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| ==Reference:== | | ==Reference:== |
| a) May 11, 1990 letter from H. Richter to USNRC providing a revised schedule for Implementation of Generic letter 89-04 Guidance, b) July 6, 1990 letter from T. Schuster to USNRC requesting review and approval of Draft Relief Requests VR-21 and VR-22. | | a) {{letter dated|date=May 11, 1990|text=May 11, 1990 letter}} from H. Richter to USNRC providing a revised schedule for Implementation of Generic letter 89-04 Guidance, b) {{letter dated|date=July 6, 1990|text=July 6, 1990 letter}} from T. Schuster to USNRC requesting review and approval of Draft Relief Requests VR-21 and VR-22. |
| c) September 14, 1990, NRC Safety Evaluation issued for Draft Relief Requests VR-21 and VR-22 of the Byron Inservice Testing Valve Program, d) September 14, 1990, NRC Supplemental Safety Evaluation issued for review of Byron Inservice Testing Pump and Valve Programs, Revisions 7 and 8. | | c) September 14, 1990, NRC Safety Evaluation issued for Draft Relief Requests VR-21 and VR-22 of the Byron Inservice Testing Valve Program, d) September 14, 1990, NRC Supplemental Safety Evaluation issued for review of Byron Inservice Testing Pump and Valve Programs, Revisions 7 and 8. |
| e) October 17, 1990, NRC Safety Evaluation and Technical Specification Amendment 39 deleting Type C Test requit ements for Steam Generator Blowdown Valves. | | e) October 17, 1990, NRC Safety Evaluation and Technical Specification Amendment 39 deleting Type C Test requit ements for Steam Generator Blowdown Valves. |
Similar Documents at Byron |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities 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 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 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 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 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 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.. 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 ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) 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 ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff 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 ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick 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 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 ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective 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 ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station 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 ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities 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) 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 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) 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 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.. 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 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 ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl ML20209G1391999-07-0909 July 1999 Forwards Results of SG Tube Insps Performed During Byron Station,Unit 1,Cycle 9 Refueling Outage within 12 Months Following Completion of Insps ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196G2161999-06-25025 June 1999 Forwards for NRC Region III Emergency Preparedness Inspector,Two Copies of Comed Emergency Preparedness Exercise Manual for 1999 Byron Station Annual Exercise. Exercise Is Scheduled for 990825.Without Encls ML20209D4861999-06-17017 June 1999 Informs That R Heinen,License OP-30953-1 & a Snow,License SOP-30212-3,no Longer Require License at Byron Station 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 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 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 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 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 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 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 ML20206E7521999-04-22022 April 1999 Submits Rept on Number of Tubes Plugged or Repaired During Inservice Insp Activities Conducted at Plant During Cycle 9 Refueling Outage,Per TS 5.6.9 ML20206A7431999-04-22022 April 1999 Forwards Comments Generated Based on Review of NRC Ltr Re Preliminary Accident Sequence Precursor Analysis for Byron Station,Unit 1 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 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 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 ML20206A8141999-04-20020 April 1999 Advises NRC of Review of Cycle 10 Reload Under Provisions of 10CFR50.59 & to Transmit COLR for Upcoming Cycle ML20205T3901999-04-13013 April 1999 Forwards Byron Station 1998 Occupational Radiation Exposure Rept, Which Is Tabulation of Station,Utility & Other Personnel Receiving Annual Deep Dose Equivalent of Less than 100 Mrem ML20196K6661999-03-31031 March 1999 Forwards Byron Nuclear Power Station 10CFR50.59 Summary Rept, Consisting of Descriptions & SE Summaries of Changes, Tests & Experiments.Rept Includes Changes Made to Features Fire Protection Program,Not Previously Presented