ML20153B154
ML20153B154 | |
Person / Time | |
---|---|
Site: | 05000000, 05000447, 05000605 |
Issue date: | 03/15/1988 |
From: | Rubenstein L Office of Nuclear Reactor Regulation |
To: | Artigas R GENERAL ELECTRIC CO. |
References | |
NUDOCS 8803210431 | |
Download: ML20153B154 (3) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20100M3571996-02-26026 February 1996
[Table view]Forwards Proprietary Documentation of Algebraic for of GE Critical Power Correlation.Ge Requests Concurrence Recognizing Attachment as Legal Documentation of GEXL & GEXL-PLUS Critical Quality Correlations ML20073T0701994-07-0101 July 1994 Reports Changes & Errors in ECCS Evaluation Models ML20099F5851992-08-0404 August 1992 Clarifies Statement Made in NRC Safety Evaluation of Rept NEDE-31758P-A, GE Marathon Control Rod Assembly, W/ Regards to Stress Limit Used by Ge.Nrc Concurrence W/ Clarification Requested by 920930 ML20090J9651992-03-11011 March 1992 Forwards Piping Design Insps,Tests,Analysis & Acceptance Criteria (Itaac).Piping Design ITAAC Will Be Included as Part of Generic ITAAC ML20090J9701992-03-11011 March 1992 Forwards Proprietary Responses to Issues Re Sections 9.3,9.5 & 11.2 of Advanced BWR Ssar.Responses Reflect Correctons & Additions to Earlier Proprietary Submittals.Responses Withheld ML20090J9791992-03-11011 March 1992 Forwards Responses to Resolution of Issues Related to Advanced BWR Draft SER Chapters 1,2,3,5,6,9,10,12,13,14 & 15 (SECY-91-355) ML20090J9941992-03-11011 March 1992 Forwards Draft Rev 0 to Advanced BWR Srvdl Wetwell Piping Stress Analysis Design Rept & Draft Rev 0 to Design Rept, Main Steam Line a & Safety Relief Valve Discharge Piping Stress Analysis, Per 911209-10 Ge/Nrc Meeting ML20090G5801992-03-0909 March 1992 Summerizes Staff Position Re NRC Conference Call on Dser Comments to Advanced BWR Ssar ISI Requirements ML20090F6171992-03-0505 March 1992 Forwards Rev B to 23A6100AQ,Section 17.3 Re Responses to Request for Resolution of Issues Related to Reliability Assurance Program (Rap).Subj Responses Will Be Included as Amend to Advanced BWR Ssar in Future ML20094G9691992-03-0202 March 1992 Forwards Radwaste Bldg Seismic Analysis. Informs That GE Intends to Amend Ssar W/Subj Analysis in Future Amend ML20094G7401992-02-25025 February 1992 Forwards Proprietary Summary of 920127 Telcon W/Nrc & Brookhaven Lab to Clarify Aspects of Human Factors Review of Advanced Bwr,Specifically Review of Design Implementation Process.Summary Withheld ML20094G7141992-02-25025 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092N1451992-02-25025 February 1992 Requests Addition of Listed Individual to Advanced BWR Document Distribution List ML20090A0441992-02-25025 February 1992 Forwards Proprietary Rev R-0 to Advanced BWR Project Common Engineering Work Plan. Plan Withheld ML20092L0801992-02-25025 February 1992 Forwards App 19P to Chapter 19 of Evaluation of Potential Mods to Advanced BWR Design ML20090B1881992-02-24024 February 1992 Forwards Draft Rev 0 to Advanced BWR Ssar Main Steam, Feedwater & Srvdl Piping Sys Design Criteria & Analysis Methods & Draft Rev 0 to Advanced BWR Feedwater Loop a Piping & Equipment Loads, Per Ge/Nrc 911209-10 Meeting ML20092M2931992-02-20020 February 1992 Forwards Discussion of Differences Between Us Advanced BWR & K-6/7 Project.Advanced BWR Design Under Review for for Differences to K 6/7 & Addl Differences Will Be Included in Future Ssar Amend ML20094G7201992-02-17017 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092F4241992-02-14014 February 1992 Forwards Proprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch. Response Withheld ML20092F4601992-02-14014 February 1992 Forwards Nonproprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch Re Standby Liquid Control Sys