Responds to Generic Ltr 90-04 Re Status of GSI Resolved W/ Imposition of Requirements or Corrective Actions.Status of GSI Implementation Encl| ML20044B208 |
| Person / Time |
|---|
| Site: |
Byron  |
|---|
| Issue date: |
07/11/1990 |
|---|
| From: |
Schuster T
COMMONWEALTH EDISON CO. |
|---|
| To: |
Murley T
Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| REF-GTECI-A-13, REF-GTECI-A-16, REF-GTECI-A-35, REF-GTECI-AS, REF-GTECI-B-10, REF-GTECI-B-36, REF-GTECI-B-63, REF-GTECI-CO, REF-GTECI-EL, REF-GTECI-PI, REF-GTECI-SU, REF-GTECI-SY, TASK-A-13, TASK-A-16, TASK-A-35, TASK-B-10, TASK-B-36, TASK-B-63, TASK-OR GL-88-03, GL-88-14, GL-88-17, GL-88-3, GL-89-13, GL-90-04, GL-90-4, NUDOCS 9007180113 |
| Download: ML20044B208 (11) |
|
Similar Documents at Byron |
|---|
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)
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
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
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
ML17191B4761999-09-16016 September 1999
Refers to Meeting Conducted at Region III Office in Lisle,Il on 990713 Re Licensee Nuclear Generation Group Performance as Performance Relates to Actions Comed Taken in Response to NRC 10CFR50.54(f) Ltr, Re Safety Performance
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
ML17191B4031999-07-23023 July 1999
Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE
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)
ML20210D2601999-07-16016 July 1999
Forwards Revised Byron Unit 1 Cycle 10 COLR in ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA
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
ML17191B3951999-07-15015 July 1999
Forwards Environ Assessment & Finding of No Significant Impact Related to Proposed Exemptions for Braidwood,Byron, Dresden,Lasalle & Quad Cities Stations.Proposed Exemptions Would Provide Relief from Requirements of 10CFR50.71(e)(4)
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
ML17191B3941999-07-0909 July 1999
Ack Receipt of Rev 7L to Portions of Emergency Plan in Oct 1998.No NRC Approval Required Based on Determinations That Rev 7L Does Not Decrease Effectiveness of Emergency Plan
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
ML17191B3931999-06-30030 June 1999
Forwards Rev to Confirming Discussion Between Members of Staff to Have Meeting on 990713,in Region III Ofc to Discuss Util Performance Re Actions Util Has Taken in Response to NRC 970127,10CFR50.54 Ltr
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
ML17191B3821999-06-17017 June 1999
Discusses 990521 Meeting in Downers Grove,Il.Purpose of Visit to Meet Risk Mgt Staff Collectively Prior to Visiting Each Plant.Forwards Attendance List & Licensee Presentation
ML17191B3761999-06-11011 June 1999
Confirms Plans to Hold Meeting on 990713 in Region III Ofc to Discuss Ceco Nuclear Generation Group Performance Re Actions Taken in Response to NRC 970127 10CFR50.54(F) Ltr Safety Performance at Nuclear Facilities
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
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
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)
ML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
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
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)
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
ML20210D2601999-07-16016 July 1999
Forwards Revised Byron Unit 1 Cycle 10 COLR in ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA
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
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
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
ML20195D6351999-06-0404 June 1999
Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs
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
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
ML20195B2301999-05-19019 May 1999
Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB
ML20207E9831999-05-18018 May 1999
Forwards Copy of Commonwealth Edison Co EP Exercise Evaluation Objectives for 1999 Byron Station Annual EP Exercise,Which Will Be Conducted on 990825.Without Encl
