Similar Documents at Salem |
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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARLR-N980595, Comment Supporting Proposed Rules 10CFR50,52 & 72 Re Changes,Tests & Experiments.Pse&G Supports Comments Submitted by NEI in Their Ltr1998-12-21021 December 1998 Comment Supporting Proposed Rules 10CFR50,52 & 72 Re Changes,Tests & Experiments.Pse&G Supports Comments Submitted by NEI in Their Ltr LR-N980588, Comment on Proposed Rule 10CFR50.65 Re Monitoring Effectiveness of Maint at Npps.Util Agrees with General Principle Behind Proposed Rulemaking,But However,Concerned That Proposed Rule Contain Language Open to Interpretation1998-12-14014 December 1998 Comment on Proposed Rule 10CFR50.65 Re Monitoring Effectiveness of Maint at Npps.Util Agrees with General Principle Behind Proposed Rulemaking,But However,Concerned That Proposed Rule Contain Language Open to Interpretation ML18106A8811998-09-15015 September 1998 Comment Opposing Draft NUREG-1633, Assessment of Use of Potassium Iodide as Protective Action During Severe Reactor Accidents. Believes That Discussion Contained in SECY-98-061 Should Be Included in Draft NUREG ML18106A8731998-09-15015 September 1998 Comment on Draft NUREG-1633 Re Assessment of Use of Potassium Iodide (Ki) as Protetive Action During Severe Reactor Accidents. Believes That NUREG Should Provide Balanced Discussion on Benefits & Risks of Use of Ki LR-N980284, Comment on PR-50 Re IEEE Std 603-1991 for Salem & Hope Creek Generating Stations.Lack of Adverse Comments to Draft RG Should Not Have Been Construed as Endorsement to IEEE 603-19911998-06-12012 June 1998 Comment on PR-50 Re IEEE Std 603-1991 for Salem & Hope Creek Generating Stations.Lack of Adverse Comments to Draft RG Should Not Have Been Construed as Endorsement to IEEE 603-1991 LR-N980149, Comment on Proposed Rule 10CFR50 Re Industry Codes & Stds. Comments Address Use of Engineering Judgment,Limitations on Use of Later ASME III Code Editions for Weld Leg Dimensions & Seismic Analysis1998-03-30030 March 1998 Comment on Proposed Rule 10CFR50 Re Industry Codes & Stds. Comments Address Use of Engineering Judgment,Limitations on Use of Later ASME III Code Editions for Weld Leg Dimensions & Seismic Analysis ML18102B4361997-07-0707 July 1997 Comment Opposing NUREG-1606, Proposed Regulatory Guidance Re Implementation of 10CFR50.59 (Changes,Tests or Experiments). Util Endorses Comments Submitted by Nuclear Energy Inst ML20132A8961996-12-0606 December 1996 Comment Supporting Pr 10CFR50, NRC Draft Ps on Restructuring & Economic Deregulation of Electric Utility Industry ML20084H9251995-06-0202 June 1995 Comment Opposing Proposed Change in State Cooperative Agreements Program Concerning NRC Intention to Reduce Scope of Work.Believes That NRC Should Maintain Environ Monitoring Program & Find Other Ways to Reduce Duplicative Svcs ML20134K5021995-02-24024 February 1995 Transcript of 950224 Enforcement Conference in King of Prussia,Pa Re C Vondra.Pp 1-136 ML20134K4511995-02-0808 February 1995 Transcript of 950208 Enforcement Conference in King of Prussia,Pa Re Plant.Pp 1-93 ML20134K4791995-02-0808 February 1995 Transcript of 950208 Enforcement Conference in King of Prussia,Pa Re V Polizzi.Pp 1-115 ML20134K4971995-02-0808 February 1995 Transcript of 950208 Enforcement Conference in King of Prussia,Pa Re L Reiter.Pp 1-64 ML20080G8321995-02-0606 February 1995 Comment Opposing Proposed Rule 10CFR50 Re Shutdown & low-power Operations for Npp.Encourages NRC to Reevaluate Regulatory Analyses in Light of Higher Costs.Concludes That Addl Rules on Shutdown & Low Power Operations Not Necessary ML20077L8631995-01-0303 January 1995 Comment Supporting Proposed Rules 10CFR2,51 & 54 Re NPP License Renewal.Util of Belief That Proposed Rev Reflect Positive Effort Towards Establishing Regulatory Process Requirements for Continued Operation of Nuclear Facilities ML20132B2281994-08-0202 August 1994 Transcript of 940802 Enforcement Conference in Salem,Nj W/Salem Senior Nuclear Shift Supervisor Involved in 940407 Event ML20067C1591994-02-17017 February 1994 Comments on NUREG/CR-5884 Re Analyses of Decommissioning for Ref PWR Power Station ML18100A5591993-08-26026 