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
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O)mmonwealth Illison O)mpany lly ron Generating St.ition 4 650 North Gernan Church ituad fly ron. 11.61010 9794 Tel1415-231511I March 2,1998 LTR: BYRON-98-5054 FILE: 2.01.0700 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk
Subject:
Additional Request for Temporary Relief from ASME Section III Requirements - Use of Line Stopping Equipment on Essential Sersice Water ASME Class 3 Piping Byron Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455
Reference:
- 1. " Request for Temporary Relief from ASME Section 111 Requirements -
Use ofLine Stopping Equipment on Essential Senice Water ASME Class 3 Piping," Byron letter 97-5081, D. B. Wozniak to NRC Document Control Desk, dated April 11,1997 and supplemented on July 10,1997.
- 2. " Temporary Relief From ASME Section III Requirements; Use ofLine Stopping Equipment on Essential Senice Water ASME Class 3 Piping; Byron Station, Units 1 and 2 (TAC Nos. M98514 and M98515)," NRC Safety Evaluation Report, R. A. Capra (NRC) to 1. M. Johnson (Comed), dated October 3,1997.
Pursuant to 10 CFR 50.55a(a)(3), Commonwealth Edison (Comed) is hereby requesting temporary relief for Byron Nuclear Generating Station Units 1 and 2 from the requirements of the 1974 Edition of American Society of Mechanical Engineers (ASME)
Boiler & Pressure Vessel Code,Section III, Subsections NA and ND, Articles NA-3700, ND-2100, ND-3100, ND-3500, and ND-4100. In Reference 1, Comed requested relief to install temporary line stopping equipment in eight individual 24" lines in the Essential Service Water (SX) Cooling Tower cell return piping lines. NRC approved Comed's request as documented in Reference 2. This additional teliefrequest (Attachment A) is , .I being submitted to expand the scope of the planned maintenance activity for two of the individual iterations to allow Comed to temporarily install mechanical line stopping v ,gL ' f 3
' 9003170278 980302 PDR ADOCK 05000454 l ~ _ o ,-n, lillillillHIElf!!E
u i
j l
equiprnent in two individual 48" diameter SX cooling tower cell return piping lines. This j
' would still allow for replacement of the cooling tower 24" diameter carbon steel riser piping with stainless steel piping for the two affected cells and the change out of each corresponding riser isolation motor operated valve (0SX163D and H). In addition, it
.would allow for replacement of the cooling tower hot water bypass isolation valves in pairs of two during each individual iteration, OSX162A/C and OSX162B/D, respectively.
Replacement of the cooling tower riser piping, the riser isolation valves, and the hot water bypass valves will provide significant improvement in the materiel condition of the safety- ;
related SX cooling tower at Byron Station.
Byron Station requests that this relief request be approved in a timely manner to support cooling tower work currently scheduled to begin in September,1998,
, if there are any additional questions, please contact Marcia Lesniak, Nuclear Licensing Administrator, at (630)-663-6484.
Sincerely, I
, s-K. L. Kofron 1 Station Manager ]
. Byron Nuclear Power Station j KLK/BA/cb Attachment A: Byron Station Temporary Relief Request from ASME Section III Requirements - Use of Line Stopping Equipment on Essential Service Water ASME Class 3 Piping Attachment B: Byron UFSAR Figure 9.2-2, sheet 11
]
cc: Regional Administrator-RIII Byron Project Manager - NRR Senior Resident inspector - Byron Office ofNuclear Safety-IDNS i
T 4
ATTACHMENT A Request for Temporary Relief from ASME Section III Class 3 Requirements for Byron Essential Service Water Cooling Tower Piping Lines Stop Installation.
Pursuant to 10 CFR 50.55a(a)(3), Commonwealth Edison (Comed) is hereby requesting temporary relief for Byron Nuclear Generating Station Units 1 and 2 from the requirements of the 1974 Edition of American Society of Mechanical Engineers (ASME)
Boiler & Pressure Vessel Code, Section 111, Subsections 'NA and ND, Articles NA-3700, ND-2100, ND-3100, ND-3500, and ND-4100. The relief request is being submitted to allow Comed to temporarily install mechanical line stopping equipment in individual i I
safety-related Essential Service Water (SX) cooling tower cell return piping lines. The temporary line stop equipment will be installed sequentially in two SX piping lines, over a period of approximately five to six days for each line stopping iteration. The line stopping l equipment would temporarily isolate the dual bypass lines and riser for a single SX cooling ;
tower cell from the remaining seven cooling tower cells and basin. This would allow for: I l
replacement of the downstream 24" diameter carbon steel riser piping with stainless steel piping; replacement and refurbishment of the downstream riser isolation motor operated valves, OSX163D and OSX163H; and replacement of hot water bypass valves OSX162A, D, C and D.
I Previously, Byron Station requested (Reference 1) and was granted temporary relief by l the NRC (Reference 2) from the requirements of the ASME code to allow for replacement f of all eight riser isolation valves and corresponding riser piping. Comed is requesting to expand the scope of that previous relief request for two of the valves, OSX163D and l OSX163H. By moving the temporary line stopping equipment upstream of the previous location for two of the eight iterations, it is possible to isolate the hot water bypass lines as well. This will enable replacement of bypass valves OSX162A and C (in conjunction with riser valve OSX163D) and OSX162B and D (in conjunction with riser valve OSX163H).
