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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) IR 05000456/19993011999-07-15015 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams 1999-09-08
[Table view] Category:NRC TO VENDOR/MANUFACTURER
MONTHYEARML20246C7101989-08-18018 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 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 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 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) 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 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 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 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 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 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 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 ML20133L6851985-08-0707 August 1985 Provides Guidance on Required 10CFR21 Notification Re Stainless Steel Pipe Furnished to Util,Per . Notification Requirements Apply to Any Defect,As Defined by 10CFR21,discovered After Effective Date of 10CFR21 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) ML20128L5161985-05-22022 May 1985 Concludes That 1985 Financial Info,Per 850419 Submittal, Satisfies 10CFR140.21,requiring That Each Licensee Maintain Approved Guarantee of Payment of Deferred Premiums for Each Operating Reactor Over 100 Mw(E) ML20129B2161985-05-20020 May 1985 Approves 841018 & 830926 Requests for Withholding WCAP-10690 & WCAP-10691, Technical Bases for Eliminating Large Primary Loop Pipe Rupture..., from Public Disclosure Per 10CFR2.790 ML20137G9831983-12-0909 December 1983 Notifies of 840111 Meeting in Shiller Park,Il to Discuss Scheduling Problems Re Exam Process & Examiner Stds, (NUREG-1021).Attendee Names & Addl Discussion Subjs Should Be Submitted by 831219.Preliminary Agenda Encl ML20137G9721983-07-22022 July 1983 Advises That Region III Telephone Number Will Be Changed Effective 830822.New Number Listed.Notice of Change Will Appear in Fr Prior to 830822 ML20055A4331982-06-16016 June 1982 Discusses Alternative Methods for NRC to Conduct Confirmatory Analyses of Westinghouse NSSS Designed NSSS W/O Involvement of OL Applicants.Transient & Accident Evaluation Performed on Generic Basis Generally Acceptable ML20054E8951982-06-0707 June 1982 Approves Request for Withholding Info Per 10CFR2.790 Re Improved Thermal Design Procedures (CAW-82-15) ML20137G8881981-08-28028 August 1981 Forwards IE Info Notice 81-26, Compilation of Health Physics Related Info Items. Five Items of Info That Generally Have Impact on Areas Normally Under Responsibility of Health Physics Group Listed ML20137G5071981-07-31031 July 1981 Forwards IE Info Notice 81-22, Section 235 & 236 Amends to Atomic Energy Act of 1954, Which Should Be Brought to Attention of Employees & Others Involved in NRC-licensed Activities.No Response Required IR 05000264/19790031979-12-0505 December 1979 Forwards Insp Rept 50-264/79-03 on 791022-24 & Notice of Violation ML20137H0401979-11-0909 November 1979 Forwards IE Info Notice 79-12A, Attempted Damage to New Fuel Assemblies. No Response Requested ML20137H0341979-10-17017 October 1979 Submits New Telephone Number for Region Iii,Effective 791022 ML20137H0031978-08-11011 August 1978 Ack Receipt of 780727 Response to Notice of Violation ML20137H0221978-06-12012 June 1978 Forwards IE Bulletin 78-08, Radiation Levels from Fuel Element Transfer Tubes ML20137H1121978-02-0606 February 1978 Confirms 780202 Telcon Re Meeting Between NRC & Dow Chemical Co on 780207 at Facility to Discuss Results of Physical Security Insp on 780110-12 ML20137H3941977-11-21021 November 1977 Forwards Amend 3 Renewing License R-108 & Incorporating Security Plan as License Condition.Safety Evaluation,Eia Notice of Issuance & Negative Declaration Also Encl.Security Plan Withheld (Ref 10CFR2.790) ML20137G9311977-08-18018 August 1977 Forwards Insp Rept 50-264/77-02 on 770719-22,26 & 27.No Noncompliance Noted ML20137H1161977-07-22022 July 1977 Ack Receipt of Informing of Recovery of 200-mCi Cs-137 Sealed Source from Brine Well on 770621 ML20137H2171977-07-18018 July 1977 Forwards IE Circular 77-10, Vacuum Conditions Resulting in Damage to Liquid Process Tanks ML20140F5801977-06-0606 June 1977 Advises That GE 770303 Conclusions That Leaking Safety/Relief Valves Would Result in Lower Loads on Structures than First Actuation W/O Leakage Unjustified,For Listed Reasons ML20137H3901977-04-15015 April 1977 Requests That Encl Notice Re Direct Accessibility of IE to Employees Concerned About Quality of Work,Radiological Safety or Safeguards at Facility Be Posted ML20137H3511976-12-17017 December 1976 Forwards IE Circular 