ML20206N8551999-05-11011 May 1999
Forwards 1998 Annual Radioactive Environ Operating Rept for Byron Station. Rept Includes Summary of Radiological Liquid & Gaseous Effluents & Solid Waste Released from Site
ML20206U3351999-04-30030 April 1999
Forwards Evaluation of Matter Described in Re Byron Station.Concludes That Use of Overtime at Byron Station Was Controlled IAW Administrative Requirements & Mgt Expectations Established to Meet Overtime Requirement of TS
ML20206F5381999-04-30030 April 1999
Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape
ML20206C7901999-04-23023 April 1999
Provides Suppl Info Re Use of W Dynamic Rod Worth Measurement Technique,As Requested During 990413 Telcon.Rev Bars in right-hand Margin Identify Changes from Info Submitted by
ML20206E7521999-04-22022 April 1999
Submits Rept on Number of Tubes Plugged or Repaired During Inservice Insp Activities Conducted at Plant During Cycle 9 Refueling Outage,Per TS 5.6.9
ML20206A7431999-04-22022 April 1999
Forwards Comments Generated Based on Review of NRC Ltr Re Preliminary Accident Sequence Precursor Analysis for Byron Station,Unit 1
ML20206B3941999-04-21021 April 1999
Forwards Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors, for Byron & Braidwood Stations.Updated Info Re PCT for Limiting Small Break & Large Break LOCA Analysis Evaluations & Detailed Description of Errors
ML20206B2471999-04-20020 April 1999
Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412
ML20205S9621999-04-20020 April 1999
Responds to 981203 RAI Telcon Re SG Tube Rupture Analysis for Byron Station,Unit 2 & Braidwood Station,Unit 2.Addl Info & Subsequent Resolution of Issues Discussed During 990211 Telcon Are Documented in Encl
ML20206A8141999-04-20020 April 1999
Advises NRC of Review of Cycle 10 Reload Under Provisions of 10CFR50.59 & to Transmit COLR for Upcoming Cycle
ML20205T3901999-04-13013 April 1999
Forwards Byron Station 1998 Occupational Radiation Exposure Rept, Which Is Tabulation of Station,Utility & Other Personnel Receiving Annual Deep Dose Equivalent of Less than 100 Mrem
ML20196K6661999-03-31031 March 1999
Forwards Byron Nuclear Power Station 10CFR50.59 Summary Rept, Consisting of Descriptions & SE Summaries of Changes, Tests & Experiments.Rept Includes Changes Made to Features Fire Protection Program,Not Previously Presented to NRC
ML20205K5841999-03-31031 March 1999
Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML20205B4241999-03-23023 March 1999
Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util
ML17191B2671999-03-12012 March 1999
Forwards Revs to Dresden,Quad Cities,Zion,Lasalle,Byron & Braidwood Station Odcm,Current as of 981231.ODCM Manual & Summary of Changes,Included
ML20205C6861999-03-0404 March 1999
Provides Notification That Byron Station Implemented ITS on 990205 & Braidwood Station Implemented ITS on 990219
ML20207K0351999-03-0404 March 1999
Forwards Util Which Transmitted Corrected Pages to SG Replacement Outage Startup Rept.Subject Ltr Was Inadvertently Not Sent to NRC Dcd,As Required by 10CFR50.4
ML20207D6831999-03-0101 March 1999
Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d)
ML20207D4301999-02-26026 February 1999
Informs NRC That Supplemental Info for Byron & Braidwood Stations Will Be Delayed.All Mod Work Described in Ltr Is on Schedule,Per GL 96-06
ML20207B8971999-02-25025 February 1999
Expresses Concern That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazard at Some Commercial Nuclear Plants in Us
ML20203C7001999-02-0202 February 1999
Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List
ML20202F5911999-01-29029 January 1999
Forwards Byron Unit 1 Cycle 9 COLR in ITS Format & W(Z) Function & Byron Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function. New COLR Format Has Addl Info Requirements
1999-09-30
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059K6741990-09-17017 September 1990
Suppls Responses to Violations Noted in Insp Repts 50-454/89-11,50-455/89-13,50-456/89-11 & 50-457/89-11. Corrective Actions:Procedures Changed & Valve Tagging Status Provided
