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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes 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 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 ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted 1999-09-08
[Table view] Category: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 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed 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) 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 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 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 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 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 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 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 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-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 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 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 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 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 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 ML20206T3351999-05-17017 May 1999 Provides Written follow-up of Request for NOED Re Extension of Shutdown Requirement of TS Limiting Condition for Operation 3.0.3.Page 9 of 9 of Incoming Submittal Not Included ML20206N7861999-05-14014 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Braidwood Station. Rept Contains Info Associated with Stations Radiological Environ & Meteorological Monitoring Programs ML20206Q8521999-05-13013 May 1999 Submits Rept on Numbers of Tubes Plugged or Repaired During SG Inservice Insp Activities Conducted During Plant Seventh Refueling outage,A2R07,per TS 5.6.9 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 ML20210C7221999-05-0303 May 1999 Forwards Initial License Exam Matls for Review & Approval. Exam Scheduled for Wk of 990607 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 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 1999-09-08
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Commonwealth 1:dison Company fly ron Generating Station
- 4450 North German Church Road liyron, !!. 61010-979 6 Tel HI 5-2315411 October 1,1998 LTR: BYRON-98-0276 FILE: 2.01.0700 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington D.C. 20555 - 0001 l l
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Subject:
Commomvealth Edison's (Comed's) Revised Response to the NRC's Request for !
Additional Information (RAI) for Improved Technical Specifications (ITS) !
Beyond Scope Changes (BYS)
Byron Nuclear Power Station, Units 1 and 2 I Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Numbers: 50-454 and 50-455 Braidwood Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Numbers: 50-456 and 50-457 References; G. Stanley and K. Graesser (Comed) letter to USNRC, " Conversion to the improved Standard Technical Specifications," dated December 13,1996 The purpose of this letter is to transmit Comed's revised responses to the NRC's RAI for the ITS Beyond Scope Changes (BYS). The responses are clarifications due to further discussions with the staff reviewers on the individual requests beyond the allowed deviation from the NUREG standard and current licensing basis. The responses to the RAI questions are contained in the Attachment, Revised Response to NRC RAI for ITS BYS.
The RAI contains questions and comments stemming from the NRC's initial review of a Comed request (Reference 1) to amend the Current Technical Specifications (CTS) for Byron Units 1 and f 2 and Braidwood Units I and 2. The amendments to the RAI responses were requested in order to adopt the improved Technical Specifications of NUREG-1431, Revision 1. \
9810060359 981001 (
PDR ADOCK 05000454 -
p PM u 1
A linicom Company
Addressed in the attachment are the beyond scope changes BYS 3.0,5.0, 6.0, and 8.0 that have not been closed during our review process.
Please address any comments or questions regarding this . matter to our Nuclear Licensing Department.
Sincerely, s .
Kenneth L. Graesser .
Site Vice President Byron Nuclear Power Station KG/KG/cib
Attachment:
Response to NRC RAI for ITS Beyond Scope Changes cc: Regional Administrator- RIII Senior Resident Inspector - Braidwood Senior Resident inspector- Byron Office of Nuclear Facility Safety - IDNS
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Byron / Braidwood Revised Response to NRC RAI for ITS Beyond Scope Changes (BYS) l (Improved Technical Specification Submittal) l 1
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. Response to NRC RAI Dated 01/16/98 NRC RAI Number NRC lssued Date RAI Status BYS 3.0 1/16/98 Closed NRC Description ofIssue DOC L.7 JFD P.16 ITS LCO 3.3.2, Condition M CTS Table 3.3-3, Action 15a The proposed change involves the action completion time for restoring an inoperable instrumentation channel for the auxiliary feedwater pump (AFWP) suction transfer function on low pressure. The proposed TS change would specify 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for restoration of an inoperable AFW actuation instrumentation channel plus an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after declaring an associated AFW pump inoperable before going to mode 3. The staff finds this unacceptable because the ITS permits only 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for an inoperable instrument channel to be restored before going to mode 3. As a separate action, the ITS specifies 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for restoration of an inoperable AFW pump. The actions associated with an inoperable instrumentation channel and an inoperable AFW pump are not combined in the ITS or in the current Byron and Braidwood TS. As justification for the above proposed TS changes, the licensee stated " Typically, it is inapproprime for one train of actuation instrumentation to require a shutdown in a shorter completion time than if the component is inoperable." The staff finds thisjustification to be inadequate in that instrumentation restoration action times are typically shorter than associated component action times and no basis for the proposed new action is provided.
