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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
BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999
Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle
ML20210U8031999-08-0404 August 1999
Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program
ML20210M9131999-08-0202 August 1999
Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed
ML20210K0771999-07-30030 July 1999
Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46
ML20210K9761999-07-30030 July 1999
Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant
ML20210G6291999-07-29029 July 1999
Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy
ML20210J8951999-07-29029 July 1999
Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal..
BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999
Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr
ML20210E2151999-07-23023 July 1999
Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition
ML20216D3781999-07-21021 July 1999
Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA
ML20210C3961999-07-20020 July 1999
Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA
ML20216D7061999-07-19019 July 1999
Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21
BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999
Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7
ML20209H2991999-07-16016 July 1999
Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl
ML20210A3151999-07-16016 July 1999
Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations
ML20210B7071999-07-16016 July 1999
Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7)
IR 05000456/19993011999-07-15015 July 1999
Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams
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
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
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
[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
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
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
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
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
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
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
ML20055H7631990-07-25025 July 1990
Forwards Financial Info Re Decommissioning of Plants
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
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
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
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
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
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
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
ML20043B7771990-05-23023 May 1990
Forwards Endorsement 9 to Nelia & Maelu Certificates N-108 & M-108 & Endorsement 8 to Nelia & Maelu Certificates N-115 & M-115
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
ML20043C2811990-05-15015 May 1990
Responds to NRC 900416 Ltr Re Violations Noted in Insp Repts 50-456/90-09 & 50-457/90-09.Corrective Actions:Gas Partitioners Tested Following Maint During Mar 1990 & Tailgate Training Session Will Be Held
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
ML20042F6771990-05-0303 May 1990
Advises NRC of Util Plans Re Facility Cycle 2 Reload Core. Plant Cycle 2 Reload Design,Including Development of Core Operating Limits Has Been Generated by Util Using NRC Approved Methodology,Per WCAP-9272-P-A
ML20055C5761990-04-30030 April 1990
Forwards Results of Investigation in Response to Allegation RIII-90-A-0011 Re Fitness for Duty.W/O Encl
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
ML20042E9601990-04-30030 April 1990
Forwards Response to NRC 900327 Ltr 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.
ML20042F2681990-04-18018 April 1990
Provides Supplemental Response to Violation Noted in Insp Repts 50-456/89-21 & 50-457/89-21 Re Safeguards Info.Util Request Extension of 891010 Commitment Re Reviews of Plants. List of Corrective Actions Will Be Submitted by 900601
ML20042F0241990-03-28028 March 1990
Forwards Part 3 of 1989 Operating Rept.W/O Rept
ML20012D8671990-03-21021 March 1990
Reissued 900216 Ltr,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date
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
1990-09-17
[Table view] |
Text
( - - - . . -- --
.,' Commonwrith Edison
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'fM# 72 v West Adams Street, Chicago, Illinois .
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- j l g'V Chcago, Illinois 60690 0767J. Kddress Rippli to
- Post Office BM
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July 27, 1989 Director of Nuclear Reactor Regulation US Nuclear Regulatory Commission j Mail Station P1-137 1 Washington, DC 20555- ')
Subject:
' Byron /Braidwood Simulator Facility Response to Request for Additional Information '
NRC Docket'Nos. 50-454, 455. 456. and 457
Reference:
'May 26, 1989 letter from S.P. Sands to T.J. Kovach Gentlemen 1 l
Our submittal of October 7, 1988 provided information pursuant to 1
-10 CFR 55.45.b.5 in order to attain Certification of the Braidwood Simulation l Facility. Your review'of our submittal indicated the need_for additional information in order to ensure the completeness of the documentation associated with the certification. process. Your request for additional
-information was transmitted to us by the letter indicated in the above' ,
reference. Our response to your request is provided in the Attachment'to this I letter.
Each of the seventeen questions contained in your Enclosure was addressed by the Simulator Review Board. This Board is composed of members with responsibilities in the areas of Simulator Configuration Management .j Control and Simulator Fidelity. In addition, the Board included the Siinulator .
