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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) 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 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 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 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 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 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 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 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) 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 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 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 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 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 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 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) 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 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 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 ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle 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 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 ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff 05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999 Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below 05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999 Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations 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 ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative 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 ML20195F3231999-06-0909 June 1999 Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration 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 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 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 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl 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 05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999 Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below 05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999 Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations 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 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 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 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 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 ML20206E3991999-04-29029 April 1999 Forwards 1998 Annual Environ Operating Rept & Listed Attachments Included in Rept.Without Encls ML20206C7901999-04-23023 April 1999 Provides Suppl Info Re Use of W Dynamic Rod Worth Measurement Technique,As Requested During 990413 Telcon.Rev Bars in right-hand Margin Identify Changes from Info Submitted by ML20206B3941999-04-21021 April 1999 Forwards Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors, for Byron & Braidwood Stations.Updated Info Re PCT for Limiting Small Break & Large Break LOCA Analysis Evaluations & Detailed Description of Errors ML20205S9621999-04-20020 April 1999 Responds to 981203 RAI Telcon Re SG Tube Rupture Analysis for Byron Station,Unit 2 & Braidwood Station,Unit 2.Addl Info & Subsequent Resolution of Issues Discussed During 990211 Telcon Are Documented in Encl ML20206B0821999-04-20020 April 1999 Requests to Reschedule Breaker Maint Insp for Either Wk of 990607 or One of Last Two Wks in Jul 1999,in Order to Better Accommodate Insp Activity ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20206B0251999-04-14014 April 1999 Forwards Reg Guide 1.16 Rept for Number of Personnel & Person-Rem by Work Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions ML20205K3581999-04-0606 April 1999 Submits Request to Reschedule Breaker Maint Insp for Braidwood Nuclear Power Station for Either Wk of 990607 or One of Last Two Wks in Jul 1999 ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20210C7181999-03-30030 March 1999 Forwards Integrated Exam Outline Which Plant Submitting for Review,Comment & Approval for Initial License Exam Scheduled for Wk of 990607 ML20205E6401999-03-26026 March 1999 Forwards Proprietary Ltr Re Notification of Corrected Dose Rept for One Individual,Per 1997 Annual Dose Repts for All Comed Nuclear Power Facilities,Submitted 970430.Proprietary Info Withheld ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207J4321999-03-0808 March 1999 Forwards Braidwood Station ISI Outage Rept for A1R07, Per Requirements of ASME Section Xi,Article IWA-6200 ML20205C6861999-03-0404 March 1999 Provides Notification That Byron Station Implemented ITS on 990205 & Braidwood Station Implemented ITS on 990219 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 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 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 ML20059A3991990-08-15015 August 1990 Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp Program 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 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 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 ML20044B1411990-07-12012 July 1990 Forwards Addl B&W Rept 77-1159832-00 to Facilitate Completion of Reviews & Closeout of Pressurized Thermal Shock Issue,Per NRC Request ML20044B2141990-07-11011 July 1990 Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification 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 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 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 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 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 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 