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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20210B8491999-07-21021 July 1999 Exemption from Certain Requirements of 10CFR50.54(w),for Three Mile Island Nuclear Station Unit 2 to Reduce Amount of Insurance for Unit to $50 Million for Onsite Property Damage Coverage ML20206D4141999-04-20020 April 1999 Exemption from Requirements of 10CFR50,App R,Section III.G.2 Re Enclosure of Cable & Equipment & Associated non-safety Related Circuits of One Redundant Train in Fire Barrier Having 1-hour Rating ML20206T7211999-02-11011 February 1999 Memorandum & Order (CLI-99-02).* Denies C George Request for Intervention & Dismisses Subpart M License Transfer Proceeding.With Certificate of Svc.Served on 990211 ML20198A5111998-12-11011 December 1998 Comment Opposing Proposed Rule 10CFR50.65 Re Requirements for Monitoring Effectiveness of Maintenance at Nuclear Power Plants.Proposed Rulemaking Details Collaborative Efforts in That Rule Interjects Change ML20154G2941998-09-17017 September 1998 Transcript of 980917 Public Meeting in Rockville,Md Re License Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen. Pp 1-41 ML20199J0121997-11-20020 November 1997 Comment on Pr 10CFR50 Re Financial Assurance Requirements for Decommisioning Nuclear Power Reactors.Three Mile Island Alert Invokes Comments of P Bradford,Former NRC Member ML20148R7581997-06-30030 June 1997 Comment on NRC Proposed Bulletin 96-001,suppl 1, Control Rod Insertion Problems. Licensee References Proposed Generic Communication, Control Rod Insertion, & Ltrs & 961022 from B&W Owners Group ML20078H0431995-02-0101 February 1995 Comment Opposing Proposed Rule 10CFR50 Re Shutdown & Lowpower Operations for Nuclear Reactors ML20077E8231994-12-0808 December 1994 Comment Supporting Proposed Rules 10CFR2,51 & 54 Re Rev to NRC NPP License Renewal Rule ML20149E2021994-04-20020 April 1994 R Gary Statement Re 10 Mile Rule Under Director'S Decision DD-94-03,dtd 940331 for Tmi.Urges Commissioners to Engage in Reconsideration of Author Petition ML20065Q0671994-04-0707 April 1994 Principal Deficiencies in Director'S Decision 94-03 Re Pica Request Under 10CFR2.206 ML20058A5491993-11-17017 November 1993 Exemption from Requirements in 10CFR50.120 to Establish, Implement & Maintain Training Programs,Using Sys Approach to Training,For Catorgories of Personnel Listed in 10CFR50.120 ML20059J5171993-09-30030 September 1993 Transcript of 930923 Meeting of Advisory Panel for Decontamination of TMI-2 in Harrisburg,Pa.Pp 1-130.Related Documentation Encl ML20065J3461992-12-30030 December 1992 Responds to Petition of R Gary Alleging Discrepancies in RERP for Dauphin County,Pa ML20065J3731992-12-18018 December 1992 Affidavit of Gj Giangi Responding to of R Gary Requesting Action by NRC Per 10CFR2.206 ML20198E5581992-12-0101 December 1992 Transcript of Briefing by TMI-2 Advisory Panel on 921201 in Rockville,Md ML20210D7291992-06-15015 June 1992 Exemption from Requirements of 10CFR70.24 Re Criticality Accident Requirements for SNM Storage Areas at Facility Containing U Enriched to Less than 3% in U-235 Isotope ML20079E2181991-09-30030 September 1991 Submits Comments on NRC Proposed Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. Informs That Util Endorses Comments Submitted by NUMARC ML20066J3031991-01-28028 January 1991 Comment Supporting SECY-90-347, Regulatory Impact Survey Rept ML20059P0531990-10-15015 October 1990 Comment Opposing Proposed Rules 10CFR2,50 & 54 Re Nuclear Power Plant License Renewal ML20059N5941990-10-0404 October 1990 Transcript of 900928 Public Meeting in Rockville,Md Re Studies of Cancer in Populations Near Nuclear Facilities, Including TMI ML20055F4411990-06-28028 June 1990 Comment Supporting Petition for Rulemaking PRM-50-55 Re Revs to FSAR ML20248J1891989-10-0606 October 1989 Order.* Grants Intervenors 891004 Motion for Permission for Opportunity to Respond to Staff Correspondence.Response Requested No Later That 891020.W/Certificate of Svc.Served on 891006 ML20248J1881989-10-0303 October 1989 Motion for Permission for Opportunity to Respond to Staff Correspondence in Response to Board Order of 890913.* Svc List Encl ML20248J0301989-09-29029 September 1989 NRC Staff Response to Appeal Board Order.* Matters Evaluated in Environ Assessment Involved Subjs Known by Parties During Proceeding & Appear in Hearing Record & Reflect Board Final Initial Decision LBP-89-7.W/Certificate of Svc ML20247E9181989-09-13013 September 1989 Order.* Requests NRC to Explain Purpose of 890911 Fr Notice on Proposed Amend to Applicant License,Revising Tech Specs Re Disposal of Accident Generated Water & Effects on ASLB Findings,By 890929.W/Certificate of Svc.Served on 890913 ML20247G0361989-07-26026 July 1989 Transcript of Oral Argument on 890726 in Bethesda,Md Re Disposal of accident-generated Water.Pp 1-65.Supporting Info Encl ML20247B7781989-07-18018 July 1989 Certificate of Svc.* Certifies Svc of Encl Gpu 890607 & 0628 Ltrs to NRC & Commonwealth of Pa,Respectively.W/Svc List ML20245D3651989-06-20020 June 1989 Notice of Oral Argument.* Oral Argument on Appeal of Susquehanna Valley Alliance & TMI Alert from ASLB 890202 Initial Decision Authorizing OL Amend,Will Be Heard on 890726 in Bethesda,Md.W/Certificate of Svc.Served on 890620 ML20245A5621989-06-14014 June 1989 Order.* Advises That Oral Argument on Appeal of Susquehanna Valley Alliance & TMI Alert from Board 890202 Initial Decision LBP-89-07 Authorizing OL Amend Will Be Heard on 890726 in Bethesda,Md.W/Certificate of Svc.Served on 890614 ML20247F3151989-05-22022 May 1989 NRC Staff Response to Appeal by Joint Intervenors Susquehanna Valley Alliance/Tmi Alert.* Appeal Should Be Denied Based on Failure to Identify Errors in Fact & Law Subj to Appeal.W/Certificate of Svc ML20246Q2971989-05-15015 May 1989 Comment Opposing Proposed Rule 10CFR50 Re Ensuring Effectiveness of Maint Programs for Nuclear Power Plants ML20246J6081989-05-12012 May 1989 Licensee Brief in Reply to Joint Intervenors Appeal from Final Initial Decision.* ASLB 890203 Final Initial Decision LBP-89-07 Re Deleting Prohibition on Disposal of accident- Generated Water Should Be Affirmed.W/Certificate of Svc ML20247D2761989-04-20020 April 1989 Transcript of 890420 Briefing in Rockville,Md on Status of TMI-2 Cleanup Activities.Pp 1-51.Related Info Encl ML20244C0361989-04-13013 April 1989 Order.* Commission Finds That ASLB Decision Resolving All Relevant Matters in Favor of Licensee & Granting Application for OL Amend,Should Become Effective Immediately.Certificate of Svc Encl.Served on 890413 ML20245A8381989-04-13013 April 1989 Transcript of Advisory Panel for Decontamination of TMI-2 890413 Meeting in Harrisburg,Pa.Pp 1-79.Supporting Info Encl ML20245A2961989-04-13013 April 1989 Transcript of 890413 Meeting in Rockville,Md Re Affirmation/Discussion & Vote ML20248H1811989-04-0606 April 1989 Valley Alliance/Tmi Alert Motion for Leave to File Appeal Brief out-of-time.