to NRC 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) 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 ML20207K0351999-03-0404 March 1999 Forwards Util Which Transmitted Corrected Pages to SG Replacement Outage Startup Rept.Subject Ltr Was Inadvertently Not Sent to NRC Dcd,As Required by 10CFR50.4 ML20205C6861999-03-0404 March 1999 Provides Notification That Byron Station Implemented ITS on 990205 & Braidwood Station Implemented ITS on 990219 ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207D4301999-02-26026 February 1999 Informs NRC That Supplemental Info for Byron & Braidwood Stations Will Be Delayed.All Mod Work Described in Ltr Is on Schedule,Per GL 96-06 ML20207B8971999-02-25025 February 1999 Expresses Concern That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazard at Some Commercial Nuclear Plants in Us ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202F5911999-01-29029 January 1999 Forwards Byron Unit 1 Cycle 9 COLR in ITS Format & W(Z) Function & Byron Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function. New COLR Format Has Addl Info Requirements ML20199E1611999-01-15015 January 1999 Forwards Response to 980902 RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. CE Endorses Industry Response to RAI as Submitted by NEI ML20199B7511999-01-0808 January 1999 Forwards Proprietary Versions of Epips,Including Rev 52 to Bzp 600-A1 & Rev 48 to Bzp 600-A4 & non-proprietary Version of Rev 52 to Bzp 600-A1 & Index.Proprietary Info Withheld 1999-09-30
[Table view] |
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\
/ C:mm:nneelth Edis:n i _ 1400 Opus Place
\ '~ 7 Downert, Grove. luinois 60515 LJ December 7, 1990 Dr. Thomas E. Hurley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regelatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Byron Station Units 1 and 2 Intervice Testing Program For Pumps and Valves Revisions 8 and 9 respectively HRC._ Dont.tJioL_50-A 5A _end_50- 455
Reference:
a) May 11, 1990 letter from H. Richter to USNRC providing a revised schedule for Implementation of Generic letter 89-04 Guidance, b) July 6, 1990 letter from T. Schuster to USNRC requesting review and approval of Draft Relief Requests VR-21 and VR-22.
c) September 14, 1990, NRC Safety Evaluation issued for Draft Relief Requests VR-21 and VR-22 of the Byron Inservice Testing Valve Program, d) September 14, 1990, NRC Supplemental Safety Evaluation issued for review of Byron Inservice Testing Pump and Valve Programs, Revisions 7 and 8.
e) October 17, 1990, NRC Safety Evaluation and Technical Specification Amendment 39 deleting Type C Test requit ements for Steam Generator Blowdown Valves.
Dr. Hurley:
Attached is the Inservice Testing (IST) Program for Pumps and Valves, Revisions 8 and 9 respectively, for Byron Station Units 1 and 2.
Enclosure 1 provides a brief summary of the changes to the IST Pump Program and Enclosure 3 is the actual Revision 8 documtnt with revision lines in the right hand margin Indicating the affected text. Enclosure 2 provides a brief summary of the changes to the IST Valve Program and Enclosure 4 is the actual Revision 9 document with revision lines in the right hand margin indicating the affected text.
I
~
I~ZNLD:ID651rg OM 9012140141 901207 PDR ADOCK 05000454 P PDC l
By transmittal of the Byron IST Program for Pumps and Valves, Revisions 8 and 9 respectively, the following major tasks are being accomplished:
- 1) Major changes to the program were made to reconcile it with Generic Letter 89-04 guidance. Submittal of these IST Program revisions complies with a commitment made in the letter of Reference (a). The letter stated an IST Program revision incorporating Generic Letter 89-04 guidance would be submitted within 90 days of receipt of the supplemental SER for IST program Revision 7 for pumps and Revision 8 for valves.
One significant change was the addition of backflow tests (BT) to various check valves in Valve Program Table 4.3 to comply with Generic Letter 89-04 requirements.
- 2) Request for NRC review and approval of a revised Draft Relief Request VR-1. Type C Testing requirements for Steam Generator Blowdown Valves were deleted from Technical Specifications by issuance of Amendm:,nt #39 in reference (e). The revised Draft Relief Request VR-1 removes reference to the Steam Generator Blowdown Valves to align VR-1 with Technical Specifications. The Steam Generator Blowdown Valves will continue to be leakage tested, but under different requirements, since they remain in the Valve Program Tables of Section 4.3.
- 3) Request for NRC review and approval of revised Draft Relief Request VR-12. Added eight valves to the list of valves that normally stroke in 2 seconds or less.
- 4) Request for NRC review and approval of Draft Relief Requests VR-18, 19, and 20 and revised Draft Relief Requests PR-1 and PR-2. The changes of VR-20 reflect a program improvement in valve stroke time trending.
- 5) Hithdrawal of Draft Relief Request VR-21 submitted in the letter of Reference (b) and reviewed by the NRC in Reference (c). As a result of a teleconference with the NRC staff and the subsequent Safety Evaluation issued in Reference (c) an alternate method of testing the check valves of VR-21 in compliance with GL 89-04 guidance was determined.
