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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2871999-10-21021 October 1999
Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased
ML20217P6171999-10-21021 October 1999
Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4)
ML20217M4361999-10-19019 October 1999
Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21
ML20217J4411999-10-18018 October 1999
Forwards Exemption from Certain Requirements of 10CFR73.55 for Zion Nuclear Power Station,Units 1 & 2 in Response to Application Dtd 990730,to Allow Util to Discontinue Specific Aspects of Security Plan & SER
ML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217G9791999-10-14014 October 1999
Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2
ML20217F7891999-10-0808 October 1999
Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV
ML20217B6351999-10-0505 October 1999
Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in
ML20212L1791999-10-0505 October 1999
Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2
ML20217B2991999-10-0101 October 1999
Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry
ML20216J8241999-09-30030 September 1999
Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr
ML20212J6751999-09-30030 September 1999
Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts
ML20217A5821999-09-29029 September 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities
ML20217A9311999-09-29029 September 1999
Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem
ML20216G9541999-09-27027 September 1999
Forwards Environ Assessment & Finding of No Significant Impact Re 990730 Application for Exemption.Exemption Would Allow Zion Nuclear Power Station to Discontinue Specific Aspects of Security Plan
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
A99025, Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station1999-09-15015 September 1999
Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station
ML20212A6991999-09-10010 September 1999
Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2
ML20211Q9011999-09-0808 September 1999
Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed
ML20211P1841999-09-0808 September 1999
Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented
ML20211Q6821999-09-0606 September 1999
Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529
ML20211Q6611999-09-0606 September 1999
Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218
ML20211P1901999-09-0303 September 1999
Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls
ML20211N5151999-09-0303 September 1999
Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided
ML20211M1371999-09-0202 September 1999
Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl
ML20211K1081999-09-0202 September 1999
Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2
ML20211P1761999-09-0202 September 1999
Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required
ML20211L1551999-09-0101 September 1999
Forwards Insp Repts 50-295/99-03 & 50-304/99-03 on 990608-0812 at Zion 1 & 2 Reactor Facilities.No Violations Noted.Activities in Areas of Facility Mgt & Control, Decommissioning Support,Sf & Radiological Safety Examined
ML20211J9701999-08-31031 August 1999
Discusses Request for Approval of Defueled Station Emergency Plan & Exemption from Certain Requirements of 10CFR50.47, Emergency Plans, for Plant,Units 1 & 2.Exemption & Safety Evaluation Encl
ML20211J0311999-08-30030 August 1999
Agrees with Content in NRC 990810 Memo Re Plant Spent Fuel Pool.Memo Contains Accurate Summation of Info That Util Communicated to NRC During 990713 Telcon
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)
ML20211G8191999-08-26026 August 1999
Forwards Amend 6 to Fire Protection Rept for Zion Nuclear Power Station,Units 1 & 2, IAW 10CFR50.71(e).Attachment 1 Contains Summary of Changes
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
ML20211F5971999-08-20020 August 1999
Submits Request for Addl Info Re Proposed Defueled TSs for Plant,Per NRC Bulletin 94-001, Potential Fuel Pool Draindown Caused by Inadequate Maint Practices at Dresden Unit 1
ML20211C7401999-08-19019 August 1999
Informs That NRC Plans to Stop Using Office Complex at Zion Nuclear Generating Station Which Commonwealth Edison Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1). NRC-owned Equipment to Be Moved on or About 991001
ML20211J4421999-08-13013 August 1999
Forwards, EA & Finding of No Significant Impact Re Application for Exemption ,as Suppl by 990708 & 19 Ltrs.Proposed Exemption Would Modify Emergency Response Plan Requirements 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
ML20210J0861999-07-30030 July 1999
Requests NRC Approval of Exemption from Certain Requirements of 10CFR73, Physical Protection of Plants & Matls, by 990921.Exemption Is Needed to Support Scheduled 991001 Implementation of Plant Sf Ni.Encl Withheld,Per 10CFR73.21