* W/Certificate of Svc.Served on 890411.Granted for Aslab on 890410 ML20248G0151989-04-0606 April 1989 Valley Alliance/Tmi Alert Motion for Leave to File Appeal Brief out-of-time.* Requests to File Appeal Brief 1 Day Late Due to Person Typing Document Having Schedule Problems ML20248G0261989-04-0606 April 1989 Susguehanna Valley Alliance/Tmi Alert Brief in Support of Notification to File Appeal & Request for Oral Argument Re Appeal.* Certificate of Svc Encl ML20248D7211989-04-0404 April 1989 Memorandum & Order.* Intervenors Application for Stay Denied Due to Failure to Lack of Demonstrated Irreparable Injury & Any Showing of Certainty That Intervenors Will Prevail on Merits of Appeal.W/Certificate of Svc.Served on 890404 ML20247A4671989-03-23023 March 1989 Correction Notice.* Advises That Date of 891203 Appearing in Text of Commission 890322 Order Incorrect.Date Should Be 871203.Certificate of Svc Encl.Served on 890323 ML20246M2611989-03-22022 March 1989 Order.* Advises That Commission Currently Considering Question of Effectiveness,Pending Appellate Review of Final Initial Decision in Case Issued by ASLB in LBP-89-07. Certificate of Svc Encl.Served on 890322 ML20236D3821989-03-16016 March 1989 Valley Alliance & TMI Alert Motion for Extension of Time to File Brief in Support of Request for Appeal in Matter of 2.3 Million Gallons Of....* Certificate of Svc Encl.Served on 890316.Granted for Aslab on 890316 ML20236D3121989-03-15015 March 1989 Licensee Answer to Joint Intervenors Motion for Extension of Time to File Brief on Appeal.* Motion Opposed Based on Failure to Demonstrate Good Cause.W/Certificate of Svc ML20236D2901989-03-11011 March 1989 Valley Alliance/Tmi Alert Motion for Extension of Time to File Brief in Support of Request for Appeal in Matter of Disposal of 2.3 Million Gallons of Radioactive Water at Tmi,Unit 2.* Svc List Encl ML20236A3761989-03-0808 March 1989 Licensee Answer Opposing Joint Intervenors Motion for Stay.* Stay of Licensing Board Decision Pending Appeal Unwarranted Under NRC Stds.Stay Could Delay Safe,Expeditious Cleanup of Facility.Certificate of Svc Encl ML20236C2441989-03-0808 March 1989 NRC Staff Response in Opposition to Application for Stay Filed by Joint Intervenors.* Application for Stay of Effectiveness of Final Initial Decision LBP-89-07,dtd 890202 Should Be Denied.W/Certificate of Svc ML20235V2641989-03-0202 March 1989 Notice of Aslab Reconstitution.* TS Moore,Chairman,Cn Kohl & Ha Wilber,Members.Served on 890303.W/Certificate of Svc ML20235V2161989-02-25025 February 1989 Changes & Corrections to Susquehanna Valley Alliance/Three Mile Island Alert Documents Submitted on 890221.* Certificate of Svc Encl 1999-07-21
[Table view] Category:TRANSCRIPTS
MONTHYEARML20154G2941998-09-17017 September 1998 Transcript of 980917 Public Meeting in Rockville,Md Re License Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen. Pp 1-41 ML20059J5171993-09-30030 September 1993 Transcript of 930923 Meeting of Advisory Panel for Decontamination of TMI-2 in Harrisburg,Pa.Pp 1-130.Related Documentation Encl ML20198E5581992-12-0101 December 1992 Transcript of Briefing by TMI-2 Advisory Panel on 921201 in Rockville,Md ML20059N5941990-10-0404 October 1990 Transcript of 900928 Public Meeting in Rockville,Md Re Studies of Cancer in Populations Near Nuclear Facilities, Including TMI ML20247G0361989-07-26026 July 1989 Transcript of Oral Argument on 890726 in Bethesda,Md Re Disposal of accident-generated Water.Pp 1-65.Supporting Info Encl ML20247D2761989-04-20020 April 1989 Transcript of 890420 Briefing in Rockville,Md on Status of TMI-2 Cleanup Activities.Pp 1-51.Related Info Encl ML20245A2961989-04-13013 April 1989 Transcript of 890413 Meeting in Rockville,Md Re Affirmation/Discussion & Vote ML20245A8381989-04-13013 April 1989 Transcript of Advisory Panel for Decontamination of TMI-2 890413 Meeting in Harrisburg,Pa.Pp 1-79.Supporting Info Encl ML20235N2161989-02-17017 February 1989 Follow-up Testimony Clarifying Position on Question of Disposition of Over 2 Million Gallons of Accident Generated Water.Related Documentation & Certificate of Svc Encl ML20235S9911989-02-16016 February 1989 Transcript of 890216 Public Meeting of Advisory Panel for Decontamination of TMI-2 in Harrisburg,Pa.Pp 1-119. Supporting Documentation Encl ML20206C9391988-11-0707 November 1988 Transcript of 881107 Hearing in Lancaster,Pa.Pp 1,122- 1,417.Witnesses:JA Auxier,Ji Fabrikant,Skolnik & Mather ML20235M7601988-11-0303 November 1988 Transcript of 881103 Public Hearing in Lancaster,Pa for Presentation of Limited Appearance Statements.Pp 998-1,121 ML20206C2801988-11-0303 November 1988 Transcript of 881103 Hearing in Lancaster,Pa Re TMI-2 License Amend Application.Pp 859-997.Witnesses:JA Martin, SS Yaniv,F Skolnik,S Lewis & a Bhattacharyya ML20205Q6581988-11-0202 November 1988 Transcript of 881102 Hearing in Lancaster,Pa Re TMI-2 License Amend Application.Pp 573-858.Supporting Documentation Encl.Witnesses:Gg Baker,Wj Cooper & L Munson ML20205Q6441988-11-0101 November 1988 Transcript of 881101 Hearing in Lancaster,Pa Re TMI-2 License Amend Application.Pp 288-572.Supporting Info Encl. Witnesses:K Hofstetter,Kl Harner,L Thomas & M Masnik ML20205N5791988-10-31031 October 1988 Transcript of ASLB 881031 Meeting in Lancaster,Pa Re License Amend Application.Pp 87-287 ML20205P0451988-10-25025 October 1988 Transcript of 881025 Periodic Briefing by TMI-2 Advisory Panel in Rockville,Md.Pp 1-30 ML20205G1851988-10-25025 October 1988 Licensee Testimony of GG Baker & Wj Cooper on Dose Assessments & Microorganisms (Contentions 2,3 & 5d).* Supporting Documentation Encl.Related Correspondence ML20205E5021988-10-24024 October 1988 Licensee Rebuttal Testimony of Ji Fabrikant on Health Effects of Tritium (Contention 5d).* Related Correspondence ML20155H1751988-10-11011 October 1988 Licensee Testimony of GG Baker & Wj Cooper on Dose Assessments & Microorganisms (Contentions 2,3 & 5d).* Related Correspondence ML20155H1531988-10-11011 October 1988 Licensee Testimony of Ww Weaver on Accident Risks (Contention 2).* Related Correspondence ML20155H1901988-10-11011 October 1988 Licensee Testimony of Ja Auxier & Ji Fabrikant on Effects of Tritium (Contentions 3 & 5d).* Supporting Info Encl.Related Correpondence ML20155H1661988-10-11011 October 1988 Licensee Testimony of Kl Harner & Kj Hofstetter on Sampling & Analysis of accident-generated Water (Contentions 3 & 4b).* Related Correspondence ML20155H1401988-10-11011 October 1988 Licensee Testimony of Je Tarpinian on Occupational Dose Assessments (Contention 2).* Related Correspondence ML20155H1281988-10-11011 October 1988 Licensee Testimony of Dr Buchanan on Evaporation Proposal & Joint Intervenors Alternative (Contentions 2 & 3).* Related Correspondence ML20155H4751988-10-10010 October 1988 Testimony.* Discusses Environ Impact of Force Evaporation of 2.3 Million Gallons of accident-generated Water by Licensee. W/Certificate of Svc.Related Correspondence ML20155H4711988-10-10010 October 1988 Affidavit of Cw Huver (Contention 5):further Considerations of Biological Effects & Health Hazards of Tritium.