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| ==Reference:== | | ==Reference:== |
| (a) June 23, 1988 letter from S.C. Hunsader to Dr. T.E. Murley conveying grease mixture test results (b) August 26, 1988 letter from S.C. Hunsader to Dr. T.E. Murley conveying grease mixture test results (c) November 22, 1988 letter from S.C. Hunsader to Dr. T.E. Morley containing an assessment by Dr. R. Bolt | | (a) {{letter dated|date=June 23, 1988|text=June 23, 1988 letter}} from S.C. Hunsader to Dr. T.E. Murley conveying grease mixture test results (b) {{letter dated|date=August 26, 1988|text=August 26, 1988 letter}} from S.C. Hunsader to Dr. T.E. Murley conveying grease mixture test results (c) {{letter dated|date=November 22, 1988|text=November 22, 1988 letter}} from S.C. Hunsader to Dr. T.E. Morley containing an assessment by Dr. R. Bolt |
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| ==Dear Dr. Murley:== | | ==Dear Dr. Murley:== |
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| l Dr. Thomas E. Murley - 2 - November 21, 1990 The environmental qualifications of the Exxon Nebula EP-0 and EP-1 is not compromised by the addition of 2% and 5% of Sun 50 EP. Test results and j visual examination indicated little difference in performance between pure Nebula EP-0/EP-1 and mixed grease samples containing up to and including 5% | | l Dr. Thomas E. Murley - 2 - November 21, 1990 The environmental qualifications of the Exxon Nebula EP-0 and EP-1 is not compromised by the addition of 2% and 5% of Sun 50 EP. Test results and j visual examination indicated little difference in performance between pure Nebula EP-0/EP-1 and mixed grease samples containing up to and including 5% |
| Sun 50 EP. The Exxon Nebula EP-0 and EP-1 remains environmentally qualified consistent with the Limitorque requirements, Therefore, there is no need to replace the grease of Limitorque operators containing mixed grease samples of up to and including 5% Sun 50 EP. | | Sun 50 EP. The Exxon Nebula EP-0 and EP-1 remains environmentally qualified consistent with the Limitorque requirements, Therefore, there is no need to replace the grease of Limitorque operators containing mixed grease samples of up to and including 5% Sun 50 EP. |
| Currently, six valves at Byron Station Unit I have grease mixtures in excess of 5%. It was determined that a Justification for Continued Operation (JCO) was required for these valves. Documentation of the JC0 was supplied to Byron Station by the CECO Nuclear Engineering Department by letter dated November 5, 1990 and was immediately made available to the NRC resident inspector for review. Changeout of the grease mixtures in these valves will be accomplished no later than the next refueling outage for Byron Unit 1. | | Currently, six valves at Byron Station Unit I have grease mixtures in excess of 5%. It was determined that a Justification for Continued Operation (JCO) was required for these valves. Documentation of the JC0 was supplied to Byron Station by the CECO Nuclear Engineering Department by {{letter dated|date=November 5, 1990|text=letter dated November 5, 1990}} and was immediately made available to the NRC resident inspector for review. Changeout of the grease mixtures in these valves will be accomplished no later than the next refueling outage for Byron Unit 1. |
| Sampling-and testing of these six valves will be performed on a six month frequency to assure no significant degradation of the grease occurs until changeout. Results will be provided to the NRC after sampling and analysis is complete. | | Sampling-and testing of these six valves will be performed on a six month frequency to assure no significant degradation of the grease occurs until changeout. Results will be provided to the NRC after sampling and analysis is complete. |
| Additional documentation is available at Byron Station and/or CECO Nuclear Engineering and can be supplied upon request. Please direct any questions you may have concerning this matter to this office. | | Additional documentation is available at Byron Station and/or CECO Nuclear Engineering and can be supplied upon request. Please direct any questions you may have concerning this matter to this office. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211Q6611999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218 ML20211P1901999-09-0303 September 1999 Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211P1761999-09-0202 September 1999 Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210U8031999-08-0404 August 1999 Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210K9761999-07-30030 July 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant ML20210G6291999-07-29029 July 1999 Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20210C3961999-07-20020 July 1999 Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 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) ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations 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 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 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999 Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl ML20209G1391999-07-0909 July 1999 Forwards Results of SG Tube Insps Performed During Byron