|
---|
Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML20195H1941998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20154L5081998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Browns Ferry Nuclear Plant.With ML20151Y2681998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20237B5511998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20236R2551998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Brown Ferry Nuclear Plant,Units 1,2 & 3 ML20249B5711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20247Q8381998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Browns Ferry Nuclear Plant ML20216K0101998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Browns Ferry Nuclear Plant ML20216H5961998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20202G4821998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Browns Ferry Nuclear Plant ML20198T0271997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Browns Ferry Nuclear Plant ML20203J7081997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20199D1431997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20198J7911997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20210V0331997-08-31031 August 1997 Monthly Operating Repts for Aug 1997 for BFN ML20217M3761997-07-31031 July 1997 Monthly Operating Repts for July 1997 for BFN ML20141H2501997-06-30030 June 1997 Monthly Operating Repts for June 1997 for BFN Per TS Section 6.9.1.3 ML20141C0631997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Browns Ferry Nuclear Plant (BFN) Units 1,2 & 3 ML20141G2471997-04-30030 April 1997 Monthly Operating Repts for Apr 1997 for Browns Ferry Nuclear Plant Units 1,2 & 3 ML20137T2001997-03-31031 March 1997 Monthly Operating Repts for Mar 1997 for Browns Ferry Nuclear Plant Unit 1,2 & 3 ML20137A4711997-02-28028 February 1997 Monthly Operating Repts for Feb 1997 for BFN Units 1,2 & 3 ML20134M6601997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20133M1241996-12-31031 December 1996 Monthly Operating Repts for Dec 1996 for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20132E2421996-11-30030 November 1996 Monthly Operating Repts for Nov 1996 for Browns Ferry Nuclear Plant Units 1,2 & 3 ML20129B8841996-09-30030 September 1996 Monthly Operating Repts for Sept 1996 for Browns Ferry Nuclear Plant Unit 1,2 & 3 ML20129C2471996-08-31031 August 1996 Monthly Operating Rept for Aug 1996 for Browns Ferry Nuclear Plant,Unit 1 & 2 ML20129B9101996-08-31031 August 1996 Revised MOR for Aug 1996 for Browns Ferry Unit 2 ML20116M6181996-07-31031 July 1996 Monthly Operating Repts for July 1996 for BFN ML20115G4121996-06-30030 June 1996 Monthly Operating Repts for June 1996 for Brown Ferry Nuclear Plant,Units 1,2 & 3 ML20112J2081996-05-31031 May 1996 Monthly Operating Repts for May 1996 for Browns Ferry Nuclear Plant Units 1,2 & 3 ML20112B5201996-04-30030 April 1996 Monthly Operating Repts for Apr 1996 for Browns Ferry Nuclear Plant Units 1,2 & 3 ML20107G0251996-03-31031 March 1996 Monthly Operating Repts for March 1996 for Browns Ferry Nuclear Plant ML20106G9401996-02-29029 February 1996 Monthly Operating Repts for Feb 1996 for Browns Ferry Nuclear Plant Units 1,2 & 3 ML20101D0311996-01-31031 January 1996 Monthly Operating Repts for Jan 1996 for Browns Ferry Nuclear Plant Units 1,2 & 3 ML20096D8751995-12-31031 December 1995 Monthly Operating Repts for Dec 1995 for Browns Ferry Nuclear Plant Units 1,2 & 3 ML20095K3231995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for Browns Ferry Nuclear Plant ML20096D8821995-11-30030 November 1995 Revised Monthly Operating Rept for Nov 1995 for Browns Ferry Nuclear Plant Unit 3 ML20094K4561995-10-31031 October 1995 Monthly Operating Repts for Oct 1995 for Browns Ferry Nuclear Plant ML20093G6131995-09-30030 September 1995 Monthly Operating Repts for Browns Ferry Nuclear Plant Units 1,2 & 3 ML20092G3511995-08-31031 August 1995 Monthly Operating Repts for Aug 1995 for Browns Ferry Nuclear Plant 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6661998-12-31031 December 1998 Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr 1999-09-30
[Table view] |
Text
.-. . _ _ - _ _ _ _ _ - _ _ - _ _ _ _ -_-__-
\
i L .
?: .
. ng >
Tennessee Valley Authcrity, Post Office 804 2000, Decator. Alabama 35609 December 12, 1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authe !.ty ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - NOVEMBER 1997 MONTHLY OPERATING REPORT The enclosure provides the November 1997 Monthly Operating -
Report as required by BFN Technical Specifications Section 6.9.1.3.
If you have any questicas concerning this matter, please call me at (205) 729-2636.
