ML20078P719

Monthly Operating Repts for Nov 1994 for Sequoyah Nuclear Plant

ML20078P719
Person / Time
Site:	Sequoyah
Issue date:	11/30/1994
From:	Hollomon T, Shell R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9412200099
Download: ML20078P719 (10)

Text

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December 15, 1994 l U.S. Nuclear Regulatory Commission l ATTN: Document Control Desk l Washington, D.C. 20555 l

Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAI! NUCLEAR PLANT (SQN) - NOVEMBER 1994 MONTHLY OPERATING REPORT Enclosed is the November 1994 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10.

If you have any questions concerning this matter, please call J. W. Proffitt at (615) 843-6651.

Sincerely.

0,N.AAdf  :

R. II. Shell Manager l SQN Site Licensing l l

l Enclosure I cc: See page 2 l

9412200099 941130 <

PDR ADOCK 05000327 k J R PDR ,

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,9 U.S. Nuclear Regulatory Commission Page 2 December 15, 1994 cc (Enclosure): -

l IhPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. D. E. LaBarge, Project Manager .

U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike l

Rockvf11e, Maryland 20852-2739 l

Mr. Joseph Santucci, Manager Advanced Reactor Department Electric Power Research Institute 3340 lii11 view Avenue Palo Alto, California 94304 1

l NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 --

Regional Administration U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 Regional Administrator U.S. Nuclear Regulatory Commission ,'

Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 Mr. F. Yost, Director Research Services Utility Data Institute 1200 G Street, NW, Suite 250 Washington, D.C. 20005 ,

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9 TElefESSEE VALIEY AUTHORITY

f. SEQUOYAH NUCLEAR PLANT 1p h

MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY CGMISSION HQYE2Hl53L199_4 .

gi UNIT 1 DOCKET NIMBER 50-327 LICENSE NIMBER DPR-77 UNIT 2 4

DOCKET NIMBER 50-328 LICENSE NIMBER DPR-79 s

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. OPERATIONAL

SUMMARY

NOVEMBER 1994 illilL1 Unit 1 generated 785,920 megawatthours (MWh) (gross) electrical power during November with a capacity factor of 94.84 percent.

On November 29 at 0713 EST, with Unit 1 operating at approximately 100 percent reactor power, an automatic turbine trip signal was generated from a loss of both 48-volt electrohydraulic control (EHC) power sources, resulting in a reactor trip. The immediate cause of the trip was the loss of both 48-volt direct current EHC power supplies as a result of an electrical spike on the power supply output.

Unit i remained in Mode 3 at the end of November.

UNIT 2 Unit 2 8enerated 293.207 megawatthours (MWh) (gross) electrical power during November wit' a capacity factor of 35.54 percent.

The Unit 2 Cycle 6 refueling outage ended on November 16 at 0209 EST when the generator was synchronized to the grid. On November 18 at 1649 EST, with the unit operating at approximately 30 percent reactor power, a manual power reduction was initiated when a steam leak resulted from a faulty weld on 2-VLV-7-542. This test connection could not be isolated for repair. Reactor power was reduced to 20 percent, and the generator was taken of f-line for the repairs to be performed. Unit 2 was tied on-line on November 19 at 0436 EST, and reactor power increase was initiated. Unit 2 reached 100 percent reactor thermal power on November 25 at 0935 EST and remained at 100 percent power at the end of the month.

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AVERACE DAILY IBfIT PORR 12 VEL DOCKET NO. 50-327 UNIT No. One DATE: 12-05-94 COMPLETED BY: L_J. Ho11omon TELEPHONE: (615) 843-7528 MONTH: -NOVjtiBER 1994 l AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL M (MWe-Net) L6Y (MWe-Net) 1 1137 17 1133 2 1136 18 1138 3 1134 19 1141 4 1130 20 1142 ,

5 1128 21 1067 6 1134 22 1032 i 7 1133 23 1050 -t 8 1132 24 1061 ,

9 1132 25 1067 10 1132 26 1083 11 1136 27 1081 12 1129 28 1087 13 1138 29 11 14 _

1134 30 -15 15 1136 31 0 16 1134 P

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l AVERACE MILY UNIT FOMB IJNEL DOCKET NO. 50-328 UNIT No. Two DATE: 12-05-94 i

COMPLETED BY: T. J. Hollomon TELEPHONE: (615) 843-7528 j MONTH: _ NOVEMBER 1994 AVERAGE DAILY POWER LEVEL /NERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY . (MWe-Net) 1 -20 17 266 2 -7.1 18 200 3 -25 19 721 4 -21 20 826 5 -28 21 834 6 -21 22 846 ,

7 -22 23 843 8 -23 , 24 872 I 9 -25 25 1086 10 -25 26 1132 11 -21 27 1141 -

1128 12 -27 28 13 -25 29 1117 14 -25 30 1092 15 -23 31 0 16 174 I

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. r OPERATING DATA REPORT DOCKET NO. 50 327 DATE 12/05/94 COMPLETED BY T . J . Hol l omon TELEPHONE (6151 843-7528 r

