ML20128M700
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999
[Table view]Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified 1999-09-09 Category:NRC TO EDUCATIONAL INSTITUTION MONTHYEARIR 05000097/19890011989-05-12012 May 1989
[Table view]Forwards Safety Insp Repts 50-097/89-01 & 50-157/89-01 on 890425-26.Weakness Identified in Area of Documentation IR 05000072/19880011988-10-28028 October 1988 Ack Receipt of 880804 & 25 Ltrs Informing NRC of Steps Taken to Correct Violations & Deviations Noted in Insp Repts 50-072/88-01 & 50-407/88-01 & Order.Concludes That W/ Exception of Violation 5.c,violations Did Not Occur ML20147D0421988-02-29029 February 1988 Requests That Recipient Resubmit Proposal to Convert to Low Enriched U Fuel to Meet 10CFR50.64(6)(2) or (3) Requirements by 880327.Identical Ltrs Sent to Listed Dockets ML20206C6061987-04-0808 April 1987 Ack Receipt of & Payment of $3,000 for Civil Penalty Imposed on 870313.Corrective Actions Described in Will Be Examined During Future Insps ML20212P1851987-03-11011 March 1987 Responds to 870309 10CFR2.206 Petition for Commission Review of Director'S Decision DD-87-2.Time Period for Commission Review Expired & Decision Became Final Agency Action on 870310.Served on 870312 ML20136G3791985-11-18018 November 1985 Discusses Actions Re Claims of Alleged Inadequacies in Containment Leak Rate Tests Performed at LWR Plants.Matter Will Not Be Considered Further ML20126E4311985-03-25025 March 1985 Responds to FOIA Request for Records Re FIN B-0489, Containment Leak Rate Testing Program & Quadrex Corp/Nrc Contracts.Forwards Documents Re FIN B-0489.Documents Also Available in Pdr.No Documents Re Quadrex Subj to Request ML20128P3091984-12-0404 December 1984 Responds to 841126 & 27 Telcon Requests for Listed Info. Diagram of Mark II Containment Encl.S&W Will Forward Correct Diagram of Surry Containment.Experimental Data for Decay Heat Curve Does Not Exist.W/O Encl ML20128P2691984-11-20020 November 1984 Forwards Diagrams Illustrating Core Concrete Interaction, Based on Corcon Calculations for Facility.Concrete Consists of Limestone ML20128P2331984-11-14014 November 1984 Forwards Microfiche of EPRI Mar 1980 Revised Rept NSAC-1, Analysis of TMI-2 Accident. Version Out of Print.W/O Encl NUREG-0850, Forwards Vol 1 to NUREG-0850, Preliminary Assessment of Core Melt Accidents at Zion & Indian Point Nuclear Power Plants & Strategies for Mitigating Effects. Vol 1 Only Vol Available at Present1984-08-14014 August 1984 Forwards Vol 1 to NUREG-0850, Preliminary Assessment of Core Melt Accidents at Zion & Indian Point Nuclear Power Plants & Strategies for Mitigating Effects. Vol 1 Only Vol Available at Present ML20128N9361984-08-14014 August 1984 Forwards Vol 1 to NUREG-0850, Preliminary Assessment of Core Melt Accidents at Zion & Indian Point Nuclear Power Plants & Strategies for Mitigating Effects. Vol 1 Only Vol Available at Present ML20128N3851984-05-31031 May 1984 Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls NUREG/CR-3028, Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls1984-05-31031 May 1984 Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls ML20210E6761984-03-23023 March 1984 Forwards Region V Evaluation of Emergency Preparedness Concerns Expressed in 831104,1209 & s Included in Latest Plant Sser ML20128N2001984-03-18018 March 1984 Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept NUREG/CR-1250, Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept1984-03-18018 March 1984 Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept ML20210E6891983-12-30030 December 1983 Ack Providing Addl Data Re Concern About Method of Notifying Population in Case of Flood.Siren Concern Being Addressed.Fema Ltr Addressing Items Identified in Initial Encl ML20128M7001983-11-0101 November 1983 Forwards Draft Vols I-III to BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7741983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7601983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7311983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7951983-09-0909 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7981983-08-12012 August 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M8191983-08-12012 August 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20054L3881982-06-16016 June 1982 Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl ML20137G4721971-06-23023 June 1971 Advises That Presence & Irradiation of Explosives in Reactor Must Be Evaluated Due to Potential for Damage to Reactor. Evaluation Requested Establishing Operating Restrictions,Max Quantity of Explosives Allowed in Facility & Form ML20235C9201968-08-28028 August 1968 Requests Nm Newmark Consulting Engineering Svcs Provide Listed Svcs,Including Analyses of Engineering Factors Included in Proposed Design to Minimize Damage from Seismically Induced Ground Motion for Proposed Plant Const ML20151W9761967-02-14014 February 1967 Requests Listed Svc for Commission Per Conditions of Contract AT(49-5)2667 Re Proposed Const of PWR by PG&E at Diablo Canyon Site,Including Rept on Analyses of Engineering Factors by 670415 ML20234D9591964-11-0909 November 1964 Forwards Repts Released Re Proposed Nuclear Power Plant at Bodega Head,Ca in Accordance W/Telcon.Util Has Withdrawn Application for CP on Project.W/O Encls ML20235A3801964-09-23023 September 1964 Forwards 640916 Amend 9 to License Application for Proposed Nuclear Reactor at Bodega Bay,Ca.W/O Encl ML20239A4371964-08-0606 August 1964 Confirms Telcons W/Eg Case Re Preparations for ACRS 640824 Meeting Re Bodega Bay Reactor.Aec Has Understanding That Rept Re Seismic Aspects of PG&E Application Will Be Furnished at 640810 Meeting in Chicago,Il.Guide Encl ML20234C0651964-07-24024 July 1964 Forwards 640720 Amend 8 to PG&E Application to Construct Reactor at Bodega Head & Informs of ACRS Meeting on 640824 to Discuss Amend.W/O Amend ML20234B2981964-06-0808 June 1964 Forwards Background Info on High Energy Physics Program & Proposed Stanford Linear Electron Accelerator Project, 1961 Rept to Joint Committee on Atomic Energy,Per Re Const of Reactor at Bodega Head.W/O Encl ML20234B1921964-05-20020 May 1964 Forwards AEC to PG&E Re Bodega Head Case.Several Members of ACRS Will Be Present at Meeting at Anl on Fri, Which May Include Kv Steinbrugge ML20234B2071964-05-18018 May 1964 Confirms 640522 Meeting at Anl to Discuss Bodega Head Case, Per Telcons Last Wk.Ltr Being Prepared to Send to PG&E Re Questions Worked Out W/Acrs Members ML20234E8131964-04-0303 April 1964 Forwards Amend 7 to Util Application for License for Bodega Bay Atomic Park.W/O Encl ML20234D9511964-04-0303 April 1964 Forwards Amend 7 to Util Application for License to Unit 1 for Bodega Bay Atomic Park.W/O Encl ML20235C4831964-03-24024 March 1964 Forwards PG&E Amend 6 to Application Re Earthquake Deign Criteria for Proposed Bodega Head Reactor,Superseding Amend 4.Rept on Adequacy of Amend Criteria Will Be Discussed at ACRS May 1964 Meeting.W/O Encl ML20235C5221964-03-24024 March 1964 Forwards PG&E Amend 6 to Application Re Earthquake Design Criteria for Proposed Bodega Bay Reactor,Superseding Amend 4.Rept on Adequacy of Amend Criteria Will Be Discussed at ACRS May 1964 Meeting.W/O Encl ML20235B2061964-01-27027 January 1964 Forwards USGS Dec 1963 Rept Entitled Engineering Geology of Proposed Nuclear Power Plant Site on Bodega Head,Sonoma County,Ca for Review.Will Contact to Schedule Meeting.W/O Encl ML20235B2521964-01-24024 January 1964 Forwards Amend 5 Filed by PG&E Consisting of Bodega Head Site Repts for Review.Will Contact to Discuss Rept.W/O Encl ML20235B2701964-01-24024 January 1964 Forwards Amend 5 Filed by PG&E Consisting of Bodega Head Site Repts for Review.Will Contact.W/O Encl ML20235B1361964-01-21021 January 1964 