S ncerel ,
f i
. he ~
Manager of M censitg c 7 and I ustry Affa rs 3 A.I ') n Enclosur cci See pa e--2 /
m *1 r, ,9 >
o -
9712220048 97113')
PDR .ADOCK 05000259 PDR R m
4 c
U.S. Nuclear Regulatory Commissi i.
Page 2 December 12, 1997 Enclosure cc (Enclosure):
Mr. Mark S. Lesser, Branch Chief U. S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.
Suite 23T85 Atlanta, Georgia 30303 Mr. Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects I-II Office of Nuclear Reactor Regulation, Mail 13 H3 '
Washington, D.C. 20555 INPO Records Center Instituce of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. James Lang, Manager Advanced Reactor Department Electric Power Research Institute 3340 Hillview Avenue Palo Alto,- California 94304 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Regional Administrator U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.
Suite 23T85 Atlanta, Georgia 30303 Ms. Barbara Lewis McGraw-Hill Companiec 1200 G Street,.N.W.
Suite-1100 Washington, D.C.'20005-3802
- ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN) d MONTHLY OPERATING REPORT NOVEMBER 1997 UNIT 1 DOCKET NUMBER 50-259 LICENSE NUMBER DPR-33 UNIT 2 DOCKET NUMBER 50-260 !
LICENSE'h0MBER DPR-52 l
UNIT 3 l
DOCKET NUMBER 50-296 )
1 LICENSE NUMBER'DPR-68 l
l
. OPERATIONAL
SUMMARY
NOVEMBER 1997 BROWNS FERRY NUCLEAR PLANT UNIT 1 Unit i remains shutdown on administrative nold to resolve various TVA and NRC concerns. Unit 1 has,been on administrative hold 3
since June 1, 1985. As a result, TVA considers that accrual of reporting hours is suspended since the unit has a maximun.
6ependable capacity of zero MNe. Accordingly, TVA does not consider reporting cumulative hours for the period beginning June 1, 1985, when calculhting the operating st'atus variable..
BROWNS FERRY NUCLEAR PLANT UNIT 2 For the month of November, Unit 2 generated 794,210 megawatt hours gross electrical power and operated at a net capacity
\ factor of 101.3 percent. As of November 30, 1997, Unit 2 has operated contir.uously for 32 days.
R O BROWNS FERRY NUCLEAR PLANT UNIT 3 For the month of November, Unit 3 generated 787,210 megawatt hours-gross electrical power with a net capacity factor of 100.3 percent. As of November 30, 1997, Unit 3 has operated continuously for 262 days. ,
'E E-l
4 AVERAGE DAILY UNIT POWER LEVEL 4
DOCKET NO. 50-259 UNIT NO. ONE DATE: Dec. 15, 1997 COMPLETED BY: J. W. Davenport TELEPIIONE 205-729-2690 MONTH November 1997 h
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL E DAY (MWa-Net) DAY (MWe-Net) s
- 1. 0 17. 0
- 2. 0 18. O K
- 3. 0 19. 0
- 4. 0 20. O i
I 5. 0 21. 0
- 6. 0 22. 0
- 7. 0 23. 0
- 8. 0 24. 0
- 9. 0 25. O a
- 10. 0 26. 0
- 11. 0 27. 0 12 0 28. 0
- 13. 0 29. 0
- 14. 0 30. 0
- 15. 0
- 16. O I
E-2
1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 UNIT NO. TWO DATE: Dec. 15, 1997 COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 MONTH November 1997 AVERAGE C3ILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (MWe-Net) (MWe-Net)
- 1. 1057 17. 1086
- 2. 1059 18, 1093
- 3. 1057 19, 1088
- 4. 1091 20. 1084
- 5. 1091 21. 1099
- 6. 1092 22. 1087 7, 983 23. 1092
- 8. 1054 24, 1089
- 9. 964 25. 1091 10, 1090 26. 1092
- 11. 1087 27. 1090 12 1091 28. -1099
- 13. 1093 29. 1092
- 14. 1104 30. 1091
- 15. 1087
- 16. 1086 E-3
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT NO. THREE DATE: Dec. 15, 1997 COMPLETED BY: J. W. Davenport TELEPHONE 205-729-2690 MONTH November 1537 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY (MWe-Net) (MWe-Net)
- 1. 1065 17, 1085
- 2. 1054 18, 1091
- 3. 1051 19. 1077
- 4. 1072 20. 1083
- 5. 1072 21, 1099
- 6. 1071 22. 995
- 7. 983 23, 1073
- 8. 1016 24. 1089
- 9. 1066 25. 1086
- 10. 1087 26; 1090
