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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML1108302361993-05-0303 May 1993 Forwards Rev 1 to NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. Submittal Made on Behalf of Eight Utils Having Enterprize EDGs for Emergency Standby Ac Power ML18010A9501992-12-0808 December 1992 Forwards NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. Submittal Made on Behalf of Eight Utils Having Enterprise EDGs for Emergency Standby Ac Power ML18036A8701992-09-30030 September 1992 Forwards Updated Distribution Lists for Brown Ferry & Bellefonte Nuclear Plants to Reflect Recent Reorganizational Changes.Lists Should Replace Lists Sent on 920515 ML20086K0871991-12-11011 December 1991 Requests Mod of Periodicity in Which Util Conducts Annual Practice Sessions for Fire Brigade Personnel.Rev to Commitment C.3.D.6(b) of BTP Cmeb 9.5-1 Will Permit Practice Session to Be Held Annually ML20065R6891990-12-12012 December 1990 Advises That Util Intends to Reopen Simulator Training Facility at Plant Site Near Hollywood,Al.Requests That Existing NPDES Permit AL0024635 Be Modified to Include Simulator Training Facility Outfall ML20247C3771989-09-0606 September 1989 Confirms Understanding of Applicability of NRC Requirements Developed During Deferral Period of Plant ML20245D9851989-06-22022 June 1989 Forwards 21 Insp Rept Executive Summaries,Per NRC Contract NRC-03-87-029,Task Order 037.Individual Quality Evaluations of Insp Repts Also Prepared ML20246E3551989-06-21021 June 1989 Submits Plan for Quadrex Corp to Lease Plant,Complete Facility,Operate Facility,Sell Power & Eventually Return Plant to Tva.Topic Will Be Discussed at 890711 Meeting ML20248K5451989-04-0505 April 1989 Responds to 890224 & 0322 Ltrs Re NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. NRC Agrees W/Suggestion for 890407 Meeting to Discuss Util Schedular Proposal ML20247G5411989-03-24024 March 1989 Informs of Recent Changes Made within Mgt Structure of Util Organization.Util Reorganization Efforts Aimed at Implementing Changes Necessary to Reflect Reorientation from Design & Mod ML20247E4941989-03-10010 March 1989 Forwards Insp Repts 50-438/89-01 & 50-439/89-01 on 890111.No Violations or Deviations Noted ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20236V7341987-12-0101 December 1987 Partial Response to FOIA Request for Documents.Forwards Documents Listed in App C ML20236V2801987-11-20020 November 1987 Informs That on 871019,Director of NRR Issued Encl Director'S Decision Which Declined to Institute Proceedings Requested by Ucs Petition,In Response to 870731 Request.W/O Encl NUREG-1231, Forwards NUREG-1231, SER Re B&W Owners Group Plant Reassessment Program. NRC Unable to Reach Final Conclusion on Acceptability of Human Factors Portion of Program. Consideration of NRC Recommendations Requested1987-11-0606 November 1987 Forwards NUREG-1231, SER Re B&W Owners Group Plant Reassessment Program. NRC Unable to Reach Final Conclusion on Acceptability of Human Factors Portion of Program. Consideration of NRC Recommendations Requested 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 ML20235L3261987-09-29029 September 1987 Responds to to Zech Informing That Ltrs Recently Received from Two Members of Smud Board of Directors Requesting Adjudicatory Hearing Does Not Reflect Views of Majority of Board.Nrc Responded to Kehoe & Smeloff Re Issue ML20235J5351987-09-28028 September 1987 Responds to Constituent Tf Gross Ltr Supporting Ucs 870210 10CFR2.206 Petition to Suspend OLs & CPs of Any Util Operating or Bldg Nuclear Power Reactors Designed by B&W,Per 870803 Request.Nrc Statements Re Plants Discussed ML20235J1171987-09-28028 September 1987 Responds to Requesting Info Re Ucs 870210 Petition Requesting Mods to B&W Facilities,Per E Gallizzi to Recipient Requesting Support of Petition. Gallizzi Statements Discussed.Petition Under Review ML20235B6261987-09-16016 September 1987 Responds to 870812 Request for Hearing to Address Design Flaws in Each of Five Specific Sys Identified in Ucs Petition & Ability of NRC to Evaluate & Assess Level of Danger Inherent in Continued Operation of B&W Plants ML20235B6581987-09-16016 September 1987 Responds to 870912 Request for Hearing Re Design Flaws in Five Specific Sys Identified in Ucs Petition & NRC Ability to Evaluate & Assess Level of Danger Inherent in Continued Operation of B&W Plants ML20235L3771987-08-27027 August 1987 Advises That Received from Two Smud Board of Directors Re Request for Adjudicatory Hearing Does Not Reflect Views of Majority of Board of Directors ML20237H0091987-08-12012 August 1987 Responds to Ucs Et Al 870210 Petition Requesting Public Hearing Re Sufficiency of Mods for Continued Operation of B&W Designed Nuclear Reactors.Util Requests NRC to Hold Hearing in Sacramento,Ca to Discuss Design Flaws & Dangers ML20236L1811987-08-0404 August 1987 Responds to Addressed to Chairman Zech,Requesting That Commission Keep Recipient Fully Apprised of All Developments Re Both Petition Filed by Ucs & Ongoing Reassessment of B&W Reactors.Review of Petition Continuing ML20235J5701987-08-0303 August 1987 Requests Response to Encl Constituent Tf Gross Urging Support of Ucs Petition to Suspend OLs & CPs for All B&W Nuclear Plants Pending Resolution of Extraordinary Safety Problems ML20236L2431987-07-13013 July 1987 Requests That Author Be Fully Apprised of All Developments Re Both Ucs Petition & Ongoing NRC Reassessment of B&W Reactors ML20215D6371987-06-12012 June 1987 Forwards Reply to Responses from NRC & B&W Owners Group. NRC Response Evidences No Independent Review of B&W Claims. Commission Urged to Take Personal Jurisdiction of Petition to Ensure That Latest Commitment Not Frustrated ML20214E2841987-05-18018 May 1987 Final Response to FOIA Request.No PRAs on File for McGuire 1,Bellefonte 1 & Gassar.Pras for Susquehanna 1 & Oyster Creek Available in PDR IA-87-221, Final Response to FOIA Request.No PRAs on File for McGuire 1,Bellefonte 1 & Gassar.Pras for Susquehanna 1 & Oyster Creek Available in PDR1987-05-18018 May 1987 Final Response to FOIA Request.No PRAs on File for McGuire 1,Bellefonte 1 & Gassar.Pras for Susquehanna 1 & Oyster Creek Available in PDR ML20214E2281987-04-16016 April 