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
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)
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
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
A99025, Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station1999-09-15015 September 1999
Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station
ML20211Q9011999-09-0808 September 1999
Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed
ML20211J0311999-08-30030 August 1999
Agrees with Content in NRC 990810 Memo Re Plant Spent Fuel Pool.Memo Contains Accurate Summation of Info That Util Communicated to NRC During 990713 Telcon
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)
ML20211G8191999-08-26026 August 1999
Forwards Amend 6 to Fire Protection Rept for Zion Nuclear Power Station,Units 1 & 2, IAW 10CFR50.71(e).Attachment 1 Contains Summary of Changes
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
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
BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999
Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station
ML20210N5651999-08-0606 August 1999
Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes
BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999
Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle
ML20210M9131999-08-0202 August 1999
Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed
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
ML20210J0861999-07-30030 July 1999
Requests NRC Approval of Exemption from Certain Requirements of 10CFR73, Physical Protection of Plants & Matls, by 990921.Exemption Is Needed to Support Scheduled 991001 Implementation of Plant Sf Ni.Encl Withheld,Per 10CFR73.21
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
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
ML20210C2561999-07-19019 July 1999
Forwards Rev 1 to Calculation 22S-B-110X-0068, Determination of Heat Load for Assemblies F50D & Z33A, as Replacement Pages to Rev 0.Calculation Submitted Re Request for Approval of Proposed Plant Defueled Station EP
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
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
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
ML20209E7391999-07-0808 July 1999
Forwards Proposed Revised Znps Defueled Station Emergency Plan & Supporting Calculations.Revs to Proposed Defueled Station Emergency Plan Have Been Reviewed & Approved IAW Comed QA Program
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
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)
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
05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999
Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below
05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999
Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations
ML20195H9391999-06-15015 June 1999
Forwards Revised Monthly Operating Rept for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2.Data Was Revised to Reflect Change in Daylight Savings Time
05000456/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed1999-06-15015 June 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed
BW990028, Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.51999-06-10010 June 1999
Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.5
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
ML20195E3451999-06-0707 June 1999
Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data
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
A99018, Responds to NRC Re Violations Noted in IR 3-98- 017.Corrective Actions:Three Security Guards Unescorted Access to All Comm Ed Nuclear Stations Put on Temporary Hold1999-05-27027 May 1999
Responds to NRC Re Violations Noted in IR 3-98- 017.Corrective Actions:Three Security Guards Unescorted Access to All Comm Ed Nuclear Stations Put on Temporary Hold
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
05000457/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Listed1999-05-21021 May 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are 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
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059L0341990-09-20020 September 1990
Forwards Addl Station Blackout Info Re Diesel Loading & Alternate Ac Analysis,Per 900404 Meeting.Info Will Be Helpful When Evaluating Unit O Diesel Generator cross-tie Mod
ML20059K6741990-09-17017 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
ML20059K5081990-09-14014 September 1990
Forwards Tj Kovach to E Delatorre Re Visit by Soviet Delegation to Braidwood Nuclear Station in May 1990
ML20059L6611990-09-10010 September 1990
Forwards Byron Station Units 1 & 2 Inservice Insp Program
