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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV 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 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 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 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 ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) 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 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 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 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 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 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 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 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations IR 05000456/19993011999-07-15015 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative ML20195F3231999-06-0909 June 1999 Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20207A5891999-05-20020 May 1999 Forwards Insp Repts 50-456/99-05 & 50-457/99-05 on 990405-23.Two non-cited Violations Identified ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities 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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i
- fQntsQ-.nk UNITED STATES :
/,./-
D i'
- NUCLEAR REGULATORY COMMISSION-WAsHINeToN, D.C. 30086 00lH
- Ms. Irene Johnson, Acting Manager Nuclear Regulatory Services - :
Commonwealth Edison Company Executive Towers West lli 9 1400 Opus Place, Suite 500 j Downers Grove, IL 60515 ,
SUBJECT:
COMED NOTIFICATIONS PURSUANTTO 10 CFR 50.72 THAT BOTH BYRON STAh0N, UNIT 1, AND BRAIDWOOD STATION, UNIT 1, ARE OUTSIDE
' THEIR DESIGN BASES (TAC NOS. M97894, M97895, M99535 AND M99536)
Dear Ms. Johnson:
On October 7,1997, the Commonwesith Edison Company (Comed) notified the Nuclear Regulatory Commission (Event No. 33040) pursuant to 10 CFR 50.72(b)(1)(ii)(B) that Byron Station, Unit 1, was outside its design basis for offsite radiation dose exposures. On October 10,1997, a similar notification (Event No. 33062) was made for Braidwood Station, Unit 1.- One of the factors cited in these two notifications contributing to the projected increase.
In the primary-to-secondary leakage over that projected in prior Byron Station, Unit 1, and Braidwood Station, Unit 1, fuel cyc es, is steam generator (SG) tube leakage attributable to circumferential crack indications,
(
l~
p However, in our letter dated March 28,1997, regarding Comed's proposed extension of the '
i ~ Byron Station, Unit 1, maximum operating cycle between SG eddy current inspections (ECl), the l staff contluded that Comed's proposal to extend the present operating cycle (i.e., Cycle 8) from 448.5 days to 540 days above a T,,,, of 500 degrees Fahrenheit, was acceptable. The stars E review in this area 'ncluded information Comed had provided relative to the structural and L leakage integrity o the SG tubes dus to the occurrence of circumferential crack indications at the top of the tube sheet in the roll transition zone. This issue arose due to the relatively large '
number of circum 'erential crack indications (e.g., about 6000) found in the Byron Station, Unit 1, SG during the provious ope sting cycle (i.e., Cycle 7).
The staff's conc:asion cited above was based on our review of the quclitative considerations associated with Comed's' prior SG tube inspections as well as Comed's quantitative cycle
. length assessmeat. However, since the staff found that there was insufficient data to support a correlation between voltages found during an ECl and SG tube leakage attributable to >
circumferential crack indications, it was unable to accept Comed's quantitative assessment.
Accordingly, the stats acceptance of Comed's proposal for an extended Byron Station, Unit 1, operating cycle war based solely on our finding that the additional qualitative measures cited in Comed's letter dated January 7,1997, would provide reasonable assurance that large _
throughwall, free span circumferentie! cracks would not develop during the present Byron Station, Unit 1, operating cycle.1These measures included: (1) more sensitive eddy current E probes; (2) data analysis software with features to facilitate the detection of circumferential 7
- indications in the roll transition zone; (3) the' pulling and destructive metallurgical examination of ,
ten SG tubes in the October 1995 outage at Byron Statior; Unit 1; (4) the in-situ pressure tests .