Station,Unit 1,Cycle 9 Refueling Outage within 12 Months Following Completion of Insps ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196G2161999-06-25025 June 1999 Forwards for NRC Region III Emergency Preparedness Inspector,Two Copies of Comed Emergency Preparedness Exercise Manual for 1999 Byron Station Annual Exercise. Exercise Is Scheduled for 990825.Without Encls ML20209D4861999-06-17017 June 1999 Informs That R Heinen,License OP-30953-1 & a Snow,License SOP-30212-3,no Longer Require License at Byron Station 05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999 Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations 05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999 Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below 05000456/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed1999-06-15015 June 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed BW990028, Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.51999-06-10010 June 1999 Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.5 05000454/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed1999-06-0808 June 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20211M1611999-05-28028 May 1999 Discusses 990527 Meeting with Comed Re Safety Culture & Overtime Control at Byron Nuclear Plant from Videoconference Location at NRC Headquarters.Requests That Aggressive Actions Be Taken to Ensure That Comed Meets Expectations ML20207D5261999-05-26026 May 1999 Forwards Response to NRC 990318 RAI Concerning Alleged Chilling Effect at Byron Station.Attachment Contains Responses to NRC 12 Questions ML20211M1781999-05-25025 May 1999 Summarizes Concerns with Chilling Effect & Overtime Abuses at Commonwealth Edison,Byron Station.Request That Ltr Be Made Part of Permanent Record of 990527 Meeting ML20195C7911999-05-25025 May 1999 Forwards Revised COLR for Byron Unit 2,IAW 10CFR50.59.Rev Accounts for Planned Increase of Reactor Coolant Full Power Average Operating Temp from 581 F to 583 F 05000454/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed1999-05-21021 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed 05000457/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Listed1999-05-21021 May 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Listed ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20207E9831999-05-18018 May 1999 Forwards Copy of Commonwealth Edison Co EP Exercise Evaluation Objectives for 1999 Byron Station Annual EP Exercise,Which Will Be Conducted on 990825.Without Encl ML20206T3351999-05-17017 May 1999 Provides Written follow-up of Request for NOED Re Extension of Shutdown Requirement of TS Limiting Condition for Operation 3.0.3.Page 9 of 9 of Incoming Submittal Not Included ML20206N7861999-05-14014 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Braidwood Station. Rept Contains Info Associated with Stations Radiological Environ & Meteorological Monitoring Programs ML20206Q8521999-05-13013 May 1999 Submits Rept on Numbers of Tubes Plugged or Repaired During SG Inservice Insp Activities Conducted During Plant Seventh Refueling outage,A2R07,per TS 5.6.9 ML20206N8551999-05-11011 May 1999 Forwards 1998 Annual Radioactive Environ Operating Rept for Byron Station. Rept Includes Summary of Radiological Liquid & Gaseous Effluents & Solid Waste Released from Site ML20210C7221999-05-0303 May 1999 Forwards Initial License Exam Matls for Review & Approval. Exam Scheduled for Wk of 990607 ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206U3351999-04-30030 April 1999 Forwards Evaluation of Matter Described in Re Byron Station.Concludes That Use of Overtime at Byron Station Was Controlled IAW Administrative Requirements & Mgt Expectations Established to Meet Overtime Requirement of TS 1999-09-08
[Table view] |
Text
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Ctmmtnwealth Edison i '
l._ } 1400 Opus Plac9
'\ Downers Grove. Illinois 60515 November 21, 1990 Dr. Thomas E. Murley Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
Subject:
Byron Units 1 and 2 Braidwood Units 1 and 2 Environmental Qualification of Grease Mixtures in the Main Gear Case of Limitorque Operators HRC_QQLLt.Ltios. 50-45A/A51JL52-151L451
Reference:
(a) June 23, 1988 letter from S.C. Hunsader to Dr. T.E. Murley conveying grease mixture test results (b) August 26, 1988 letter from S.C. Hunsader to Dr. T.E. Murley conveying grease mixture test results (c) November 22, 1988 letter from S.C. Hunsader to Dr. T.E. Morley containing an assessment by Dr. R. Bolt
Dear Dr. Murley:
The purpose of this letter is to convey the most recent information available regarding Commonwealth Edison's position on the environmental
-qualification of grease mixtures present in some Limitorque motor operated valve (MOV) gear cases at Byron Station. The letter of Reference (a) provided testing results requested by the NRC staff as a result of environmental qualification concerns arising from grease mixtures present in Braidwood Unit i valves. Additional testing results were provided for NRC review in the letter of-Reference (b). The test results provided the basis of an operability judgement made for eight Braidwood Unit i valves found to contain grease mixtures of 12% to 33% of Sun 50 EP mixed with Exxon Nebula EP-0/EP-1.