* Copyrighted Matl Encl.Related Correspondence ML20154D5201988-09-0707 September 1988 Transcript of Advisory Panel for Decontamination of TMI-2 880907 Meeting in Harrisburg,Pa.Pp 1-109.Supporting Documentation Encl ML20151G6951988-07-14014 July 1988 Transcript of Advisory Panel for Decontamination of TMI-2 880714 Meeting in Harrisburg,Pa.Pp 1-140.Related Documentation Encl ML20196B6041988-05-26026 May 1988 Transcript of 880526 Advisory Panel Meeting in Harrisburg, PA to Discuss Decontamination of TMI-2.Pp 1-117.Supporting Documentation Encl ML20154N4101988-04-14014 April 1988 Transcript of 880414 Advisory Panel for Decontamination of TMI-2 Public Meeting in Lancaster,Pa.Related Info Encl. Pp 1-100 ML20148F2351988-03-17017 March 1988 Transcript of 880317 Briefing in Washington,Dc Re Status of TMI-2.Pp 1-51.Supporting Documentation Encl ML20236Y1061987-12-0808 December 1987 Transcript of Special Prehearing Conference on 871208 in Harrisburg,Pa Re Disposal of accident-generated Water. Pp 1-86 ML20238C6981987-10-0505 October 1987 Deposition of a Beach.* Transcript of 871005 Deposition in Washington,Dc Re R Parks Allegations.Pp 1-244.Supporting Documentation Encl ML20235J7071987-09-30030 September 1987 Transcript of 870930 Prehearing Conference in Bethesda,Md. Pp 225-343 ML20238D4641987-09-0909 September 1987 Transcript of 870909 Oral Argument in Bethesda,Md.Pp 1-57 ML20238C7531987-08-20020 August 1987 Vol II to Transcript of Hl Hofmann 870820 Deposition in San Francisco,Ca Re Civil Penalty.Pp 208-471 & 489-494. Supporting Documentation Encl ML20238C7891987-08-18018 August 1987 Deposition of Rd Parks.* Vol IV to Transcript of 870818 Deposition in San Francisco,Ca Re Civil Penalty.Pp 551-818. Supporting Documentation Encl ML20238C7651987-06-25025 June 1987 Deposition of Hl Hofmann.* Transcript of 870625 Deposition in San Francisco,Ca Re Civil Penalty.Pp 1-206 ML20238C8041987-06-24024 June 1987 Deposition of Rd Parks.* Vol III to Transcript of 870624 Deposition in Newport Beach,Ca Re Civil Penalty.Pp III-1 - III-89 ML20235J1271987-06-24024 June 1987 Deposition of Rd Parks.* Vols II & III of Transcript of Rd Parks 870624 Deposition.Related Correspondence ML20238C7981987-06-23023 June 1987 Deposition of Rd Parks.* Vol II to Transcript of 870623 Deposition in Newport Beach,Ca Re Civil Penalty.Pp II-1 - II-263.Supporting Documentation Encl ML20238C7941987-06-22022 June 1987 Deposition of Rd Parks.* Vol I to Transcript of 870622 Deposition in Newport Beach,Ca Re Civil Penalty.Pp 1-199. Supporting Documentation Encl ML20238C5921987-06-16016 June 1987 Deposition of R Meeks.* Transcript of 870616 Deposition in Washington,Dc Re Allegations of Harassment Against R Parks. Pp 1-198.Supporting Documentation Encl ML20238C6171987-06-16016 June 1987 Deposition of R Meeks.* Corrected Title Page of 870616 Deposition ML20215L2731987-05-0808 May 1987 Transcript of 870508 Prehearing Conference in Bethesda,Md.Pp 19-224.In Camera Session (Pp 101-138) Bound Separately ML20238C7331987-04-24024 April 1987 Deposition of Rc Arnold.* Transcript of 870424 Deposition in Washington,Dc Re Civil Penalty.Pp 1-224.Supporting Documentation Encl ML20212Q9801987-04-16016 April 1987 Transcript of 870416 Periodic Meeting W/Advisory Panel for Decontamination of TMI-2 in Washington,Dc.Pp 1-50.Supporting Documentation Encl ML20212Q8021987-04-15015 April 1987 Transcript of 870415 Briefing by DOE in Washington,Dc Re TMI-2 Core Exam Program.Pp 1-64.Viewgraphs Encl ML20238C6521987-04-10010 April 1987 Deposition of Bk Kanga.* Transcript of 870410 Deposition in Gaithersburg,Md Re R Parks.Pp 1-151.Supporting Documentation Encl 1998-09-17
[Table view] Category:DEPOSITIONS
MONTHYEARML20154G2941998-09-17017 September 1998 Transcript of 980917 Public Meeting in Rockville,Md Re License Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen. Pp 1-41 ML20059J5171993-09-30030 September 1993 Transcript of 930923 Meeting of Advisory Panel for Decontamination of TMI-2 in Harrisburg,Pa.Pp 1-130.Related Documentation Encl ML20198E5581992-12-0101 December 1992 Transcript of Briefing by TMI-2 Advisory Panel on 921201 in Rockville,Md ML20059N5941990-10-0404 October 1990 Transcript of 900928 Public Meeting in Rockville,Md Re Studies of Cancer in Populations Near Nuclear Facilities, Including TMI ML20247G0361989-07-26026 July 1989 Transcript of Oral Argument on 890726 in Bethesda,Md Re Disposal of accident-generated Water.Pp 1-65.Supporting Info Encl ML20247D2761989-04-20020 April 1989 Transcript of 890420 Briefing in Rockville,Md on Status of TMI-2 Cleanup Activities.Pp 1-51.Related Info Encl ML20245A2961989-04-13013 April 1989 Transcript of 890413 Meeting in Rockville,Md Re Affirmation/Discussion & Vote ML20245A8381989-04-13013 April 1989 Transcript of Advisory Panel for Decontamination of TMI-2 890413 Meeting in Harrisburg,Pa.Pp 1-79.Supporting Info Encl ML20235N2161989-02-17017 February 1989 Follow-up Testimony Clarifying Position on Question of Disposition of Over 2 Million Gallons of Accident Generated Water.Related Documentation & Certificate of Svc Encl ML20235S9911989-02-16016 February 1989 Transcript of 890216 Public Meeting of Advisory Panel for Decontamination of TMI-2 in Harrisburg,Pa.Pp 1-119. Supporting Documentation Encl ML20206C9391988-11-0707 November 1988 Transcript of 881107 Hearing in Lancaster,Pa.Pp 1,122- 1,417.Witnesses:JA Auxier,Ji Fabrikant,Skolnik & Mather ML20235M7601988-11-0303 November 1988 Transcript of 881103 Public Hearing in Lancaster,Pa for Presentation of Limited Appearance Statements.Pp 998-1,121 ML20206C2801988-11-0303 November 1988 Transcript of 881103 Hearing in Lancaster,Pa Re TMI-2 License Amend Application.Pp 859-997.Witnesses:JA Martin, SS Yaniv,F Skolnik,S Lewis & a Bhattacharyya ML20205Q6581988-11-0202 November 1988 Transcript of 881102 Hearing in Lancaster,Pa Re TMI-2 License Amend Application.Pp 573-858.Supporting Documentation Encl.Witnesses:Gg Baker,Wj Cooper & L Munson ML20205Q6441988-11-0101 November 1988 Transcript of 881101 Hearing in Lancaster,Pa Re TMI-2 License Amend Application.Pp 288-572.Supporting Info Encl. Witnesses:K Hofstetter,Kl Harner,L Thomas & M Masnik ML20205N5791988-10-31031 October 1988 Transcript of ASLB 881031 Meeting in Lancaster,Pa Re License Amend Application.Pp 87-287 ML20205P0451988-10-25025 October 1988 Transcript of 881025 Periodic Briefing by TMI-2 Advisory Panel in Rockville,Md.Pp 1-30 ML20205G1851988-10-25025 October 1988 Licensee Testimony of GG Baker & Wj Cooper on Dose Assessments & Microorganisms (Contentions 2,3 & 5d).* Supporting Documentation Encl.Related Correspondence ML20205E5021988-10-24024 October 1988 Licensee Rebuttal Testimony of Ji Fabrikant on Health Effects of Tritium (Contention 5d).* Related Correspondence ML20155H1751988-10-11011 October 1988 Licensee Testimony of GG Baker & Wj Cooper on Dose Assessments & Microorganisms (Contentions 2,3 & 5d).* Related Correspondence ML20155H1531988-10-11011 October 1988 Licensee Testimony of Ww Weaver on Accident Risks (Contention 2).