Instrumentation & Controls ML20092F4971992-02-13013 February 1992 Forwards Proprietary App 18F, Emergency Operation Info & Controls to Chapter 18, Human Factors Engineering of Advanced BWR Std SAR Covering Control Room Inventory.App 18F Withheld ML20092F5251992-02-11011 February 1992 Responds to Performance & Quality Evaluation Branch Open Items on Advanced BWR Std SAR Chapter 14 ML20092F5181992-02-10010 February 1992 Forwards Responses to 920110-16 Requests for Addl Info on Advanced BWR Design for Severe Accidents ML20092C0251992-02-0303 February 1992 Forwards Proprietary Responses to Addl Info Noted in 911004 Draft SER for Chapter 7.Responses Are Cross Ref W/Summary Item Number Corresponding to Review Meeting in San Jose on 910807 & 08.Responses Withheld ML20092C1671992-02-0303 February 1992 Forwards Nonproprietary Responses to Addl Items of Concern Noted in Draft SER for Chapter 7.Advises That GE Will Amend Advanced BWR Ssar W/Responses in Future Amend ML20092C1831992-02-0303 February 1992 Forwards Response to Leak Before Break Issue Addressed in 911209-10 Ge/Nrc Meeting.Advises That GE Intend to Amend Ssar W/Response in Future Amend ML20100P9651992-01-31031 January 1992 Forwards Proprietary NEDC-30032 Joint Study Final Rept - Joint Study W/Regard to 'Study (II) Related to Advanced Bwr' - Thermal Margin During Rapid Coastdown,820401-830331. Rept Withheld ML20091K8911992-01-22022 January 1992 Forwards Response to Open Issue 3 of SECY-91-153 Re Main Steam Line Seismic Classification Including,Static Design Procedure to Be Utilized in Evaluation of Seismic Capability of Condenser Anchorage & Turbine Bldg ML20094E4571992-01-17017 January 1992 Forwards Tier 1 Design Certification Matl,Pilot Itacc Examples for GE Advanced BWR Design & Advanced BWR Design Certification Generic ITAAC for Seismic Category 1 Structures,Position Paper ML20087D4771992-01-10010 January 1992 Forwards Responses to Agenda Item 12 Discussed During 911120-21 Meeting W/Reactor Sys Branch of Nrc.Responses Withheld ML20087D2641992-01-10010 January 1992 Forwards Response to Agenda Items 1,5,9 & 16 Discussed at Ge/Nrc Reactor Sys Branch 911120-21 Meetings.Items Include, Stability Performance in Normal Operating Region,Loss of Ac Power & Loss of Feedwater Heating Transient ML20087D0011992-01-0606 January 1992 Forwards Proprietary Tables to App 18F to Chapter 18 Re Human Factors Engineering.Ge Will Amend Ssar to Include Subj Info in Future Amend.Encl Withheld ML20087B7161992-01-0606 January 1992 Forwards Response to Issues Raised at Ge/Nrc 911209-10 Meetings Re Inservice Insp Relief Requests for Reactor Pressure Vessel Bottom Head Weld & Reactor Pressure Vessel Bottom head-to-shell Weld ML20086U5451992-01-0606 January 1992 Forwards Response to NRC Request for Addl Info Re Incorporation of Operating Experience in Advanced BWR ML20086U1941991-12-20020 December 1991 Confirms That Licensee Advanced BWR Application Should Be Processed as Application for Part 52 Final Design Approval & Subsequent Design Certification Per 10CFR52.45 ML20086P2251991-12-19019 December 1991 Forwards Nonproprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20086P2161991-12-19019 December 1991 Forwards Proprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20086N9601991-12-19019 December 1991 Forwards Proprietary & Nonproprietary Versions of Rev B to Update of App 9A, Reactor Bldg Fire Hazard Analysis ML20086N2161991-12-13013 December 1991 Forwards Amend 19 to Advanced BWR Ssar ML20091H4061991-12-13013 December 1991 Forwards Selected Sections of Chapter 9, Auxiliary Sys & Chapter 18, Human Factors Engineering of Ssar for Advanced Bwr,Amend 19,including Update of Control Bldg Fire Protection Drawings.Encl Withheld ML20094D2041991-12-12012 December 1991 Forwards Proposed