]
Training Supervisor and Senior Reactor Operator representatives from both l Byron and Braidwood Stations. j
.i l
The responses to the questions in your request are supported by seventeen additional Attachments. One copy of these Attachments is being provided at this time. Please advise us if you require additional copies of this material.
Please forward any questions that you may have regarding this matter to this office. 1 j
very truly yours,
/ !
i G.E. Trzyna Nuclear Licensing Administrator ,
i
/scJ 0222T 1 Att.
cc A.B. Davis-w/o Att.'s 00 S.P. Sands-w/o Att.'s I
'I l 1 8908020210 890727 3 PDR ADOCK 05000454 .i
- p. PDC l
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _J
BRAIDWOOD SIMULATOR CERTIFICATION l- .
RESPONSE TO NRC QUESTIONS w
l 11 ATTACHMENTS
- 1. Normal Operations Test Abstract (NO-1) 1
- 2. Real Time Test Abstract (RT-1)
- 3. Valve Stroke Time Test Abstract (ST-1)
- 4. Surveillance Test Abstract (SV-1)
- 5. Malfunction Tests Abstract / Initial Conditions
- 6. Simulator Tasting Program Procedure
- 7. Dyron Units 1/2 Control Room Layout
- 8. Braidwood Units 1/2 Control Room Layout
- 9. Simulator Control Room Layout
- 10. Revised Panels / Equipment Listing
- 11. Transient Tests Baseline Data
- 12. Rx Trip /SI Procedure - Braidwood Unit 1
- 13. Rx Trip /SI Procedure - Braidwood Unit 2
- 14. Rx Trip /SI Procedure - Byron Unit 1
- 15. Rx Trip /SI Procedure - Byron Unit 2
- 16. Braidwood Procedure Generation Package
- 17. Steady State Test (SS-1) 0222T:2
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ -. __ J
JOusation;1:j Your submittal includsd performance. test abstracts only for' steady state l tests.atl30%,i SO%, 75%, and 100% power and the' ten ANSI /ANS-3.5-1985,
[.. Appendix B transient' tests. Regulatory Guide 1.149 explains that the performance testing to be performed is that' described 'in ANSI /ANS-3.5-1985,' Section 5.4, " Simulator Testing." This section states that the' simulator's performance shall be compared to the requirements of Section 4, " Performance Criteria." Section 4' requires tests for the limiting cases of the evolutions in Sections 3.1.1, " Normal Plant Evolutions,'? and 3.1.2, ." Plant Malfunctions." Tests demonstrating-compliance with-the criteria-of Section 4.3, "S3mulator Operating Limits,"
are also required. Please. provide; performance tests abstracts for these additional tests or provide justification for. exception to the s
requirements'for these tests.
Response 1:
Per your request, Attachments 1-5 are test abstracts for " Normal Plant Evolutior.s", " Plant Malfunctions", and " Simulator Operating Limits".
Attachment 6 describes the administration of'the simulator testing program.
Question 2:
Regarding DR #3 in Attachment A to Form 474; please explain why the simulator and station performed their tests at different core ages'(1.e.
why not initialize the simulator to the same core age as that'for which the data exists)?
Response'2 l
l' The Simulator Review Board has concluded that the steady state test and analysis are valid,as performed. The simulator performed steady state L testing using beginning-of-life (BOL) initial conditions. The simulator BOL initial conditions were not the same core Ege as the. station when it performed its steady state testing. The simulator's boron concentration does not detract from training and'it is not cost-effective to change the simulator's core model in order to change'its core age (boron concentration).
Question 3:
Regarding DR #7 in Attachment A to Form 474; please provide justification for use of this valve stroke time criteria. Include in this justification an explanation of whether the criteria of ANSI /ANS-3.5-1985, Section 4.2,
" Transient Operation," are met. Of particular concern are automatically p actuated valves with stroke times of less than 20 seconds.
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, iRasponsaL33 .c ,
b.