MJ J fIg 9711200267 971113 f_ ucpu2 RRllBl(Ml 20 R.E CERE 08py PDR: ADOCK 05000454 (p . PDR _ __ _ , , _ _. .- _ _ _ _ - __ _
. . q V c. Ms. Irene Johnson 2 in the April 1996 outage at Byron Station, Unit 1, of a, sample of SG tubes containing the most significant circumferential indications; and (5) additional defense-in-depth measures cited in our letter dated March 28,1997. .The staffs finding was that as a result of Comed's aggressive approach to this issue, circumferential flaws that could become potentially significant defects at
- the end of Cycle 8 for Byron Station, Unit 1, were likely to have been detected and removed
. from service.- Further, any small circumferential crack indications below the threshold of detection and, therefore, neither repaired nor removed from service, would not grow to the extent of extending throughwall based on Comed's look back review of past ECis at Byron, Unit 1. Accordingly, it was the staffs position that all of the qualitative measures cited above, when taken as a whole, had the not effect of reducing to a very low value, the probability of throughwall, free span SG tube leakage from circumferential indications in the Byron Station, - 4 Unit 1, SG. It was our understanding when we issued our letter of March 28,1997, that this was also Comed's position. The staff concluded that these qualitative measures were also applicable to this issue in the Braidwood Station, Unit 1, SG.
The staff is concemed that the two 10 CFR 50.72 notifications cited above appear to contradict our prior findings that the qualitative measures Comed implemented at Byron Station, Unit 1, and Braidwood Station, Unit 1, reduced to a very low value, the probability of throughwall, freespan lockage from circumferential cracks. Accordingly, state whether Comed has changed its position on this issue. Furthermore, indicate whether Comed has obtained additional
~ information or performed any other analyses that could affect our evaluation or understanding of -
the bases for Comed's prior proposals to operate both Byron Station, Unit 1, and Braidwood Station, Unit 1, without any midcycle eddy current inspections for circumferential crack indications. In this regard, state whether Comed has conducted a re review of Comed's ECl data from prior inspections which might affect Comed's prior position that the circumferential crack indications found in the Byron Station, Unit 5, SG had taken several operating cycles to
( develop, if there are any questions on these issues. please contact me at (301) 415-3023.
The staff believes that the apparent reversal of Comed's prior position in the two 10 CFR 50.72 1- notifications cited above regarding the low probability of throughwall, freespan SG tube leakage attributable to :ircumfersntial crack indications, may have arisen from a lapse in the quality control of these notifications. Assuming this to be the case, we encourage Comed to avoid such problems in the future by ensuring close coordination between the personnel at the Byron and Braidwood Stations and the corporate staff at Downers Grove.
l l- Sincerely nn A w- t -
M; David Lynch, Senior Project Manager Project Directorate lll-2 Division of Reactor Projects - I!!/lV Office of Nuclear Reactor Regulation Docket Nos. STN 50-454 and STN 50-456 cc: See next page
=a- ; *
in the April 1996 outage at Byron Station, Unit 1, of a sample of SG tubes containing the most significant circumferential indications; and (5) additional defense-in-depth measures cited in our letter dated March 26,1997. The staff's finding was that as a result of Comed's aggressive approach to this issue, circumferential flaws that could become potentially significant defects at the end of Cycle 8 for Byron Station, Unit 1, were likely to have been detected and removed from service. Further, any small circumferential crack indications below the threshold of detection and, therefore, neither repaired nor removed from service, would not grow to the extent of extending throughwall based on Comed's look back review of past ECis at Byron, Unit 1. Accordingly, it was the staff's position that all of the qualitative measures cited above, when taken as a whole, had the not effect of reducing to a very low value, the probability of throughwall, free span SG tube leakage from circumferential indications in the Byron Station, Unit 1, SG, it was our understanding when we issued our letter of March 28,1997, that this was also Comed's position. The staff concluded that these qualitative measures were also applicable to this issue in the Braidwood Station, Unit 1, SG.
The staff is concemed that the two 10 CFR 50.72 notifications cited above appear to contradict our prior findings that the qualitative measures Comed implemented at Byron Station, Unit 1, and Braidwood Station, Unit 1, reduced to a very low value, the probability of throughwall, freespan leakage from circumferential cracks. Accordingly, state whether Comed has changed its position on this issue. Furthermore, indicate whether Comed has obtained additional information or performed any other analyses that could affect our evaluation or understanding of the bases for Comed's prior proposals to operate both Byron Station, Unit 1, and Braidwood Station, Unit 1, without any midcycle eddy current inspections for circumferential crack l
indications. In this regard, state whether Comed has conducted a re-review of ComEdis ECl l
data from prior inspections which might affect Comed's prior position that the circumferential crack indications found in the Byron Station, Unit 1, SG had taken several operating cycles to develop. If there are any questions on these issues, please contact me at (301) 415-3023.
