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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
ML20154P815	16 October 1998	SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1
ML20154P859	16 October 1998	SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for 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
ML20217K394	24 April 1998	SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2	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
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
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
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
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
ML20235Z284	8 March 1989	Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.2.1 & 3.2.2
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
ML20235M577	16 February 1989	Safety Evaluation Supporting Control Room Habitability Sys of Plant & Acceptability of Existing Tech Spec Re Control Room Pressurization Requirement
ML20147G066	2 March 1988	Safety Evaluation Supporting Proposed Functional Testing Plan for Snubbers
ML20236D131	22 October 1987	Safety Evaluation Re Util Request for Relief from Schedular Requirements for Performance of Visual Insp & Hydrostatic Test of CRD Withdrawal & Insert Lines.Granting of Request Recommended	Hydrostatic VT-2 Pressure Boundary Leakage
ML20235A733	18 September 1987	Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable
NUREG-0661, Safety Evaluation Re Util 840831 Submittal of Addendum to Plant Unique Analysis Rept on Mark I Containment Mod Program.Safety/Relief Valve Load Cases C3.2 & C3.3 Adequately Addressed & Resolved	7 May 1987	Safety Evaluation Re Util 840831 Submittal of Addendum to Plant Unique Analysis Rept on Mark I Containment Mod Program.Safety/Relief Valve Load Cases C3.2 & C3.3 Adequately Addressed & Resolved
ML20212H567	16 January 1987	Safety Evaluation Supporting Util Response to Generic Ltr 83-08 Re Restoring Safety Margins of Vacuum Breakers by Replacing Critical Parts W/Adequate Matls
ML20207A853	5 November 1986	Safety Evaluation Supporting Operation for Full Fuel Cycle W/O mid-cycle Insp for Crack Growth
ML20215N377	30 October 1986	Safety Evaluation Re Util 860320 Response to Generic Ltr 84-09, Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii). Licensee Should Remove All Potential Oxygen Sources from Containments	Probabilistic Risk Assessment
ML20203N008	17 September 1986	Safety Evaluation Supporting Util 850919 Request for Relief from Installing Excess Flow Switch & Automatic Shutoff Valve in Diesel Fire Pump Fuel Line to Provide Protection in Event of Fuel Line Rupture	Fire Barrier
ML20212N020	22 August 1986	Safety Evaluation Denying Util 860325 Request for Relief from Inservice Insp Requirements of ASME Code Section XI, Table IWC-2500-1 for Volumetric Exam of HPCI Pump Studs	VT-2
ML20211G608	12 June 1986	Safety Evaluation Supporting IGSCC Insp,Repair & Replacement Program During Dec 1985 Refueling Outage	Weld Overlay Liquid penetrant
ML20205S254	4 June 1986	Safety Evaluation Accepting Rev 2 to Nuclear Const Issues Group Spec 1, Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants, for non-ASME Code Welds
ML20211A828	3 June 1986	Safety Evaluation Re Rev 4 to Offsite Dose Calculation Manual.Rev Acceptable	Offsite Dose Calculation Manual
ML20198S728	29 May 1986	Safety Evaluation Supporting 851203 Proposal to Modify Tech Spec 3/4.5.3 to Clarify Min Amount of Condensate Storage Tank Water Required to Ensure Operability of Core Spray Sys During Operating Conditions 4 or 5.Rev to Tech Specs Encl
ML20133N414	23 October 1985	Safety Evaluation Re Util 831107 & 850828 Responses to Generic Ltr 83-28,Items 3.1.2 & 3.2.1 & 850701 Request for Addl Info.Responses Re Vendor & Engineering Test Guidance & Testing Requirements After Maint Acceptable
ML20134P521	28 August 1985	Safety Evaluation Approving Use of ASME Code Case N-411 for Damping Curves	Safe Shutdown Earthquake Operating Basis Earthquake Earthquake
ML20128M291	16 July 1985	Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28, Salem ATWS Event, Items 3.1.3 & 3.2.3 Re post-maint Testing

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