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 ML20042G4641990-03-20020 March 1990 Responds to NRC 900216 Ltr Re Violations Noted in Insp Repts 50-456/90-02 & 50-457/90-02.Corrective Actions:Existing safety-related Temporary Alterations Will Be Reviewed to Determine Which Alterations Include Installation of Parts ML20012D8711990-03-19019 March 1990 Forwards Corrected No Significant Hazards Consideration to 890814 Application for Amends to Licenses NPF-72 & NPF-77 ML20012C0861990-03-14014 March 1990 Forwards Response to Insp Repts 50-456/90-03 & 50-457/90-03 on 900122-26.Encl Withheld (Ref 10CFR73.21) ML20012E9221990-03-13013 March 1990 Forwards Final Version of Action Plan for post-accident Sample Sys QC Program,Per Insp Repts 50-456/90-05 & 50-457/90-05 ML20012C5471990-03-12012 March 1990 Provides Results of Completed Util Reviews & Addresses Addl Info Requested by NRC Re 890317 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 to Change Tech Spec 4.5.2,supplemented on 890825 & 890925-27 Meetings ML20012C5061990-03-12012 March 1990 Forwards Braidwood Nuclear Station Unit 1 Inservice Insp Summary Rept,Interval 1,Period 1,Outage 1. ML20011F6211990-02-21021 February 1990 Forwards Revised PHOENIX-P/ANC Benchmark Scope to Replace Existing Ark & 2D Codes Used to Perform Neutronic Analyses for PWR Reload Designs.Codes Expected to Be Used in Dec 1990 for Cycle 3 Design Calculations ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20055D4121990-01-29029 January 1990 Forwards Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,For Review ML19354E1741990-01-22022 January 1990 Provides Current Status of Ds Breaker Insps for Plant Following Completion of Recent Unit 1 Refueling Outage & Advises That Remaining Ds Breaker Insps Will Be Completed by End of Upcoming Unit 2 Refueling Outage ML20006D9621990-01-22022 January 1990 Forwards Info Re Invalid Test Failure Experienced on Diesel Generators 1DG01KA & 1DG01KB,per Reg Guide 1.108 ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20011E7391990-01-16016 January 1990 Responds to NRC 891222 Ltr Re Violations Noted in Insp Repts 50-456/89-28 & 50-457/89-27.Corrective Actions:Maint Work Request Procedure Will Be Revised to Clarify Testing Performed within Nuclear Work Request Package ML20006A1641990-01-11011 January 1990 Forwards Info Describing Initial Use of Rod Worth Measurement Using Rod Exchange Technique,Per Sser 2 (NUREG-1002) 1990-09-17
[Table view] |
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m} Commonwealth Edison One Fd National Plaza Chicago, linos Address Repy M: Post Offc2 Box 76,7 Chicago, Enos 60690 0767 November 22, 1988 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory' Commission Washington, DC 20555 Attnt Document Control Desk Subjects Braldwood Station Unit 1 Application for Amendment to I racility Operating License NPF-72 Appendix A, Technical Specifications tiRC_ Docket No.__50-456 Referencet (a) October 26, 1988 S. C. Hunsader letter to T. E. Murley Dear Mr. Murleys
(. In reference (a), pursuant to 10CFR 50.90, Commonwealth Edison
. Edison) proposed to amend Appendix A, Technical Specifications, of racility Operating Licenr.e NPT-72. The proposed amendn;ent requests a change to fechnical Specification 4.8.1.1.2f to extend, on a one-time basis, the previously accepted 31 month surveillance testing requirement for Diesel Generators 1DG01KA and 1DG01KB, for an additional 7 months, until the first refueling outage for Braidwood Station Unit 1, currently scheduled for September, 1989.
The purpose of this letter is to provide additional information that supports what was provided to you in reference (a). Specifically, you will find attached the folicvingt Attachment "A" is the September 285, 1988 Cooper Energy Services Group letter that provides their approval of a one time extension up to 38 months for the 'init 1 Diesei Janerator Technical Specification surveillance.
Attachment "L" is the October 20, 1988 Westinghouse letter that transmitted thelv risked based evaluation performed to support the extension of the Diesel Generator Technical Specification survelliance (teardown inspgetion) from 31 months to 38 months.
Attachment "C" is the November 17, 1988 Cooper Energy Service = Group letter that provides the results of the ENSPEC 3000 Engine Analyser operated on Diesel Generators, 1DG01KA and ID01KB on November 14, and '
17, 1988. As stated in the letter, all operating parametets were wit.hin manuf acturer's specifications.
G311290081 881122 FDR ADOCK 05000456 4 1 1 P PDC ,
_ _ _ _ _ _ _ _ _ - _ _ _ _ _ _J
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In the Safety Evaluation and Evaluation of Significant Hazards Considerations provided with Reference (a) Edison Indicated that the failure histories of 50th diesel generators had been reviewed and trends of abnormal failures had not been identifled. The information provide 3 in Attachment "C" supports that conclusion.
As indicated in reference (a), an expedited NRC review is requested so that the revised Technical Specification can be in piece ptfor to the Braldwood Unit 1 surveillance outage, scheduled to start in early February, i 1989. Associated work packages will need to begin to be prepared soon, prior to the start of the outage. In addition, with Unit 2 surveillances becoming ,
due at the same time, a February, 1909 Unit 1 outage would result in a December, 1988 surveillance outage start for Unit 2. Acceptance of this ,
snendment will allow the Unit 1 surveillance outage to be cancelled and allow for these Technical Specification surveillances to be accomplished during the Braldwood Unit 1 Refueling outage, scheduled to start in early Septenber, i 1999. Also, the extension will allow the Unit 2 surveillance outage to begin in early January, 1989 instead of December, 1988.