The staff believes that the apparent reversal of Comed's prior position in the two 10 CFR 50.72 notifications cited above regarding the low probability of throughwall, freespan SG tube leakage attributable to circumferential crack indications, may have arisen from a lapse in the quality l
control of these notifications. Assuming this ' be the case, we encourage Comed to avoid l such problems in the future by ensuring clos coordination between the personnel at the Byron and Braidwood Stations and the corporate staff at Downers Grove.
Sincerely, OilpnalSIGCMi:
M. David Lynch, Senior Project Manager Project Directorate ill-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation R. Assa Docket Nos. STN 50-454 and STN 50-456 }STRIBUTION: Docket R. Capra RJBLIC PDill-2 r/f C. Moore
, cc: See next page E. Adensam, EGA1 D. Lynch C. Miller M. Jordan, Rill OGC,015B18 ACRS, T2E26 G. Dick S. Bailey M. Holmberg, Rill S. Coffin C. Beardslee E. Sullivan J. Strosnider G. Lainas B. Sheron C. Hinson R. Emch J. Gavula, Rlli l DOCUMENT NAME: G:\ BRAID-BY\BBNOTIF.EOC *See previous concurrence io w= . m or w. * ,= io,*A uene c conv maa -- m c=v e -%. -w wo ennv G
OFFICE PJWO , LA:lfDI2 b EMCB* D:PD32 NAME 9tTP@N } BMODf(E ESULLIVAN RCAPPA W DATE 11//gl9FUT 11 6 /97 11/10/97 11/ft/97 OFFICIAL RECORD COPY
I Ms. Irene Johnson =2-in the April 1996 outage at Byron Station, Unit 1, of a sample of SG tubes containing the most significant circumferential indications; and (5) additional defense-in-depth measures cited in our letter dated March 28,1997. The staff's finding was that as a result of Comed's aggressive approach to this issue, circumferential flaws that could become potentially significant defects at the end of Cycle 8 for Byron Station, Unit 1, were likely to have been detected and removed from service. Further, any small circumferential crack indications below the threshold of detection and, therefore, neither repaired nor removed from service, would not grow to the extent of extending throughwall based on Comed's look back review of past ECis at Byron, Unit 1. Accordingty, it was the staff's position that all of the qualitative measures cited above, when taken as a whole, had the net effect of reducing to a very low value, the probability of throughwall, free span SG tube leakage from circumferential indications in the Byron Station, Unit 1, SG. It was our understanding when we issued our letter of March 28,1997, that this was also Comed's position. The staff concluded that these qualitative measures were also applicable to this issue in the Braidwood Station, Unit 4, SG.
The staff is concemed that the two 10 CFR 50.72 notifications cited above appear to contradict ou: prior findings that the qualitative measures Comed implemented at Byron Station, Unit 1, and Braidwood Station, Unit 1, reduced to a very low value, the probability of throughwall, freespan leakage from circumferential cracks. Accordingly, state whether Comed has changed its position on this issue. Furthermore, indicate whether Comed has obtained additional information or performed any other analyses that could affect our evaluation or understanding of the bases for Comed's prior proposals to operate both Byron Station, Unit 1, and Braidwood Station, Unit 1, without any midcycle eddy current inspections for circumferential crack indications. In this regard, state whether Comed has conducted a re-review of Comed's ECl data from prior inspections which might affect Comed's prior position that the circumferential crack indications found in the Byron Station, Unit 1, SG had taken several operating cycles to develop. If there are any questions on these issues, please contact me at (301) 415-3023.
The staff believes that the apparent reversal of Comed's prior position in the two 10 CFR 50.72 notifications cited abovt, regarding the low probability of throughwall, freespan SG tube leakage attributable to circumferential crack indications, may have arisen from a lapse in the quality control of these notifications. Assuming this to be the case, we encourage Comed to avoid such problems in the future by ensuring close coordination between the personnel at the Byron and Braidwood Stations and the corporate staff at Downers Grove.
