Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20217L8931999-10-31031 October 1999
Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs
ML20210K8831999-07-29029 July 1999
Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates
ML20196A6251999-05-31031 May 1999
Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML20248D6011998-03-31031 March 1998
Suppl 9 to CENPD-279, Annual Rept on ABB CE ECCS Performance Evaluation Models
ML20203H6701998-01-31031 January 1998
Rev 0 to non-proprietary Version of BAW-10232, OTSG Repair Roll Qualification Rept (Including Hydraulic Expansion Evaluation)
ML20199G9531998-01-31031 January 1998
Non-proprietary Alternate Repair Criteria for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once- Through Sgs
ML20211N4921997-09-30030 September 1997
Rev 1 to SIR-94-080-A, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements
ML20135F3681996-11-30030 November 1996
Non-proprietary Final Rept Repair of 3/4 O.D. SG Tubes Using Leak Tight Sleeves
ML20112E8491996-02-28028 February 1996
Suppl 7 to Annual Rept of ABB C-E ECCS Performance Evaluation Models
ML17353A4341995-10-31031 October 1995
Rev 1 to BAW-2245, Initial RT of Linde 80 Welds Based on Fracture Toughness in Transition Range
ML17264A1181995-07-31031 July 1995
Response to Part (1) of GL 92-01,Rev 1,Suppl 1
ML17311B3581995-05-31031 May 1995
Joint Applications Rept for Low Pressure Safety Injection Sys AOT Extension
ML20083Q9261995-05-30030 May 1995
Joint Applications Rept for Safety Injection Tank Aot/Sti Extension
ML20083Q9861995-05-30030 May 1995
Joint Applications Rept for Emergency Diesel Generators AOT Extension
ML20085H3221995-02-28028 February 1995
Suppl 6 to Topical Rept CENPD-279, Annual Rept on ABB CE ECCS Performance Evaluation Models,Final Rept,Ceog Task 865, Dtd Feb 1995
ML20073D4561994-09-30030 September 1994
Verification of Cecor Coefficient Methodology for Application to PWRs of Entergy Sys
ML20069D4261994-02-28028 February 1994
Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46
ML20063C7571993-12-31031 December 1993
Qualification of Reactor Methods for Pressurized Water Reactors of Entergy Sys
ML20081K9821991-05-31031 May 1991
Final Rept on Reactor Vessel App G Pressure-Temp Limits for Arkansas Nuclear One Unit 2 for 21 Efpys
ML20067A5241990-12-31031 December 1990
Final Submittal in Response to NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification
ML16162A7041990-12-31031 December 1990
Final Submittal for NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification
ML20042F3391990-04-30030 April 1990
Suppl 1 to Responses to Questions on C-E Rept CEN-386-P, Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for C-E 16X16 PWR Fuel
ML20059M4481990-03-31031 March 1990
Unit 1 Pressure-Temp Limits for 15 Efpy
ML20034B7071989-10-31031 October 1989
Rev 1 to, Analysis of Capsule AN1-C,Arkansas Nuclear One, Unit 1,Reactor Vessel Matl Surveillance Program
ML20247E3231989-06-30030 June 1989
Nonproprietary Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for C-E 16x16 PWR Fuel
ML20245G7121989-05-31031 May 1989
Submittal in Response to NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification
ML20246N3841989-04-30030 April 1989
Analysis of Capsule ANI-C,Arkansas Power & Light Co, Arkansas Nuclear One,Unit 1,Reactor Vessel Matl Surveillance Program
ML20211A1031986-09-30030 September 1986
Small Break LOCA Analysis for B&W 177FA Lowered Loop Plants in Response to NUREG-0737,Item II.K.3.31
ML20155J5231986-05-31031 May 1986
Rev 1 to Functional Design Requirement for Core Protection Calculator
ML20155J5051986-05-31031 May 1986
Rev 1 to Functional Design Requirements for Control Element Assembly Calculator
ML20155J4911986-05-31031 May 1986
Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block
ML20202B1131986-04-30030 April 1986
Nonproprietary Suppl 1,Rev 3, CPC Protection Algorithm Software Change Procedure
ML20151Z0521986-01-31031 January 1986
Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure
ML20151Z0641986-01-31031 January 1986
Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines
ML20135A9021985-09-30030 September 1985
Rev 00-NP to Overview Description of Core Operating Limit Supervisory Sys
ML20135A5571985-08-31031 August 1985
B&W Owners Group Cavity Dosimetry Program
ML20134N3021985-07-31031 July 1985
Rev 00 to Functional Design Requirement for Core Protection Calculator
ML20134N2941985-07-31031 July 1985
Rev 00 to Functional Design Requirement for Control Element Assembly Calculator
ML20129F9301985-07-31031 July 1985
Cycle 5 Shoulder Gap Evaluation
ML20100J2221985-03-31031 March 1985
Nonproprietary Rev 1 to Core Protection Calculator/Control Element Assembly Calculator Sys Phase II Software Verification Test Rept
ML20100J1991985-03-31031 March 1985