Advanced BWR Tech Specs,Per Vendor to Nrc.Specs Will Be Documented Via Amend to Chapter 16 of Advanced BWR Ssar,Once Specs Finalized ML20086H5741991-12-0202 December 1991 Describes Plan for Submitting Advanced BWR Tech Specs to Nrc,Per 911108 Meeting.First Submittal of Noninstrumentation & Control Sys Will Be Submitted by 911213.Third Submittal Re 65 Unchanged LCOs Will Be Submitted by 920131 ML20086H6161991-11-27027 November 1991 Forwards Proprietary Responses to Open Issues 8.3.3.6 & 8.3.5 for Advanced BWR Ssar,Chapter 8,per Commitment at 910916-18 Meeting in San Jose.Encl Withheld ML20086H6101991-11-27027 November 1991 Forwards Responses to Open Issues in GE Advanced BWR Ssar Chapter 8 Re Offsite Power Sys & Protective Sys for Reactor Internal Pumps,Per 910916-18 Meeting W/Nrc.Proprietary Versions of Response Withheld ML20086E4831991-11-25025 November 1991 Forwards Tables Re Significant New Open Issues Included in Final,Draft Ser,Significant Open Items Included in All Draft Sers,Ge Future Submittals & Proposed Issues for Discussion at Dec Mgt Meeting,Per NRC ML20086A8121991-11-12012 November 1991 Forwards Draft Writeup for Fire Protection Probabilistic Risk Assessment Requested in Draft SER on Advanced BWR Probabilistic Risk Assessment.Ge Will Amend Ssar to Include Info When Finalized ML20086C7201991-11-12012 November 1991 Forwards Proprietary Draft Writeup for Fire Protection PRA, as Requested in Draft SER on Advanced BWR Pra,Per SECY-91-309,dtd 911001.Encl Withheld ML20079P1731991-11-0707 November 1991 Forwards Response to Discussion Item 7 from 910906 Conference Call Re Rod Block Algorithm & Setpoint ML20079M2561991-11-0101 November 1991 Forwards Proprietary GE Responses to Staff Position Re GE BWR Power Upgrade Program,Dtd 910930.Responses in Ref to Licensing Topical Rept NEDC-31897P-1, Generic Evaluations of GE BWR Power Uprate,June 1991. Responses Withheld ML20079L7461991-11-0101 November 1991 Forwards Summary of Major Advanced BWR Design Differences, Assessment of How TS Differ from Improved Ts,Including Summary of New,Different or Inapplicable & Example of How TS Would Be Written Where TS Differ from Improved TS 1996-02-26 Category:NRC TO VENDOR/MANUFACTURER MONTHYEARML20059L2881990-09-19019 September 1990
[Table view]Forwards Request for Addl Info Re Application for Certification of Advanced BWR Design ML20059A3931990-08-15015 August 1990 Forwards Request for Addl Info Re GE Application for Certification of Advanced BWR Design.Responses to Encl 1 Requested by 900831 & Responses to Encls 2 & 3 by 900928 ML20055J2661990-07-27027 July 1990 Forwards Request for Addl Info Re GE Application for Certification of Advanced BWR Design ML20246C7101989-08-18018 August 1989 Forwards Order,Effective Immediately,Modifying CPs CPEP-1 & CPEP-2 to Require Notification of Commission Before Taking Possession of Any Classified Equipment & to Show Cause Why CPs Should Not Be Revoked ML20246E1681989-08-17017 August 1989 Forwards Draft SER Re Final Design Approval & Design Certification of Advanced Bwr,For Use ML20245F0271989-08-0707 August 1989 Provides Clarification & Further Guidance Re Containment Design to Assure That Containment Conditional Failure Probability Less than 1 in 10 When Weighted Over Credible Core Damage Sequences.Goal of 0.1 Possible ML20246P0181989-07-17017 July 1989 Forwards Request for Addl Info Re 890620 Filing for Reorganization in Us Bankruptcy Court.Nrc Will Initiate Proceeding for Suspension or Revocation of CPs Should Licensee Fail to Respond by 890815 ML20246C0101989-06-30030 June 1989 Forwards Ltr from Director,Ofc of Nrr,Ack Receipt of Petition Filed by Ecology Ctr of Southern CA & Stating That Petition Is Being Treated Under 10CFR2.206 ML20245B6941989-06-16016 June 1989 Forwards