* Related Correspondence ML20155H1901988-10-11011 October 1988 Licensee Testimony of Ja Auxier & Ji Fabrikant on Effects of Tritium (Contentions 3 & 5d).* Supporting Info Encl.Related Correpondence ML20155H1661988-10-11011 October 1988 Licensee Testimony of Kl Harner & Kj Hofstetter on Sampling & Analysis of accident-generated Water (Contentions 3 & 4b).* Related Correspondence ML20155H1401988-10-11011 October 1988 Licensee Testimony of Je Tarpinian on Occupational Dose Assessments (Contention 2).* Related Correspondence ML20155H1281988-10-11011 October 1988 Licensee Testimony of Dr Buchanan on Evaporation Proposal & Joint Intervenors Alternative (Contentions 2 & 3).* Related Correspondence ML20155H4751988-10-10010 October 1988 Testimony.* Discusses Environ Impact of Force Evaporation of 2.3 Million Gallons of accident-generated Water by Licensee. W/Certificate of Svc.Related Correspondence ML20155H4711988-10-10010 October 1988 Affidavit of Cw Huver (Contention 5):further Considerations of Biological Effects & Health Hazards of Tritium.* Copyrighted Matl Encl.Related Correspondence ML20154D5201988-09-0707 September 1988 Transcript of Advisory Panel for Decontamination of TMI-2 880907 Meeting in Harrisburg,Pa.Pp 1-109.Supporting Documentation Encl ML20151G6951988-07-14014 July 1988 Transcript of Advisory Panel for Decontamination of TMI-2 880714 Meeting in Harrisburg,Pa.Pp 1-140.Related Documentation Encl ML20196B6041988-05-26026 May 1988 Transcript of 880526 Advisory Panel Meeting in Harrisburg, PA to Discuss Decontamination of TMI-2.Pp 1-117.Supporting Documentation Encl ML20154N4101988-04-14014 April 1988 Transcript of 880414 Advisory Panel for Decontamination of TMI-2 Public Meeting in Lancaster,Pa.Related Info Encl. Pp 1-100 ML20148F2351988-03-17017 March 1988 Transcript of 880317 Briefing in Washington,Dc Re Status of TMI-2.Pp 1-51.Supporting Documentation Encl ML20236Y1061987-12-0808 December 1987 Transcript of Special Prehearing Conference on 871208 in Harrisburg,Pa Re Disposal of accident-generated Water. Pp 1-86 ML20238C6981987-10-0505 October 1987 Deposition of a Beach.* Transcript of 871005 Deposition in Washington,Dc Re R Parks Allegations.Pp 1-244.Supporting Documentation Encl ML20235J7071987-09-30030 September 1987 Transcript of 870930 Prehearing Conference in Bethesda,Md. Pp 225-343 ML20238D4641987-09-0909 September 1987 Transcript of 870909 Oral Argument in Bethesda,Md.Pp 1-57 ML20238C7531987-08-20020 August 1987 Vol II to Transcript of Hl Hofmann 870820 Deposition in San Francisco,Ca Re Civil Penalty.Pp 208-471 & 489-494. Supporting Documentation Encl ML20238C7891987-08-18018 August 1987 Deposition of Rd Parks.* Vol IV to Transcript of 870818 Deposition in San Francisco,Ca Re Civil Penalty.Pp 551-818. Supporting Documentation Encl ML20238C7651987-06-25025 June 1987 Deposition of Hl Hofmann.* Transcript of 870625 Deposition in San Francisco,Ca Re Civil Penalty.Pp 1-206 ML20238C8041987-06-24024 June 1987 Deposition of Rd Parks.* Vol III to Transcript of 870624 Deposition in Newport Beach,Ca Re Civil Penalty.Pp III-1 - III-89 ML20235J1271987-06-24024 June 1987 Deposition of Rd Parks.* Vols II & III of Transcript of Rd Parks 870624 Deposition.Related Correspondence ML20238C7981987-06-23023 June 1987 Deposition of Rd Parks.* Vol II to Transcript of 870623 Deposition in Newport Beach,Ca Re Civil Penalty.Pp II-1 - II-263.Supporting Documentation Encl ML20238C7941987-06-22022 June 1987 Deposition of Rd Parks.* Vol I to Transcript of 870622 Deposition in Newport Beach,Ca Re Civil Penalty.Pp 1-199. Supporting Documentation Encl ML20238C5921987-06-16016 June 1987 Deposition of R Meeks.* Transcript of 870616 Deposition in Washington,Dc Re Allegations of Harassment Against R Parks. Pp 1-198.Supporting Documentation Encl ML20238C6171987-06-16016 June 1987 Deposition of R Meeks.* Corrected Title Page of 870616 Deposition ML20215L2731987-05-0808 May 1987 Transcript of 870508 Prehearing Conference in Bethesda,Md.Pp 19-224.In Camera Session (Pp 101-138) Bound Separately ML20238C7331987-04-24024 April 1987 Deposition of Rc Arnold.* Transcript of 870424 Deposition in Washington,Dc Re Civil Penalty.Pp 1-224.Supporting Documentation Encl ML20212Q9801987-04-16016 April 1987 Transcript of 870416 Periodic Meeting W/Advisory Panel for Decontamination of TMI-2 in Washington,Dc.Pp 1-50.Supporting Documentation Encl ML20212Q8021987-04-15015 April 1987 Transcript of 870415 Briefing by DOE in Washington,Dc Re TMI-2 Core Exam Program.Pp 1-64.Viewgraphs Encl ML20238C6521987-04-10010 April 1987 Deposition of Bk Kanga.* Transcript of 870410 Deposition in Gaithersburg,Md Re R Parks.Pp 1-151.Supporting Documentation Encl 1998-09-17
[Table view] Category:NARRATIVE TESTIMONY
MONTHYEARML20154G2941998-09-17017 September 1998 Transcript of 980917 Public Meeting in Rockville,Md Re License Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen. Pp 1-41 ML20059J5171993-09-30030 September 1993 Transcript of 930923 Meeting of Advisory Panel for Decontamination of TMI-2 in Harrisburg,Pa.Pp 1-130.Related Documentation Encl ML20198E5581992-12-0101 December 1992 Transcript of Briefing by TMI-2 Advisory Panel on 921201 in Rockville,Md ML20059N5941990-10-0404 October 1990 Transcript of 900928 Public Meeting in Rockville,Md Re Studies of Cancer in Populations Near Nuclear Facilities, Including TMI ML20247G0361989-07-26026 July 1989 Transcript of Oral Argument on 890726 in Bethesda,Md Re Disposal of accident-generated Water.Pp 1-65.Supporting Info Encl ML20247D2761989-04-20020 April 1989 Transcript of 890420 Briefing in Rockville,Md on Status of TMI-2 Cleanup Activities.Pp 1-51.Related Info Encl ML20245A2961989-04-13013 April 1989 Transcript of 890413 Meeting in Rockville,Md Re Affirmation/Discussion & Vote ML20245A8381989-04-13013 April 1989 Transcript of Advisory Panel for Decontamination of TMI-2 890413 Meeting in Harrisburg,Pa.Pp 1-79.Supporting Info Encl ML20235N2161989-02-17017 February 1989 Follow-up Testimony Clarifying Position on Question of Disposition of Over 2 Million Gallons of Accident Generated Water.Related Documentation & Certificate of Svc Encl ML20235S9911989-02-16016 February 1989 Transcript of 890216 Public Meeting of Advisory Panel for Decontamination of TMI-2 in Harrisburg,Pa.Pp 1-119. Supporting Documentation Encl ML20206C9391988-11-0707 November 1988 Transcript of 881107 Hearing in Lancaster,Pa.Pp 1,122- 1,417.Witnesses:JA Auxier,Ji Fabrikant,Skolnik & Mather ML20235M7601988-11-0303 November 1988 Transcript of 881103 Public Hearing in Lancaster,Pa for Presentation of Limited Appearance Statements.Pp 998-1,121 ML20206C2801988-11-0303 November 1988 Transcript of 881103 Hearing in Lancaster,Pa Re TMI-2 License Amend Application.Pp 859-997.Witnesses:JA Martin, SS Yaniv,F Skolnik,S Lewis & a Bhattacharyya ML20205Q6581988-11-0202 November 1988 Transcript of 881102 Hearing in Lancaster,Pa Re TMI-2 License Amend Application.Pp 573-858.Supporting Documentation Encl.Witnesses:Gg Baker,Wj Cooper & L Munson ML20205Q6441988-11-0101 November 1988 Transcript of 881101 Hearing in Lancaster,Pa Re TMI-2 License Amend Application.Pp 288-572.Supporting Info Encl. Witnesses:K Hofstetter,Kl Harner,L Thomas & M Masnik ML20205N5791988-10-31031 October 1988 Transcript of ASLB 881031 Meeting in Lancaster,Pa Re License Amend Application.Pp 87-287 ML20205P0451988-10-25025 October 1988 Transcript of 881025 Periodic Briefing by TMI-2 Advisory Panel in Rockville,Md.Pp 1-30 ML20205G1851988-10-25025 October 1988 Licensee Testimony of GG Baker & Wj Cooper on Dose Assessments & Microorganisms (Contentions 2,3 & 5d).