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| | February 16, 1983 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of ) |
| | ) |
| | METROPOLITAN EDISON COMPANY ) Docket No. 50-289 |
| | ) (Restart) |
| | (Three Mile Island Nuclear ) |
| | Station, Unit No. 1) ) |
| | LICENSEE'S TESTIMONY OF ROBERT C. JONES, JR. AND LOUIS C. LANESE IN RESPONSE TO ALAB-708 ISSUE NO. 2' (USE OF HOT LEG VENTS IN PROMOTING NATURAL CIRCULATION) 8302220362 830216 PDR ADOCK 05000289 T PDR |
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| | (. |
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| | ==SUMMARY== |
| | |
| | This testimony responds to the Appeal Board's request for information concerning the usefulness of the hot leg high point vents in promoting or restoring natural circulation in the event of a small-break loss of coolant accident. |
| | Based upon a review of the size of the hot leg vents to be installed at TMI-1 (and therefore their capability to relieve steam) and of the reactor coolant system response during various small-break scenarios, it is concluded that opening of these vents provides very little benefit during the early stages of a small-break LOCA. The vents would provide some assistance in recovering natural circulation during the refill stage, when the HPI flow has matched the leak flow. While the vents may provide some incremental assistance in recovering-natural circulation at this latter phase, Licensee has deter-mined that this limited benefit does not outweigh the com-plexities associated with determining the conditions under which the vents may be opened. Licensee will instruct the TMI-l operators to utilize the vents under inadequate core cooling conditions. |
| | m e |
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| | INTRODUCTION 1 |
| | This testimony, by Robert C. Jones, Jr., Supervisory 2 |
| | Engineer, Operational Analysis Unit, Babcock & Wilcox Company, 3 |
| | and Louis C. Lanese, Senior Safety Analysis and Plant Control 4 |
| | Engineei, GPU Nuclear Corporation, is in response to Issue No. |
| | 5 2 of the Appeal Board's Memorandum and Order of December 29, 6 |
| | 1982 (ALAB-708), which states: |
| | 7 |
| | : 2. When and under what circumstances such 8 vents would or would not be useful to promote natural circulation, including 9 reasons for the conclusions reached (from the staff). |
| | 10 This testimony will also address the concerns expressed by the 11 Appeal Board at pp. 22-23 and n. 40 of ALAB-708, regarding the 12 procedural guidelines for use of the hot leg high point vents. |
| | 13 y4 BY WITNESS JONES: |
| | 15 High point vents in the hot legs were designed and are 16 being installed in the reactor coolant system (RCS) as a means f r control of non-condensible gases. To assure that a failure 7 |
| | f this vent system does not result in a LOCA, the vents have 8 |
| | g been sized such that the leak flow rate could be compensated by the makeup system. The size of the vents limits their useful-O ness for recovery of natural circulation for a small break LOCA. |
| | 22 Before examining the potential usefulness of the vents for recovery of natural circulation for a small break, I would like to review briefly the several different RCS responses as a 26 |
| | |
| | function of break size. For larger-sized small breaks, greater 1 |
| | than approximately 0.02 ft2, energy removal via the break alone 2 |
| | is sufficient to remove all the core decay heat. For very 3 |
| | small breaks, less than approximately 0.005 ft2, a high 4 |
| | pressure injection (HPI) or make-up (MU) pump provides suffi-5 cient flow to assure that the RCS remains full of liquid. |
| | 6 Therefore, natural circulation will be continually maintained. |
| | 7 What remains is the break size range between 0.005 and 0.02 8 ft2. For this range of small breaks, energy removal from the 9 |
| | system is accomplished by a combination of the break flow and 0 |
| | steam generator (SG) heat removal; natural circulation is not 11 continuously maintained. Opening of the vents could possibly 12 aid in the restoration of natural circulation for these 13 transients, but for the reasons provided below, usefulness of 14 the vents is severely limited. |
| | 15 A brief discussion of the RCS response for this break size 16 range is necessary to understand the potential usefulness of |
| | . 17 high point vents. Within this break size range, the HPI flow 18 is not able to match the inventory being lost through the 19 break, and the RCS will depressurize and evolve to saturated j 20 fluid conditions. Energy removal via the SG will first be by 1 |
| | 21 all-liquid phase natural circulation and then by two-phase 22 natural circulation. Continued energy additions from the core i 23 decay heat will result in boiling within the vessel and 24 subsequent formation of pure steam re:; ions within the primary l |
| | l 25 system. These pure steam regions will interrupt the two-phase 26 l |
| | |
