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Issue date | Title | Topic | |
---|---|---|---|
ML20210P918 | 10 August 1999 | Safety 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 Part | Coatings Nondestructive Examination VT-2 Moisture barrier |
ML20210P944 | 10 August 1999 | Safety 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 Risers | Safe Shutdown Earthquake Stress corrosion cracking |
ML20210N234 | 5 August 1999 | SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 | Safe Shutdown Safe Shutdown Earthquake Design basis earthquake Earthquake Manual Operator Action |
ML20206G187 | 4 May 1999 | Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 | Incorporated by reference Stress corrosion cracking |
ML20205F903 | 30 March 1999 | Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively | |
ML20203D706 | 9 February 1999 | SER 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 Denied | Reactor Vessel Water Level Stroke time Incorporated by reference Excess Flow Check Valve Breakaway torque Cold shutdown justification Overspeed trip |
ML20154P859 | 16 October 1998 | SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2 | Incorporated by reference |
ML20154P815 | 16 October 1998 | SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1 | |
ML20217K394 | 24 April 1998 | SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2 | Incorporated by reference |
ML20217K846 | 24 April 1998 | Safety 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 1.147 | Incorporated by reference |
ML20217E684 | 23 April 1998 | Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD Housings | Incorporated by reference |
ML20217E747 | 21 April 1998 | Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds | Incorporated by reference |
ML20217B524 | 20 April 1998 | SE 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 |
ML20216B104 | 4 March 1998 | SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1 | Incorporated by reference |
ML20198J092 | 18 September 1997 | Safety 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 | |
ML20198H235 | 8 September 1997 | Safety 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 & 2 | Incorporated by reference |
ML20137A483 | 18 March 1997 | SER Re CP&L Review of Power Uprate Process & Commitment Preventing Operation at Uprated Power Levels for Plant, Units 1 & 2 | Time of Discovery Reactor Vessel Water Level Fuel cladding Power Uprate |
ML20129E082 | 26 September 1996 | Safety 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 & 2 | Incorporated by reference |
ML20056D676 | 28 July 1993 | Safety Evaluation Concluding That Interior Masonry Walls May Be Downgraded to non-fire Related | Safe Shutdown Fire Barrier Fire Protection Program |
ML20128K771 | 11 February 1993 | Safety Evaluation Granting Relief from Certain Inservice Testing Program Requirements for Several Pumps & Valves | Incorporated by reference Thermography |
ML20198E508 | 23 November 1992 | Safety Evaluation Accepting Licensee 120-day Response to Suppl 1 to GL 87-02 | Safe Shutdown Earthquake Earthquake |
ML20247K253 | 11 September 1989 | Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively | |
ML20247E376 | 7 September 1989 | Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | Offsite Dose Calculation Manual Process Control Program |
ML20246D681 | 18 August 1989 | Safety 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 | |
ML20248C073 | 3 August 1989 | Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants | |
ML20246C420 | 27 June 1989 | SER Accepting Util Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Operating Reactors | |
ML20246L257 | 26 June 1989 | Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | |
ML20247P620 | 1 June 1989 | Safety Evaluation Supporting Util SAFER/GESTR-LOCA Analysis | |
ML20247M191 | 25 May 1989 | Safety Evaluation Re Denial of Amend Request to Licenses DPR-71 & DPR-62 | Half scram |
ML20246P940 | 10 May 1989 | Safety Evaluation Accepting Plant Second 10-yr Interval Inservice Insp Program | Incorporated by reference |
ML20246J553 | 9 May 1989 | Safety 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 IGSCC | Non-Destructive Examination Weld Overlay Nondestructive Examination Stress corrosion cracking |
ML20245J075 | 25 April 1989 | Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | |
ML20245D376 | 25 April 1989 | Safety Evaluation Supporting Licensee IGSCC Program for Refuel 7 Outage | Non-Destructive Examination Weld Overlay Nondestructive Examination Finite Element Analysis Stress corrosion cracking Liquid penetrant Through Wall Leak Unidentified leakage |
ML20236D548 | 17 March 1989 | Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability | |
ML20236D538 | 17 March 1989 | Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for safety-related Components | |
ML20236D464 | 15 March 1989 | Safety Evaluation Re Generic Ltr 83-28,Item 2.1 (Parts 1 & 2) Concerning Equipment Classification & Vendor Interface for Reactor Trip Sys Components | |
ML20235Z345 | 8 March 1989 | Safety Evaluation Supporting Util Compliance W/Atws Rule, 10CFR50.62 Re Power Testability Features of Alternate Rod Insertion Sys & Recirculating Pump Trip Design | |
ML20235Z284 | 8 March 1989 | Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.2.1 & 3.2.2 | |
ML20235M577 | 16 February 1989 | Safety Evaluation Supporting Control Room Habitability Sys of Plant & Acceptability of Existing Tech Spec Re Control Room Pressurization Requirement | |
ML20205Q572 | 31 October 1988 | SER 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 & Security | Exemption Request |
ML20205Q576 | 31 October 1988 | SER 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 & Security | Exemption Request |
ML20205M573 | 26 October 1988 | Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | |
ML20155G480 | 28 September 1988 | Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively | |
ML20195G553 | 24 June 1988 | Safety 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 | |
ML20154H217 | 18 May 1988 | Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program | |
ML20147G066 | 2 March 1988 | Safety Evaluation Supporting Proposed Functional Testing Plan for Snubbers | |
ML20147D963 | 25 February 1988 | Safety 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 | |
ML20147E926 | 23 February 1988 | Safety Evaluation Supporting Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively | |
ML20236M963 | 6 November 1987 | Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue | Anticipated operational occurrence |
ML20236L200 | 30 October 1987 | Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72 |