Please direct any questions you may have concerning this matter to ,
this office. ,
Very truly yours, S. C. Huns 6 der Nuclear Licensing Administrator l
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Attachments (A): September 26, 1988 Cooper Energy Services Group Letter I (B): October 20, 1988 Westinghouse Letter (C): November 17, 1988 Cooper Energy Services Group Letter cc Resident Inspector - Braidwood l S. P. Sands - NRR Regional Office KIII M. C. Parker - State of Ill.
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9E961 ENEMY SEm4CES QW '
Sepember 26, 1988 l
Comonwes1th Edison Braidwood Nuclear Station !
Rt. 1 Box 84 '
Bracev111e. Illinois 60407 Attention: Mr. Randall , Smith
Dear Mr. Smith:
Referring to Mr. Querio's September 16 1988 letter to G. L. Miller of Energy Services Group requesting an app,roximate thirty-eight (33) month elapsed time since the last full maintenance / inspection surveillance of your 1A and 18 diesal generator sets, which is two (2) months longer than previously agreed to.
On July 31, 1987 Energy Services Group approved a 36 month extension for the 1A and 18 diesel with a mutual agreement that thirteen (13) items of inspection be perfomed and in your September 16, 1988 letter y(Thecheck-listisattachedforyourreview.)ou state that this inspection wa It is my understanding you do trend monitoring of diesel generator operating parameters. I suggest you continue to do so and any significant change is cause to perfor* any or all the thirteen (13) points of inspection again.
Energy Services Group grants approval of a one tirne extension (36 to 38 months) for the 1A and 18 diesels to allow Braidwood to schedule diesel generator inspection with reactor full outage.
Sincerely, hh Glenn L. Miller Service Manager Eastern Regiun
/m Attachment (ThirteenPointInspectionList)
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. i ATTACHMENT g./#
The following items will be perfomed during the Preventative Maintenance Program.
- 1) A review of the Diesel Generator's starting times. operating logs and maintenance history to identify any significant trends of degradation.
- 2) Perfom engine analyzer to monitor peak firing pressures, compression pressures and cyltader vibration.
- 3) Record Turbocharger spindown time.
- 4) Inspect crosshead clearances by verifying freedom of movement.
(Until rocker am issue resolution.)
- 5) Inspect rocker am assemblies for each cylinder without disassembly.
- 6) Adjust intake and exhaust valve tappets for each cylinder.
- 7) Review operating logs for the following filter's differential pressure readings. If differential pressures are rising, inspect and clean filters as necessary.
! a Fuel 011 $ trainers l b Fuel Oil Filters l
c Full Flow Lube Oil Filter d Turbocharger Lube Oil Fitlers
- 8) Inspect and clean as necessary the following filters and strainers:
i a Luba 011 Strainers b Crankcase Breather Filter e Cylinder Head treather Filters d Ate Intake Filtors e Air Start Header Filters f Air Intake Manifolds
- 9) Inspect the fuel contro* linkage.
- 10) Inspect and clean as necessary fuel injector pump metering rods, tl) Inspect and clean as necessary the governer control "bimba" cylinder.
- 12) Inspect local control panel for cleanlinns.
- 13) Perfom engine analyzer to monitor peak firing pressures and cylinder vibration.
'i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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/ ' ,/ J CCE-88-502 Pener Systems Omsv Westinghouse Energy Systems Electric Corporation e ns Pittsburp Pevsytvoa 15230 0355 NS-OPLS-OPL-I-88-422 October 20, 1988 Mr. C. A. Moerke General Design Engineer Byron and Braidwood Stations Corrconwealth Edison Company P.O. Box 767 Chicago, IL 60690 C0f00hVEALTH EDISON COMPANY BRAIIkDOD - UNITS 1 AND 2 DIESEL GENERATOR SURVEILLANCE EXTDJSION
Dear Mr. Moerke:
. This letter transmits the risk based evaluation which has been perforned to support extension of the diesel generator teardown inspection from a 31 month interval to a 38 month interval. The effort was perforved at the request of Mr. E. Swartz with the cooperation of Mr. R. &ith at the Braidwood site, who received an advanced copy of the report via telex on 10/14/88.
