Outline of Intended cross-examination by Util,Contingent Upon Denial of Util 790423 Objections to Intervenor'S Profferred Testimony.Certificate of Svc EnclML19269D415 |
Person / Time |
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Site: |
Salem ![PSEG icon.png](/w/images/c/cc/PSEG_icon.png) |
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Issue date: |
04/25/1979 |
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From: |
Wetterhahn M CONNER, MOORE & CORBER |
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To: |
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References |
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NUDOCS 7906020252 |
Download: ML19269D415 (10) |
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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:OTHER LEGAL DOCUMENT
MONTHYEARML18085A2791980-11-20020 November 1980 Notice of Withdrawal of Appearance as Counsel for Intervenors Coleman.Intervenors Coleman to Remain Parties to Proceeding.Certificate of Svc Encl ML19309D5501980-03-25025 March 1980 Notice That Cj Valore Appears as Attorney of Record for Petitioner SE Donelson,Mayor of Lower Alloways Township, Salem County,Nj ML18082A1271980-03-10010 March 1980 Notices of KA Onsdorff Withdrawal & Re Makul Appearance on Behalf of Intervenors Colemans in Proceeding ML18079B0481979-08-31031 August 1979 Certificate of Svc Re Util 790831 Response to Motion for Reconsideration of Intervenors Coleman Contention 13 & Util 790831 Response to Motion to Reopen Intervenors Coleman Contentions 2 & 6 for Receipt of New Evidence ML19209B0571979-08-31031 August 1979 Certificate of Svc Verifying Parties Who Have Been Served W/Intervenors Coleman Motion to Amend Petition Seeking Issuance of Order to Show Cause & Stay Licensing ML18081A4131979-08-10010 August 1979 Notice of Appearance of RM Rader on Behalf of Util. Certificate of Svc Encl ML19254B2911979-08-0303 August 1979 Certifies Svc of Affidavit in Support of Issuance of Order to Show Cause & Stay Licensing ML18079A9671979-07-0909 July 1979 Notice of Appearance of Jj Degnan for Intervenor State of Nj.Certificate of Svc Encl ML18079A8281979-07-0202 July 1979 Outline of cross-examination of Intervenors Coleman. Questions Relate to Initial Events for TMI Incident, Operation of Reactor Containment Sys During Loss of Feedwater Transient & Operation of Auxiliary Bldg ML19270H4241979-06-30030 June 1979 Outline of Util cross-examination of R Webb & Gulbransen Testimony on Behalf of Intervenor Lower Alloways Creek Township.Matl Will Be Used to Extent 790630 Objections to Testimony Are Overruled.Certificate of Svc Encl ML20125A6261979-06-30030 June 1979 Outline of cross-examination Submitted by Util to Be Used to Extent That Util 790630 Objections to Intervenor Lower Alloways Creed Township Testimony Are Not Sustained. Certificate of Svc Encl ML19269D4151979-04-25025 April 1979 Outline of Intended cross-examination by Util,Contingent Upon Denial of Util 790423 Objections to Intervenor'S Profferred Testimony.Certificate of Svc Encl ML19289F1851979-04-25025 April 1979 Outline of Areas of cross-examination,submitted Per 790329 Pretrial Order.Certificate of Svc Encl ML19284A7121979-02-0606 February 1979 KA Onsdorff Will Appear on Behalf of Intervenors a & E Coleman in Place of RW Potter 1980-03-25
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3 'Q NRC PUBLIC DOCUMENT ROOM hg UNITED STATES OF AMERICA
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- d' NUCLEAR REGULATORY COMMISSION b, os tav \ y In the Matter of )
)
PUBLIC SERVICE ELECTRIC & GAS ) Docket No. 50-272 COMPANY, et al. ) (Proposed Issuance
) of Amendment to (Salem Nuclear Generating ) Facility Operating Station, Unit 1) ) License No. DPR-70)
LICENSEE'S OUTLINE OF CROSS-EXAMINATION If and to the extent that " Licensee's Obj ections to Intervenor's Profferred Testimony" dated April 23, 1979, is not granted, the following represents Licensee's outline of intended cross-examination:
I. Testimony of George Luchak, Ph.D.
- 1. Qualifications of the Witness to testify with regard to:
- a. The design of commercial nuclear power plants
- b. The design of the Salem Generating Station, Unit 1
- c. The design of fuel pools and racks, particularly the fuel pool and racks for Salem Generating Station Unit 1
- d. The siting, design, and construction of an ISFSI
- e. Costs associated with the siting, design, construction and operation of an ISFSI 2259 006 79060209 Q
-~ - ...
l
- f. Costs associated with operation of a nuclear power plant and spent fuel pool at that plant, particularly the Salem Generating Station, Unit 1
- g. Safe and permanent disposal of spent fuel, including technology and costs
- h. Accident evaluation at nuclear power plants and spent fuel pools, particularly Salem Generating Station, Unit 1
- 2. Bias and prejudice of the Witness
- 3. Basis for Testimony Regarding Availability of an ISFSI as an alternative.
