|
---|
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 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 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 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 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 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:NRC TO STATE/LOCAL GOVERNMENT
MONTHYEARML20206C0631988-11-0707 November 1988 Responds to Re Enrichment of Naturally Occurring Radionuclides in Proposed Alchemie Facilities.Company Advised That Facilities Subj to State of Tn Regulations ML20205C3521988-09-23023 September 1988 Final Response to FOIA Request for Documents Re Plant. Forwards App D Documents.App D Documents Also Available in PDR ML20154M5051988-09-22022 September 1988 Responds to Re Rev to Info on Applicability of 10CFR50 Applications for Enriching Stable Isotopes.Listed Observations Provided Based on Info in Ltr & 880914 Telcon ML20236V7341987-12-0101 December 1987 Partial Response to FOIA Request for Documents.Forwards Documents Listed in App C ML20195G6881987-11-0202 November 1987 Responds to to Chairman Zech Re Plant Restart W/O Effective Radiological Emergency Response Plan.Improvements Currently Underway,Based on 870806 FEMA Rept Listing Six Areas of Concern.Plant Will Not Start Until Issues Resolved ML20236B8491987-10-21021 October 1987 Forwards Nrc/State of Nc Environ Monitoring Appraisal on 871005-06.State Met All Obligations in 1986 Contract W/ Exceptions of H-3 Analyses in Surface Waters & I-131 Analyses in Milk,Both Required Lower Detection Limits ML20235S6281987-10-0101 October 1987 Responds to Supporting Request from Smud That Commission Hold Hearing in Sacramento,Ca Re Safety of B&W Nuclear Plants.Response to Concerns Will Be Addressed When Response to Ucs Petition Issued ML20151W0201987-09-0909 September 1987 Summarizes 870521 Meeting W/Massachsetts Officials Re Restart of Facility.Understands That Prior to Decision on Restart,Further Public Meetings Will Be Held ML20238B2991987-08-24024 August 1987 Responds to Expressing Concern That Mgt & Safety Problems Recently Identified at Facility Could Endanger Constituents.Nrc Ready to Take Appropriate Action If Performance Degrades to Levels Endangering Public ML20235G2511987-06-16016 June 1987 Discusses Manner NRC Used to Select Sample of safety-related Concerns in Safeteam Files for Review,Per 870528 Request. Safety Concerns Properly Addressed.Applicable Insp Repts & Related Info Encl ML20213G5001987-03-26026 March 1987 Submits Comments Re Legislation Proposing Placement of Nuclear Safety Inspector at Facility.Mou May Not Be Necessary Due to Precision & Detail of Legislation ML20237C9261987-03-17017 March 1987 Responds to Questions Raised at 870116 Meeting in Bethesda,Md Re Emergency Response Data Sys (Erds).Daily Status Repts Cannot Be Provided Due to Limitations on NRC Computer Sys.Info on Status of SPDS for State Plants Encl ML20237D2331987-02-24024 February 1987 Responds to Questions Raised at 870116 Meeting in Bethesda,Md Re Emergency Response Data Sys.Implementation Status of SPDS for State Nuclear Power Plants Listed ML20215G2071987-02-20020 February 1987 Responds to Expressing Concerns Re 870104 Newsday Article on Plant Emergency Plan.Given Unwillingness of State & Local Govts to Participate in Development of Plan,Approved Util Offsite Emergency Plan Only Such Plan Available ML20211C5251987-02-0606 February 1987 Discusses NRC Analysis of Licensing Schedules for Facility, Per Util 870202 Request for NRC Statement to State of Ca. NRC Sept 1981 - Feb 1982 Monthly Repts to Congress Re Licensing Projections for Pending OL Applications Encl ML20214U1621986-12-0303 December 1986 Responds to FOIA Request to DOJ for Records Re DOJ Investigation of Util Role in Siting,Licensing & Constructing Diablo Canyon.Forwards App a & B Documents. Documents Also Available in PDR IA-86-699, Responds to FOIA Request to DOJ for Records Re DOJ Investigation of Util Role in Siting,Licensing & Constructing Diablo Canyon.Forwards App a & B Documents. Documents Also Available in PDR1986-12-0303 December 1986 Responds to FOIA Request to DOJ for Records Re DOJ Investigation of Util Role in Siting,Licensing & Constructing Diablo Canyon.Forwards App a & B Documents. Documents