|
---|
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 ML20212G2241999-09-27027 September 1999 Safety Evaluation Supporting Amend 221 to License DPR-68 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 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 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 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With 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 05000259/LER-1999-001-01, :on 990115,inoperable CR Emergency Ventilation Sys During Post Maint Testing Was Noted.Caused by Failure of Procedure Writers & Reviewers.Returned a Crev to Operable State & Revised B Crev Train Procedures.With1999-02-12012 February 1999
- on 990115,inoperable CR Emergency Ventilation Sys During Post Maint Testing Was Noted.Caused by Failure of Procedure Writers & Reviewers.Returned a Crev to Operable State & Revised B Crev Train Procedures.With
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 ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 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 ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With 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 1999-09-30
[Table view] |
Text
,
Tennessee Valley Authority. Post offee Box 2000. Decatur. Alabama 35609-2000 August 14, 1997 i,
L!
U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington,-D.C. 20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-259 Tennessee Valley-Authority
)
50-260 50-296 t--
BROWNS FERRY NUCLEAR PLANT (BFN) - JULY 1997 MONTHLY OPERATING REPORT
=The_ enclosure provides the July 1997 Monthly Operating Report as required by BFN Technical Specifications Section 6.9.1.3.
If you have any questions concerning this matter, please call
'me at (205) 729-2636.
- Sij1cerely n _.
)
1
,6 Manage Licensi g h7 a
an Industry Aff rs j
~
Enclosure cc:
See page.2 9708220171 970731 PDR ADOCK 05000259 R
PDR
U.S. Nuclear Regulatory Commission Page 2 August 14. 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 l
INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway i
Atlanta, Georgia 30339-5957 Mr. James Lang, Manager I
Advanced Reactor Department Electri'c Power Research Institute 3340 Hillview Avenue-4 Palo Alto, California 94304 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Read 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 Companies 1200 G Street, N.W.
Suite 1100 Washington, D.C. 20005-3802 1
____U
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
MONTHLY OPERATING REPORT JULY 1997 UNIT 1 DOCKET NUMBER 50-259 LICENSE NUMBER DPR-33 UNIT 2 DOCKET NUMBER 50-260 LICENSE NUMBER DPR-52 UNIT 3 DOCKET NUMBER 50-296 LICENSE NUMBER DPR-68 l
I
e OPERATIONAL SUt44ARY JULY 1997-BROWNS FERRY NUCLEAR PLANT UNIT 1 Unit I remains shutdown on administrative hold to resolve various TVA and NRC concerno.
Unit 1 has been on adminf.strative hold since June 1, 1985.
As a result, TVA considers that accrual of reporting hours is suspended since the unit has a maximum dependable capacity of zero MWe,_ Accordingly, TVA does not consider reporting cumulative hours for'the-period beginning June 1, 1985, when calculating the operating status variables.
BROWNS FERRY NUCLEAR PLANT UNIT 2 For the month of July, Unit 2 generated 796,910 megawatt hours gross electrical power and operated at a net capacity factor of 98.0 percent.
As of July 31, 1997, Unit 2 has operated continuously for 95 days.
l l
BROWNS FERRY NUCLEAR PLANT UNIT 3 For the month of July, Unit 3 generated 794,650 megawatt hours gross electrical power with a net capacity factor of 97.8-percent.
As of July-31, 1997, Unit 3 has operated continuously for_140_ days.
E-1
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 UNIT NO.
ONE DATE: August 15, 1997 COMPLETED BY:
J. W. Davenport TELEPHONE 205-729-2690 MONTH July 1997
-AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe-Net) 1.
0 17.
0 2.
0 18.
0 3.
0 19.
0 l
4.
0 20.
0 5.
0 21.
O i
6.
0 22.
O 7.
0 23.
0 8.
0 24.
0 l
9.
0 25.
0 10.
0 26.
0 11.
0 27.
O 12 0
28.
0 13.
0 29.
0 14.
0 30.
0 15.
0 31.
0 16. -
0 E-2
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 UNIT NO.
TWO DATE:
August 15, 1997 COMPLETED BY:
J. W. Davenport TELEPHONE 205-729-2690 MONTH July 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l
DAY DAY-(MWe-Net)
(MWe-Net)
- 1. -
1051 17.
1057 2.
1059 18, 1052 3.
1053 19.
1036 4,
1053 20.
1034-5.
1054 21.
1050 6.
1053-22.
1023 7.
1062 23, 1037 8.
1054 24.
1050 9.
1035 25.