* Supporting Documentation Encl.Related Correspondence ML20205E5021988-10-24024 October 1988 Licensee Rebuttal Testimony of Ji Fabrikant on Health Effects of Tritium (Contention 5d).* Related Correspondence ML20155H1751988-10-11011 October 1988 Licensee Testimony of GG Baker & Wj Cooper on Dose Assessments & Microorganisms (Contentions 2,3 & 5d).* Related Correspondence ML20155H1531988-10-11011 October 1988 Licensee Testimony of Ww Weaver on Accident Risks (Contention 2).* Related Correspondence ML20155H1901988-10-11011 October 1988 Licensee Testimony of Ja Auxier & Ji Fabrikant on Effects of Tritium (Contentions 3 & 5d).* Supporting Info Encl.Related Correpondence ML20155H1661988-10-11011 October 1988 Licensee Testimony of Kl Harner & Kj Hofstetter on Sampling & Analysis of accident-generated Water (Contentions 3 & 4b).* Related Correspondence ML20155H1401988-10-11011 October 1988 Licensee Testimony of Je Tarpinian on Occupational Dose Assessments (Contention 2).* Related Correspondence ML20155H1281988-10-11011 October 1988 Licensee Testimony of Dr Buchanan on Evaporation Proposal & Joint Intervenors Alternative (Contentions 2 & 3).* Related Correspondence ML20155H4751988-10-10010 October 1988 Testimony.* Discusses Environ Impact of Force Evaporation of 2.3 Million Gallons of accident-generated Water by Licensee. W/Certificate of Svc.Related Correspondence ML20155H4711988-10-10010 October 1988 Affidavit of Cw Huver (Contention 5):further Considerations of Biological Effects & Health Hazards of Tritium.* Copyrighted Matl Encl.Related Correspondence ML20154D5201988-09-0707 September 1988 Transcript of Advisory Panel for Decontamination of TMI-2 880907 Meeting in Harrisburg,Pa.Pp 1-109.Supporting Documentation Encl ML20151G6951988-07-14014 July 1988 Transcript of Advisory Panel for Decontamination of TMI-2 880714 Meeting in Harrisburg,Pa.Pp 1-140.Related Documentation Encl ML20196B6041988-05-26026 May 1988 Transcript of 880526 Advisory Panel Meeting in Harrisburg, PA to Discuss Decontamination of TMI-2.Pp 1-117.Supporting Documentation Encl ML20154N4101988-04-14014 April 1988 Transcript of 880414 Advisory Panel for Decontamination of TMI-2 Public Meeting in Lancaster,Pa.Related Info Encl. Pp 1-100 ML20148F2351988-03-17017 March 1988 Transcript of 880317 Briefing in Washington,Dc Re Status of TMI-2.Pp 1-51.Supporting Documentation Encl ML20236Y1061987-12-0808 December 1987 Transcript of Special Prehearing Conference on 871208 in Harrisburg,Pa Re Disposal of accident-generated Water. Pp 1-86 ML20238C6981987-10-0505 October 1987 Deposition of a Beach.* Transcript of 871005 Deposition in Washington,Dc Re R Parks Allegations.Pp 1-244.Supporting Documentation Encl ML20235J7071987-09-30030 September 1987 Transcript of 870930 Prehearing Conference in Bethesda,Md. Pp 225-343 ML20238D4641987-09-0909 September 1987 Transcript of 870909 Oral Argument in Bethesda,Md.Pp 1-57 ML20238C7531987-08-20020 August 1987 Vol II to Transcript of Hl Hofmann 870820 Deposition in San Francisco,Ca Re Civil Penalty.Pp 208-471 & 489-494. Supporting Documentation Encl ML20238C7891987-08-18018 August 1987 Deposition of Rd Parks.* Vol IV to Transcript of 870818 Deposition in San Francisco,Ca Re Civil Penalty.Pp 551-818. Supporting Documentation Encl ML20238C7651987-06-25025 June 1987 Deposition of Hl Hofmann.* Transcript of 870625 Deposition in San Francisco,Ca Re Civil Penalty.Pp 1-206 ML20238C8041987-06-24024 June 1987 Deposition of Rd Parks.* Vol III to Transcript of 870624 Deposition in Newport Beach,Ca Re Civil Penalty.Pp III-1 - III-89 ML20235J1271987-06-24024 June 1987 Deposition of Rd Parks.* Vols II & III of Transcript of Rd Parks 870624 Deposition.Related Correspondence ML20238C7981987-06-23023 June 1987 Deposition of Rd Parks.* Vol II to Transcript of 870623 Deposition in Newport Beach,Ca Re Civil Penalty.Pp II-1 - II-263.Supporting Documentation Encl ML20238C7941987-06-22022 June 1987 Deposition of Rd Parks.* Vol I to Transcript of 870622 Deposition in Newport Beach,Ca Re Civil Penalty.Pp 1-199. Supporting Documentation Encl ML20238C5921987-06-16016 June 1987 Deposition of R Meeks.* Transcript of 870616 Deposition in Washington,Dc Re Allegations of Harassment Against R Parks. Pp 1-198.Supporting Documentation Encl ML20238C6171987-06-16016 June 1987 Deposition of R Meeks.* Corrected Title Page of 870616 Deposition ML20215L2731987-05-0808 May 1987 Transcript of 870508 Prehearing Conference in Bethesda,Md.Pp 19-224.In Camera Session (Pp 101-138) Bound Separately ML20238C7331987-04-24024 April 1987 Deposition of Rc Arnold.* Transcript of 870424 Deposition in Washington,Dc Re Civil Penalty.Pp 1-224.Supporting Documentation Encl ML20212Q9801987-04-16016 April 1987 Transcript of 870416 Periodic Meeting W/Advisory Panel for Decontamination of TMI-2 in Washington,Dc.Pp 1-50.Supporting Documentation Encl ML20212Q8021987-04-15015 April 1987 Transcript of 870415 Briefing by DOE in Washington,Dc Re TMI-2 Core Exam Program.Pp 1-64.Viewgraphs Encl ML20238C6521987-04-10010 April 1987 Deposition of Bk Kanga.* Transcript of 870410 Deposition in Gaithersburg,Md Re R Parks.Pp 1-151.Supporting Documentation Encl 1998-09-17
[Table view] |
Text
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WTED COmg.g f LIC 9/15/80 - %,
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UNITED STATES OF t.MERICA N NUCLEAR REGULATORY COMMISSION 1s te
1 BEFORE THE ATOMIC SAFETY AND LICENSING BOARD i
In the Matter of )
)
4 METROPOLITAN EDISON COMPANY ) Docket No. 50-289
) (Restar t)
(Three Mile Island Nuclear )
Station , Unit No. 1) )
I l
l LICENSEE'S TESTIMONY OF ROBERT C. JONES, JR., AND T. GARY BROUGHTON IN RESPONSE TO UCS CONTENTION NO. 8 AND ECNP CONTENTION NO. 1(e)
(ADDITIONAL LOCA ANALYSIS) l l
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OUTLINE The purposes and objectives of this testimony are to respond to UCS Contention 8, which asserts that adequate small-break loss of coolant accident (LOCA) analyses have not been performed, and to respond to related Board questions. The testimony addresses the small-break LOCA analyses performed prior to the TMI-2 accident and their conformance to 10 CFR Part 50, Section 50.46. The purpose, assumptions and results of small-break analyses subsequent to the TMI-2 accident are described. Operating guidelines and procedures for small-break LOCA mitigation are discussed. It is shown that adequate protection for small-break LOCA's is provided.