Also Available in PDR ML20206U8151986-10-0101 October 1986 Ack Receipt of in Response to NRC 851203 Acceptance Appraisal & Concerns.Responses Acceptable. Implementation of Corrective Actions Will Be Reviewed During Future Performance Appraisal ML20203N3241986-09-17017 September 1986 Responds to Re Mitchell Allegations Re as-built Drawings at Byron Station.Allegations Will Be Vigorously Pursued.Recommendation to Pursue Investigation at Byron 2 & Braidwood 1 & 2 Premature ML20209E3901986-09-0202 September 1986 Responds to 860815 Request That Perry Not Be Licensed for Full Power & Davis-Besse Not Be Permitted to Achieve Full Power Operation Until State of Oh Review of Emergency Evaluation Plans Completed ML20215B2851986-09-0202 September 1986 Requests Addl Info Clarifying State of Oh Position Re Participation in Perry Evacuation Plan Prior to 860905 Meeting to Consider Issuance of Full Power License ML20197F8291986-04-15015 April 1986 Forwards Population Density Map for Emergency Planning Zone. Map Developed by ORNL by Projecting from 1982 Census Data & Must Be Taken as Estimate.W/O Encl ML20203J0071986-04-15015 April 1986 Addresses Questions & Concerns on Mod 4 to Agreement NRC-31-83-671 Re Interim Preoperational Environ Surveillance Programs at Facilities,Per Jf Thiel & Subsequent Telcons.Funding Levels Detailed ML20197F0381986-04-15015 April 1986 Forwards Population Density Map for Emergency Planning Zone. Map Developed by ORNL by Projecting from 1982 Census Data & Must Be Taken as Estimate.W/O Encl ML20199J8471986-03-27027 March 1986 Forwards Population Density Maps for Facilities Emergency Planning Zones.Maps Developed by ORNL from 1980 Census Data & Must Be Taken as Estimate.W/O Encl ML20199J8951986-03-27027 March 1986 Forwards Population Density Maps for Facilities Emergency Planning Zones.Maps Developed by ORNL from 1980 Census Data & Must Be Taken as Estimate.W/O Encl ML20199J8971986-03-27027 March 1986 Forwards Population Density Maps for Facilities Emergency Planning Zones.Maps Developed by ORNL from 1980 Census Data & Must Be Taken as Estimate.W/O Encl ML20199J9021986-03-27027 March 1986 Forwards Population Density Maps for Facilities Emergency Planning Zones.Maps Developed by ORNL from 1980 Census Data & Must Be Taken as Estimate.W/O Encl ML20142A1111986-02-21021 February 1986 Forwards Appraisal of State of Nc Program for Performing Environ Monitoring Activities at Listed Plants,Including Assessment of Facilities,Equipment,Program Staffing & Personnel Qualification.Program Meets NRC Requirements ML20133P8001985-10-30030 October 1985 Forwards Hb Tucker & H Thompson Draft Ltrs & Environ Assessment Re Duke Power Co Request for Approval of Procedure for Disposal of Radioactively Contaminated Wood, for Review.W/O Encl ML20137E9531985-08-20020 August 1985 Responds to & 850809 Telcon Re Environ Surveillance Program Under Cooperative Agreement NRC-31-83-671.Program Satisfactory,Based on Accumulated Baseline Environ Data Collected During Jan 1984 - Aug 1985 ML20213F3811985-07-30030 July 1985 Responds to 850711 & 15 Requests for Suspension of Low Power Testing Program at Facility & Review of Training of Personnel & Condition of Equipment to Determine If Plant Safe to Test at Low Power.Plant Safely Operated by Util ML20133M1301985-07-0303 July 1985 Further Response to FOIA Request for Documents Re Drafting of IE Bulletins 79-14 & 80-11.Forwards App B Documents. Documents Also Available in Pdr.App C Documents Already in PDR ML20128Q5291985-06-18018 June 1985 Responds to FOIA Request for Documents Re Drafting of IE Bulletins 79-14 & 80-11.Forwards App a Documents.App a Documents Also Available in PDR ML20129A9571985-05-17017 May 1985 Informs That Region III Will Not Conduct Public Meetings Concerning 850410 Events Re Rupture of Oa Boric Acid Evaporator Rupture Disk & Reactor Trip Caused by Drop of Four Control Rods.Events Will Be Documented in Future Rept ML20206H0951985-02-0505 February 1985 Forwards Insp Rept 50-482/84-18 in Response to Five Nonspecific Allegations Forwarded in .W/O Rept ML20136G6271984-12-28028 December 1984 Notifies of 850110 Meeting in Springfield,Il,Per 841220 Request,To Discuss Lack of Documentation for Installed Piping Matl.Other State Agencies Invited.Related