1987 FOIA Request for PRAs for Listed Plants Be Placed in PDR ML20206P5191987-04-15015 April 1987 Responds to Severity Level IV Violation Noted in Insp Repts 50-438/86-09 & 50-439/86-09.Corrective Actions:Procurement QA Branch Inspectors Conducted Addl Training in Welding Insp.Future Insp Plans Will Address Welding Requirements ML20207U0731987-03-0606 March 1987 Forwards Insp Repts 50-438/86-09 & 50-439/86-09 on 861201-870131 & Notice of Violation ML20207T4561987-02-26026 February 1987 Forwards Insp Repts 50-438/86-10 & 50-439/86-10 on 861216-18.No Violation or Deviation Noted ML20211C3231987-02-12012 February 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-438/86-07 & 50-439/86-07 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 ML20209D7441987-01-28028 January 1987 Responds to NRC Re Violations in Noted Insp Repts 50-438/86-07 & 50-439/86-07.Corrective Actions: Requirements for Timely Documenting of Conditions Adverse to Quality Reviewed by Involved Supervisors ML18031B1361987-01-16016 January 1987 Forwards Updates of TVA Activities for Wks of 870119 & 26 ML20212F4541986-12-29029 December 1986 Forwards Insp Repts 50-438/86-07 & 50-439/86-07 on 861001-1130 & Notice of Violation ML20215A1581986-12-0909 December 1986 Final FOIA Response to Request for Documents Re Welding,Mfg & Const Deficiencies Concerning Tdi.Forwards App E Documents.Documents Also Available in PDR ML18031B0011986-11-14014 November 1986 Forwards Updates of TVA Activities for Wks of 861117 & 24 ML20215K5601986-10-16016 October 1986 Notifies of Util Commitments on Response to IE Bulletin 85-001 Re Steam Binding of Auxiliary Feedwater Pumps. Procedures to Be Developed Will Meet Intent of Bulletin Re Monitoring Fluid Conditions & Recognizing Binding IR 05000438/19860041986-08-0606 August 1986 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-438/86-04 & 50-439/86-04 ML20198E2981986-05-20020 May 1986 Discusses Points of View & Concerns Expressed in Ucs Press Release & Re B&W Reactors,Including Plan Responsiveness,Auxiliary Feedwater Sys & Integrated Control Sys.Achievement of Goals Will Reduce Ucs Concerns ML20203N3901986-05-0101 May 1986 Forwards Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications. Rev Approved by Tdi Owners Group & Tdi ML20141A3541986-03-13013 March 1986 Addl Response to FOIA Request for Documents Re Delays or Progress on Const.App C Documents Available in PDR ML20154M2591986-02-18018 February 1986 Discusses SER of Rev 1 to BAW-1847 & BAW-1889P Re Elimination of Postulated Pipe Breaks in PWR Primary Main Loops.Repts Acceptable.Leakage Detection Sys Info Requested ML20137Y0581986-02-18018 February 1986 Requests facility-specific Info Re Requests for Exemption from GDC 4,concerning Protection Against Dynamic Loads Resulting from Postulated Breaks of Primary Main Loop Piping.Info Re Leakage Detection Sys Should Be Included ML20137Y0431986-02-18018 February 1986 Discusses Safety Evaluation of B&W Owners Group Repts Dealing W/Elimination of Postulated Pipe Breaks in PWR Primary Main Loops.Exemption from GDC 4 & Demonstration That Leakage Sys in Compliance W/Reg Guide 1.45 Needed ML20199F2381986-02-0404 February 1986 FOIA Request for All Documents Re Delays or Progress of Const at Bellefonte Nuclear Plant,Including Const Schedules or Projections & Const Status Repts 1999-08-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML1108302361993-05-0303 May 1993 Forwards Rev 1 to NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. Submittal Made on Behalf of Eight Utils Having Enterprize EDGs for Emergency Standby Ac Power ML18010A9501992-12-0808 December 1992 Forwards NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. Submittal Made on Behalf of Eight Utils Having Enterprise EDGs for Emergency Standby Ac Power ML18036A8701992-09-30030 September 1992 Forwards Updated Distribution Lists for Brown Ferry & Bellefonte Nuclear Plants to Reflect Recent Reorganizational Changes.Lists Should Replace Lists Sent on 920515 ML20086K0871991-12-11011 December 1991 Requests Mod of Periodicity in Which Util Conducts Annual Practice Sessions for Fire Brigade Personnel.Rev to Commitment C.3.D.6(b) of BTP Cmeb 9.5-1 Will Permit Practice Session to Be Held Annually ML20247C3771989-09-0606 September 1989 Confirms Understanding of Applicability of NRC Requirements Developed During Deferral Period of Plant ML20245D9851989-06-22022 June 1989 Forwards 21 Insp Rept Executive Summaries,Per NRC Contract NRC-03-87-029,Task Order 037.Individual Quality Evaluations of Insp Repts Also Prepared ML20246E3551989-06-21021 June 1989 Submits Plan for Quadrex Corp to Lease Plant,Complete Facility,Operate Facility,Sell Power & Eventually Return Plant to Tva.Topic Will Be Discussed at 890711 Meeting ML20247G5411989-03-24024 March 1989 Informs of Recent Changes Made within Mgt Structure of Util Organization.Util Reorganization Efforts Aimed at Implementing Changes Necessary to Reflect Reorientation from Design & Mod ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20235L3771987-08-27027 August 1987 Advises That Received from Two Smud Board of Directors Re Request for Adjudicatory Hearing Does Not Reflect Views of Majority of Board of Directors ML20237H0091987-08-12012 August 1987 Responds to Ucs Et Al 870210 Petition Requesting Public Hearing Re Sufficiency of Mods for Continued Operation of B&W Designed Nuclear Reactors.Util Requests NRC to Hold Hearing in Sacramento,Ca to Discuss Design Flaws & Dangers ML20235J5701987-08-0303 August 1987 Requests Response to Encl Constituent Tf Gross Urging Support of Ucs Petition to Suspend OLs & CPs for All B&W Nuclear Plants Pending Resolution of Extraordinary Safety Problems ML20236L2431987-07-13013 July 1987 Requests That Author Be Fully Apprised of All Developments Re Both Ucs Petition & Ongoing NRC Reassessment of B&W Reactors ML20215D6371987-06-12012 June 1987 Forwards Reply to Responses from NRC & B&W Owners Group. NRC Response Evidences No Independent Review of B&W Claims. Commission Urged to Take Personal Jurisdiction of Petition to Ensure That Latest Commitment Not Frustrated ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure ML20214E2281987-04-16016 April 1987 FOIA Request for PRAs for Listed Plants Be Placed in PDR