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MONTHYEARML20199G9891998-01-21021 January 1998 Forwards SER Accepting Pressure Temp Limit Curves & Low Temp Overpressure Protection Sys Limits Methodology & Pressure Temp Limits Rept Submitted by Commonwealth Edison Co Project stage: Approval 1998-01-21
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217P6171999-10-21021 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 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations 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 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 1999-09-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 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 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) IR 05000456/19993011999-07-15015 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative ML20195F3231999-06-0909 June 1999 Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20207A5891999-05-20020 May 1999 Forwards Insp Repts 50-456/99-05 & 50-457/99-05 on 990405-23.Two non-cited Violations Identified ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities 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 ML20207B8751999-05-18018 May 1999 Responds to Ltr Dtd 990225,expressing Concerns That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazards at Some Commercial Nuclear Power Plants in Us 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 1999-09-08
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a n: g-WfY p t UNITED STATES ['
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NUCLEAR RECULATORY CEMMISSIEN WASHINGTON, D.C. 30MH001 4,*****
January 21, 1998 Mr. Oliver D dngsley, President Attn.: Regulatory Services Nuclear Generation Group Commonwealth Edison Company Executive Towers West lli ,
1400 Opus Place, Suite 500 l Downers Grove,IL 60515
SUBJECT:
BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, ACCEPTANCE FOR REFERENCING OF PRESSURE TEMPERATURE LIMITS REPORT (TAC NUMBERS M98799, M98800, M98801, AND M98802)
Dear Mr. VJngsley:
REFERENCES:
- 1. Letter from R. R. Assa, NRC, to D. L. Farrar, Commonwealth Edisen Company,' Exemption from Requirements of 10 CFR 50.60 Braidwood Station, Unit 1, July 13,1995,
- 2. Letter from C. l. Grimes, NRC, to R. A. Newton, Westinghouse Electric Corporation, " Acceptance for Referencing of Topical Report WCAP 14040, Revision 1,' Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Ccoldown Limit Curves '" October 16,1995. (Also known as WCAP 14040-NP-AL
- 3. Letter from G. F. Dick, NRC, to I. M. Johnson, Commonwealth Edison Company,
- Exemption from Requirements of 10 CFR 50.60, ' Acceptance Criteria for Fracture Prevention Measures for Lightwater Nu; lear Power Reactors for Nomial Operation'- Byron Station, Units 1 and 2,"
November 29,1996.
- 4. Letter from J. B. Hosmer, Commonwealth Edison Company, to NRC Document Control Desk,
(WCAP-14824, Revision 1 is Attached).
- 5. Letter from J. B. Hosmer, Com; anwealth Edison Company, to NRC Document Control Desk, "Ap,..wuon for Amendment to Appendix A.
Technical Specifications, far Facility operating Licenses Relocation of Pressure and Temperature Limits," May 21,1997. l
- 6. Letter from J. B. Hosmer, Commonwealth Edison Company, to NRC L, y g' U V Document Control Desk, "Supp'ement to the Application for Amendment to Appendix A, Technical Specifications, for Facility Operating Licenses hhII O Relocation of Pressure and Temperature Limits," November 18,1997.
(WCAP 14940 and rata to WCAP-14940 and WCAP-14970 are Attached).
Contact:
Maggalean W. Weston, (301) 415-3151 b0 00 54 llllll l lll llll lllll P PDR .. . , . . .
a .
Mr. Oliver D. Kingsley 2 January 21, 1998
- 7. Letter from J. B. Hosmer, Commonwealth Edison Company, to NRC Document Control Desk, *SupplementalInformation Pertaining to Byron &
Braidwood's Reactor Vesse; integrated Surveillance Prograni,'
December 3,1997. (WCAP-14824, Revision 2, and Erratum to WCAP.
14824, Revision 2 are Attached).
- 8. Letter from G. F. Dick, NRC, to I. M. Johnson, Commonwealth Edison Company,
- Exemption from Requirements of 10 CFR 50.60 - Braidwood Nuclear Station, Unit 2,* December 12,1997,
- 9. Letter from H. G. Stanley, Commonwealth Edison Company, to NRC Document Control Desk, *SupplementalInformation Pertaining to Technical Specification Amendment Regarding Pressure Tempera'ure Curves Byron and Braidwoed Nuclear Power Stations,' January 8,1998.
(Errata to WCAP 14824 Revision 2, WCAP-14940 and WCAP-14970 are Attached).