1
'IANSI/ANS-3.5-1985, Saction 4.2'critoria are mat. Section 4.11critoria has.
been modified for valve stroke times less than twenty' seconds. The p . . acceptance' criteria for each valve's stroke time is 1-10% of the reference
. plant valve's stroke: time. However, 1 10% of most: valve's stroke time would yield a small tolerance which does not lend itself' to enhanced Loperatoritraining'due'to the fact that the: operator is but directly af fected: by a difference 'in valve stroke time of a f as seconds.
a ,
In response to the 6o-ential problem of changing most valve's stroke. time to that of Braidwoon , our tolerance was changed to 310% or 12 seconds, whichever is greater as long as Braidwood acceptance criteria is not violated. A biennial comparison of Braidwood Unit I valve stroke times to the. simulator valve stroke times will be performed to ensure that the revised valve stroke time critoria will be mainte.'ned. 'See Attachment 3' for a copy of the valve stroke time' test (ST-1). This minor' change in the criteria will not detract.from operator training.
Question 4:
' Item'9, on page 10c/5 in the " Simulator Information" portion of your submittal states lthat the plant computer is not. fully modeled.
ANSI /ANS-3.5-1985, Section 3.2.2,." Controls on Panels," requires "... plant computer interface hardware and other components or displays-that would function during normal, abnormal, and emergency evolutions shall be included in'the simulator." Please confirm that this criteria is met even though the plant computer is not fully modeled or provide justification for' exception.
Response 4:
The in-plant computer possesses sufficient modeling for the operators to review ~che necessary data for the normal, abnormal, and emergency evolutions required by ANSI /ANS-3'.5-1985. Full modeling of the Braidwood in-plant computer will be completed after SUN Computer installation.
Differences exist'between the Byron computer hardware and the simulator computer hardware, however, these differences will not adversely impact training.
i 0222T:4
Ou:stion 5:
Ragarding Saction A.1.2.2, " Pan'als/Equipmant," in the " Simulator
'Information" portion of your submittal; it is difficult to determine the
. scope of your panel and equipment simulation as compared to anch of the units'for which you are certifying the simulator. ANSI /ANS-3.5-1985, l Section 3.2.1, " Degree of Panel Simulation," requires that the simulator contain sufficient operational panels to provide the controls, instrumentation, alarms, and other man-machine interfaces to conduct the j normal plant evolutions of 3.1.1 and respond to the malfunctions of 3.1.2. Please confirm that the Braidwood Unit 1 simulator meets these criteria for Braidwood Units 1 &- 2 and Byron Units 1 & 2. Floor plan sketches,-including full panel names, of the simulator and each of the plant control rooms would be helpful. Any differences which preclude operations required by 3.1.1 or 3.1.2 of ANSI /ANS-3.5-1985 should be noted as exceptions and justifications should be provided.
Response 5:
The Braidwood Simulator contains sufficient operational panels to provide the controls, instrumentation, alarms, and other man-machine interfaces to conduct normal plant evolutions of 3.1.1 and respond tc the malfunctions of 3.1.2 for each of the Braidwood and Byron Units to the extent identified in the certification Report. Attachments 7-9 are control room layouts of Byron Units 1/2, Braidwood Units 1/2, and the simulator.
Attachment 10 is a revised listing (page 10c/5 of the Certification Report) of the simulator's Panels / Equipment.
Question 6:
ANSI /ANS-3.5-1985, Section 3.3.1, " Systems Controlled from the Control Room," requires the inclusion of systems and the degree of simulation to be to the extent necessary to perform the normal plant evolutions in 3.1.1 and respond to the n malfunctions in 3.1.2. Items 4,7,8,9 and 10 under A.1.2.2, " Panels / Equipment," and section A.I.2.3, " Systems," in the
" Simulator Information" portion of your submittal, would appear to indicate that the criteria of 3.3.1 of ANSI /ANS-3.5-1985 may not be met in all cases. Any discrepancies which preclude operations required by 3.1.1 or 3.1.2 of ANSI /ANS-3.5-1985, for any of the four units, should be noted as exceptions and justification should be provided.