Comment: Provide additionaljustification for the proposed change.
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. Response to NRC RAI Dated 01/16/98 Comed Response to Issue Revised Response: Comed withdrew this Beyond Scope change and adopted Current Licensing Basis. This change was provided in our ITS Section 3.3 submittal Revision E. !
l Original Response: No change. CTS Table 3.3-3 (Functional Unit 6g) Action 15a requires l declaring the associated AF pump inoperable immediately whenever an ESFAS channel for "AF 1 Pump Suction Transfer on Suction Pressure-Low" is inoperable. ITS LCO 3.3.2 (Functional Unit 6f) Condition M is proposed as the appropriate action requirements associated with this Function. ITS Condition M is proposed with a Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to restore a single inoperable channel of the "AF Pump Suction Transfer on Suction Pressure-Low" Function. If restoration of the instrument channel is not completed in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, Condition N is entered and the AF train is immediately declared inoperable. In accordance with ITS LCO 3.7.5, " Auxiliary ,
Feedwater System," a Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for restoring the AF train to l operable status. This is consistent with CTS 3.3.2, Table 3.3-3, Functional Unit 6g and Action 15a. As stated in DOC 3.3-L7, it is inappropriate for one train of the actuation instrumentation to require a shutdown in a shorter Completion Time than if the component is inoperable. The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time for restoration of the instrumentation channel is considered appropriate due to: 1) the capability of the channel on the operable ESFAS train to actuate a suction transfer on the unaffected AF train,2) the fact that the preferred source (i.e., the CST) is available and aligned, and monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,3) the capability of manually realigning the AF pump ,
suction to the Essential Service Water System from the Main Control Room, and 4) the l availability in the Main Control Room of a low suction pressure alarm from the operable channel, a CST low level alarm, CST level indication, and other instrumentation to alert the Operator during this interval. Comed continues to pursue this change.
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l Response to NRC RAI Dated 01/16/98 1
NRC RAI Number NRC Issued Date RAI Status i BYS 5.0 1/16/98 Open - Comed Action Required NRC Description ofIssue
! DOC M.15 JFD P.3 l l ITS SR 3.4.1.4 Note CTS SR 4.2.3.5
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l The Surveillance Frequency Note not requiring verification of the measured RCS total flow (by l performance of a precision calorimetric heat balance) is increased to 7 days after reaching 2 90% !
L RTP. Although the current plant TS do not specify a time limit for this calibration, they do j l require the RCS total flow rate to be determined by precision heat balance measurement prior to l completion of physics tests. In addition, the STS specify a 24-hour time interval once 90% RTP
- is reached. Since the 7 day frequency has previously been approved for Vogtle, it appears that ;
I this proposed change is generic and should be requested and justified through the WOG as a 1 generic change to the WOG STS. Therefore,it is not approved as a plant-specific change at this time.
Comment: Revise the submittal to adapt the STS.
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/ Response to NRC RAI Dated 01/16/98 Comed Response to Issue Revised Response: Byron and Braidwood's Current Licensing Basis (CLB) does not require a time' limit for completing the precision calorimetric heat balance. The measurement is completed prior to the completion of Physics Testing, during the initial ascent to full power. Current requirements verify that the measurement instrumentation is calibrated within 7 days prior to the performance of the calorimetric. The performance of the calorimetric is done as close to full power as possible to get a more accurate indication of reactor power. Comed performs this measurement at 98% Rated Thermal Power (RTP). If there are any unexpected delays in the ascent from 90% to 98% RTP, the more restrictive completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the surveillance could be missed and could result in an unnecessary issuance of an LER. The calorimetric test is performed every eighteen months during the initial ramp to 100% RTP.