| | natural circulation. System pressurization will then occur due 1 |
| | to the loss of SG heat removal. Once sufficient primary system 2 |
| | inventory has been lost to establish a condensing surface 3 |
| | within the steam generator, boiler-condenser cooling will be 4 established. This will terminate the system pressure increase 5 |
| | and a depressurization of the RCS will commence. Ultimately, 6 |
| | the primary system pressure will settle at a condition where 7 |
| | mass and energy flow added to the system is balanced by mass 8 |
| | and energy flow through the break. |
| | 9 Opening of the high point vents, as a means of recovering 10 natural circulation, has been examined at various points in the 11 sequence of RCS response for the break sizes between 0.005 and 12 0.02 ft2 where the conditions described above will occur. |
| | 13 Obviously, opening of the vents would serve no use so long as 14 liquid single-phase natural circulation is maintained. |
| | 15 Therefore, the earliest situation of interest is during the 16 two-phase natural circulation period of the transient. |
| | 17 Opening of the vents during the two-phase natural circula-18 tion period of the transient could be useful if by doing so the 19 depressurization rate of the primary system was materially 20 increased, thereby aiding HPI injection flow. Opening of the 21 vents when the system is in two-phase natural circulation would 22 provide an additional energy removal path from the RCS and lead 23 to some increase in the depressurization rate. Since the RCS 24 is saturated during this phase of the transient however, liquid 25 in the RCS would flash, retarding the depressurization rate. |
| | 26 |
| | . I 1 |
| | Additionally, because of the staall size of the vent, which is the equivalent of only a .000u5 ft2 break in the RCS, the 2 |
| | addition to the depresr'.rization rate would be small in any 3 |
| | event. Thus, while some additional HPI flow could be obtained 4 |
| | as a result of the depressurization, the incremental effect 5 |
| | would be minimal and not sufficient to cover the large range of 6 |
| | leak flows expected over the break size range of 0.005 to 0.02 7 |
| | ft2. |
| | 8 Opening of the vents after natural circulation is lost 9 |
| | would also not result in a recovery of natural circulation. |
| | 10 The steam flow through the vents (approximately 3 lb/see total) 11 is only 4 percent of tne steam production rate from the core at 12 one-half hour, for example. Thus, unless the combination of 13 the break flow and the HPI were nearly sufficient alone to 14 provide the necessary energy relief (a situation which only 15 occurs for the larger small-break sizes), opening of the vents 16 would not provide sufficient additional energy relief to l 17 prevent pressurization of the system. However, for these 18 breaks, the HPI flow is small relative to the break flow. |
| | 19 Thus, recovery of the system inventory, and thereby natural 20 circulation, would not occur. |
| | 21 Opening of the vents would provide a means of recovering 22 natural circulation only when two conditions are met. First, 23 the HPI flow has matched the leak flow; and second, the energy 24 flow through the leak is sufficient to remove essentially all 25 of the energy being added to the system. The vent path would i |
| | 26 result in additional energy removal with a subsequent decrease 1 |
| | in RCS pressure and increased HPI flow. Since the HPI flow 2 |
| | rate would then be greater than the leak flow, RCS refill would 3 |
| | commence. Refill timcs for this mode of recovery could be 4 |
| | expected to be on the order of one to two hours, assuming core 5 |
| | boiling is suppressed by the incoming HPI. |
| | 6 In summary, opening of hot leg high point vents would 7 |
| | provide virtually no benefit for recovering natural circulation 8 during the early phases of a small break LOCA. |
| | Thus, the vents 9 |
| | are not capable of replacing the role of the steam generators 10 for small-break LOCAs. In the long term, however, the vents 11 could provide a means of recovering the system inventory and 12 thereby reestablish natural circulation. |
| | 13 g BY WITNESS LANESE: |
| | 15 The hot leg high point vents will be used during situ- |
| | , ations of inadequate core cooling. Guidelines have been 16 developed and included in the abnormal transient operating 17 l guidelines (ATOG) program and are undergoing review by the NRC j 18 l Staff. |
| | 19 Proposed guidelines for utilizing the hot leg high point 20 were first submitted by the B&W Owners Group for NRC Staff review in mid-1981. These guidelines addressed two conditions for opening the hot leg vents: (1) during inadequate core cooling conditions, and (2) during the refill phase of a small-break LOCA. However, the vent guidelines for use during 26 the refill phase a small break LOCA have been withdrawn by the 1 |
| | B&W owners from NRC Staff consideration. This was done after 2 |
| | the initial submission of the guidelines because the owners and 3 |
