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Category:INTERVENTION PETITIONS
MONTHYEARML20203G7821999-02-16016 February 1999 Petition of Local 369 & 387,Utility Workers Union of America,AFL-CIO for Leave to Intervene & Request Hearing.* Requests That Hearing Be Scheduled on Commission Consideration to Approve Transfer.With Certificate of Svc ML20045D2271993-06-0808 June 1993 Response of Boston Edison Co to Ma Atty General Request for Hearing & Petition to Intervene.* W/Certificate of Svc & Notices of Appearance ML20045D2201993-06-0808 June 1993 Response of Boston Edison Co to Commonwealth of Ma Atty General Request for Hearing & Petition to Intervene.* Util Will Defer Further Response Until Petitioner Files Suppl Re Specific Contentions.Certificate of Svc Encl ML20045A6721993-05-27027 May 1993 State of Ma Atty General Request for Hearing & Petition to Intervene Re Plant Proposed Amend to License DPR-35 Increasing Allowed Fuel Assembly Storage Cells.* W/Certificate of Svc ML20128M4031985-07-19019 July 1985 Response Opposing Jf Doherty 850629 Petition for Leave to Intervene in Facility Proceeding.Petition Should Not Be Granted Due to Failure to File in Timely Fashion ML20129D3071985-07-12012 July 1985 Answers Opposing Petition of Jf Doherty for Leave to Intervene & Request for Hearing.Doherty Has Not Stated One Good Contention.W/Certificate of Svc ML20082F8251983-11-21021 November 1983 Response to Jf Doherty 831103 Suppl to 830930 Petition for Leave to Intervene in Proceeding Re Amend for Loop 1 Operation.Petitioner W/O Standing But Contentions Would Be Admissible.Certificate of Svc Encl ML20081J7391983-11-0303 November 1983 Suppl to 830930 Petition of Jf Doherty for Leave to Intervene & Request for Hearing on Licensee Request for License Amend Permitting Single Loop Operation.Certificate of Svc Encl ML20078D2951983-09-30030 September 1983 Petition of Jf Doherty to Intervene & Request for Hearing on Util Requested Amend to License DPR-35 Re Operation W/One Recirculation Loop Out of Svc.Certificate of Svc Encl ML20050C1721982-04-0202 April 1982 Brief Supporting Petition to Intervene in Proceeding to Modify Ol.No Precedent Exists for Licensee & NRC Position That State of Ma Atty General Must Oppose Amend to Claim Requisite Standing.Certificate of Svc Encl ML20050H5341982-03-29029 March 1982 Petition to Intervene in Proceeding ML20049H5271982-02-26026 February 1982 Response Opposing Ma Atty General 820217 Petition to Intervene in OL Mod Proceeding.No Proceeding Exists in Which to Intervene 1999-02-16
[Table view] Category:RESPONSES & CONTENTIONS
MONTHYEARML20203G7821999-02-16016 February 1999 Petition of Local 369 & 387,Utility Workers Union of America,AFL-CIO for Leave to Intervene & Request Hearing.* Requests That Hearing Be Scheduled on Commission Consideration to Approve Transfer.With Certificate of Svc ML20045D2271993-06-0808 June 1993 Response of Boston Edison Co to Ma Atty General Request for Hearing & Petition to Intervene.* W/Certificate of Svc & Notices of Appearance ML20045D2201993-06-0808 June 1993 Response of Boston Edison Co to Commonwealth of Ma Atty General Request for Hearing & Petition to Intervene.* Util Will Defer Further Response Until Petitioner Files Suppl Re Specific Contentions.Certificate of Svc Encl ML20045A6721993-05-27027 May 1993 State of Ma Atty General Request for Hearing & Petition to Intervene Re Plant Proposed Amend to License DPR-35 Increasing Allowed Fuel Assembly Storage Cells.* W/Certificate of Svc ML20128M4031985-07-19019 July 1985 Response Opposing Jf Doherty 850629 Petition for Leave to Intervene in Facility Proceeding.Petition Should Not Be Granted Due to Failure to File in Timely Fashion ML20129D3071985-07-12012 July 1985 Answers Opposing Petition of Jf Doherty for Leave to Intervene & Request for Hearing.Doherty Has Not Stated One Good Contention.W/Certificate of Svc ML20082F8251983-11-21021 November 1983 Response to Jf Doherty 831103 Suppl to 830930 Petition for Leave to Intervene in Proceeding Re Amend for Loop 1 Operation.Petitioner W/O Standing But Contentions Would Be Admissible.Certificate of Svc Encl ML20081J7391983-11-0303 November 1983 Suppl to 830930 Petition of Jf Doherty for Leave to Intervene & Request for Hearing on Licensee Request for License Amend Permitting Single Loop Operation.Certificate of Svc Encl ML20078D2951983-09-30030 September 1983 Petition of Jf Doherty to Intervene & Request for Hearing on Util Requested Amend to License DPR-35 Re Operation W/One Recirculation Loop Out of Svc.Certificate of Svc Encl ML20050C1721982-04-0202 April 1982 Brief Supporting Petition to Intervene in Proceeding to Modify Ol.No Precedent Exists for Licensee & NRC Position That State of Ma Atty General Must Oppose Amend to Claim Requisite Standing.Certificate of Svc Encl ML20050H5341982-03-29029 March 1982 Petition to Intervene in Proceeding ML20049H5271982-02-26026 February 1982 Response Opposing Ma Atty General 820217 Petition to Intervene in OL Mod Proceeding.No Proceeding Exists in Which to Intervene 1999-02-16