ML20206P5191987-04-15015 April 1987 Responds to Severity Level IV Violation Noted in Insp Repts 50-438/86-09 & 50-439/86-09.Corrective Actions:Procurement QA Branch Inspectors Conducted Addl Training in Welding Insp.Future Insp Plans Will Address Welding Requirements ML20209D7441987-01-28028 January 1987 Responds to NRC Re Violations in Noted Insp Repts 50-438/86-07 & 50-439/86-07.Corrective Actions: Requirements for Timely Documenting of Conditions Adverse to Quality Reviewed by Involved Supervisors ML20207Q6461987-01-21021 January 1987 Forwards Two Lists Revising Commitment Completion Dates for Final Deficiency Repts.Encl 1 Lists Items to Be Completed at Least 6 Months Prior to Fuel Load.Encl 2 Lists Items Scheduled to Undergo Peer Review ML18031B1361987-01-16016 January 1987 Forwards Updates of TVA Activities for Wks of 870119 & 26 ML18031B0011986-11-14014 November 1986 Forwards Updates of TVA Activities for Wks of 861117 & 24 ML20215K5601986-10-16016 October 1986 Notifies of Util Commitments on Response to IE Bulletin 85-001 Re Steam Binding of Auxiliary Feedwater Pumps. Procedures to Be Developed Will Meet Intent of Bulletin Re Monitoring Fluid Conditions & Recognizing Binding ML20198E2981986-05-20020 May 1986 Discusses Points of View & Concerns Expressed in Ucs Press Release & Re B&W Reactors,Including Plan Responsiveness,Auxiliary Feedwater Sys & Integrated Control Sys.Achievement of Goals Will Reduce Ucs Concerns ML20203N3901986-05-0101 May 1986 Forwards Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications. Rev Approved by Tdi Owners Group & Tdi ML20199F2381986-02-0404 February 1986 FOIA Request for All Documents Re Delays or Progress of Const at Bellefonte Nuclear Plant,Including Const Schedules or Projections & Const Status Repts ML20206J2521986-01-24024 January 1986 Forwards Early Draft of Executive Summary from Analysis of Station Blackout Accidents for Bellefonte PWR, Per Request. Initial Draft of Rept Scheduled to Be Completed by 860315 ML20136F4771985-12-31031 December 1985 Forwards PNL-5718, Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept ML20138Q8581985-12-17017 December 1985 Forwards Update to Deficiency Rept & Outstanding Commitment Completion Schedules,Per 851107 Commitment.Milestones Revised to Allow Final Repts for Each Item to Be Next Rept Submitted ML20133A3141985-09-27027 September 1985 Forwards Review of Section 4.7 of Technical Evaluation Rept PNL-5600, Review of Resolution of Known Problems in Engine Components for Tdi Emergency Diesel Generators, Reflecting Views Re Crankshafts for 16-cylinder Engines ML20132D1941985-09-16016 September 1985 Resubmits Encl BAW-1875, B&W Owners Group Cavity Dosimetry Program, Inadvertently Addressed to Incorrect Individual at Nrc.Timely Review of Rept Requested ML20133H1511985-08-0202 August 1985 Forwards Drawings to Be Incorporated Into Amend 25 to FSAR Question 480.41.W/25 Oversize Drawings.Aperture Cards Available in PDR ML20136H8721985-07-11011 July 1985 FOIA Request for CA Dobbe & R Chambers, Analysis of Station Blackout Transient for Bellefonte PWR & PD Bayless & R Chambers, Analysis of Station Blackout Transient at Seabrook Nuclear Power Plant ML20128H7371985-06-27027 June 1985 Forwards Rev 1 to Review of Engine Base & Bearing Caps for Tdi DSRV-12,DSRV-16 & DSRV-20 Diesel Engines, Technical Evaluation Rept ML20126E8721985-05-24024 May 1985 Forwards PNL-5200-3, Review of Emergency Diesel Generator Engine & Auxiliary Module Wiring & Terminations, Dtd May 1985 ML20127F8441985-04-10010 April 1985 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-21 & 50-439/84-21.Corrective Actions:Plumb & Levelness Requirements Incorporated Into General Drawing, QC Procedure 6.7 Revised & Ducts Inspected ML20127F9781985-03-29029 March 1985 Responds to NRC Re Violations Noted in Insp Repts 50-438/85-04 & 50-439/84-04.Corrective Actions:Terminal Boards Labeled ML20127J6941985-03-28028 March 1985 Provides Second Supplemental Response to NRC Re Deviations Noted in Insp Repts 50-438/83-10 & 50-439/83-10. Corrective Actions:Deficient Fire Damper/Sleeve Tack Welds Installed Per Ul Approved Instructions ML20099K1391985-02-20020 February 1985 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-26 & 50-439/84-26.Corrective actions:dual-rated Foreman No Longer Supervising Crew & Will Not Supervise Until Proper Training Received ML20112G3451984-12-26026 December 1984 Responds to IE Bulletin 84-03, Refueling Cavity Water Seal. Evaluation of Potential for & Consequences of Refueling Cavity Water Seal Failure Encl,Per 841204 Agreement ML20113A8111984-12-0505 December 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-20 & 50-439/84-20.Corrective Actions: Nonconformance Rept 3522 Written to Document Exceeding of Allowable Temp Limit of Paint Storage Warehouse ML20113A3411984-12-0303 December 1984 Suppls Response to NRC Re Violations Noted in Insp Repts 50-438/84-01 & 50-439/84-01.Corrective Actions: Relevant QC Procedures Will Be Issued by 841212 ML20101T2841984-11-30030 November 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-22 & 50-439/84-22.Corrective Actions:Assemblies Placed on Curbing & Damaged Closures Replaced ML20113A3111984-11-16016 November 1984 Suppls Response to NRC Re Violations Noted in Insp Repts 50-438/81-29 & 50-439/81-29.Corrective Actions: Three Replacement Bolts Returned to B&W Due to Inadequate Markings.Corrective Action Will Be Completed by 850222 ML20107G9331984-09-19019 September 1984 Submits Second Revised Response to NRC 840906 Telcon & Re Violations Noted in Insp Repts 50-438/84-04 & 50-439/84-04.Corrective Actions:Battery Cells Replaced & Reported on 840822 as NRC Bln Eeb 8416 ML20106C4091984-09-19019 September 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-15 & 50-439/84-15.Alleged Violation Re Failure to Follow Procedure for Inspecting for Floor Penetrations Denied ML20106C6501984-09-18018 September 1984 Clarifies Response to NRC Re Violations Noted in Insp Repts 50-438/84-12 & 50-439/84-12 Re Failure to Follow Procedures for Hanger Insps.Rev to Nonconformance Rept 1968 Accomplished on 840712 ML20106C3561984-09-12012 September 1984 Suppls Response to NRC Re Violations Noted in Insp Rept 50-438/84-01.Corrective Actions:Environ Qualified Motor Starters