ML20056D627

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Monthly Operating Repts for Jul 1993 for Sequoyah Nuclear Plant,Units 1 & 2.W/930812 Ltr
ML20056D627
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 07/31/1993
From: Fenech R, Hollomon T
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9308170210
Download: ML20056D627 (10)


Text

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g k _ _ . . . . . _ - . . _ _ ~ . - - . _ . _ . . . _ . . _ _ _ . . _ . _ _ _ _ _ _ _ .__._ ._.- _._._. Tentessee Va%y Authorny. Post Offee Box 2000 SoddyCarsy. Tennessee 37379-2aX) Robert A. Fenech v ce Prer,, cont, Sequoyah Nxlear Plant August 12, 1993 U.S. Nuclear Regulatory Conunission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - JULY 1993 MONTHLY OPERATING REPORT Enclosed is the July 1993 Monthly Operating Report as requJr.:d by SQN

  • Technical Specification 6.9.1.10. l If you have any questions concerning this matter, please call (

J. W. Proffitt at (615) 843-6651. Sincerely, I h) f h- hk Robert A. Fenech Enclosure cc: . See page 2 I

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1 I i 9308170210-93o733 y l'1

         -j--DR ADOCK 0500o327: -

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L U.S. Nuclear Regulatory Commission Page 2 August 12, 1993 cc (Enclosure): INPO 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 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 Il 101 Marietta Street, NW, Suite 2900 l Atlanta, Georgia 30323-2711 Regional Administrator i U.S. Nuclear Regulatory Commission l Region II l 101 Marietta Street, NW, Suite 2900 l Atlanta, Georgia 30323-2711, Mr. F. Yost, Director Research Services Utility Data Institute 1700 K Street, NW, Suite 400 'I Washington, D.C.- 20006-3800

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A b TENNESSEE VA!.T.EY AUTHORITY { NUCLEAR POWER GROUP  ; SEQUOYAH NUCLEAR FIANT l 1

                                                                                   't' MONTHLY OPERATING REPORT i

i TO THE '; i NUCLEAR REGULATORY C0FMISSION-JULY 1993 + i i i UNIT 1 l DoCrET NinBER 50-327 i

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LICENSE NIMBER DPR-77 i

                                                                                    'f UNIT 2                                 I DOCKET NIMBER 50-328                           [

LICENSE NLMBER DPR-79 , I _I

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k- , , OPERATIONAL

SUMMARY

[ JULY 1993 l t UNIT 1 l l' Unit I remained in Mode 6 at the beginning of July. On July.5, the fuel  ! assembly that had tilted over because of foreign material on the core { plate, as reported last month, was removed from the core and placed in l the spent fuel pit. On July 7, the decision was made to offload or l l reposition fuel assemblies in the Unit 1 core to allow 100 percent core  ! plate inspection. At 2345 Eastern daylight time (EDT) on July 7,. the core offload was initiated. At 0948 EDT on July 8, the core had been offloaded except for two assemblies. The lower core plate inspection was completed with no additional problems identified. At 2058 EDT on July 8,  : che reload of the Unit I core was initiated. On July 12 at 0346 EDT, the core reload was completed. On July 13 at 0549 EDT, all control rods had  : been latched. Unit i remained in Mode 6 at the end of July. The i scheduled date for generator synchronization is November 19, 1993. {; UNIT 2 > 1 Unit 2 remained in Mode 5 during the entire month of July as a result of l inspection / repairs on secondary side piping as a result of erosion / corrosion problems. The scheduled date for generator , synchronization is September 10, 1993. ' l 1 POWER-OPERATED RELIEF VALVES (PORVs) AND SAFETY VALVES

SUMMARY

There were no challenges to PORVs or safety valves'in July. l. l. l l

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       ,                               AVERACE IMILY UNIT POWER LEVEL                         ,

DOCKET NO. 50-327 UNIT No. One DATE: _D8-04-93 i-COMPLETED BY: T. J. Hollnman TELEPHONE: (615) 843-7528 l

                                                                                            -r MONTH: __J1TLY 1993 AVERAGE DAILY POWER LEVEL                 AVERAGE DAILY POWER LEVEL DM             (MWe-Net)                 DM              (MWe-Net) 1               -7                       17                -9 2               -6                       18                -9                    ,

3 -7 19 -9 4 -7 20 -9 5 -7 21 -7 6 -7 22 -7 7 -7 23 -9 8 -6 24 -7 9 -7 25 -7 10 -6 26 -7 11 -7 27 -9

           '12              -9                       28                -7 13             -11                       29                -7                     ,

14 -7 30 -12 15 -11 31 -9 16 -9

i AVERAGE IMILY UNIT POWER LEVEL ', i i DOCKET NO. 50-328 UNIT No. Two DATE: 08-04-93  ! COMPLETED BY: T. J. Hollomon TELEPHONE: (615) 843-7528 MONTH: . JULY _15L93 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net) - 1 -6 17 -9 f 2 -7 18 -7 3 -6 19 -7 4 -5 20 -7 5 -6 21 -7 6 -7 22 -7 7 _

                            -10                      23                 -7 8                  -9                      24                 -7 9                 -10                      25                 -7 10                 -8                      26                 -7 11                 -9                      27                 -9 12                 -8                      28                 -5 i

13 -4 29 -5 14 -5 30 -9 , 15 -8 31 -7 16 -7

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OPERATING DATA REPORT DOCKET NO. _50:327 , DATE 08/04/93 COMPLETED BY L_L_liollomon ' TELEPHONE (615) 843-7528 l i OPERATING STATUS l Notes l

