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Category:AFFIDAVITS
MONTHYEARML20054E1401982-04-21021 April 1982 Affidavit of RA Dieterich Answering Questions in Aslab 820415 Memorandum & Order.Missing Thermal Sleeve Could Impact & Damage in-core Instrument Guide Tubes or Other Components in Reactor Vessel Lower Head Region ML20054D8271982-04-21021 April 1982 Affidavit of Jf Stolz in Response to Aslab 820415 Memorandum & Order Requesting Info Re Plans for Repairs & Future Operation of Plant Following Discovery of Missing Thermal Sleeve from Cracked Makeup Nozzle ML20054D8581982-04-16016 April 1982 Affidavit of ML Padovan Supplementing 820331 Testimony Re Aslab Questions 2 & 3.Discusses Verification of Results of Inservice Insp Record Findings & Clarification Re Thermal Cycle ML20040F8701982-02-0505 February 1982 Affidavit of Wl Jensen Supplementing 811214 Affidavit. Explains Basis for NRC Conclusion Re Min Time Available for Operator Action After Break in Reactor Coolant Pump Suction Piping Vs Break in Discharge Piping ML20126A8371980-02-0404 February 1980 Affidavit by CA Energy Commission Re Issue 5-2.Attests That Implementation of Controlled Filtered Venting at Facility Is Feasible Since Equipment Is Commercially Available ML19257D2251980-01-23023 January 1980 Affidavit Attesting That Allegation Re Inadequacy of Pressurizer Tank & Quench Tank Sizes Is Unfounded.Statement of Qualifications & Certificate of Svc Encl ML19257D2201980-01-22022 January 1980 Affidavit Attesting That,Contrary to G Hursh & R Castro Allegations,Licensee Reactor Trip Circuitry Is Fully Operational Per NRC 790627 Safety Evaluation.Prof Qualifications Encl ML19257D2211980-01-22022 January 1980 Affidavit Attesting That Contrary to G Hursh & R Castro Allegations,Licensee Developed & Implemented Operating Procedures for Emergency Feedwater Sys Independent of Integrated Sys.Prof Qualifications Encl ML19257D5841980-01-22022 January 1980 Affidavit Attesting That NUREG-0585 Rept Cited as Basis for CA Energy Commission Contention 5-2 Re Controlled Filtered Venting Sys Constitutes Future Option & Is Not Technically or Commercially Available.Certificate of Svc Encl ML19249D6311979-07-15015 July 1979 Affidavit Declaring Intention to Participate in All Hearings of Proceeding ML19309A1801978-05-23023 May 1978 Affidavit Re Allegations That Erroneous Calculations & Drawings Used to Const Spent Fuel Storage Bldg.Erroneous Calculations & Drawings Not Used.Change in Cooling Tower Design Criteria Not Justified ML19309A1771978-05-22022 May 1978 Affidavit Re Allegations That Erroneous Calculations & Drawings Used to Const Spent Fuel Storage Bldg.Erroneous Calculations & Drawings Not Used.Change in Cooling Tower Design Spectra Not Justified ML19309A1721978-05-16016 May 1978 Affidavit Re Allegations That Erroneous Calculations & Drawings Used to Const Spent Fuel Storage Bldg.Erroneous Calculations & Drawing Not Used.Change in Cooling Tower Design Spectra Not Justified 1982-04-21
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20149E4541994-05-13013 May 1994 Licensee First Set of Interrogatories & Request for Production of Documents to Eco.* W/Certificate of Svc. Related Correspondence ML20058P3701993-12-16016 December 1993 Memorandum & Order (Telcon 931209).* Smud Unopposed Motion Granted.W/Certificate of Svc.Served on 931217 ML20058P4161993-12-15015 December 1993 Licensee Petition for Review of Second Prehearing Conference Order & Motion for Directed Certification.* Advises That Commission Accept Review & Grant Directed Certification of Board Rulings.W/Certificate of Svc ML20058E0471993-11-30030 November 1993 Second Prehearing Conference Order (Proposed Contentions; Summary Disposition).* Environmental & Resources Conservation Organization Bases 1,5,11,13,2 & 14 Accepted for Litigation.W/Certificate of Svc.Served on 931201 ML20058E0361993-11-30030 November 1993 Transcript Corrections (Second Prehearing conference,930921- 22).* Board Adopts Listed Corrections.W/Certificate of Svc. Served on 931201 ML20058D6481993-11-19019 November 1993 Exemption from Requirements of 10CFR140.11(a)(4) to Extent That Primary Financial Protection in Stated Amount Shall Be Maintained ML20058E0151993-11-14014 November 1993 Comment Opposing Proposed Rule 10CFR50 Re Exemptions in Accident Insurance for Nuclear Power Plants Prematurely Shut Down ML20057G2181993-10-14014 October 1993 Proposed Transcript Corrections.