Info Encl ML20128Q7451984-12-0707 December 1984 Discusses Util Program for Early Completion of Const & rate-setting Procedures.Danger in Speeding Up Const Noted IA-84-354, Discusses Util Program for Early Completion of Const & rate-setting Procedures.Danger in Speeding Up Const Noted1984-12-0707 December 1984 Discusses Util Program for Early Completion of Const & rate-setting Procedures.Danger in Speeding Up Const Noted ML20134M9201984-07-13013 July 1984 Forwards Certification of Pollution Control Facilities,Per Util 840529 & 0703 Submittals.Portions of Certification Abate or Control Atmospheric Pollutants or Contaminants ML20062A0881982-07-0101 July 1982 Extends Invitation to Attend 820721 Meeting of Senior Public Officials to Discuss Regulatory Program for Nuclear Power Plants & Resident Insp Program.Agenda Encl ML20133M9961979-10-23023 October 1979 Ack Receipt of Requesting NRC Present Testimony on Me Puc Investigation of Facility.W Russell Will Meet W/Me Puc,Complainants & Util on 791025 in Augusta,Me to Discuss Issues Outlined ML20237J6771975-04-22022 April 1975 Forwards RW Caudle to GL Madsen & GL Madsen to Pg Brittain ML20134B4451975-04-0808 April 1975 Forwards Documents Listed on Encl a Re Facilities ML20237J7061975-04-0707 April 1975 Forwards GL Madsen Transmitting Insp Repts 50-445/75-05 & 50-446/75-05 ML20237J5401974-04-10010 April 1974 Forwards Pg Brittain Responding to Insp Repts 50-445/73-02 & 50-446/73-02 & EM Howard Forwarding Insp Repts 50-445/74-01 & 50-446/74-01 ML20237J6411974-01-28028 January 1974 Forwards EM Howard Transmitting Insp Repts 50-445/73-02 & 50-446/73-02 ML20234A9111971-10-21021 October 1971 Forwards Oct 1964 Rept to Aec,Entitled, Seismic Effects on Bodega Bay Reactor, AEC Press Announcement Issued at Same Time,Rept by ACRS on Proposed Bodega Bay Facility & Summary Analysis of Safety Aspects of Proposed Plant.W/O Encls ML20235C3291970-05-0404 May 1970 Forwards Listed Items for Info,Including Transmitting Repts on Proposed Inservice Insp Program & Proposed Containment Design Pressure for Brunswick Steam Electric Plant. Info Will Be Included in FSAR ML20234E6761964-12-0404 December 1964 Advises That,Per Encl PG&E & Notice,Util Has Withdrawn Application for License to Construct & Operate Reactor at Bodega Bay,Ca.W/O Encls 1988-09-23
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 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 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 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) 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 ML20209H5141999-07-14014 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle 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 ML20196H0631999-06-28028 June 1999 Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20196D4591999-06-18018 June 1999 Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20196A6671999-06-17017 June 1999 Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff ML20195J3741999-06-14014 June 1999 Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative ML20195F3231999-06-0909 June 1999 Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration 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 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 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 ML20207A5891999-05-20020 May 1999 Forwards Insp Repts 50-456/99-05 & 50-457/99-05 on 990405-23.Two non-cited Violations Identified 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 ML20206U4641999-05-18018 May 1999 Responds to Util 990517 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3.0.3. Documents 990516 Telcon with Licensee Re NOED ML20207B8751999-05-18018 May 1999 Responds to Ltr Dtd 990225,expressing Concerns That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazards at Some Commercial Nuclear Power Plants in Us ML20206N4791999-05-13013 May 1999 Forwards RAI Re 980529 Amend Request for Byron & Braidwood to Credit Automatic PORV Operation for Mitigation of Inadvertent SI at Power Accident.Response Requested 60 Days After Receipt Date ML20206Q5321999-05-11011 May 1999 Forwards Insp Repts 50-456/99-06 & 50-457/99-06 on 990302-0413.Configuration Control Error Resulted in Isolation of Unit 1 Emergency Boration Flow Path Through Designated Boric Acid Pump for Period of 3 H Occurred ML20206H8161999-05-0505 May 1999 Confirms Discussion Re Meeting to Be Conducted on 990527 at Braidwood Station Training Building.Meeting Will Discuss Braidwood Station Performance as Described in Most Recent Plant Performance Review 1999-09-08