ML20059L6611990-09-10010 September 1990
Forwards Byron Station Units 1 & 2 Inservice Insp Program
ML20064A3681990-08-24024 August 1990
Forwards Response to 900517 Request for Addl Info Re Design of Containment Hydrogen Monitoring Sys.Util Proposes Alternative Design That Ensures Both Containment Isolation & Hydrogen Monitoring Sys Operability in Event of LOCA
ML20064A0181990-08-16016 August 1990
Submits Supplemental Response to NRC Bulletin 88-008,Suppls 1 & 2.Surveillance Testing Revealed No Leakage,Therefore Charging Pump to Cold Leg Outage Injection Lines Would Not Be Subjected to Excessive Thermal Stresses
ML20063Q1051990-08-10010 August 1990
Forwards Monthly Operating Repts for Jul 1990 for Byron Units 1 & 2 & Corrected Monthly Operating Rept for June 1990 for Unit 2
ML20055J1221990-07-25025 July 1990
Notifies That Plants Current Outage Plannings Will Not Include Removal of Snubbers.Removal of Snubbers Scheduled for Future Outages.Completion of Review by NRC by 900801 No Longer Necessary
ML20055H7631990-07-25025 July 1990
Forwards Financial Info Re Decommissioning of Plants
ML20055J1261990-07-25025 July 1990
Notifies That Replacement of 13 Snubbers w/8 Seismic Stops on Reactor Coolant Bypass Line Being Deferred Until Later Outage,Per Rl Cloud Assoc Nonlinear Piping Analyses
ML20055G3251990-07-16016 July 1990
Responds to SALP Board Repts 50-454/90-01 & 50-455/90-01 for Reporting Period Nov 1988 - Mar 1990.Effort Will Be Made to Continue High Level of Performance in Areas of Radiological Controls,Plant Operations,Emergency Preparedness & Security
ML20044A9621990-07-13013 July 1990
Forwards Rev 0 to Topical Rept NFSR-0081, Comm Ed Topical Rept on Benchmark of PWR Nuclear Design Methods Using PHOENIX-P & Advanced Nodal Code (Anc) Computer Codes, in Support of Implementation of PHOENIX-P & Anc
ML20044B1411990-07-12012 July 1990
Forwards Addl B&W Rept 77-1159832-00 to Facilitate Completion of Reviews & Closeout of Pressurized Thermal Shock Issue,Per NRC Request
ML20044B2081990-07-11011 July 1990
Responds to Generic Ltr 90-04 Re Status of GSI Resolved W/ Imposition of Requirements or Corrective Actions.Status of GSI Implementation Encl
ML20044B2141990-07-11011 July 1990
Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification
ML20044A9521990-07-10010 July 1990
Provides Supplemental Response to NRC Bulletin 88-001. Remaining 48 Breakers Inspected During Facility Spring Refueling Outage
ML20044A7991990-06-29029 June 1990
Forwards Description of Change Re Design of Containment Hydrogen Monitoring Sys,Per 900517 Request.Util Proposing Alternative Design Ensuring Containment & Hydrogen Monitoring Sys Operability in Event of Power Loss
ML20055D4811990-06-29029 June 1990
Discusses Revised Schedule for Implementation of Generic Ltr 89-04 Re Frequently Identified Weaknesses of Inservice Testing Programs.All Procedure Revs Have Either Been Approved or Drafted & in Onsite Review & Approval Process
ML17202L2921990-06-28028 June 1990
Provides Update on Alternative Schedule for Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance
ML20055D2951990-06-22022 June 1990
Discusses Results of 900529-0607 Requalification Exam.Based on Results of Exam,Station Removed/Prohibited Both Shift & Staff Teams & JPM Failure from License Duties.Shift Team Placed in Remediation Program from 900611-14
ML20058K3521990-06-22022 June 1990
Requests Withdrawal of 900315 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,changing Tech Specs 3.8.1.1 & 4.8.1.1.2 to Clarify How Gradual Loading of Diesel Generator Applied to Minimize Mechanical Stress on Diesel
ML20043D3151990-06-0101 June 1990
Forwards Rev 30 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20043E3141990-05-31031 May 1990
Withdraws 880302 Application for Amend to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,changing Tech Spec 4.6.1.6.1.d to Reduce Containment Tendon Design Stresses to Incorporate Addl Design Margin,Due to Insufficient Available Data
ML20043F4731990-05-30030 May 1990