- a. Status, design, construction or operation of all 79FSI's
- b. Capacity of proposed ISFSI's
- c. Lead time associated with siting, design and construction of an ISFSI
- d. Costs associated with siting, design, and construction of various ISFSI's and basis for calculation of such costs
- e. Changes in ISFSI costs v. time
- f. Operating costs of an ISFSI
. g. Operating costs associated with the Salem spent fuel pool
- h. Differential operating costs at the Salem Generating Station, Unit 1 resulting from changing the racks
- i. Factors regarding need for an ISFSI, including national policy considerations 2259 007
- 4. Basis for statements regarding Regulatory Guide 3.24 and ISFSI regarding:
- a. Siting requirements for an ISFSI
- b. Comparison to the requirements of proposed Regulatory Guide 3.44 and proposed 10 C.F.R. Part 72
- c. An ISFSI as a permanent storage facility
- d. Purported U.S. policy regarding directed away-from-reactor storage
- e. Changes in U.S. position after President Carter's
- position on reprocessing
- f. Subsequent bias of NRC towards at-reactor storage
- 5. Basis for knowledge of Browns Ferry incident, including:
- a. Nature of sources utilized
- b. Type of and time spent on research
- c. Detailed chronology of events at Browns Ferry
- d. Offsite consequences
- e. Knowledge of investigators performed
- f. Differences in type of reactor between Browns Ferry and Salem Generating Station Unit 1
- g. Relationship of Browns Ferry accident to the design changes of the spent fuel pool
- 6. Basis for knowledge of the Three Mile Island Incident, including
- a. Nature of sources of information
- b. Type of and time spent on research
- c. Detailed chronology of events
- d. Offsite consequences
- e. Effect on the spent fuel pool at Three Mile Island Unit 2 2259 008
- f. Differences in design between Three Mile Island Unit 2 and Salem Unit 1
- 7. Basis for predicting impact of Three Mile Island Unit 2 type event on Salem Fuel Pool, including
- a. Knowledge of predicted radiation levels and conenmination at various locations at Salem Unit 1 as result of Three Mile Island Unit 2 type event
- b. Knowledge of details of design and location of equipment at Salem as related to the spent fuel pool c .. Knowledge of redundant and backup fuel pool systems at Salem Unit 1
- 8. Basis for predicted risk of accident at Artificial Island, including
- a. Methodology and assumptions utilized
- b. Data utilized
- c. Accuracy of results and uncertainty
- 9. Basis of prediction of type of spent fuel pool accident, including
- a. Assumptions utilized
- b. Failure mode analysis utilized
- c. Type of contamination assumed or calculated
- d. Type and extent of instrument failures assumed or predicted
- e. Assumptions or predictions as to age of fuel in spent fuel pool by region 2259 009
- f. Assumptions or prediction as to radioactive decay of spent fuel
- g. Assumptions or predictions as to. heat rejected by spent fuel pool
- h. Type and extent of hydrogen explosion predicted and mechanisms involved
- i. Type and extent of " scattering" of nuclear debris assumed or predicted
- j. Type and extent of maintenance required post accident k.' Mechanism for water boiling off due to a break in the cooling system
- 1. Assumptions regarding radioactive transport modes and predicted effects
- 10. Basis for statements regarding asserted criteria for determining location for storage of spent fuel:
- a. Assumptions regarding dispersion of radioactive material
- b. Sitine criteria for ISFSI
- c. Basis for and completeness of asserted necessarr infor.Tation needed to site an ISFSI
- 11. Basis for'ulH mate conclusions regarding availability of an ISFSI as an alternative IJ. Crockett Letter
- 1. Basis for Crockett letter, including
- a. Identification of DOE letter and determinatior.
of basis, purpose and extent of inquiry from LOE 2259 010
- b. Conditions or programs existing at time which caused inquiry from DOE
- c. Changes since Crockett letter which may have changed responses if requested today or changed PSE&G position
- d. Status of DOE programs
- 2. Basis for response to Question 1, including
- a. Assumptions and methodology used to determhe number of spent fuel assemblies discharged by calender year
- b. Nature of changes which could affect the dis-charge rate
- 3. Basis for response to Question 2, including
- a. Assumption and. methodology used to predict cumulative total of spent fuel cooled for five years
- 4. Basis for response to Question 3, including
- a. Basis for PSE&G position with regard to shorter period of time for shipment of spent fuel
- b. Assumptions and type of economic evaluations used to determine when transfer to the government should take place
- c. Advantages and incentives for a utility to wait for a geologic repository to be in service ...