The attachment includes a safety evaluatioa checklist (SECL-88-562) and a "no significant hazards" determination in support of the tecnnical specification change. This evaluation has as it's basis a recent evaluation which extended the surveillance interval to 31 months and was transmitted to Commonwealth Edison v.ia CAh'-10557/CE'a'-6021 dated 6/4/87.
Should you have any questions, please do not hesitate to call.
Very truly yours, rl x,-l, . .l, j
h G.P. Toth, Manager pf, 4%ws L Ccenonwealth Edison Projects smd/
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CCE-68-502 NS-OPLS-OPL-I-88-422 cc: R.E. Querio, Braidwood
<S.C;? Hunsader = .. s
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D. Swartz R. Sraith, Braidwood I
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nu NS-RH01-!G-10 5 SEC L- 8 8 - 5(o 2.
ATTACHMENT 1 Customer Reference No(s).
WestinghouseReferenceNo(s).
(Change, Control or RFQ As Applicable)
WESTINGHOUSE NUCLEAR SAFETY EVALVATION CHECK LIST PAGE 1 0F 3 (1) NUCLEAR PLANT (S) u / -/ e/
(2) CHECK LIST APPLICABLE TO: - I[ A'c- 4 # wen (SubjectofChange) y '
(3) The written safety evaluation of the revised procedure, design change or modification required by 10CFR50.59 has been prepaied to the extent required and is attached. If a safety evaluation is not required or is incomplete for any reason, explain on Page 3.
Parts A and B of this Safety Evaluation Check List are to be ecmpleted only on the basis of the safety evaluation performed.
CHECK LIST - PART A (3.1) Yes No X A change to the plant r, described in the FSAR?
(3.2) Yes No X A change to the procedsrcs as described in the FSAR?
(3.3) Yes No X A test or experiment .iot described in the FSAR?
(3.4) its g_ No A change to the piart technical specifications (Appen x A to the Orerating License)?
W'CW,- htn C on CHECK LIST - PART B (J tificat on for Fart B answers must be included on Page 3.
(4.1) Yes No X Will the probability of an accident previously evaluated in the FSAR be increased?
(4.2) Yes No k Wili the consequences of an accident previously evaluated in the FSAR be increased?
(4.3) Yes_. No A Way the possibility of an accident which is different than any already evaluated in the FSAR be created?
(4.4) Yes No k May the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
(4.5) Yes No X W111 the consequences of a La1 function of equipment important to safety previously y evaluated in the FSAR bs increased?
(4.6) Yes No n Nay the possibility of a malfunction of equipment important to safety different than any j No N already evaluated in the FSAR be created?
Will the margin of safety as defined in the 4 (4.7) Yes g bases to any technical specification be reduced?
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, NS-RM0!-IG-10 5
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SEC4 F61 i
ATTACHMENT 1(Continued)
Customer Reference No(s).
Westinghouse Reference No(s).
(Change Control or RFQ As Applicable)
WESTINGHOUSE NUCLEAR SAFETY EVALUATION CHECK LIST PAGE 2 0F 3 If the answers to any of the p.*., ceding questions are unknown, indicate under (5) REMARKS and explain on page 3.
If the answer to any of the above questions in (4) cannot be answered in the negative, based on written safety evaluation, the change cannot be approved without an application for license amendment submitted to NRC pursuant to 10CFR50.90.
(5) REMARKS:
Re f ere>,c e 'c s w - so 2; (sh/gy)
L'C A tow -to Tarn Se/s s 7,fon " Byron /Braic/ weed Diese/ $ rnera tor E L; c.a /
Spee; fiutio,, Es t-enven Ji45 6i $ cot jon ".
Re (enu e 2. : Byen Geneedinj 5 + w % Z ;,,i 6 in g C o n d h ,s f e r- Opeation Rdo otion Prepa m ,Wc 6 P- lo s 2 6 Apr,1 19 64 .