Will Be Installed by 850330 & QC Procedure 3.4 Will Be Revised & Issued by 841014 ML20106C6601984-08-31031 August 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-12 & 50-439/84-12.Corrective Actions:Disposition of Unacceptable Hanger Welds Documented on 840203 Under Nonconformance Rept 1968 ML20113A5441984-08-31031 August 1984 Revises Response to NRC Re Violations Noted in Insp Repts 50-438/83-31 & 50-439/83-31.Corrective Actions: Administrative Controls in Nutac Rept on Generic Ltr 83-28 Will Be Reflected in Interdivisional Procedure 1999-08-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20247C3771989-09-0606 September 1989 Confirms Understanding of Applicability of NRC Requirements Developed During Deferral Period of Plant ML20247G5411989-03-24024 March 1989 Informs of Recent Changes Made within Mgt Structure of Util Organization.Util Reorganization Efforts Aimed at Implementing Changes Necessary to Reflect Reorientation from Design & Mod ML20235L3771987-08-27027 August 1987 Advises That Received from Two Smud Board of Directors Re Request for Adjudicatory Hearing Does Not Reflect Views of Majority of Board of Directors ML20237H0091987-08-12012 August 1987 Responds to Ucs Et Al 870210 Petition Requesting Public Hearing Re Sufficiency of Mods for Continued Operation of B&W Designed Nuclear Reactors.Util Requests NRC to Hold Hearing in Sacramento,Ca to Discuss Design Flaws & Dangers ML20206P5191987-04-15015 April 1987 Responds to Severity Level IV Violation Noted in Insp Repts 50-438/86-09 & 50-439/86-09.Corrective Actions:Procurement QA Branch Inspectors Conducted Addl Training in Welding Insp.Future Insp Plans Will Address Welding Requirements ML20209D7441987-01-28028 January 1987 Responds to NRC Re Violations in Noted Insp Repts 50-438/86-07 & 50-439/86-07.Corrective Actions: Requirements for Timely Documenting of Conditions Adverse to Quality Reviewed by Involved Supervisors ML18031B1361987-01-16016 January 1987 Forwards Updates of TVA Activities for Wks of 870119 & 26 ML18031B0011986-11-14014 November 1986 Forwards Updates of TVA Activities for Wks of 861117 & 24 ML20215K5601986-10-16016 October 1986 Notifies of Util Commitments on Response to IE Bulletin 85-001 Re Steam Binding of Auxiliary Feedwater Pumps. Procedures to Be Developed Will Meet Intent of Bulletin Re Monitoring Fluid Conditions & Recognizing Binding ML20198E2981986-05-20020 May 1986 Discusses Points of View & Concerns Expressed in Ucs Press Release & Re B&W Reactors,Including Plan Responsiveness,Auxiliary Feedwater Sys & Integrated Control Sys.Achievement of Goals Will Reduce Ucs Concerns ML20203N3901986-05-0101 May 1986 Forwards Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications. Rev Approved by Tdi Owners Group & Tdi ML20138Q8581985-12-17017 December 1985 Forwards Update to Deficiency Rept & Outstanding Commitment Completion Schedules,Per 851107 Commitment.Milestones Revised to Allow Final Repts for Each Item to Be Next Rept Submitted ML20132D1941985-09-16016 September 1985 Resubmits Encl BAW-1875, B&W Owners Group Cavity Dosimetry Program, Inadvertently Addressed to Incorrect Individual at Nrc.Timely Review of Rept Requested ML20133H1511985-08-0202 August 1985 Forwards Drawings to Be Incorporated Into Amend 25 to FSAR Question 480.41.W/25 Oversize Drawings.Aperture Cards Available in PDR ML20127F8441985-04-10010 April 1985 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-21 & 50-439/84-21.Corrective Actions:Plumb & Levelness Requirements Incorporated Into General Drawing, QC Procedure 6.7 Revised & Ducts Inspected ML20127F9781985-03-29029 March 1985 Responds to NRC Re Violations Noted in Insp Repts 50-438/85-04 & 50-439/84-04.Corrective Actions:Terminal Boards Labeled ML20127J6941985-03-28028 March 1985 Provides Second Supplemental Response to NRC Re Deviations Noted in Insp Repts 50-438/83-10 & 50-439/83-10. Corrective Actions:Deficient Fire Damper/Sleeve Tack Welds Installed Per Ul Approved Instructions ML20099K1391985-02-20020 February 1985 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-26 & 50-439/84-26.Corrective actions:dual-rated Foreman No Longer Supervising Crew & Will Not Supervise Until Proper Training Received ML20112G3451984-12-26026 December 1984 Responds to IE Bulletin 84-03, Refueling Cavity Water Seal. Evaluation of Potential for & Consequences of Refueling Cavity Water Seal Failure Encl,Per 841204 Agreement ML20113A8111984-12-0505 December 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-20 & 50-439/84-20.Corrective Actions: Nonconformance Rept 3522 Written to Document Exceeding of Allowable Temp Limit of Paint Storage Warehouse ML20113A3411984-12-0303 December 1984 Suppls Response to NRC Re Violations Noted in Insp Repts 50-438/84-01 & 50-439/84-01.Corrective Actions: Relevant QC Procedures Will Be Issued by 841212 ML20101T2841984-11-30030 November 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-22 & 50-439/84-22.Corrective Actions:Assemblies Placed on Curbing & Damaged Closures Replaced ML20113A3111984-11-16016 November 1984 Suppls Response to NRC Re Violations Noted in Insp Repts 50-438/81-29 & 50-439/81-29.Corrective Actions: Three Replacement Bolts Returned to B&W Due to Inadequate Markings.Corrective Action Will Be Completed by 850222 ML20107G9331984-09-19019 September 1984 Submits Second Revised Response to NRC 840906 Telcon & Re Violations Noted in Insp Repts 50-438/84-04 & 50-439/84-04.Corrective Actions:Battery Cells Replaced & Reported on 840822 as NRC Bln Eeb 8416 ML20106C4091984-09-19019 September 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-15 & 50-439/84-15.Alleged Violation Re Failure to Follow Procedure for Inspecting for Floor Penetrations Denied ML20106C6501984-09-18018 September 1984 Clarifies Response to NRC Re Violations Noted in Insp Repts 50-438/84-12 & 50-439/84-12 Re Failure to Follow Procedures for Hanger Insps.Rev to Nonconformance Rept 1968 Accomplished on 840712 ML20106C3561984-09-12012 September 1984 Suppls Response to NRC Re Violations Noted in Insp Rept 50-438/84-01.Corrective Actions:Environ Qualified Motor Starters Will Be Installed by 850330 & QC Procedure 3.4 Will Be Revised & Issued by 841014 ML20106C6601984-08-31031 August 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-12 & 50-439/84-12.Corrective Actions:Disposition of Unacceptable Hanger Welds Documented on 840203 Under Nonconformance Rept 1968 ML20113A5441984-08-31031 August 1984 Revises Response to NRC Re Violations Noted in Insp Repts 50-438/83-31 & 50-439/83-31.Corrective Actions: Administrative Controls in Nutac Rept on Generic Ltr 83-28 Will Be Reflected in Interdivisional Procedure ML20099L2331984-08-0303 August 1984 Submits Results of Survey to Determine Extent of Missing Washers on Wedge Bolts,Per Initial 840330 Response to Insp Repts 50-438/84-03 & 50-439/84-03.QC Procedure Re Bolt Anchors Set in Concrete Revised ML20095G5361984-07-23023 July 1984 Forwards Supplemental Response to IE Bulletin 81-03 Re Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel) ML20095G1081984-07-13013 July 1984 Forwards Supplemental Response to NRC Re Violations Noted in Insp Repts 50-438/83-05 & 50-439/83-05. Corrective actions:BNP-QCP-6.3 Revised to Clarify Listing of Attributes Inspected on Thermal Expansion Devices ML20090J1001984-06-27027 June 1984 Responds to NRC Re Violations Noted in IE Insp Rept 50-438/84-05.Corrective actions:BNP-QCP-10.6 Will Not Be Used for Revised Drawing Changes ML20113A5481984-06-25025 June 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/83-31 & 50-439/83-31.Corrective Action Will Be Completed by 840901 ML20107G9391984-06-20020 June 1984 Submits Revised Response to NRC 840601 Telcon & Re Violations Noted in Insp Repts 50-438/84-04 & 50-439/84-04.Corrective Actions:Nonconformance Rept 2856 Initiated Re Froth on Station Batteries ML20092D3201984-05-21021 May 1984 Responds to NRC Re Violations Noted in IE Insp Repts 50-438/84-09 & 50-439/84-09.Corrective Actions:Qc Procedure Revised to Prohibit Any Installation of Ssd Anchors in Concrete Walls ML20107G9541984-05-10010 May 1984 Responds to NRC Re Violations Noted in Insp Repts 50-438/84-04 & 50-439/84-04.Violation Re Station Battery Frothing Denied ML20092D3921984-05-0202 May 1984 Forwards Supplemental Response to Notice of Violation in IE Insp Repts 50-438/83-24 & 50-439/83-24,per NRC 840404 Request to Admit Part A.3 & Revise Schedule for Parts A.4 & A.5 Re Questionable Ultrasonic Exams ML20091B3051984-04-18018 April 1984 Responds to NRC Re Violations Noted in IE Insp Repts 50-438/84-05 & 50-439/84-05.Corrective Actions:All Accessible Portions of 74 Welds Inspected Visually ML20093F2351984-03-30030 March 1984 Responds to NRC Re Violations Noted in IE Insp Repts 50-438/83-31 & 50-439/84-31.Corrective Actions: Procedure IDP 52.05 Re Control & Handling of Vendor Manuals Will Be Issued by 840720,per Generic Ltr 83-28 ML20092P4581984-03-30030 March 1984 Responds to NRC Re Violations Noted in IE Insp Repts 50-438/84-03 & 50-439/84-03.Corrective Actions: Procedures to Be Revised to Provide Design Clarification That Bolt Torques Not Required to Be Reproducible ML20087P3911984-03-14014 March 1984 Responds to NRC Re Violations Noted in IE Insp Repts 50-438/84-01 & 50-439/84-01.Corrective Actions: Nonconformance Rept 2721 Generated to Document Rework of Rusted Unit 1 Conduit.Motor Starter Will Be Replaced ML20093F2781984-02-10010 February 1984 Responds to NRC Re Violations Noted in IE Insp Repts 50-438/83-31 & 50-439/83-31.Corrective Actions:Vendor Drawings Will Be Revised to Reflect Correct Solenoid Orientation.Item 1 Denied as Violation ML20092D3991984-01-19019 January 1984 Forwards Supplemental Info to Clarify Questions & Concerns Raised by NRC Region II Inspectors Re Violations in IE Insp Repts 50-438/83-24 & 50-439/83-24.Violations Involve Questionable Ultrasonic Exams ML20095G1281984-01-0404 January 1984 Supplemental Response to Violations Noted in Insp Repts 50-438/83-05 & 50-439/83-05.Corrective Action:Const QC Unit Waiting for Computer Printout to Verify Insp of All Affected Equipment Under Revs 0 & 1 to Qcp 6.3 ML20092D4051983-12-29029 December 1983 Provides Supplemental Response to Notice of Violation in Area of Ultrasonic Exams in IE Insp Repts 50-438/83-24 & 50-439/83-24,per 831128 Discussion ML20079J5181983-12-28028 December 1983 Responds to NRC Re Violations Noted in IE Insp Repts 50-438/83-28 & 50-439/83-28.Corrective Actions:Memo Emphasizing Awareness of Requirement That Heaters Remain Energized Issued & FSAR Revised to Reflect Exception ML20091B1831983-12-22022 December 1983 Responds to NRC Re Violations Noted in IE Insp Repts 50-438/83-10 & 50-439/83-10.Corrective Actions:Efforts Underway to Obtain Vendor Verification of Correct Fire Damper Installation ML20083H3061983-12-21021 December 1983 Forwards Response to NRC Re Violations Noted in IE Insp Repts 50-438/83-27 & 50-439/83-27.Corrective Actions:Training Sessions Will Be Conducted to Reemphasize Proper Insp of Clamp Spacers & Allowable Tolerance ML20091B1981983-12-15015 December 1983 Suppls Response to NRC Re Violations Noted in IE Insp Repts 50-438/83-10 & 50-439/83-10.Corrective Actions: Fire Protection Sys Nonconformances Will Be Corrected by 851114 1989-09-06
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 37401 ;%
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August 26, 1983
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U.S. Nuclear Regulatory Commission Region II Attention: Mr*. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - REVISED RESPONSE TO DEVIATIONS 50-438/83-10-01, 50-439/10-01, PORTIONS OF THE FIRE PROTECTION SYSTEMS DO NOT CONFORM TO THE DESIGN CRITERIA 0F THE APPLICABLE NFPA CODE 438/83 03, 50-439/10-03, EXTERIOR FIRE PROTECTION WATER SYSTEM WAS NOT INSTALLED UNDER A QA/QC PROGRAM 438/83-10-05, 50-439/83-10-05, IMPROPER FIRE DAMPER INSTALLATION This is in response to the TVA/NRC telecons of July 19 and July 21, 1983, concerning activities at Bellefonte Nuclear Plant which appeared to have been in violation of NRC regulations as discussed in R. C. Lewis' letter to H. G. Parris dated May 23, 1983 The NRC has requested that TVA provide additional information to supple-ment our initial response as stated in my Letter to you dated July 7,1983 to the alleged violations. Enclosed is a revision to the initial response with supplemental changes and/or corrections. Please note that a two-week delay of the submittal was discussed with Bill Miller of your staff on August 12, 1983.