- 11. 1089 27, 1088 12 -1084 28. 1098
-13. 1083 29. 1048
- 14. 1098 30. 1057
- 15. -1047
- 16. 1052 E-4
, OPERATING DATA REPORT Docket No. 50-259 Date: December 15.1997 Completed By: J. W. Davenport Telephone: 205-729-2690 1- Unit Name: BFN Unit 1
- 2. Reporting Period: November 1997
- 3. Licensed Thermal Power (MWt): 3293
- 4. Nameplate Rating (Gross Mwe): 1152
. 5. Design Electrical Rating (Net Mwe): 1065
- 6. Maximum Dependable Capacity (Gross MWe): 0-7, Maximum Dependable Capacity (Net MWe): 0
- 8. If cbmges Occur in Capacity Rating (item Numbers 3 Through 7) Since Last Report, Give Reasons: N/A
- 9. Power Level To Which Restricted, if any (net MWe): 0
- 10. Reasons for Restrictions, if any: Administrative lloid Ihis Month Yr-To-Date Cumulative *
- 11. Hours in Reporting Period 0 0 95743
- 12. Number of Hours Reactor was Critical 0 0 59521
- 13. Reactor Reserve Shutdown Hot.rs 0 0 6997
- 14. Hours Generator On-Line 0 0 58267
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWh) 0' 0 168066787-
- 17. Gross Electric Energy Generated (MWh) 0 0 55398130
- 18. Net Electrical Energy Generated (MWh) 0 0 53796427
- 19. Unit Service Factor 0 0 60.9
- 20. Unit Availability Factor 0 0 60.9
- 21. Unit Capacity Faaor (Using MDC Net) 0 0 52.8
- 22. Unit CapaS:y Factor (Using DER Net) 0 0 52.8
- 23. Unit Forced Outage Rate 0 0 25.6
- 24. . Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): N/A
- 25. If Shutdown at End of Report Period, Estimate Date of Startup: To Be Determined a
Excludes hours under Administrative !!old (June 1,1985 to present)
E-5
\ .
. OPERATING DATA REPORT Docket No. 50-260 Date: December 15.1997 Completed By: J. W. Davenno.t Telephone: 205-729-2690
- 1. Unit Name: HFN Uni; 2 2.- Reporting Period: November 1997
- 3. Licensed Thermal Power (h1Wt): 3293
- 4. Nameplate Rating (Gross hiwe): 1152
- 5. Design Electrical Rating (Net hiwe): 1065
- 6. hiaximum Dependable Capacity (Gross h1We): 1098.4
- 7. hiaximinn Dependable Capacity (Net htWe): 1065
- 8. If changes Occur in Capacity Rating (1:em Numbers 3 Through 7) Since Last Report, Give Reuons: N/A
- 9. Power Level To Which Restricted, if any (net h1We): N/A
- 10. Reasons for Restrictions, if any: N/A This 51onth Yr-To-Date Cumulative *
- 11. Hours in Reporting Period 720.0 8016.0 147631
- 12. Number of Hours Reactor was Critical 720.0 7413.0 106062
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 14200
- 14. Hoiirs Generator On-Line 720.0 7386.9 103669
- 15. Unit Reservc Shutdown Hours 0.0 0.0 0
- 16. Gross Thermal Energy Generated (h1Wh) 2351952.0 23400960 307588060
- 17. Gross Electric Energy Generated (hiWh) 794210.0 7752060 102173428
- 18. Met Electrical Energy Generated (h1Wh) 776582.0 7562627 99395792
- 19. Unit Service Factor 100.0 92.1 70.2
- 20. Unit Availability Factor 100.0 92.1 70.2
- 21. Unit Capacity Factor (Using AfDC Net) 101.3 88.6 63.2
- 22. Unit Capacity Facter (Using DER Net) 101.3 88.6 63.2
- 23. Unit Forced Outage Rate 0.0 1.4 14.2
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): N/A
- 25. If Shutdown at End of Report Period, Estimate Date of Startup: N/A
- Excludes ho' irs under Administrative lloid (June 1,1985 to Stay 24,1991)
E-6
. OPERATING DATA REPORT Docket No. 59d96 Date: December 15.1997 Completed By: J. W. Davenoort Telephone: 205-729-2690
- 1. Unit Name: HFN Unit 3;
- 2. Reporting Period: November 1997
- 3. Licensed Thermal Power (MWt): 3293 4 Nameplate Fating (Gross Mwe): 1152
- 5. Design Electrical Rating (Net Mwe): 1065
- 6. Maximum Dependable Capacity (Gross MWe): 1098.4
- 7. Maximum Dependable Capacity (Net MWe): 1065
- 8. If changes Occur in Capacity Rating (Item Nembers 3 Through 7) Since Last Report, Give Reasons: N/A