August 1993 Comment Opposing Proposed Rule Re Whistleblower Protection ML20126F2721992-12-21021 December 1992 Comment Endorsing Positions & Comments of NUMARC & BWROG Re Draft GL, Augmented Inservice Insp Requirments for Mark I & Mark II Steel Containments,Refueling Cavities & Associated Drainage Sys ML20091Q8661992-01-31031 January 1992 Comment Opposing Draft NUREG-1022,Rev 1, Event Reporting Sys,10CFR50.72 & 50.73,Clarification of NRC Sys & Guidelines for Reporting ML20072T2421991-04-11011 April 1991 Comment Re Proposed Change to 10CFR50.55A Re Inservice Testing of Containment Isolation Valves.Proposed Rule Should Be Revised to Allow Plants within Last 12 Months of Current Interval to Substitute Deferred Rv Shell Exams ML20235T1861989-02-24024 February 1989 Comment Supporting Proposed Rule 10CFR50 Re Ensuring Effectiveness of Maint Programs for Nuclear Power Plants, Extension of NRC Authority to BOP Portion of Plant & Misapplication of Adequate Protection Std of Backfit Rule ML20195H0331988-11-21021 November 1988 Comment on Proposed Rule 10CFR26 Re Fitness for Duty Program Which Includes Random Drug Testing.Util Strongly Favors 180- Day Period for Implementation of Rule & 360-day Implementation Period for Random Drug Testing ML20153F9681988-08-17017 August 1988 Comment Opposing Proposed Rule 10CFR50 Re Licensee Flexibility During Natl Crisis.Deferral of Issuance of Final Rule Until Proper Implementation Guidance Formulated Encouraged ML20154G1421988-04-20020 April 1988 Comment Opposing Proposed Rules 10CFR50 & 73 Re Policy Statement on Nuclear Power Plant Access Authorization Program.Nrc Should Establish Program Mutually Agreed Upon Between Union & Util,Per Hope Creek & Salem Programs ML20154G4601988-04-18018 April 1988 Comment Opposing Proposed Rule 10CFR50 Re Notification of Inspector Visits to Facility ML18093A6331988-02-0101 February 1988 Comment Supporting Proposed Rule 10CFR50 Re Proposed Policy Statement on Integrated Schedules for Implementation of Plant Mods ML20151B3641987-02-24024 February 1987 Comment Opposing Proposed Rule 10CFR50 Re Licensing of Nuclear Power Plants Where State &/Or Local Govts Decline to Cooperate in Offsite Emergency Planning ML20079N4271984-01-25025 January 1984 Response to State of DE 840120 Motion to Withdraw Petition for Leave to Intervene.Licensee Concurs in Motion.Dismissal of Proceeding Requested.Certificate of Svc Encl ML20079K9311984-01-20020 January 1984 Motion to Withdraw Petition for Leave to Intervene & Request for Hearing Re Extension of Time for Type a Test.Certificate of Svc Encl ML20078P6771983-11-0404 November 1983 Answer to State of DE Atty General 831021 Petition for Leave to Intervene & Request for Hearing on License Amend Re Inservice Integrated Leak Tests.Notices of Appearance & Certificate of Svc Encl ML20078M1551983-10-21021 October 1983 Petition for Leave to Intervene & Request for Hearing on Proposed Issuance of Amend to License DPR-70 Re Inservice Integrated Leak Tests.Affidavit of Mailing Encl ML18087A8331983-04-12012 April 1983 Petition for Order to Show Cause Why Util Should Not Be Restrained from Restarting Facility Until Qualifications for Operation Demonstrated at Public Hearing ML18087A8341983-04-11011 April 1983 Affidavit of DG Bridenbaugh Re Delay of Facility Restart. Full Review of safety-related Equipment Must Be Completed & Appropriate Changes Implemented.Prof Qualifications Encl ML20213E3601983-03-0808 March 1983 Testimony Before Subcommittee on Energy & Environ Re Plant Licensing Concerns ML18086A9691981-10-14014 October 1981 Affidavit Confirming Validity of Util 811009 Response to IE Insp Repts 50-272/81-15 & 50-311/81-14 ML20005B6831981-08-20020 August 1981 Petition for Review of Aslab 810717 Order,Permitting OL Amend,Allowing Installation of New Storage Racks & Increasing Pool Capacity.Notice of Appearance & Affidavit of Svc Encl.Related Correspondence ML20010C1481981-08-14014 August 1981 Response in Opposition to Lower Alloways Creek Township 810803 Petition for Review of ALAB-650.Petitioner Has Raised No Issue Which Warrants Commission Consideration.Certificate of Svc Encl ML20009H2221981-08-0303 August 1981 Petition Supporting Review of Aslab