TVA has denied deviation 50-438/83-10-01 and 50-439/83-10-01. The NRC staff has taken the position with TVA on other nuclear plants that for the preaction sprinkler system (1) control valves should be electrically supervised and (2) piping be provided with air supervision per standard industry practices. TVA maintains that NFPA 13 does not require these types of supervision. TVA has elected to request formal code interpretations from the appropriate NFPA code committees. We expect to receive the results of both interpretations by December 1,1983 The NRC will be apprised of these findings at that time and, if as a result it becomes necessary, TVA will modify its deviation response appropriately.
If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.
8405300242 840507 PDR ADOCK 05000438 O PDR 1983-TVA 50m ANNIVERSARY An Equal Opportunity Employer
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U.S. Nuclear Regulatory Comission August 26, 1983 To the best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Enclosure cc (Enclosure):
Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Comission Washington, D.C. 20555 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339
ENCLOSURE BELLEFONTE NUCLEAR PLANTS UNITS 1 AND 2 REVISED RESPONSE TO DEVIATON 50-438/83-10-01, 50-439/83-10-01 PORTIONS OF THE FIRE PROTECTION SYSTEMS DO NOT CONFORM TO THE DESIGN CRITERIA 0F THE APPLICABLE NFPA CODE Description of Deficiency FSAR Section 9 5.1.1 states that the codes and standards of the National Fire Protection Association (NFPA) will be used in the design of the fire protection system.
Contrary to the above, the following NFPA code deficiencies were identified:
- 1. Fire Pumps
- a. The fire pump starting circuits are not of the normally closed type and arranged such that breakage, disconnection, shorting of wires, or loss of power to the starting circuits would cause automatic continuous operation of the fire pump which is not in accordance with NFPA-20, Centrifugal Fire Pump, Sections 9-5.2.2 and 9-5.2.5.
- b. The fire pump relief valves are not provided with a means of -
detecting flow of water through the relief valves as required by NFPA-20 Section 2-12.6.
- 2. Automatic Sprinkler Systems (Fire Pump any Diesel Generator Buildings) a.
The electrical circuits from the fire detection control panels to the sprinkler system actuation panels for the preaction control valves are not electrically supervised as required by NFPA-13, Sprinkler Systems, Section 5-3.5.4.
- b. The sprinkler piping systems are not supervised as required by NFPA-13 Section 5-3 5.4.
TVA Response 1(a)
Admission or Denial of Deviation' TVA denies the deviation occurred as stated.
Note: NRC's reference to NFPA-20 Section 4-5.2.5 is based on a more recent issue of the code than the code of record (1q76). TVA believes that our reference to NFPA-20 Section 9-5.2.4 is identical.
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R-' sons for D nini The fire pump actustion circuits are routed from two fire detection control panels in the auxiliary instrument rooms through the Solid-State Control System (SSCS) cabinets to the pump controllers. The starting circuits from the SSCS cabinets to the pump controllers are wired to normally closed contacts and are arranged such that breakage, disconnection, or loss of power to the starting circuits will cause automatic continuous operation of the fire pumps. Circuits from the fire detection panels to the SSCS cabinets are wired to normally open contact, and failure of these circuits will not cause automatic start of the fire pumps. However, if an input signal to the detection panels requiring fire pump start fails to generate a ocrresponding output to the SSCS, the control room operator is notified that an alarm condition exists on that panel. This is transmitted over a common alarm circuit from the detection panels to the Data Acquisition and Control, Operation Recording, Annunciation, Cata Logging, Access Control, and Fire Detection System (DAC0ADA). Appropriate manual actions will then be taken to start the fire pumps. All input signals to the detection panels are supervised. In addition, the fire pumps can be started from the main control room through the SSCS. If the SSCS should fail, the fire pumps can also be started by an emergency bypass switch located in the immediate vicinity of the SSCS cabinets. This switch is a normally closed e'ntact and the circuit is arranged such that any breakage, disconnection, or loss of power will cause automatic continuous operation of the fire pumps. The fire pump controller is also wired so that a loss of power to the controller will cause automatic continuous operation of the fire pumps.
TVA believes that the unique arrangement of the Bellefonte Nuclear Plant's SSCS in conjunction with the level of supervision of fire detection input circuitry to the detection panels and plant operating procedures provide a level of protection that meets the intent of NFPA 20-1976, Section 9-5.2.4 (FSAR Code of Record).
The following Fire Pump Start Block Diagram (Figure 1) with accompanying explanatory notes illustrates the fire pump start circuitry inputs.
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EXPLANATORY NOTES
- 1. In event of either a detector actuation or manual fire pump start initiation, there is an alarm on DAC0ADA (supervised) for the individual '
condition and a common alarm (supervised).
- 2. There is a pressure-switch indication downstream of each valve (supervised) which can be compared with the alarm in item 1 to ensure pumps have started and valve has opened. (Exceptions are standoipes which do not have valves).