Response 6:
The minor differences in the Essential Service Water System, Circulating Water System, and Suitchyard/ Electrical Bus nomenclature between the Byron Units and the simulator do not detract from training. In addition, these differences do not impact on the ability to perform the normal plant evolutions in 3.1.1 or respond to the malfunctions in 3.1.2. Most of the tasks related to these differences are minor in nature and are handled administrative 1y.
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Raspon33.6 (Con't) ' s The systems.that are not modelsd'(Saction A.1.2.3 offths Certification
~ "
g Report) do notidetract'from training. The tasks related to-these systems
- f. ;are handled administrative 1y to ensure procedural compliance is
~
maintained. The Turbine-Generator Temperature Monitoring System, Fire Protection Detection System,'and Radiation Monitors (RM-23's)'are located Joutsidelthe normal operating area. In' addition, these non-modeled systems
'do not impact on the ability to perform the normal plant evolutions in L
.3.1.1 or respond to the malfunctions in 3.1~.2. The Equipment Status
} Display (ESD)~ is located inside the normal operating area 'and is considered' visually simulated hardware until SUN Computer installation.
Question 7:
Regarding item 6 " der A.l.2.2, " Panels / Equipment," in the " Simulator Information" portron of your submittal; it appears that you-are utilizing-
-an operator a10 the sinulator which does not exist in the plant. For examination purpt.an, operator aids which are not used in the plant should
~
not be used in thel simulator. Please describe your intentions in this regard.
Response 7:
Operator aids are not used in the simulator unless they are approved for use in the plant. Item 6 of'A.1.2.2 did not intend to imply that meter sideplates were operator aids. However, since the submittal of the Certification Report, ,a Computer-Aided-Drafting System has been developed which can replicate the meter sideplates currently installed at the station. . Work Requests have been written for changing the simulator's meter sideplates to match the plant's meter sideplates. Estimated completion date is January 1, 1990.
Question 8:
Regarding item 18 under A.1.2.2, " Panels / Equipment," in the "Simulat or Information" portion of your submittal; please provide justification for the acceptability'of the failure of'the recorder paper drives to deenergize upon a loss of power to the chart recorders.
Response 8:
The Simulator Review Board has determined that negative training does not occur with the chart drive motors being continuously driven. The chart drive motors are continuously driven to minimize maintenance upkeep. If the chart drive motors are deenergized for a long period of time (i.e.,
weekend / loss of power), the recorder pens become dryed out/ clogged due to a loss of capillary flow and extensive maintenance work would then be required to restore the recorder pens to operable status. Dyron and Braidwood Stations are considering a change to felt-tip pens. If this change occurs, we will reevaluate our position on this matter.
0222T:6
Ra:ponso'8_(Con't):
Static simulator exams on a frozen simulator can be successfully accomplished by deenergizing each chart recorder by its "on-off" switch.
Question 9 ANSI /ANS-3.5-1985, Section 3.2.3, " Control Room Environment", requires communication systems that a control room operator would use to communicate with an' auxiliary operator or other support activities to be operational to the extent that the simulator instructor, when performing these remote activities, shall be able to communicate over the appropriate communication system. Please provide-justification for the lack of sound powered phone jacks and the lack of simulation of the plant's radio system.
Response 9: ,
The lack of sound-powered phone jacks does not detract from training since sound-powered phones are normally used for maintenance activities in the plant.
The lack of a simulated plant radio system does not detract f rom training since the page'and telephone systems adequately address communications outside the control room.
Question 10:
It is not clear that simulator design data updating and simulator modifications will be performed in accordance with the time frames of ANSI /ANS-3.5-1985, Section 5.2, " Simulator Update Design Data," and 5.3
" Simulator Modifications." Please confirm that these criteria are met or provide justification for exception. Also, please provide a schedule for the planned corrections listed on page 10c/10 of A.1.2.2 of your submittal and for installation of the SUN computer.