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INDEX INTRODUCTION .............................................. 1 RESPONSE TO UCS CONTENTION NO. 8 .......................... 2 TABLE SUMMARIZING PRE-TMI-2 LOCA EVALUATIONS .............. 12 TABLES SUMMARIZING LOCA ANALYSES RESULTS .................. 13 1
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INTRODUCTION This testimony, by Mr. Robert C. Jones, Jr., Supervisory Engineer , ECCS Analysis Unit, Babcock & Wilcox Company, and Mr.
T. Gary Broughton, GPU Control and Safety Analysis Manager, is addressed to the following contention:
UCS CONTENTION NO. 8 10 CFR 50.46 requires analysis of ECCS performance "for a number of postulated loss-of-coolant accidents of different sizes, locations, and other properties sufficient to provide assurance that the entire spectrum of postulatec' loss-of-coolant accidents is covered." For the spectrum of LOCA's, specific perameters are not to be exceeded. At TMI, certain of these were exceeded. For ex ample ,
the peak cladding temperature exceeded 2200' fahrenheit (50.46(b)(1)), and more than 1% of the cladding reacted with water or steam to produce hydrogen (50.46(b)(3 )) . The measures proposed by the staff address primarily the very specific case of a stuck-open power operated relief valve. However, any other sm could lead to the same consequences.all Additional LOCA ,
analyses to show that there is adequate protec- !
tion for the entire spectrum of small break !
locations have not been performed. Ther e for e ,
there is no basis for finding compliance with 10 i 1
CFR 50.46 and GDC 35. None of the corrective actions to date have fully addressed the demonstrated inadequacy of protection against small LOCA's.
ECNP Contention 1(e) was accepted only to the extent that ECNP was permitted to adopt UCS Contention 8. Consequen tly, ECNP Contention 1(e) is not quoted here. (See, Board Memorandum and Order, September 8, 1980.) UCS withdrew its
sponsorship of UCS Contention 8, which has been adopted as a Board Question (See, Board Memorandum and Order of Prehearing Conference of August 12-13, 1980, dated August 20, 1980).
RESPONSE TO UCS CONTENTION NO. 8 BY WITNESS JONES :
UCS Contention 8 asserts that analyses to demonstrate conformance with 10 CFR Part 50, Section 50.46 (10 CFR 50.46) l for the entire spectrum of small-break loss of coolant accident j (LOCA) locations have not been performed. Additionally, it is stated that none of the corrective measures being implemented for TMI-l assure that adequate protection is provided for small-break LOCA 's. Contrary to the contention, compliance with 10 CFR 50.46 has been demonstrated and adequate protection for small-break LOCA's is provided.
Prior to the TMI-2 accident, small-break LOCA evaluations had been performed to verify conformance of TMI-l to 10 CFR 50.46. In order to perform these analysec, the break location which imposes the most severe requirements on the ECCS was identified. As a result of this identification, an analysis was performed of the core flood line break, which results in only one core flood tank and one high pressure injection train available to mitigate the accident under the worst single failure assumption. Also, an analysis of a spectrum of breaks
in the reactor coolant pump discharge piping was performed, as this location results in the loss of a portion of the high pressure injection fluid. These analjaes were performed using the B&W ECCS evaluacion model which has been approved by the NRC as meeting the requirements of Appendix K to 10 CFR Part
- 50. The actual analyses which were performed are contained in References 1 and 2, and are summarized in Table 1. For the worst case break, the peak cladding temperature was less than 1100*F and no metal-water reaction nor cladding rupture were calculated to occur. Therefore, conformance to 10 CFR 50.46 was demonstrated.
The analysis performed prior to the TMI-2 accident assumed the use of only safety-grade equipment for accident mitigation, and assumed no mitigating operator actions within ten minutes of the initiating event, except as follows:
o Emergency feedwater was assumed to be available, o Operator action to cross-connect the High Pressure Injection System (HPI) was determined to be required in the event of a small break in the reactor coolant pump discharge piping and the postulated failure of the HPI train which discharges into the unbroken coolant loop.
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BY WITNESS BROUGHTON:
With regard to the first of the above items, Licensee's testimony on the Emergency Feedwater System (in response to Licensing Board Question No. 6) will address the reliability of the Emergency Feedwater System (EFW).
BY WITNESS JONES:
In the event of a loss of all feedwater following the EFW upgrade, the feed and bleed mode of emergency cooling is available for LOCA mitigation. See Licensee's testimony on Natural and Forced Circulation (in response to UCS Contentions Nos. 1 and 2).
l BY WITNESS BROUGHTON.
With regard to the second of the above items, modifica-tions to the high pressure injection lines have been made to add cross connections and flow limiting devices to ensure sufficient flow without operator action (See, TMI-l Restart Report, Supplement 1, Part 3, responses to questions 1, 2 and 3).
BY WITNESS JONES:
Subsequent to the TMI-2 accidenc', additional small-break ;
LOCA analyses were performed. In light of the fact that the severity of the TMI-2 accident was aggravated by operator l
actions, the purpose of these analyses was to provide an improved analytical basis for emergency operating procedures for small-break LOCA's, not to demonstrate compliance with 10 CFR 50.46. A description of the events analyzed, the key assumptions, and the results of the evaluations are provided in Tables 2 through 8. The analyses performed included an extension of the lower end of the break spectrum previously analyzed, an assessment of the effect of failures in the feedwater system, and an assessment of small-break LOCA's with delayed reactor coolant pump trip. From these analyses it was concluded that multiple failures must occur before a LOCA scenario can result in a challenge to 10 CFR 50.46 limits. A summary of the results of the analyses is also provided below:
o In the event of a loss of all feedwater, without a small-break LOCA, operator action within twenty minutes to either establish emergency feedwater or manually actuate high pressure injection assures that the core remains covered, thus assuring adequate core cooling. (See Table 2.)
o In the event of a small-break LOCA with loss of all feedwater, ECCS may not be automatically actuated. For this situ-ation, operator action within twenty minutes to either establish emergency feedwater flow (which will in turn result in automatic ECCS actuation), or to manually actuate high pressure injection, assures that the core remains covered, thus assuring adequate core cooling. (See Table 3.)
o In the event of a loss of main feedwater followed by the pressurizer power operated relief valve (PORV) opening and failing to close, the automatic actuation of high pressure injection is cufficient to assure adequate core cooling. (See Table 4.)
o In the event of the pressurizer PORV opening and failing to close, followed by the loss of all feedwater , the automatic actuation of high pressure ir.jection is sufficient to assure adequate core cooling.
(See Table 5.)
o For certain very small breaks (between 2
0.005 ft and 0.01 ft2) which cause a loss of coolant inventory at a rate in excess of the capacity of high pressure injection, the steam generators would normally be utilized to remove a portion of the energy added to the primary system fluid by core decay heat. During the transition from natural circulation to the boiler-condenser o
mode of cooling (see Licensee's testimony on Natural and Forced Circulation in response to UCS Contention No. 1), an interruption of the energy removal process from the primary system will occur due to i
void formation in the hot legs, and the primary system pressure will increase.