The letter of reference (c) included relevant information regarding; 1) the grease's physical properties, 2) the testing to verify those properties and 3) the impact of changes in the properties on the grease's lubrication function.
It is included as Enclosure 2 for ease of reference.
Enclosure 1 is an internal Commonwealth Edison Company (CECO) memo summarizing the Nuclear Engineering Department's engineering evaluation and conclusions regarding the acceptability of grease mixtures of 1 5% Sun 50 EP contained in Exxon Nebula EP-0/EP-1. References (a) and (b) contained test results which are summarized in this enclosure.
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{. g ,; { } DR M
l Dr. Thomas E. Murley - 2 - November 21, 1990 The environmental qualifications of the Exxon Nebula EP-0 and EP-1 is not compromised by the addition of 2% and 5% of Sun 50 EP. Test results and j visual examination indicated little difference in performance between pure Nebula EP-0/EP-1 and mixed grease samples containing up to and including 5%
Sun 50 EP. The Exxon Nebula EP-0 and EP-1 remains environmentally qualified consistent with the Limitorque requirements, Therefore, there is no need to replace the grease of Limitorque operators containing mixed grease samples of up to and including 5% Sun 50 EP.
Currently, six valves at Byron Station Unit I have grease mixtures in excess of 5%. It was determined that a Justification for Continued Operation (JCO) was required for these valves. Documentation of the JC0 was supplied to Byron Station by the CECO Nuclear Engineering Department by letter dated November 5, 1990 and was immediately made available to the NRC resident inspector for review. Changeout of the grease mixtures in these valves will be accomplished no later than the next refueling outage for Byron Unit 1.
Sampling-and testing of these six valves will be performed on a six month frequency to assure no significant degradation of the grease occurs until changeout. Results will be provided to the NRC after sampling and analysis is complete.
Additional documentation is available at Byron Station and/or CECO Nuclear Engineering and can be supplied upon request. Please direct any questions you may have concerning this matter to this office.
Very truly yours, h/ A.R. Checca 2V-Nuclear Licensing Administrator Enclosure cc: Resident Inspector-Byron Resident Inspector-Braidwood T, Shia-NRR R. Pulsifer-NRR Regional Administrator-RIII
/scl:ID628:2
i t . . 's
158908 November 7, 1990 To: T. J. Kovach
Subject:
Byron Units 1 and 2 Braidwood units I and 2 '
EQ of Mixed Grease in the Main Gear _ Case of Limitorque Operators
References:
June 23, 1988 Letter from S. C. Hunsader to T. E. Murley.
regarding Braidwood Unit 1 Limitorque Operator Lubrication. ,
The following provides a summary of the Design Support EQ group evaluation of the effect that mixing small quantitles of Sun 50 EP with Exxon' Nebula EP-0 or EP-1 has upon the environmental qualification of the EP-0 or EP-1
-main gear _ case lubricant used in Limitorque operators. As discussed below, >
mixtures of Sun 50 EP that do not exceed 5%, have been evaluated to-determine:the affect on the environmental qualification of the EP-0 and EP-1
- for Limitorque operators at the Byron and Braidwood_ Stations.
Lubricants that can be used in the Limitorque actuators are identified in the appropriate instruction manual and Lubrication Data form LC8. The main gearboxes were originally tested and supplied for in-containment-applications with. Exxon Nebula EP-1 grecsc. Nebula EP-0 is now supplied for in-containment appitcations, although Nebula EP-1 can be mixed with or used in place of the EP-0; Limitorque does not recommend mixing the Nebula EP-0 and EP-1 with any other type lubricant.