* Submits Listed Transcript Corrections for 930921 & 22 Prehearing Conference. W/Certificate of Svc ML20058M8951993-10-0505 October 1993 Order (Proposed Transcript Corrections).* Util Submitted Proposed Transcript Corrections for 930921-22 Prehearing Conference.Other Parties May Submit Proposed Corrections by 931015.W/Certificate of Svc.Served on 931005 ML20058M8581993-10-0101 October 1993 Licensee Motion to Correct Transcript of Prehearing Conference.* Requests That Licensing Board Direct Correction of Prehearing Conference Trancript in Manner Described Above.Certification of Svc& Svc List Encl ML20057D1021993-09-27027 September 1993 Eco Answer in Opposition to Smud Motion for Summary Disposition of Eco Original Loop Contention.* Urges Board Either to Deny Motion or to Defer Consideration of Smud Motion to Conclusion of Proceeding.W/Certificate of Svc ML20057D0861993-09-27027 September 1993 NRC Staff Response in Support of Licensee Motion for Summary Disposition of Eco Original Loop Contention.* Summary Disposition Should Be Granted.Certificate of Svc Encl ML20057D1891993-09-27027 September 1993 Exemption from Training rule,10CFR50.120 Requirements to Establish,Implement & Maintain Training Program,Using Sys Approach to Training,For Categories of Personnel Listed in 10CFR50.120.Exemption Effective 931122 ML20057D1351993-09-27027 September 1993 Eco Concise Statement of Material Facts as to Which There Exists Genuine Issue to Be Heard.* Eco Original LOOP Contention Continues to Present Justifiable & Matl Issues Requiring Denial of Smud Motion.Certificate of Svc Encl ML20057D0451993-09-24024 September 1993 Notice of Hearing.* Notifies That Hearing Will Be Conducted in Matter of Proposed Decommissioning of Plant.W/Certificate of Svc.Served on 930924 ML20057D0441993-09-23023 September 1993 Notice of Appearance.* Notice Given That Undersigned Attorney Enters Appearance in Listed Matter & Listed Info Provided.W/Certificate of Svc ML20057C0851993-09-22022 September 1993 Transcript of 930922 Hearing in Bethesda,Md Re Facility.Pp 387-579 ML20057B9611993-09-21021 September 1993 Transcript of 930921 Hearing in Bethesda,Md.Pp 181-386 ML20057B0091993-09-10010 September 1993 Memorandum & Order CLI-93-19.* Informs That Further Questions of Board Re Effect of Commission Holding in Issues Concerning CLI-93-3 & CLI-93-12 Should Be Certified to NRC, Per 10CFR2.718(i).W/Certificate of Svc.Served on 930910 ML20057B0101993-09-0707 September 1993 Licensee Statement of Matl Facts as to Which There Is No Genuine Issue to Be Heard (Environ & Resources Conservation Organization Original Loop Contention).* Advises That Contention No Longer Matl Issue.W/Certificate of Svc ML20057B0051993-09-0707 September 1993 Licensee Motion for Summary Disposition of Environ & Resources Conservation Organization Original Loop Contention.* Advises That Contention Presents No Genuine Issue of Matl Fact to Be Heard & Should Be Dismissed ML20057A1721993-08-31031 August 1993 Notice of Prehearing Conference.* Notifies of 930921 Prehearing Conference in Bethesda,Md to Discuss Proposed Decommissioning of Plant.W/Certificate of Svc.Served on 930901 ML20046C5241993-08-0202 August 1993 NRC Staff Response to Eco Contentions on Staff Ea,Finding of No Significant Impact & Se.* W/Certificate of Svc & Notice of Appearance ML20045G9611993-07-12012 July 1993 Environ & Resources Conservation Organization Contentions on Staff Environ Assessment Findings of No Significant Impact & Safety Evaluation.* Urges ASLB to Admit Foregoing Contention Per 10CFR2.714(b)(2).W/Certificate of Svc ML20044F8041993-05-26026 May 1993 Memorandum & Order CLI-93-12.* Util Motion for Reconsideration of CLI-93-03 Denied.W/Certificate of Svc. Served on 930526 ML20045D1871993-05-10010 May 1993 Erratum.* Informs That Correct Ref for Footnote 34 on Page 22 of Commission Memoranudm & order,CLI-93-03,dtd 930303 Is 57 Fed Reg 20,718 (920514).W/Certificate of Svc.Served on 930610 ML20035G3321993-04-21021 April 1993 NRC Staff Response to Eco Contention Re Loss of Offsite Power.