Decision.Case Involves Matter That Could Significantly Affect Environ,Public Health & Safety & Involves,Important Procedural Issues & Public Policy Questions.Certificate of Svc Encl ML18086A5181981-05-15015 May 1981 Answer Opposing AC Coleman 810504 Request for Stay of Initial decision,LBP-80-27,pending Appeal.Request Untimely & Fails to Meet Requirements for Issuance of Stay. Certificate of Svc Encl ML18085A8401981-02-17017 February 1981 Brief Supporting ASLB 801027 Decision Authorizing OL Amend to Permit Storage of 1,170 Spent Fuel Elements in Facility Spent Fuel Pool.All Exceptions Should Be Denied.Aslb Has Adequately Weighed Evidence.Certificate of Svc Encl ML18085A5231981-01-13013 January 1981 Findings of Fact & Conclusions of Law in Support of 801111 Exceptions to ASLB 801027 Initial Decision Re Applicant Proposed Expansion of Fuel Storage.Certificate of Svc Encl ML18085A4091980-12-0808 December 1980 Response to Intervenors Eg & a Coleman Motion for Extension Until 810131 to File Brief in Support of Exceptions.Opposes Motion But Would Not Object to 2-wk Extension.Certificate of Svc Encl ML18085A4081980-12-0404 December 1980 Appeal from ASLB Initial Decision Granting Util Right to Increase Spent Fuel Pool Storage Capacity.Nepa Requires Detailed Analysis of Safety & Health Problems Posed by Reracking.Certificate of Svc Encl ML19340D3431980-11-30030 November 1980 Request for Extension to 810131 to File Brief in Support of Exceptions to ASLB 801027 Initial Decision Re Spent Fuel Pool Proceeding.Certification of Svc Encl ML18085A2791980-11-20020 November 1980 Notice of Withdrawal of Appearance as Counsel for Intervenors Coleman.Intervenors Coleman to Remain Parties to Proceeding.Certificate of Svc Encl ML18085A2501980-11-11011 November 1980 Appeal from ASLB 801027 Initial Decision.Alleges Erroneous Finding of Facts Re Contentions 2 & 6,evaluation of Eia, Acceptance of Pasedag Testimony & Rejection of Benjamin Testimony.Counsel Withdrawal & Certificate of Svc Encl ML18085A2161980-11-0404 November 1980 Exceptions & Appeal from ASLB 801027 Initial Decision. Exclusion of as Benjamin of Sandia Labs Testimony Is Arbitrary Due to Relevant Evidence Re Oxidation That Could Propagate to Older Fuel.Certificate of Svc Encl ML20062J4921980-10-21021 October 1980 Addl Testimony Presented Before ASLB to Correct & Clarify 800710 Testimony Re Loss of Water from Spent Fuel Storage Pool ML18082A7101980-07-11011 July 1980 Reply Findings of Fact & Conclusions of Law in Form of Partial Initial Decision Substituting for Licensee 800613 Findings,In Response to ASLB 800509 Order & ASLB 800626 Question 5 on away-from-reactor Issues.W/Certificate of Svc 1998-09-15
[Table view] Category:PLEADINGS
MONTHYEARML20079N4271984-01-25025 January 1984 Response to State of DE 840120 Motion to Withdraw Petition for Leave to Intervene.Licensee Concurs in Motion.Dismissal of Proceeding Requested.Certificate of Svc Encl ML18087A8331983-04-12012 April 1983 Petition for Order to Show Cause Why Util Should Not Be Restrained from Restarting Facility Until Qualifications for Operation Demonstrated at Public Hearing ML20005B6831981-08-20020 August 1981 Petition for Review of Aslab 810717 Order,Permitting OL Amend,Allowing Installation of New Storage Racks & Increasing Pool Capacity.Notice of Appearance & Affidavit of Svc Encl.Related Correspondence ML20010C1481981-08-14014 August 1981 Response in Opposition to Lower Alloways Creek Township 810803 Petition for Review of ALAB-650.Petitioner Has Raised No Issue Which Warrants Commission Consideration.Certificate of Svc Encl ML20009H2221981-08-0303 August 1981 Petition Supporting Review of Aslab Decision.Case Involves Matter That Could Significantly Affect Environ,Public Health & Safety & Involves,Important Procedural Issues & Public Policy Questions.Certificate of Svc Encl ML18086A5181981-05-15015 May 1981 Answer Opposing AC Coleman 810504 Request for Stay of Initial decision,LBP-80-27,pending Appeal.Request Untimely & Fails to Meet Requirements for Issuance of Stay. Certificate of Svc Encl ML18085A4091980-12-0808 December 1980 Response to Intervenors Eg & a Coleman Motion for Extension Until 810131 to File Brief in Support of Exceptions.Opposes