As a result of the identification of grease mixtures-In Limitorque Operators at Braldwood Station in Harch, 1988, PHR Engineering estabitsbed a. testing-program to determine the effect of mixing different quantitles of Sun 50 EP with Exxon' Nebula EP-0.and EP-1. This was accomplished by comparing the physical properties of Exxon Nebula EP-0 andLEP-1-containing in each case 2%
and 5% Sun 50 EP against the physical properties of pure Exxon Nebula EPO and EP-1. To evaluate the effect upon. environmental; qualification,.the test
' program subjected samples of mixed and unmixed grease to. radiation
~
environments of 2-x.10E5 and 2 xul0E8 Rads. During May and June', 1988, samples were radiation tested at Hyle Labs. ASTH D-1403 Penetration tests were_ performed before and after testing-to measure changes in consistency of
- the grease mixtures. Dropping point measurements (the temperature at which-the first drop offfluid separates from grease in a standard-apparatus) were also made, i
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\
Any' sample in which the worked' penetration values, between mixed and unmixed
. samples, which resulted in a change of less than 30 points were considered to be compatible based on the following:
a) The EPRI NP-4916 " Lubrication Gulde" which defines compatibility as "a change of-nqJAon_th6LL30_DRin11 (1 point = 0.1mm) in ASTM worked penetration on mixing."
b) The NLGI definition of incompatibility which states:
"Two lubricating greases.show incompatibility where a mixture of the products shows physical properties or service performance which are markedly inferior to those of either of the greases before mixing. Performance or-properties inferior to one of the products and superior to the other may be due to simple mixing and xquid not be consMentas evidente_of incomoatibility."
The tables below show the results of penetration tests for mixtures containing 2%_and 5% Sun 50 EP with Exxon Nebula EP-0 and EP-1.
Exxon Nebula EP-0 Worked Peneingtlon ASTM D-1403*
Radiation 2% Sun 51 Sun lxp.olure_._ 100% EP-0 M% EP Cttegg 95L.EP.0_ __ Chang e_.
0 395 395 0 392 -3 l_ 2 X-10E5 -362- 388 +26 388 +26 L
2 x 10E8 407 410 +3 407- 0 Exxon Nebula EP-1 Worked Penetration 60 Strokes ASTM D-1403*
Radiation 2% Sun N ' Sun
_Expolute 100% EP-1 _ElP- 1 Change E EP-1 .Jhuge_,
0 327 339 +12 332 +5 2 x 10E5 309 328 +19 324 +15 2 x 10E8 395 407 +12 407 +12
- Penetration valves provided are converted to full scale (ASTM 0-217) l penetration values, l
L
i \
- t. 1 i.
l l
l In all cases, the penetration results are within the EPRI NP-4916
" Lubrication Guide" criteria of no more than 30 points difference indicating compatible'gisase, when compared to 100% EP-0 and 100% EP-1 at radiation levels of zero, 2 x 10E5, and 2 x 10E8 Rads. The penetration values of the mixtures change (either up or down) in a similar fashion as the 100% Exxon product.
Overall, the_ test results show that under environmental conditions of zero, 2 x 10ES, and 2 x 10E8 Rads, mixtures of 2% and 5% Sun 50 EP in Exxon Nebula EP-0 and EP-1 will not.lmpact the lubricating qualities of the Exxon product. This continues to allow the Limitorque operator to operate and perform its intended function. As a result, the environmental qualification of the Exxon Nebula EP-0 and EP-1 is not compromised by the addition of 2%
and 5% of Sun 50 EP, The Exxon Nebula EP-0 and'EP-1 remains environmentally quallfled consistent with the Limitorque requirements.
For. assessing the effects of thermal aging on mixed grease, drop point and penetrant testing of the samples was evaluated. These tests, following thermal aging, Indicate that the mixed and unmixed greases perform similarly. Thus, there is no effect on thermal performance of the grease with the presence of Lithium. Since the lubricating performance has been demonstrated to follow the same trend of degradation as that of pure Nebula EP-1, the qualification testing performed by Limitorque on Nebula EP-1 is not compromised by the presence of Lithium in the mixed grease cases.
There has been no visual indication of a chemical reaction taking place as evidenced by normal consistency, and the absence of hardening, softening or separation. During sampling, the station utilizes BFP FS-28 to record data on the general consistency, color, presence of foreign matter (contalminants), and water. This data is recorded on BFP FS-28-T1. As a result of Fuel Handling Foreman Review there have been no abnormalities noted with respect to the above variables for all valves with the exception of two. Those-two, which had Indications outside the norm, were then chemically analyzed and found to have less than 2% Li content. It can be concluded from the visual results. documented, that no chemical reaction is taking place in the gear box which-would lead to premature hardening or
-softening of the grease. These valves have all been in service for a minimum of 5 years at Byron.
Should you have any questions, please call me at Ext. 7492.
S. C, Hunsader C hem M Corporate EQ Coordinator Design Support Group 20ESIGN/230 SCH/bim cc: N. P. Smith T. Schuster
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