* Advises That Eco Contention & Bases Must Be Rejected in Entirety.W/Certificate of Svc ML20035F5841993-04-13013 April 1993 Licensee Response to Eco Proposed Loop Contentions.* Util Opposes Eco Proposed Contentions on LOOP Because Contentions Vague & Confusing & Lack Factual & Legal Bases.W/Certificate of Svc & Svc List ML20035E0031993-04-12012 April 1993 NRC Staff Response to Eco Contentions Re Funding of Decommissioning.* All Bases Eco Decommissioning Funding Contention & Contention Should Be Rejected.W/Certificate of Svc ML20035B5391993-03-26026 March 1993 NRC Staff Support of Licensee Motion for Reconsideration.* Decommissioning Funding Plan Cannot Be Deemed Adequate Until Listed Issues Resolved.W/Certificate of Svc ML20035B5711993-03-26026 March 1993 Environ & Resources Conservation Organization Answer in Opposition to Licensee Motion for Reconsideration.* W/Certificate of Svc ML20035B5441993-03-22022 March 1993 Environ & Resources Conservation Organization Contention on Licensee Proposed Decommissioning Funding Plan.* Environ & Resources Conservation Organization Contends That Licensee Decommissioning Plan Inadequate.W/Certificate of Svc ML20034H8441993-03-12012 March 1993 NRC Staff Opposition to Environ & Resources Conservation Organization Petition for Reconsideration.* Staff Opposes Petition W/Respect to Reconsideration of Paragraph 2.W/ Certificate of Svc ML20034H7991993-03-12012 March 1993 Order.* Orders That Any Response to Smud Petition,From Either NRC or Environ & Resources Conservation Organization, Shall Be Filed by 930326.W/Certificate of Svc.Served on 930312 ML20034H8661993-03-10010 March 1993 Licensee Motion for Reconsideration.* Licensee Requests Commission Reconsider Grant of Discretionary Intervention to Environmental & Resources Conservation Organization. W/Certificate of Svc ML20034G7151993-03-0909 March 1993 Licensee Response to Eco Petition for Reconsideration.* Eco 930305 Petition Should Be Denied in Toto.Certificate of Svc Encl ML20034G6841993-03-0505 March 1993 Environmental & Resources Conservation Organization Petition for Reconsideration.* Urges Commission to Reconsider & Amend 930303 Decommissioning Order.W/Certificate of Svc ML20128D4951993-01-28028 January 1993 Notice of Appointment of Adjudicatory Employee.* W/Certificate of Svc.Served on 930129 ML20127D5091992-09-11011 September 1992 Environ & Resources Conservation Organization Brief in Support of Appeal from LBP-92-23.* Certificate of Svc Encl ML20127D4711992-09-0808 September 1992 Notice of Appeal.* Gives Notice of Appeal from Order of Board (Served 910821),denying Environ & Resources Conservation Organization Petition for Intervention & Request for Hearings & Termination of Proceedings ML20141M5981992-08-20020 August 1992 Prehearing Conference Order (Terminating Proceeding).* Petition for Leave to Intervene & Request for Prior Hearing of Petitioner, ,denied & Proceeding Terminated. W/Certificate of Svc.Served on 920821 ML20141M5881992-08-17017 August 1992 NRC Staff Response in Support of Licensee Motions to Strike Improper Argument in Environmental & Resources Conservation Organization (Eco) Filings.* Further Argument by Eco Unauthorized.Certificate of Svc Encl ML20029B5991991-03-0404 March 1991 Environ Conservation Organization Reply to 910215 Order.* ASLB Should Limit Any Rulings Based on Current State of Record to Rulings Which Presume That Petitioner & Members Have Standing Under Atomic Energy Act.W/Certificate of Svc ML20029B6701991-02-22022 February 1991 Exemption from 10CFR50-54(q) Requirements Re Offsite Emergency Preparedness That Provides Reactor Shutdown & Changes Long Term Defueled Condition ML20024F8321990-12-0505 December 1990 NRC Staff Response in Opposition to Petition to Intervene Filed by Environmental Conservation Organization on Proposed License Amend.Petition Should Be Denied Based on Listed Reasons.W/Certificate of Svc ML20024F8311990-11-30030 November 1990 Licensee Answer to Environ Conservation Organization Petition.* Organization Seeks to Litigate Issues That Are Beyond NRC Jurisdiction & Scope of Proposed License Amend. Petition Should Be Denied.W/Certificate of Svc ML20024F8301990-11-26026 November 1990 Order.