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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] |
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Tennessee vaney Auhbrdy Nd 09 ce Box 2000. Decaw. A;abama 35609 l
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FEB .0 81991 U.S. Nuclear Regulatory Commission 'i ATTN: Document Control Desk ,
Washington, D.C. 20555 Gentlemen:
In the Matter Of _
) Docket'Nos. 50-259 f Tennessee Valley Authority ) 50-260 ;
50-296 r i
BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT- 1 FOR THE MONTH OF JANUARY 1994 s B In accordance with the requirements of BFN Units'1, 2,.and 3 l Technical Specifications Section 6.9.1.3, TVA_is submitting !
'the Monthly Operating Report for the month of January.1994-in the enclosure.
If you have any questions, please telephone me at '
(205) 729-2636.
Sincerely, l
k 2 3 Pe alas Manager of Site Licensing Enclosure cc: See page 2 l w
.9402160012 940131 g;i .
j.
PDR .ADOCK 05000259 PDR g-g
/4'1 F ) :
R ./ pg.1: 1 v.- t. !
a .
4
, U.S. Nuclear Regulatory Commission '
Page 2 FEB 0 91?4 ;
- Enclosure 2 cc (Enclosure): ;
Mr. R. V. Crlenjak, Project Chief i U.S. Nuclear Regulatory Commission Region'II .
101 Marietta Street, NW, Suite 2900 ,
Atlanta, Georgia. 30323 l Mr. Frederick J. Hebdon, Director ~!
Project Directorate II-4 Division of Reactor Projects I-II .
Office of Nuclear ~ Reactor l Regulation Mail 13 H3 i Washington, D.C. 20555 ;
INPO Records Center .
Institute of Nuclear Power Operations f 1100 Circle 75 Parkway, Suite 1500 !
Atlanta, Georgia 30389 i Mr. Ted Martson, Director :
Electric Power Research Institute P. O. Box 10412 -
Palo Alto, California 94304 :1 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 ;
Athens, Alabama 35611 ,
Regional Administrator i U.S. Nuclear Regulatory Commission a Region II l 101 Marietta Street, NW, Suite 2900 +
Atlanta, Georgia 30323 Mr. Fred Yost, Director of Research :
Services, Utility Data Institute, Inc. -I 1700'K Street, NW, Suite 400 +
Washirgton, D.C. 20006 ,g -
bIl i i
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..s ; . __ ; . _ . , , .
4 ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 HONTHLY OPERATING REPORT JANUARY 1994 9
}
i a
i OPERATIONAL
SUMMARY
' JANUARY 1994 BROWNS FERRY 1 ,
I Unit i rcmains shutdown on administrative hold to resolve various TVA and NRC concerns. Unit 1 has been on administrative hold since June 1,~1985. . As a-result,-TVA-considers-that accrual of i reporting hours is suspended since the unit has a maximum dependable capacity of 0-MWo. Accordingly, TVA does not consider '
cumulative reporting period hours for the period beginning June 1, 1985, when calculating the operating status variables.
BROWNB FERRY 2 ,
Unit 2 operated-continuously during the month of January at a capacity factor of'102.4 percent and generated 830,130_ megawatt hours gross electrical power. As of January 31, 1994, Unit 2 has ,
' operated continuously for 242 days since returning to service in early June 1993 following the Cycle 6 refueling outage.
t DROWNS FERRY 3 i
Unit 3 remains shutdown on administrative hold to resolve various TVA and NRC concerns. Unit 3 has been on' administrative hold _
3 since June 1, 1985. As a result, TVA considers that accrual of I reporting hours is suspended since the unit has a maximum dependable capacity of 0 MWe. Accordingly, TVA does not consider ,
cumulative reporting period hours for the period beginning June 1, 1985, when calculating the operating status variables. j
'l l
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4
. AVERAGE DAILY UNIT POWER-LEVEL DOCKET NO: 50-259 'i UNIT BROWNS FERRY 1' PREPARED BY: T, ' R. ' Smith TELEPHONE: 'f205) 729-2955 MONTH January 1994 DAY ~ AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL '
-(MWe-Net)- .. (MWe-Net ) ,
1 0 17 0 2 0 18 0 i 3- 0 19 0 4 0 20 0 ;
5 0 21 0 ,
6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 _ _ _
0 12 0 28 0 13 0 29 0 P
14 0 30 _
0 15 0 31 0 16- 0 5 5
A m - a 4
4 I
J
. l
. AVERAGE DAILY UNIT POWER LEVEL 1 DOCKET NO: 50-260 UNIT: BROWNS FERRY 2' PREPARED BY: T. R. Smith TELEPHONE:- (205) 729-2955 '
MONTH January 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
. (MWe-Net) .(MWe-Net) ,
l 1 1085 17 1087 !