Forwards Suppl to 881130 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77.Changes Requested Per Generic Ltr 87-09,to Remove Unnecessary Restrictions on Operational Mode Changes & Prevent Plant Shutdowns
ML20043C8641990-05-29029 May 1990
Forwards Rept of Local Leakage Rate Test Results for Third Refueling Outage.Leakage Rates of Six Valves Identified as Contributing to Failure of Max Pathway Limit
ML20043B7691990-05-23023 May 1990
Forwards Endorsement 11 to Nelia & Maelu Certificates N-93 & M-93 & Endorsement 9 to Nelia & Maelu Certificates N-101 & M-101
ML20043A9161990-05-16016 May 1990
Provides Advanced Notification of Change That Will Be Made to Fire Protection Rept Pages 2.2-18 & 2.3-14
ML20034C9721990-05-12012 May 1990
Forwards Eddy Current Rept Cycle 3 Refueling Outage,Jan 1990
ML20043A6391990-05-11011 May 1990
Submits Revised Schedule for Implementation of Generic Ltr 89-04 Guidance.Rev to Procedures for Check Valve & Stroke Time Testing of power-operated Valves Will Be Completed by 900629
ML20043A2891990-05-10010 May 1990
Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for Byron Nuclear Power Station
ML20042G7111990-05-0707 May 1990
Responds to NRC Questions Re leak-before-break Licensing Submittal for Stainless Steel Piping.Kerotest Valves in Rh Sys Will Be Replaced in Byron Unit 2 During Next Refueling Outage Scheduled to Begin on 900901
ML20042F6851990-05-0404 May 1990
Requests Resolution of Util 870429,880202 & 0921 & 890130 Submittals Re Containment Integrated Leak Rate Testing in Response to Insp Repts 50-454/86-35 & 50-455/86-22 by 900608
ML20042G3591990-04-30030 April 1990
Forwards Errata to Radioactive Effluent Rept for Jul-Dec 1989,including Info Re Sr-89,Sr-90 & Fe-55 Analysis for Liquid & Gaseous Effluents Completed by Offsite Vendor
ML20055C5761990-04-30030 April 1990
Forwards Results of Investigation in Response to Allegation RIII-90-A-0011 Re Fitness for Duty.W/O Encl
ML20042E9601990-04-30030 April 1990
Forwards Response to NRC Re Violations Noted in Insp Repts 50-454/90-09 & 50-455/90-08.Response Withheld (Ref 10CFR73.21)
ML20042E9111990-04-25025 April 1990
Forwards Rev 1 to Nonproprietary & Proprietary, Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants
ML20034A8101990-04-18018 April 1990
Responds to NRC Bulletin 88-011,Action 1.a Re Visual Insp of Pressurizer Surge Line at First Available Cold Shutdown Which Exceeds 7-days.Insp Performed by Qualified Visual Examiner.No Abnormal Conditions Revealed
ML20034B6901990-04-12012 April 1990
Forwards Rev 58 to CE-1-A, QA Program for Nuclear Generating Stations. Rev Being Made to Reflect Correct Frequency of Cumulative Deviation Reporting & to Clarify Applicability of Other ANSI N45.2 Stds
ML20034A3131990-04-11011 April 1990
Discusses Commitments in Response to Violations Noted in Insp Repts 50-454/89-16 & 50-455/89-18.Corporate Task Force Completed Draft Document Entitled 10CFR50.59 Implementation Task Force Rept on 900208
ML20034C7291990-04-10010 April 1990
Forwards Part 3 of 1989 Operating Rept.W/O Rept
ML20033G5021990-03-29029 March 1990
Summarizes 900226 Telcon Re Science Applications,Inc Questions Re Station Blackout.Record of Telcon & Am Rubin Encl
ML20033G7691990-03-26026 March 1990
Forwards Deviation Investigation Repts Dir 06-01-90-021 & 022 Addressing Valid & Invalid Failures Experienced on Diesel Generator 1A,including Cracked Fuel Injection Pump Discharge Fittings & Spurious Overspeed Trip Signals
ML20012D7871990-03-21021 March 1990
Forwards Recorded Annual Whole Body External Exposures for CY89 for Listed Plants
ML20012E1081990-03-21021 March 1990
Forwards Calculations Verifying Operability of Facility Dc Battery 111 W/Only 57 of 58 Cells Functional & Onsite Review Notes,Per Request
ML20012D8671990-03-21021 March 1990
Reissued ,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date
ML20012C5471990-03-12012 March 1990
Provides Results of Completed Util Reviews & Addresses Addl Info Requested by NRC Re 890317 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 to Change Tech Spec 4.5.2,supplemented on 890825 & 890925-27 Meetings
ML20033E8261990-02-27027 February 1990
