Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ML20210P91810 August 1999Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in PartCoatings
Nondestructive Examination
VT-2
Moisture barrier
ML20210P94410 August 1999Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump RisersSafe Shutdown Earthquake
Stress corrosion cracking
ML20210N2345 August 1999SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46Safe Shutdown
Safe Shutdown Earthquake
Design basis earthquake
Earthquake
Manual Operator Action
ML20206G1874 May 1999Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17Incorporated by reference
Stress corrosion cracking
ML20205F90330 March 1999Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively
ML20203D7069 February 1999SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 DeniedReactor Vessel Water Level
Stroke time
Incorporated by reference
Excess Flow Check Valve
Breakaway torque
Cold shutdown justification
Overspeed trip
ML20154P85916 October 1998SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2Incorporated by reference
ML20154P81516 October 1998SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1
ML20217K39424 April 1998SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2Incorporated by reference
ML20217K84624 April 1998Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147Incorporated by reference
ML20217E68423 April 1998Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD HousingsIncorporated by reference
ML20217E74721 April 1998Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential WeldsIncorporated by reference
ML20217B52420 April 1998SE Accepting Licensee Request for Approval to Use Alternative Exam Requirement for Brunswick,Unit 1,reactor Vessel Stud & Bushing During Second 10-yr ISI Interval Per 10CFR50.55a(a)(3)(ii)VT-2
Incorporated by reference
ML20216B1044 March 1998SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1Incorporated by reference
ML20198J09218 September 1997Safety Evaluation Authorizing Licensee & Suppls & 16 Request for Approval of Alternative Reactor Vessel Weld Exam,Per 10CFR50.55a(g)(6)(ii)(A)(5) for Plant, Unit 2 for Next 2 Operating Cycles
ML20198H2358 September 1997Safety Evaluation Approving Licensee 970311 Request for Use of ASME Code Case N-509 & Relief from ASME Code Section IX Requirements for Exam of Hpcip Studs for Plant,Units 1 & 2Incorporated by reference
ML20137A48318 March 1997SER Re CP&L Review of Power Uprate Process & Commitment Preventing Operation at Uprated Power Levels for Plant, Units 1 & 2Time of Discovery
Reactor Vessel Water Level
Fuel cladding
Power Uprate
ML20129E08226 September 1996Safety Evaluation Supporting Request to Use Certain Portions of Later Edition of ASME Code for Inservice Leakage Testing Valves for Brunswick Steam Electric Plant Units 1 & 2Incorporated by reference
ML20056D67628 July 1993Safety Evaluation Concluding That Interior Masonry Walls May Be Downgraded to non-fire RelatedSafe Shutdown
Fire Barrier
Fire Protection Program
ML20128K77111 February 1993Safety Evaluation Granting Relief from Certain Inservice Testing Program Requirements for Several Pumps & ValvesIncorporated by reference
Thermography
ML20198E50823 November 1992Safety Evaluation Accepting Licensee 120-day Response to Suppl 1 to GL 87-02Safe Shutdown Earthquake
Earthquake
ML20247K25311 September 1989Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively
ML20247E3767 September 1989Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectivelyOffsite Dose Calculation Manual
Process Control Program
ML20246D68118 August 1989Safety Evaluation Supporting Installation & Design of Nitrogen Pneumatic Sys,Per Generic Ltr 84-09,by Adding New Check Valves to Existing Drywell Noninterruptible Instrument Air Lines
ML20248C0733 August 1989Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants
ML20246C42027 June 1989SER Accepting Util Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Operating Reactors
ML20246L25726 June 1989Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20247P6201 June 1989Safety Evaluation Supporting Util SAFER/GESTR-LOCA Analysis
ML20247M19125 May 1989Safety Evaluation Re Denial of Amend Request to Licenses DPR-71 & DPR-62Half scram
ML20246P94010 May 1989Safety Evaluation Accepting Plant Second 10-yr Interval Inservice Insp ProgramIncorporated by reference
ML20246J5539 May 1989Safety Evaluation Concluding That Plant Can Be Safely Operated for Another 18-month Fuel Cycle in Configuration Following Reload 5,per Improvements,Insps & Repairs to Plant IGSCCNon-Destructive Examination
Weld Overlay
Nondestructive Examination
Stress corrosion cracking
ML20245J07525 April 1989Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20245D37625 April 1989Safety Evaluation Supporting Licensee IGSCC Program for Refuel 7 OutageNon-Destructive Examination
Weld Overlay
Nondestructive Examination
Finite Element Analysis
Stress corrosion cracking
Liquid penetrant
Through Wall Leak
Unidentified leakage
ML20236D54817 March 1989Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability
ML20236D53817 March 1989Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for safety-related Components
ML20236D46415 March 1989Safety Evaluation Re Generic Ltr 83-28,Item 2.1 (Parts 1 & 2) Concerning Equipment Classification & Vendor Interface for Reactor Trip Sys Components
ML20235Z3458 March 1989Safety Evaluation Supporting Util Compliance W/Atws Rule, 10CFR50.62 Re Power Testability Features of Alternate Rod Insertion Sys & Recirculating Pump Trip Design
ML20235Z2848 March 1989Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.2.1 & 3.2.2
ML20235M57716 February 1989Safety Evaluation Supporting Control Room Habitability Sys of Plant & Acceptability of Existing Tech Spec Re Control Room Pressurization Requirement
ML20205Q57231 October 1988SER Re Const Mod & Licensing of Company Facility-1 Cpdf. Licensee Technically Qualified to Modify Existing Facility in Such Way as to Assure Adequate Protection of Common Defense & SecurityExemption Request
ML20205Q57631 October 1988SER Re Application for CP for Alchemie Facility-2 Oliver Springs.Licensee Technically Qualified to Construct & Operate Proposed Facility in Such Way as to Assure Adequate Protection for Common Defense & SecurityExemption Request
ML20205M57326 October 1988Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20155G48028 September 1988Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively
ML20195G55324 June 1988Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pools from Criticality Standpoint.Enrichment of Fuel to 4.5 Weight % U-235 May Be in Conflict W/ 10CFR51 Table S4 & Should Be Investigated by NRC
ML20154H21718 May 1988Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program
ML20147G0662 March 1988Safety Evaluation Supporting Proposed Functional Testing Plan for Snubbers
ML20147D96325 February 1988Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90
ML20147E92623 February 1988Safety Evaluation Supporting Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively
ML20236M9636 November 1987Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec IssueAnticipated operational occurrence
ML20236L20030 October 1987Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72