Director'S Decision,Ltr of Transmittal & Fr Notice in Response to Ocre Petition Filed Under 10CFR2.206. Petitioner Expressed Concerns Re 890309 Power Oscillation Event at LaSalle Unit 2 & Requested Commission Action ML20245C3691989-06-16016 June 1989 Advises of Intended Visit to Audit Process of Verification & Validation for Advanced BWR Software Development ML20247F3491989-05-16016 May 1989 Requests Addl Info Re Application for Certification of Advanced BWR Design.Questions Cover Qa,Instrumentation & Controls,Electromagnetic Compatibility Qualification & Design & Performance Info.Response Requested by 890711 ML20246P4171989-03-23023 March 1989 Advises That 890210 Condition III.6 of CP Issued to Alchemie Re Financial Assurances for Protection of Common Defense & Security by Control of Classified Machinery Not Applicable ML20235N9801989-02-22022 February 1989 Forwards Notices of Issuance of CPs for Alchemie Centrifuge Plan Demonstration & Oliver Springs Facilities ML20195G9371988-11-22022 November 1988 Provides Recently Developed Info Re Scope of Future Std Design Applications & of Staff Review of Advanced BWR ML20205T5991988-11-0707 November 1988 Requests Survey of Proposed Oliver Spring Site to Look for Evidence of Threatened or Endangered Species ML20205T6961988-11-0303 November 1988 Notifies of 890110 Meeting W/Region V in San Francisco,Ca to Discuss NRC Reactor Operator Licensing Program in Region ML20205R7171988-11-0303 November 1988 Requests 880912 Submittal Re Ability to Assure Funding for Decontamination Over Entire Period of License Be Revised. NRC Expects That Sale of Unneeded,Unclassified Matl Will Realize Sufficient Funds to Cover Costs of Removal of Matl ML20205M9061988-10-28028 October 1988 Advises That Addendum 2 to WCAP-10988, COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment, Forwarded by Will Be Withheld from Public Disclosure,Per Request ML20205L0381988-10-27027 October 1988 Informs That WCAP-11935, McGuire 2 - Evaluation for Tube Vibration-Induced Fatigue Will Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20155K5151988-10-26026 October 1988 Forwards Request for Addl Info Re GE Application for Certification of Advanced BWR Design.Info Includes Suppression Pool Water,Condensate Storage Tank,Discharge Line Fill Pump & Standby Liquid Control Sys ML20205Q5661988-10-25025 October 1988 Forwards SERs Re Company 871117 Application for Authority to Construct & Operate Facilities to Enrich Stable Isotopes at Facility-1 Cpdf & to Construct Facility for Same Purpose at Facility-2 Oliver Springs ML20154Q1741988-09-26026 September 1988 Forwards Request for Addl Info Re Application for Certification of Advanced BWR Design.Responses Requested by 881130 ML20154J9201988-09-20020 September 1988 Forwards Request for Addl Info Re GE Application for Certification of Advanced BWR Design for Response by 881121 in Order to Maintain Review Schedule ML20154D8091988-09-12012 September 1988 Forwards Request for Addl Info Re GE Application for Certification of Advanced BWR Design for Response by 881115 ML20154E7171988-09-0808 September 1988 Forwards Notice of Issuance of Environ Assessment & Finding of No Significant Impact & Environ Assessments Re 871107 Application to Construct & Operate Facility for Enriching Stable Isotopes ML20153A8471988-07-0707 July 1988 Forwards Request for Addl Info Re GE Application for Certification of Advanced BWR Design.Responses Requested by 880915 ML20195F1951988-06-0303 June 1988 Responds to Re Fee for Design Approvals & Certifications.Commission in Process of Examining Fees for All Types of Reviews.Ge Concerns Will Be Included in Commission Review Process ML20150F7751988-03-29029 March 1988 Advises That Info on Advanced BWR Fuel Design in Chapter 4 of Supplemental