3 Re f ennce. 3 . B y en Ann,y P R n rechnol.j y L n s fe r D o c u . . < ,3 + .
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(6) APPROVAL LADDER (Signatures): g /
//
, (6.1)Preparedby(NuclearSafety): N/ . I d ate: /#/7/88 (6.2)CoordinatedwithEngineer(s): / Date:
(6.3) Coordinating Group Manager (s): Date:
(6.4) Nuclear Safety Group Manager: 8 M /, / h _ Date: /M/FN f
.i i.
NS-RM01-IC-10 5
SECL-68.g&L ATTACHMENT 1 (Continued)
Customer Reference No(s).
Westinghouse Reference No(s).
(Change Control or RFQ As Applicable)
WESTINGHOUSE NUCLEAR SAFETY EVALUATION CHECK LIST PAGE 3 0F 3 The following sumarizes the justification upon the written safety evaluation,II) for answers given in Part B of the Safety Evaluation Check List:
. ' G.Ct W ? .N h Af IIIReference to document (s) containing written safety evaluation:
.- ,>s >. . .
j PREPARED BY: [Meu, 8 ddy////
_ DATE: /d'/7/[8 v
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BRAImoOD DIESEL GENERAICR 'DDWICAL SnMFICATIN EmNSIN DmotUCTIm Westinghouse was requested by orncrusalth niiscn to rupport, fmn a probabilistic riax a-nt (PRA) perspectise, an extansicn of the Braidwcod Unit 1 diesel generators teardown inspection requirement, tactnical specificaticn 4.8.1.1.2f, frun a crie time 31 month interval to a one time 38 acnth interval to coincide with the currently planned refueling outage.
A previous study performed for n=-1 wealth FAiem by Westinghouse, reference 1, made two evaluaticris: the first evaluaticn was of a perinanent extension of the time interval for the diesel generator teardown inspections frun 18 acriths to 24 acriths, the second evaluaticn was a cne time extensicn of the teardown inspecticos frun 24 months to 31 zenths.
'Diese evi.luations showed both proposals to be acomptable. 'Ihe diesel generator manufacturer also approved, subject to the utility ocmducting a trund analysis ytwtam of diesel generator operating parameters.
Subsequently, the Nuclear Regulatory himmien (NRC) appIUved the request for the one time extensicn of the teardown inspection to 31 acnths.
02monwealth Ediscn had prvvicusly supplied Westinghouse the following inforation cancerning their maintenance piMares for the diesel generators.
- 1. Braidwood Unit 1, IA diesel ge:)arator cperability nonthly (staggered) and sardannual (staggered) surveillance, IBwCS 8.1.1.2a-1, revision 54.
l 2. Diesel generator 1A 18 acrith teardcun inspection,1BNS 8.1.1.2e-1, revisicn 1
- 3. A list of a$diticm1 preventative maintenance to be carried cut during the 18th acrith when the current 18 acrith taardown inspectice is extended to the 24th actith.
In ackiiticri, 0: mcr1 wealth Biiscn prtnidad the following updated information for this study:
- 4. Braidwood Unit 1, IA diesel generator eparability scrithly (staggered) and amninrruel (staggered) surveillance,1BwoS 8.1.1.2a-1, revision 0 (Nota the revision rwverted to zero because it had been a Braidwood and Byron pr M m but is now exclusively a Braidwood ps M are).
- 5. Memo 5f/88-1130, Septem w 16,1988 frun R. E. Querio, Braidwood Nuclear staticri to G. L. Miller, Cocpar Industries
- 6. Meno, Septerter 26, 1988 frun G. L. Miller, Cooper Industries to R.
smith, BraicMxx1 Nuclear statico
- 7. List of ' Nots of araidwood thit 1 Diesel Generators frun 12/10/86 to 7/14/88 1
SEC L - 8 8 - 5 6 2.
)ODEL AND ASSLMPTICtfS
'Ihe tasting re bres outlined in the monthly surveillance and is month taardown inrpecticn had been previously reviewed to estimate the type of potenttal f.ailure nedan detectable by these tests. 'Ihe then prt. posed pzwventau.ve maintenance swie was also reviewed in a similar manner.
'Iha tym of potential failuru modes that might be undetected by the preventative maintenance s w s e , but might be detectable by the 18 month taardown inspecticn prwie , wars identified. A m: del was w 'M to estimate the impact of these potentially undetected failury modes cm the oorunalt frequency and other risk critaria developed for the Byron PPA nrdal of references 2 and 3.
