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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML18038B9901997-10-31031 October 1997 Bfnp Unit 2 Completion Rept for USI A-46, for Oct 1997 ML18038B8591997-03-31031 March 1997 Completion Rept for USI A-46, for Mar 1997 ML18038B8271997-03-0707 March 1997 Rev 1 to GE-NE-523-B13-01869-032, Evaluation of Indications on Browns Ferry 3 Annulus Core Spray Piping. ML20132B7801996-11-12012 November 1996 Engineering Rept for Safety/ Relief Valves Safety Function Lift Setpoint Tolerence Relaxation Summary Rept ML18038B9291996-06-30030 June 1996 Rev 0 of Plant,Unit 3:Probabilistic Safety Assessment W/ Unit 2 Operating. ML18038B9281996-05-31031 May 1996 Rev 1 of Plant,Unit 2:Probabilistic Safety Assessment W/ Unit 3 Operating. ML20094G9781995-11-30030 November 1995 Evaluation to Determine Limiting Operating Condition in BFN III RPV Flaw Handbook ML18038B4811995-06-30030 June 1995 Brown Ferry Steam Electric Station Unit 2 Vessel Surveillance Matls Testing & Fracture Toughness Analysis. ML18038B3371995-06-23023 June 1995 SWS Operational Performance Insp (Swsopi) Browns Ferry Nuclear Plant. ML18038B2431995-04-0808 April 1995 Multi-Unit Pra. W/6 Oversize Encl ML18037A4461993-03-12012 March 1993 Proposed Tech Spec Amend Diesel Generator Maint Insp Frequency Change Engineering Evaluation Rept. ML20086N8271991-12-13013 December 1991 Training Dept Initial Simulator Certification ML20072R2401991-01-16016 January 1991 Operational Readiness Review Rept,Final Phase ML20059L5771990-09-30030 September 1990 Rev 2 to Browns Ferry Nuclear Plant Cable Issues Supplemental Rept Corrective Actions ML20064B4191990-09-30030 September 1990 Rev 3 to Cable Issues Supplemental Rept Corrective Actions ML20058C7101990-09-10010 September 1990 Response to Operational Readiness Review Phase Two Rept ML18033B0851989-11-30030 November 1989 Rev 3 to Electrical Cable Separations Rept, Clarifying Pages 4 & 35a of Rept ML19327B4581989-10-0606 October 1989 Rev 2 to Electrical Cable Separations Rept. ML19325C4121989-09-15015 September 1989 Seismic Assessment of Browns Ferry 2 Reactor Vessel & Internals. ML20245H3481989-08-31031 August 1989 Evaluation of Browns Ferry Nuclear Unit 2 Instrument Sense Line Issues ML20245G0651989-06-0909 June 1989 Operational Readiness Review Interim Rept,Browns Ferry Unit 2 ML20245C2901989-06-0808 June 1989 Rev 3 to Cable Issues Walkdown Rept ML20244B9211989-05-26026 May 1989 Rev 1 to Electrical Cable Separations Rept ML20245A9131989-04-13013 April 1989 Rev 2 to Test to Determine Ampacity De-Rating Effects of Cable Coatings & to Confirm Principle of Load Diversity ML20245C2751989-03-22022 March 1989 Rev 1 to Mar 1989 Evaluation of Browns Ferry Nuclear Plant Cable Installation Concerns, Summary Rept ML20247A5581989-03-0101 March 1989 Rev 1,Vol V to TVA Welding Project Browns Ferry Phase II Review ML20248H2351989-02-14014 February 1989 Vol 1,to Engineering Evaluations in Support of 10CFR50 App R Submittal for Browns Ferry Nuclear Power Plant ML20153G8081988-08-31031 August 1988 Mgt Self-Assessment (MSA) of Readiness for Restart ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20151E7231988-06-30030 June 1988 Evaluation of Browns Ferry Nuclear Plant Cable Installation Concerns ML20238E5481987-12-31031 December 1987 Safe End Replacement:Util Perspective ML20238E5081987-12-31031 December 1987 Rept of Pipe Insps,Corrective Actions & Analyses,Browns Ferry Nuclear Plant,Unit 2,Cycle 5 Outage ML20147J3141987-11-21021 November 1987 Vol V to, Welding Project Browns Ferry Nuclear