76-03, Radiation Exposures in Reactor Cavities. Prompt Reply Requested.Original Submittal Forwarded on 760913 Not Received as Noted on 761214 IA-85-256, Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies1976-09-0101 September 1976 Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies ML20137H4101976-09-0101 September 1976 Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies ML20234E7981976-07-0808 July 1976 Forwards List of Info Required to Complete Review of LWR ECCS Performance to Verify Conformance to 10CFR50.46.Info Must Be Filed on GESSAR-238 & GESSAR-251 Dockets as Part of Std SAR & Be Reviewed Prior to Preliminary Design Approval ML20235E5831976-07-0707 July 1976 Forwards Description of NRC Position on Safety Relief Valve Discharge Piping as Result of NRC Continuing Review of Quencher Safety Relief Valve Discharge Device for Facility. Commitment to Implement NRC Position Requested by 760716 1989-08-18
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations IR 05000456/19993011999-07-15015 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative ML20195F3231999-06-0909 June 1999 Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20207A5891999-05-20020 May 1999 Forwards Insp Repts 50-456/99-05 & 50-457/99-05 on 990405-23.Two non-cited Violations Identified ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities ML20207B8751999-05-18018 May 1999 Responds to Ltr Dtd 990225,expressing Concerns That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazards at Some Commercial Nuclear Power Plants in Us ML20206U4641999-05-18018 May 1999 Responds to Util 990517 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3.0.3. Documents 990516 Telcon with Licensee Re NOED ML20206N4791999-05-13013 May 1999 Forwards RAI Re 980529 Amend Request for Byron & Braidwood to Credit Automatic PORV Operation for Mitigation of Inadvertent SI at Power Accident.Response Requested 60 Days After Receipt Date ML20206Q5321999-05-11011 May 1999 Forwards Insp Repts 50-456/99-06 & 50-457/99-06 on 990302-0413.Configuration Control Error Resulted in Isolation of Unit 1 Emergency Boration Flow Path Through Designated Boric Acid Pump for Period of 3 H Occurred ML20206J1981999-05-0505 May 1999 Forwards Exam Answer Key for Forms a & B,Grading Results for Facility & Copies of Individual Answer Sheets for Each Individual Taking Gfes of Written Operator Licensing Exam Administered by NRC on 990407.Without Encls 1999-09-08
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Mr. Robert A. Wiesemann ,WN 10185 You stated that the submitted information should be considered exempt from i mandatory public disclosure for the following reasons:
The use of infomation developed by Westinghouse gives Westing-house a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position. The information is marketable in many ways and the extent to which it is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information. Use of the information by a competitior would put Westinghouse at a competitive disadvantage by reducing the expenditure of resources at Westinghouse expense.
We have reviewed your application and the material based on the requirements and criteria of 10 CFR 2.790 and, on the basis of Westinghouse and Comonwealth
- Edison Company statements, have detemined that the submitted infomation sought
{ to be withheld contains trade secrets or proprietary comercial information.
We have determined that WCAP-10553, " Technical Bases for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for Byron Units 1 and 2 and Braidwood Units 1 and 2," marked as proprietary, should be withheld from i public disclosure pursuant to 10 CFR 2.790(b)(5) and Section 103(b) of the Atomic '
Energy Act of 1954, as amended.
We, therefore, approve your request for withholding pursuant to 10 CFR 2.790 and are withholding WCAP-10553 " Technical Bases for Eliminating Large Primary
- Loop Pipe Rupture as the Structural Design Basis for Byron Units 1 and 2 and
! Braidwood Units 1 and 2," from public inspection as proprietary, except as
{ noted in paragraph 2 of page 1.
I Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, we may send copies of this information to our consultants working in this area. We will, of course, insure that the consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should '
change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You should also 3
understand that the NRC may have cause to review this determination in the
- future, such as if the scope of a Freedom of Information Act request includes
- your information. In all review situations, if the NRC needs additional
, infomation from you or makes a detemination adverse to the above, you will
- be notified in advance of any public disclosure.