OPERATING STATUS l Notes l 1 Unit Name: Seauevah Unit One l l

2. Reporting Period: November 1994 l 'l

3. Licensed Thermal Power (HWt): _3411.0 l l

4. Nameplate Rating (Gross MWe): 1220.6 *l l ,

5. Design Electrical Rating (Net MWe): 1148.0 l l ,

6. Maximum Dependable Capacity (Gross HWe): _1111.0 l l

7. Maximum Dependable Capacity (Net HWe): 1111.0 l I

8. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net HWe): N/A

10. Reasons For Restrictions, If Any: N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 720 8.016 117,625 _

12. Number of Hours Reactor Was Critical 679.2 5.389.2. 61.418

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 679.2 5.162.9 59.991.4

15. Unit Reserve Shutdown Hours 0 0 0  ;

16. Gross Thermal Energy Generated (HWH) 2.268.344.8 16.714.285.8 195.600.039

17. Gross Electrical Energy Generated (MWH) 785.920 5.667.980 66.370.534 ..

18. Net Electrical Energy Generated (MWH) 755.372 5.445.573 63.609.610

19. Unit Service Factor 94.3 64.4 51.0 .

20. Unit Availability factor 94.3 64.4 51.0

21. Unit Capacity Factor (Using HDC Net) 94.4 61.1_ 48.7

22. Unit Capacity factor (Using DER Net) 91.4 59.2. 47.1 l

23. Unit Forced Outage Rate 5.7 4.3 . 36.8

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

25. If Shut Down At End Of Report Period, Estimated Date of Startup: December 6. 1994 ,

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OPERATING DATA REPORT DOCKET NO. 50-328

-DATE 12/05/94 COMPLETED BY T. J. Hollomon '

TELEPHONE f615) 843-7528' i

Qf1 RATING STATUS .l' l Notes l

1. Unit Name: _StAugyah Unit Two l l

2. Reporting Period: 1 November 1994 l l

3. Licensed Thermal Power (MWt): 3411.0 l l

4. Nameplate Rating (Gross MWe): 1220.6 l l ,

5. Design Electrical Rating (Net MWe): 1148.0 l l

6. Maximum Dependable Capacity (Gross MWe): 1146.0 l l r

7. Maximum Dependable Capacity (Net MWe): _1106.0 l l

8. If Changes Occur in Capacity Ratings (Item Hembers 3 Through 11 Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe): N/A

10. Reasons for Restrictions, If Any: N/A _

i This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 720 8.016 109J85 12 Number of Hours Reactor Was Critical 475.8 4.853.5 63.612  :

13. Reactor Reserve Shutdown Hours 0 0 0 l

14. Hours Generator On-Line 349.7 4.672.2 61.965.7

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 944.910.6 15.230.849 9. 194.993.802 -

17. Gross Electrical Energy Generated (HWH) 293.207 5.206.233 66.134.177 _  ;

18. Het Electrical Energy Generated (MWH) __,_213.187 4.990.520 63.268.806

19. Unit Service factor 48.6 58.3 _ _ .

56.5 ,

20. Unit Availability factor 48.6 58.3. 56.5 ,

21. Unit Capacity Factor (Using MDC Net) 34.3 56.3 52.2 ,

22. Unit Capacity Factor (Using DER Net) 33 1 54.2 50.3  ;

, 23. Unit forced Outage Rate 2.3 2.5 35.4  ;

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

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

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DOCKET NO: 50-327 '

UNIT SHUTD0kNS AND POWER REDUCTIONS UNIT NAE : One DATE: 12/06/94 REPORT MONTN: November 1994 COMPLETED BY:T. J. Hollomon **

TELEPHONE:I615) 843-7523 Method of Licensee Cause and Corrective Duration Shatting Down Event Systga Compgnent Action to '

ko. Date Type (Hours) Reason Reactor Report No. Code Code Prevent Recurrence 5 941129 F 40.8 A 3 327/94014 JJ RJX On November 29 at 0713 EST, with Unit 1 operating at 100 percent reactor power, an automatic turbine trip / reactor trip signal was generated from a loss of both 48-volt electrohydraulic control (EHC) power sources. The cause of the event was inadequate technical review in the changing of the EHC overvoltage trip point. A contri-buting factor was an increase in radio frequency interference, resulting in the overvoltage trip point being exceeded, causing the loss of OHC power supply. Actions are being developed to ensure that vendor information is properly evaluated before being utilized.

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I: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) File D-Regulatory Restruction 4-Continuation of Existing Outage (NUREG-1022)

E-Operator Training and License Examir:ation 5-Roduction F-Administrative 9-Other S

G-Operational Error (Explain) Exhibit I-Sase Source H-Other (Explain)

DOCKET NO: 50-328 ~ *

• UNIT SHUTD0bMS AND POWER REDUCTIONS UNIT NAME: Two DATE: 12/06/94 REPORT MONTH: November 1994 COMPLETED BY:T. J. Hollomon

• TELEPHONE: f 6151 84'3-7528 l Method of Licensee Cause and Corrective l Duration Shutting Down Event System Component Action to

• I Reason 2 Reactor3 Report No. 4 5 No. Date Type (Hours) Code Code Prevent Recurrence 3 941101 S 362.1 C 4 N/A N/A N/A The Unit 2 Cycle 6 refueling outage ended on November 16 at 0209 EST when the generator was synchronized to the grid.

4 941118 F 8.2 B 1 N/A SD PSF On November 18 at 1431 EST, a steam leak was discovered at Test Connection 2-VLV-7-542. The leak could not be isolated for repairs.

At 1649 EST, power reduction was initiated, and the Unit 2 generator was removed from the grid. The cause of the leak was a failed weld. The weld was repaired, and the equipment was returned to service. ,,

2 3 #

I: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) File D-Regulatory Restruction 4-Continuation of Existing Outage (NUREG-1022)

F-Operator Training and License Examination 5-Reduction F-Administrative 9-Other G-Operational Error (Explain) 5Exhibit I-Same Source H-Other (Explain)

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