| | NRC Staff agreed that certain questions raised about the 4 |
| | guidelines could not be resolved without an extensive testing 5 |
| | and analytical effort to demonstrate to the NRC Staff that use 6 |
| | of the vents under certain conditions woul not be detrimental 7 |
| | to plant safety. Since the use of the vents during the refill 8 |
| | phase was considered to be of marginal benefit, the owners 9 |
| | decided to withdraw the refill guidelines in April of 1982. |
| | 10 GPU Nuclear made a plant-specific notification of this decision 11 by letter to the Staff dated August 23, 1982. |
| | 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 I |
| | ROBERT C. JONES, JR. |
| | Business Address: Babcock & Wilcox Company Nuclear Power Generation Division Post Office Box 1260 Lynchburg, Virginia 24505 Education: B.S., Nuclear Engine'ering, Pennsylvania State University, 1971. Post Graduate Courses in Physics, Lynchburg College. |
| | Experience: July 1982 to present: Supervisory Engineer, Operational Analysis Unit, B&W. Responsible for the performance of plant transient analyses and analyses used in the development of operator guidelines. During this period, has continued as Project Engineer for B&W analyses performed in response to NUREG-0737 Item II.K.3.30. |
| | June 1975 to July 1982: Acting Supervisory Engineer and Supervisory Engineer, ECCS Analysis Unit, B&W. Responsible 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 pre-paration of operator guidelines for small-break LOCA's and inadequate core cooling mitigation. |
| | June 1971 to June 1975: Engineer, ECCS Analysis Unit, B&W. Performed both large and small break ECCS analyses under both the Interim Acceptance Criteria and the present Acceptance Criteria of 10 CFR 50.46 and Appendix K. |
| | k |
| | -,-w -- - . --,-,-e ,- - ,---.v-r , - , ~ , - - - - - , , , , . s - - - - + , , --,--1 |
| | |
| | e LOUIS C. LANESE Business Address: GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 Education: B.S., Engineering Science, Newark College of Engineering, 1970, M.E., Nuclear Engineering, New York University, 1972. Nuclear Engineering courses, Polytechnic Institute of New York, 1975 to 1980. Com-pleted course work for Degree of Engineer. |
| | Experience: Senior Safety Analysis and Plant Control Engineer, GFU Nuclear Corporation, 1979 to present. Kesponsi-bilities include the performance of the TMI-1 Restart Safety Analysis; TMI-l Emergency Feedwater design, design review of TMI-l restart and long-term modifications. Member of TMI-2 Generation Review Committee (GRC), 1979 through June 1982. |
| | Member of TMT-1 GRC, 1979 to present. |
| | Chairman of the Babcock & Wilcox Owners Group Analysis Subcommittee from May 1981 to July 1982. |
| | Currently a member of the Analysis Subcommittee. |
| | Member of the GPUNC inhouse committee responsible for implementing the Abnormal Transient Operating |
| | ! Guidelines (ATOG) at TMI-1. Currently working on |
| | ! improvement of steam generator tube rupture emer-gency procedures,' including analyses of tube rupture events using the RETRAN computer code. Working with EPRI in benchmarking RETRAN with RELAP 5 for tube rupture events. Independent safety reviewer for emergency procedures from August 1982 to present. |
| | f Control and Safety Analysis Engineer, GPU Service |
| | ! Corporation, 1978 to 1979. Responsibilities |
| | ! included the performance of containment analyses in support of plant operation; developing analyses in support of the TMI-2 feedwater system modifica-tion; preparation of the TMI-l restart safety analysis. |
| | Lead Nuclear Licensing Engineer, GPU Service Corporation, 1977 to 1978. Primary responsibility for TMI-2 licensing activities and for licensing matters involving generic safety issues affecting all GPU system plants. |
| | l |
| | |
| | LOUIS'C. LANESE Page Two - |
| | Safety and Licensing Engineer, GPU Service Corporation, 1974 to 1977. Responsibilities included technical resolution of TMI-2 licensing open items; conformance of Forked River systems. |
| | design to licensing criteria; and, safety review of Oyster Creek radwaste facility. |
| | Assistant Safety and Licensing Engineer, Ebasco Services, Inc., Performed licensing and safety review of St. Lucie Units 1 and 2 Safety Analysis Report pertaining to instrumentation and power systems; cooling water and HVAC systems, radwaste systems; and, accident analysis. Performed dose analyses and developed secondary system source terms. |
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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
r l ,
February 16, 1983 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of )
)
METROPOLITAN EDISON COMPANY ) Docket No. 50-289
) (Restart)
(Three Mile Island Nuclear )
Station, Unit No. 1) )
LICENSEE'S TESTIMONY OF ROBERT C. JONES, JR. AND LOUIS C. LANESE IN RESPONSE TO ALAB-708 ISSUE NO. 2' (USE OF HOT LEG VENTS IN PROMOTING NATURAL CIRCULATION) 8302220362 830216 PDR ADOCK 05000289 T PDR
(.