- d. Basis for statements regarding spent fuel pool capacity for Hope Creek
- e. Basis for saturation of the spent fuel facility with and without full core dump 2259 011
- 5. Basis for response to Question 4, including
- a. Basis for PSE&G position with regard to DOE design criteria of five year fuel cooling
- b. Basis of position on advance notice for transfer of spent fuel
- c. PSE&G position on situations which might neces-sitate shorter notice and earlier transfer
- 6. Basis for response to Question 5, including
- a. PSE&G position on reprocessing as preferable to disposal
- b. PSE&G position on schedule for geologic repository
- c. PSE&G position with regard to advance notice of transfer of spent fuel, including contract conditions
- d. PSE&G position on fee structure for away-from-reactor storage including transportation and separate fee for geologic disposal
- e. PSE&G position on technical design bases for repository
- 7. Basis for response to Question 6, including
- a. PSE&G position with regard to determination of fee for interim offsite storage and geological repository storage
- 8. Bases for response to Question 7, including
- a. PSE&G position with regard to change in title associated with disposal of fuel and subsequent liability 59 012
- b. PSE&G position regarding disposal fee reflecting the right of a utility to recover its spent fuel Respectfully submitted, CONNER, MOORE & CORBER Mark J. Wetterhahn Counsel for the Licensee April 25, 1979 2259 013 O
UNITED STATES 05' AMERICA NUCLEAR REGULATORY COMMISSION Before the' Atomic Safety and Licensing Board In the Matter of )
)
PUBLIC SERVICE ELECTRIC AND GAS ) Docket No. 50-272 COMPANY, et al. ) (Proposed Issuance of
- ) Amendment to Facility (Salem Nuclear Generating . ) Operating License Station, Unit 1) ) No. DPR-70)
CERTIFICATE OF SERVICE I hereby certify that copies of " Licensee's outline of Cross-rvamdnation," dated April 25, 1979, in the captioned matter, have been served upon the following by deposit in the United States m il this 25th day of April, 1979:
Gary L. Milhnllin, Esch. chai man, Atomic Safety and ch=4 man _, Atomic Safety Licensing Board Panel and Licensing Board U.S. Nuclear Regulatory 1815 Jefferson Street Ccmmission
. . . . , _ Madison, Wisconsin 53711 Washington, D.C. 20555 - .
Mr Lester Kornblith, Jr. Barry Smith, Esq.
Ma har, Atomic Safety and Office of the Executive Licensing Board Panel. Legal Director U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Ccamission Washington, D.C. 20555 Washington, D.C. 20555 Dr. James C. Lamb, III Richard Hluchan, Esq.
Member, Atomic Safety and Deputy Attorney General Licensing Board Panel Department of Law and 313 Woodhaven Road Public Safety Chapel Hill, N.C. 27514 Envireamental Protection Section Chair: nan, At:omic Safety and 36 West State Street Licensing Appeal Board Panel Trenton, N.J. 08625 U.S. Nuclear Regulatory
'o.umission Washington, D.C. 20555 2259 014
Richard Fryling, Jr., Esq. Carl Valore, Jr., Esq.
Assistant General Solicitor. Valore, McAllister, Aron Public Service Electric & Westmoreland
& Gas Company Mainland Professional Plaza 80 Park Place P. O. Box 175
. Newark, N. J. 07101 Northfield, N. J. 08225 Keith Onsdorff, Esq. Office of the Secretary Assistant Deputy Public Advocate Docketing and Service Section Department of the Public Advocate U.S. Nuclear Regulatory Division of Public Interest Commission Advocacy. Washington, D. C. 20555 Post Office Box 141 Trenton, N. J. 08601 June D. MacArtor, Esq. -
Deputy Attorney General Sandra T. Ayres, Esq. Tatnall Building, P. O. Box 1401 Department of the Public Advocate Dover, Delaware 19901 520 East State Street Trenton, N. J. 08625 Mr. Alfred C. Coleman, Jr.
Mrs. Eleanor G. Coleman 35 "K" Drive Pennsville, New Jersey 08070 1
A b M7#
Marx J. @ tterbahn 2259 015