The entire scope of piping and valve replacements is planned because Byron Station has determined the minimum remaining life for the carbon steel riser piping is approximately five years. In addition, all eight of the riser isolation valves and four hot water bypass valves bave shown some degree of reduction in performance, which is causing operational difficulties during various plant configurations and ambient conditions. Therefore, installation of stainless steel riser piping and replacement / refurbishment of the riser isolation valves and hot water bypass valves will significantly improve both the materiel condition of piping and configuration flow control for the SX cooling tower.
The permanently installed line stop fittings, including the 36" diameter piping, flanges, and saddle material, will be installed in accordance with 1974 Edition of ASME Boiler &
Pressure Vessel Code,Section III, with Addenda and Code Cases in effect up to and including Summer 1975 Addenda with the exception that alternate hydrostatic pressure test requirements per Byron Station 2nd 10-year interval Inservice Inspection Relief Request 12R-15 will be utilized for post installation testing. This reliefrequest was AI
, recently approved by the NRC in Reference 3. This alternate pressure test is consistent with ASME Code Case N-416-1, " Alternate Pressure Test Requirement for Welded Repairs or Installation of Replacement items by Welding for Class 1,2, and 3, System,Section XI, Division 1" l
This relief request will demonstrate, per 10 CFR 50.55a(a)(3)i, that the proposed temporary installation of piping line stops will provide an acceptable level of quality and safety.
I. COMPONENT FOR WHICH RELIEF IS REQUESTED Essential Service Water (SX) Cooling Tower Return Piping The components for which temporary reliefis requested are piping lines OSX03CA-48 and OSX03CB-48. This request only expands the scope of the original request for two of the replacement iterations to allow for the replacement of all four hot water bypass valves in pairs of two, OSX162A/C and OSX1628/D, (see Attachment B for location of proposed line stop locations). With each line stopping iteration, the sequence of events for individual work activities will be scheduled so as to minimize the potential consequences of a faulted line stop.
The SX lines mn underground between the Auxiliary Building and the SX Cooling Tower Basin, returning SX system water from the plant to the basin. Flow is either directed to the SX cooling tower riser valves and piping, or through the hot water bypass valves and lines directly to the basin. The affected piping components provide a passive pressure boundary for the SX Cooling Tower at Byron Station, per the requirements of ASME Section Ill, Class 3. The SX Cooling Tower Basin is the primary component of the Ultimate Heat Sink (UHS) for Byron Station.
II. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Per the requirements of 10 CFR 50.55a(a)(3)(e), Quality Group C components j must meet the requirements for Class 3 components in Section 111 of the ASME I Boiler & Pressure Vessel Code. The afTected components listed in Section I of this document are safety-related, Quality Group C. The components are constmeted to meet the requirements of ASME Section Ill,1974 Edition, up to and including Su 1mer 1975 Addenda. Anicle NA-3700 requires material minufacturers and suppliers to have a Quality System Cenificate and Certified Materials Test Reports. Article ND-2100 requires that pressure retaining materials conform to the requirements of Tables I-7.0 and 1-8.0 of Appendix 1 and a Cer'ified Material Test Report be provided. Article ND-3100 defines the loading critetia tbr design conditions. In panicular, subarticle ND-3112.3(b) requires the effec's of earthquakes be considered in the design of components. Article ND-3500 requires the use of ASME material specifications for valves. Anicle ND-A2 1
.. 1 4100 requires the component manufacturer to certify by application of the appropriate Code symbol and completion of the appropriate Data Report in accordance with NA-8000. ND-4100 also requires certification of treatments, tests, and examinations.
111.~ PROPOSED ALTERNATIVE TO CODE REQUIREMENTS As an alternative to the ASME Section 111 requirements, Comed proposes to install temporary line stop equipment which meets or exceeds the temperature and pressure requirements of ANSI B16.5, Class 150. The line stop equipment will be provided by TDW Services, Inc., a vendor certified to International Organization for Standardization (ISO) 9001 and 9002 Quality Systems - Model for Quality Assurance.
In addition, Byron Station will implement a compensatory action during the temporary line stop installation to maintain elevated water levels in the SX Cooling Tower Basin and ensure sufficient water is available to mitigate the consequences of a temporary line stop failure. Finally, thorough job planning, on-line risk assessment, and operator briefing will be implemented for each iteration of the temporary condition to enhance overall plant safety. This will ensure that operators are fully aware of the necessary actions to be taken following a postulated failure of the line stop to provide cooling tower riser piping isolation.
IV. BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3), temporary reliefis requested o i the basis that j the proposed alternatives provide an acceptable level of quality and dety. Also, compliance with the current specified requirements would result in a har& hip for l Byron Station without a compensating increase in quality and safety.