Motion But Would Not Object to 2-wk Extension.Certificate of Svc Encl ML18085A4081980-12-0404 December 1980 Appeal from ASLB Initial Decision Granting Util Right to Increase Spent Fuel Pool Storage Capacity.Nepa Requires Detailed Analysis of Safety & Health Problems Posed by Reracking.Certificate of Svc Encl ML19340D3431980-11-30030 November 1980 Request for Extension to 810131 to File Brief in Support of Exceptions to ASLB 801027 Initial Decision Re Spent Fuel Pool Proceeding.Certification of Svc Encl ML18085A2501980-11-11011 November 1980 Appeal from ASLB 801027 Initial Decision.Alleges Erroneous Finding of Facts Re Contentions 2 & 6,evaluation of Eia, Acceptance of Pasedag Testimony & Rejection of Benjamin Testimony.Counsel Withdrawal & Certificate of Svc Encl ML18085A2161980-11-0404 November 1980 Exceptions & Appeal from ASLB 801027 Initial Decision. Exclusion of as Benjamin of Sandia Labs Testimony Is Arbitrary Due to Relevant Evidence Re Oxidation That Could Propagate to Older Fuel.Certificate of Svc Encl ML18082A5481980-05-23023 May 1980 Proposed Corrections for 800430 Evidentiary Hearing Transcript.Certificate of Svc Encl ML18082A5281980-05-13013 May 1980 Proposed Corrections to Transcript of 800328-29 Evidentiary Hearings.Certificate of Svc Encl ML18082A5261980-05-13013 May 1980 Request for Extension Until 800528 to File Transcript Corrections.States No Objection to NRC Motion for Similar Extension.Transcript Not Yet Received in Licensee Newark,Nj Ofc ML19323A9571980-04-21021 April 1980 Response in Opposition to Webb,Fankhauser & Portion of NRC Testimonies Based on Class 9 Accident Scenarios.Testimony Beyond ASLB Jurisdiction & Should Not Be Admitted Into Evidence.Certificate of Svc Encl ML18082A5011980-04-18018 April 1980 Reply in Opposition to Licensee Response to ASLB 800222 Memorandum & Order,Question 5,re Spent Fuel Pool Gross Loss of Water.Urges to Strike Testimony W/Appropriate Sanctions ML18082A4991980-04-18018 April 1980 Motion to Strike Licensee 800410 Response to ASLB 800222 Memorandum & Order,Question 5,re Spent Fuel Pool Gross Loss of Water.Licensee Should Be Barred from Participation or Compelled to File Testimony Due to Dilatory Conduct ML18082A5021980-04-18018 April 1980 Response in Opposition to NRC Testimony of Wf Pasedag Re ASLB Question 5.Spent Fuel Pool Old Fuel Would Be Involved in Enlargement Case & Would Consequently Increase Radiological Effects.Certificate of Svc Encl ML19305D7371980-04-11011 April 1980 Comments in Opposition to Township of Lower Alloways Creek 800325 Request for Suspension of Issuance of OL Per 10CFR2.206.Urges Denial Due to Untimeliness of Petition & Inadequacy of Allegations Re Noncompliance W/Nepa Rules ML19323D1891980-04-10010 April 1980 Response to ASLB Question 5 Re Gross Loss of Water from Facility Spent Fuel Pool.Loss Will Have No Adverse Consequences on Public Health & Safety Due to Adequate Cooling Achieved in Facility.Prof Qualifications Encl ML19323D5131980-04-0909 April 1980 Forwards Re Webb Technical Rept,In Response to ASLB 800222 Order Re Consequences of Gross Water Loss from Spent Fuel Storage Pool.Certificate of Svc Encl ML19305E7281980-04-0909 April 1980 Response Enclosing DB Fankhauser Testimony in Reply to ASLB 800222 Order Re Consequences of Gross Water Loss from Spent Fuel Storage Pool.Certificate of Svc Encl ML19309A4931980-03-25025 March 1980 Request for Suspension or Moratorium on Issuance of OL for Facility,Pending Conclusion of ASLB Hearing on Safety of Spent Fuel Storage Pool at Unit 1.Notice of Appearance of Cj Valore on Behalf of Intervenor Encl ML18082A1391980-03-25025 March 1980 Intervenor Request for Suspension or Moratorium on Issuance of Ol.Issuance Would Permit Same Enlarged Spent Fuel Pool That Is Subject of Ongoing Hearing ML18082A1301980-03-19019 March 1980 Motion for 30-day Extension to File Testimony Re Consequences of Water Loss from Spent Fuel Storage Pool. Urges Postponement of 800422 Evidentiary Hearing, Accordingly.Notice of Appearance & Certificate of Svc Encl ML18081B0861980-02-14014 February 1980 Request for Taking Official Notice of White House 800212, Fact Sheet,President'S Program on Radwaste Mgt, Due to Relevancy of First Bullet,Page 2 & Third Bullet,Page 6.W/ Certificate of Svc & Fact Sheet ML18081A8881980-01-10010 January 1980 Opposition to Intervenors Coleman 791018 Request for Action Under 10CFR2.206.NRC Fulfilled Statutory Duty Per Endangered Species Act.No New Matters Raised by Intervenors Request ML18081A8171979-12-18018 December 1979 Opposition to Public Advocate of State of Nj 791106 Request to Reopen Intervenors Coleman Contention 9.Appeal Is Proper Procedure If Intervenors Dissatisfied W/Aslb Initial Decision.Certificate of Svc Encl ML18081A7471979-11-13013 November 1979 Response in Opposition to Public Advocate of State of Nj 791030 Supplemental Argument Supporting Motion for Reconsideration of Colemans Contention 13.Colemans Failed to Demonstrate Relevance of Claim.Certificate of Svc Encl ML18081A6971979-10-30030 October 1979 Supplemental Argument on Behalf of Intervenors Coleman to Reopen Coleman Contention 13 Re Reracking of Spent Fuel Pool.Actual Figures of Radiation Exposure During Reracking of Peach Bottom Nuclear Station Never Received ML18081A4181979-10-18018 October 1979 Petition Seeking NRC Issuance of Show Cause Order for Suspension &/Or Revocation of Ols.Operation of Facility Would Threaten Local Existence of short-nosed Sturgeon. Affidavit & Certificate of Svc Encl ML18081A4871979-10-18018 October 1979 Seeks Show Cause Order & Suspension or Revocation of OL for Unit 1 & Stay or Licensing & Suspension or Revocation of CP for Unit 2.No Eia Performed Re Impact on Endangered Fish Species.Certificate of Svc Encl ML18079A9711979-09-20020 September 1979 Applicant Comments on Request of Intervenors Coleman for Issuance of Order to Show Cause for Stay ML18079B0891979-08-31031 August 1979 Opposes Intervenors Coleman 790801 Request That ASLB Reopen Record for Newly Discovered Evidence Re Contentions 2 & 6. Insp Document Has No Relevance & No Significance to Proceeding ML19249B8201979-08-31031 August 1979 Petition to Amend 790802 Motion for Issuance of Show Cause Order & Stay of Licensing Procedure.Adds Addendum 7A & Contentions 8-10.Certificate of Svc Encl ML19209C3871979-08-31031 August 1979 Motion,Submitted by Intervenors Coleman,That NRC Amend Request for Order to Show Cause & Stay Licensing.Seek Addl Contentions Re Cost/Benefit Analysis,Seismic Analysis & Class 9 Accidents ML18081A4141979-08-31031 August 1979 Seeks Denial of Intervenors Coleman 790802 Motion for Reconsideration of Contention 13 Re Release of Radioactive Matl.No Justification for Late Filing.Criteria for Compliance W/Operation Objectives Defined in 10CFR50,App I ML18079B1161979-08-29029 August 1979 Request by Intervenors Coleman That ASLB Accept Addl Argument on ASLB Question 4 Re Consideration of Class 9 Accidents.Nrc Admits That TMI Accident Was Class 9. Certificate of Svc Encl ML18079B1151979-08-27027 August 1979 Response to ASLB Question 4 Re Class 9 Accidents.Tmi 790328 Accident Was Class 9,constituting Successive Failures of Operator Procedures & Equipment.Testimony in Present Proceedings Requires Wide Latitude.Certificate of Svc Encl ML18079B0881979-08-21021 August 1979 Response to ASLB Question 4,submitted on Behalf of Intervenors Coleman.Alleges TMI Accident Was Class 9 Accident.Accident Posed Significant Risk to Health & Safety of Population & Environ.Certificate of Svc Encl ML18079B0611979-08-20020 August 1979 Responds to Question 4 of ASLB 790710 Order.Forwards C Kepford Rept on TMI Accident.Prof Qualifications & Certificate of Svc Encl ML18081A4111979-08-10010 August 1979 Requests That ASLB Order Extension Until 790831 for Response to Intervenors Coleman Request to Reopen Consideration of Contentions 2 & 6 ML18079B0461979-08-0303 August 1979 Forwards Re Webb 790723 Rept, TMI Accident:Was It Class 9 Accident, in Response to ASLB 790710 Question 4 ML19208C3681979-08-0202 August 1979 Requests Issuance of Order to Show Cause & Stay of Licensing Per 10CFR2.202 & 2.206.NRC Has Failed to Act on Info Re PA-NJ-MD Grid,Cost/Benefit Analysis,Expansion of Spent Fuel Pool & Lessons Learned Re TMI ML18079B0851979-08-0202 August 1979 Request by Intervenors Coleman That ASLB Reconsider Dismissal of Contention 13.Intervenor State of Nj Supports Motion.Util Is Obliged Per 10CFR50 to Explore