Both the previous study and this stud" are hamad en the following
= == ='tions .
- 1. 'Ihe coremalt frequency miel for G e loss of offsite power event, given the Byrtn Limiting Orditions for Operatico Relaxatico Program of refersnos 2, and in the subsequent Byrtn Living PRA ;wport of reference 3, is aplicable to both the Byrtn ard Braidwood generatinJ stations. 'Ihe type of diesel gr nerators used in both staticms are the same. 'Ihe cosite electric power systams of the two stations are similar with the Braidwood offsita power systan being considered to be more reliable than that of the Byrtn statier. as s.%m in referarce 4.
'Ibereform, this investigatico is based en the model developed in reference 2.
- 2. 'Ihe value used in reference 2 for the unvailability of the diesel generator (fails to start and fails to run) was 2.4E-02 and the maintenance unavailability was 1.54E-02. 'Ihe sum of these unavailabilities is a four percent unavailability cn demand for each diesel generator. 'Ihese values are used as a basis for ocrparison of the results of the two nodals.
- 3. Periodic testing (acothly, quarterly ard semiannually) will detect the majority of the potential failure ardaa. 'Ihis assucptico is in gros ent with the Byrcn PPA model ard is also a ocmncnly accepted assmpticn in other PRA studies.
- 4. 'Iha diesel generator actual operating time is small in the extended 31 months to 38 mcoths period ocupared to the cperating time anticipated during the expected service life of 40 years.
CCtCI11SICH It is concludai that the proposed eatensicn of the diesel generator taardown inspections frta 31 mmths to 38 acnths is acceptable as lcrg as a trerd analysis swie is in place and the acothly tests ccotinue with no indications of significant degredatico of the critical engine parameters specified by the manufacturer.
i
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0 SUWARY OF JUSTIFICATICri OF SIQiIFICNTT HA2ARDS DETEIMDaTICti
'1he standarti used to arrive at a proposed detemination that a request for ar=.idments involves no significant hazards consideration is included in 10 CER 50.92. It states that the operation of the facility in accordance with the proposed &Eed.eits would not (1) irralve a significant increase in the probability or consequences of an accident previously evaluated; or (2) crwate the possibility of a new or different kind of accident fran any accident previously evaluated; or (3) involve a significant reduction in a -
martJ i n of safety.
'Ibe following evaluation in relation to the three c.riteria denonstrates that the prtpcsed change to technical specificatien 4.9.1.1.2f does not involve a significant hazards ocnsideration. <
FIRST CRITERIA It is shown that the prop.; sed, one tire technical specification charge will not significantly increase the unavailability of the diesel generators. 'Ihe diesel generators are currently perfomirg well, with one failure in the last 28 vralid tests. Wear ard tear of the diesel generators is minimal sirce they are called upon infrequently. A review of the diesel generator failure history shcus no trends of abnormal failures. 'Iberefore, the proposed, one time technical specification change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
SEcct:D CRITERIA >
'Ihe prtposed, one tire technical specification only changes the teardcun impection interval of the diesel generators. It dces not add or replace any equipTnt that may result in a new or different kind of accident frcn any accident previously evaluated.
'ntIRD CRrIIRIA
'Ibe prtposed, one tire technical specificatien change does not reduce any martli n.
ca. ..- c, si t
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ENERGY SERVKES GROUP w.e November 17. 1988 Comonwealth Edison Company R.M. #1 P. O. Box 84 Braceville, Illinois 60407 Attention: Mr. Jim Grzemski RE: Electronic Engine' Analysis Unit 1A - S/N 7175 Unit 18 - S/N 7176 Gentlemen:
On November 14 and 17,1988 the ENSPEC 3000 Engfrie Analyzer was set up and operated on the above re/crenced units. At this time, complete analysis and compression testirig was performed.
Both units ran very well throughout the test. All operating parameters were within rnanufacturer's specifications. Please review the 3ttached for additional information.
If you have any questions or if I can be of further assistance, please don't hesitate calling.
Sincerely, yg, j
, h~
/ James Burdette
' Field Service Representative
- JB/sjs Attachment r
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