1034-
-10.
1028 26.
1039
'11.
1047 27.
1044 12 1050 28.
1025-13.
1049 29.
1027 14.
1050 30.
1027
- 15, 1045 31.
1047 16.
1036 E _
t AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-296 UNIT NO.
THREE DATE:
August 15, 1997 Cot 4PLETED BY:
J. W. Davenport TELEPHONE 205-729-2690
-MONTH July 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DAY.
(MWe-Net)
(MWe-Net) 1.
1069 17.
1042 2.
1070 18.
1043
-3.-
1063 19.
831 4.
1069 20.
879 5.
1058 21.
-1051 6,
1044 22, 1050 7,
1073 23.
1052 8.
'1076 24.
1048 9.
1050 25.
1053 1
10.
-1067 26.
1047 11.
1050 27.
1037 12 1056..
29.
1031 13, 1051 29.
1057 14.
1064 30.
1038 15, 1061 31.
1054 16, 1047 E-4
OPERATING DATA REPORT Docket No.
$0-259 Date:
Aucust 15.1997 Completed By:
1 W. Davenport Telephone:
205-729-2690 1.
Unit Name:
BFN Unit i 2.
Reporting Period:
July 1997 3.
Licensed Thermal Power (MWt):
3293 4.
Nameplate Rating (Gross Mwe):
1I52 5.-
Design Electrical Rating (Net Mwe):
1065 6.
Maximum Dependable Capacity (Gross MWe)-
g 7.
Maximum Dependable Capacity (Net MWe):
0 8.
If changes Occur in Capacity Rating (Item Numbers 3 Through 7) Since Last Report, Give Reasons: N/A 9.
Power Level To Which Restricted, If any get MWe): 0 10.
Reasons for Restrictions, If any: Administrative lloid This Month Yr-To-Date Cumulative
Hours in Reporting Period 0
0 95743 12.
Number of Hours Reactor was Critical 0
0 59521 13.
Reactor Reserve Shutdown Hours 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 Factor (Using MDC Net) 0 0
52.8 22.
Unit Capacity Factor (Using DER Net) 0 0
52.8 23.
Unit Foret;d Outage Rate 0
0 25.6 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, cnd Duration of Each): N/A 25.
If Shutdown at End of Report Period, Estimate Date ~
of Startup: To Be Determined Excludes hours under Administrative Hold a
(June 1,1985 to present)
E-5 l
OPERATING DATA REPORT Docket No.
50-260 Date:
August 15.1997 Completed By:
J. W. Davenpon Telephone:
205-729-2690 1.
Unit Name:
BFN Unit 2 2.
Reporting Period:
July 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):
1098.4 7.
Maximum Dependable Capacity (Net MWe):
1065 8.
If changes Occur in Capacity Rating (Item Numbers 3 Through 7) Since Last Report, Give Reasons: N/A l
9.
Power Level To Which Restricted, if any (net MWe): N/A 10.
Reasons for Restrictions, If any: N/A This Month Yr-To-Date Cumulative
Hours in Reporting Period 744.0 5087.0 144702 12, Number of Hours Reactor was Critical 744.0 5029.0 103678 13.
Reactor Reserve Shutdown Hours 0.0 0.0 14200 14.
Hours Generator On-Line 744.0 5024.0 101306 15.
Unit Reserve Shutdown Hours 0.0 0.0 0
16.
Gross Thermal Energy Generated (MWh) 2443632.0 16073088 300260188 17.
Gross Electric Energy Generated (MWh) 796910.0 5362180 99783548 18.
Net Electrical Energy Generated (MWh) 776674.0 5233565 97066731 19.
Unit Service Factor 100.0 98.8 70.0 20.
Unit Availability Factor 100.0 98.8 70,0 21.
Unit Capacity Factor (Using MDC Net) 98.0 96.6-63.0 22.
Unit Capacity Factor (Using DER Net) 98.0 96.6 63.0 23.
Unit Forced Outage Rate 0.0 1.2 14.4
. 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration ofEach): Unit 2 Cycle 9 Refueling Outage, Scheduled to begin 9/26/97, 21 days duration 25.
If Shutdown at End of Report Period, Estimate Date of Staitup: N/A
- Excludes hours under Administrative lloid (June 1,1985 to May 24,1991)
E-6 m
_A
4 i,
OPERATING DATA REPORT Docket No.
50-296 Date:
August 15.1997 Completed By:
J. W. Davenport Telephone:
205-729-2690 1.
Unit Name:
BFN Unit 3 2.