- 3. If pumps start, there will be indication on main control room board (MCR)
IM-22. If not started, operator can attempt to start them from: (1) MCR (nonsupervised circuit), (2) manual fire punp start switch downsteam of solid state control system (SSCS) (supervised), or (3) at the fire pump controller.
4 In summary, there are supervised circuits to alarm the operator that the pumps should be started and status (most of which is supervised) to show that they have started. If they did not start, there is both nonsupervised start circuits in MCR and supervised start circuits at the l
SSCS cabinet.
- 5. There are 20,000-gallon tanks on top of the turbine building which would gravity-feed most areas which would automatically fill from the four electric pumps.
TVA Response 1(b)
Admission or Denial of Alleged Deviation TVA admits the deviation occurred as stated.
Corrective Steps Taken and Results Achieved The present configuration allows the relief valves to discharge into a short run of 6-inch piping that connects to an overhead 12-inch common header which carries the discharge to yard drainage. A 1/2-inch open-ended line taps into the 6-inch line and releases a portion of the relief valve discharge into an open funnel that also discharges to the yard drainage system.
In the event of relier valve discharge, it could be difficult to visually determine which pump relief valve (s) was discharging when more than one fire pump was in operation. To alleviate this potential problem, TVA will install a finnged enclosed waste cone in the 6-inch relief valve discharge line of each pump at a location downstream of the existing one-half drain line. This will provide a visual means of determining operation of a relief valve.
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Corr 7ctiva Step, Tck:n to Avoid Furthnr Daviationn The fire pump installations designed in accordance with NFPA 20 at other TVA nuclear plants have been provided with a visual means of determining relief valve operation. The fire pumps that were designed to standards other than NPFA 20 have been accepted by NRC-NRR. Therefore no actions to prevent recurrence of the subject deviation are necessary.
Action to be Taken or Planned to Improve Management Control Effectiveness This deviation occurred as a result of misinterpretation of the code rather than a breakdown in the management control process. Therefore no additional action is required to improve management control.
Date When Full Compliance Will Be Achieved TVA's Division of Engineering Design (EN DES) Engineering Change Notice (ECN) 2330 will document this change. The corresponding design drawing and bill of materials will be revised and issued by October 31, 1983. Installation should be completed by January 15, 1984.
TVA Response 2(a)
Admission or Denial of Alleged Deviation -
TVA denies the deviation occurred as stated.
Note: NRC's reference to NFPA 13 Section 5-3 5.4 is based on a more recent issue of the code than the code of record (1476). TVA believes that our reference to NFPA 13 Section 5-3 5.2 is identical.
Reasons for Denial NFPA 13-1976 (FSAR Code of Record) section 5-3 5.2 only requires fire detection devices to be supervised. It is TVA's position that this section does not require electrical supervision of the circuits from the fire detection control panels to the sprinkler system preaction control valves.
At Bellefonte, the fire detectors, pressure switches, and fire pump start switches associated with the preaction and deluge systems are monitored by class A supervised circuits in accordance with NFPA 72D-1975 and NFPA 72E-1974 TVA feels that this level of supervision meets the requirements of NFPA 13-1976, section 5-3.5.2.
In addition, the contacts of the breakers which supply power to the solenoids that actuate the preaction and deluge valves, the circuits providing power to the fire protecticn panels, and *.he circuits from the panels to the pressure switches downstream of the valve are all electrically supervised. The pressure switches provide contro room indication of valve status.
There fore , failure of any suppression valve to open in a fire alarm condition will be indicated in the main control room. Appropriate actions would then be taken by the fire brigade to manually actuate the valve at the local control valve station.
.. m TVA Response 2(b)
Admission or Denial of Alleged Deviation TVA denies the deviation occurred as stated.
Note: NRC's reference to NFPA 13 Section 5-3.5.4 is based on a more recent issue of the code that the code of record (1976). TVA believes that our reference to NFPA 13 Section 5-3.5.2 is identical.
Reasons for Denial All preaction sprinkler systems at Bellefonte, including those in the diesel generator and fire pump buildings, are supervised by pressure switches downstream of the system control valves. The switches provide annunciation in the main control room anytime a control ' valve opens and water is admitted into the sprinkler systems.
The preaction sprinkler systems covering areas of the plant containing class 1E motor control centers and auxiliary control panels are also provided with low pressure air supervision. The systems have pressure switches that provide main control room annunciation indicating when the integrity of the piping systems have been lost.
Both types of supervision were provided in the sprinkler system design out of concern for release of water in safety-related areas of the plant. Pressure switch supervision coupled with normally dry headers downstream of the control valves, closed sprinkler heads, seismically designed ocmponents, and control valve actuation by cross-zone fire detector provides a high degree of l
assurance that water damage to safety-related equipment cannot occur due to i spurious sprinkler system operation. Air supervision was provided as an added degree of assurance around critical electrical equipment that is very susceptible to water damage. This philosophy was part of the original fire hazard analysis and was based on defense in-depth approach instead of a rigorous analysis.
Therefore, is is TVA's position that adequate supervision of all sprinkler system piping is provided in accordance with NFPA 13-1976, Section 5-3 5.2 (FSAR Code of Record).
5
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 REVISED RESPONSE TO DEVI ATION 50-419/83-10-03, 50-439/83-10-03 EXTERIOR FIRE PROTECTION WATER SYSTEM WAS NOT INSTALLED UNDER A QA/QC PROGRAM Description of Deficiency FSAR Appendix 9.5A, Section C, identifies the quality assurance program to be applied to the design and construction of the fire protection systems at Bellefonte to ensure a reliable and quality product. TVA drawing 7YWO400-RS-01 is marked to indicate that the exterior fire protection water system is to be installed under a quality assurance program.
Contrary to the above, the exterior fire protection unter system was not installed under a quality assurance program.
TVA Response Admission or Denial of Alleged Deviation TVA admits the deviation occurred as stated.
Corrective Steps Which Have Reen Taken and Results Achieved TVA acknowledges that construction activities for all the exterior fire l protection piping systems shown on TVA drawing No. 7YWO400-RS-01 have not 5een installed in accordance with a fire protection quality assurance prog ram. It is our position that the program applies only to those features I which may affect fire protection for safety-related areas of the plant.
Thus, only those features required for the performance of the fire protection
- system in the safety-related structures or adjacent nonsafety-related l structures where an uncontrolled fire could affect safety-related structures should fall under the quality assurance program.
