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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
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Commonwealth Edison
.- q One Fird Nabonal Piar, Chcago, Ilhnors 3 s ' Address R$y to. Post 05UBoT6F s- Chcago, Ilhros 60690 0767 March 29, 1988 Mr. T. E. Murley Of fice o f Nuclear Reactor Regulation U.S. Nuclear Reactor Regulation Washington, D. C. 20555
Dear Mr. Murley:
Subject:
Braidwood Unit 1 and Unit 2 Limitorque Operator Lubrication NRC Docket Nos. 50-4 56 and 50-4 57 The purpose of this letter is to document information provided to the NRC Staff in telephone meetings on March 25, 1988 and March 28, 1988 concerning the ongoing Commonwealth Edison program to validate the adequacy of Limitorque operator lubrication at Braidwood Units 1 and 2. This program was undertaken to resolve the concern created recently upon the discovery by Commonwealth Edison of trace amounts of a grease product not qualified for harsh environment service in a Limitorque operator subject to harsh environment requirements.
Although all safety-related Limitorque operators were scmpled in 1985/1986 to ensure proper lubricatito products were installed, the recent sample anomaly ha' resulted in an extensive program, described in attachrants to this letter, to resolve all reasonable concerns related to the qualification of the affected Limitorque operators.
Attachment 1 to this letter, entitled Lubrication Contamination Evaluation,. discusses the background to the issue and describes the sampling and testing program underway to identify unacceptable lubricants.
Attachment 2 to this letter provides a summary of the logic to be used to evaluate the acceptability of an operator based upon the sampling and testing program.
Attachment 3 to this letter provides a summary of the sampling and testing results compiled through March 28, 1988.
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8803310262 880329 PDR ADOCK 05000456 P DCD
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_2-Attachment 4 to this letter discusses the applicability of 10 CFR 50.49 to the lubrication issue being addressed herein.
It is our understanding that the NRC Region III Staff has lead responsibility for coordinating the review of this issue. We further understand that the NRR Staff is providing technical expert support on matters related to lubricant adequacy. The materials provided in this letter are intended to facilitate that technical review.
If additional information is required or questions arise concerning this material, please contact me or Steve Hunsader of our Nuclear Licensing Staff.
Very truly yours, Louis 0.DelGeorgek Assistant Vice President Attachments ec: NRC Region III Braidwood Residenc Mr. S. Sands
Attachment 1 Lubrication Contamination E/aluation Braidwood Unit 2
, As a result of questions raised during the NRC audit of the electrical equipment environmental qualification (EQ) r,rogram applied by Commonwealth Edison on Braidwood Unit 2 (Reference Issue 30, 31; i.e., quality of lubricant for service at time of Unit 2 initial operation), a sample lubricant inspection program was undertaken. With the agreement of the NRC, it was decided to evaluate lubricants in ten Limitorque motor operators and one motor to determine whether any of those lubricants had any construction or time related quality discrepancies. If this sample did not identify any such discrepancies, the EQ audit questions would be closed. !
! However, the result of this sample did identify one of the ten Limitorque operstors to have what appeared to be mixed grease.
(It should be noted that Limitorque specifies Nebula EPO and Nebula EPl as acceptable operator greases for EQ applications.
Those greases are light tan in color. Another grease, Sun 50 EP, has been qualified by Limitorque for non-EQ use in '
safety-related applications outside containment. This grease product is dark brown / black.) The possible mixing was identified by the expected tan grease having black streaks in the sample.
i As a result of this observation, Commonwealth Edison agreed to a more extensive Limitorque operatur lubricant sampling program to assure that safety-related operators did, in f act, contain properly qualified lubricants with no unacceptable contamination. This program entailed sampling all safety-related Limitorque operators (Braidwood Unit 1 and 2 total - 263), including those operators (Braidwood Unit 1 and 2 total - 81) on valves for which the EQ program was not applicable; i.e., are not subject to the requirements of 10 CFR 50.49. The sample would be evaluated visually for any contamination and a chemical analysis by atomic absorption spectroscopy would also be performed to identify any mixed constituents in the lubricant. This program of sampling was reviewed and accepted by the NRC (Reference 1).
At this point, it is importsnt to note that in 1985, Commonwealth Edison undertook an extensive operator lubricant sample program that included the visual inspection of grease samples from all safety-related operators. This sample was taken from the grease injection point at the top of each operator. Forty valves were determined by visual observation l to have SUN 50 EP grease in the gearbox. These operators are outside containment. Use of SUN 50 EP in this applicatirn is :
acceptable per a 10/29/85 Limitorque letter (Reference 2). One l .
