE3 .

DATE 02-16-87 '

REPORT MONTH Januarv. 1987 COMPLETED BY Jerel Rehvis- -

TELEPHONE (704)-373-7567 MET-l R HDD l E OF T A SHU- LICENSE N Y S TING EVENT SYS- CAUSE AND CORRECTIVE O P DURATION O DOWN REPORT TEM COMPONENT ACTION TO

. DATE E HOURS N- R/X NO. CODE CODE. PREVENT RECURRENCE 1 87 1 S 744.00 C 4 RC FUELXX l END OF CYCLE 9 REFUELING OUTAGE CONTINUING l 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)

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DOCKET NO: 287 UNIT: ~0conee 3 DATE:.._02-16-87 NARRATIVE

SUMMARY

Month: January. 1987 Oconee Unit-3 was in its end of cycle 9 refueling outage for the entire month of January.

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i MONTHLY REFUELING INFORMATION REQUEST

1. Facility name: Oconee, Unit 3

2. Scheduled next refueling shutdown: January, 1987

3. Scheduled restart following refueling: March, 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 Committee regarding unreviewed safety

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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: 469

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

l DUKE POWER COMPANY DATE: February 16, 1987 Name of

Contact:

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

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g c OCONEE NUCLEAR STATION

1. MONTHLY OPERATING STATUS REPORT 4

1. Personnel Exposure

'['/ForthemonthofDecember,noindividual(s) exceeded 10percentof their allowable annual radiation dose limit.

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

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

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DUKE POWER GOMPANY P.O. Box 33189 CHARLOTTE, N.O. 28242 HAL B. TUCKER Tut.EPHONE vna paammaar (704) 373-4531 moossam rancocuton February 16, 1987 U. S. Nuclear Regulatory Commaission Attention: 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 January, 1987.

.Very truly yours, M

Hal B. Tucker JAR /02/sbn Attachment xc: Dr. J. Nelson Grace, Regional Administrator American Nuclear Insurers U. S. Nuclear Regulatory Commission c/o Dottie Sherman, ANI Library Region II The Exchange, Suite 245 101 Marietta Street, NW, Suite 2900 270 Farmington Avenue Atlanta, Georgia 30323 Farmington, CT 06032 i

l-Mr. Phil Ross INPO Records Center i U. S. Nuclear Regulatory Consnission Suite 1500 MNBB-5715 1100 Circle 75 Parkway Washington, D. C. 20555 Atlanta, Georgia 30323 l

l 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 j Oconee Nuclear Station '

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