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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) 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 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 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 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 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 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 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 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) 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 ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes 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 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 ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 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 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 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 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 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) 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 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 BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted 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 ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes 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 05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999 Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below 05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999 Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations 05000456/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed1999-06-15015 June 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed 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 BW990028, Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.51999-06-10010 June 1999 Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.5 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 1999-09-08
[Table view] Category:NRC TO ENGINEERING/CONSTRUCTION/CONSULTING FIRM
MONTHYEARML20235C4991987-09-16016 September 1987 Responds to 870723 & 31 Ltrs to R Reagan & L Zech, Respectively,Requesting Reconsideration of Approval of License for Facility.Aslb Concluded Reasonable Assurance Exists That Electrical Sys Could Be Operated Safely ML20237F9341987-08-11011 August 1987 Responds to on Decisions Made by ASLB to Authorize NRR to Issue License to Operate.Unanimous Decision Not Needed.Majority Vote Controls in Any Decision ML20235F5321987-07-0101 July 1987 Responds to Requesting That Facility Not Be Allowed to Operate Since There Was Not Unanimous Decision by Aslb.Regulations Do Not Require Unanimous Decision.License Authorizing Operation Up to 5% Power Issued on 870521 ML20214V9111987-06-0909 June 1987 Partial Response to FOIA Request for Documents Re Status of Preparedness for Licensing.Forwards App F Documents.App E & F Documents Available in PDR ML20129C7121985-04-19019 April 1985 Responds to FOIA Request for All Info on NRC Const Assessment Team Analysis of Facility.Advises That Const Assessment Team Rept Available in PDR ML20126J9081985-03-0606 March 1985 Further Response to FOIA Request That All Internal Memos to Div of Licensing from May-Nov 1984 Which Provided Draft SER, SER Sections & Questions or Requests for Addl Info Be Placed in Pdr.App C Documents Placed in PDR 1987-09-16
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 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 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 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 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 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) 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 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 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 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 ML20206H8161999-05-0505 May 1999 Confirms Discussion Re Meeting to Be Conducted on 990527 at Braidwood Station Training Building.Meeting Will Discuss Braidwood Station Performance as Described in Most Recent Plant Performance Review ML20206E7021999-05-0303 May 1999 Advises That Info Contained in Document Entitled, Licensing Rept for Sf Rack Installation at Byron & Braidwood Stations, HI-982083,will Be Withheld from Public Disclosure Per 10CFR2.790 ML20205G9631999-03-26026 March 1999 Advises of Planned Insp Effort Resulting from Braidwood Plant Performance Review for Period 870830-990131.