Alternatives to Spent Fuel Pool Expansion ML19225D1441979-08-0202 August 1979 Request That NRC Issue Order to Show Cause & Request to Stay Licensing.Requests Intervenor Status.Submits List of Contentions & Partial List of Resouce Documents.Certificate of Svc Encl ML18079B0871979-08-0101 August 1979 Request by Intervenors Coleman That ASLB Reopen Record Re Contentions 2 & 6.Intervenor State of Nj Supports Motion. Experiences at Northern State Power Co Are Pertinent to Proceedings ML18079A7621979-07-0909 July 1979 Response Submitted by Intervernor Township of Lower Alloways Creek to NRC Motion to Strike Portions of Re Webb & EA Gulbransen Testimony Re ASLB 790418 Order. Affidavit of EA Gulbransen & Certificate of Svc Encl ML18079A8311979-07-0606 July 1979 Request Submitted by Util for Denial of Intervenors Coleman 790625 Request for Reconsideration of Dismissal of Coleman Contention 7.NRC Must Remand Matter to Aslb. Certificate of Svc Encl ML18079A8291979-07-0606 July 1979 Request Submitted by Util for Denial of Intervenors Coleman 790626 Request That ASLB Compel Licensee to Suppl Responses to Interrogatories 1,3 & 6.Questions Have No Relation to Grid Strap Problem 1984-01-25
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coc W ED usgo 97 gg11 M# T2 UNITED STATES OF AMERICA L d NUCLEAR REGULATORY COMMISSION O P Cn Before the Atomic Safety and Licensing Board In the Matter of )
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PUBLIC SERVICE ELECTRIC AND ) Docket No. 50-272 GAS COMPANY, et al. ) (Proposed Issuance of
) Amendment to Facility (Salem Nuclear Generating ) Ope ating License Station, Unit 1) ) No. DPR-70)
LICENSEE'S RESPONSE TO LICENSING BOARD QUESTION 5 REGARDING A " GROSS LOSS OF WATER" FROM THE SALEM SPENT FUEL POOL In its Memorandum and Order dated February 22, 1980, the Atomic Safety and Licensing Board (" Licensing Board")
directed the parties to address the following question:
In the event of a. gross loss of water from the storage pool, what would be the difference in conse-quences between those occasioned by the pool with expanded storage and those occasioned by the present pool?
For ease of reference, this question will be referred to as Question 5.
The Fuel Handling Building is a T-shaped, reinforced concrete Seismic Class I structure located next to the reactor containment building. It is designed to store new and spent fuel, and also to provide facilities for the delivery and shipment of new and spent fuel. Its design l
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, takes into account such phenomena as seismic avents, tor-nadoes, and high water levels. The spent fuel pool is located within the Fuel Handling Building. A design basis of the spent fuel pool is to prevent any " gross loss of
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water" from occuring. In this respect, the spent fuel pool is of Seismic Class I design and construction, and has a bottom foundation consisting of 11 feet of reinforced struc- !
i tural concrete below which is 48 feet of lean concrete. The l
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concrete is founded upon a geological stratum known as the i Vincentown Formation. The pool is lined with 1/4" welded stainless steel plates. Because there are no drains below the surface of the spent fuel pool and because anti-syphon devices have been provided as needed, inadvertent water loss which would constitute a " gross loss of water" is not possible.
The spent fuel pool is designed such that the cask handling area is not located within it, but rather within a transfer pool separated by redundant gates. Given the design of the cask handling crane, it is physically in-possible to move a spent fuel shipping cask over the spen fuel pool. Moreover, when the transfer pool is empty, the crane used to remove the gates fran between the spent fuel
- pool and cask handling area does not have sufficient lifting capacity to remove these gates. Furthermore, even if these gates were postulated to be removed, the water level could
not fall below the top of the spent fuel rods, since the bottom of the gates is higher than the top of the spent fuel; thus adequate cooling would be assured.