ML20059G1611990-09-0606 September 1990
Submits Supplemental Response to Generic Ltr 89-06, Certifying That SPDS Satisfies or Will Be Modified to Satisfy Requirements of Suppl 1 to NUREG-0737.Classroom Instruction on SPDS Incorporated Into Program
ML20059G1751990-08-31031 August 1990
Provides Results of Util Reevaluation of Response to NRC Bulletin 85-003.Util Believes That Previous Testing Results & Subsequent Submittals Provide Assurance of Continued Operability of Sys motor-operated Valves
ML20064A3751990-08-24024 August 1990
Forwards Revised Pages to Operating Limits Rept for Cycle 2, Correcting Fxy Portion of Rept,Per Tech Spec 6.9.1.9, Operating Limits Rept
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
ML20059D8271990-08-23023 August 1990
Provides Written Communication Re Util Intentions & Commitments,Per 900808 Telcon W/M Wallace.Standing Order 90-24 Issued to Provide Administrative Controls Beyond Tech Spec Requirements to Assure Svc Water Pump Availability
ML20059C0781990-08-22022 August 1990
Submits Supplemental Info to Util 900412 Response to Notice of Violation in Insp Repts 50-295/89-40 & 50-304/89-36.Info Regards Requalification program,180 H of Required Training Through SAT Process & Policy for Remediation of Individual
ML20056B4331990-08-20020 August 1990
Forwards Errata,To Radioactive Effluent Rept for Jan-June 1990 & Gaseous Effluent Errata Sheet
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
ML20059A3991990-08-15015 August 1990
Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp Program
ML20058P7791990-08-13013 August 1990
Provides Supplemental Response to NRC Bulletin 89-001 Re Mechanical Plugs Supplied by Westinghouse,Per .All Mechanical Plugs from Heats NX-3513 & NX-4523 Removed from Hot Legs of Plant Steam Generators
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
ML20058N0551990-08-0707 August 1990
Provides Supplemental Response to NRC Bulletin 88-008, Suppls 1 & 2.Surveillance Testing Performed Revealed No Leakage,Therefore,Charging Pump to Cold Leg Injection Lines Would Not Be Subjected to Excessive Thermal Stresses
ML20058N0651990-08-0707 August 1990
Responds to NRC Bulletin 88-009 Re Incore Neutron Monitoring Sys Thimble Tube Integrity.Thimble Tube Insps Will Be Performed at Every Refueling Outage Until Sufficient Data Accumulated on Thimble Tube Wear
ML20056A3351990-08-0202 August 1990
Responds to NRC Bulletin 88-009 Requesting That Addressees Establish & Implement Insp Program to Periodically Confirm in-core Neutron Power Reactors.All Timble Tubes Used at Plant Inspected & 18 Recorded Evidence of Degradation
ML20056A0271990-07-30030 July 1990
Provides Addl Info Re Resolution of Number of Older Licensing Issues,Including Containment Isolation Valve Position Indication,Per NRC
ML20056A0741990-07-27027 July 1990
Forwards Justification for Rev to Installation Schedules for Two Commitments Re Safeguards Inadequacies & Program Concerns.Encl Withheld
ML20055J2231990-07-26026 July 1990
Requests Withdrawal of Proposed Amend Re Deletion of Confirmatory Order
ML20055J1191990-07-26026 July 1990
Responds to Generic Ltr 90-04, Request for Info Re Status of Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions. Current Status of Issues Encl
ML20055H7631990-07-25025 July 1990
Forwards Financial Info Re Decommissioning of Plants
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
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
ML20055H0871990-07-20020 July 1990
Provides Status Rept on Molded Case Circuit Breakers Replacement,Per NRC Bulletin 88-010.Traceable Replacement Breakers for Units 1 & 2 Being Procured safety-related & Meet Criteria of Bulletin Action 7
ML20055H0291990-07-17017 July 1990
Forwards Revised Monthly Performance Rept for Braidwood Unit 2 for June 1990
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
ML20055G4631990-07-13013 July 1990
Responds to NRC Re Violations Noted in Insp Repts 50-456/90-08 & 50-457/90-08.Corrective Actions:Discrepancy Record for Cable Generated & Cable That Had Been Previously Approved for Use on Solenoid Obtained & Installed
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
ML20044B2141990-07-11011 July 1990
Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification
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
ML20044A9521990-07-10010 July 1990
Provides Supplemental Response to NRC Bulletin 88-001. Remaining 48 Breakers Inspected During Facility Spring Refueling Outage
ML20044B2871990-07-0909 July 1990
Forwards Brief Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,Per NUREG-1002 & Util 900629 Original Submittal
ML20058N6821990-07-0606 July 1990
Suppls 900626 Response to CAL-RIII-90-011 Re Torque Switch Settings,Per NRC Bulletin 85-003.Program to Address Generic Ltr 89-10 Which Expands Scope of Bulletin 85-003 Testing to safety-related motor-operated Valves,Being Developed