SAR Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 870929 Request ML20148B5101988-03-15015 March 1988 Informs of Relocation of NRR to Stated Address in Rockville,Md ML20153B1541988-03-15015 March 1988 Informs of Relocation of NRR to Stated Address in Rockville, MD ML20147C4121988-02-29029 February 1988 Submits List of Concerns to Be Addressed During 880223-25 Preliminary Design QA Audit ML20149L8971988-02-22022 February 1988 Forwards Request for Addl Info Re GE Application for Certification of Advanced BWR Design by 880430.Request Addresses Areas of SRP Chapters 4,5,6 & 15,reviewed by Mechanical,Matls & Chemical Engineering Branches ML20235L6161987-09-25025 September 1987 Extends Invitation to Attend Region V 871110 Meeting in South San Francisco,Ca to Discuss NRC Reactor Operator Licensing Program.W/O Stated Encl ML20235T2431987-09-24024 September 1987 Forwards Insp Repts 50-018/87-01,50-070/87-01,50-073/87-01 & 50-183/87-01 on 870901-03 & Notice of Violation ML20214M6631987-05-22022 May 1987 Forwards Revised NRC Form 398.Rev Reflects Changes to 10CFR55 Effective on 870526.Revised Form Requires New Applications to Complete Each Category Including Educ, Training & Experience.Changes Detailed in Encl 2 ML20205L6971987-03-27027 March 1987 Requests Further Info & Documentation Re Steam Generator Tube Vibration Problem for Generic CESSAR Sys 80 Steam Generator Design by 870410.Specific Questions Re Request Encl ML20210J3961986-09-22022 September 1986 Forwards Amend 2 to Final Design Approval FDA-1 for BWR/6 Nuclear Island Design (GESSAR-II) & Notice of Issuance of Amend.Amend Removes Constraints on Issuing CPs & OLs to Applicants Ref GESSAR-II Design ML20207H6641986-07-22022 July 1986 Ack Receipt of 860508 Application for Approval of Transfer of Ga Co Control for Licenses R-38,R-67 & SNM-0696. Application Fee Required NUREG-0979, Forwards Sser 5,(NUREG-0979).W/o Encl1986-06-25025 June 1986 Forwards Sser 5,(NUREG-0979).W/o Encl ML20199D5321986-06-11011 June 1986 Forwards Proposed Amend 2 to Final Design Approval-1 for BWR/6 Nuclear Island Design,Gessar Ii,Documenting Staff & ACRS Review of Gessar II for Severe Accident Concerns,For Comment.Amend Removes Constraints on Issuance of CPs & OLs ML20199F2211986-02-19019 February 1986 Further Response to FOIA Requests for Documents Re Humboldt Bay File Up to 761231,Bodega Bay file,4x4 Test Info & Wuergassen Plant 1972 Incident.Forwards App J Documents.App J Documents Withheld Due to Proprietary Nature ML20137L4871986-01-22022 January 1986 Forwards,For Info & Comment,Acrs Rept Re Review of GESSAR-II for Concerns Addressed in Commission Severe Accident Policy Statement.Comments Requested by 860204 ML20140F3691986-01-14014 January 1986 Further Response to FOIA Request for Several Categories of Documents Re Pressure Suppression Containment.Fsar & SER for Limerick Only Documentation Re 4x4 Tests.Encl Apps D-G Documents Responsive to Item 4 Also Available in PDR ML20137C5151986-01-13013 January 1986 Forwards Summary of Changes & Revised Pages Incorporating Changes to Braidwood Draft Tech Specs.Byron Tech Specs Should Address diesel-driven Essential Svc Water Makeup Batteries.Amend Request Will Be Needed ML20239A1971985-12-17017 December 1985 Further Response to 850927 & 1106 FOIA Requests for Documents Re Pressure Suppression Containment,Including Humboldt Bay & Bodega Bay Docket Files.Bodega Bay File Being Placed in Pdr.Review of Addl Documents Continuing ML20138A7521985-10-0808 October 1985 Requests Listing of Customers Purchasing or Ordering Valve Operators Containing Magnesium Motor Rotors.Test Anomalies Have Raised Concern Re long-term Availability of Valve Operator Motors W/Magnesium Rotors ML20134A5511985-08-0909 August 1985 Forwards Amend 1 to Final Design Approval FDA-1 & Fr Notice of Issuance.Amend Removes Constraint on Forward Referenceability of GESSAR-II Design & Permits Ref in New CP & OL Applications ML20133B2801985-07-29029 July 1985 Approves 841219 & 21 Requests for Withholding CAW-84-117, Equipment Justification for Interim Operation - Wolf Creek Generating Station,Unit 1 & Callaway Station,Unit 1, from Public Disclosure,Per 10CFR2.790 ML20126C1121985-06-10010 June 1985 Approves Request That WCAP-10553, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Byron Units 1 & 2 & Braidwood Units 1 & 2, Be Withheld (Ref 10CFR2.790) ML20126F4911985-06-0707 June 1985 Forwards Proposed Amend 1 to FDA-1 for GESSAR-II BWR/6 Nuclear Island Design,For Review.Amend Prepared in Anticipation of Final Commission Action on Severe Accident Policy Statement.Comments Requested by 850614 1990-09-19 Category:OUTGOING CORRESPONDENCE MONTHYEARML20059L2881990-09-19019 September 1990
[Table view]Forwards Request for Addl Info Re Application for Certification of Advanced BWR Design ML20059A3931990-08-15015 August 1990 Forwards Request for Addl Info Re GE Application for Certification of Advanced BWR Design.Responses to Encl 1 Requested by 900831 & Responses to Encls 2 & 3 by 900928 ML20055J2661990-07-27027 July 1990 Forwards Request for Addl Info Re GE Application for Certification of Advanced BWR Design ML20055E0691990-06-29029 June 1990 Forwards Synopsis of NRC Investigation Rept 03-87-011 Re Investigation Performed at Facility,For Info ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) IA-89-409, Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6)1989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20247R3361989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248F0321989-09-14014 September 1989 Forwards Rept of AOs at Licensed Facilities for First Calendar Quarter 1989.Plug Failure Resulted in Steam Generator Tube Leak at North Anna Unit 1 & Steam Generator Ruptured at McGuire Unit 1.W/o Encl ML20247L2401989-09-13013 September 1989 Responds to Re K Barnes Concerns Regarding Safety at Plants.Advises That to Date,Releases from Plants Remain Well within Accepted Stds ML20247G2781989-09-13013 September 1989 Partial Response to FOIA Request for Records.Apps F & G Records Available in Pdr.App H Records Partially Withheld & App I Record Completely Withheld (Ref FOIA Exemption 5) ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246K8571989-08-25025 August 1989 Discusses NRC Actions in Reponse to Constituent Concerns Re Excessive Overtime Worked by Employees of Plants ML20246C7101989-08-18018 August 1989 Forwards Order,Effective Immediately,Modifying CPs CPEP-1 & CPEP-2 to Require Notification of Commission Before Taking Possession of Any Classified Equipment & to Show Cause Why CPs Should Not Be Revoked ML20246B6591989-08-18018 August 1989 Forwards 40th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants from Apr-June 1989. Lilco Shareholders Voted to Accept Terms That Provide for Sale of Plant to State of Ny ML20246E1681989-08-17017 August 1989 Forwards Draft SER Re Final Design Approval & Design Certification of Advanced Bwr,For Use ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20246C8211989-08-11011 August 1989 Confirms 890808 Telcon Re Util Participation in NRC Regulatory Impact Survey on 891023 in Berlin,Ct.Schedule & General Discussion Groups Shown in Encl ML20245F0271989-08-0707 August 1989 Provides Clarification & Further Guidance Re Containment Design to Assure That Containment Conditional Failure Probability Less than 1 in 10 When Weighted Over Credible Core Damage Sequences.Goal of 0.1 Possible ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan ML20248C0561989-08-0303 August 1989 Forwards Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants.Nrc