Letter Sequence Approval |
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MONTHYEARML20101L6601996-04-0303 April 1996 Requests Addl Info Re Second 10-yr ISI Program & Associated Relief Requests 12R-11 & 12R-12 Be Completed by 960701.Addl 12R-12) Be Completed by 960701 Project stage: Request ML20129A3341996-10-16016 October 1996 Requests Addl Info & Amount of Time Required to Formally Respond in Response to Re Remaining Relief Requests Project stage: Approval ML20132A7301996-12-13013 December 1996 Submits Request for Additional Info Re Remaining Relief Requests Issued on 960613 & 1016 Project stage: Approval ML20134D0591997-01-30030 January 1997 Forwards RAI Re Second 10 Yr ISI Program Project stage: RAI ML20199C0811998-01-13013 January 1998 Forwards Safety Evaluation Re Second 10-yr Interval Inservice Insp Program Plan Project stage: Approval 1996-04-03
[Table View] |
Similar Documents at Byron |
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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 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl 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 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 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 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 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 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 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 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.. 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 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) 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 ML20209G1391999-07-0909 July 1999 Forwards Results of SG Tube Insps Performed During Byron Station,Unit 1,Cycle 9 Refueling Outage within 12 Months Following Completion of Insps 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 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 ML20196G2161999-06-25025 June 1999 Forwards for NRC Region III Emergency Preparedness Inspector,Two Copies of Comed Emergency Preparedness Exercise Manual for 1999 Byron Station Annual Exercise. Exercise Is Scheduled for 990825.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20209D4861999-06-17017 June 1999 Informs That R Heinen,License OP-30953-1 & a Snow,License SOP-30212-3,no Longer Require License at Byron Station 05000454/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed1999-06-0808 June 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed 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 ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs 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 ML20211M1611999-05-28028 May 1999 Discusses 990527 Meeting with Comed Re Safety Culture & Overtime Control at Byron Nuclear Plant from Videoconference Location at NRC Headquarters.Requests That Aggressive Actions Be Taken to Ensure That Comed Meets Expectations ML20207D5261999-05-26026 May 1999 Forwards Response to NRC 990318 RAI Concerning Alleged Chilling Effect at Byron Station.Attachment Contains Responses to NRC 12 Questions 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 ML20211M1781999-05-25025 May 1999 Summarizes Concerns with Chilling Effect & Overtime Abuses at Commonwealth Edison,Byron Station.Request That Ltr Be Made Part of Permanent Record of 990527 Meeting ML20195C7911999-05-25025 May 1999 Forwards Revised COLR for Byron Unit 2,IAW 10CFR50.59.Rev Accounts for Planned Increase of Reactor Coolant Full Power Average Operating Temp from 581 F to 583 F 05000454/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed1999-05-21021 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed 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 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 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 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 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 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 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 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) 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 ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick 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 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 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 ML20206J1981999-05-0505 May 1999 Forwards Exam Answer Key for Forms a & B,Grading Results for Facility & Copies of Individual Answer Sheets for Each Individual Taking Gfes of Written Operator Licensing Exam