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 6 Months Encl ML20204J4241999-03-23023 March 1999 Forwards Insp Repts 50-456/99-04 & 50-457/99-04 on 990222-24 & 0303 Onsite & 0309 & 11 Region 3 Ofc.No Violations Noted. Implementation of Physical Security Plan Was Examined ML20204J9001999-03-23023 March 1999 Forwards Insp Repts 50-456/99-02 & 50-457/99-02 on 990120- 0301.No Violations Noted ML20204G2031999-03-22022 March 1999 Forwards Year 2000 Readiness Audit Rept Which Documents Results of NRR Audit Conducted at Facility from 990124-28 ML20204C7201999-03-16016 March 1999 Ack Receipt of Expressing Concern Over Sale of Certain Properties by Commonwealth Edison Co ML20204E3341999-03-16016 March 1999 Expresses Appreciation for Re Concerns Over Sale of Certain Properties by Licensee.No Regulatory Basis for NRC to Require Util to Rely on strip-mine Ponds as Suppl Source of Cooling Water ML20204E2801999-03-16016 March 1999 Ack Receipt of Rev 3M to Portions of Braidwood Nuclear Power Generating Station Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Ceco Determinations That Changes in Rev 3M Do Not Decrease Effectiveness of Plan ML20207J9741999-03-11011 March 1999 Discusses Rev 3,to Portions of Braidwood Power Station EP Site Annex.Based on Licensee Determinations That Changes Do Not Decrease Effectiveness of EP & Plan Continues to Meet Standards of 10CFR50.47(b),NRC Approval Not Required ML20203E9521999-02-11011 February 1999 Forwards Insp Rept 50-456/98-16 on 980916-990121.No Violations Were Identified.Insp Was Exam of Activities Re Engineering & Maint Activities for Replacement of Steam Generators for Compliance with Commission Regulations ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203C9761999-02-0808 February 1999 Ack Receipt of ,Which Transmitted Changes Identified as Rev 44 to Security Plan.No NRC Approval Required ML20203A4601999-02-0505 February 1999 Ack Receipt of 981109 Evaluation of Indication in Base Metal of Braidwood Station,Unit 1,main Steam Piping Sys Elbow ML20203A3641999-02-0303 February 1999 Forwards Copy of FEMA Evaluation Rept for 980520 Emergency Preparedness Exercise at Braidwood.One Deficiency & Three Areas Requiring Corrective Action Identified.Deficiency Corrected During Remedial Exercise Held on 980806 ML20199E6561999-01-15015 January 1999 Discusses Unresolved Security Item Re Adequacy of Compensatory Measures Implemented for Section of Vehicle Barrier Sys.Issue Briefly Described as Listed ML20199E1351999-01-0808 January 1999 Forwards Revised Dates for Engineering & Technical Support Insp,Emergency Planning Insp,Security Insp & Operational Assessment Insp for Braidwood IR 05000456/19980141999-01-0505 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts on 50-456/98-14 & 50-457/98-14 Issued on 981117 ML20198R0741998-12-30030 December 1998 Forwards Insp Repts 50-456/98-20 & 50-457/98-20 on 981020-1207.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20197J6831998-12-10010 December 1998 Forwards Insp Repts 50-456/98-21 & 50-457/98-21 on 981110- 24.No Violations Noted.Insp Reviewed Corrective Actions for Previously Identified Issues ML20197H4261998-12-0404 December 1998 Forwards Insp Rept 50-456/98-18 on 981015-23 & 1109-10.No Violations Noted.Some Weaknesses Identified in Operator Performance & Training ML20197K1311998-12-0202 December 1998 Forwards Planned Insp Effort for Next 6 Months at Plant.Info Provided to Minimize Resource Impact on Staff & Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite 1999-09-06
[Table view] |
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September 16, 1987 i
Docket No. STN 50-456 Mr. Milan G. Weber, President The Milan G. Weber Associates, Inc.
. P.O. Box 81 Deerfield, Illinois 60015
Dear Mr. Weber:
Your letters of July 23, 1987 to the President of the United States and of j July 31, 1987 to Chairman Lando Zech have been forwarded to me for reply. In your letters, you urge that the Nuclear Regulatory Commission (NRC) reconsider its approval of a license for the Braidwood nuclear power station. You base your request, in principal part, on the fact that the Chairman of the Atomic Safety and Licensing Board (ASLB) in the Braidwood case prepared a dissenting opinion concerning licensing the plant. We have previously responded to this concern in our letters to you dated July 1,1987 and August 11, 1987.
The hearing conducted by the ASLB was only one part of the Braidwood licensing process. Prior to the hearing in which the ASLB handed down its decision on Braidwood, the hRC had extensively evaluated the plant. Each of the plant's safety systems was reviewed to ensure that it met all of the Commission's regulations and requirements. Throughout the construction of Braidwood, the NRC staff, including a full-time person on the site, reviewed and inspected all major facets of the plant to verify that it was constructed in conformance with NRC requirements. In response to concerns about construction quality, Commonwealth Edison Company, the Braidwood licensee, initiated the Braidwood Construction Assessment Program. In that program, a thorough reinspection of completed work and records was conducted by qualified' teams not connected with those engaged in the original work. Additionally, the Commission's Advisory Committee on Reactor Safeguards reviewed the design and the proposed operation of Braidwood, and concluded that Braidwood Units 1 and 2 could be operated at full power without undue risk to the health and safety of the public. Finally, I in a separate action, in its Memorandum and Order (CLI-87-07), the Connission found that the ASLB decision resolved all contested issues and authorized the i Director, Office of Nuclear Reactor Regulation, to issue a full power license for the Braidwood facility.