Initial setup time of the measurement equipment takes approximately two days and performance of the test about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.' Since this parameter does not normally change significantly, there is no l
need to perform this test in the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 90% RTP. During the performance of the last two precision calorimetric heat balances, there was only a 0.2% and a 0.43% deviation between the actual precision heat balance measurements and the computer calculations, with both measurements finding the computer reading to be higher than the actual calorimetric heat balance
- measurement. Several other utilities have also included this change in their ITS submittals, l which was originally submitted to WOG by Byron /Braidwood as WOG-99 and has been under review by the NRC as TSTF-282 since May 29,1998. Comed continues to pursue this change which is still more conservative than our CLB.
Original Response: No change. The NRC has previously approved the 7-day Frequency for SR 3.4.1.4 for Vogtle, Ginna, and Zion on a plant specific basis. In addition, several other utilities have also included this change in their ITS submittals. This change was originally submitted by Byron /Braidwood and approved by the Westinghouse Owner's Group (WOG) as WOG-99, and has been under TSTF review since November 19,1996. Comed continues to pursue this change.
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Response to NRC RAI Dated 01/16/98 NRC RAI Number NRC Issued Date RAI Status l BYS 6.0 1/16/98 Closed 1
i NRC Description ofissue l DOC L.28 l JFD P.44 )
ITS LCO 3.4.3 !
CTS LCO 3.4.9.1 )
The proposed change, Pfr Limits Action for P/T limits, would require placing the unit in mode 5 rather than in mode 5 with RCS pressure < 500 psig. Keeping the RCS pressure < 500 psig at RCS~ temp of 200*F is essential to maintaining Pfr limits. The current Byron TS require this condition be achieved in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and the ITS allows 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. This is already a relaxation in ;
action time. To further delay the RCS pressure reduction will increase risk. Also there is the possibility that Action C may not be entered if Action B.2 is completed, i.e., when the RCS temperature is s 200 F but the RCS pressure is still > 500 psig. Therefore, there is no requirement to immediately go into Action C to restore the parameters to s 500 psig. Therefore, this change is unacceptable.
1 Comment: Revise the submittal to retain the 500 psig RCS pressure requirement.
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.' Response to NRC RAI Deed 01/16/98 Comed Response to Issue l
No change. Comed agrees with the NRC statement, " . . there is the possibility that Action C l may not be entered if Action B.2 is completed, i.e., when the RCS temperature is less than or l equal to 200 F but the RCS pressure is still greater than or equal to 500 psig." The Byron /Braidwood P/F limits curves in the PTLR may not necessarily require RCS pressure to be less than or equal to 500 psig to be within acceptable limits, as is currently the case for the Byron /Braidwood P/T limits curves at 200 F. Therefore, Condition C may not be applicable.