However, the subsequent establishment of steam condensation by the steam generators as i heat removal mechanism controls the repressurization and assures that the core remains covered, thus assuring adequate core cooling. (See Table 6.)
o If the reactor coolant pumps operate continuously throughout the LOCA transient, or are tripped promptly upon receipt of a low reactor coolant pressure safety signal, adequate core cooling is provided for all break sizes. For certain break sizes (between 0.025 ft 2 and 0.2 ft2), adequate core cooling has not been demonstrated if the reactor coolant pumps remain in operation and are subsequently tripped at certain times in the transient. Therefore, in order to assure adequate core cooling, the reactor coolant pumps should be tripped i
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o In the event of a very small LOCA with loss of all feedwater, system repressurization may actuate the PORV which can subsequently stick open. For this situation, operator action within twenty minutes to either establish emergency feedwater flow (which will in turn result in automatic ECCS actuation) or to manually actuate high pressure injection assures that the core remains covered, thus assuring adequate core cooling. (See Table 8. )
Similar to the pre-TMI-2 analyses, the analyses performed after the accident assumed the use of only safety-grade equipment for accident mitigation, and assumed no mitigating operator actions within ten minutes of the initiating event, except for the two items previously identified (at page 3 abcve) and the manual action of tripping of the reactor coolant pumps following automatic initiation of high pressure injec-tion. l The system behavior which results in the instruction for pump trip involves an extended loss of inventory due to continuous operation of the reactor coolant pumps. While l
continued pump operation provides forced circulation cooling of the core, it also causes more fluid inventory to be discharged out the break than would otherwise occur for certain break sizes. As a result of this increased loss of inventory, the fluid in the Reactor Coolant System will evolve to a high void fraction. If the pumps are tripped after a high void fraction is reached, the available water in the Reactor Coolant System would not be sufficient to keep the core covered. If the core is significantly uncovered, the cladding temperature would begin to increase and the ECCS may not provide, under these conditions, reflooding of the core at a rate which assures that cladding temperatures are maintained within the criteria of 10 CFR 50.46. Since all analyses have confirmed that the plant can be maintained in a safe condition (as defined by 10 CFR 50.46) during a small-break LOCA without the reactor ecolant pumps operating during the transient, provision for prompt tripping of the pumpt upon indication of a LOCA (receipt of a low reactor coolant pressure safety injection signal) assures that adequate core cooling is provided. While other, non-LOCA events may lead to a low pressure safety signal, tripping of the reactor coolant pumps for these events still allows adequate core cooling to be provided. .
BY WITNESS BROUGHTON:
)
The generic analyses performed by B&W are applicable to TMI-1. The low pressure reactor trip setpoint has been raised to 1900 psig and the Engineered Safety Features Actuation l
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System (ESFAS) setpoint has been raised to 1600 psig, the values assumed in the generic analyses. (See TMI-l Restart Report sections 11. 2.11 and 11. 2.12) .
BY WITNESS JONES:
Based upon the analyses described above, B&W has also developed operator guidelines for managing small-break LOCA's.
These guidelines contain two parts: Part I provides the guidelines which define operator actions during a small-break LOCA; Part II provides a description of plant behavior during a small-break LOCA and discusses the effect of the operator actions given in Part I.
BY WITNESS BROUGHTON:
TMI-1 procedures have subsequently been developed to implement these guidelines. The TMI-l Emergency Procedures which implement the B&W Loss of Coolant Accident guidelines place strong emphasis on maintaining reactor coolant system i pressure-temperature relationships to assure that a subcooling condition of at least 50*F exists. Specifically, procedures require that upon automatic initiation of high pressure injection, flow shall not be reduced unless: (1) low pressure injection pumps are in operation and flowing at a rate of not less than one thousand gallons per minute each and the situ-ation has been stable for 20 minutes; or (2) all hot and cold leg temperatures are at least 50*F below the saturation j
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temperature for the existing reactor coolant system pressure and the flow reduction is necessary either to prevent pressurizer level from going off scale high or to avoid excessive reactor vessel pressure /downcomer temperature limits.
If 50*F subcooling cannot be maintained, the procedure requires the high pressure injection system to be reactivated. In situations where high pressure injection is manually initiated, flow reductions are permitted only if reactor coolant system pressure is above 1600 psig and the 50*F subcooling margin exists and can be maintained, or if the criteria for flow reductions following automatic initiation are satisfied.
BY WITNESS JONES:
In summary, extensive small-break analyses have been performed for the TMI-l facility. These analyses demonstrate l
that small LOCA's can be mitigated within the criteria of 10 l CFR 50.46. Also, additional small-break analyses have been performed 1.2 order to develop improved emergency procedures.
Thus, contrary to the contention adequate protection for small LOCA's has been demonstrated and is provided.
References
- 1. Topical Report, BAW-10103A, Rev. 3, "ECCS Analysis of B&W's 177-FA Lowered Loop NSS," July 1977.
- 2. Letter, J. H. Taylor (B&W) to S. A. Varga (NRC), July 18, 1978.
TABLE 1 PRE-TMI-2 LOCA EVALUATIONS Topical Report BAW-10103A, Rev. 3 o Core Flood Tank Line Break o 2 0.5 ft Reactor Coolant Pump Discharge Piping Break o 2 0.04 ft Reactor Coolant Pump Suction Piping Break Letter Report, J. H. Taylor (B&W) to S. A. Varga (NRC), July 18, 1978 o 2 0.15 ft Reactor Coolant Pum'. Discharge Piping Break o 0.10 ft 2 Reactor Coolant Pump Discharge Piping Break o 2 0.085 ft Reactor Coolant Pump Discharge Piping Break o 0.07 ft Reactor Coolant Pump Discharge Piping Break o 2 0.055 ft Reactor Coolant Pump Discharge Piping Break o 2 0.04 ft Reactor Coolant Pump Discharge Piping Break l I TABLE 2 LOSS OF ALL FEEDWATER WITHOUT SMALL-BREAK LOCA Sequence of Events and Assumptions o Loss of main feedwater occurs.
o Direct trip on loss of feedwater fails and reactor trips on high reactor coolant pressure.
o Loss of offsite power occurs coincident with reactor trip.
o Emergency feedwater is not provided to steam generators, o Reactor coolant pressure continues to increase, o Pressurizer PORV does not open. !
o Pressurizer safety valves open. )
o Core decay heat is 1.0 times the ANS standard value.
o Single failure occurs in the High Pressure Injection System.
Summary of Results o Operator action within twenty minutes to initiate emergency feedwater will lower reactor coolant pressure and terminate loss of reactor coolant inventory, assuring adequate core cooling; or o Operator action within twenty minutes to activate high pressure injection provides sufficient reactor coolant inventory to assure adequate core cooling.
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TABLE 3 SMALL-BREAK LOCA WITH LOSS OF ALL FEEDWATER !
Sequence of Events and Assumptions o Small-break LOCA occurs.
o Reactor trip occurs on low reactor coolant pressure.
o Loss of offsite power and loss of main feedwater occur coincident with reactor trip.
o Emergency feedwater is not provided to steam generators.
o Core decay heat is 1.2 times the ANS standard value, o Both high pressurw injection trains function.
Summarv of Results o For break sizes greater than 0.01 ft 2 emergency core i
cooling is automatically initiated anc no operator action is required to assure adequate core cooling.
o For break sizes equal to or less than 0.01 ft2 the setpoint for initiation of high pressure injection is not reached. Operator action within twenty minutes to initiate emergency feedwater (which will subse-quently result in high pressure injection) or to actuate high pressure injection will assure adequate core cooling.
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TABLE 4 LOSS OF MAIN FEEDWATER WITH PORV FAILURE Sequence of Events and Assumptions o Loss of main feedwater occurs.
o Direct trip on loss of feedwater fails and reactor coolant pressure increases.
o Pressurizer PORV opens and does not close.
o Reactor trip occurs on high reactor coolant pressure.
o Emergency feedwater is provided to steam generators.
o Core decay heat is 1.2 times the ANS standard value, o Single failure occurs in the High Pressure Injection System.
Summary of Results.
o Automatic actuation of high pressure injection provides sufficient reactor coolant inventory to assure adequate core cooling.