Provides Info Re High Density Fuel Storage Rack Blackness Testing for NRC Review & Acceptance & Advises That Schedule to Perform Blackness Testing within 2 Yrs of Placing Racks in Svc Reflects Relevant Testing Schedule on Boraflex
ML20033E1491990-02-26026 February 1990
Forwards Unit 1 Cycle 4 Reload Core Rept.Vendor Elected Not to Exercise Option of Performing Cycle 4 Neutronic Design in-house Because of Transition to Westinghouse VANTAGE5 Fuel
ML20006E1441990-02-16016 February 1990
Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals
ML20012A4491990-02-16016 February 1990
Advises That 16 Tubes in All Four Steam Generators Removed from Svc as Result of Eddy Current Insp During Cycle 3 Refueling Outage.Tube Plugging Distribution Between Steam Generators Listed
ML20006E4201990-02-14014 February 1990
Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690
ML20006E2611990-02-0909 February 1990
Responds to NRC Bulletin 88-009 Re Thimble Tube Thinning. Thimble Tube Insps Performed Using Eddy Current Testing Methodology & Performed at Every Refueling Outage Until Sufficient Data Accumulated to Generate Correlation
1990-09-17
[Table view] |
Text
..z
' Camm:nwealth Edissn ei,
. g 1400 Opus Place Downers Grove,Illinols 60515 y
July 11. 1990 Dr. Thomas-E. Hurley, Director Office of Nuclear Reactor Regulation-U.S. Nuclear Regulatory Commission
- Hashington, DC 20S55 Attn: Document Control Desk
Subject:
. Byron Station Units 1 and 2 Response to Generic Letter 90-04 HRC Docket _Has. 50-454 and_50-12
Reference:
(a) Generic letter 90-04
-Request for Information Concerning Status of Implementation of Generic Safety Issues (GSI)
Resolved with Imposition of Requirements or Corrective Actions (b) June 28, 1990 letter from T.J. Kovach to T.E. Hurley
Dear Dr. Murley:
' Generic Letter 90-04 was issued as a part of the NRC's continuing effort to establish and maintain an accurate and validated implementation status for all significant staff imposed regulatory requirements or corrective actions. An important aspect of this effort is to ensure that the licensee and the NRC agree on the status of GSI resolution implementation at each facility.
Reference (b)
-indicated that compilation of the requested informati_on would be completed in less than two weeks from the_ original request date of June 29, 1990.
This letter represents the Commonwealth Edison (Edison) response to Generic Letter 90-04, for
- Byron Station.
Byron Station has reviewed the guidance provided in the Generic Letter.
The attached GSI table (Enclosure 1 from the. generic letter) has been updated to reflect the current status of GSI implementation.
The generic letter's guide for updating GSI status was utilized for this process.
Accordingly, the Attachment to this letter provides the status of the efforts for Byron Station.
Please direct any questions regarding this rescense to this office.
Respectfully, C' Y %&
9007180iis 90o711 g - T.K Schuster gDR ADOCK~O5000454 tluclear Licensing Administrator PDC
/scl:1056-2 t%
Attachment O
cc:
A. Bert Davis-RIII Resident Inspector-Byron T. Boyce-NRR
\\
~ -
7
~
-=
m
^ 'GSI/(MPA No.) '
TITLE APPLICABILITY STATUS
- C0ffENTS
.e
=
- FACILITY NAME: Evron Nuclear Station DOCKET NO.:
50-454 and 50-455 LICENSEE:
Commonwealth Edison Comoany-ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF CENERIC SAFETY ISSUES RESOLVED WITH' IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS GSI/(MPA No.)
TITLE
' APPLICABILITY STATUS C0ffENTS 60 (B065)
Safety Concerns Associated All BWRs N/A With Pipe Breaks in ths BWR Scram System 41 (B058)
BWR Scram Discharge Volume All BWRs N/A Systems.
43 (B107)
Reliability of Air Systems All. Plants C
NTS #434-104-88-014000 Generic Letter 88-14 1.
Letter from M. Richter (NLA).
(SOER 88-1) to NRC-dated 2/16/89..
~
2.
Letter from D. R. Muller (NRC).
to H. E. Bliss (NLA) dated.
4/11/89.
.3. The supplemental: response providing the results of engineering reviews will be provided by 8/4/90.
srm:1782v:1
+.
z.
- CSIHMPA "to. I
' TITLE APPLICABILYTE STATUS COPf!ENTS a
-FACILITY NAME: - Evron Nucle.ar Station
~ DOCKET NO.:
50-454 and 53-455 LICENSEE:.