[Table view] |
Text
>
e s
-t 4 d
BEP 1 7 1986-Illinois Department of Nuclear Safety ATTN: Dr. Terry R.-Lash, Director 1035 Outer Park Drive
- Springfield, IL 62704 _
Dear Dr.. Lash:
This is 'in -response to your letter of August 22,1986, concerning l Mr. Schuyler Mitchell's recent allegations regarding Consonwealth Edison
. Company's (CECO) as-built drawings at the Byron Station. During the Springfield .
meeting of August 12, 1986, members of my staff emphasized to you the importance placed on this allegation by the NRC. Let me personally re-emphasize this point to you. Mr. Mitchell's allegation, like the many other allegations received by this office, will be vigorously pursued to determine whether there are any.
- safety concerns or violations of NRC regulations governing the construction and/or operation of a nuclear power facility.
Your letter expressed the -view that the proposed NRC investigation of Mr. Mitchell's allegations is too narrow and-limited in scope to sufficiently address the concerns. Specifically, you recommend that the initial investigation should involve a complete quadrant in the containment for Byron 1 and that similar investigations should be considered at Byron' 2 and at Braidwood 1.and 2. In our view, it is premature to implement the extensive program you suggest until the relative technical significance of Mr. Mitchell's allegations can be established. As you know we initiated an inspection, .
which is being observed by your staff of Byron Unit 1 on September 15, 1986. .!
In addition to potential areas of concern identified to us by Mr. Mitchell (about 20' dimensions) we plan to expand the inspection sample considerably. .
The expanded sample will be safety-related systems (such as safety. injection '
and component cooling water) located inside Unit 1 and Unit 2 Containment Buildings as well as those' located in the Auxiliary Building. The resulting
,. dimensions checked will be in the range of 400 to 600. This, of course,
- . is in addition to the inspections-performed during the period of -
t' August:13, 1984 through April 2, 1985,'where similar issues were inspected and l l reported in Inspection Report Nos. 50-454/84-51 and 50-455/84-35-(we previously ,
j provided you a copy of this report). .
I
, The dimensions'obtained from these inspections will be compared to as-built
_ drawings and any significant discrepancies will'be evaluated. Once this effort
! ' is completed and the relative safety significance is determined, a decision will i be made either to continue to expand or to terminate our as-built verification efforts. This represents a logical and pragmatic approach to resolving the allegation based on the infonnation now available, and is consistent with NRC's
! handling of past similar allegations.
! With regard to your questions about NRC's requirements for the accuracy of l "as-built" drawings at the time a plant is licensed to operate and thereafter ,
L l 8609230314 860917 l
PDR ADOCK 05000454
SEP 171986 Illinois Department of Nuclear 2 Safety throughout the plant's operating lifetime", enclosed is a copy of IE Bulletin 79-14 for your review. Paragraph 4.D of the enclosure states:
. Revise documents to reflect the as-built conditions in plant, and describe measures which are in effect which provide assurance that future modifications of piping systems, including their supports will be reflected in a timely manner in design documents and the seismic analysis.
It has been our policy to have each licensee develop as well as defend accuracy requirements on a case-by-case basis. The NRC evaluates these requirements also on a case-by-case basis using best engineering judgement.
As you are aware, a member of your staff is accompanying us during our inspection efforts on this allegation. We look forward to his participation until final resolution has been achieved. We hope that this information alleviates your concerns and explains our position.