- 10. Letter from H. G. Stanley, Commonwealth Edison Company, to NRC Document Control Desk, *SupplemertalInformation Pertaining to Technical Specification Amendment Regarding Pressure Temperature Curves Byron and Braidwood Nuclear Power Stations,' January 13, 1998,
- 11. Letter from G. F. Dick, NRC, to O. D. Kingsley, Commonwealth Edison Company. *Exemptior, from Requirements of 10 CFR 50.60 Byron, Units 1 and 2, and Braidwood, Units 1 and 2,* January 16,1998.
l
- 12. Letter from R. A. Capra, NRC, to O. D. Kingsley, Commonwealth Edison l Company, " Integration of Reactor Pressure Vessel Surveillance Program j for Byron and Braidwood, Units 1 and 2," January 16,1998.
1 We have completed our review of the pressure temperature (P/T) limit curves and low temperature overpressure protection (LTOP) system limits methodology and the pressure temperature limits report (PTLR) (as referenced above), submitted by the Commonwealth Edison Company (Comed). We find the methodology to be acceptable for referencing in the administrative controls section of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, technical specifications (TS) to the extent specified and under the limitations delineated in your submittals and the associated NRC safety evaluation, which is enclosed. The safety evaluation defines the basis for acceptance of the submittals. Our acceptance applies only to the matters described in the submittals.
The NRC reviewed Comed's method for integrating the data from the reactor pressure vessel surveillance capsules as a part of the methodology for developing the P/T limit curves. While the staff finds the method acceptable, as stated in the safety evaluation, the NRC notes that Comed should (1) re-evaluate the appropriate method for determining the best estimate chemical composition as additional chemical composition data become available, (2) assess the impoet of the assumption that the vessel weld has the same RTm value as determined from the surveillance weld in future revisions to the PTLR and/or when additional surveillance data
e 1
Mr. Oliver D. Kingsley 3 January 21, 1998 become available, and (3) address the methort for assessing the credibilliy of the surveillance capsule data, including the method for accounting for irradiation environment .id chemical composition differences, la future revisions to the PTLR.
The methodology for review relating to the P/T limit curves and the LTOP system limits was provided in the references listed above. Reference 2 included WCAP-14040-NP A which provided parts of the inethodology used for determining the amptance of the Byron and Braidwood methodology.
The methodology in WCAP 14040 NP A, along with supplements provided by Comed will bo
~
used to calculate future changes to the P/T limit curves and LTOP system limits. Comed may generate new P/T limit curves and LTOP system limits in accordance with this methodology without prior approval of the staff. However, changes to the methodology must first be reviewed and approved by the staff. Syst(..n limits may be subject to audit by the staff through inspections as necessary.
We do not intend to repeat our review of the matters described in the submittals if the submittals appear as references in other license applientions relating to your plants, except to ensure that the material in the submittals is still applicable to your plants as indicated in the conclusion section of the safety valuation.
Should our criteria or regulations change so that our conclusions as to the acceptability oi .no methodology is invalidated, licensees referencing these documents will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the documents without revision of their respective documentation.
Sincerely, YUG.fW Robert. A. Capra, Director Project Directorate ill 2 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation Docket No. STN 50-454, STN 50-455 STN 50-456 r.nd STN 50-457
Enclosure:
Safety Evaluation l cc w/ encl: See next page
Mr. Oliv:r D. Kingsley 3 January 21, 1998 become available, and (3) address the method for assessing the credibility of the surveillance c ,psuie data, including the inethod for accounting for irradiation environment and chemical composition differences, in future revisions to the PTLR. 1 The methodology for review relating to the P/T limit curves and the LTOP system limits was provided in the references listed above. Reference 2 included WCAP 14040-NP A which provided parts of the methodology used for determining the acceptance of the Byron and i Braldwood methodology. l
! The methodology in WCAP-14040-NP A, alcag with supplements provided by Comed will be used to calculate future changes to the P/T limit curves and LTOP system limits. Comed may
, generate new P/T limit curves and LTOP system limits in accordance with this methodology l
without prior approva! of the staff. However, changes to the methodology must first be reviewed and approved Sy the staff. System limits may be subject to audit by the staff through inspections as necese ",.
We do not intend to repeat our review of the matters described in the submittals if the submittals appear as references in other license applications relating to your plants, except to enscrc that the materialin the submittals is still applicable to your plants as indicated in the conclusion section of the safety evaluation.
Should our criteria or regulations change so that our conclusions as to the acceptability of the r.iethodology is invalidated, licensees referencing these documents will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the documents without revision of their respective documentation.