Commonwealth Cdison Comoany ATTACHMENT TO GENERIC LETTER 90--04 RESPONSE STATUS OF LICENSEE' IMPLEMENTATION OF CENERIC SArr u ISSUES
' RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREcuve. ACTIONS 51 (L913)
Improving the Reliability of All Plants I
NTS #454-104-89-01300-A01 thru A13 Graeric Letter 89-13 Open-Cycle Service Water 1.
Letter from M. Richter to NRC Systens dated 1/29f90, CECO Response to Generic Letter 89-13.
2.
Letter from P. Shemanski (NRC) to T. Kovach (NLA) dated 3/21/90.
The following actions are pending for Generic Letter 89-13.
Dates shown below are for Unit 2 and cosmoon. Due dates for Unit 1 are~
approximately 11/15/91.
Action 1.
Intake Structure Inspection Program Action Item Record (AIR)
(454-104-89-01300-A11). Inspection procedure in review process.
Implementation anticipated by end' of September 1990.
Action 2.
Flushing stagnant / infrequently used lines.
srm:1782v:2 I
ll
a GSI/(MPA No.)
TITLE APDLXCABILITY STATHS-C0fffENTS FACILITY NAME:'LEvron Nuclear Station DOCKET NO.:
'5'0-454 and 50-455
, LICENSEE:
~ Commonwealth Edison Comoany ATTAcimedi TO GENERIC LETTER 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SArtu ISSJIES
' RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS AIR #
Subject 51 (L913) continued 01300-A02 AF Pp Miniflow Recire.
due end of B2R02 01300-A03 DG Jkt Wtr Train X-tie-lines due end of B2R02-01300-A04 Unit 0 CC Ex Flush 01300-A06 SX to FP X-tie lines due end of B2R02 AF Pp SX Suction piping Pending installation of Mod.'due 09/30/90 Action 3.
Heat Exchanger Test / Inspection Program AIR 01300-A-09 Heat Exchanger Inspections Scheduled, to be completed by end of B2R02 - approximately 09/30/90 Action 4.
Ultrasonic inspection of high and low flow locations AIR 01300-A12 Due 09/30/90 Action 5.
Single Active Failure Analysis AIR 01300-A01 Due 09/30/90' srm:1782v:3
a ui n
GSJ H MPA No.1 TITLE AERLXCABILITY STATUS CCtM NIS FACILITY.NAME: Byron Nuclear Station
-DOCKET NO.: 454 and 50-455' LICENSEE:
Commonwealth Edison Comoany ATTACHMENT TO GENERIC LETTER 90-44 RESPONSE STATUS OF LICENSEE IMPLEMENTATION-OF GENERIC SArtir ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREc11vt ACTIONS 67.3.3'(A017)
Improved Accident Monitoring All Plants I
Item I.D.1 is still'open.
Anticipated completion' 12/05/90 75 (B076)
Item 1.1 - Post-Trip-Review All Plants C
B. Youngblood (NRC) to D. Farrar.
(NLA), 7-11-85. Item'1.1 complete ~
(Program Description and and closed.
Procedure) 75 (3085)
Ites 1.2 - Post-Trip Review All Plants C
V. Noonan (NRC) to D. Farrar (NLA)
May 5, 1986. Item 1.2 SER..
Item Daca and Information Closed.
Capability 75 (3077)
Item 2.1 - Equipnent All Plants C
L. Olshan (NRC) to D. Farrar (NLA), 1-14-87, Item 2.1 found Classification and Vendor acceptable and closed (references Interface (Reactor Trip given). EGG-NTA-7212 for Part I,.
System Components)
EGG-NTA-7447 for Part II.
S. Sands (NRC) to T. Kovach (NLA)'
75 (B086)
Item 't 2.1 - Equipment All Plants C
March 26, 1990. Item 2.2.1 classification for GL 83-28, item closed.
dafety-Rt: ?2 1 Components 75 (LOO 3)
Item 2.2.2 - Vendor All Plants awaiting G. Alexander (NLA) to H. Denton closure (NRC) May 7, 1985. Items 2.1, Interface fcr Safety-Related 2.2, 4.5.2, provides. additional Components information.
srm:1782v:4 d
~
iGfSZ/(MPA No.
TITLE APPLICABILITY SJATUS COPMENTS f
2
-FACILITY NAME: Byron Nuclear Station-DOCKET NO.:
50-454 and 50-455
- LICENSEE:
Commonwealth Edison Comcany
' ATTACHMENT-TO GENERIC Ltntx 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES ACTIONS BESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREL ~nvE All Plants C
B. Youngblood (NRC) to D..Farrar 75 (B078)
Items 3.1.1 & 3.1.2
'(NLA), 9-26-85.