Requested to Be Notified Upon Completion of Human Factors Review ML20245H5331989-08-0202 August 1989 Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed ML20247P9581989-08-0101 August 1989 Partial Response to FOIA Request.App a Records Available in Pdr.App B Records Encl & Available in PDR ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration ML20247F0481989-07-25025 July 1989 Partial Response to FOIA Request for Records.App L Record Available in Pdr.App M Records Partially Withheld Ref (FOIA Exemption 7).App N Record Provided to Requestor But Not Made Publicly Available at This Time ML20246P0181989-07-17017 July 1989 Forwards Request for Addl Info Re 890620 Filing for Reorganization in Us Bankruptcy Court.Nrc Will Initiate Proceeding for Suspension or Revocation of CPs Should Licensee Fail to Respond by 890815 ML20246C0101989-06-30030 June 1989 Forwards Ltr from Director,Ofc of Nrr,Ack Receipt of Petition Filed by Ecology Ctr of Southern CA & Stating That Petition Is Being Treated Under 10CFR2.206 ML20246A2951989-06-29029 June 1989 Forwards Request for Addl Info Re NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20246L2211989-06-26026 June 1989 Forwards Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Revise Tech Specs by Removing Tech Spec Figures 6.2-1 & 6.2-2 Re Organizations Functional Requirements ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245B4271989-06-21021 June 1989 Final Response to FOIA Request.App U Records Encl & Available in Pdr.App V Record Withheld (Ref FOIA Exemption 5) ML20245F2691989-06-16016 June 1989 Forwards SER Accepting Licensee 850612 Response to Generic Ltr 83-28,Item 4.5.3 Re Trip Reliability & on-line Functional Testing of Trip Sys ML20245C3691989-06-16016 June 1989 Advises of Intended Visit to Audit Process of Verification & Validation for Advanced BWR Software Development ML20245B6941989-06-16016 June 1989 Forwards Director'S Decision,Ltr of Transmittal & Fr Notice in Response to Ocre Petition Filed Under 10CFR2.206. Petitioner Expressed Concerns Re 890309 Power Oscillation Event at LaSalle Unit 2 & Requested Commission Action ML20245H1491989-06-15015 June 1989 Submits Correction/Clarificaton to Util 890508 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Program on Critical Air Demand Equipment Is in Addition to Investigations Performed ML20245B3881989-06-15015 June 1989 Responds to Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels.Util Actions Do Not Have Adverse Impact on Nuclear Reactor Safety to Extent That Protection of Safety of Environ Affected ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable ML20244C2941989-06-0909 June 1989 Advises Tht Util 890329 Request for Approval to Use Fuses for Electrical Isolation of non-Class 1E Dc Power Sys Acceptable Provided That Circuit Breaker in Parallel to Two Fuses Locked Open ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20244C5091989-06-0101 June 1989 Advises That Bunker Ramo Penetration Assemblies Environmentally Qualified to Perform Intended Functions for Plants,Per 890224 Rept & .Concerns Expressed in Re Byron Unit 2 Satisfied ML20248C2671989-05-31031 May 1989 Forwards Insp Repts 50-321/88-37,50-366/88-37 & 50-424/88-53 on 881102-890106 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790(d) & 73.21) ML20247M7731989-05-26026 May 1989 Forwards Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 ML20247H3511989-05-19019 May 1989 Advises That Licensee Response to Generic Ltr 82-33 Re post-accident Monitoring Instrumentation,Per Rev 3 to Reg Guide 1.97,acceptable,except for Four Items Listed in Technical Evaluation Rept ML20247J7801989-05-19019 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, Mutually Agreed Upon Between NRC & Westinghouse During 890411 Meeting ML20247C1521989-05-18018 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Understands That Westinghouse Will Provide Util W/Generic Bounding Analysis Re Seismic Loadings ML20247G5241989-05-18018 May 1989 Responds to Re Util Position on Dealing W/Dc Grounds After Discussion W/Nrc in 890301 Meeting.Continued Plant Operation Will Be Allowed Only So Long as Applicable Limiting Conditions/Or Action Statements Met 1990-09-19 |