I ZNLD:106Sirg i
Efforts are underway to disposition Draft Relief Request VR-22 and final resolution will be provided at a later date. The NRC staff granted interim relief in Reference (c) for the affected valves of VR-22 allowing the ct:rrent testing methods to continue for relief period specified as 1 year from September 14, 1990 or until the next refueling outage. New Draft Relief Request PR-7 for the Essential Service Water Makeup Pumps is not complete and
- a supplemental transmittal required by Reference (d), providing PR-7 in its entirety, will be transmitted by March 15, 1991.
Completion of NRC review and approval of the new and revised Draft Relief )
Requests is requested by February 16, 1991, so that comments may be incorporated into the March 1991 submittal required by the NRC Safety Evaluation of Reference (d). If this schedule cannot be met, we request the l review be completed no later than Ap"il 15, 1991 to allow adequate time for IST l procedure revision for the fall 1991 Unit 1 Refueling Outage.
Please direct any quettt&., you r.iay have concerning this matter to this office.
Respectfully, Y.ucf f &c?/Ob{ '""
Terence K. Schuster Nuclear t.lcensing Administrator Enclosures cc: Resident inspector-Byron w/o enclosures T. Shla - NRR
- 5. Sands - NRR w/o enclosures Regional Administrator - RIII w/o enclosures s
P
Page 1 of 2 ;
e Ins 1ctture . )
S umma ry_ILLthe_RettslonJLChang e s.
10_ ibLDJInn.ita110 LIST ProgIAM_f.Qr._EURDA Set 110tLLO: TablLQLCont.enh I. Added brief explanation of reason for deleting note 4.
- 2. Added Draft Relief Request PR-07 5e111on1J : Program.le. sir.1D1100
- 1. Revised to add the status and requirements of HRC approval on relief requests.
2 Revised to delete remarks on Actt's Pumps
- 3. Revised to explain when reference values are revised; after pump replacement, repair, routine servicing and any other reasons.
Ses.tionA2L._ Refetentes
- 1. Added this section to list references used in development of the IST Program Plan for Pumps, including NRC SER'S and IST Plan Review Responses.
Section_ h 3t EtogtanLlhble.s T
- 1. Added "following maintenance" description to when bearing temperatures are taken.
- 2. Added pump inoperable exemption period to quarterly test frequency description.
- 3. Added horizontal and vertical lines to the Pump Program Plan lables.
SetilotL3d; _No_te5
- 1. No changes, other than section number.
l Page 2 of 2 i SeC t10fL3 A._Rellef_Requeit s
- 1. Added step number 9 to PR-1, PR-2, PR-5, and PR-6 to document I approval status of each relief request. ,
4
- 2. Draft Relief Request PR-1 was revised to include the following changes:
- a. Update to most recent revision of OMb-1989, Part 6.
- b. Change the bearing where axial vibration readings will be taken for the CS and RH pumps from upper motor bearing to lower motor bearing,
- c. Delete taking the CS and R11 casing vibration due to lack of pump bearings,
- d. Remove all references to the OSX02PA,B pumps (to be included in Draft Rellef Request PR-07 at a later date).
- 3. Added Draft Relief Request PR-2 revision to eliminate recording of pump bearing temperatures on all pumps in the IST Program. This is consistent with industry and other CECO Stations practice as vibre.tlon trending quarterly is superior to bearing temperatures taken once per year for trending of pump performance. Note that the currently approved PR-2 already exempts 25 of 41 pumps from this requirement.
- 4. Added Draft Relief Request PR-07 which will encompass vibration !
monitoring of the OSX02PA B Essential Service Water Haleup Pumps.
The technical justification for relief will be provided by March 15, 1991.
u 4
Pagt 1 of 3 '
1 ERCLOSURL2 SummerroLttleJerision_9_Changel
.to_theJyrotLSIation 1SLEtogtanttor_XAhes lettion.j # Table _.oLC.co.ttati
- 1. Added new Section 4.2
- 2. Added new Section 4.5
- 3. Added new Hotes (from #23 on) and Relief Requests (from VR-18 on).
- 4. Added brief description of reason for deletion of Relief Requests VR-11 and VR-14. ,.
- 5. Changed status of Relief Requdst VR-21 from " draft" to " withdrawn" l (See changes to Section 4.6, item 10).
- 6. Changed status of Relief Request VR-22 from " draft" to " interim" (see changes to Section 4.6, item 11 for details of this change).