. Sincerely, Ortstant n)gnng by L*.ws G. Kapptog.
James G. Keppler Regional Administrator
Enclosure:
As stated cc w/ enclosure:
V. Stello, ED0 G. W. Kerr, OSP G. H. Cunningham, OGC J. M. Taylor, IE J. W. McCaffrey, Chief, Public Utilities Division i
R I RI RIII RIII YO G ula/jk Dan Ison I. son e/1ello Lds 09/f7/86 09/ 7/86 09/l'7/86 09/f1/86 09// 7/86 yfRbI RIII f3 E I y NR Davis pler Ta or Jordan' NovaT 09// /86 09/ /7/86 / 86 09/j7/86 09//7/86 l
l i
S w y , - .. - . ~ - . _ _ _ , ,. .. .. ._ ,
.. q e
(
U.S. NUCLEAR REGULATORY COMMISSION
- OFFICE OF INSPECTION AND ENFORCEMENT REGION III July 2, 1979 IE Bulletin No. 79-14 SEISMIC ANALYSES FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS Description of Circumstances:
Recenty tv., issues were identified which can cause seismic analysis of safety-related piping systems to yield nonconservative results. One issue involved algebraic summation of loads in some seismic analyses. This was addressed it.
show cause orders for Beaver Valley, Fitzpatrick, Maine Yankee and Surry. It was also addressed in IE Bulletin 79-07 which was sent to all power reactor licensees.
The other issue involves the accuracy of the information input for seismic analyses. In this regard, several potentially unconservative factors were discovered and subsequently addressed in IE Bulletin 79-02 (pipe supports) and 79-04 (valve weights). During resolution of these concerns, inspection by IE and by licensees of the as-built configuration of several piping systems revealed a number of nonconformances to design documento which could potentially affect the validity of seismic analyses. Nonconformances are identified in Appendix A to this bulletin. Because apparently significant non-conformances to design documents have occurred in a number of plants, this issue is generic.
The staff has determined, where design specifications and drawings are used to obtain input information for seismic analysis of safety-related piping systems, that it is essential for these documents to reflect as-built con-i figurations. Where subsequent use, damage or modifications affect the con-l dition or configuration of safety-related piping systems as described in documents from which seismic analysis input information was obtained, the l
licensee anast consider the need to re-evaluate the seismic analyses to con-t sider the as-built configuration.
l l
l l
l l
l l
f
]f) Ulwug'l k
s - . . ~ .. w _ m .
. ,.q~
. . ( ( ;
f
4 July 18, 1979 )
IE tulletin No. 79-14 -
Page 2 of 3 Revision 1 Action to be taken by Licensees and Pemit Holders:
All power reactor facility licensees and construction pemit holders are requested to verify unless verified to an equivalent degree within the last 12 months. that the seismic analysis applies to the actuaT configura-tion of safety-related piping systems. The safety related pipin Seismic Category I systems as defined by Regulatory SeismicGuide 1.29. g Design Classification" Revision 1 dated August 1,1973 or as defined in the applicable FSAR. The action items that follow apply to all safety related pipinc 21/2-inches in diameter and creater and to seismic Category I piping, regarclass of size which was dynamically analyzed by computer.. For older plants, where Seismic Category I requirements did not exist at the time of licensing, it must be shown that the actual configuration of Aldid safety-
.related systems, utilizina 01pina 21/2 inches in diameter and areater, meets design requirements.
Specifically, each licensee is requested to:
- 1. Identify inspectior, elements to be used in verifying that the seismic analysis input infomation conforms to the actual configuration of safety-related systems. For each safety-related system, submit a list of design documents, including title identificaticn msnber, revision and date, which were sources of input infomation for the seismic analyses. Also submit a description of the seismic analysis input infonmation which is contained in each document. Identify systems or portions of systems which are planned to be inspected during each sequential inspection identified in items 2 and 3. Submit all of this infonnation within 30 days of the date of this bulletin.
- 2. For portions of systems which are nomally accessible *. inspect one system in each set of redundant systams and all nonredundant systens for con-fomance to the seismic analysis input infonnation set forth in design documents. Include in the inspection: pipe run geometry; support and restraint design, locations, function and clearance (including floor '
and us11 penetration); estiedments (excluding those covered in IE i
Bulletin 79-02); pipe attachements; and valve and valve operator locations -and weights (excluding those covered in IE Bulletin 79-04).
