ML20202F964
From kanterella
| ML20202F964 | |
| Person / Time | |
|---|---|
| Issue date: | 12/04/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20202F947 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, NUDOCS 9712090269 | |
| Download: ML20202F964 (9) | |
Similar Documents from NRC (Affiliation Not Assigned) | |
|---|---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217L8831999-10-21021 October 1999
[Table view]Some use of "" in your query was not closed by a matching "".Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 ML20217H8991999-10-18018 October 1999 SER Approving Licensee Requests for Relief NDE-R001 (Part a & B),NDE-R027,NDE-028,NDE-R029,NDE-R030,NDE-R032 & NDE-R035. Relief Request NDE-036,denied & Relief Request NDE-R-034, Deemed Unnecessary ML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair ML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217H8501999-10-14014 October 1999 Safety Evaluation Supporting Amend 197 to License DPR-64 ML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20217D3061999-10-13013 October 1999 SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 ML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217C1311999-10-0808 October 1999 Safety Evaluation Supporting Amend 153 to License DPR-3 ML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212H2381999-09-22022 September 1999 Safety Evaluation Supporting Amend 228 to License DPR-49 ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 ML20216F9831999-09-20020 September 1999 Safety Evaluation Supporting Amend 11 to License R-115 ML20212D4471999-09-20020 September 1999 Safety Evaluation Supporting Amend 31 to License R-103 ML20212D1911999-09-20020 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 ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 ML20212D1461999-09-17017 September 1999 SER Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 ML20212B3151999-09-14014 September 1999 Safety Evaluation Re B&Wog EOP Technical Bases Document (Tbd).All Outstanding Issues Closed Re Generic Review.One Unresolved Issue May Be Addressed on plant-specific Basis. Staff Has No Plans for Further Generic Review of TBD ML20212D0711999-09-14014 September 1999 Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 1999-09-09 Category:TEXT-SAFETY REPORT MONTHYEARML20217L8831999-10-21021 October 1999
[Table view]Some use of "" in your query was not closed by a matching "".Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 ML20217J0721999-10-18018 October 1999 Safety Evaluation of Topical Rept EMF-2158(P),Rev 0, Seimens Power Corp Methodology for Boiling Water Reactors, Evaluation & Validation of Casmo-4/Microburn-B2. Rept Acceptable for Licensing Evaluations of BWR Neutronics ML20217H8991999-10-18018 October 1999 SER Approving Licensee Requests for Relief NDE-R001 (Part a & B),NDE-R027,NDE-028,NDE-R029,NDE-R030,NDE-R032 & NDE-R035. Relief Request NDE-036,denied & Relief Request NDE-R-034, Deemed Unnecessary ML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 ML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217G0931999-10-15015 October 1999 Safety Evaluation of Topical Rept BAW-10179P,Rev 3, Safety Criteria & Methodology for Acceptable Cycle Reload Analysis. Rev 3 Found Acceptable & Accurately Include Conditions & Limitations for Applicability of References ML20217K0651999-10-15015 October 1999 Safety Evaluation of Topical Rept BAW-10193P, RELAPS5/MOD2-B&W for Safety Analysis of B&W-Designed Pressurized-Water Reactors. Rept Acceptable for Referencing in Licensing Applications ML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair ML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217H8501999-10-14014 October 1999 Safety Evaluation Supporting Amend 197 to License DPR-64 ML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 ML20217J1101999-10-13013 October 1999 Safety Evaluation of Topical Rept TR-108727, BWRVIP Vessel & Internals Project,Bwr Lower Plenum Insp & Flaw Evaluation Guideline (BWRVIP-47). Rept Will Provide Acceptable Level of Quality for Exam of safety-related Components ML20217D3061999-10-13013 October 1999 SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217C1311999-10-0808 October 1999 Safety Evaluation Supporting Amend 153 to License DPR-3 ML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217B1641999-10-0505 October 1999 Safety Evaluation of Topical Rept BAW-10228P. Science. Rept Acceptable for Licensing Applications,Subject to Listed Conditions in Accordance with Fcf Agreement (Reference 4) ML20212M2141999-10-0505 October 1999 Safety Evaluation Concluding That Topical Rept EMF-2158(P), Rev 0,acceptable for Licensing Evaluations of BWR Neutronics Designs & Applications,As Per SPC Agreement (Ref 9) Subj to Stated Conditions ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico ML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML20212J1301999-09-30030 September 1999 Safety Evaluation Concluding That Topical Rept WCAP-12472-P-A,Addendum 1, Beacon-Core Monitoring & Operations Support System, Acceptable for Licensing Applications Subj to Pertinent Restrictions ML20212J9141999-09-29029 September 1999 Safety Evaluation of Topical Rept TR-108724, BWRVIP Vessel & Internals Project,Vessel Id Attachment Weld Insp & Flow Evaluation Guidelines (BWRVIP-48) ML20212J9661999-09-29029 September 1999 Safety Evaluation of Topical Rept TR-107285, BWRVIP Vessel & Internals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dated Dec 1996.Rept Acceptable ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20212H2381999-09-22022 September 1999 Safety Evaluation Supporting Amend 228 to License DPR-49 ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212D1911999-09-20020 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 ML20216F9831999-09-20020 September 1999 Safety Evaluation Supporting Amend 11 to License R-115 ML20216H9901999-09-20020 September 1999 Proposed Final Rept Impep Review of South Carolina Agree- Ment State Program 990712-16 ML20212D4471999-09-20020 September 1999 Safety Evaluation Supporting Amend 31 to License R-103 ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 1999-09-30 |
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