* Motion for Extension of Time for 1 Wk to Respond to Environ Conservation Organization Petition for Leave to Intervene & Request for Hearing,Granted.Util Response Due on 901130.W/Certificate of Svc.Served on 901127 ML20024F9081990-11-16016 November 1990 Licensee Motion for Extension of Time.* Extension of Time of 1 Wk Beyond 901123 Deadline Requested,Based on Length of Petition/Request & Intervening Two Holidays.W/Certificate of Svc ML20024F9051990-11-0808 November 1990 Environ Conservation Organization Comment on Proposed NSHC & Petition for Leave to Intervene & Request for Prior Hearing.* Other Remedies Sought Should Be Granted.Notice of Appearance & Certificate of Svc Encl ML20058G9051990-10-23023 October 1990 Comment on Fr Notice Page 41280 to 41282 Re Smud Possession Only License Amend.Believes Termination of Plant OL Prior to End of Authorized Operating Term Will Have Significant Impact on Environ Sources Needed to Generate Power 1994-05-13
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of SACRAMENTO MUNICIPAL UTILITY DISTRCT
)
Docket No. 50-312 (SP)
)
(Rancho Seco Nuclear Generating Station))
AFFIDAVIT OF WALTON L. JENSEN, JR.
I, Walton L. Jensen, Jr., being duly sworn, depose and state that:
1.
I am an employee of the U.S. Nuclear Regulatory Commission (NRC).
My present position is Senior Nuclear Engineer, Reactor Systems Branch, Division of Systems Integration within the Office of Nuclear Reactor Regulation. A copy of my professional qualifications is attached.
2.
The purpose of this affidavit is to supplement the information provided in my affidavit filed in this proceeding on November 24, 1981.
The information in this supplementary a'fidavit is provided to explain in more detail the basis for the Staff's conclusion that the minimum time available for operator action after a break in the reactor coolant pump suction piping would not be signficantly different from that available for operator action after a break in the reactor coolant pump-discharge piping.
3.
The NRC Staff has reviewed the information contained in the letter from Babcock and Wilcox to Sacramento Municipal Utility District on " Reactor Coolant Pump Suction break LOCA" dated Ma~rch 25, 1981, which 8202100404 820208 DRADOCKOSOOO3g2
i ndicated that more reactor coolant system water might be lost for sinall breaks at the reactor coolant pump suction than for breaks at the reactor coolant pump discharge in the event that all feedwater were temporarily lost. We conclude that this informatio is not significant with regard to the safe operation of Rancho Seco and that additional small break LOCA analyses at the reactor coolant pump suction need not be performed. This conclusion was derived from the following considerations:
a.
Regardless of the postulated break location in the cold leg piping, the reactor vessel water level would initially decrease to the same approximate elevation.
b.
The additional loss of primary system inventory during a break.in the pump suction piping would be from water in the cold leg piping.
c.
In the absence of Emergency Feedwater the operator has a minimum of 20 minutes to actuate High Pressure Injection (HPI) regardless of break location in the cold leg piping, d.
Emergency procedures instruct the operator to actuate HPI immedi$tely regardless of break location if a loss of all feedwater has occurred.
The discussion below addresses these areas:
In the event of a small break LOCA at Rancho Seco, the liquid level in the broken pipe would decrease to the elevation of the break by liquid discharge from the break. The break flow would then be steam which would
' be generated in the core by decay heat. The High Pressure Injection system at Rancho Seco has sufficient capability to replenish the water boiled in the core by the decay heat.
For breaks in the cold leg piping
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at the reactor coolant pump suction water would be lost from the reactor vessel to the break until the liquid level dropped to the reactor vessel inlet nozzle elevation. At this point only steam would be lost from the reactor vessel.