- 1. TVA has initiated the designation of Q' (which denotes a limited quality l assurance for systems not requiring complete compliance with 10CFR50 Appendix B) on all applicable fire protection system drawings in accordance with TVA's Division of Engineering Design Engineering Procedures (EN DES-EP) 4.25, revision 3 (issued March 24, 1980), and EN DES-EP 3 09, revision 2 (issued October 29, 1980), and defined the Q' boundaries on the applicable design criteria diagrams under engineering change notice (ECN) 1357 on September 14, 1981. In addition, TVA has issued General Constructirn Specification 0-73 (G-73), " Inspection, Testing, and Documentation Requirements for Fire Protecton Systems and Features," dated March 16, 1082.
- 2. EN DES has tasued EN DES-EP 1.59, Limited Fire Protection Quality Assurance Program, which defines what organizations are responsible for i
l defining fire protection quality assurance boundaries on design drawings l and states the general critoria for establishing these boundaries. A review of all Bellefonte drawings that fall under the fire protection quality assurance program for conformance to the procedure will be made.
Any deficiencies will he corrected through drawings rovisions.
l
- 3. EN DES has reviewed the construction procedures and instructions in effect,during the period from December 1, 1977, to March 16,1982, for compliance with the. intent of G-73 The procedures and instructions have been determined to satisfy the requirements established in G-73.
- 4. The Division of Construction (CONST) will review all Bellefonte drawings under Fire Protection Quality Assurance Program and will verify that adequate quality assurance records exist in compliance with G-73 for-installations after March 16, 1982, and in compliance with the intent of G-73 for installations between December 1, 1977, and March 16,1982. ;In the.even0 that adequate records cannot be identified to serve as "QA documentation," .nonconformances will be written describing the corrective actions that will be implemented (performance of tests, inspections, etc.). These nonconformances will provide a method for documenting, scheduling, tracking, and closing out any deficiencies.
In addition, all significant nonconformances will be handled in accordance with EN DES-EP 2.02, " Handling of Conditions Potentially Reportable Under Title 10 of the Code of Federal Regulations, Parts 21, 50.36, and 55.55(e)," which requires that these nonconformances be evaluated for reportability to the NRC.
Corrective Steos Taken to Avoid Further Deviations Full implementation of EN DES-Ep 1.55 and the existing general construction specification should prevent further deviations at Bellefonte.
TVA is currently evaluating the adequacy of the fire protection quality assurance boundaries and the required documentation on other active nuclear plants. If problems are identified, they will be corrected in a manner similar to the actions outlined above.
Date When Full Compliance will be Achieved The review of drawings and identification of nonconforming areas as discussed above will be completed for Bellefonte by July 1, 1984 Corrective actions as required by the nonconformances will be completed by February 1, 1985.
Action to be Taken or Planned to Improve Management Control E f fectiveness As previously stated in the TVA response above, TVA attempted to initiate the requirements of the fire protection quality assurance program through the issuance of TVA memorandums. At the time, this appeared to be the most expedient method to establish QA requirements consistent with our commitment in Bellefonte FSAR Appendix 9.5A, section C. TVA acknowledges that <
memorandums are not appropriate to establish a formal quality assurance f
program. Consequently, TVA initiated action to correct this problem by I establishing Fire Protection Quality Assurance requirements in the Office of l Engineering Design and Construction (OEDC) Program l
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Requirements Manual (PRM) No. 2QAI-2 issued on June 29, 1982. Additionally, TVA issued EP 1.55, " Limited Fire Protection Qualf *,y Assurance Program," on August 4, 1983 The issuance of these documents will formally establish a quality assurance program beginning with the upper tier OEDC level program requirements. EN DES-EP 1.55 formally established the requirements for design and procurement activities within EN DES, and G-73 formally establishes the requirements for control of these activities within CONST.
These actions are considered adequate to prevent recurrence, and no additional action beyond those listed above and the corrective actions for this specific finding are planned.
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6
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 REVISED RESPONSE TO DEVIATION 50-438/83-10-05, 50-439/83-10-05 IMPROPER FIRE DAMPER INSTALLATION Description of Deficiency FSAR Appendix 9.5 A Section C.2 states that the design, installation, .
inspection, and tests associated with the fire protection systems are accomplished in accordance with written and approved instructions, procedures, and drawings. TVA drawing 3AWO910-00-01 note 29 states that the fire dampers and sleeve assemblies for fire barrier penetrations will be installed per vendor installations and Sheet Metal and Air Conditioning Contractors National Association (SMACNA) standards. The vendor's fire damper documents require the dampers to be attached to the damper sleeve by welds, bolts, screws, or rivets spaced no more than 8 inches on center on all sides of the damper assembly.
Contrary to the above, the fire dampers are not installed in accordance with manufactures's specifications in that the dampers are attached to the sleeve by tack welds spaced 12 inches on center and located only on one side of the damper assembly in lieu of the required 8-inch spacing on all sides of the assembly.
TVA Response Admission or Denial of Deviation TVA admits the deviation occurred as stated.
Corrective Steps Which Have Been Taken TVA's Division of Construction (CONST) has been instructed to install fire dampers in the future in accordance with approved manufacturer's instructions. In addition, CONST has generated nonconformance report (NCR) 2391 which documents the as-built configuration of the installed dampers.
TVA's Division of Engineering Design (EN DES) has requested the damper manufacturers to evaluate the as installed configuration against the approved vendor installation method for possible equivalency. If a vendor is unable to make this determination, TVA will request an Underwriters Laboratories' (UL) test to demonstrate the adequacy of the installed configuration. If this test does not demonstrate adequacy, construction will rework the dampers to conform to the vendor installation procedure.
Corrective Steps Taken to Avoid Further Deviations CONST personnel installed fire dampers per SMACNA standards which were referenced on TVA drawings. TVA considered this adequate requirements for installation of fire dampers. This interpretation of the requirements for installation was not a failure to meet these requirements but rather an incorrect decision that 'SMACNA' would satisfy vendor installation requirements.
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Date When Full Compliance will be Achieved A. EN DES anticipates vendor's response on equivalency by December 1, 1983.
B. Any rework required by the disposition of NCR 2391 should be corrected by December 3, 1984.
Action to be Taken or Planned to Improve management Control Effectiveness TVA G-73, issued March 16, 1982, includes requirements to ensure that CONST personnel use all applicable EN DES-approved design drawings and/or the EN DES-approved manufacturer's instructions when installing fire dampers.
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