Semantic search

This page or action requires JavaScript to work. Please enable JavaScript in your browser or use a browser where it is supported, so that functionality can be provided as requested. For further assistance, please have a look at the noscript help page.

Search Clear all entries

	Issue date	Title	Topic
ML20212D191	20 September 1999	SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2
ML20211G526	24 August 1999	SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1	VT-2 Incorporated by reference Dissimilar Metal Weld Unidentified leakage
ML20211A979	20 August 1999	Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2	Incorporated by reference
ML20209E436	9 July 1999	SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation
ML20196K663	7 July 1999	Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers	Operability Determination
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
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
ML20205S555	21 April 1999	Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20205N365	12 April 1999	Safety Evaluation Accepting IPE of External Events Submittal	Fire Barrier Internal Flooding Probabilistic Risk Assessment Earthquake
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
ML20196J835	8 December 1998	Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys
ML20196C025	27 November 1998	SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station
ML20196A688	25 November 1998	Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds	Hydrostatic VT-2 Unidentified leakage
ML20249B628	12 June 1998	Safety Evaluation Accepting 980303 Request to Review & Approve Proposed Change to Plant,Units 1 & 2 TS Re Relocation of Meteorological Tower
ML20248B044	27 May 1998	Safety Evaluation Authorizing Proposed Alternative Use of Current TS Section 3/4.7.8 Requirements for Snubber Visual Exam & Functional Testing,Based on Finding That Proposed Alternative Proposes Acceptable Level of Quality & Safety	Incorporated by reference
ML20247M086	21 May 1998	SER Accepting 1997 Rev to Catawba UFSAR Submitted on 970925. Rev Added Analysis for Postulated Accident Involving Dropping of Sf Pool Weir Gate Onto Sf Assemblies
ML20216E177	13 April 1998	Safety Evaluation Accepting Relief Request 98-01 for Catawba Nuclear Station Units 1 & 2 from Requirements of ASME Boiler & PV Code for Second 10-year Interval Program for Inservice Testing of Pumps & Valves
ML20217M421	3 April 1998	Safety Evaluation Approving Request for Relief 97-04, non-code Repair Valves.Relief Granted Retroactively to Unit 1 & Expired Dec 1997.Relief for Unit 2 Will Expire at End of Cycle 9 Outage or Next Scheduled Outage Exceeding 30 Days	Through-Wall Leakage Operability Assessment
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
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
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
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
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
ML20198J765	15 October 1997	Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units	VT-2 Incorporated by reference
ML20211F880	22 September 1997	Safety Evaluation Supporting Second ten-year Interval Inservice Inspection Program Plan & Associated Requests for Relief for Catawba Nuclear Station Unit 1	Incorporated by reference Unidentified leakage
ML20211E687	22 September 1997	SER Accepting DPC Responses to GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves	Backfit
ML20149K828	29 July 1997	SER Granting Request for Exemption from Requirements of 10CFR70.24 for Units 1 & 2
ML20148S223	2 July 1997	Safety Evaluation Accepting Supplemental Test Program for Relief Request 1.4.2 for Units 1 & 2
ML20141E112	16 June 1997	Safety Evaluation Approving Licensee Position That UFSAR Table 6-77 Be Revised to Identify SA-1 & SA-4 Instead of SA-3 & SA-6 as Containment Isolation Valves	Local Leak Rate Testing Excess Flow Check Valve Exemption Request
ML20148H250	5 June 1997	Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp
ML20141G670	20 May 1997	Safety Evaluation Accepting Proposed Alternative Use of TS Requirement for Code Class Snubbers	Incorporated by reference
ML20135B305	27 February 1997	Safety Evaluation Granting Second 10 Yr ISI Program Plan & Associated Requests for Relief	Incorporated by reference
ML20134P242	20 February 1997	Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications
ML20134L408	19 November 1996	SER Accepting Performance of Plant Standby Nuclear Svc Water Pond	Ultimate heat sink
ML20134G555	7 November 1996	Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel
ML20129E485	1 October 1996	Safety Evaluation Recommending That Relief Request 96-02 Be Granted,Per 10CFR50.55a(g)(6)(i),per Request	Incorporated by reference
ML20059G860	29 October 1993	SE Granting 921130 Request for Relief from Requirements of 1986 Edition of ASME Boiler & Pressure Vessel Code,Section XI Re Inservice Insp of safety-related Snubbers During Second 10-yr Interval
ML20057F412	12 October 1993	Safety Evaluation Re Inservice Testing Program Requests for Relief.Alternatives Authorized Per 10CFR50.55a(a)(3) or Relief Granted Per 10CFR50.55a(f)(6)(i)
ML20057A036	26 August 1993	Safety Evaluation Supporting Amends 138 & 120 to Licenses NPF-9 & NPF-17,respectively	Shutdown Margin
ML20056H319	24 August 1993	SER Accepting Proposed TS Changes Re RWST & Cla Boron Concentrations	Shutdown Margin Systematic Assessment of Licensee Performance
ML20056D961	30 July 1993	SER Accepting Licensee 930325-0429 Submittals of Technical Info to Support Continued Operation of Facility for Remainder of Fuel Cycle 7	Stress corrosion cracking Operational leakage
ML20126H317	28 December 1992	Safety Evaluation Granting Extension of First 10-yr ISI Interval to Coincide W/Start of end-of-cycle 8 Refueling Outage	Hydrostatic Incorporated by reference
ML20058N796	9 August 1990	Safety Evaluation Approving Relief Request 89-01 Re ASME Code Test Requirements for Nuclear Svc Water Sys	Hydrostatic
ML20055H915	27 July 1990	Safety Evaluation Accepting Actions Taken to Resolve NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generators Tubes
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
ML20248C073	3 August 1989	Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants
ML20247H761	18 July 1989	Safety Evaluation Supporting Amends 100 & 82 to Licenses NPF-9 & NPF-17,respectively

Semantic search

Query log

Navigation menu