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	Issue date	Title	Topic
ML20150C265	28 June 1988	Safety Evaluation Supporting Licensee Assessment to Fracture Toughness Requirements for Protection Against PTS Events,Per 10CFR50.61
ML20151X719	23 January 1968	AEC Safety Evaluation in Matter of Licensee Plant	Safe Shutdown Boric Acid Design basis earthquake Earthquake Fuel cladding
ML20153F351	7 February 1987	Safety Evaluation Accepting Util Latest Design Mods to MSIV Actuation Control Sys,Per IEEE 279 & GDC 21
ML20153F367	30 April 1987	Safety Evaluation Accepting Util 870311 Proposed Changes to Tech Spec Tables 2.2.1-1,3.6.1.2-1 & 3.6.3-1 Re MSIV-closure Setpoint
ML20153F385	4 May 1987	SER Accepting Util 870301 & 0407 Requests for Rev to Tech Specs,Modifying MSIV Actuation Control Sys,Per IEEE Std 279 & GDC 21
ML20153F629	27 August 1986	Safety Evaluation Concurring W/Applicant 860703 Exemption Request Re Testing of 16 Relief Valves,Per 10CFR50,App J	Hydrostatic Exemption Request
ML20154A405	14 November 1985	Safety Evaluation Supporting 831108 Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability.Salp Input Encl
ML20154A420	4 November 1985	Safety Evaluation Supporting 831108 Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability
ML20154C364	25 February 1986	Suppl to Safety Evaluation Supporting Results of Tests Conducted by Wyle Labs Contained in Test Rept 17769-01 to Justify Less Separation Between Class 1E & non-Class 1E Cables than Required by Reg Guide 1.75
ML20154H217	18 May 1988	Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program
ML20155E986	19 December 1973	Draft Safety Evaluation Detailing Items Requiring Resolution Expected to Occur Prior to Issuance of Const Permit	Ultimate heat sink Fuel cladding
ML20155G480	28 September 1988	Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively
ML20195G546	21 August 1987	Safety Evaluation Accepting Proposed Util Tech Specs Change to Increase Max Allowed Enrichment of Reload Fuel to 4.2 Weight % U-235
ML20195G550	28 October 1987	Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pool.Licensee May Be Required to Perform Addl Analyses to Verify Maint of Required Subcriticality If Staff Boraflex Studies Reveal Gap Development in Subj Boraflex	Systematic Assessment of Licensee Performance
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
ML20196A688	25 November 1998	Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds	Hydrostatic VT-2 Unidentified leakage
ML20196C025	27 November 1998	SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station
ML20196J835	8 December 1998	Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys
ML20196K663	7 July 1999	Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers	Operability Determination
ML20197A655	2 March 1998	Safety Evaluation Supporting Licensee Proposed Action to Set Gwl Alarm at Higher Elevation than Current Level of El 731 Feet	Hydrostatic
ML20198A448	11 December 1998	Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted	Incorporated by reference
ML20198C554	15 May 1986	Safety Evaluation Accepting Util Response to Items 3.1.3 & 3.2.3 of Generic Ltr 83-28 Requiring Licensee Review of Existing Tech Specs for post-maint Testing Requirements That May Degrade Safety.Items Closed
ML20198J765	15 October 1997	Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units	VT-2 Incorporated by reference
ML20198P964	15 January 1998	SE Granting Relief Request 97-03 for Second 10-yr Interval Inservice Insp Program	Incorporated by reference
ML20198R995	30 October 1997	Safety Evaluation Authorizing Request for Approval of Alternative to Exam Requirement of Reactor Vessel Shell Weld,Per 10CFR50.55a(g)(6)(ii)(A)(5)	Incorporated by reference
ML20199A552	22 January 1998	Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, for Cns,Units 1 & 2	Safe Shutdown Power-Operated Valves Backfit