Plant Phase II Review ML20237K8201987-08-26026 August 1987 TVA Employee Concerns Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-2, Review of Nuclear Safety Review Staff Non-Startup Items at Bellefonte ML20151Z0561987-08-18018 August 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-16-BFN, Structural Steel Preweld Insps at Browns Ferry Nuclear Plant ML20237K7691987-08-0606 August 1987 Rev 3 to TVA Employee Concern Special Program Browns Ferry Nuclear Plant Element Rept BFN-NSRS-1, Review of Nuclear Safety Review Staff Restart Items at Browns Ferry ML20237K7981987-07-28028 July 1987 Rev 1 to TVA Employee Concerns Special Program Browns Ferry Nuclear Plant Element Rept BFN-NSRS-2, Review of Nuclear Safety Review Staff Non-Restart Items at Browns Ferry ML20237K8081987-07-23023 July 1987 Rev 0 to TVA Employee Concern Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-1, Review of Nuclear Safety Review Staff Startup Items at Bellefonte ML20151Z0731987-07-18018 July 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-32-BFN, Adequacy of Structural Support Welds at Browns Ferry Nuclear Plant ML20151Z0381987-05-21021 May 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-06-BFN, Inspector Training & Certification at Browns Ferry Nuclear Plant ML20151Z0281987-05-11011 May 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-04-BFN, Insp Tools,Browns Ferry Nuclear Plant ML20151Z0691987-05-0707 May 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-25-BFN, Weld Repairs Not Meeting ASME Code Requirements at Browns Ferry Nuclear Plant ML20151Z0791987-04-20020 April 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-35-BFN, Weld Insp Procedures at Browns Ferry Nuclear Plant ML20151Z0241987-04-17017 April 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-03-BFN, Welder Qualification & Continuity at Browns Ferry Nuclear Plant ML20151Z0671987-04-16016 April 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-24-BFN, Welder Qualification at Browns Ferry Nuclear Plant ML20151Z0501987-04-0606 April 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-13-BFN, Welding Equipment ML20151Z0451987-04-0606 April 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-07-BFN, Welder Training & Experience at Browns Ferry Nuclear Plant ML20151Z0151987-04-0404 April 1987 Rev 0 to Welding Project Employee Concern Evaluation Rept WP-02-BFN, Insp of Welds Through Carbo-Zinc Primer at Browns Ferry Nuclear Plant 1999-08-31
[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
BROWNS FERRY NUCLEAR PLANT ELECTRICAL CABLE SEPARATIONS REPORT (Revision 3)
Prepared by Date Reviewed by Tlirt Ca/f 5' ec o Date // P8-Reviewed by Sod Z ]N 8'c'ate f QZ cP$
Reviewed by Date /I 2 / 8/
Approved by Date Approved by Date l/X+ ~f 0425e/5/BFN 8912200227 891214 PDR ADOCK 05000260 P PNU
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Nondivisional V3 cables which originate from nonsafety-related power supplies (Subsection 4.5).
Nondivisional Vl and V2 cables which originate from both safety-related and nonsafety-related power supplies (Subsection 4.6).
Divisional and nondivisional cables designated with an "IE" suffix (Subsection 4.7).
Nondivisional V4 and V5 cables contained in the project Q-List (Subsection 4.8).
Nondivisional V3 cables contained in the project Q-List (Subsection 4.9).
Nondivisional Vl and V2 cables contained in the project Q-List (Subsection 4.10).
Divisional Vl and V2 cables (Subsection 4.11)
Evaluation of cables contained in divisional and nondivisional cable trays that physically connect (Subsection 4.12).