I Sincerely, l 8506140317 B506 54 Am 0 B. J. Youngblood, Chief j
l fR PDR Licensing Branch No. 1 Division of Licensing cc: See next page
- SEE PREVIOUS CONCURRENCES 1
, c I L LB#1/DL LB#1/DL OELD LBA IN,,l l MEIM-
- MRu rook /mac *L01shan *JStevens *RShomaker B; Y m b ood ecker L _ . _ 3
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/ %, UNITED STATES
.5[ g-
- j NUCLE AR REGULATORY COMMISSION WASHINGTON, D. C. 20655
,/ JUN 101985 Docket Nos.: STN 50-454, STN 50-455 and- STN 50-456, STN 50-457 i
Mr. Robert A. Wiesemann, Manager
- Regulatory & Legislative Affairs Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 j
Dear Mr. Wiesemann:
Subject:
Withholding from Public Disclosure - CAW-84 44I - WCAP-10553 and
., WCAP-10554 " Technical Bases for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for Byron Units 1 l
- , and 2 and Braidwood Units 1 and 2" ;
By your application and affidavit, dated June 1, 1984 and September 26, 1983, respectively, the proprietary version (WCAP-10553) and the non-proprietary version (WCAP-10554) of the report entitled " Technical Bases for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for Byron Units 1 and 2 and Braidwood Units 1 and 2," were transmitted by Commonwealth Edison Company letter, dated September 17, 1984. You requested that WCAP-10553, the proprietary version of this report be withheld from public disclosure pursuant to 10 CFR 2.790.
Discussions among Westinghouse and NRC technical / legal staffs regarding the release of infonnation considered by Westinghouse to be proprietary have
, resulted in Westinghouse agreeing to pennit the NRC staff to release infor-mation concerning mechanistic fracture mechanics analyses of RCS primary loop piping and large Class 1 piping attached to the RCS. The information which ,
Westinghouse agreed to release as stated in a letter to Darrell G. Eisenhut, dated November 15, 1984 is as follows-l
- 1. Plant parameters (operating temperatures, operating pressures, i
pipe dimensions)
- 2. Margin numbers (e.g., a factor of ,10 on a specific criteria)
- 3. Specific plant moments and forces
. 4. Reference to the analytical methods used (i.e., limit load) f
- 5. Leak rates
- 6. Reference crack size The informatien will be released in the staff Safety Evaluation or a Supplement
- - thereto. Other than the items indicated above the report is considered to be proprietary.
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BYRON /BRAIDWOOD Mr. Dennis L. Farrar Director of Nuclear Licensing Comonwealth Edison Company Post Effice Box 767 Chicago, Illinois 60690 cc: Mr. William Kortier Dr. Bruce von Zellen Atomic Power Distribution Department of Biological Sciences Westinghouse Electric Corporation Northern Illinois University Post Office Box 355 DeKalb, Illinois 61107 Pittsburgh, Pennsylvania 15230 Mr. Julian Hinds Joseph Gallo, Esq. V. S. Nuclear Regulatory Comission Isham, Lincoln & Beale Byron / Resident Inspectors Office 1120 Connecticut Ave., N. W. 4448 Gennan Church Road Suite 840 Byron, Illinois 61010 .
Washington, D. C. 20036 Ns. Diane Chavez C. Allen Bock, Esquire 528 Gregory Street Post Office Box 342 Rockford, Illinois 61108 Urbana, Illinois 61801 Mrs. Phillip B. Johnson Thomas J. Gordon, Esquire 1907 Stratford Lane Waaler, Evans & Gordon Rockford, Illinois 61107 2503 S. Neil Champaign, Illinois 61820 Douglass Cassel, Esq.
109 N. Dearborn Street Ms. Bridget Little Rorem Suite 1300 Appleseed Coordinator Chicago, Illinois 60602 117 North Linden Street Essex, Illinois 60935 Ms. Pat Morrison 5568 Thunderidge Drive Mr. Edward R. Crass Rockford, Illinois 61107 Nuclear Safeguards and Licensing Division David C. Thomas Esq.
Sargent & Lundy Engineers 77 S. Wacker Drive 55 East Monroe Street Chicago, Illinois 60601 Chicago, Illinois 60603 Rebecca J. Lauer, Esq.
U. S. Nuclear Regulatory Comission Isham, Lincoln & Beale Resident Inspectors Office Three First National Plaza RR#1, Box 79 Suite 5200 Braceville, Illinois 60407 Chicago, Illinois 60602
o- .
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-DISTRIBUTION:
- ,6 NRC PDR
' PRC System
.NSIC Local PDR
'LB#1 R/F MRushbrook L01shan JStevens EJordan EHeinschman OELD, Attorney ACRS (16)
.EShomaker, OELD 8