Items.3.1.1-Post-Maintenance Testing 3.1.2, 3.2.1, 3.2.2, 4.1, and
.(Reactor Trip System 4.5.1 complete and components )
closed.
75 (B079)
Items 3.1.3 - Post All Plants C
B. Youngblood (NRC) to D. Farrar (NLA), 11-5-85.
Items 3.1.3 and Maintenance Testing-Changes.
3.2.3 complete and closed.
to Test Requirements (Reactor Trip System Components) 75 (B087)
Items 3.2.1 & 3.2.2 All Plants C
B. Youngblood (NRC) to D. Farrar
-(NLA),-9-26-85.
Items 3.1.1, Post-Maintenance Testing 3.1.2, 3.2.1, 3.2.2, 4.1, and (All Other Safety-Related 4.5.1 complete and closed.
Components) 75 (B088)
Item 3.2.3 All Plants C
B. Youngblood (NRC) to D. Farrar (NLA), 11-5-85.
Items 3.1.3 and Post-Maintenance.
3.2.3 complete and closed.
Testing-Changes to Test Requirements (All Other Safety-Related Components) 75 (B080)
Item 4.1 - Reactor Trip All Plants C
B. Youngblood GiRC) to li. Farrar (NLA), 9-26-85.
Items 3.1.1, System Reliability 3.1.2,-3.2.1, 3.2.2, 4.1, ano (Vendor-Related 4.5.1 complete and closed.
Modifications) sen:1782v:5 I
^
.GSJ/(MPA No.).
TITLE ~
APPZ.YCABIIITY-STATUS COPMENTS
- j
- FACILITY NAME: Byron Nuclear Station
- DOCKET NO. :
50-454 and 50-455 LLICENSEE:
Commonwealth Edison Comoany-ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE-STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SArtu ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECT 1vt ACTIONS 75 (B081)
-Items 4.2.1 & 4.2.2 All PWRs C
V. Noonan (NRC) to D. Farrar (NLA)..
April 28, 1986. SER for Items Reactor Trip System 4.2.1 and 4.2.2.
Items closed.
Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (B082)
Item 4.3 - Reactor Trip-All W and conditionally B. Youngblood (NRC) to D. Farrar System Reliability - Design B&W Plants--
approved (NLA), 3-13-85.
Item 4.3, auto shunt trip modification approved Modifications (Automatic on 4 conditions.- Awaiting final Actuation of Shunt Trip Attachment for Westinghouse approval and closeout, and B&W Plants) 75 (B090)
Item 4.3 - Reactor Trip All W & B&W C
L. Olshan (NRC) to T. Kovach System Reliability - Tech Plants May 22, 1989. Technical Specification amendment and SER.
Spec Changes (Automatic Closed Generic Letter 85-09 and Actuation of Shunt Trip 82-33. Item 4.3.
Attachment for Westinghouse and B&W Plants) 75 (B091)
Item 4.4 - Reactor Trip All B&W N/A System Reliability Plants (Improvements in Maintenance and Test Procedures for B&W Plants) srm:1782v:6
~
_-.m.
~
~
GSY/(MFA NoN' TITLE APPLIC BILITY ! STATUS C0tetENTS FACILITY NAME: Byron Nuclear' Station J DOCKET NO.:
50-454 and 50-455
. LICENSEE:
Commonwealth EdisonLComcany ATT CHMENT TO GENERIC LEntx 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ~ ACTIONS 75 (B092)
Item 4.5.1 - Reactor Trip
-All Plants C
.B. Youngblood (NRC) to D. Farrar.
System Reliability-Diverse
-(NLA) 9-26-85.
Items'3.3.1, Trip Features (System
'3.1.2, 3.2.1, 3.2.2, 4.1 and 4.5.1 Functional Testing) complete and closed.
75 (B093)
Items 4.5.2 & 4.5.3
'All Plants C
L. Olshan-(NRC) to D..Farrar (NLA)
Reactor Trip System January 23, 1987. SER for Item Reliability - Test-4.52.
Item closed.
Alternatives and Intervals L. Olshan (NRC) to T. Kovach (NLA)
(System Functional Testing)
June 16, 1989.