Within 60 days of the date of this bulletin, submit a description of the results of this inspection. Where nonconfonnances are found which affect operability of any system, the licensee will ex;iedite coupletion of the inspection described in Item 3.
'Homally accessible refars to those areas of the plant which can be entered during reactor operation.
--,-- -y._ __ . . , , . _ . - . _ . , , , , , , . . . .,.,_-m__ _. - , - , _ , _ , _ _ . - _ , . _ . - _ , _.,,..- - _. -
>_....-..-....._._._.....,_.m,......_.c .
(
('
IE Bulletin No. 79-14 July 2, 1979 Page 3 of 3
- 3. In accordsuce with Item 2, inspect all other normally accessible safety-related system: and all normally inaccessible safety-related systems.
Within 120 days of the date of this bulletin, submit a description of the results of this inspection.
- 4. If nonconformances are identified:
A. Evaluate the effect of the nonconformance upon system operability under specified marthquake loadings and comply with applicable action statements in your technical specifications including prompt report-ing.
B. Submit an evaluation of identified nonconformances on the validity of piping and support analyses as described in the Final Safety Analysis Report (FSAR) or other NRC approved documents. Where you determine that reanalysis is necessary, submit your schedule for: (i) completing the reanalysis, (ii) comparisons of the results to FSAR or other NRC approved acceptance criteria and (iii) submitting descrip-tions of the results of reanalysis.
C. In lieu of B, submit a schedule for correcting nonconforming systems so that they conform to the design documents. Also submit a descrip-tion of the work required to establish conformance.
D. Revise documents to reflect the as-built conditions in plant, and describe measures which are in effect which provide assurance that future modifications of piping systems, including their supports, will be reflected in a timely manner in design documents and the seismic analysis.
Facilities holding a construction periait shall inspect safety-related systems in accordance with Items 2 and 3 and report the results within 120 days.
Reports shall be submitted to the Regional Director with copies to the i
Director of the Office of Inspection and Enforcement and the Director i of the Division of Operating Reactors, Office of Nuclear Reactor Regulation, Washington, D.C. 20555.
Approved by GAO (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for generic problems.
Enclosures:
- 1. Appendix A
- 2. Listing of IE Bulletins Issued in Last Twelve Months i
_ _ _ _ _ _ . .- =. _ _ . . . . . . _ . .
~. . .,_ _. . _ _ . q f
i APPENDIX A PLANTS WITH SIGNIFICANT DIFFERENCES BETWEEN ORIGINAL DESIGN AND AS-BUILT CONDITION OF PIPING SYSTI!MS Difference Remarks Plant Surry 1 Mislocated supports. As built condition Wrong Support Type. caused majority of pipe Different Pipe Run - overstress problems, not Geometry, algebraic summation.
Beaver Valley Not specifically identified. As built condition resulted Licensee reported "as-built in both pipe and support conditions differ signifi- overstress.
cantly from orginal design."
IE inspection identified Licensee is using as Fitzpatrick built configuration differences similar to Surry. for reanalysis.
Pilgrim Snubber sizing wrong. Plant shutdown to restore Snubber pipe attachment original design condition.
welds and snubber support assembly nonconformances.
Brunswick 1 and 2 Pipe supports undersize. Both units shutdown to restore original design condition.
Pipe supports not built Supports were repaired Ginna during refueling outage.
to original design, St. Lucie Missing seismic supports. Install corrected Supports on wrong piping. supports before start up from refueling.
2.-.- ,,e--- ,-,._.-.,.-.em,,-..m.-___..m.,._,_,.,,m,.,-. ......-.r.-,_,_._.--... . , . . , , , _ , . . - - - . . , - . . - , , , . . - - . - . - . ,
.. , _ .. .. __ . - m _._.._..._..g..z_........__.....,
t .'
t Page 2 APPENDIX A Plant Difference Remarks Nine Mile Point Missing seismic supports. Installed supports before startup from refueling.
Indian Point 3 Support location and Licensee performing as support construction built verification to be deviations. completed by July 1.