Sincerely, Origin 31 S);ned By Robert. A. Capra, Director Project Directorate 1112 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket No. STN 50-454, STN 50-455 STN 50-456 and STN 50 457
Enclosure:
Safety Evaluation cc w/ encl: See next page Distribution-N ocket D File BSheron JStrosnider RZimmerman Byron R/F GHolahan KWichman EAdensam Braidwood R/F EWeiss TCollins RCapra PUBLIC ESullivan MShuaibi GDick OGC BElliot WDBeckner SBailey ACRS LLois MWWeston RAssa ABeach, R-lil KKarwoski TSB R/F THarris DOCUMENT NAME: G:\MWW\B_BRPTLR.LTR To receive a copy of this document, Indicate in the boa: *C" a copy w/o attachmenvenclosure *E'
- Copy w'sttachmenvenclosure *N" a No copy _
OFFICE - TSB.ADP- 4; - j j ,m PM PDill-2 lf PM.PDill 2/ o l5 N,AME MWWestort(//g/)7/ SBailey <ed GDick M' DATE / d()/99 l /Al /98 / 2 / /98' OFFICE C/S $8 QSW D C/EMCB DE - p C C/TSB.ADP af) PD PDill-2 l l NAMEAm TCc)thAF ESuthvan 6W WDBeckner' RCapra mob DATE F \ /M /98 l /M /98 OI~ J/ t\ /98 1 /2.1 /98
\ OFFICIAL RECORD NPY 7
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O. Kingsley Byronsreldwood Stesons .
Commonwealth Edison Company January 21, 1998 ,
cc:
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Mr. Wluiam P. Poirier, Director Anomey General !
Wesenshouse Electric Corporaton 500 8. Second Street i Energy Systems Businees Unit Springleid,lHinois 62701 Post Ofnce Box 355, Bay 236 W.
Plamburgh, Pennsylvania 15230 tilinois (Jepartment of Nuclear safety Office of Nuclear Facility Safety Joeoph Gallo 1035 Outer Park Drive Gallo & Ross Springleid,lilinois 62704 1250 Eye St., N.W., Sune 302 .
Washington, DC 20005 Commonwealth Edison Company Byron Stat >n Managt.
MichaelI. Miller, Esquire 4450 N. German Church Road Sidley and Ausen Byron, Illinois 61010-9794 One First Natonal Plaza
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Site Vice Proeident- Byron '
Howard A. Leamer 4450 N. German Churcre Road
- Environmentallaw and Policy Byron, Illinois 61010-9794 !
Center of the L16dwest 203 N. LaSalle St. Suite 1390 U.S. Nuclear Reguietory Commission Chicago, Illinois 60601 Braidwood Resident inspectors Ofnce .
. RR t, Box 79 U.S. Nuclear Regulatory Commiselon Braceville, Illinois 60407 1
Byron Residentinspectors Ofnce 4 4448 N. German Church Road Mr. Ron Stephens Byron, Illinois 61010-g750 lilinois Emergency Services and D:saster Agency
. Regional Administrator, Region 111 110 E. Adams Street U.S. Nuclear Regulatory Commission Springneld, Illinois 62706 -
801 Warrenville Road Lisle, Illinois 60532 4351 Chairman -
. Will County Board of Supervisors 4 Ms. Lonaine Creek Will County Board Courthouse
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. Chairman, Ogle County Board Braidwood Station Manager Poet Oftco Box 357 ' RR t, Box 84 ,
Oregon, Illinois 61061 Braceville, Illinois 60407 '
Mrs. Phillip B. Johnson Ms. BrHget Little Rorem 1907 Stratford Lane Appleseed Coordinator
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- George L. Edgar i Morgan, Lewis and Bochius Document Control Dssk-Licensing l
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- 0. Kingsley Commonweahh Edison Company Byron /Brandwood Stations .
January 21, 1998 Commonwealth E.dison Comp &
Site Wee Preeldent- Braidwood RR 1 Box 84 BracevWie,ll 60407 Mr. Michael J. Wallace Nuclear Services Senior Vice President Commonwealth Edison Company Executive Towers West lil 1400 Opus Place, Suite 900 Downers Grove.IL 60515 Mr. Gene H. Stanley PWR's Vice President Commonwealth Edison Company Executive Towers Westlit 1400 Opus Place, Suite 900 Downers Grove,ll 60515 Mr. Steve Perry BWR's Mce President Commonwealth Edison Company Executive Towers West til 1400 Opus Place, Suite 900 Downers Grove,IL 60515 Mr. Dennis Farrar Regulatory Services Manager Commonwealth Edison Company E s'tive Towers West til NS Opus Place, Suite 500 Downers Grove,IL 60515 Ms. Irene Johnson, Licensing Director Nuclear Regulatory Services Corr.monwealth Edisnn Company Executive Towers West lil 1400 Opus Place. Suite 500 Downers Grove,IL 60515 Commonwealth Edison Company Reg. Assurance Supervisor - Braidwood RR 1 Box 79 Braceville,lilinois 60407 Commonwealth Edison Company Reg. Assmnce Supervisor- Byron 4450 N. German Church Road Byron, Illinois 61010-9794
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