Other than potential discrepancies in the "IE" cable population and those nondivisional V3 cables in the project Q-list, no known design separation discrepancies existed for V3 divisional cables. Therefore, these cables were not chosen as a separate population to review. However, during the course of the Appendix R and ampacity reviews, a total of 168 safety-related V3 cables were field verified and their routing evaluated. The results of those evaluations did not reveal any problems which would indicate any further review was required. These evaluations were performed using the present separations criteria (BFN-50-728 Rl).
TVA recently issued Design Input Memorandum (DIM) BFN-50-728-1 which is an advance revision notice to design criteria BFN-50-728. This DIM allows exceptions for nonsafety-related power cables to share a power supply and enclosure with one safety-related division and an enclosure or raceway with the other safety-related division if the circuit is provided with protection consisting of two safety-related electrical protection devices to prevent it from degrading safety-related circuitry. A safety-related protection device may consist of a qualified Class lE breaker or a qualified or non-qualified fuse because of its operation (fails safe).
Exceptions are also allowed for nonsafety-related instrumentation and low voltage control circuitry to be routed with both safety-related divisions when an analysis demonstrates the absence of adverse interactions between safety-related circuitry and associated nonsafety-related circuits.
Each of the specific cable population evaluations considered this DIM to be either an acceptable method for satisfying the separation criteria or an acceptable corrective action for any discrepancies that might be identified. The methodology used in these evaluations and the results are contained in Section 4.0 of this report.
0425e/1/BFN
1 The only potential source of damage to divisional V1/V2 cables is from an external source such as jet impingement, pipe whip,missle, seismic event, or fire. TVA's pipe rupture evaluations have confirmed that safety is not compromised as a result of jet impingement, (both inside and outside containment), pipe whip (both inside and outside containment), and externally generated missles inside containment because safety related raceways are not affected as a result of these events. This evaluation is documented in Civil Engineering Branch Report CEB 88-06-C, entitled "Pipe Rupture Evaluation Program for Inside and Outside Pr'imary Containment for Browns Ferry Nuclear Plant Unit 2" (B41881114005). TVA has evaluated the Vl/V2 cables for potential damage from missles outside containment and concluded that cables of redundant functions are not affected in any area susceptible to externally generated missles.
This review is documented by QIR BFEBFN89086 (B22890928009).
All raceway in Category I structures are seismically supported and documented in QIRCEBBFN88155 (B22881018021).
All piping in a Category I structure is seismically supported at a minimum position retention. This evaluation is documented in EQE Report Number 51001.02-R-001 Revision 0 dated July 11, 1989 "Evaluation of Seismic-Induced Spray Hazards at BFNP" attached to TVA calculation CD-Q0999-894853 (B22 890930 101) and NUREG-1232, Volume 3, supplement 1 "Safety Evaluation Report on Tennessee Valley Authority:
Browns Ferry Nuclear Performance Plan." The only remaining source of damages is from an external fire. TVA has field verified the 62 Vl/V2 Appendix R required cables identified in QIR TEPBFN89038. No corrective actions are required.
This field verification is documented by QIR BFEBFN89055.
4.12 Evaluation of Cables Contained in Divisional and Nondivisional Cable Tra s that Ph sicall Connect While performing the evaluation of field verified cable data in section 4.1, drawing discrepancies for unit 3 cables were identified where divisional cable was routed on nondivisional cable tray. The reason for this is that in some instances divisional trays and nondivisional trays are physically attached as shown in Figure 4.12 with a common intersection node point in the Unit 3 computer cable routing program.
Since the Unit 3 computer cable routing program automatically routes cables, it was possible for nondivisional cables to route undetected through these divisional/nondivisional intersections and then route in an opposite division tray.
The purpose of this evaluation was to identify these situations and evaluate the cables common to these intersections to determine conformance to the separations
'riteria.
0304e/38
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