Administered by NRC on 990407.Without Encls 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 ML20206D0361999-04-28028 April 1999 Confirms Plans to Have Meeting on 990527 in Lisle,Illinois to Discuss Results of Ceco Evaluation on Potential Chilling Effect Concern within Working Environ & Use of Overtime within Operations Dept Organization at Byron Station ML20205Q2621999-04-14014 April 1999 Forwards Insp Repts 50-454/99-03 & 50-455/99-03 on 990217-0329.Five Violations Identified & Treated as Ncvs. Expresses Continued Concern with Configuration Control & Human Performance Errors at Byron Station ML20206U3261999-03-29029 March 1999 Forwards RAI Re 981208 Response & Suppls to NRC Re Use of Overtime in Byron Station Operations Dept.Response Requested within 30 Days of Date of Ltr ML20196K8821999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990201 to Develop Integrated Understanding of Safety Performance. Overall Performance Acceptable.Plant Issues Matrix & Insp Plan Encl ML20205B4901999-03-26026 March 1999 Forwards SER Authorizing Util 981022 Relief Requests 12R-24, Rev 0,which Requests Deferral of Rv shell-to-flange Vessel Weld Exam to End of Second 10-year Insp Interval,Pursuant to 10CFR50.55a(a)(3)(ii) & 12R-34,rev 0 ML20204G3641999-03-19019 March 1999 Forwards Safety Evaluation & Technical Ltr Rept Re Second 10-yr Interval ISI Request for Relief 12R-11,rev 2.Licensee Proposed Alternative to code-required Pressure Test Authorized for Current Interval ML20204E2631999-03-18018 March 1999 Discusses Review of Ceco Evaluation of Chilling Effect on Byron Station Personnel.Identified Number of Questions Re Ceco Findings & C/As.Requests Further Evaluation of Chilling Effect at Byron Be Conducted & Response to Encl Questions ML20204D1971999-03-16016 March 1999 Discusses Review of Revision 4Q to Portions of Licensee Emergency Plan Site Annex ML20204B6721999-03-12012 March 1999 Forwards Copy of Preliminary Accident Sequence Precursor Analysis of Operational Condition Discovered at Plant on 980912 ML20207K1861999-03-11011 March 1999 Discusses Review of Rev 4P to Portions of Byron Power Station EP Site Annex.Based on Determinations That Changes Do Not Decrease Effectiveness of EP & Plan Continues to Meet Standards of 10CFR50.47(b),NRC Approval Not Required ML20207J5201999-03-10010 March 1999 Forwards Insp Repts 50-454/99-02 & 50-455/99-02 on 990105-0216.No Violations Noted.Expresses Concern Re Trend of Configuration Control & Human Performance Errors at Byron Station ML20203G7981999-02-11011 February 1999 Forwards Insp Repts 50-454/99-01 & 50-455/99-01 on 990119-22.No Violations Noted.Insp Involved Exam of Maint & Engineering Related Activities for Electrical Circuit Breakers ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203C9861999-02-0808 February 1999 Ack Receipt of ,Which Transmitted Changes Identified as Rev 52 to Security Plan.No NRC Approval Required ML20202H9401999-02-0303 February 1999 Informs That Update of Set Number 58 of UFSAR Has Been Completed.Confirmation Sheet Providing Update Encl ML20199H8561999-01-19019 January 1999 Discusses Insp Repts 50-454/98-25 & 50-455/98-25 on 981124-990104 & Forwards Nov.Violation Identified Involving Unacceptable Preconditioning of Stroke Time Testing of AFW Pump Discharge Valves ML20199E8861999-01-15015 January 1999 Discusses Two Unresolved Security Items Identified in Sections S3.b1 & S3.b2 of Insp Repts 50-454/98-03 & 50-455/98-03,dtd 980211.One Item Re Adequacy of Alarm Sys Testing When Two Alarm Zones Were Returned to Svc ML20198N8261998-12-30030 December 1998 Forwards Insp Repts 50-454/98-24 & 50-455/98-24 on 981130- 1204.No Violations Noted.Purpose of Insp Was to Determine If Licensed Operator Requalification Training Activities Conducted IAW with NRC Requirements ML20198J0211998-12-18018 December 1998 Forwards Insp Repts 50-454/98-20 & 50-455/98-20 on 981006- 1123.No Violations Noted ML20198F4451998-12-17017 December 1998 Forwards Insp Repts 50-454/98-23 & 50-455/98-23 on 981116-14.No Violations Noted.Purpose of Insp Was to Verify Accuracy of Licensee Response to Region III Questions Re Grid Stability ML20206N4431998-12-10010 December 1998 Forwards Security Insp Repts 50-454/98-22 & 50-455/98-22 on 981116-20.No Violations noted.Challenge-testing of Some Detection Equipment Showed Some Vulnerabilities That Util Indicated Would Be Corrected 1999-09-08
[Table view] |
Text
__._ __..__..__._ _ _ _- - _ . _ _ _ _ _ _ _ _
i e . .QL /GY,/lKS" i
, y% \
i y UNITED OTATES t
- NUCLEAR REGULATORY COMMISSION f 5 wmmeton, o.c. menwen !
'e*** January 13, 1998
- Mr. Oliver D. Kingsley, President !
