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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
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. WELDING PROJECT EMPLOYEE CONCERN EVALUATION REPORT WELDING EQUIPMENT PREPARED BY M* M/[7 WP/ECTG u
REVIEWED BY \ iP. % bl/ (#fl, DNC/WP 4!n!o7 REVIEWED BY
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APPROVED BY a)ALLb Vk M- PROGRAM MANAGER N
FM Report Number WP-13-BFN Re ision 0 Date ~ /$ ~ 0 7 8808290148 880822 PDR ADOCK 050 g 9 P
11860
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WP-13-BFN l Revision 0 EMPLOYEE CONCERN ,
1
SUMMARY
SHEET 1 WELDING EQUIPMENT AT BROWNS FERRY l
NUCLEAR PLANT I. SCOPE OF EVALUATION This report addresses two employee concerns dealing with the welding equipment used at Browns Ferry Nuclear Plant (BFN). These concerns were grouped into two issues to aid in the evaluation effort.
A. Welding machines do not have suitable amperage settings for welding with 3/32 inch diameter electrodes which leads to porosity and pinholes.
B. Welding machines should have remote switches to prevent tungsten inclusions.
II. ANALYSIS OF ISSUES ADDRESSED BY CONCERNS The issues addressed by this evaluation evolved from Watts Bar concerns that were applied to Browns Ferry for evaluation for generic '
implication.
A. One issue stated that the McKay and Hobart welding machines only provided a 50 and 100 amp setting which is unsuitable for welding with 3/32 inch diameter electrodes and contributes to porosity and pinholes. Browns ferry utilized the Lincoln Idealare TIG 300, K1312 which has a current output range of 2-375 amps in both AC and DC.
This issue is discussed in WP-13-BFN, Paragraph III A.
B. One issue stated that all welding machines should have remote switches for are starting to prevent tungsten inclusions. The Lincoln Idealarc TIG 300 has the remote switches for are starting and current control adjustment.
This issue is addressed in WP-13-BFN, Paragraph III B.
III. COLLECTIVE SIGNIFICANCE No collective significance was identified in that Browns Ferry did not utilize the welding machines addressed by the concerns.
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WP-13-BFN Revision 0 IV. ROOT CAUSE(S)
The root cause of the employee concerns in this area is the TVA decision to apply Watts Bar employee concerns to other nuclear sites for evaluation for generic implications.
V. CORRECTIVE ACTION No corrective action is indicated.
VI. REINSPECTION REQUIRED ._
No.
VII. ISSUE CLOSURE Closed.
VIII. ATTACHMENTS
- 1. Evaluation Report WP-13-BFN.
i 11860 Pago 2 of 2
(' WP-13-BFN Revision 0 p
WELDING PROJECT EMPLOYES CONCERN EVALUATION REPORT WELDING EQUIPMENT AT BROVNS FERRY i
NUCLEAR PLANT
~~
I. SCOPE OF EVALUATION This report addresses two employee concerns. Text of the concerns is provided Under Attachment 1.
The subject concerns originated at Watts Bar Nuclear Plant, and were generically applied to Browns Ferry Nuclear Plant (BFN). This evaluation is based on review of the BFN Welding Phase I Report, current and superseded process specifications and implementing procedures, and the Welding Project Report WP-13-SQN. Also reviewed were the BFN Corrective Action Reports, Discrepancy Report's, Nonconformance Reports, and the AEC/USNRC Inspection Reports. The Americen Society of Mechanical Engineers (ASME) Boiler and Pressure .
Vessel Code Section III and The USA Standard for Pressure Piping i B31.1.0 were reviewed for applicability to the text of the concerns.
The findings presented herein are based upon review of the above noted documents and interviews with cognizant TVA personnel.
II. ISSUES ADDRESSED BY CONCERNS A. Welding machines do not have suitable amperage settings for welding with 3/32 inch diameter electrodes which leads to porosity and pinholes.
B. Welding machines should have remote switches to prevent tungsten inclusions.
III. ANALYSIS OF ISSUES ADDRESSED ~BY CONCERNS A. One concern stated that welding machines (McKay and Hobart) used by steamfitters have only two settings, 50 and 100 amps, which are unsuitable for use with 3/32 inch diameter electrodes and that contributes to porosity and pinholes.
There is no mandated requirement for the type welding equipment to be used. The choice of particular types of welding equipment is based on overall management and engineering judgements relative to the type activities to be accomplished, space limitations, and equipment availability and suitability.
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WP-13-BFN Revision 0 Browns Ferry has, since beginning cor.straction, used Lincoln Idealarc TIG 300, K1312 Welding machines. These machines have a current output range of 2-375 amps in both AC and DC and have remote current adjustment controls. Both the GAS Tungsten Arc Welding (GTAW) and the Shielded Metal Arc Welding (SMAW) processes can be used with this equipment.
Welding equipment, normally grid banks and multiple operator units, with only a 50 and 100 amp range, not fixed, settings are suitable for use and are used throughout the industry and have a history of satisfactory performance. These machines do have fine current ._
adjustment features. Depending on the type, these machines can be adjusted in 2 1/2 or 5 amp increments. Each will produce current ranges required by the Browns Ferry Detail Weld Procedures. The use and capability of these machines are discussed in detail in Wold Project Report WP-13-SQN.
B. One concern stated that all welding machines should have remote switches for are starting to prevent tungsten inclusions in the weld.
The Lincoln Idealare TIG 300 used at Browns Ferry has the remote switch to assist in smooth are starting. A detailed discussion on prevention of tungsten inclusions, when using other types of welding machines, is included in the Weld Project Report VP-13-SQN.
IV. COLLECTIVE SIGNIFICANCE None. Browns Ferry did not use the types of welding equipment addressed by the issues. ,
V. ROOT CAUSE(S)
The reason for the employee concerns relating to welding equipment is the application of Watts Bar concerns to other TVA sites for evaluation for generic implications.
VI. CORRECTIVE ACTION 4
No corrective action is indicated.
VII. ATTACHMENTS
- 1. Employee concerns, f
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WP-13-BFN -
Revision 0 i WELDING PROJECT EMPLOYEE CONCERN EVALUATION REPORT ATTACHMENT 1 TEXT OF EMPLOYEE CONCERNS Evaluation Report WP-13-BFN addresses two employee concerns. The text of the .
concerns is shown on the following page.
IN-85-247-002 IN-85-303-001 I
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