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UNITED STATES NUCLEAR REGULATORY COMMISSION t aj wAssiNatoN, D, C. 20555 March 15,1988
%, . . . . p' Docket No. STN 50-447 Mr. Ricardo Artigas, Manager Licensing and Consulting Services GE Nuclear Energy, Mail Code 682 General Electric Company 175 Curtner Avenue San Jose, CA 95125
Dear Mr. Artigas:
SUBJECT:
RELOCATION OF 0FFICE OF NUCLEAR REACTOR REGULATION I would like to inform you of the relocation of the Nuclear Regulatory Comission's Office of Nuclear Reactor Regulation to a building located at One White Flint North, 11555 Rockville Pike, Rockville, Meryland. Our official mailing address still remains U.S. Nuclear Regulatory Comissicn, Washington, D.C. 20555. Our Project Managers have new locations and phone numbers. Mr. Dino C. Scaletti is still the lead Project Manager for your facility and is located at 11-H-8. His new phone number is 1-301-492-1104.
Mr. Paul H. Leech will serve as the back-up Project Manager and he is located at 11-H-6 and his phone number is 1-301-492-1103.
Sincerely.
- E 6-( 6 fy.b.tu N
- v-l Lester S. Rubenstein Director Standardization and Non-Power Reactor Project Directorate :
Division of Reactor Projects - III, IV V and Special Projects Office of Nuclear Reactor Regulation ec: See next page !
ee032k$hck PDR e
GESSAR II Docket No. STN 50-447 cc: Mr. Robert Mitchell General Electric Company 175 Curtner Avenue San Jose, California 95114 Mr. L. Gifford, Manager Regulatory Operations Unit General Electric Company 7910 Woodmont Avenue Bethesda, Maryland 20814 Director, Criteria & Standards Division Office of Radiation Programs U. S. Environmental Protection Agency 401 M Street, S.W.
Washington, D.C. 20460 Mr. Daniel F. Giessing Division of Nuclear Regulation and Safety Office of Converter Reactor Deploynent, NE-12 Office of Nuclear Energy Washington, D.C. 20545 i
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I
March 15,1988 Docket No. STN 50-605 ABUR ,
e i
Mr. Ricardo Artigas, Manager l Licensing and Consulting Services GE Nuclear Energy, Mail Code 682 :
General Electric Company 175 Curtner Avenue San Jose, CA 95125
Dear Mr. Artigas:
SUBJECT:
RELOCATION OF OFFICE OF NL' CLEAR REACTOR REGULATION I would like to inform you of the relocaMon of the Nuclear Regulatory Comission's Office of Nuclear Reactor Regulation to a building located at One White Flint North, 11555 Rockville Pike, Rockville, Maryland. Our '
official mailing address still remains U.S. Nuclear Regulatory Comissien, Washington, D.C. 20555. Our Project Managers have new locations and phone numbers. Mr. Dino C. Scaletti is still the lead Project Manager for your facility and is located at 11-H-8. His new phone number is 1-301-492-1104.
Mr. Paul H. Leech will serve as the back-up Project Manager and he is located at 11-H-6 and his phone number is 1-301-492-1103.
Sincerely, ,
priginni Signed By:
t Lester S. Rubenstein, Director Standardization and Non-Power ,
Reactor Project Directorate Division of Reactor Projects - III, IV V and Special Projects ;
Office of Nuclear Reactor Regulation Distribution: A SIMILAR LETTER WAS ALSO SENT TO N C. STN 50-447 NRC~& Iccal PDRs ,
PDSNP Reading EHylton DScaletti FC :PD5NP :PD5N :PD5NP
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. . .fL t o n: $.aletti
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