Liquid discharge would continue from the break until the break was uncovered. More water would be lost for a break in the reactor coolant pump suction piping than for a break in the discharge piping since the cold leg suction piping is located at a lower elevation than the cold leg discharge piping. The additional coolant loss, however, would be limited to the cold leg piping inventory below the reactor vessel inlet nozzle. The water loss from the reactor vessel which provides core cooling is limited by the elevation of the reactor vessel inlet nozzle so that loss of vessel water would be approximately the same regardless of the break location in the cold leg.
Following the event at TMI-2, B&W performed small break LOCA analyses beyond those which had been presented to the Staff as a licensing basis to show conpliance with 10 C.F.R. 5 50.46. These
- additional analyses were performed for the purpose of providing guidance to the operator and are documented in the B&W report titled " Evaluation of Transient Behavior and Small Reactor Coolant System Breaks in the 177-FA Plant" dated May 7, 1979.
These analyses demonstrated that Emergency feedwater would be 2
required for breaks of 0.01 ft and smaller in the reactor coolant pump discharge piping to depressurize the reactor system sufficiently to actuate High P'ressure Injection.
It was further demonstrated that operator action within 20 minutes to manually actuate HPI would prevent core uncovery.
Operators at Rancho Seco are instructed to initiate HPI w
immediately in the event that all feedwater is lost in loss of feedwater e
procedures and to monitor auxiliary feedwater flow in the small break LOCA procedure for the purpose of maintaining full HPI flow if auxiliary feedwater is lost.
Pump suction breaks coincident with a loss of all feedwater were not analyzed in the May 7th report.
For the reasons discussed above, the amount of reactor vessel water that would be available to cool the core would be approximately the same after 20 minutes for a break at the pump suction as for a break at the pump discharge.
It should be noted that more HPI water would be available to makeup the water boiled by decay heat in the core for the pump suction break than was assumed for the pump discharge break. The pump discharge break analyses in the May 7th report assumed that the break was between the HPI nozzle and the reactor vessel and that 30% of the total HPI flow was lost through the break.
For a pump suction break, all of the HPI water would be available to flow to the core. We therefore conclude that a minimum of 20 minutes would be available to the operator to actuate HPI and prevent core uncovery for breaks in the pump suction as well as at the pump discharge, even if all feedwater is temporarily lost, and that the operating procedures at Rancho Seco are adequate for either event.
).
The above statements and opinions are true and correct to the best of my. personal knowledge and belief.
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WaltofL ensen,.Jrg Subscribed and sworn jo before me this $^^ day of 7Aw,_,1982.
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My Commission Expires Q,L_
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WALTON L. JENSEN, JR.
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PROFESSIONAL QUALIFICAT]DNS I am a Senior Nuclear Engineer in the Reactor Systems Branch of the Nucleac Regulatory Commission.
In this position I am responsible for the technical analysis and evaluation of the public health and safety aspects of reactor.
systems.
~
From June 1979 to December 1979, I was assigned to the Bu11etins and Orders Task Force of the Nuclear Regulstory Commission.
I participated in the preparation of HUREG-0565, " Generic Evaluation of Small Break Loss-of-Coolant Accident Behavior in Babcock & Wilcox Designed 177-FA Operating Plants."
From 1972 to 1976, I was assigned to the Containment Systems Branch of the NRC/AEC, and from 1976 to 1979, I was assigned to the Analysis Branch of the In these positions I was responsible' for the development,and evaluation NRC.
of computer programs and techniques to calculate the reactor system and containment system response to postulated loss-of-coolant accidents.
From 1967 to 1972, I was employed by the Babcock and Wilcox Company at Lynchburg, There I was lead engineer for the development of loss-of-coolant Virginia.
computer programs and the qualification of these programs by comparison with experimental data.
M
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from 1963 to 1957,1 was employed by the Atomic Energy Commission in the Division of Reactor Licensing.
I assisted in the safety reviews of large I
power reactors, and 1 led the reviews of several small research reactors.
I received an M.S. degree in Nuclear Engineering at the Catholic University of A,7. erica in 1968 and a B.S. degree in Nuclear. Engineering at iiississippi State Uni.versity.in 1963.
I am a graduate of the Oak Ridge School for Reactor Technology, c.
1963-1964.
I am a member of the American Nuclear Society.
I am the author of three scientific papers dealing with the response of B&W reactors to loss-of-Coolant Accidents and have authored one scientific paper dealing with containment analysis.
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