Davis-Besse Gussets missing from main Supports would be over-Steam Line Supports. stressed. Repairs will be completed prior to start-UP-
7~--.e~.---....._=-,._...-.-....--- . . _ -
-_a e
- SSINS: 6820 Accessiee No:
5 3399000969 ==="-'
e
UNITED STATES
, NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT f
, WASHINGTON, D.C. 20555 -
f 1
August 15, 1979 f
. k Supplement IE Bulletin No. 79'-14 SEISMIC ANAI.YSIS FOR AS-3UILT SAFETY-RELATED PIPING SYSTEMS Discription of Circumstances:
l IE Bulletin No. 79-14 was issued on July 2,1979 and revised on July 18, 1979.
The bulletin requested licensees to take certain actions to verify that seismic
! analyses are applicable to as-built plants. This supplement to the bulletin provides additional guidance and definition of Action Items 2, 3, and 4. l To comply with the requests in IE Bulletin 79-14, it will be necessary for licensees to do the following: ,
l
- 2. Inspect Part of the Accessible Piping For each system selected by the licensee in accordance with Item 2 of the Bulletin, the licensee is expected to verify by physical inspection, to the extent practicable, that the inspection elements
~
meet the acceptance criteria. In performing these inspectons, the licensee is expected to use measuring techniques of sufficient accuracy ;
to demonstrate that acceptance criteria are met. Where inspection l elements important to the seismic analysis cannot be viewed because of thermal insulation or location of the piping, the licensee is expected to remove thermal insulation or provide access. Where physical inspection
- l. is not practicable, e.g., for valve weights and materials of construction, I l
the license is expected to verify conformance by inspection of quality
, assurance records. If a nonconformance is found, the licensee is expected l
in accordance with Item 4 of the Bulletin to perform an evaluation of the ;
significance of the nonconformance as rapidly as possible to determine whether or not the operability of the system might be jeopardized during a safe shutdown earthquake as defined in the Regulations. This evaluation is expected to be done in two phases involving an initial engineering judgement (within 2 days), followed by an analytical engineering evaluation (within 30 days). Where either phase of the evalustion shows that system operability is in jeopardy, the licensee is expected to meet the applicable
! g technical specification action statement and complete the, inspections required by Item 2 and 3 of the Bulletin as soon.as possple. The licensee
- 9:.S must report the results of these inspections in accordanch with the . require ,
i
~~
ments for content and schedule as given in Item:2 and 3 y the Bulletin.
9 l
. , - . _ _ , _ . _ , . - , - . . _ . . . _ - - _ _ . .,m___,m.y.m__....,,,,,,_,,,,,_._,_.,,_.~.-,,-.r,. , - - , ,
,..._..-....z-.......-..~....~..~.........._........
~
Supplement IE Bulletin No. 79-14 Page 2 of 2
,- August 15, 1979 .
e
, I3. Inspect Remainina Pipina -
The licensee is expected to inspect, as in Item 2 above, (he remaining safety-related piping systems which were seismically analized and to
. report the results in accordance with the requirements fos content and
( schedule as given in Item 3 of the Bulletin.
. Evaluate Noneoeformances With regard to Item 3A for the Bulletin, the licensee is expected to include in the initial engineering judgement his justification for continued reactor operation. For the analytical engineering evaluation, the licensee is expected to perform the evaluation by using the same analytical technique used in the seismic analysis or by an alternate, less complex technique provided that the licensee can show that it is conservative.
If either part of the evaluation shows that the system may not perform its intended function during a design basis earthquake, the licensee must promptly comply with applicable action statements and reporting requirements in the Technical Specifications.
4B. Submit Nonconformance Evaluations The licensee is expected to submit evaluations of all nonconformances and, where the licensee concludes that the seismic analysis may not be conservative, submit schedules for reanalysis in accordance with Ites 4B of the Bulletin or correct the noncomformances.
4C. Correct Nonconformances If the licensee elects to correct nonconformances, the licensee is expected to submit schedules and work descriptions in accordance with Ites 4C of the Bulletin.
