Letter Sequence RAI |
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MONTHYEARML20134K7381997-02-11011 February 1997 Forwards RAI Re First 10 Yr ISI Program for Plant,Units 1 & 2 Project stage: RAI ML20137Q9581997-03-17017 March 1997 Forwards RAI Re First 10-yr ISI Program & Associated Relief Requests for Plant,Units 1 & 2 Project stage: RAI ML20137B1611997-03-19019 March 1997 Forwards RAI Re First ten-year Inservice Insp Program for Plant.Copy of Response to Be Sent to Inel in Order to Expedite Review Process Project stage: RAI ML20137H5811997-03-25025 March 1997 Forwards Response to Request for Addl Info Re First 10-Yr ISI Project stage: Request ML20141B5331997-05-13013 May 1997 Forwards SE Accepting First 10-yr ISI Program Plan Request for Relief NR-29 for Braidwood Station,Units 1 & 2 Project stage: Approval ML20148G8631997-05-19019 May 1997 Forwards Revised Relief Requests for NR-27,NR-28,NR-31 & New Relief Request NR-34 Project stage: Request ML20197F9821997-12-11011 December 1997 Forwards SE Re First 10-yr Interval Insp Program Plan,Rev 4 & Associated Request for Relief for Braidwood Station,Units 1 & 2.Concludes That Rev 4 of ISI Had No Deviation from ASME Requirements Project stage: Approval 1997-03-19
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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: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] |
Text
fDE-March 1 17, l'997
LMs. Irene M.- Johnson,! Acting Manager Nuclear Regulatory Services
, Commonwealth Edison Company.
Executive Towers West III 1400 Opus P1 ace, Suite 500 Downers Grove,:IL 60515
SUBJECT:
REQUEST FOR ADDITIONAL;INFORMATION REGARDING THE FIRST 10-YEAR-INSERVICE' INSPECTION PROGRAM .BRAIDWOOD STATION (TAC.NOS. M97134
~AND M97135)
Dear Ms. Johnson:
On October 8, 1996, Commonwealth Edis Company (Comed) submitted its first 10-year, Inservice Inspection (ISI)-pr ai$gingstociatedreliefrequestsfor
Braidwood Station, Units l' and 2.- Subsequent t'a tM*3(>bmittal, Comed i st NR-29.
requested expedited review for ReliggWHENT Rn -
i' A Request for Additional Information (RAI) _was issued on February.11,1997.
Comed provided.its response on February 25, 1997, and a followup conference L call was held on March 11, 1997. A review of Comed's February 25, 1997,
. : submittal has revealed the need for further information regarding Relief Request NR-29 as discussed in the enclosed RAI. Please provide your response l' to the questions so.that we may continue our review of your submittal.
In addition, in order to expedite the review process, please send a copy of i the RAI response to our contractor, Idaho National Engineering Laboratory
[ (INEL),.at the following address:
Mr. Michael T. Anderson
- INEL Research Center 2151 North Boulevard -
i- PO Box 1625
- . Idaho Falls, Idaho 83415-2209 i Sincerely, ORIGINAL SIGNED BY
NRC HLE CEN1B CMProject ceo,,e ,. Oica, o ,., g,oject Directorate III-2
,,,,,e, i
Division of Reactor Projects - III/IV D[th r Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457f.
. DISTRIBUTION: ; Docket Filet g
- PUBLIC 2 PDIII-2 r/f
Enclosure:
. RAI J. Roe, JWR R. Capra
+
E. Adensam, EGA1 C. Moore R. Lanksbury, RIII G. Dick cc w/ encl: -see next page; T. McLellan, 07H15 OGC,- 015B18 f-9704110185 97031 J. Strosnider G. Bagchi y? PDR ADOCK 05000456 M.; Holmberg, RIII ACRS, T2E26 P PDR & D. Naujock, 07D4 Ta receive a copy of this document, indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy 0FFICE- PM:PDII?2n E LA:lGIII-2-l O ECGB -
EMCB / D:PDIII-2 l C
. NAME '
GDICK h M Ch004 GBAGCHI * -
JSTROSfD8ER RCAPRA Ra .-
DATE 03/H/97 03/%/97- 03/13/97' 0 7 /97 03/n /97 j' 300UMENT l4AME: : BR97134.LTR. ;0FFICIAL RECORD COPY E*fConcurrence b'y memorandum. dated 3/13/97
. . . - . . . - .a. J' . - . . . - -.