2 1091 18 1090 3 1092 19 1095 4 1093 20 1087 :
i 5 1088 21. 1088 6 1088 22 1090
8 1093 24 1095 F
9 1083 - 25 1085 .,
'I 10 1091 26 1092 '
^
11 1089 2 *? 1090 12 1088 28 1092 13 1093 29 1092
. 14 1093 30 1092 15 1092 31 1090 16 1082 ,
- ?
.9 i
e
' AVERAGE DAILY UNIT POWER LEVEL ,
r DOCKET NO: 50-296 ,
UNIT: BROWNS FERRY 3 ~!
PREPARED BYt T. R. Smith TELEPHONE: (205) 729-2955 MONTH January 1994 :
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) ,(MWe-Net) 1 0 17 0 ,
2 0 18 0 3 0 19 0 4 0 20 0
+
5 0 21 0
[
6 0 22 0 ,
7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 i
14 0 30 0 ,
15 0 31 0 16 0 i
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--._2-__:
00CKET NO: 150-259 UNIT SHUTDOWiS ACD POWER REDUCTICNS UNIT: BROWNS MRR71 PREPARED BY T. R. Smith -
REPORT MONTH: ' January 1994 TELEPHONE: (205) 729-2955 Method of License Cause and corrective Duration Shutting Event System Conpanent Action to Prevent Type' 8 No. Date (Nours) Reason' Down Reactor Report No. Code
- Code' Recurrence 1 06/01/85 S 744 F 4 A&rinistrative hold to resolve various TV4 and NRC concerns.
'F: Forced #R eason: ' 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 Restriction 4-Continuation of Existing Outage (NUREG w )
E-Operator Training and License Examination 5-Reduction F-Adninistrative 9-Other G-Operational Error (Explain) ' Exhibit I-Same Source M-Other (Explain)
_. _ . . . . - _c -- . . , . . _ . . , . _ _ ~.. ._ . . . . , _ , _ . _ , . _ _
000GT No: 50-260-LNIT SHUTDOLMS QND PCUER REDUCTTONS LOI?: BROWNS FERRY 2 PREPARED BY: T. P. Smith .
REPORT M0alTH: Jarcary 1994 TELEPHONE: (205) 729-2955 9
Method af License Cause and Corrective ~.
Duration shutting Event System Cceponent Action to Prevent No. Date Type' (Hours) Reason' Down Reactor' Report No. Code
'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 Restriction 4-Continuation of Existing Outage (NUREG-061)
E-Operator Training and License Examination 5-Reduction F-Adninistrative 9-Other '
G-Operational Error (Explain) ' Exhibit'I-Same source H-Other (Explain)
DCIKET NO: 50-?96 UNIT SHUTDOWNS E3 POWER REDUCTIONS - OIT: BROWS FERRY 3 PREPARED ST: T . R . "At th +
REPORT MONTM: January 1994 TELEPHONE: (205) 729-2955 Method of License Cause and Corrective Duration Shutting Event System Component Action to Prevent No. Date Type' (Hours) Reason Down Reactor' Report No. Code' Code' Recurrence 1 D6/01/85 S 744 F 4 Administrative hold to resolve various TVA and NRC concerns.
1
'F: Forced ' Reason: 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 Restriction .
4-Continuation of Existing Outage (NUREG-061)
E-operator Training and License Examination 5-Reduction F-Administrative 9-Other ..
G-Operational Error (Explain)
- Exhibit I-Same Source H-Other (Explain)
e;,
e U .