Nonproprietary Rev 0 to Arkansas Nuclear One - Unit 2 Core Protection Calculator & Control Element Assembly Calculator Data Base Listing
ML20100J1551985-03-31031 March 1985
Nonproprietary Typical Data Base Constants for Arkansas Nuclear One Unit 2
ML20100J1801985-03-31031 March 1985
Nonproprietary Rev 0 to Arkansas Nuclear One - Unit 2 Core Protection Calculator Sys Phase I Design Qualification Test Rept
ML20101U3551984-12-31031 December 1984
Nonproprietary Revised Rod Bow Penalties for Arkansas Nuclear One Unit 2
ML20107N0221984-10-31031 October 1984
Nonproprietary CPC Methodology Changes for Arkansas Nuclear One Unit 2 Cycle 5
ML20106E3251984-10-31031 October 1984
Nonproprietary Once-Through Steam Generator Mechanical Sleeve Qualification
ML20094J7101984-07-31031 July 1984
Analyses of Capsule AN1-A,Arkansas Power & Light Co, Arkansas Nuclear One,Unit 1,Reactor Vessel Matl Surveillance Program
ML20098F1361984-04-30030 April 1984
Thermal-Hydraulic Crossflow Applications
ML20083G5321983-11-30030 November 1983
Cycle 4 Shoulder Gap Evaluation
1999-07-29
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999
Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs
05000313/LER-1999-313, :on 990911,AI of EFWS Occurred During Plant Shutdown as Result of Securing Running RCPs Due to Reverse Rotation of Idle Pump.Caused by Failure of Motor anti-rotation Device.Device Was Replaced.With1999-10-11011 October 1999
- on 990911,AI of EFWS Occurred During Plant Shutdown as Result of Securing Running RCPs Due to Reverse Rotation of Idle Pump.Caused by Failure of Motor anti-rotation Device.Device Was Replaced.With
ML20217B6261999-10-0404 October 1999
Safety Evaluation Supporting Amend 202 to License DPR-51
ML20212L1141999-10-0101 October 1999
Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c
05000368/LER-1999-005-02, :on 990831,two Trip Functions of One Core Protection Calculator Channel Potentially Inoperable Longer than TS Allow Was Discovered.Caused by Resistance Fluctuations.Util Plans to Replace Switch.With1999-09-30030 September 1999
- on 990831,two Trip Functions of One Core Protection Calculator Channel Potentially Inoperable Longer than TS Allow Was Discovered.Caused by Resistance Fluctuations.Util Plans to Replace Switch.With
0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With
ML20216J6271999-09-27027 September 1999
Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr
ML20212F5261999-09-22022 September 1999
SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1
ML20212D5611999-09-14014 September 1999
Safety Evaluation Supporting Amend 200 to License DPR-51
ML20212D4091999-09-14014 September 1999
Safety Evaluation Supporting Amend 201 to License DPR-51
ML20211P9551999-09-0909 September 1999
Safety Evaluation Supporting Amend 199 to License DPR-51
0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with
ML20211K3311999-08-26026 August 1999
Safety Evaluation Supporting Amends 198 & 209 to Licenses DPR-51 & NPF-06,respectively
ML20211F4281999-08-25025 August 1999
Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety
05000313/LER-1999-002-04, :on 990706,TS Allowable Outage Time for One EDG Was Exceeded Due to Idler Gear Stub Shaft Bracket Bolting Failure.Caused by Loss of Bolt pre-load.Installed New Modified Idler Stub Shaft Assembly.With1999-08-0505 August 1999
- on 990706,TS Allowable Outage Time for One EDG Was Exceeded Due to Idler Gear Stub Shaft Bracket Bolting Failure.Caused by Loss of Bolt pre-load.Installed New Modified Idler Stub Shaft Assembly.With
0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with
ML20210K8831999-07-29029 July 1999
Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates
0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with
ML20196J2771999-06-29029 June 1999
Safety Evaluation Supporting Amend 208 to License NPF-6
05000313/LER-1999-001-04, :on 990521,automatic Actuation of CREVS Occurred Due to Higher than Normal Radiation at Detector When Radioactive Filter Was Moved in Adjacent Area.Training Has Been Provided to Personnel.With1999-06-21021 June 1999
- on 990521,automatic Actuation of CREVS Occurred Due to Higher than Normal Radiation at Detector When Radioactive Filter Was Moved in Adjacent Area.Training Has Been Provided to Personnel.With
ML20195G9531999-06-10010 June 1999
Safety Evaluation Supporting Amend 197 to License DPR-51
ML20207G2901999-06-0707 June 1999
Safety Evaluation Supporting Amend 207 to License NPF-6
ML20207E7231999-06-0202 June 1999
Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect
ML20196A6251999-05-31031 May 1999
Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs
ML20196A0191999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With
ML20195D1991999-05-28028 May 1999
Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14
ML20207A4651999-05-19019 May 1999
Safety Evaluation Supporting Amend 205 to License NPF-6
ML20207B7071999-05-19019 May 1999
Safety Evaluation Supporting Amends 196 & 206 to Licenses DPR-51 & NPF-6,respectively
05000368/LER-1999-004-01, :on 990414,noted That Two Trip Functions of One Core Protection Calculator Channel Were Potentially Inoperable.Caused by Excore Detector Drift.Affected Trip Functions Have Remained Bypassed or Tripped.With1999-05-12012 May 1999
- on 990414,noted That Two Trip Functions of One Core Protection Calculator Channel Were Potentially Inoperable.Caused by Excore Detector Drift.Affected Trip Functions Have Remained Bypassed or Tripped.With
ML20206M7711999-05-11011 May 1999
SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2
0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with
ML20206F0691999-04-29029 April 1999
Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1
ML20205Q7721999-04-16016 April 1999
Safety Evaluation Supporting Amends 195 & 203 to Licenses DPR-51 & NPF-6,respectively
ML20205M6941999-04-12012 April 1999
Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1
ML20205D6061999-03-31031 March 1999
Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel
ML20205R6351999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with
ML20205D4711999-03-26026 March 1999
SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2
05000368/LER-1999-003, :on 990224,noted That One Excore Nuclear Instrumentation Channel Was Inoperable Longer than Allowed by Ts.Caused by Detector Failure.Proposed Exigent TS Change Was Submitted to Allow Operation.With1999-03-23023 March 1999
- on 990224,noted That One Excore Nuclear Instrumentation Channel Was Inoperable Longer than Allowed by Ts.Caused by Detector Failure.Proposed Exigent TS Change Was Submitted to Allow Operation.With
ML20204H7451999-03-23023 March 1999
Safety Evaluation Supporting Amend 202 to License NPF-6
ML20204B1861999-03-15015 March 1999
Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5)
05000368/LER-1999-001, :on 990108,TS Requirements for as-lift Settings of MSSV Were Not Met.Caused by Errors in Determination of Effective Seating Area by Vendor During Test Device Qualification.Replaced All Mssvs.With1999-03-0909 March 1999
- on 990108,TS Requirements for as-lift Settings of MSSV Were Not Met.Caused by Errors in Determination of Effective Seating Area by Vendor During Test Device Qualification.Replaced All Mssvs.With
05000368/LER-1999-002-01, :on 990202,noted Failure to Verify Station Battery cell-to-cell & Terminal Tightness.Caused by Inadvertent Omission of Requirements During Procedure Revs. Svc Test Procedures Were Revised.With1999-03-0404 March 1999
- on 990202,noted Failure to Verify Station Battery cell-to-cell & Terminal Tightness.Caused by Inadvertent Omission of Requirements During Procedure Revs. Svc Test Procedures Were Revised.With
0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with
ML20212G6381999-02-25025 February 1999
Ano,Unit 2 10CFR50.59 Rept for 980411-990225
ML20203E4891999-02-11011 February 1999
Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14
05000368/LER-1999-001-01, :on 990108,four Main Steam Safety Valves as- Found Lift Values Failed to Meet TS Requirements.Cause of Evaluation in progress.Short-term & long-term Corrective Actions Will Be Described in Suppl to Rept.With1999-01-28028 January 1999
- on 990108,four Main Steam Safety Valves as- Found Lift Values Failed to Meet TS Requirements.Cause of Evaluation in progress.Short-term & long-term Corrective Actions Will Be Described in Suppl to Rept.With
ML20202B4581999-01-26026 January 1999
Safety Evaluation Supporting Amend 200 to License NPF-6
05000313/LER-1998-005-03, :on 981225,two Manual RTs & Manual Actuations of EFWS Due to Reduced Cw Flow to Mc.Caused by Large Intrusions of Fish Exceeding Removal Capability of Traveling Screen.Increased Fish Removal Capability.With1999-01-21021 January 1999
- on 981225,two Manual RTs & Manual Actuations of EFWS Due to Reduced Cw Flow to Mc.Caused by Large Intrusions of Fish Exceeding Removal Capability of Traveling Screen.Increased Fish Removal Capability.With
ML20199F7931999-01-19019 January 1999
Safety Evaluation Supporting Amend 199 to License NPF-6
05000368/LER-1998-008-01, :on 981215,one CR Emergency Chiller,Part of CREVS Discovered to Be Inoperable,While Chiller in Other Train Was Out of Svc for Planned Maint.Caused by Equipment Failure.Operations Personnel Verified.With1999-01-14014 January 1999
- on 981215,one CR Emergency Chiller,Part of CREVS Discovered to Be Inoperable,While Chiller in Other Train Was Out of Svc for Planned Maint.Caused by Equipment Failure.Operations Personnel Verified.With
1999-09-09
[Table view] |