A leak detection system has been provided to detect any water which may leak through the liner and, ultimately, to carry it off to the liquid radwaste system. The leak detection system consists of channels located below each weld seam in the spent fuel pool connected to piping which penetrates one of the walls of the spent fuel pool at its ;
lowest elevation. Any leakage into the leak detection system flows into a trough and then into a sump located at the end of this trough. The wall through which the leak detection system piping penetrates is the thickest wall of ,
l the spent fuel pool and is approximately 9' 7" thick. The i 1
remaining walls of the spent fuel pool range from 6' to 9' 7" thick.
l A system has also been incorporated into the spent fuel l
pool to detect and alarm a loss of water level. This system j annunciates in the control room.
Another level alarm has been provided in the leak detection system sump to detect l leakage of water from the leak detection system. This alarm l
also annunciates in the control room.
The spent. fuel pool is provided with a number of sources of makeup water to replenish water in the pool should the need arise. The makeup sources are from the demineralized water system, which supplies approximately 100 GPM; the
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1 refueling water storage tank, which can supply 100 GPM; the primary water storage tanks, capable of supplying 100 GPM; and the CVC Hold-Up tanks, which can supply approximately 500 GPM. Also, a portable pump is maintained under adminis-trative control to supply at least 100 GPM of water to the spent fuel pool.
For purposes of responding to the Board's Question 5 and to explore the " gross loss of water" postulated by it, while not a design basis for the spent fuel pool as approved by the Commission and while there is no reason to make it one, the arbitrary and nonmechanistic ultraconservative assumption has been made that the Class I spent fuel liner welds covering one leak detection channel completely fail. With this assumption as a departure for analysis of the " gross loss of water" hypothesis, the resulting leak rate to the leak detection sump would only be 53 GPM, well within the capability of any of the makeup systems. Thus, even in this extreme case postulated for purposes of analysis, there would be no " gross loss of water" from the spent fuel pool.
Even were one to postulate the complete failure of all the fuel liner welds, which would be, in effect, a complete failure of the liner, the makeup sources noted above (even without inclusion of the capacity of the portable pump) 1 would be sufficient to keep the spent fuel covered and j cooled at all times. Even this simplified analysis is t
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extremely conservative in that it neglects the decrease in leakage rate as the level of the water in the spent fuel pool would decrease. Thus even under these incredible 1 I
conditions, the desira of the Fuel Handling Building and the )
i spent fuel pool v.ecludes any consequences resulting from a "gro:s loss of water." Thus, there is no, reason to change j the design basis of the pool because of the installation of l
l the increased capacity racks. Furthermore, there is no l difference in these analyses as the result of the installa- I tion of the increased capacity racks in the spent fuel pool l 1
as compared to the present pool and no significant change in any " consequences" even were one to postulate a " gross' loss of water" consisting of a failure of the spent fuel liner welds. Again, these. evaluations are based upon the present design basis of the facility. ,
Even the predicted minor consequences could be reduced by relatively modest design changes, such as installing flow restrictors on the tell-tales. In that case, even the above postulated events would result in only a very small water level reduction in the spent fuel pool. This is true for both cases analyzed and' again independent of the type of racks installed.
Thus, because adequate cooling is achieved under any of the above described circumstances, even in the extreme cases postulated above, a " gross loss of water" in the spent fuel
- pool, also as defined above, would have no adverse conse-l quences upon the public health and safety.
i l
. While the matter is beyond the jurisdiction of the Licensing Board and clearly beyond the scope of Question 5, Licensee wishes to add some comment to the statement made on page 15 of the Licensing Board's Memorandum and Order, to the effect that:
Salem 1 sits on an artificial island at the head of an important estuary.
It is surrounded by liquid pathways. ,
Salem 1 does not float, but according to the analysis in Offshore Power, pathways, rather than floating,'are the critical factor.
We are concerned that this statement resulted from a mis-understanding on the Board's part of the nature of the site and the actual potential for a contribution to the liquid pathway.
As previously discussed, underneath the spent fuel pool there are 11 feet of reinforced structural concrete.. This concrete rests on top of an additional 48 feet of lean con-crete fill that extends down to the Vincentown Formation, which is composed of silty sands, primarily quartz, feldspar and glauconite (Appendix B to Salem FSAR) .
