ML20067C743

Monthly Operating Repts for Jan 1994 for Sequoyah Nuclear Plant

ML20067C743
Person / Time
Site:	Sequoyah
Issue date:	01/31/1994
From:	Fenech R, Hollomon T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403040002
Download: ML20067C743 (10)

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tennessee Vaaey Authert,. Post Of'-ce Ocx 2000 Scxt@O.rsy Tennessee 3?r9 2000 Raben A. Fenech v<e nes.aent, sequeyan Neear Mant February 15, 1994 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C. 20555 Gentlemen:

l l In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAll NUCLEAR PLANT (SQN) - JANUARY 1994 MONTHLY OPERATING REPORT Enclosed is the January 1994 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10. It should be noted that the unit capacity indicators, gross maximum capacity and net maximum dependable capacity, have been revised to reflect baseline testing that was performed on each unit.

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

Sincerely, f /Ycep h Robert A. Fenech

, Enclosure cc: See page 2 1

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U.S. l'eclear aegulatory Commission Page 2 i February 15, 1994 i

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! INP0 Records Center

' Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. D. E. LaBarge, Project Manager U.S. Nucicar Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Ted Marston, Director Electric Power Research Institute P.O. Box 10412 Palo Alto, California 94304 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 j l

Mr. F. Yost, Director Research Services i Utility Data Institute l 1200 G Street, NW, Suite 250 l Washington, D.C. 20005

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f TENNESSEE VALLEY AUTHORITY NUCLEAR POWER GROUP SEQUOTAH NUCLEAR PIANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGUIATORY COPMISSION JANUARY 1993 i

i UNIT 1  ;

DOCKET NIMBER 50-327 1

LICENSE NUMBER DPR-77 i UNIT 2 l 1

DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79

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t OPERATIONAL SUMttARY l JANUARY 1994 l mIIa The Unit 1 Cycle 6 refueling outage continues. Unit i remained in Mode 5 through the end of January.

i 173E_2 Unit 2 generated 713,520 megawatthours (MWh) (gross) electrical power during January with a capacity factor of 83.69 percent. Unit 2 was operating at approximately 100 percent reactor power at the beginning of January.

At 1610 Eastern standard time (EST) on January 5, the 2B-B centrifugal l charging pump (CCP) tripped on timed overcurrent "A" phase, and letdown l isolated. The 2A-A CCP was started. It was later discovered that the 2B-B l

CCP had a broken shaft. On January 7 at 1352 EST, a power decrease was  !

initiated because of technical specification requirements when it was  !

determined that the repair time on the 2B-B CCP would exceed the 72-hour '

limiting condition for operation requirement.  !

Unit 2 was taken offline on January 8 at 0420 EST and entered Mode 2 at ,

1420 EST, maintaining reactor power at approximately 2 percent to test the main steam isolation valves at operating temperature. Unit 2 entered Mode 3 at 1838 EST on January 8 and entered Mode 4 at 2305 EST that day.

Unit 2 heatup to Mode 3 was initiated on January 11 at 0625 EST. Unit 2 entered Mode 3 at 0708 EST on January 11, and the reactor was taken critical at 0612 EST on January 12. Unit 2 entered Mode 1 on January 12 at 1428 EST and tied to the grid at 2159 EST that day. Unit 2 was operating at 100 percent reactor power on January 14 at 1446 EST and continued to operate at 100 percent reactor power through the end of January.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 5Q-311 UNIT No. _ Qne DATE: _Q2_-f4-94 COMPLETED BY: T. J. Ilo110 mon TELEPHONE: 1615) 843-7528 MONTil: . JANllARY_.1294 AVERAGE DAILY POWER LEVEL AVERACE DAILY POWER LEVEL DAY IMWe-Net) DAX (MWe-Netl 1 -2 17 -1 2 -2 18 -1 3 -1 19 -1 4 -1 20 -2 _

5 -1 21 - Z_

6 -L._ 22 -1

-2 7 23 .

8 -28 24 -2 9 -26 25 -1 10 - 16 26 -1 11 -2.8 27 -2 12 -35 28 -1 ,

1 13 -7 29 .

-1 14 -2 30 -1 15 -2 31 -1 16 -1 l l

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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. ___1Q-328 UNIT No. _ lwo _. DATE: _02-01-3 1 4 l

COMPLETED BY: L._Jdlqllamon TELEPil9NE: 16111_643-15 Z8 l

MONTil: __JARUARY 1994 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (tMe-Ne t ) DAY (MWe-Net) 1 1142 17 1144 2 1M3 18 1142 3 1142 19 1L42 4 1M2 20 1L42 5 1135 21 1142 6 1143 22 1143 7 106h 23 143 8 47 24 11A0 9 -2 _ 25 1143 10 -3 __ 26 1143 11 -5 27 1144 12 10 28 _ ll40 13 437 29 1143 l 14 1085 30 11A2_

15 1143 31 1142 16 1143

OPERATING DATA REPORT l DOCKET NO. _50-321 - .