- 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. Honts in Reporting Period 720.0 8016.0 90853
- 12. Number of Hours Reactor was Critical 720.0 7576.0 62330
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 5150
- 14. Hours Generator On-Line 720.0 7558.2 60977
_ 15. Unit Reserve Shutdown Hours 0.0 0.0 0
- 16. Gross Thermal Energy Generated (MWh) 2335752.0 23775432 185006089 ,
17 Gross Electric Energy Gererated (MWh) 787210.0 7918410 61942550 i
- 18. Net Electrical Energy Generated (MWh) 769202.0 7721347 59403478
- 19. Unit Service Factor 100.0 94.3 67.1 20 Unit Availability Factor 100.0 94.3 67.1
- 21. Unit Capacity Factor (Using MDC Net) 100.3 90.4 61.4 3 22. Unit Capacity Factor (Using DER Net) 100.3 90.4 61.4
- 23. Unit Forced Outage Rate 0.0 0.0 16.9
>- 24. Shutdowns Scheduled Over Nex; 6 Months (Type, Date, and Duration of Eacl.). N/A
- 25. If Shutdown at End of Report Period, Estimate Date of Startup: N/A
- Excludes hours ander Administrative Hold (June 1,1985 to November 19,1995)
E-7
I UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT MONTil: NOVEMBER 1997 .
DOCKET NO: 50-259 UNIT NAME: BFN-1 DATF: December 15,1997 COMPLETED BY: J W. Davenport TELEPIIONE: (205) 729-2690 Type' Duration Reason
- Metho I of. Licensee - System Component Cause and Corrective Action to Prevent Na ~ Date.. _
5 Sinutting Event Report Code' Code Recurrence L , (flours)
Down' ' No.
Reactor3 1 06/01/85 S 720 F 4 N/A N/A N/A Administrative hold to resolve various TVA and NRC concerns, f
I l
2 Reason: a Method
- Exhibit G -Instmetions for (NUREG
' F: Forced A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets S: Scheduled 2-Manual Scram for Licensee Esent Report (LER)
B-Maintenance or Test C-Refueling 3-Aatomatic Scram File - NUREG - 1922 D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage 8
Examination 5-Reduction Exhihit I-Same Source F-Administrative 9-Other G-Operational Enor (Explain) iI-Other (Explain)
E-8
UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT 310NTII: NOVEMBER 1997 .
DOCKET NO: 50-260 UNIT NAME: BFN-2 DATE: December 15,1997 COMPLETED BY: J. W. Davennort TELEPilONE: (205) 729-2690 Type' f Duration - Reason' Method of Licensee System Component Cause and Corrective Action to Prevent l No. c Datel Shutting l Event Report Code' Code' Recurrence '
f (flours) .-
Down. No.
l Reactdr' 1
N/A I
r
- Heason: ' Alethod
- Exhibit G -Instructions for (NUREG ,
' F: Forced A-Equipment Failure (Explain) 1-hianual Preparation of Data Entry sheets S: Schedofed 2 %1anual Scram for Licensee Event Report (LER)
B-hfaintenance or Test C-Refueling 3-Automatic Scram File - NU REG - 1022 D-Re2uhtory Restriction 4-Continuation, of Existing E-Operator Training and License Outage 8
Examination 5-Reduction Exhibit I-Same Source F-Administrative 9-Other G-Operational Error (Explain)
H-Other (Explain)
E-9 l
4 UN?T SIIUTDOWNS AND POWER REDUCTIONS REPORT MONTII: NOVEMBER 1997 ,
DOCKET NO: 50-296 UNIT NAME: BFN-3 DATE: December 15,1997-COMPLETED BY: J. W. Davent ort TELEPIIONE: (205) 729-2090 Type' Duration 2
Licensee System Component Cause and Corrective Action to Prevent
- 1. I Nr. . Date - Reason l Method of Shutting .. Event. Report Code
- Code' Recurrence I (Ilours)
Down No. '
ll Reactor' N/A l
l 1
i r
2 Reason: ' Method
- Exhibit G -Instructions for (N UREG
' F: Forced A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets i S: Scheduled 2-Manual Scram for Licensee Event Report (LER) l B-Maintenance or Test C-Refueling 3-Automatic Scram File - N UREG - 1022 D-Regulatory Restriction 4-Contimaation of Existing l Outage E-Operator Training and License 5 Examination 5-Reduction Exhibit 1-Sana Source F-Administrative 9-Othn G-Operational Error (Explain)
Il-Other (Explain)
E-10
- >