Reporting Period:
July 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):
1998.4 7.
Maximu'm Dependable Capacity (Net MWe):
1065 8.
If changes 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): N/A 10.
Reasons for Restrictions, If any: N/A This Month Yr-To-Date Cumulative
Hours in Reporting Period 744.0
-5087.0 87924 12.
Number ofHours Reactor was Critical 744,0 4647.0 59401 13.
Reactor Reserve Shutdown Hours 0.0 0.0 5150 14.
Hours Generator On-Line 744,0 4629.2 58048 15.
Unit Reserve Shutdown Hours 0.0 0.0 -
0 16.
Gross Thermal Energy Generated (MWh) 2416872,0 14263656 175494313 17.
- Gross Electric Energy Generated (MWh) 794650.0 4743580 58767720 18.
Net Electrical Energy Generated (MWh) 774689.0 4622462 56304593 19.
Unit Service Factor 100.0 91.0 66.0 20.
Unit Availability Factor 100.0 -
91.0 66.0 21.
Unit Capacity Factor (Using MDC Net) 97.8-85.3 60,1 22.
Unit Capacity Factor (Using DER Net) 97.8 85.3 60.1 23.
Unit Forced Outage Rate 0.0 0.0 17.6 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: N/A
- Excludes hours under Administrative Iloid (June 1,1985 to November 19,1995)
E-7
-_ J
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JULY 1997 DOCKET NO:
50-259 UNIT NAME:
BFN-1 DATE:
August 151997 COMPLETED BY: J. W. Davenport TELEPHONE:
(205) 729-2690 No.
s.Datet
!Typeh Durationi Reason- Method of Licensee SystesmL,Cesapement Cause and Corrective Action to PrevenO (Hours)[
Sbstting Event Report Code Code' Recurrence d~
. Dews.
No; -
^
Reacted 1
06/01/85 S
744 F
4 N/A N/A N/A Administrative hold to resoh e various TVA and NRC concerns.
i
' F: Forced Reason:
Method
- Exhibit G -Instmeticus for(NUREG 2
8 S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets B-Maintenance or Test 2-Manual Scram for Licensee Event Report (LER)
C-Refueling 3-Automatic Scram File-NUREG - 1922 D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage Examination 5-RMuction
- Exhibit I-Sanic Source F-Administrative 9-Other G-Operational Error (Explain)
H-Other (Explain)
E-8
~
~
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JULY 1997 i
i DOCKET NO:
50-260 UNIT NAME:
BFN-2 DATE:
August 15,1997 I
COMPLETED BY: J. W. Davenport TELEPHONE:
(205) 729-2690-L Reason *i Method of Licensee
_ Systems.1 Cossponent
_Cause and Corrective Action to Prevent !
No?
h Da'ted Type"
-Duration -
jHosrk)}
Shutting Event Report Code' C0de.a Recurmece s
Down No.?
.ggQef
^
N/A j
' Reason:
' Method
- Exhibit G -Inst wctions for (NUREG S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets B-Maintenance or Test 2-Manual Scram for Licensee Event Report (LER)
C-Refueling 3-Automatic Scram File - NUREG - 1922 D-Regulatory Restriction 4-Continuation ofExisting E-OperatorTraining and License Outage Examination 5-Reduction s Exhibit I-Samee Searce F-Administrative 9-Other G-Operational Error (Explain)
H-Other (Explain)
E-9
e UNIT SHUTDOWNS AND POWER REDUCTIONS REPORTMONTH: JULY 1997 DOCKET NO:
50-2% -
UNIT NAME:
BFN-3 DATE:
August 15,1997 COMPLETED BY: J. W. Davenport TELEPHONE:
(205) 729-2690 No.5
? Datel Type' Duration-Reason ' Method of Licensee Systesu Component; Cause and Corrective Action to Prevent :
2
.(Hours) 9 Shutting Event Report CodeV CodeV Recurrence
~
'~ '
..Down !-..
NoE
~~
2r R$ actor'!
~
4 07/18/97 S
0 B
5 N/A N/A N/A Power reduction for scheduled maintenance and testing.
' Method
- Exhibit G -Instructions for(NUREG 2
S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets B-Maintenance or Test 2-Manual Scram for Licensee Eirst Report (LER)
C-Refueling 3-Automatic Scram File - NUREG - 1922 D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage Examination 5-Reduction
' Exhibit I-Same Source F-Administratist 9-Other G-Operational Error (Explain)
H-Other (Explain)
E-10