' hundred fourteen valves were determined by visual observation ,
1 l to have Nebula EPO grease in the gearbox. The remaining 109 !
I
valves (S/R, EQ and non-EQ) had indications of mixed greases by visual examination.
Of those 109 valves, 43 of the operators were removed to the mechanical ma.intenance shop where they were disassembled and degreased. They were then regreased in the field with Nebula EPO grease.
The remaining 66 valves were maintained by Project Construction Depar tn'. cot (PCO) . These 66 operators were drained of grease, the geartrain components were removed and degreased in a bucket, the inside of the casing was wiped down such that all accessible areas of the casing were cleaned. The operator was then reassembled and refilled with Nebula EPO grease.
Based upon this 100% sample initiated in 1985, the
., possibility of mixed grease in the Limitorque operators was thought to be completely resolved. Therefore, the finding of apparent grease mixing in one of ten oper.ators in the recent sampling was a surprise. Howeier, further investigation appears to demonstrate that the original sampling and grease replacement program, though typical of industry practice at the time , might allow for findings of the type recently made.
First, the 1985 sample was taken only from the top of the operator, whereas the recent samples are being drawn from the top, middle und bottom of the operator. Second, the solvent cleaning of operators in place, though consistent with common accepted practice, could have left traces of the retioved
e lubricant in the operator in hideout locations not identified during the cleaning or in uncleaned locations at the sampling points. With respect to this secor;d point, the opening and detailed inspection of uperators on valves ICC9412A, ISI8821A, and 2RH8702A for which the recent sampling identified potential mixed greases, did not find evidence of contamination or mixing of greases internal to the operator. These supplemantal detailed inspections, which were witnessed, in part, by NRC RIII personnel, support the integrity of the 1985 inspection and grease changoout program. ( Ad di tional. supporting Information of this type is expected as more operators are opened for cleaning and regreasing.)
It is recognized that the mixing of incompatible lubricants can undermine the acceptability of the lubricant.
However, examples exist demonstrating that grease mixing, depending upon the greases involved and the degree of mixing, may have no safety significance. In fact, the NRC has allowed for continued operation of plants that have identified mixed greases (Reference 3). Crucial to the determination of safety-significance of a mixed grease in a Limitorque operator is the compatibility of the grease mixture. Compatibility is typically determined through "penetration testing" (Reference ASTM D217 or 1403). This point is discussed in EPRI Report NP -4 916 , for which the principal contributor was Dr. R. Bolt, a lubricant expert. I f, as has been the case in other situations
where NRC review has resulted in the temporary acceptance of a mixed grease, the composite grease can be shown to be compatible, the mixture can be accepted. The penetration test is appropriate for establishing compatibility.
Our position regarding the acceptability of lubricants in Limitore.de operators at Braidwood Station is based on an inspection of the operators to determine if a mixture of lubricents has occurred. In those cases where sensory tests, similar to those stated in EPRI document NP-4916, indicate a mir, of lubricants, a penetration test will be performed. The penetration test will be used to determine if softening or hardening of the installed lubricant is occurring. The samples found to have either visual indication of mixing of lubricant types or that have penetration values outside those of a non-contaminated qualified lubricants will then be subjected to periodic inspection or regreased based on defined acceptance criteria. Further, for those Limitorque gearboxes identified with mixed grease by visual or chemical test, the lubricant t
will be replaced as soon as practicable, but no later than startup after the first refueling outage. This overall approach is in agreement with the NRR position taken with Duke Power (September, 1986) in that the acceptability of the lubricants is et .ablished through a combination of inspection and testing on a periodic basis. This methodology will insure the adequacy of the lubricant and not compromise plant safety. .
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l l A detailed explanation of this inspection and testing program is described in later sections of this discussion and is i i
defined in Attachment 2.
When the incompatibility is a sharp breakdown of the grease gel structure, excessive softness occurs. The result is an increased possibility of leakage of the lubricant away from the parts to be lubricated. For Limitorque gearboxes this is not a concern since the lubricant is contained in a sealed gear ;
case. The lubricant will not escape in quantitles large enough !
to result in a loss of the lubrication function. In equipment f such as the Limitorque operator, grease or oil is satisfactory
, as a lubricant. Grease is specified only to reduce potential for leakage through the gear case seals. The base ol'.s and I their additives will perform the required lubrication function irrespective of any softening of the lubricant in the ,
Limitorque gear case. The inspection of the Limitorque ;
operators in question at Braidwood will reveal any such f softening from either excessive leakage at the seals or from sampling of the contents of the gearbox. Inspections to date of the installed Limitorque operators at Braidwood have not revealed any signs of excescive leakage of the gearbox seals. ;
The other issue regarding incompatability of mixed I
greases is ha rdening. This issue is addressed by the sampling of the contents of the gearboxes and the penetration testing that is described later in this document. A change in ;
consistency of less than or equal to 30 points, as stated in l l !