Settion.A di ProgEAULQelCdRtioD
- 1. Added status and requirements of NRC approval on relief requests.
- 2. Added paragraph describing scope of Valve Program. ,
1
- 3. Added description of positions on valve stroke timing and check valve testing per NRC Generic letter 89-04.
- 4. Added required response when valve data is in Required Action Range.
- 5. Added description of when new stroke time reference value changes are requi"ed.
Sec.tlon_L2; ProstanLRefe.tentes
- 1. Added this section to list references used in development of tSe IST Program Plan for Valves.
. Page 2 of 3
- SectioUiJi__Erogru Tabhs l
- 1. Added description of check valve back flow testing method to
- part L.
- 2. Deleted Maximum Stroke Time method description. (former part M)-
4 i' 3; Added description of Technical Approaches and Positions (part W and Notes (part P).
- 4. Deleted Maximum Stroke Time column in the Tables.
- 5. Added Technical Approaches and Position, and Notes columns-in the Tables.
- 6. Added " closed" stroke direction to several check valves in the Tables as required by NRC Generic letter 89-04, Attachment 1 ,
Position #3.
g 7. Added "back flow" test methods for those check valves noted in #6 above.-
F 8. Added new Relief Request, Technical Approaches and Positions, and f Notes to the Table columns, where appropriate.
- 9. Updated P & ID number in the Tables to current revisions, where required.
- 10. Removed reference to VR-1 from the table listings for valves l- 1/2SD002A-H and 1/250005A-D (see changes to section 4.4, item 3 3 for details of this change). -
- 11. Changed stroke test mode from "CS"_to "0P" for valves 1/2518804B, 1/2518807A,B to correct a typing error.
E 12. Chas,7ed check valve full stroke test mode from "RR"-_to "CS" for valves 1/2SI8922A,0 and 1/2S18926 to correct a _ typing error. ,
SectLon A.ALNotes .
, 1. Added valves 1/2RH8705A,o +o Note 6 (see changes to section 4.6, item 6 for details).and added last sentence.
- 2. Added new Notes (#23 on)
- 3. Added Note 34 to document the fact that, due to a recent Byron Tech Spec Amendment #39 valves 1/2SD002A-H and 1/250005A-D are-no g"
longer considered to be 10CFR50 Appendix J__ type containment isolation valves. Therefore,-they will no longer be_ tested in
- compilance with 10CFR50 Appendix J. They wlll now be tested in accordance with ASME Code Section XI IWV-3420,
- 4. Added Note 35 to document the fact that valves 1/2RH8705A/B will j- be operability tested-using an alternate method which has been ,
i ~ identified as acceptable by NRC SER dated 9/14/90.
t.a_...;._..._._,._,_..___._,_.-__._,_,_.__._..,____,,_.,.____
Page 3 of 3 5eCllDILA 51-_lechnicaLApoteacheLandE1111cas
- 1. Added new section to implement standard IST practices as outlined in the Conduct of ISI/IST Manual.
Section_4J.L Relltf. Rtautit.s
- 1. Added new Relief Requests (VR-18 on).
- 2. Removed valves 1/2SD002A-H and 1/250005A-D from Relief Request VR-01 (see changes to section 4.4, item 3 for details of this change)
- 3. Added itemized history of approval status for all previously submitted relief requests.
- 4. Added brief description of reasons for deletion of Relief Requests VR-07, VR-il, and VR-14. -
- 5. VR-1: -Arranged in valve EPN order.
-Added that trending requirements of IHV-3427(b) will not be utilized as allowed by NRC Generic Letter 89-04.
- 6. VR-2: -Noted sample disassembly plan given in VR-18 and allowed by HRC Generic Letter 89-04.
- 7. VR-4: -Noted sample disassembly plan given in VR-18 and allowed by NRC Generic Letter 89-04,
- 8. VR-8: -Revised "(Ct)" to "(Bt)" per new definitions.
- 9. VR-12: -Added 2SD002A-H.
- 10. Draft Relief Request VR-21 was withdrawn. No relief is required because valves 1/2Ril8705A,B will be operability tested by verifying that there is depressurization in the applicable line when they are opened. This method was acceptable per NRC SER dated 9/14/90.
- 11. Relief Request VR-22 wes changed from a " draft" relief request to an " interim" relief request. Interim relief was granted per NRC SER dated 9/14/90 for a 1 year period or until the next refueling outage (whichever is later) to permit further investigation of a possible alternate test of valve operability.
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