Nuclear Generation Group l j Commonwealth Edison Company [
- ' Executive Towers West lli (
1400 Opus Place, Suite 500 !
Downers Grove,IL 60515 3
SUBJECT:
SECOND 10 YEAR IN8ERVICE INSPECTION PROGRAM RELIEF REQUESTS - L BYRON STATION, UNITS 1 AND 2 (TAC NOS. M94830 AND M94831) l
Dear Mr. Kingsley:
l 4 i By letter dated February 23,1996, Commonwealth Edison Company (Comed) submitted its j
. second 10 year inservice inspection (181) program for Byron Station, Un is 1 and 2. Additional -;
information was provided in Comed's letters of April 10,1996, August 05,1996, December 16, i
- 1996, and April 10,1997.
i' By letter of June 12,1996, Comed withdrew Relief Request 12R 11, and 12R 11 (Revision 1) was submitted on August 12,1996. On July 22,1996, we authorized Relief Request 12R 12 pursuant ;
to 10 CFR 50.55a(s)(3)(i). The enclosed Safety Evaluation (SE) documents our review of l i
additional relief requests from the February 23,1996, submittal.
With the exception of Relief Request 12R 13, "lWF 5300, inservice Examination and Test l Requirements for Snubbers," we reviewed and evaluated (with the assistance of our contractor, j the Idaho National Engineering Laboratory (INEL)), the information provided h support of the !
remaining relief requests. We adopt INEL's conclusions and recommendations presented in their Technical Letter Report which is attached to the SE. ;
Relief Rsquests 12R 05 (Revision 2),12R-06,12R 07,12R-06,12R 10,12R 13 (Revision 1), and ,
12R 18 are authorized pursuant to 10 CFR 50.55a(a)(3)(i) because the proposed altematives !
would provide an acceptable level of quality and safety. !
Relief Request 12R 09, " Examination Categories C-F 1 and C F 2, items C5.41 and C5.61, !
Circumferential tranch Connection Wolds," is authorized pursuant to 10 CFR 50.55a(g)(6)(i) ;
, because of the impracticality of the Code requirements for the subject welds and the assurances !
I provided by the altemative surface examination and Code-required pressure tests, l
- Relief Request 12R 11 (Revision 1), " Paragraph (WA 5242(a), VT Visual Examination of Insulated
- Components," is authorized for Class 1 systems because the proposed altemative provides a thorough approach to ensuring the leak tight integrity of systems borated for the purose of >
I controlling reactivityi For Class 1 systems, comed's approach will provide an soceptable level of quality and safety, and is authortrod pursuant to 10 CFR 50.55a(a)(3)(i). However, for Class 2 ,
and 3 systems, the frequencies proposed for insulation removal have not been found acceptable >
l by the NRC, and the attemative proposed 'n 12R 11 (Revision 1) is not authorized for those i systems. '
Relief Request 1215, "Use of Code Case N-4161, Altomate Testing for Class 1, Class 2,'and -
Class 3 Welded Repaired / Replaced Components, Relief Request 12R 16 "Use of Code Case ]j !
l
_0 4 l g s.
m
O. Kingsley 2- '
i N-4961, Ahomative Rules for 10 Year System Hydraulic Testing for Class 1,2, and 3 Systems,"
and Relief Request 12R 17 (Revision 2),"Use of Code Case N 50g, Ahomate Rules for the selection and Examination of Class 1,2, and 3 Integrally Wolded Attact ments, Section Xl, Division 1,* are authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the current interval or until such time as published in a future revision of RG 1.147. At that time, if Comed intends to continue to implement these Code Cases, it must follow all provisions, if any, in the Code Cases, with limnations issued in RG 1.147.
The results of our review of the remaining relief requests will be issued at a later date by a separate letter.
Sincerely, frWW*fW Rober1 A. Capra, Director ,
Project Directorale 1112 Division of Reactor Projects - lil/IV office of Nuclear Reactor Regulation Docket Nos. 8TN 50-454, STN 50-455
Enclosure:
SE w/ attached TLR cc w/ encl: See next page
- , . - . , , . . - ~ . - , _ . ~ . ,, , . . , . , - . - , , ,
e ..
r .
.O. Einssicy ,
a N-4861 Allemative Rules for 10-Year system Hydraulic Testing for Class 1,2, and 3 Systems," ;
and Relief Roguest 12R.17 (Revision 2), "Use of Code Case N 509, Allemale Rules for the -!
i selection and Examination of Class 1,2, and 3 Inte0 rally Wolded Attachments, section XI, :
f Division 1," are authortred pursuant to 10 CFR 50.55a(a)(3)(l) for the current interval or until such time as putdished in a future revision of RG 1.147. At that time, if Comed intends to continue to !
implement these Code Cases, it must follow all provisions, if any, in the Code Cases, with !
limitations issued in RG 1.147. l t
The results of our review of the remaining relief requests will be issued at a later date by a i separate lettw, i J
sincerely, !