The NRC's Liquid Pathway Generic Study (NUREG-0440) reccgnizes a significant difference between land-based plants and floating plants as to their respective potential for dispersion of large quantities of radioactivity through a liquid pathway. For land-based plants such as Salem, NUREG-0440 estimates a one or two year delay before leaching
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of radioactive material could begin. Even after this one to two year period, the rate of travel of the leachate in the soils under the foundation of a land-based plant would be very slow. Both PSE&G (Section 2.6 of the FSAR) and the NRC (Section 2.5 of the Safety Evaluation Report) have concluded that at the site of the Salem Generating Station "the horizontal component of groundwater movement is quite slow, due to the low hydraulic gradient and relatively low formation 1 ,
permeabilities." i l
It is therefore reasonable to conclude that in any land-based plant including Salem, appropriate measures could ;
be taken to monitor and install any necessary " barriers" to l l
migration and put into effect any interdiction to effec-tively control the liquid pathway. By contrast, the leaching of radioactivity is expected to "begin immediately for the floating nuclear plant (p. i-9 of NUREG-0440)." Hence, the two cases are not comparable. The reference to the Salem site as on " Artificial Island" does not in any way imply that an appropriate comparison may be made with a floating nuclear plant. Furthermore, as far as liquid pathways are concerned, the Salem site is typical of land-based sites.
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EDUCATIONAL AND PROFESSIONAL QUALIFICATIONS 9- APR 11ggg0 F :
LAWRENCE REITER ot WS PUBLIC SERVICE ELECTRIC AND GAS COMPANY b -
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My name is Lawrence [Reiter. My business address is 80 Park Place, Newark, New Jersey.
I am employed as a Principal. Engineer in the Engineering Department of Public Service Electric and Gas Company. In this capacity, I am engaged in supervising the engineering design, installation and start-up of Nuclear Steam Supply and Associated Systems.
I was graduated from Villanova University in 1966 with a Bachelor of Mechanical Engineering degree. I have done graduate study work in Nuclear Engineering and Heat Transfer, at University of Connecticut and Stevens Institute of Technology. I received a Master of Business Administration degree from Rutgers University in 1974.
Previous to my employment with Public Service Electric and Gas Company, I was engaged in engineering design and analysis of Nuclear Components for the U.S. Navy nuclea; power program, by Curtiss-Wright Corporation from 1969 to 1971. Prior to this, I was engaged in nuclear engineering design and analysis of nuclear related systems for nuclear submarines, by General Dynamics / Electric Boat Division from 1966 to 1969.
G o In 1971, I joined Public Service Electric and Gas Company and was assigned to the Mechanical Division of the Electric Enginejering Department. I have been involved with design and specification of various nuclear and related systems for the Salem Nuclear Generating Station.
My current position is as group head of the Salem Group, Mechanical Division, Engineering Department. In this capacity,i! am responsible for all mechanical engineering on nuclear systems, auxiliary systems, ventilation systems and insulation. In addition, I am responsible for all mechanical field engineering. I supervise the engineer responsible for the Increased Capacity Spent Fuel Racks.
I am a member of the American Nuclear Society and the American Society of Mechanical Engineers.
I am a registered professional engineer in the State of New Jersey.
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Doc EDUCATIONAL AND PROFESSIONAL QUALIFICATIONS u pc PhNUEL O. BANDEIRA APR i.1 O " s '
sua@M PUBLIC SERVICE ELECTRIC AND GAS COMPANY L tr N
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My name is Manuel O. Bandeira. My business address -
is 80 Park Place, Newark, New Jersey 07101.
I am employed as a Lead Engineer in the Engineering and Construction Department of Public Service Electric and Gas Company. In this capacity I am engaged in the design, analysis, installation and start-up of various nuclear power related systems.
I graduated from Newark College of Engineering in 1971 with a Bachelor of Science in Mechanical Engineering. I am currently pursuing the Master of Science in Mechanical En-gineering degree at New Jersey Institute of Technology.
Upon graduating from Newark College of Engineering in 1971, I joined Public Service Electric and Gas Company. My l
employment with Public Service Electric and Gas Company has )
i been diversified. From 1971 through 1974 I was responsible for the design, analysis, installation and start-up of power station turbine and auxiliary equipment. From 1974 through 1976 I was a field engineer at salem Nuclear Generating Station responsible for the resolution of field related in-stallation, start-up, testing and operation problems of nuclear and non-nuclear equipment and systems. From 1976 to the present, I am a member of the Salem Group, Mechanical
/ *t Division, Engineering Department engaged in the design, analysis, installation, start-up and testing of nuclear related systems; I am the engineer in charge of design, analysis and installation of the increased capacity spent fuel storage racks.
I am a registered Professional Engineer of the State of New Jersey and I am a member of The American Society of Mechanical Engineers. ,