SUMMARY
This testimony responds to the Appeal Board's request for information concerning the usefulness of the hot leg high point vents in promoting or restoring natural circulation in the event of a small-break loss of coolant accident.
Based upon a review of the size of the hot leg vents to be installed at TMI-1 (and therefore their capability to relieve steam) and of the reactor coolant system response during various small-break scenarios, it is concluded that opening of these vents provides very little benefit during the early stages of a small-break LOCA. The vents would provide some assistance in recovering natural circulation during the refill stage, when the HPI flow has matched the leak flow. While the vents may provide some incremental assistance in recovering-natural circulation at this latter phase, Licensee has deter-mined that this limited benefit does not outweigh the com-plexities associated with determining the conditions under which the vents may be opened. Licensee will instruct the TMI-l operators to utilize the vents under inadequate core cooling conditions.
m e
INTRODUCTION 1
This testimony, by Robert C. Jones, Jr., Supervisory 2
Engineer, Operational Analysis Unit, Babcock & Wilcox Company, 3
and Louis C. Lanese, Senior Safety Analysis and Plant Control 4
Engineei, GPU Nuclear Corporation, is in response to Issue No.
5 2 of the Appeal Board's Memorandum and Order of December 29, 6
1982 (ALAB-708), which states:
7
- 2. When and under what circumstances such 8 vents would or would not be useful to promote natural circulation, including 9 reasons for the conclusions reached (from the staff).
10 This testimony will also address the concerns expressed by the 11 Appeal Board at pp. 22-23 and n. 40 of ALAB-708, regarding the 12 procedural guidelines for use of the hot leg high point vents.
13 y4 BY WITNESS JONES:
15 High point vents in the hot legs were designed and are 16 being installed in the reactor coolant system (RCS) as a means f r control of non-condensible gases. To assure that a failure 7
f this vent system does not result in a LOCA, the vents have 8
g been sized such that the leak flow rate could be compensated by the makeup system. The size of the vents limits their useful-O ness for recovery of natural circulation for a small break LOCA.
22 Before examining the potential usefulness of the vents for recovery of natural circulation for a small break, I would like to review briefly the several different RCS responses as a 26
function of break size. For larger-sized small breaks, greater 1
than approximately 0.02 ft2, energy removal via the break alone 2
is sufficient to remove all the core decay heat. For very 3
small breaks, less than approximately 0.005 ft2, a high 4
pressure injection (HPI) or make-up (MU) pump provides suffi-5 cient flow to assure that the RCS remains full of liquid.
6 Therefore, natural circulation will be continually maintained.
7 What remains is the break size range between 0.005 and 0.02 8 ft2. For this range of small breaks, energy removal from the 9
system is accomplished by a combination of the break flow and 0
steam generator (SG) heat removal; natural circulation is not 11 continuously maintained. Opening of the vents could possibly 12 aid in the restoration of natural circulation for these 13 transients, but for the reasons provided below, usefulness of 14 the vents is severely limited.