Origins 1 Signed by: >
Robert A. Capra, Director [
Proja:t Directorate lil 2 1 Division of Reactor Projects lil/IV --
office of Nuclear Reactor Regulation !
l Docket Nos. 8TN 50 454, STN 50-455, !
3
Enclosure:
SE w/ attached TLR cc w/ encl: See next pa9e DISTRIBUTION: !
Asestj PUBLIC . PD3-2 r/f E. Adensam, EGA1 l R. Capra i C. Moore G, Dick . ACRS. T2E26 OGC,015818 , M. Jordan, Rill T. McLellan F. Grubelich !
t
+ , t v
DOCUMENT NAME: G:\CMNTJR\ BYRON \BY94830.lSi !
e T3 steelve e oesy of see desessened ineeste in gmhost *C" = Ce py weheul enclosuree 't's Copy weh enclosuree "ti" = No ce av OFFICE - PM:PD3 ~ / f IE LA:tDS2 O OGC D:PD3-2 &
NAME GDICK ' hM %l455 % R. 'husu o RCAPRA w 'i DATE 01/u 198 /" Oi/LS /915 44T/99 : 01/ t3 /98 ;
OFFICIAL RECORD COPY ;
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! lechsel1. heller Esquire Atomey General Sidney and Ausen 500 8. Second Street l
One First Nellonel Plere Spttngeoid,lillnois 82701 Chloe00, Illinois 80003 ,
Commonwoollh Edloon Compeay '
Regional Adminielretor, Repion IN Spon tiellon Manager U.s. Nuclear Requistory Comminolon 4450 North German Church Road 001 Werrorwille Reed Dron, Illinois 81010-8794 i Unio, Illinois 00532 4351 #
Commonwoollh Edloon Company :
lillnois Department of Nuclear safety Site Vloo Proeident. Spon Ottoo of Nuoleer Poolley safety 4461 N. German Church Reed .!
1035 Outer Park Drtve tron, Illinois $1010-8794 i Mr. Michael J. Wellece Document Control Dook-Ucensing Nuclear Servlees senior Vlos Proeident Commonwoollh Edloon Company Commonwoollh Edison Company -
1400 Opus Pleos, Sulle 400 Eueoutve Towers West til DownersGrove, Illinois 00515 1400 Opus Pleos, Sulle 900 !
Downers Grove,IL 60515 i Mr.Willlem P Poirior.Direo6er 7l: " #.:m Elecirle Corporaton Mr. Gene H. Stanley :
> Energy Syoiems Businees Unit PWR's Vlos President !
Post 0%ios Bau 355, Boy 236 W. Commonwealth Edison Company Painburgh, Pennsylvania 15230 Exeov0ve Towers West til ,
1400 Opus Place, Sulle 900 t Joseph Gallo Downers Grove,IL 00515 Gallo & Ross 4 1250 Eye St., N.W., sulle 302 Mr. 8teve Perry ;
?!W: ,, DC 20005 BWR's Vlos President .
Commonweehh Edison Company ;
Noward A. Leemer Executve Towers West til +
Erwironmentallow and Polley 1400 Opus Pleos, Sulle 900 Center of the Mldwest Downers Grove,IL 60515 i 203 North Letelle Street Sulle 1390 Mr. Dennis Ferror Chicago, Illinois 40601 Regulatory Services Manoper .
Commonwoolth Edison Company ,
U.S. Nuclear Regulatory Comminaion Execupve Towers West til t Bron Residentinspectors Ofnce 1400 Opus Pleos, Sulle 500 4444 North German Church Road Downers Grove,IL 90515 Spon, Illinois 81010-G750 Ms. lrone Johnson, Llooneing Director Ms.Lonreine Crook Nuclear Regulatory Serv 6ces RR 1 Box 152 Commoinveelth Edloon Company Monteno,Ilknois 80050 Executve Towers West 111 1400 Opus Place, suite 500 l
. Chelrman, Ogle County Board Downers Grove,IL 80515 '
Post oftco Don 357 .
l Oregon, Illinois 61081 Commonwoolth Edison Company Reg. Assurance Supervisor. Byron Mrs.Phillip 8. Johnson 4450 N. Germen Church Road 1907 Stralford Lane Bron, Illinois 61010-9704 !
Rocidord,llenois $1107
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