Comed has determined that the temporary line stop equipment provides an equivalent alternative to the current ASME Section 111 requirements, for the planned temporary iterations. The original safety-related components within the SX system were designed per ASME Section 111, Class 3 or equivalent codes and standards, based on the criteria in ANSI N18.2a-1975. This criteria was used in the design and classification of the Byron Station SX system and components, as a supplement to Regulatory Guide 1.26 criteria.
The temporary line stop equipment has been designed and tested at higher pressures than the maximum anticipated pressure in the riser piping, at the location of the temporary line stop installation. For the anticipated SX system operating 4 configuration, the calculated maximuni differential pressure across the nearby downstream riser isolation valves (OSX163D and H) is 26 psig, which is significantly lower than the rated pressure of 140 psig for the 48" diameter line A3
9 stop plugging head. The line stopping equipment is rated for a maximum temperature of 1807. The SX piping was originally qualified to a design pressure of 125 psig and a design temperature of 1507.
Post installation verification ofline stopping equipment integrity will be verified prior to removing the riser isolation valves (0SX163D and H), their associated downstream piping, and the SX tower hot water bypass valves. The line stop equipment will be seismically restrained to prevent damaging the safety related SX piping system during a design basis earthquake. In addition, ASME Section 111, Class 3 blind flanges will be available on site to restore system integrity if a failure were to occur that required isolation of the cooling tower return line. A special procedure will be implemented which directs the work activities and provides guidance to station operators for the appropriate actions to take in the event of a failure of the line stop equipment.
Therefore, Comed has determined that the installation of the temporary line stop equipment provides an acceptable level of quality and safety, with respect to the ASME Section III requirements. This argument is further supported by the installation inspections, compensatory actions, and operator briefings that will be implemented during each line stopping iteration. In addition, to date, Byron Station has successfully completed the planned replacements for three of the eight cells per the previously referenced relief request. This provides additional assurance that the planned scope expansion for the two line stop iterations can be accomplished safely.
The UHS for Byron Station is required to be operable in all modes of operation.
The Byron Station Technical Specifications do not allow the SX Cooling Tower A or B trains to be isolated long enough to allow the scheduled work to be completed without shutting down and defueling both units. There is no existing isolation capability for the section of piping that is the subject of this relief request.
Also, Comed knows of no line stop vendors that can provide their equipment as ASME Section lil, Class 3 material. Therefore, relief from the requirements of ASME Section 111 is required to perform the scheduled maintenance activities.
Delaying or not performing the scheduled maintenance would prevent a significant improvement in the materiel condition of the SX Cooling Tower. Over the long term, this would represent a net decrea.;e in plant quality.
The SX system will be considered fully operable during the course of the modification work. Technical Specification 3/4.7.5," Ultimate Heat Sink"(UHS) requires, in part, that 6 SX fans are OPERABLE (high speed) and that SX pump discharge temperature be 5907. In other words, up to two cells can be unavailable with SX pump discharge temperature 590T and the UHS is considered operable. The modification work will directly affect only one cell at a time with installation of the linestop device at the location noted on Attachment B.
Note that the hot water bypass valves are typically used during cold weather operations in the winter to maintain minimum temperatures in the SX basin. It is A4
e not anticipated that hot water bypass operation will be required during the scheduled replacements. In the event further temperature control at the SX basin I
is required, the alternate train bypass valves wculd be available to plant operators.
l In summary , Comed believes that this relief request isjustified per the provisions l of 10 CFR 50.55a(a)(3) in that the proposed alternative temporary installation provides an acceptable level of quality and safety.
V. PER. LOD FOR WHICH RELIEF IS REQUESTED Reliefis requested for two temporaiy periods, during which the two riser isolation valves (0SX163D and H) along with two sections of riser piping will be replaced
- . and four hot water bypass valves in pairs of two (OSX162A/C and OSX162B/D) will be changed out. The relief request is only app!icable to the period of time in I
which the line stopping equipment is credited with maintaining system integrity and not the entire scope of thejob. This time period for reliefis anticipated to have a duration of approximately five to six days during each iteration.
The temporary line stop and piping replacement discussed in this request is i currently scheduled to begin in September,1998. The schedule is planned for this period to allow for plant operations at Byron Station to enjoy greater operational flexibility between Summer and Winter operation of the SX Cooling Tower.
VI. REFERENCES
- 1. " Request for Temporary Relief from ASME Section 111 Requirements -
Use of Line Stopping Equipment on Essential Service Water ASME Class 3 Piping," Byron letter 97-5081, D. B. Wozniak to NRC Document Control Desk, dated April 11,1997 and supplemented on July 10,1997.
- 2. " Temporary Relief From ASME Section Ill Requirements; Use of Line Stopping Equipment on Essential Service Water ASME Class 3 Piping; Byron Station, Units 1 and 2 (TAC Nos. M98514 and M98515), NRC Safety Evaluation Report, R. A. Capra (NRC) to 1. M. Johnson (Comed),
dated October 3,1997.
- 3. "Second 10-Year Inservice inspection Program Relief Requests - Byron Station, Units 1 and 2 (TAC Nos. M94830 and M94831), NRC Safety Evaluation, R. A. Capra (NRC) to O. D. Kingsley, (Comed), dated l January 13,1998.
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