4D. Improve Qualtiy Assurance If noncomformances are identified, the licensee is expected to evaluate and improve quality assurance procedures to assure that future modifica-tions are handled efficiently. In accordance with Item 4D of the Bulletin, the licensee is expected to revise design documents and seismic analyses in a timely manner.
he schedsle for the action and reporting requirements given if the Bulletin gas originally issued remains unchanged. .L Approved by CAO, B180225 (R0072), clearance expires 7/31/80. 4pproval was given vnder a blanket clearance specifically for identified generic $roblems.
Enclosure:
Listing of IE Bulletins Issued in 1.ast 6 Months
_ i. _ ,,, , _ i i ,;, ,,
%. ~ ~ . d ~ .. . . . _ . .. ... . .. _ .
SSINS: 6820 Accesstion No.: J800000609=-
UNITED STATES l
NUCLEAR REGULATORY COMISSION '
0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 September 7, 1979
- IE Bulletin No. 79-14 Supplement 2 SEISMIC ANALYSIS FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS Description of Circumstances:
IE Bulletin No. 79-14 was issued on July 2, revised on July 18, and first supplemented on August 15, 1979. The bulletin requested licensees to take certain actions to verify that seismic analyses are applicable to as-built plants. Supplement 2 provides the following additional guidance with regard to implementation of the bulletin requirements:
Nonconformances One way of satisfying the requirements of the bulletin is to inspect safety-related piping systems against the specific revisions of drawings which were used as input to the seismic analysis. Some architect-engineers (A-E) however, are recommending that their customers inspect these systems against the latest revisions of the drawings and mark them as necessary to define the as-built configuration of the systems. These drawings are then returned to the AE's offices for comparison by the analyst to the seismic analysis input. For licensees taking this approach, the seismic analyst will be the person who will identify nonconformances.
The first supplement to the bulletin provided guidance with regard to evaluation of nonconformances. That guidance is appropriate for licensees inspecting against later drawings. The licensee should assure that he is promptly notified when the AE identifies a nonconformance, that the initial engineering judgment is completed in two days and that the analytical engineering evaluation is completed in 30 days. If either the engineering judgement or the analytical engineering evaluation indicates that system operability is in jeopardy, the licensee is expected to meet the applicable technical specification action statement.
Visual Approximations Some licensees are visually estimating pipe lengths and other inspection elements, and have not documented which data have been obtained in that way.
Visual estimation of dimensions is not encouraged for most measurements; however, where visual estimates are used, the accuracy of estimation must be within toler-ante requirements. Further, in documenting the data, the licensee must specif-ically identify those data that were visually estimated.
i
u._..-z-.a._..._,a...u.o......__......~.__....._.....-...-...
IE Bulletin No. 79-14, Supplement 2 September 7, 1979 Page 2 of 2 Thermal Insulation In many areas, thermal insulation interferes with inspection of pipe support details, i.e. attachment welds, saddles, support configuration, etc. In some areas, the presence of thermal insulation may result in unacceptably large ur) certainties for determination of the location of pipe supports.
W6ere themal insulation obstructs inspection of support details, the insulation should be removed for inspection of a minimum of 10% of the obstructed pipe supports in both Item 2 and 3 inspections. In the Item 3 response, the licensee should include a schedule for inspecting the remaining supports.
Where necessary to determine the location of pipe supports to an accuracy within design tolerances, thermal insulation must be removed.
Clearances For exposed attachments and penetrations, licensees are expected to measure or estimate clearances between piping and supports, integral piping attachments (e.g. lugs and gussets) and supports, and piping and penetrations. Licensees are i
not expected to do any disassembly to measure clearances.
Loose Bolts Loose anchor bolts are not covered by this bulletin, but are covered by IE Bulletin No. 79-02. Any loose anchor bolts identified during actions taken for '
this bulletin should be dispositioned under the requirements of Bulletin No. 79-02.
Other loose bolts are to be treated as nonconformances if they invalidate the seismic analysis; however, torquing of bolts is not required.
Difficult Access
(
Areas where inspections are required by the Bulletin but are considered impractical even with the reactor shutdown, should be addressed on a case by case basis. Information concerning the burden of performing the inspection and the safety consequence of not performing the inspection should be documented by the licensee and forwarded for staff review.
Schedule The schedule for the action and reporting requirements given in the Bulletin as originally issued remains unchanged.
Enclosure:
List of IE Bulletins Issued in the Last Six Months i