The Chairman of the ASLB, in his dissent on this issue, concluded that although there had been allegations that inspectors were harassed (as you mention), the inspectors " performed their field inspections competently and successfully resisted any attempts that may have been made by management to sacrifice <
quality for quantity." The ASLB was unanimous in concluding that there is j reasonable assurance that the part of the electrical system that was installed '
during the period at issue under the allegation could be operated safely.
9709240471 070916 PDR H ADOCK 05000456 PDR
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4.
Mr. Milan G. Weber .2 September 16, 1987 Please be assured that the Nuclear Regulatory Commission staff at all levels of responsibility is fully dedicated to ensuring that the Braidwood station
.will be operated safely in conformance with the Commission's Regulations.
Sincerely, orie, tral cienua bm mcuaa L.11arleZ/
Thomas E. Murley, Director
_0ffice of Nuclear Reactor Regulation Distribution:
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0FFICIAL RECORD COPY i
a % l l
. September 16, 1987 Docket No. STN 50-456 Mr. Milan G. Weber, President The Milan G. Weber Associates, 7.nc.
P.O. Box 81 Deerfield, Illinois 60015
Dear Mr. Weber:
Your letters of July 23, 1987 to the President of the United States and of July 31, 1987 to Chairman Lando Zech have been forwarded to me for reply. In ,
your letters, you urge that the Nuclear Regulatory. Commission (NRC) reconsider .)
its approval of a license for the Braidwood nuclear power station. You base !
your request, in principal part, on the fact that the Chairman of the Atomic Safety and Licensing Board (ASLB) in the Braidwood case prepared a dissenting opinion concerning licensing the plant. We have previously responded to.this concern in our letters to you dated July 1,1987 and August 11, 1987.
l The hearing conducted by the ASLB was only one part of the Braidwood licensing l process. Prior to the hearing in which the ASLB handed down its decision on Braidwood, the hRC had extensively evaluated the plant. Each of the plant's i
l safety systems was reviewed to ensure that it met all of the Commission's '
l regulations and requirements. Throughout the construction of Braidwood, the l HRC staff, including a full-time person on the site, reviewed and inspected all major facets of the plant to verify that it was constructed in conformance ,
with NRC requirements. In. response to concerns about construction quality, !
Commonwealth Edison Company, the Braidwood licensee, initiated the Braidwood Construction Assessment Program.. In that program, a thorough reinspection of j completed work and records was conducted by qualified teams not connected with l those engaged in the original work. Additionally, the Commission's Advisory Committee on Reactor Safeguards reviewed the design and the proposed operation i of Braidwood, and concluded that Braidwood Units 1 and 2 could be operated at-full power without undue risk to the health and safety of the public. Finally, in a separate action, in its Memorandum and Order (CLI-87-07), the Commission found that the ASLB decision resolved all contested issues and authorized the Director, Office of Nuclear Reactor Regulation, to issue a full power license for the Braidwood facility.
The Chairman of the ASLB, in his dissent on this issue, concluded that although there had been allegations that inspectors were harassed (as you mention), the inspectors " performed their field inspections competently and successfully resisted any attempts that may have been made by management to sacrifice quality for quantity." The ASLB was unanimous'in concluding that there is reasonable assurance that the part of the electrical system that was installed !
during the period at issue under the allegation could be' operated safely. '
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.g Mr. Milan G. Weber September 16, 1987 Please be assured that the Nuclear Regulatory Commission staff at all levels of responsibility is fully dedicated to ensuring that' the Braidwood station will be operated safely in conformance with the Commission's Regulations.
Sincerely, onpie 13 a '.3
- .u ua:.1. 2:nAcz/
Thomas E. Murley, Director Office of Nuclear Reactor Regulation Distribution:
Docket File (NRC PDRs Loc 51 PDR EDO 003135 E00 r/f TMurley/JSniezek FMiraglia PDIII-2 r/f DCrutchfield RStarostecki JFunches JBlaha ,
GHolahan !
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September 16, 1987 Docket No. STN 50-456 Mr. Milan G. Weber, President The Milan G. Weber Associates, Inc.