Response 10:
The simulator update and modification program meets the requirements of ANSI /ANS-3.5-1985, Sections 5.2 and 5.3. See Attachment 6, Section 3.k.
The status of the items listed on page 10c/10 are listed belows
- Difference #2 (PI-403/405A meter scales), #12 (FW-9 valve operation),
813 (RCFC vibration moniters) and #17 (turbine audio block circuit) ,
i have already been corrected.
- Difference #14 (SPDS subcooling/ lou setpoints) will be corrected upon SUN computer installation. Eatimated completion date for SUN Computer installation is November, 1990.
1 0222T:7
.p
.Qupstion 112 ,
' i Ws Ti DANSI/ANS-3.5-19'85,- Section 3.4.1,:" Initial. Conditions," rsquires initial
' ' conditions to-include.various times in core life. The set of initial
, i ! conditions provided with your certification does not include any
, end-of-life (EOL). conditions. Please provide justification for the-lack.
} of such, initial conditions.
y I
- Response lit.
The' list of initial conditions (IC's). incorrectly;11sted.IC-26,:28-30 as beginning-of-lifeL(BOL), initial conditions. IC-26,-28-30 are end-of-lifo
.(EOL). initial conditions. See Attachment 5 for the list'of initial-L conditions.
s.
LQuestion 12: I 10 CFR.55.45(b)('5)(vi) r+ quires "...the conduct of approximately 25 percent of the performance testa per year for the subsequent four years" following any certification report. However,'your " Proposed' Simulator
. Malfunction Testing -Schedule" indicates that you intend to perform 33
. percent of the testing in the fourth. year. It is recommended that you revise'your schedule-to more nearly perform 25. percent per year. Please provide a revised schedule.or provide jur.tification for not doing so.
( Response 12:
A revised simulator testing schedule for.the four years of fpost-certification malfunction testing is listed in Attachment B of Attachment 6. 'Please note that a new malfunction (AUX-17) hasibeen added to the malfunction testing schedule. Each year of malfunction testing contains 25% 12.5% of the total malfunctions required to be tested.
Please note that Attachment C of Attachment 6 contains non-certified' a malfunctions that are currently used to enhance operator training.
. Question 13:
NUREG-1258 states, "it is essential, for the conduct of a license examination,.that the simulation facility permit a candidate to' mitigate
.the consequences of an event using the reference plant's Umergency Operating Procedures (EOPs). It must also be possible for the candidate
,to employ the reference plant's normal and abnormal operating procedures as required." Regarding Attachment 1, " Reg. Guide 1.149 Requirements for Dual Plant Simulation Facility," to Form 474, pages 11c/119 and 11c/120; please ' provide justification for not using the Unit 2 training disc for abnormal operations or casualty training, and for not maintaining Unit 2 abnormal and emergency procedures for the simulator.
l l-
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0222T:8
R2sponta 13:
Sinco Unit l'and Unit 2 are almost idantical, except for the steam l
generator model (the differences are listed on pages 11c/119-120 of the
,- Certification Report), adequate Unit 2 training is conducted by
, concentrating on low-power operations (i.e., startups, shutoowns, abnormal and casualty operations up to 30%) by using the Unit 2 training disc. The l Unit 1 disc correctly simulates plant response for both units above 30%.
Since the' submittal of the Certification Report, abnormal operations and casualty training have been conducted on the Unit 2 training disc.
Unit 2 abnormal and emergency procedures are not maintained in the simulator since the Unit I abnormal and emergency procedures are utilized for Unit 2 abnormal operations and casualty training. The Unit 2 abnormal ano. emergency procedures are developed from Unit 1 abnormal and emergency-procedures and are almost identical as shown by the "Rx Trip /SI Procedure" in Attachments 12-15 for each of the four units (Units 1/2 for Byron and Braidwood). Byron and Braidwood emergency procedures are validated on the simulator. Attachment 16, page 3 of 50 states that commonality between Byron and Braidwood Stations allow the reference validation method to provide validation of the other three units emergency procedures. In addition, page 4 of 9 (section 6.3) discusses the step-by-step review of the individual Braidwood and Byron emergency procedure revisions to ensure consistency of information between each of the four units. Attachment 16 also contains setpoint documentation sheets that are utilized for Units 1/2 emergency procedure setpoints. The only setpoint deviations between Units 1/2 are on pages 62, 65 and 67 for the no-load S/G 1evel and the HI-2 S/G 1evel setpoints.