Sincerely, Oil;!nalSignSy:
M. David Lynch, Senior Project Manager Project Directorate 111-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation R. Assa Docket Nos. STN 50-454 and STN 50-456 JSTRIBUTION: Docket R. Capra
%)BLIC PDill-2 r/f C. Moore cc: See next page E. Adensam, EGA1 D. Lynch C. Miller M. Jordan, Rlli OGC,015B18 ACRS, T2E26 G. Dick S. Bailey M. Holmberg, Rlli S. Coffin C. Beardslee E. Sullivan J. Strosnider G. Lainas B. Sheron C. Hinson R. Emch J. Gavula, Rill DOCUMENT NAME: G:\ BRAID BYTBBNOTIF.EOC *See previous concurrence Altsglye a cony ofihlidQCumenklDdiC4Lbidhe bor "C" = Coev Mhout em!c:iures
- E* = Cocy w'th emknures "N" =.lh.CC2Y..
OFFICE J P HNd I LA:RD32 [_ EMCB* D:PD32 l G NAME 9tTMQN ) CMOORE ESULLIVAN RCAPRA W DATE 11/dl9M/T 11/A #97 11/ 10 /97 11/ft/97 OFFICIAL RECORD COPY
. ,1. L , y .
Byron /Braidwood Power Stations
-* = 1. Johnson- -
Commonwealth Edison Company - _
oc: .i
' Mr. William P. Poirier,- Director George L Edgar !
Westinghouse Electric Corporation Morgan, Lewis and Bochius Energy Systems Business Unit ' 1800 M Street, N.W. =i Post Offlos Box 355, Bay 236 West- Washington, DC 20036 .
Pittsburgh, Pennsylvania 15230 Attomey General-Joseph Gallo 500 South Second Street =
Gallo & Ross _-
Spnngfield, Illinois 62701 1250 Eye St., N.W.
- Suite 302 - EIS ReviewCoordinator Washington, DC 20005 U.S. Environmental Protection Agency 77 W. Jackson Blvd.
Michael 1. Miller, Esquire Chicago, Illinois- 60604 3590 Sidley and Austin
__ One First National Plaza lilinois Department of Chicago, Illinois 60603 Nuclear Safety-Office of Nuclear Facility Safety Howard A. Leamer 1035 Ou'or Park Drive Environmentallaw and Policy Springfield, Illinois 62704 Center of the Midwest 203 North LaSalle Street Commonwealth Edison Company Suite 1390 Byron Station Manager Chicago,Illiaois 60601 4450 North German Church Road Byron, Illinois 61010 U.S. Nuclear Regulatory Commission
. Byron Resident inspectors Office Kenneth Graesser, Site Vice President 4448 North German Church Road Byron Station Byron, Illinois 61010-9750 Commonwealth Edison Station 4450 N. German Church Road Regional Administrator, Region 111 Byron,liiinois 61010 i- U.S. Nuclear Regulatory Commission
. 801 Warrenville Road U.S. Nuclear Regulatory Commission Lisle, Illinois 60532-4351 Braidwood Resident inspectors Office
- Rural Route #1, Box 79 -
Ms. Lorraine Creek Braceville, Illinois 60407 Rt.1, Box 182
- Mantono, Illinois 60950 Mr. Ron Stephens filinois Emergency Services Chairman, Ogle County Board and Disaster Agency Post Office Box 357? 110 East Adams Street Oregon, Illinois 61061 Springfield, Illinois 62706
- Mrs. Phillip B. Johnson Chairman 1907 Stratford Lane Will County Board of Supervisors Rockford, Illinois 61107 Will County Board Courthouse Joliet, Illinois 60434
' - Commonwealth Edison Company Braidwood Station Manager Rt.1, Box 64 Bracevjile, Illinois 60407 Ms. Bridget Uttle Rorem -
Appleseed Coordinator 117 teorth unden Street Essex,lilinois 60g35 Document Control Desk-Ucensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 Mr. T. J. Tulon Site Vice President Braidwood Station Commonwealth Edison Company RR 1, Box 84 Braceville,IL 60407