March 17, 1997-j g;s, 'Ms'. Irene M.' Johnson, Acting Manager-Nuclear Regulatory Services 4;,
,, Commonwealth Edison Company
- Executive Towers West III
-1400 Opus Place,< Suite 500 Downers Grove, IL: 60515-
SUBJECT:
REQUEST FOR ADDI110NAL INFORMATION REGARDING THE FIRST 10-YEAR INSERVICE INSPECTION PROGRAM - BRAIDWOOD STATION (TAC NOS. M97134 ANDM97135) i
Dear Ms. Jo'hnson:
On 0ctober 8, ~1996, Commonwealth Edison Company (Comed) submitted.its first
'10-year Inservice Inspection-(ISI): program and associated relief requests for Braidwood Station, Units 1 and 2. Subsequent to the submittal,' Comed requested expedited review for Relief Request NR-29.
= A Request for Additional Information (RAI) was issued on February 11, 1997.
Comed provided its response on February 25, 1997, and a followup conference call was held on March 11, 1997. A review of Comed's February 25, 1997, I submittal has revealed the need for further information regarding Relief )
Request NR-29 as discussed in the enclosed RAI. Please provide your response ,
-to the questions so that we may continue our review of your submittal. i In addition, in; order to expedite the review process, please send a copy of :
the RAI response _ to our contractor, Idaho National Engineering Laboratory l
-(INEL), at the following address: 1 Mr. Michael T. Anderson INEL Research Center 2151 North Boulevard PO Box 1625 .
Idaho Falls, Idaho 83415-2209 Sincerely, ORIGINAL SIGNED BY:
! George F. Dick, Jr., Project Manager ,
L Project Directorate III-2 Division of Reactor Projects - III/IV
- Office of Nuclear Reactor Regulation
! Docket Nos. STN 50-456, STN 50-457 DISTRIBUTION: Docket File
! PUBLIC PDIII-2 r/f
Enclosure:
RAI J. Roe, JWR R. Capra E. Adensam, EGA1 C. Moore R. Lanksbury, RIII G. Dick
-cc w/ enc 1: see next page T. McLellan, 07H15 OGC, 015B18
!' J. Strosnider G. Bagchi M. Holmberg, RIII ACRS, T2E26 D. Naujock, 07D4 Ta teosive a espy of this document, inecate in the boa: 'C' = Copy without enclosures *E' = Copy with enclosures *N* = No copy L OFFICE PM:PDII7 h E LA:1311-2 -C- ECGB EMCB- / D:PDIII-2 C,
, NAME GDICK h &A Clip 0M GBAGCHI* JSTROSHI8 Ell RCAPRA Ra,.- .
DATE 03//3/97: 03/E /97 - 03/13/97 V /97 03/n /97 JOCUMENT-(AME: :BR97134.LTR OFFICIAL RECORD COPY
- Concurrence by memorandum dated 3/13/97-i
. / ?'%.,
o p* % UNITED STATES 3
I s# j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30665 0001
Ms. Irene M. Johnson, Acting Manager Nuclear Regulatory Services Commonwealth Edison Company -
Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, IL 60515
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE FIRST 10-YEAR INSERVICE INSPECTION PROGRAM - BRAIDWOOD STATION (TAC NOS. M97134 ,
AND M97135) !
Dear Ms. Johnson:
On October 8,1996, Commonwealth Edison Company (Comed) submitted its first l 10-year Inservice Inspection (ISI) program and associated relief requests for l Braidwood Station, Units I and 2. Subsequent to the submittal, Comed !
requested expedited review for Relief Request NR-29.
A Request for Additional Information (RAI) was issued on February 11, 1997.
Comed provioed its response on February 25, 1997, and a followup conference call was held on March 11, 1997. A review of Comed's February 25, 1997, submittal has revealed the need for further information regarding Relief Request NR-29 as discussed in the enclosed RAI. Please provide your response to the questions so that we may continue our review of your submittal.
In addition, in order to expedite the review process, please send a copy of the RAI response to our contr' actor, Idaho National Engineering Laboratory (INEL), at the following addiess:
Mr. Michael T. Anderson INEL Research Center 2151 North Boulevard PO Box 1625 Idaho Falls, Idaho 83415-2209 Sincerely, Geo . Dick, Jr., Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
. Docket Nos. STN 50-456, STN 50-457
Enclosure:
RAI cc w/ enc 1: see next page
g ...