1. Unit Name: _Secuovah Unit One l j '
2. Reporting Period: _Julv 1993 l l
3. Licensed Thermal Power (MWt): 3411.0 l l
4. Nameplate Rating (Gross MWe): 1220.6 l -l S. Design Electrical Rating (Net HWe): 1148.0 l l
6. Maximum Dependable Capacity (Gross MWe): 1162.0 l l
7. Maximum Dependable Capacity (Net MWe): 1122.0 l I ,
8. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:

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9. Power Level To Which Restricted, If Any (Net NWe): N/A [
10. Reasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumulative (

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11. Hours in Reporting Period 744 5.087' _ 17i.936'
12. Number of Hours Reactor Was Critical 0 1.281.3 56.029
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 0 1.220.6 54.828.5
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 3.915.909.5 178.893.754 -
17. Gross Electrical Energy Generated (MWH) 0 1 358.540 60.702,654 ,
18. Net Electrical Energy Generated (MWH) -6.D10 1.274.267 58.196.489'
19. Unit Service factor 0 24.0- 51.8
20. Unit Availability factor 0 24.0 51.8__
21. Unit tapacity factor (Using MDC Net) -0.7 22.3 ~49.0
22. Unit Capa ity factor (Using DER Net) -0.7 21.8 '47.9 ,
23. Unit forced Outage Rate 'O 47.5' 38.7 'i
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): l t

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           '25. If Shut Down At End Of Report Period. Estimated Date of Startup: ' November 19.'1993-                         'f q

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D r . OPERATING DATA REPORT  ; DOCKET NO. _50:328 DATE 08/04/93 i COMPLETED BY T. J.- Hollomon TELEPHONE (6151 843-7528 i Q.PIM11EG STATUS l Notes l-

1. Unit Name: __Seguovah Unit Two l l.
2. Reporting Period: ' July 1993 l l
3. Licensed Thermal Power (MWt): 3411.0 l l 4 Nameplate Rating (Gross HWe): _1ZZR,6 l l

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5. Design Electrical Rating (Net MWe): 1148.0 l l; I
6. Maximum Dependable Capacity (Gross HWe): 1162.0 l l
7. Maximum Dependable Capacity (Net MWe): 1122.0 'l 1 B. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
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9. Power Level To Which Restricted If Any (Net MWI): N/A
10. Reasons for Restrictions, If Any: N/A t

This Month Yr-to-Date Cumulative .

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11. Hours in Reporting Period . 744 5.087 97.896 ,
12. Number of Hours Reactor Was Critical 0 1.291.9 57.505 .;
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 0 1.158.2 56.235 6__
15. Unit Reserve Shutdown Hours.- 0 'O O
16. Gross Thermal Energy Generated (MWH) 0 3.773.305.1 176.955.084
17. Gross Electrical Energy Generated (MWH) 0 1.283.783 __hQ QQ6.902 l
18. Het Electrical Energy Generated (MWH) -5.271 1.206.874 57.422.149
19. Unit Service Factor 0 22.8 57. 4__ .

_20. Unit Availability factor 0 22.8 57.4

21. Unit Capacity Factor (Using MDC Net)_ .
                                                                             -0.6                    21.1              ~ 52.3                 l
22. Unit Capacity Factor (Using DER Net) --0.6 20.7 51.1~ -f
23. Unit Forced Outage Rate- .100.0 77.2 35.7 I
                    -24. Shutdowns Scheduled Over Ne'xt 6 Months (Type,"Date,'and Duration of Each):

a i l 25,- If Shut Down At End Of Report Period, Estimated Date of Startup: __SIRitmber 10. 1993 i 4 1

77 DOCKET NO: 50-227 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME: One

  • DATE 08/04/93 REPORT MONTH: JULY 1993 COMPLETED BY:T. J. Hollomon --

TELEPHONE:(6151 843-7528 . Method of Licensee Cause and Corrective Duration shutting Down -Event System Compgnent Action to , 2 No. Date Type l. '(Hours) Reason Reactor 3 Report No. Code # Code Prevent Recurrence 4 930701 F 744 .C 4 N/A N/A N/A The Unit 1 Cycle 6 ofueling outage continues.

                                          -I F: Forced          2 Reason:                                                    .3 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-                                             9-Other 5

G-Operational Error. (Explain) Exhibit I-Same Source ' H-Other (Explain)~ - _ _ - _ - - - - _ - - - . - . . - . . _ _ - _ - . . _ . .. ~ . . .. .. . . - , . . . . . - . . - . - . - . . - - . - . .. - .. . . . - -_- . _ - - . , - . . . . . - .

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                                                                                                                                                                                         ~ DOCKET NO:      50-328' s                                                                                      UNIT SHUTDOWNS AND POWER REDUCTIONS                                                                 UNIT NAME:       Two DATE:  08/04/93     *    *   .

REPORT MONTH: JULY 1993 COMPLETED BY:T. J. Holloman *

                                                                                                                                                                                           . TELEPHONE:(6151 843-7528 Method of                            Licensee                                               Cause and Corrective Duration                               Shutting Down                           Event         System             Component                   Action to 4

No. Date. Type l' (Hours)- Reason 2 Reactor 3 Report No. Code Code b Prevent Recurrence . 3 '930701 'F 744 A 4 328/93001 TL EXC Unit 2 remained in the forced outage through the end of July. The outage began on March 1,1993, as a result of the identified erosion / corrosion problems. i I 2 Reason: 3 # I F: Forced 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 Dutage ~(NUREG-1022) E-Operator Training and License Examination 5-Reduction F-Administrative . 9-Other-G-Operational Error (Explain) 5 Exhibit I-Same Source H-Other (Explain) c...___1.____u____... _ _ . . _ _ _ . _ - - . . _ . . . _ - - . _ . . _ _ . _ . _ . . .. .. . .. . _ _ . . . .. _ a _ . __ .. _ _. . _ _ _ _ .}}