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
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
ML20055D5291990-06-27027 June 1990
Forwards Table Outlining Status of Significant Events Re PWR Reload Safety Analysis Methods for Plant Cycle 13.Requests That Transient Analysis Topical Rept Be Reviewed & SERs Issued Prior to 910830
ML20055D5231990-06-26026 June 1990
Responds to Confirmatory Action Ltr CAL-RIII-90-11 Re Actions Required to Confirm Valve Operability for Unit 1,per IE Bulletin 85-003
ML20055D8461990-06-24024 June 1990
Forwards WCAP-10962,Rev 1, Zion Units 1 & 2 Reactor Vessel Fluence & Ref Temp for PTS Evaluations
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
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
ML20055D8391990-06-18018 June 1990
Provides Supplemental Info in Response to Generic Ltr 88-17, Loss of Dhr. Permanently Installed Level Transmitter, Independent from Refueling Vessel Level Recorder & Led Readout Will Be Utilized
ML20056A0361990-06-15015 June 1990
Responds to NRC Re Violations Noted in Insp Repts 50-456/90-10 & 50-457/90-11.Corrective Action:Valve 2CS021b Returned & Locked in Throttle Position & Out of Svc Form Bwap 330-1T4 Modified
ML20043G5851990-06-0808 June 1990
Forwards Repts Re Valid & Invalid Test Failures Experienced on Diesel Generator (DG) 1DG01KB,1 Valid Test Failure on DG 2DGO1KA & 2 Invalid Test Failures Experienced on DG 2AGO1KB
ML20043D3151990-06-0101 June 1990
Forwards Rev 30 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20043D3141990-06-0101 June 1990
Forwards Rev 18 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
1990-09-06
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Text
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Commonwealth Edison O_ne First National Plaza. Chicago. tilinois Address Reply to. Post Othee Box 767 Chicago. Illinois 60690 l
August 22, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Zion Station Units 1 and 2 Response to Generic Letter 85-12 Implementation of TMI Action Item II.K.3.5 Automatic Trip of Reactor Coolant Pumps NRC Docket Nos. 50-295/304, 50-454/455 and 50-456/457 Reference (a): Generic Letter 85-12 HL Thompson to all OLS and CPS with Westinghouse Nuclear Steam Supply Systems
Dear Mr. Denton:
Reference (a) requested that applicants respond to questions in Section IV of the enclosed Safety Evaluation on reactor coolant pump trip or establish a schedule for responding to the questions. ,
Commonwealth Edison's PWR plants are basing their responses on the WOG RCP trip methodology. Attached are responses for Byron and Braidwood and Zion to most of the questions. Where responses are not complete, proposed dates for supplementary responses are offereo.
Please contact this office if you or your staff have any further questions regarding Generic Letter 85-12.
Forty copies of this letter with attachments will be forwarded under separate cover.
Respectfully, 85082 PDR g g $$$$$95 d Greg Alexander PDR P Nuclear Licensing Administrator atts.
cc: US NRC, Document Control Desk Washington DC 20555 J. G. Keppler - RIII RIII Inspectors - BY,BW and Z
,g U l 0524K l
ATTACHMENT A Byron and Braidwood Response to Generic Letter 85-12 Automatic Trip of Reactor Coolant Pump IV. IMPLEMENTATION A. Determination of RCP Trip Criteria
- 1. The instrumentation to be used is a lE qualified RCS wide range pressure instrument. Currently there are two (2) monitor channels installed that are separate, independent and redundant.
- 2. The instrument uncertainties have been calculated by Westinghouse NSD and were provided to Byron and Braidwood by W. Kortier as part of the Emergency Procedures development effort. Normal containment uncertainties were established as 3% of span or 90 psi. Abnormal containment uncertainties were established as 13% of span or 390 psi.
adverse containment conditions are defined by the WOG ERG criteria as greater than:
- a. 5gsigcontainmentpressure, or
- b. 10 R/hr containment radiation levels.
The concern of pipe whip or jet impingment can be answered in three (3) parts.
- a. For Steam Generator Tube Rupture (SGTR), neither condition creates a problem since any break would be inside the Steam Generator.
- b. No problems arise from secondary break accidents because steamline and feedline transmitters are located at the 377' level inside the missile barriers and away from all feedwater and steamline piping,
- c. Regarding Small Break LOCA, the two pressure transmitters are located such that even if one was to be disabled by a Small Break LOCA, the other transmitter would be unaffected.
Byron has also committed to installing four (4) qualified wide range RCS pressure transmitters (per Reg. Guide 1.97) outside containment during the first refueling outage.