P.O. Box 81 Deerfield, Illinois 60015
Dear Mr. Weber:
Your letters of July 23, 1987 to the President of the United States and of July 31, 1987 to Chairman Lando Zech have been forwarded to me for reply. In your letters, you urge that the Nuclear Regulatory Commission (NRC) reconsider its approval of a license for the Braidwood nuclear power station. You base your request, in principal part, on the fact that the Chairman of the Atomic Safety and Licensing Board (ASLB) in the Braidwood case prepared a dissenting opinion concerning licensing the plant. We have previously responded to this concern in our letters to you dated July 1,1987 and August 11, 1987.
The hearing conducted by the ASLB was only one part of the Braidwood licensing process. Prior to the hearing in which the ASLB handed down its decision on Braidwood, the hRC had extensively evaluated the plant. Each of the plant's safety systems was reviewed to ensure that it met all of the Commission's regulations and requirements. Throughout the construction of Braidwood, the NRC staff, including a full-time person on the site, reviewed and inspected all major facets of the plant to verify that it was constructed in conformance with NRC requireinents. In response to concerns about construction quality, Commonwealth Edison Company, the Braidwood licensee, initiated the Braidwood Construction Assessment Program. In that program, a thorough reinspection of completed work and records was conducted by qualified teams not connected with those engaged in the original work. Additionally, the Commission's Advisory Committee on Reactor Safeguards reviewed the design and the proposed operation of Braidwood, and concluded that Braidwood Units 1 and 2 could be operated at full power without undue risk to the health and safety of the public. Finally, in a separate action, in its Memorandum and Order (CLI-87-07), the Commission found that the ASLB decision resolved all contested issues and authorized the Director, Office of Nuclear Reactor Regulation, to issue a full power license for the Braidwood facility.
The Chairman of the ASLB, in his dissent on this issue, concluded that although there had been allegations that inspectors were harassed (as you mention), the inspectors " performed their field inspections competently and successfully resisted any attempts that may have been made by management to sacrifice quality for quantity." The ASLB was unanimous in concluding that there is reasonable assurance that the part of the electrical system that was installed during the period at issue under the allegation could be operated safely.
(+-4 *
, h y
- Mr. !!ilan G. Weber 2- September 16, 1987 ,
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Please be assured that the Nuclear. Regulatory Comission':steff at all levels . *, y of responsibility is. fully dedicated to ensuring.that the'Braidwood station - ,
, j will be operated safely in conformance with the Comission's Regulations.
Sincerely, o,.w : 4! riy4 tu
,.a uar L. hurleZ/
Thomas E. Murley, Director .
Office of Nuclear Reactor Regulation .
Distribution:
Docket File NRC PDR LocalR PDRs.
EDO 003135 ,
ED0 r/f TMurley/JSniczek n FMiraglia j PDIII-2 r/f l t
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9/ /87 9/ /87 , !
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MILAN G. WEBER (?flettet3) . < FINAL' REPLY: 7/37/87 (WHITE HOUSE REFERRAL) i l TO: .s
, THE PRESIDENT & Chairmkn Zech a c OR:SIONATURE OF ** GREEN ** 'SECY NO: 87-1C05.&
.. . 87-1003
( MURLEY' DEsci, ROUTING:
URGES RECONSIDERATION OF THE LICENSE APPROAL FOR DAVIS,'RIII BRAIDWOOD DAIE:,AS/27/87 --
TSSIGNED TO: NRR
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CON 7ACT: _ . _ . -
MURLEY - )
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SPECIAL INSTRUCTIONS OR HEMARKS:
}9' REF. EDO.2949 .
RETURN CORRESPONDENCE AND WORKSHEET WITH COPY OF REPLY TO: i AGENCY' LIAISON > j)?
ROOM 91 //
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.. , THE WHITE HOUSE WASHINGTON, D.C. s20500 G h '! /
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t SECY' NUMBER: 87-1005 _
LOGGING DATE- s7nn9s
. ACTION OFFICE: EDO 1
AUTHOR: .M G Weber AFFILIATION: 9014 LETTER DATE: 870803 FILE CODE ID&R-5 Braidwnnd ,f l- ADDRESSEE:- NRC L
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SUBJECT:
Urges reconsideration of the. license approval for Braidwood :!
ACTION: Direct Reply..ll- . Sept 9 DISTRIBUTION: Docket
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