Item 4.5.3 closed per contractor report,' Idaho-National Engineering EGG-NTA-8341, March, 1989.
86 (B084)
Long Range Plan for Dealing All BWRs N/A with Stress Corrosion Cracking in BWR Piping 93 (B098)
Steam Binding of Auxiliary
.All PWRs C
1.
Letter from L. Olshan to Generic Letter 88-3 Feedwater Pumps H. E. Bliss dated 7/19/88 NTS //454-104-88-00300 accepting corporate response.
srm:1782v:7
~
gi ii SSJ HMPA Wo.)-
XITLE
-APPLICABILITY STATUS C0ff!ENTS
, FACILITY NAME: 'Evron Nuclear Station-L DOCKET NO.:
5'0-454 and 50-455 LICENSEE:
Commonwealth Edison Comoany ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SArt.li ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREcnvt. ACTIOrd 99 (L817)
RCS/RHR Suction Line Valve All PWRs I
1.
Letter from R. A. Chrzanowski' (NLA) to T.E. Murley dated Generic Letter 88-17 Interlock on PWRs 12/30/88.
NTS #454-104-88-01700 2.
Letter from R. A. Chrzanowski (NLA) to T. E. Murley dated
-1/31/89.
3.
Letter from R. A. Chrzanowski to T. E. Murley providing CECO
. response to the Generic Letter l
88-17 Programmed Enhancements p
dated 2/6/89.
i-4.
' Letter from T. E. Murley:to R.
A. Chrzanowski dated 11/1/89..
5.
Letter from P. Shamanski to-T. Kovach dated 1/17/90.
6.
Technical Specification change request in Letter from T. Schuster (NLA) to
.T. E. Murley dated 1/31/90.
Changes for removal of RHR Autoclosure Interlock, allow the operation of one safety injection pump in Mode 5, removal of RHR flowrate in Mode 6.
Amendment expected 8/1/90.
srm:1782v:8
- - :=
-e EIHMPA No.)
TITLE APPLICAEILITY STATUS COtTtENTS FACILITY NMIE: Byron Nuclear Station EOCKET NO.:
.50-454Jand 50-455 LICENSEE:
Commonwealth Edison Company ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF GENEP.IC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS 99 (L817) continu=1 Corresponding Modifications to remove the autoclosure interlock are:
M6-2-89-024 and M6-1-89-024, anticipated completion for Unit 2, end of'B2R02.
Anticipated completion for Unit 1, end of BIR04.
124 Auxiliary Feedwater System All PWRs N/A Reliability ANO-l&2, Rancho Seco,
. Prairie Island 1&2, Crystal River-3 Ft. Calhoun A-13 (B017)
' Snubber Operability.
All Plants NC Tech Spec 3/4.7.8 incorporates Assurance Hydraulic Snubbers this item.
A-13 (B022)
Snubber Operability All Plants NC Plant design and Tech Spec 3/4.7.8 Assurance Mechanical Snubbers incorporates this item.
A-16 (D012)
Steam Effects on BWR Core Oyster-Creek N/A Spray Distribution
& NMP-1 srm:1782v:9
.=
=
~
...Y Y.
y GSIHMPA No.i~
TITLE APPLICABILITY. STATUS:
C0ft1ENTS 7
'F4CILITY NAME: Byron Nuclear' Station DOCKET NO.: 454 and 50-455-LICENSEE:
Commonwealth Edison Comnany ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE STATUS OF LICENSEE' IMPLEMENTATION OF GENERIC SArt.u ISSUES
~ RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECT 1ve. ACTIONS-A-35 (B023)
Adequacy of Offsite Power All Plants NC
' Plant design incorporates this item. Reference SER and UFSAR.
Systems B-10 Behavior of-BWR Mark III All BWR N/A Containments Mark'III Plants B-36 Develop Design, Testing and All Plants NC Plant design incorporates this Maintenance Criteria for with OL item, reference SER and UFSAR.
Atmosphere Cleanup-System
' Applications Air Filtration and After 4/1/80 Adsorption Units for Engineered Saftey Features Systems and for Normal Ventilation Systems.
B-63 (B045)
Isolation of Low Pressure All Plants NC Plant design and Tech Spec 3/4.4.6 incorporates this item.
Systems Connected to the Reactor Coolant System Pressure Boundary-i srm:1782v:10.
t
__