Forwards USGS Dec 1963 Rept Entitled Engineering Geology of Proposed Power Plant Site on Bodega Head,Sonoma County,Ca. Will Contact to Schedule Meeting.W/O Encl ML20234A9761963-09-0404 September 1963 Advises That Anyone Inquiring About Proposed Plant Should Be Informed That Recipient Serving as Consultant to AEC to Assist in Evaluation of Structural Design,Per ML20234C0731963-08-15015 August 1963 Forwards Amend 4 to Facility License Application from PG&E for Proposed Nuclear Power Reactor at Bodega Bay,Ca.W/O Encl ML20234B7301963-08-15015 August 1963 Forwards Amend 4 to Facility License Application from PG&E for Proposed Nuclear Power Reactor at Bodega Bay,Ca.W/O Encl ML20234C9301963-07-26026 July 1963 Informs That Effect of Operation of Proposed Reactor on Marine Environ of Bodega Head Being Given Careful Consideration,Per ML20234C9731963-07-11011 July 1963 Forwards Us Bureau of Commercial Fisheries Review of Effects of Reactor Operations on Marine Environ at Bodega Bay,Per Re ACRS Rept on PG&E Plant.Util Will Continue Oceanographic Studies for at Least One Annual Cycle ML20234F4521963-07-10010 July 1963 Responds to to Chairman Seaborg Re Proposed Const of Nuclear Power Reactor at Bodega Head.Pamphlet Describing Procedures Re Licensing of Power Reactors by AEC Encl.W/O Encl 1989-05-12 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M6631999-10-19019 October 1999
[Table view]Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application 1999-09-09 |
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- Circ Chron NOV 1 1983 Branch r/f MSilberberg MSilberberg r/f CRyder Professor H. S. Gutkowsky Department of Chemistry University of Illinois Urbana IL 61801 ,
Dear Professor Gutkowsky:
In response to a telephone request from Dr. Havens of the American Physical Society, enclosed please find the following documents in relation to the on-going Source Term Reassessment Study.
- 1. BMI-2104, Volume I, draft report containing analysis of the PWR SURRY plant published in July 1983.
- 2. BMI-2104, Volume II and Volume III containing analysis of the BWR Mark I and Mark III (PEACH BOTTOM and GRAND GULF plants, respectively) presented during the Peer Review on July 28-29, 1983. These two volumes, as well as the others, are scheduled to'be published as BCL draft reports in October and November 1983.
In an attempt to provide you with all relevant information available to date I am enclosing a copy of the BCL presentations made during the three previous Peer Review meetings along with their official transcripts.
Relevant technical information can also be found in the attached still in draft form, prepared by Mr. S. Beal (private consultant) papers, and I Dr. D. Powers of the Sandia National Laboratory.
l As our work progresses I will be sending out the remaining reports as well as other appropriate materials.
l l
l g -110 DR g
- uw unn unC FOW 318 00 80 NRCM 0240 OFFICIAL RECORD COPY
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NOV 1 1983 Professor Gutkowsky .
Please feel free to contact me if you wish to receive any additional information or if you desire assistance in receiving referenced materials
,at(301)427-4260.
Sincerely, opir.lN Al: CPNet) RY: Yb f' pM Melvin Silberberg, Assistant Director for Research and Technical Support .
Accident Source Tenn Program Office Office of Nuclear Regulatory Research
Enclosures:
- 1. Documents (3)
- 2. BCL Presentations
- 3. Official Transcripts cc w/o enclosures:
W. Havens APS J. Gieseke, BCL D. Powers, SNL T. Kress, ORNL An identical letter with enclosures is being sent to the following:
Professor L..Lidofsky Columbia University New York, NY. 10027 ,
Dr.. David Boulware ,
Univ of Washington Seattle, WA 98195 .
o"=>! RESMSTP0 5"be4$
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une nnu ais imson uncu o2" OFFICIAL RECORD COPY
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