l Entry into Condition C is MODE dependent. Whenever the Unit is less than or equal to 200 F
! (i.e., MODE 5) and the pressure and temperature (P/T) limits are not restored, ITS Condition C must be entered. Upon entry into MODE 5 with the P/r limits still not restored (i.e., regardless of whether RCS pressure is above or below 500 psig), Condition C is applicable and must be
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entered to restore RCS pressure and temperature to within the P/T limits. In addition, the entry conditions for Condition A (unit in MODE 1,2,3, or 4), and therefore, Condition B (Required Action and associated Completion Time of A not met), are no longer applicable based on entry into MODE 5 (provided Required Action A.2 has been completed), and Conditions A and B are I exited. Specifying any MODE 5 actions in Conditions A or B is technically incorrect and against the ITS rules of usage since once the Unit reaches MODE 5, these Conditions are exited. With the changes proposed by Comed, it is clear that when the Unit is in MODES 1,2,3, or 4, only Conditions A and B apply. When the Unit is in any MODES other than MODES 1,2,3, or 4, Condition C applies. Under the requirements of the NUREG, given the situation with RCS pressure greater than or equal to 500 psig in MODE 5 and the P/T limits not restored Conditions B and C would both apply. This would lead to confusion for the Operator since the Required
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Actions are different. Furthermore, the Operator is to follow Required Actions for a Condition l for which the entry Conditions no longer are applicable. Comed believes this to be a " broke" in the NUREG, created in the conversion from CTS to ITS. Comed disagrees with the staffs statement,"The current Byron TS require this condition be achieved in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and the ITS allows 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. This is already a relaxation in action time." Both the Byron and Braidwood CTS contain actions to restore the RCS pressure and temperature to within limits in 30 minutes,
! or be in hot standby (MODE 3) in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature to less than <
l 200 F (MODE 5) within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. These same requirements are contained in ITS as Required Actions (RA) A.1 (Restore to within limits in 30 minutes), B.1 (Be in MODE 3 in 6 l hours), and B.2 (Be in MODE 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />). Comed continues to pursue this change.
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. Response to NRC RAI Dated 01/16/98 !
I NRC RAI Number. NRC Issued Date RAI Status !
BYS 8.0 1/16/98 Open - Comed Action Required NRC Description ofIssue 1 DOC L.14 l JFD P.4
- ITS SR 3.4.18.2
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CTS SR 4.4.1.5.2.2 1
- The Surveillance Frequency is proposed to be changed from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for verifying boron concentration prior to opening an isolation valve in an isolated loop. Thejustification given for this proposed change cites the amount of time to sample and confirm the concentration results. However, the Surveillance Frequency does not define the amount of time for sampling but merely the time the Surveillance should be completed prior to opening either the hot or cold i leg isolation valve. Operating experience has shown that completing this Surveillance within 2
, hours of opening an isolation valve provides reasonable assurance that the boron concentration difference will remain within acceptable limits until the loop is unisolated. This has not been !
justified for the longer time period and therefore we do not find the proposed change l
acceptable.
Comment: Revise the submittal to retain the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance frequently.
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1 Response to NRC RAI Dated 01/16/98 i
Comed Response to Issue l ,
Revised Response: Comed continues to pursue changing two hours to four hours in ITS SR 3.4.18.2 for verifying boron concentration of the isolated loop due to the difficulty in meeting the current sampling frequency. The Chemistry Department currently has difficulty collecting the RCS sample of the isolated loop from inside containment, transporting the sample to the lab, performing the analysis, and informing the control room management of the results prior to the expiration of the two-hour time limit. For the unisolated loop, in order to meet the prerequisite sample line purge time, it takes approximately one hour to collect the RCS sample from the High Radiation Sample System and transfer it to the laboratory, and another 30 minutes to analyze the sample. After verification of th: sample results, the Chemistry Department must notify the Operations personnel of the results. Due to the short amount of time left to perform the operation of stroking open the LSIVs, the two-hour time frame may expire due to other activities ongoing in the control room. This would then delay returning the unit to power operations due to the requirement to perform another sample prior to opening the LSIVs and unisolating the loop. The increased time allowance of four hours would reduce the concern in restoring an isolated RCS ;
loop and would prevent unnecessary delays. In addition, once an RCS loop is filled there is no i possible dilution path. Two 2" loop drains penetrate the isolated portion of the RCS loop, and l neither of these lines are possible dilution sources to the isolated loop. Comed continues to l pursue changing two hours to four hours in ITS SR 3.4.18.2 for verifying boron concentration of the isolated loop. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal Revision K upon NRC's concurrence with the Comed Responses to the ITS Beyond Scope RAI.
Original Response: Comed will revise ITS SR 3.4.18.2 to retain the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Surveillance l Frequency. This change will be provided in our comprehensive ITS Section 3.4 closeout i submittal revision upon NRC's concurrence with the Comed Responses to the ITS Beyond Scope RAI.
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