Braidwood has committed to the installation prior to fuel load.
- 3. The selection of criterion and consideration of uncertainties will be addressed after review of WOG supplied information. A tentative submittal date for this information is September 16, 1985.
- 8. Pote.ntial Reactor Coolant Pump Problems
- 1. Containment isolation-can be divided into two (2) parts, Phase-A and Phase B. .The important " water services" which are of concern are:
- a. _ Seal water injection from the charging system.
- b. Seal water return.
- c. Cnmponent cooling to both the pump thermal barrier and the motor oil coolers.
Phase A isolation affects only the seal water return by redirecting it from the VCT to the Pressurizer Relief Tank. This is designed so that seal leakoff will continue but collect inside containment following a Phase A isolation. Therefore Phase A isolation',
whether inadvertent or~ intentional, will not cause any RCP problems.
Phase B isolation interrupts the component cooling to the thermal barrier and to'the motor coolers. No seal problem should be encountered due to the continued cooling flow supplied by the charging system seal injection flow. However, the RCP must be stopped due to the loss of motor oil cooling. Because of this, the
. emergency procedures require that the RCP's be tripped when Phase B isolation occurs. Inadvertent actuation of Phase B isolation is virtually eliminated at Byron and Braidwood since manual actuation requires simultaneous operation of two (2) hand switches. 'Also,
' Operators are extensively trained to stop RCP's for any Phase B actuation.
- 2. The components able to trip each RCP are as follows:
- a. RCP breaker located in the 6.9 KV electrical switchgear room.
- b. 125 VDC relay power.
- c. Two (2) separate manual trip actuators, the control switch at the main control board and the emergency trip button on the remote shutdown panel.
All of these components are located outside containment and as such cannot be affected by adverse containment conditions.
C. Operating Training
- 1. All licensed operators have had previous training on RCP operation and trip criterion during several phases e of their training. In addition, they will receive
additional updated training on RCP operations and trip criterion during the review of revisions to the Emergency Operating Procedures. . This training takes place:
- a. During systems training on RCS.
- b. During accident analysis and mitigating core damage series.
- c. During Licensed Operator retraining lectures.
- d. As encountered regulsrly during annual simulator sessions.
Additionally, the philosophy regarding the need to trip pumps versus the desire to keep pumps running, is covered during initial training on 'the Byron and Braidwood Emergency Operating Procedures.
- 2. Procedures which include RCP trip related operations.
- a. RCP trips - see Tables 1 and 2
'b. RCP restart - see Tables 1 and 2
- c. Decay heat removal by natural circulation
- see Tables 1 and 2 Note, where a restart is authorized but not accomplished, decay heat removal instructions are also given.
- d. Primary system void removal (18EP-ES 0.3, 0.4, 1BFR -1.3)(1 Bw EP ES.O.3,0.4 and Bw FR 1.3)
- e. Use of steam generators with and without RCP's operating (answered in b & c above).
- f. RCP trips for other reasons - see Tables 1 and 2
Byron' Station Table-1 Summary of RCP Trip and RCP Restart Steps
' ERG RCP Trip RCP Restart 1BEP-0 T 1BEP ES-0.1~ R 1BEP ES-0.2 R 1BEP ES-0.3 R 1BEP ES-0.4 R 1BEP 1 T 1BEP ES-1.1 R 1BEP ES-1.2 TA,TI R 1BEP 3 T,TA R 18EP'ES-3.1 TI 18EP ES-3.2 .TI
-1BEP ES-3.3 TI 18CA 1.1 TI 1BCA 2.1 T R 18CA 3.1 TA,TI R 1BCA 3.2 TA,TI R 1BCA 3.3 TI R 1BFR C.1 ST SR 18FR C.2 ST 18FR H.1 ST-1BFR P.1 R 18FR I.3 R
- T - RCP trip criteria steps TA - Trip all but one RCP steps TI - No. 1 Seal RCP_ trip steps ST - Other special trip steps R - Restart criteria and support conditions required SR - Special restart-without support conditions required 0524K
s h
Braidwood~ Station Table 2 Summary ~of RCP Trip and RCP Restart Steps
.lBwEP ES-0.1 R 18wEP ES-0.2 R 18wEP ES-0.3 R 18wEP ES-0.4 R
-18wEP 1 T 18wEP ES-1.1 'R.