15 A brief discussion of the RCS response for this break size 16 range is necessary to understand the potential usefulness of
. 17 high point vents. Within this break size range, the HPI flow 18 is not able to match the inventory being lost through the 19 break, and the RCS will depressurize and evolve to saturated j 20 fluid conditions. Energy removal via the SG will first be by 1
21 all-liquid phase natural circulation and then by two-phase 22 natural circulation. Continued energy additions from the core i 23 decay heat will result in boiling within the vessel and 24 subsequent formation of pure steam re:; ions within the primary l
l 25 system. These pure steam regions will interrupt the two-phase 26 l
natural circulation. System pressurization will then occur due 1
to the loss of SG heat removal. Once sufficient primary system 2
inventory has been lost to establish a condensing surface 3
within the steam generator, boiler-condenser cooling will be 4 established. This will terminate the system pressure increase 5
and a depressurization of the RCS will commence. Ultimately, 6
the primary system pressure will settle at a condition where 7
mass and energy flow added to the system is balanced by mass 8
and energy flow through the break.
9 Opening of the high point vents, as a means of recovering 10 natural circulation, has been examined at various points in the 11 sequence of RCS response for the break sizes between 0.005 and 12 0.02 ft2 where the conditions described above will occur.
13 Obviously, opening of the vents would serve no use so long as 14 liquid single-phase natural circulation is maintained.
15 Therefore, the earliest situation of interest is during the 16 two-phase natural circulation period of the transient.
17 Opening of the vents during the two-phase natural circula-18 tion period of the transient could be useful if by doing so the 19 depressurization rate of the primary system was materially 20 increased, thereby aiding HPI injection flow. Opening of the 21 vents when the system is in two-phase natural circulation would 22 provide an additional energy removal path from the RCS and lead 23 to some increase in the depressurization rate. Since the RCS 24 is saturated during this phase of the transient however, liquid 25 in the RCS would flash, retarding the depressurization rate.
26
. I 1
Additionally, because of the staall size of the vent, which is the equivalent of only a .000u5 ft2 break in the RCS, the 2
addition to the depresr'.rization rate would be small in any 3
event. Thus, while some additional HPI flow could be obtained 4
as a result of the depressurization, the incremental effect 5
would be minimal and not sufficient to cover the large range of 6
leak flows expected over the break size range of 0.005 to 0.02 7
ft2.
8 Opening of the vents after natural circulation is lost 9
would also not result in a recovery of natural circulation.
10 The steam flow through the vents (approximately 3 lb/see total) 11 is only 4 percent of tne steam production rate from the core at 12 one-half hour, for example. Thus, unless the combination of 13 the break flow and the HPI were nearly sufficient alone to 14 provide the necessary energy relief (a situation which only 15 occurs for the larger small-break sizes), opening of the vents 16 would not provide sufficient additional energy relief to l 17 prevent pressurization of the system. However, for these 18 breaks, the HPI flow is small relative to the break flow.
19 Thus, recovery of the system inventory, and thereby natural 20 circulation, would not occur.
21 Opening of the vents would provide a means of recovering 22 natural circulation only when two conditions are met. First, 23 the HPI flow has matched the leak flow; and second, the energy 24 flow through the leak is sufficient to remove essentially all 25 of the energy being added to the system. The vent path would i
26 result in additional energy removal with a subsequent decrease 1
in RCS pressure and increased HPI flow. Since the HPI flow 2
rate would then be greater than the leak flow, RCS refill would 3
commence. Refill timcs for this mode of recovery could be 4
expected to be on the order of one to two hours, assuming core 5
boiling is suppressed by the incoming HPI.
6 In summary, opening of hot leg high point vents would 7
provide virtually no benefit for recovering natural circulation 8 during the early phases of a small break LOCA.
Thus, the vents 9
are not capable of replacing the role of the steam generators 10 for small-break LOCAs. In the long term, however, the vents 11 could provide a means of recovering the system inventory and 12 thereby reestablish natural circulation.
13 g BY WITNESS LANESE:
15 The hot leg high point vents will be used during situ-
, ations of inadequate core cooling. Guidelines have been 16 developed and included in the abnormal transient operating 17 l guidelines (ATOG) program and are undergoing review by the NRC j 18 l Staff.