EPRI NP-4916, defines compatibility. This is judged to be conservative, especially when one considers the service environment in the sealed Limitorque gearboxes. The penetration testing will be used to detect either hardening or excessive softening by measuring the point variation in this test procedure.
This discussion on the results of mixing of lubricants is in concert with the review in Docket Nos. 50-269, 50-270, and 50-287 as well as in Dr. R. Bolt's letter to J. E. Thomas of Duke Power (Reference 4) regarding a similar issue for Oconee Station (Reference 3).
In addition to inspection of lubricants, operating equipment will exhibit other signs that lubricants have experienced a property change. Increases in noise, operating times, motor running current and temperature increases are all possible indicators. In the case of the Limitorque operators, plant surveillances such as the signature analysis of selected operators will reveal such occurrences. Operating equipment can offer great tolerance to lubrication property changes,
.1.e. , one or two penetration gradec for greases (90 points),
without any significant impact on the equipment itself (NP-4916). The maintenance and surveillance program in place at Braidwood Station, along with the added testing and surveillance program described below, will preclude the possibility of degraded Grease from remaining in the subject Limitorque operators.
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- 8-The discussion that follows defines the actions being taken by Commonwealth Edison to resolve the issue of potential arease contamination of Limitorque operators at Braidwood Station.
- 1. Inspect all safety-related Limitorques (total 263) for signs of lubricant leakage from the gearbox.
- 2. Do a visual examination in accordance with l
Braidwood procedure BwFP FS-1, Rev. O of samples (using three point technique) from all operators,
- a. If the sample should fail the Limitorque maintenance requirements for grease inclusions (water, grit, dirt), consistency or other sensory tests (as described in EPRI Research
, Repor t IP-4916) , the operator must be evaluated for additional corrective action up to and including grease change-out.
- b. If the visual inspection of the grease sample shows no indications of grease contamination with other grease, and the grease cieets the Limitorque maintenance requitements, the actuator is acceptable and no further action is required. The valve will be returned to its normal routine maintenance cycle.
- c. If the sample shows indications of grease contamination with other grease based upon i
_ _, m._ . , , _ _ _ . _ _ _ . _ - . _ . _ _ _ , . . _ . . . . _ .
l visual observation, an approximate 20cc sample of the mixture will be pulled from the actuator and sent to the lab (See Note 1) for a micro penetration test ( ASTM 1403) . If the test indicates that the grease has hardened or sof tened by more than 45 points in an ASTM worked penetration test (Reference 5), the grease in the actuator will be changed out.
In addition, one additional sample of grease will be pulled for a second penetration test after an approximately nine month period. Should this test show significant hardening or softening, the grease will be monitored on a more frequent basis until an outage of sufficient duration allows for the grease to be changed out.
- 3. All actuators that show visual indications of grease contamination with another grease will have a grease change-out at the next scheduled refueling outage.
Note 1 The penetration testing will be performed at AutoResearch Laboratory, Inc. (Harvey, Illinois)
- 4. Perform a chemical analysis (See Note 2) of samples from all operators using atomic absorption spectroscopy to determine the composition of grease in the sample.
- 5. In addition to the testing described above, the following mixtures of virgin Grease will be worked and then penetration tested:
Percent
- Grease Type 100% Nebula EPO 100% Nebula EPl 95% / 5% Nebula EPO / Sun 50 EP 95% / 5% Nebula EP1 / Sun 50 EP 75% / 25% Nebula EPO / Sun 50 EP 75% / 25% Nebula EPl / Sun 50 EP 50% / 50% Nebula EPO / Sun 50 EP 50% / 50% Nebula EPl / Sun 50 EP 25% / 75% Nebula EPO / Sun 50 EP 25% / 75% Nebula EP1 / Sun 50 EP 5% / 95% Nebula EPO / Sun 50 EP 5% / 95% Nebula EPl / Sun 50 EP 100% Sun 50 EP No radiation testing will be done since both greases have already been qualified by Limitorque and radiation tends to soften the grease (Reference 6) Such softening will not affect the qualification of the greases in question.
Note 2 The chemical analysis will be performed by the Commonwealth Edison System Materials Analysis Depar tment ( SMAO) .
- If grease densities are approximately the same, percent by weight. If grease densities are far different, percent by volume.
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This additional testing will establish a supplemental basis for assessing the acceptability of mixed greases of the type possible at Braidwood. This testing is similar to that done at the Rock Island Arsenal to evaluate similar grease
- mixing issues (Reference 7). A status of the grease sampling activity is provided as an attachment to this write up.