OPERATING DATA REPORT DOCKET:' 50-259 UNIT: BROWNS FERRY 1-PREPARED BY: T. R. SMITH TEIIPHONE: (205) 729-2955' OPERATING STATUS
- 1. Unit Names BROWNS FERRY UNIT 1
- 2. Reporting Period: JANUARY 1994
- 3. Licensed Thermal Power (MWt): 3293
- 4. Nameplate Rating (Gross MWe): 1152
- 5. Design Electrical Rating (Not MWe): 1065
- 6. Maximum Dependable capacity (Gross MWe): 0
- 7. Maximum Dependable Capacity (Not HWe): 0
- 8. If Changes' Occur in Capacity Ratings (Items Number 3 Through.7) Since Last Report, Give Reason N/A-
- 9. Power Level To Which Restricted, If Any (Net MWe) . 0
- 10. Reason For Restrictions, If Any: Administrative Hold THIS HONTH YEAR TO DATE CUMULATIVE *
- 11. Hours in Reporting Period 0 0 :95743
- 12. Hours Reactor Was Critical 0 0 59521 13.. Reactor Reserve Shutdown. Hours 0 0 6997-
- 14. Hours Generator Un Line 0 0 58267-
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Cross Thermal Generation (MWh) 0 0 168066787
- 17. Gross Electrical Generation (MWh) 0 0 55398130
- 18. Net Electrical Generation (MWh) 0 0 53796427
- 19. Unit Service Factor 0 0 60.9
- 20. Unit Availability Factor 0 0 60.9
- 21. Unit capacity Factor (MDC Net) 0 0 52.8
- 22. Unit capacity Factor (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 Shut Down At End of Reporting Period, Estimated Date of Startup To be determined sq
- Excluden hours under administrative hold i
'i (June 1, 1985 to.present) il Jj
i l
i 'l
- l OPERATING DATA REPORT l
-l l
DOCKET: 50-260 ;
UNIT BROWNS FERRY 2 PREPARED BY - T. R. SMITH TELEPHONE: f205) 729-2955 OPERATING STATUS *
- 1. Unit Names BROWNS FERRY UNIT 2
- 2. Reporting Periods -JANUARY 1994
- 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 Ratings (Items Number 3 Through 7) Since Last Report, Give Reason: N/A
- 9. Power La rel To Which Restricted, If Any (Net MWe): N/A "
- 10. Reason For Restrictions, If Any N/A THIS MONTH YEAR TO DATE CUNULATIVE*
- 11. Hours in Reporting Period 744 744 114055
- 12. Hours Reactor Was Critical 744 744 75561
- 13. Reactor' Reserve Shutdown Hours 0 0 14200
- 14. Hours Generator On Line 744 744 73369
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Generation (MWh) 2445505 2445505 210993106
- 17. Gross Electrical Concration (MWh) 830130 830130 70038048
- 18. Not Electrical Generation (MWh) 811013 811013 68055675 ,
- 19. Unit Service Factor 100.0 100.0 64.3 i
- 20. Unit Availability Factor 100.0 .100.0 64.3
- 21. Unit Capacity Factor (MDC Net) 102.4 102.4 56.0
- 22. Unit capacity Factor (DER net) 102.4 102.4 56.0
- 23. Unit Forced Outage Rate 0 0 18.4
- 24. Shutdowns Scheduled over Next 6 Months
.(Type, Date, and Duration of Each): .N/A
- 25. If Shut Down At End Of Reporting Period, Estimated Date of Startup N/A ,
- Excludes hours under administrative hold (June 1, 1985 to May 24, 1991)
~
h s.
. OPERATING DATA REPORT DOCKET: 50-296 UNIT: RPOWNS FERRY'3 PREPARED BY: T. R. SMITH !
TELEPHONE: f205) 729-2955 OPERATING STATUS
- 1. Unit Names BROWNS FERRY UNIT 3 l
- 2. Reporting Period: JANUARY 1994 ]
- 3. Licensed Thermal Power (MWt): 3293 ;
- 4. Nameplate Rating (Gross MWe): 1152 1
- 5. Design Electrical Rating (Net MWe): 1065 ;
- 6. Maximum Dependable Capacity (Oross MWe): 0
- 7. Maximum Dependable Capacity (Net MWe): O i
- 8. If Changes Occur in Capacity Ratings (Items Number l 3 Through 7) Since Last Report, Give Reason: N/A
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- 9. Power Level To Which Restricted, If Any (Net MWo): 0 ,
- 10. Reason For Restrictions, If Any: Administrative Hold l
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'i THIS MONTH YEAR TO DATE CUMULATIVE
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- 11. Hours in Reporting Period 0 0 73055 l
- 12. Hours Reactor Was Critical 0 0 .45306-
- 13. Reactor Reserve Shutdown Hours 0 0 5150
- 14. Hours Generator On Line 0 0 44195
- 15. Unit Reserve Shutdown Hours 0 0 0 J
- 16. Gross Thermal Generation (MWh) 0 0 131868267- l
- 17. Gross Electrical Generation (MWh) 0 0 43473760 1 38 Net Electrical Generation (MWh) 0 0 42114009 A9. Unit Service Factor 0 0 60.5
- 20. Unit Availability Factor .0 0 60.5 !
- 21. Unit capacity Factor (MDC Net) 0 0 54.2 '
- 22. Unit Capacity Factor-(DER net) 0 0 54.2
- 23.' Unit Forced Outage Rate 0 0 21.6
- 24. Shutdowns Scheduled Over Next 6 Months i (Type, Date, and Duration of Each)s- N/A )
- 25. If Shut Dewn At End Of Reporting Period, Estimated Date of Startup: To be determined i
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- Excludes hours under administrative hold (June 1,.1985 to present) !
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