i DATE _QZlDA/.94 COMPLETED BY I .J _tiollcmon TELEPHONE 161hLO.43_l52S_

O RRAUt!G_ilA M l Notes l

1. Unit Name: J tquoyab Unit One l l

2. Reporting Period: _ _).gnyary._1294 l l

3. Licensed thermal Power (HWt): 3411.0 l l

4. Nameplate Rating (Gross HWe): 1220.6 l l S. Design Electrical Rating (Net MWe): 1148.0 l l

6. Maximum Dependable Capacity (Gross MWe): 1151.0 l l

7. Maximum Dependable Capacity (Net MWe): 1111.0 1 1

8. If Changes Occur in Capacity Rat {ngs (Item Numbers 3 Through 7) $1nce Last Report, Give Reasons:

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

10. Reasons For Restrictions, If Any: N/A l

This Month Yr-to-Date Cumulative l

11. Hours in Reporting Period 744 744 110.3 M. _

12. Number of Hours Reactor Was Critical 0 0 56.q29

13. Reactor Reserve Shutdown llours 0 _

0 0 j l 14. Hours Generator On-Line 0 ..D._ 54,02L5_ l

15. Unit Reserve Shutdown Hours 0 0 0 l

16. Gross Thermal Energy Generated (HWH) 0 0 178.893.714 )

17. Gross Electrical Energy Generated (MWH) Q 0 __501112,654

18. Het Electrical Energy Generated (MWH) -4.536 -L516 __50,159,501

19. Unit Service factor 0 0 49.7

20. Unit Availability Factor 0 0 49.7.

21. Unit Capacity Factor (Using MOC Net) -015 -011_ 47.4

22. Unit Capacity Factor (Using DER Net) -0 5 -0,1 45,9 _

23. Unit forced Outage Rate 0 _0_ ._301_

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: __11 arch _26J29119t0_synd _

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. . 1 1

1 OPERATING DATA REPORT l l

DOCKET NO.10-328 DATE JZl.04/94 COMPLETED BY T, J. Hgligino t TELEPHONE [ft151343_Z520_

QEfaAllNG STATVS l Notes l

1. Unit Name: _St.qunnh Unit Two l l

2. Reporting Period: . January 1994 _ l l

3. Licensed Thermal Power (HWt): .3411.0 l l 4 Nameplate Ratiig (Gross HWe): _.1220.6 l l

5. Design Electrical Rating (Net HWe): __1148.0 l l

6. Maximum Dependable Capacity (Gross HWe): 1146.0 l l

7. Maximum Dependable Capacity (Net HWe): 1106.0 l l

8. If Changes Ucrur 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 744 744_ _ 1021313

12. Number of Hours Reactor Was Critical 6{L4.4 68LL SL443

13. Reactor Reserve Shutdown Hours 9 0 0

14. Hours Generator On-Line 630.4 630.4_ 57.923.9

15. Unit Reserve Shutdown Hours 0 0 Q

16. Gross Thermal Energy Generated (HWH) 2.081.774.4 2.08 LIZ_4A _ _lft)1Dd4,126

17. Gross Electrical Energy Generated (HWH) . 713.520 . 71L320 __1L641.464

18. Net Electrical Energy Generated (HWH) 689.135 689.135 58.967.421 l

19. Unit Service Factor 0_4. 7 84t L _56 t6 .

20. Unit Availability Factor __. 8411 _. 84 2 , Sfu6_

21. Unit Capacity factor (Using HDC Net) HLL,_, 83t L SLL_

22. Unit Capacity Factor (Using DER Net) 8 037 801L 302L_

23. Unit Forced Outage Rate 15.3 15.L 37.0

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

UnLL2_Cnis_52thteling_outagt: Juiv 3.1994LftLdays I

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

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DOCKET NO: 50-327 UNIT SHUTDOWNS AND POWER TEDUCTIONS UNIT NAME: One DATE: 02/09/94 .

REPORT HONTH: January l')94 COMPLETED BY:T. J. Hollomon TELEPHONE:f6151 843-7528 Method of Licensee Cause and Corrective  !

Duration Shutting Down Eveet System Component Action to l 4 No. Date Type (Hours) Reason2 Reactor 3 Report No. Code Code 5 Prevent Recurrence 1 940101 5 744 C 4 N/A N/A N/A The Unit 1 Cycle 6 refueling cutagh continues.

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4 2 Reason: #

I:F Forced Hethod: Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data i

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 Examination 5-Reduction F-Administrative 9-Other S

G-Operational Error (Explain) Exhibit I-Same Source  ;

H-Other (Explain)

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DOCKET NO: 50-328 tjNIT SHUTDOWNS AND P0WER REDUCTIONS UNIT NAME: Two .

DATE: 02/09/94 - - .

REPORT NONTH: January 1994 COMPLETED BY:T. J. Hollomon TELEPHONE:f615) 843-7528 Nethod of Licensee Cause and Carrective Duration Shutting Down Event System Cormgnent Action to .

, 4 Prevent Recurrence No. Date Type (Hours) Reason' Reactor Report No. Code Code 1 940107 F 113.7 A 1 328/94002 CB P On January 7, 1994. at 1352 EST, a' reactor power shutdown was initiated because repairs to the 28-B centrifugal charging pump (CCP) broken shaft could not be completed within the 72-hour tech-nical specification time limit.

The shaf t break was determined to be the result of material fatigue.

The pump shaft was replaced, and the pump was tested and returned to service. ' The cause of the fatigue failure is being further evaluated.

Unit 2 was returned to service on January 12 at 2159 EST after the repairs were completed on the 2B4 CCP.

2 Reason: #

'I:FForced Method: Exhibit G-Instructions 5: 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 Examination 5-Reduction F-Administrative 94ther 5

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

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