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l References
- 1. A. Bert Davis Confirmatory Action Letters to Mr. C. Reed, dated March 23, 1988 for Units 1 and 2.
- 2. Daniel S. Warsin0 (Limitorque Corporation) Letter to Dr.
R.O. Bolt, dated October 29, 1985
- 3. Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269, 50-270, and 50-287
- 4. Rober t O . Bolt , Ph.D. (Bolt & Associates) Letter to Mr. J. E. Thomas (Duke Power Company), dated June 17, 1986
- 5. ASTM - D1403-86 ASTM - D217-82
- 6. EPRI Report: "Radiation Ef fects on Lubricants" Page 6-2, Figure 6-1
- 7. Technical Report: "Compatibility of Lubricating Greases" (Rock Island Arsenal Laboratory) See Abstract.
[
- l Attachment 2 Lubricant Acceptance Criteria I. All operators for which both the visual inspection of the lubricant sample and the chemical analysis of the lubricant sample meet the applicable acceptance criteria are acceptable, with no further remedial action required.
A. The visual test will be acceptable if the sensory tests required to satisfy Limitorque lubricant maintenance requirements are satisfied and no mixture of grease products is identifiable in the sample.
- 8. The chemical test will be acceptable if the primary grease constituent exceeds any secondary grease constituent by a ratio greater than or equal to 50 to 1.
II. Any operator for which either the results of the visual
- inspection of the lubricant or the results of the chemical analysis of the lubricant are questionable based upon identification of an anomoly will be subjected to a penetration test. If the penetration test identifies penetration resistance within 1 45 points of the range defined by qualified Limitorque operator lubricants (Nebula EPO or EP1, Range 310 - 395), the operator lubrication is acceptable for interim use.
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I A. The visual test will be categorized as having an anomaly if any trace of mixed grease product is identifiable or lubricant discoloration is apparent. ;
B. The chemical test will be categorized as having an anomaly if the ratio of the primary grease constituent to the secondary grease constituent is between 50 to 1 and 20 to 1.
III. All operators for which any one of the visual, chemical or penetration test results are rejectable will be regreased prior to criticality of either Braidwood 1 or 2.
A. The visual test result will be rejectable if the sensory tests required to satisfy Limitorque lubricant maintenance requirements cannot be satisfied.
B. The chemical test result will be rejectable if the ratio of the primary grease constituent to the secondary grease constituent is less than or equal to 20 to 1.
C. The penetration test will be rejectable if the range of acceptable penetration is exceeded by 1 45 penetration points.
Attachment 3 Summary of Results (3-20-88)
Background:
Total of Safety Related (S/R) Limitorque Operators 263 Tota) S/R Operators in Harsh Environments 182 Total Grease Samples Taken 233 (Complete 3-30-88)
Total Visual Inspections Completed 233 (Complete 3-31-88)
Total Chemical Tests Completed 186 (Complete 4-01-88)
Total Penetration Tests Completed 25 (Completion Est. 4-02-88)
NOTE: A detailed summary of test results is being prepared and will be made available to the NRC Staf f on or before 8-31-88.
A,r.tachment 4 10 CFR 50.49 Evaluation 10 CFR 50.49(a) states:
"Each holder of or each applicant for a license to operate a nuclear power plant shall establish a program for qualifying the electrical equipment defined in paragraph (b) of this section."
10 CFR 50.49(f) states, in part "Each holder of electrical equipment important to safety must be qualified by one of the following methods: l
. . . (4) Analysis in combination with p1rtial type test data that supports the analytical assumptions and conclusions" Edison has established a program that addresses the environmental qualification of mixed grease at Braidwood Station. Complaince with 10 CFR 50.49(f) can be demonstrated by that which is presented in this letter and its Attachments. I Attachment 1 provides references to a summary of the test data that supports the conclusion that the grease will function in a radiation environment. Attachment 1 also provides a summary of the testing that will be performed to supplement the existing test data. Upon completion of this testing, we will perform the final analysis that will determine those valve actuators i
that can be qualified. This approach will fully implement 10 CFR 50.49( f) (4 ) and demonstrate environmert vl qualification.
It should also be recognized that the subject lubricant is not itself electrical equipment. However, it is considered i to be a part of the EQ program, as defined in 10 CFR 50.49, since it must fulfill its intended function which is to lubricate. As such, full grease qualification testing, as defined in IEEE 323-74, is not specifically required for lubricants and can be accomplished only through a program of testing of the type described in Attachment 1. Therefore, it
., is judged that the test data and analysis being conducted will demonstrate compliance with 10 CFR 50.49.
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