1BWEP ES-1.2 TA,TI R 18wEP 3 T,TA R 1BwEP ES-3.1 TI 1BwEP ES-3.2 TI 18wEP ES-3.3 TI 1Bw0A 1.1 TI 18w0A 2.1 T R 18w0A 3.l' TA,TI R 18w0A 3.2 TA,TI R
'1Bw0A 3.3 TI R
~18wFR C.1 ST SR 18wFR C.2 ST.
18wFR H.1 ST
-1BwFR P.1 R 18wFR I.3 R
- T - RCP trip criteria steps TA'- Trip all but one RCP steps TI - No. 1 Seal RCP trip steps ST - Other special trip steps R - Restart criteria and support conditions required SR - Special restart without support conditions required 0524K
p ATTACHMENT B Zion Station Response to Generic Letter 85-12 Automatic Trip of Reactor Coolant Pumps A. Determination of RCP Trip Criteria Response-to Item 1:
~
The RCP trip criteria to be used at_ Zion 1s based on Revision 1 of the Westinghouse Owners Group (WOG) Emergency Response Guidelines (ERG's). The specific criterion to be used will be:
RCS wide range pressure less than a constant. The above
" constant" will be different for normal and adverse containment conditions.
For Zion, two (2) environmentally qualified wide range pressure transmitters, each on a separate'RCS loop, will be used to determine the RCP trip setpoint.
Response-to-Item 2:
The instrumentation uncertainties for both normal and adverse containment conditions for the RCP trip setpoint will be submitted by October 31, 1985. The .two (2) Barton wide range RCS pressure transmitters to be used to determine the RCP trip setpoint are both located inside the containment but outside the missile barrier. As such, the transmitters are not subject to local conditions such as fluid jets or pipe whip which might influence instrumentation reliability.
Response to-Item 3:
Uncertainties associated with the WOG supplied analyses
' values used in the RCP trip study is scheduled to be studied generically by the WOG. Based on this generic evaluation, it is expected that this item will be addressed by September 31, 1985.
B.- Potential Reactor Coolant Pump Problems Response to Item 1:
For SGTR's and most non-LOCA events, adverse containment conditions will not be present. As such, only Containment j Isolation Phase A will actuate on a Safety Injection (SI) signal for these events. Containment Isolation Phase A closes all containment isolation valves, except for the five (5) component cooling valves that supply cooling water to the RCP's. Containment Isolation Phase B will close the
)
4 *.- . .
l l
l l
- 2- j l
five component cooling valves to the RCP's. RCP seal injection flow-is not isolated by either Containment Isolation Phase A or 8. The Phase B signal is only actuated automatically following an SI signal with a
~
, high-high containment pressure of 23 psig. High-Hign containment pressure will not occur for SGTR's and most i
non-LOCA events.
- - Response Item la
Based on the above discussion, Containment Isolation-Phase A, which actuates on an SI signal, does not isolate the water services'needed for RCP operation.
Response to-Item-lb:
Actuation of Containment Isolation Phase A does not isolate the services needed for RCP-operation (e.g. seal' injection
- water and cooling water will not be terminated) and thus
! will not lead'to seal or pump damage or failure.
Response to Item 2:
The components able to trip each RCP are as follows:
- a. RCP breaker located in the 4KV electrical switchgear room i b. 125 VDC relay power
- c. Two (2) separate manual trip actuators, the control switch at the main control board, and the emergency l
trip buttons in the electrical switchgear room.
All of these compenents are located outside containment and as such cannot be affected by adverse containment conditions.
! C. Operator Training and Procedures (RCP Trip) f' Response to Iteia 1: ,
- - ,The new E0P's for Zion Staton have not yet been implemented and the training program is still being developed. The operator training program will be available on January 1, 1986.
Response to Item 2:
'The new E0P's for Zion Station have not yet been
- . implemented. The list of procedures pertaining to RCP trip
! related operations will be available on January 1, 1986.
0524K ,
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