ML20199A642	22 January 1998	Safety Evaluation Accepting Proposed EALs Changes for Plant, Units 1 & 2.Concludes That Changes Consistent W/Guidance in NUMARC/NESP-007,w/variations as Identified & Accepted in Review & Meets Requirements of 10CFR50.47(b)(4)	Safe Shutdown Reactor Vessel Water Level Ultimate heat sink Fuel cladding
ML20199F336	28 January 1998	Safety Evaluation Supporting 951227 Request for NRC Approval of Proposed EALs to McGuire Nuclear Station,Units 1 & 2	Reactor Vessel Water Level Ultimate heat sink Fuel cladding
ML20199G453	19 March 1985	Partially Withheld marked-up Rev 5 to Sser Re Allegation AQ-91 Concerning Inadequate Training of Personnel.Related Info Encl
ML20199G614	5 October 1984	Partially Withheld marked-up Rev 2 to Sser Re Allegation AQ-88 Concerning safety-related Work Performed by Illegal Aliens
ML20199G620	13 March 1985	Partially Withheld marked-up Rev 4 to Sser Re Allegation AQ-98 Concerning Extensive Delays in Repair of safety-related Matl	Hydrostatic
ML20199G624	2 October 1984	Partially Withheld marked-up Draft 4 to Sser Re Allegation A-130 Concerning Valve Disc Numbers on Repair Travelers That Differ from Code Data Rept
ML20199G630	1 November 1984	Partially Withheld marked-up Rev 3 to Sser Re Allegation AQ-131 Concerning Electrical Boxes That Were Shipped to Facility in Damaged Condition or Were Damaged & Repaired by Unauthorized Personnel.Related Info Encl	Coatings Nondestructive Examination
ML20199G775	22 January 1985	Partially Withheld marked-up Rev 1 to Sser Re Allegation AQ-41 Concerning Sandblasted Pipe Sections Which Removed Heat Markings Used for Traceability.Related Info Encl	Coatings
ML20199L394	2 July 1986	SER Providing Final Conclusions & Recommendations from Evaluation of Tdi Owners Group Program to Validate & Update Quality of Tdi Diesel Generators	Eddy Current Testing Liquid penetrant Overspeed trip
ML20203B107	4 February 1998	Safety Evaluation Approving Proposed Alternative to Reactor Vessel Augmented Exam Requirement of Reactor Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A)(5)	Incorporated by reference
ML20205H151	15 August 1986	Safety Evaluation of Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components)
ML20205M573	26 October 1988	Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20205N365	12 April 1999	Safety Evaluation Accepting IPE of External Events Submittal	Fire Barrier Internal Flooding Probabilistic Risk Assessment Earthquake
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
ML20205S555	21 April 1999	Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20206K555	4 November 1977	Safety Evaluation & Eia Supporting Proposed Amend to License DPR-35,implementing App I Requirements Re ALARA Releases of Radioactive Matls in Liquid & Gaseous Effluents	Anticipated operational occurrence
ML20206K616	13 March 1985	SER Supporting Proposed Tech Spec Change to Permit Temporary Increase in Main Steam Line High Radiation Scram & Isolation Setpoints to Facilitate Testing of Hydrogen Addition Water Chemistry.Related Documentation Encl
ML20206M562	13 August 1986	SER Accepting 840808 & 850621 Responses to IE Info Notice 84-90, Main Steam Line Break Effect on Environ Qualification of Equipment. Higher Temp Will Not Preclude Ability to Shut Down Reactor in Safe Shutdown Condition	Safe Shutdown
ML20206N351	11 May 1999	Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs	Stroke time
ML20206P520	14 May 1999	Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves	Stroke time Power Uprate
ML20207E755	30 December 1986	SER Supporting Removal of RCS Thermal Sleeves
ML20207N301	8 January 1987	Safety Evaluation on Util 830309 & 851025 Requests for Relief from 10CFR50.55a Requirements Re Pump & Valve Inservice Testing Program.Relief Granted W/Listed Exceptions
ML20207P634	31 August 1986	Safety Evaluation Accepting Util 851120 & 860324 Proposals to Eliminate Arbitrary Intermediate Pipe Breaks in Select List of High Energy Piping Sys	Stress corrosion cracking Thermal fatigue

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