The NRC has successfully completed Unit 2 examinations on the simulator for both stations. The Braidwood exam was September, 1987 and the Byron exam was September, 1986.
Question 14:
Regarding Attachment 2, " Annual Steady / Transient Test Results," Test Number SS-1, Objectives 2 and 3; the 2% and 10% criteria for critical and non-critical parameters, respectively, do not necessarily detormine whether something detracts from training. The criterion, "shall not detract from training," is an additional, more strict, performance criterion. Please confirm that the differences were determined not to detract from training in addition to meeting the 2% and 10% criteria or provide justification for exception to this requirement.
l 0222T:9 i,
Rasponse.14 :
_4
~73 Steady stateltest (SS-1) has been revised to. ensure that tha"2 2%/310%
l '
criteria and.the "does not detract from training" criteria are separate p requirements., Steady state test results for 1988 and 1989 have been.
v'erified to trieet the above criteria. .See Attachment 17 for the revised steady. state' test.(SS-1).
l4 i' Question 15:
Regarding the transient tests included in Attachment 2 to Form 474; please provide the baseline' graphs.against which the' simulator graphs may be
., compared. If such graphs are not available please provide a e.escription l" of the baseline data used to determine. fidelity to the. reference plant.
If.the baseline' data used was the judgement of a panel'of' experts, then documentation of their review, sufficient for a third party to evaluate the adequacy of the tests and results, should be included. This.
documentation should include such items as the makeup and qualifications of.the panel and any differing professional opinions as to the outcome of the tests.
Response 152-The baseline data was developed using either plant data, where available,-
l ,or_the; judgement of a Transient Test Baseline Data Review Board.
L Attachment 11 includes the makeup and qualifications of the review board.
Land the'results of each test' review.
. Question 16:
, ANSI /ANS-3.5-1985,- Appendix B, D.2.2(7) requires a transient performance L test of a maximum rate power ramp from approximately 100%_down to approximately 75% and back up to 100% a 25% power change in each
' direction. However,-in Test Numoer TR-7, " Maximum Rate _ Power Ramp" you only' performed a 10% load. swing from-96% to approximately 88%. -Please provide justification for performing this test other than as described in
-ANSI /ANS-3.5-1985.
Response 36:
^
ANSI /ANS-3.5-1985, Section 5.4.2, Simulator Operability Testing, (footnote
- 3) recommends substitution of Appendix B transient tests if these tests provide a more representative comparison to actual or predicted reference plant per:formance. In accordance with this recommendation, Braidwood Startup Test (BwSU NR-36), 10% Turbine Load Change, was substituted for U the trpendix B, Section B.2.2(7) maximum rate power ramp test.
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0222T 10
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Ousstion 17:-
In Examination Raports dated May 20, 1987 and June 17, 1987 it was noted ;
that the simulator instrumentation drifted while in freeze. This may have 1 an impact on future examinations in which candidates are asked questions related to a " frozen" simulator. Please indicate whether you have-corrected this problem. If not, please provide a schedule for ccrrecting it or justification for not correcting it.
Response 17:
Thr simulator instrumentation drif t problem has been corrected.
Fluctuating power supplies were responsible for the drifting q instrumentation noted during the May, 1987 and June, 1987 examinations.
Af ter the power supplies were replaced, numerous " frozen" simulator exams have been administered including an April, 1989 NRC " frozen / static" simulator examination. No recurring problems were noted.
i 0222T:11
_ - _ _ _ - -