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l TABLE 5 PORV FAILURES FOLLOWED BY LOSS OF ALL FEECWATER Sequence of Events and Assumptions o Pressurizer PORV fails open and does not close.
l o Reactor trip occurs on low reactor coolant pressure.
o Loss of offsite power and loss of main feedwater occur coincident with reactor trip.
o Emergency feedwater is not provided to steam generators.
o Core decay heat is 1.0 times the ANS standard value.
o Single failure occurs in the High Pressure Injection System.
Summary of Results o Automatic actuation of high pressure iniection provides sufficient reactor coolant inventory to assure adequate core cooling.
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TABLE 6 VERY SMALL LOCA WITH LOSS OF MAIN FEEDWATER Sequence of Events and Assumptions o Very small-break LOCA (0.005 - 0.01 ft2) occurs.
o Reactor trips on low reactor coolant pressure.
o Loss of offsite power and loss of main feedwater occur coincident with reactor trip.
o Emergency feedwater is provided to steam generators.
o Core decay heat is 1.2 times the ANS standard value.
o Single failure occurs in the High Pressure Injection System.
Summary of Results o Natural circulation initially removes core decay heat, then is interrupted as reactor coolant inventory decreases.
o Reactor coolant pressure increases when natural circulation is interrupted, then is stablized by steam condensation in the steam generators.
o Automatic actuation of high pressure injection provides sufficient reacter coolant inventory to assure adequate core cooling.
TABLE 7 SMALL-BREAK LOCA WITH DELAYED REACTOR COOLANT PUMP TRIP Sequence of Events and Assumptions o small-break LOCA between 0.025 f t 2 and 0.2 ft occurs.
o Reactor trips on low reactor coolant pressure.
o Reactor coolant pumps initially continue to operate, then are tripped at a later time during the accident.
o Core decay heat is 1.2 times the ANS standard value.
o Both high pressure injection trains function.
Summary of Results o If the re&ctor coolant pumps continue to operate, adequate core cooling is assured.
o If the reactor coolant pumps trip after a high system void fraction is reached, adequate core cooling has not been demonstrated, o If the reactor coolant pumps are tripped promptly upcn automatic initiation of high pressure injection, adequate core cooling is assured.
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TABLE 8 SMALL-BREAK LOCA WITH LOSS OF ALL FEEDWATLR AND SUBSEQUENT PORV FAILURE Secuence of Events and Assumptions o Very small-break LOCA (0.01 ft2) occurs.
o Reactor trips on low reactor coolant pressure.
o Loss of offsite power and loss of main feedwater occur coincident with reactor trip.
o Emergency feedwater is not provided to steam generators.
o Core decay heat is 1.2 times the ANS standard value.
o Both high pressure injection trains function.
o Reactor Coolant System repressurization results in PORV opening and remaining open.
Summary of Resuyg o Operai i ction within twenty minutes to initiate emergency feedwater (which will subsequently result in high pressure injection) or to actuate high pressure injection provides sufficient reactor coolant inventory to assure adequate core cooling. {
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i T. GARY BROUGHTON 1
- Business Address: GPU Service Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 Education: B.A., Mathematics, Dartmouth College, 1966.
Experience: Control and Safety Analysis Manager, GPU Service Corporation, 1978 to present. Responsible for nuclear safety analysis and integrated thermal, hydraulic and control system j analysis of nuclear and fossil plants.
Supervised on-site technical support groups at Three Mile Island, Unit 2 during the post-accident period.
Safety and Licensing Engineer; Safety and Licensing Manager, GPU Service Corporation, 1976 to 1978. Performed and supervised nuclear licensing, environmental licensing and safety analysis for Oyster Creek, Three Mile Island and Forked River plants.
Served as Technical Secretary to Oyster Creek and Three Mile Island General Office Review Boards.
Officer, U.S'. Navy, 1966 to 1976.
Trained at Naval Nuclear Power School, Prototype and Submarine School.
Positions held include Nuclear Propulsion Plant Watch Supervisor, Instructor at DlG prototype plant and i
Engineering Officer aboard a fast-attack nuclear submarine.
Publications: EPRI CCM-5, RETRAN - A Program for One-Dimensional Transient Thermal-Hy-draulic Analyses of Complex Fluid Flow Systems, Volume 4: Applications, December, 1978, Section 6.1, " Analysis cf Rapid Cooldown Transient - Three Mile Island Unit 2", with N.G.
Trikouros and J. F. Harrison.
_ . , . , _. . . . _ . - - - - - - m- r ----e .r- -- - -- -------r----~
"The Use of RETRAN to Evaluate Alternate Accident Scenarios at ;
TMI-2", with N. G. Trikouros.
Proceedings of the ANS/ ENS Topical Meeting on Thermal Reactor Safety, l April 1980, CONF-800403. :
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"A Real-Time Method for Analyzing Nuclear Power Plant Transients", with l P.S. Walsh. ANS Transactions, Volume 34 TANSAD 34 1-899 (1980).
OUTLINE ADDITIONAL LOCA ANALYSIS EXHIBITS
! The exhibits listed as Items 3 through 13 on Licensee's Certificate of Service, September 15, 1980, are submitted in response to the Board Question regarding UCS Contention 8, and provide a documentary history of the small break LOCA analyses performed by the Babcock & Wilcox Company which are applicable to TMI-1. The results of these analyses are presented in Licensee's Testimony of Robert C. Jones, Jr. , and T. Gary Broughton in response to UCS Contention No. 8 and ECNP Con-tention No. 1(e) (Additional LOCA Analysis) .
Report BAW-10103A, Rev. 3 (Item 3 on Licensee's Certifi-t cate of Service) , and the July 18, 1978 supplemental analysis (Item 4) constitute a complete spectrum of small break analyses which show conformance to the requirements 10 CFR 50.46 and Appendix K to 10 CFR Part 50.
Section 6 of the May 7, 1979 report, " Evaluation of Transient Behavior and Small Reactor Coolant System Breaks in the 177 Fuel Assembly Plant" (Item 5), Supplements 1, 2 and 3 (Items 6, 7 and 8) thereto, and B&W Documents 86-1103585 ';0 (System Response to Total Loss of SG Heat Sink,) (Item 9) and 86-1117679-000 (Small Break with failed PORV) (Item 13) con-sist of additional analyses of plant response to various small break scenarios, which were performed in response to specific NRC requests following the TMI-2 accident. The results of these analyses demonstrate that, with appropriate operator action, the emergency core cooling system is capable of
l controlling the consequences of these scenarios. B&W Document ,
1 69-1106001-00, "Small Break Operating Guidelines" (Item 12),
provides guidance for operator action based upon the results of the small break analyses. l The evaluations contained in the B&W report, " Analysis Summary in Support of an Early RC Pump Trip," (Item 10) and its " Supplemental Small Break Analysis," (Item 11) were per-formed pursuant to NRC IE Bulletin 79-05C. These evaluations demonstrate that, under highly voided reaction coolant condi- l tions, a delayed trip of the reactor coolant pumps will result in unacceptable consequences when Appendix K evaluation techniques are used. The analysis further shows that the prompt reactor coolant pump trip upon receipt of a low pressure ESFAS signal (as required by these results) will provide acceptable LOCA consequences.
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i ROBERT C. JONES, JR. l l
Business Address: Babcock & Wilcox Company Nuclear Power Generation Division 1 P.O. Box 1260 '
Lynchburg, Virginia 24505 Education: B.S., Nuclear Engineering, Pennsylvania State University, 1971. l Post Graduate Courses in Physics, ;
Lynchburg College. ;
1 Experience: '
June 1971-June 1975: Engineer , ECCS Analysis Unit, B&W. Performed both' large and small break ECCS analyses under both the Interim Acceptance l I
Criteria and the present Acceptance Criteria of 10 CFR 50.46 and Appendix K.
June 1975-Present: Acting Supervisory i Engineer and Supervisory Engineer, ECCS Analysis Unit, B&W. Responsible i for calculation of large and small break ECCS evaluations, evaluations of mass and energy releases to the containment during a LOCA, and performance of best estimate pretest predictions of LOCA experiments as part of the NRC Standard Problem Program. Involved in the preparation of operator guidelines for small-break LOCA's and inadequate core cooling mitigation.
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