, I. Johnson Braidwood Station Commonwealth Edison Company Unit Nos. I and 2 cc:
Michael Miller, Esquire Mr. Ron Stephens Sidley and Austin Illinois Emergency Services j One First National Plaza and Disaster Agency Chicago, Illinois 60603 110 East Adams Street Regional Administrator t U.S. NRC, Region III Chairman 801 Warrenville Road Will County Board of Supervisors Lisle, Illinois 60532-4351 Will County Board Courthouse Joliet, Illinois 60434 Illinois Department of Nuclear Safety Ms. Lorraine Creek
- Office of Nuclear Facility Safety Rt. 1, Box 182
. 1035 Outer Park Drive Manteno, Illinois 60950 Springfield, Illinois 62704 Attorney General
. Document Control Desk-Licensing 500 South Second Street i Commonwealth Edison Company Springfield, Illinois 62701 1
- 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 George L. Edgar
. Morgan, Lewis and Bochius ,
Mr. William P. Poirier 1800 M Street, N.W. !
Westinghouse Electric Corporation Washington, DC 20036 Energy Systems Business Unit Post Office Box 355, Bay 236 West Commonwealth Edison Company Pittsburgh, Pennsylvania 15230 Braidwood Station Manager Rt. 1. Box 84 l Joseph Gallo Braceville, Illinois 60407 l Gallo & Ross ,
1250 Eye St., N.W., Suite 302 EIS Review Coordinator ;
Washington, DC 20005 U.S. Environmental Protection Agency 77 W. Jackson Blvd.
Ms. Bridget Little Rorem Chicago, Illinois 60604-3590 Appleseed Coordinator 117 North Linden Street Mr. H. G. Stanley Essex, Illinois 60935 Site Vice President Braidwood Station Howard A. Learner Commonwealth Edison Company Environmental Law and Policy RR #1, Box 84 Center of the Midwest Braceville, IL 60407 203 North LaSalle Street Suite 1390 Chicago, Illinois 60601 U.S. Nuclear Regulatory Commission Braidwood Resident Inspectors Office Rural Route #1, Box 79 Braceville, Illinois 60407
4
]
i l
REQUEST FOR ADDITIONAL INFORMATION ;
FIRST 10-YEAR INSERVICE INSPECTION INTERVAL COMONWEALTH EDISON COMPANY BRAIDWOOD STATION. UNITS 1 AND 2 r
DQf8T NOS. STN 50-456. STN 50-457
1.0 BACKGROUND
The Nuclear Regulatory Commission (NRC) is responsible for the review and disposition of licensees' requests relating to inservice inspection (ISI) requirements contained in the Code of Federal Regulations (CFR) at 10 CFR +
50.55a, and Section XI of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Ves:;e1 Code (Code). When submitting such requests, licensees are required to provide both a regulatory basis (by citing the l appropriate section of 10 CFR 50.55a) and a technical discussion suoporting the request. This information is used in evaluating the request. ;
The staff has reviewed the information submitted by the licensee in a' letter ,
dated October 8, 1996, containing Relief Reque t NR-29. By letter dated :
February 25, 1997, the licensee submitted addiinnal information in response to an NRC request of February 11, 1997. On Mar d 11, 1997, a conference call was held between the NRC, the licensee's ISI vendor (Framatome), Electric Power and Research Institute (EPRI), a Performance Demonstration Initiative ;
(PDI) representative, the Idaho National Engineering and Environmental .
)
Laboratory (INEEL), and the licensee. Based on this conversation and the
- licensee response of February 25, 1997, it has been determined that further clarification is required to complete this evaluation.
2.0 ADDITIONAL INFORMATION RE0VIRED l
Th9 staff has concluded that additional information and/or clarification is j required to complete the evaluation of Relief Request NR-29.
t 2.1 It is the NRC staff's understanding that the PDI test specimens used for
- vessel performance demonstration qualifications are designed for i examination from two sides.
Use of existing PDI test specimens for qualification of procedures and
- personnel when performing one direction scans perpendicular and parallel to the weld may not provide adequate assurance of flaw detection. The l staff believes that certain adverse conditions that would challenge an
- . examiner's skills when examinatiot.s are performed from one side only may L not be represented by the
- PDI test specimens. For instance, certain actual field conditions such as off-normal flaw orientations at the weld 1
- root, incomplete fusion, flaw geometries that may mask other flaws, and ;
ENCLOSURE J
r - - - - - -
e-. . , u a - . .
9- .
, rough cladded surfaces that caus oeam redirection may result in flaws going undetected when scanning from one side only.
Provice a discussion that addresses the staff's concerns. Include a basis for concluding that one-sided examinations provide equivalent flaw detection as the Code-required two-sided examinations.
2.2 Verify that all Code requirements, except for those specifically described in the licensee's February 25, 1997, response, will be met.
2.3 Verify that the subject examinations will be performed by implementing the same essential variables as those used for the PDI qualification.
2.4 Is it the intent of the subject reactor pressure vessel examinations to satisfy the current interval Section XI requirements as well as the augmented reactor pressure vessel examinations required by 10 CFR 50.55a(g)(6)(ii)(A)?
1 a