19 Proposed guidelines for utilizing the hot leg high point 20 were first submitted by the B&W Owners Group for NRC Staff review in mid-1981. These guidelines addressed two conditions for opening the hot leg vents: (1) during inadequate core cooling conditions, and (2) during the refill phase of a small-break LOCA. However, the vent guidelines for use during 26 the refill phase a small break LOCA have been withdrawn by the 1
B&W owners from NRC Staff consideration. This was done after 2
the initial submission of the guidelines because the owners and 3
NRC Staff agreed that certain questions raised about the 4
guidelines could not be resolved without an extensive testing 5
and analytical effort to demonstrate to the NRC Staff that use 6
of the vents under certain conditions woul not be detrimental 7
to plant safety. Since the use of the vents during the refill 8
phase was considered to be of marginal benefit, the owners 9
decided to withdraw the refill guidelines in April of 1982.
10 GPU Nuclear made a plant-specific notification of this decision 11 by letter to the Staff dated August 23, 1982.
12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 I
ROBERT C. JONES, JR.
Business Address: Babcock & Wilcox Company Nuclear Power Generation Division Post Office Box 1260 Lynchburg, Virginia 24505 Education: B.S., Nuclear Engine'ering, Pennsylvania State University, 1971. Post Graduate Courses in Physics, Lynchburg College.
Experience: July 1982 to present: Supervisory Engineer, Operational Analysis Unit, B&W. Responsible for the performance of plant transient analyses and analyses used in the development of operator guidelines. During this period, has continued as Project Engineer for B&W analyses performed in response to NUREG-0737 Item II.K.3.30.
June 1975 to July 1982: Acting Supervisory Engineer and Supervisory Engineer, ECCS Analysis Unit, B&W. Responsible 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 pre-paration of operator guidelines for small-break LOCA's and inadequate core cooling mitigation.
June 1971 to June 1975: Engineer, ECCS Analysis Unit, B&W. Performed both large and small break ECCS analyses under both the Interim Acceptance Criteria and the present Acceptance Criteria of 10 CFR 50.46 and Appendix K.
k
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e LOUIS C. LANESE Business Address: GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 Education: B.S., Engineering Science, Newark College of Engineering, 1970, M.E., Nuclear Engineering, New York University, 1972. Nuclear Engineering courses, Polytechnic Institute of New York, 1975 to 1980. Com-pleted course work for Degree of Engineer.
Experience: Senior Safety Analysis and Plant Control Engineer, GFU Nuclear Corporation, 1979 to present. Kesponsi-bilities include the performance of the TMI-1 Restart Safety Analysis; TMI-l Emergency Feedwater design, design review of TMI-l restart and long-term modifications. Member of TMI-2 Generation Review Committee (GRC), 1979 through June 1982.
Member of TMT-1 GRC, 1979 to present.
Chairman of the Babcock & Wilcox Owners Group Analysis Subcommittee from May 1981 to July 1982.
Currently a member of the Analysis Subcommittee.
Member of the GPUNC inhouse committee responsible for implementing the Abnormal Transient Operating
! Guidelines (ATOG) at TMI-1. Currently working on
! improvement of steam generator tube rupture emer-gency procedures,' including analyses of tube rupture events using the RETRAN computer code. Working with EPRI in benchmarking RETRAN with RELAP 5 for tube rupture events. Independent safety reviewer for emergency procedures from August 1982 to present.
f Control and Safety Analysis Engineer, GPU Service
! Corporation, 1978 to 1979. Responsibilities
! included the performance of containment analyses in support of plant operation; developing analyses in support of the TMI-2 feedwater system modifica-tion; preparation of the TMI-l restart safety analysis.
Lead Nuclear Licensing Engineer, GPU Service Corporation, 1977 to 1978. Primary responsibility for TMI-2 licensing activities and for licensing matters involving generic safety issues affecting all GPU system plants.
l
LOUIS'C. LANESE Page Two -
Safety and Licensing Engineer, GPU Service Corporation, 1974 to 1977. Responsibilities included technical resolution of TMI-2 licensing open items; conformance of Forked River systems.
design to licensing criteria; and, safety review of Oyster Creek radwaste facility.
Assistant Safety and Licensing Engineer, Ebasco Services, Inc., Performed licensing and safety review of St. Lucie Units 1 and 2 Safety Analysis Report pertaining to instrumentation and power systems; cooling water and HVAC systems, radwaste systems; and, accident analysis. Performed dose analyses and developed secondary system source terms.
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