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20216F4891999-09-17017 September 1999 Comment Supporting NEI Comments Re Proposed Rules 50 & 72 Re Certain Reporting Requirements for Nuclear Power Reactors. Expresses Concern Re Proposed Reporting Requirement 10CFR50.73(a)(2)(ii)(c) Re Significantly Degraded Component ML20206A0541999-04-26026 April 1999 Memorandum & Order.* All Petitioners to Intervene Have Withdrawn Their Petition,Proceeding Terminated.With Certificate of Svc.Served on 990426 ML20205S0031999-04-23023 April 1999 Affidavit of JW Yelverton Supporting Proposed License Transfer & Conforming Amends.Util Requests That Designated Documents Be Withheld from Public Disclosure,Per 10CFR2.790 (a)(4) & 10CFR9.17(a)(4) ML20203G7821999-02-16016 February 1999 Petition of Local 369 & 387,Utility Workers Union of America,AFL-CIO for Leave to Intervene & Request Hearing.* Requests That Hearing Be Scheduled on Commission Consideration to Approve Transfer.With Certificate of Svc ML20153C1411998-09-20020 September 1998 Comment on Proposed Rule 10CFR2 & 51 on Subpart M Re Transfer of Operating License ML20100M5251996-03-0101 March 1996 Comment on Proposed Rule 10CFR20 Re Rept Requirements for Unauthorized Use of Licensed Radioactive Matl.Proposed Rule Change Wording Concerning What Conditions Must Be Met to Require Reporting Inexact ML20101B9931996-03-0101 March 1996 Comment Opposing Proposed Rule 10CFR20 Re Reporting Requirements for Unauthorized Use of Licensed Radioactive Matls BECO-95-125, Comment Supporting Pr 10CFR60,72,73 & 75 Re Safeguards for Spent Nuclear Fuel1995-12-14014 December 1995 Comment Supporting Pr 10CFR60,72,73 & 75 Re Safeguards for Spent Nuclear Fuel ML20093B5971995-10-0303 October 1995 Comment on Proposed Bulletin 95-XX & Reg Guide DG-1038, Debris Clogging of BWR ECCS Suction Strainers. Endorses BWROG Comments ML20086A8791995-06-14014 June 1995 Comment Supporting Proposed Rule 10CFR73 Re NRC Initiative to Eliminate Requirement to Post Security at Primary Containment Entrance During Refueling & Major Maint Periods ML20082Q5511995-04-21021 April 1995 Comment on Proposed Rules 10CFR170 & 171 Re Fee Schedules for FY95 Revisions.Endorses NEI Comments ML20082M3251995-04-14014 April 1995 Comment Supporting Proposed Draft Policy Statement Re Freedom of Employees in Nuclear Industry to Raise Concerns W/O Fear of Retaliation ML20078L2151995-02-0303 February 1995 Comment Opposing Proposed Rule 10CFR50 Re Shutdown & Low Power Operations for Nuclear Power Reactors ML20078S6631994-12-19019 December 1994 Comment Supporting Proposed GL Re Reconsideration of NPP Security Requirements for an Internal Threat ML20076L2561994-10-24024 October 1994 Comments on Proposed Rule 10CFR2 Re Reexamination of NRC Enforcement Policy.Endorses Response Submitted by Nuclear Energy Institute ML20062M4241994-01-0303 January 1994 Comment Supporting NUMARC Position on Proposed Rule Re Protection Against Malevolent Use of Vehicles at NPPs ML20059C3721993-12-29029 December 1993 Exemption from DAC Values for Kr-89 & Xe-137 in Table 1 of App a to 10CFR20.Approves Use of Proposed Values in Request When Determining Whether Area Requires Posting as Airborne Radioactivity Area BECO-93-166, Comment Supporting NUMARC Petition for Rulemaking to Amend 10CFR21,PRM 21-21993-12-28028 December 1993 Comment Supporting NUMARC Petition for Rulemaking to Amend 10CFR21,PRM 21-2 ML20058P1811993-12-14014 December 1993 Director'S Decision 93-20 Denying Petition to Delaying Startup Until Hardware Modifications Designed to Eliminate Errors in Reactor water-level Measurement Made ML20058D6561993-11-19019 November 1993 Director'S Decision Under 10CFR2.206 Denying Petition Requesting That NRC Reconsider 910730 Decision Giving Unanimous Approval of Task Force Recommendation Re Reasonable Assurance Finding Re EP for Plant ML20057C0951993-09-13013 September 1993 Memorandum & Order (Termination of Proceeding).* Informs of Petitioner Withdrawal of Motion to Intervene & Request for Hearing,Therefore Board Terminates & Dismisses Proceeding Herein.W/Certificate of Svc.Served on 930914 ML20057C1281993-09-13013 September 1993 Memorandum & Order (Termination of Proceeding).* W/Certificate of Svc.Served on 930916 ML20057A1531993-09-0202 September 1993 NRC Staff Response to Ma Atty General Withdrawal of Motion to Intervene & Request for Hearing.* NRC Does Not Object to Atty General Withdrawal.Licensing Board Should Issue Order Dismissing Proceeding.W/Certificate of Svc ML20056G5081993-08-26026 August 1993 Commonwealth of Ma Atty General Withdrawal of Motion to Intervene & Request for Hearing.* W/Certificate of Svc ML20056E6871993-08-13013 August 1993 Memorandum & Order (Extension of Time).* Petitioner Suppl W/ Contentions Should Be Filed by 930827 & Licensee Response to Suppl Should Be Filed within 10 Days Thereafter.W/ Certificate of Svc.Served on 930813 ML20046D0251993-08-11011 August 1993 Joint Motion to Extend Date for Filing Petitioners Contentions.* Parties Jointly Request That Board Extend Date for Filing Petitioner Contentions from 930813 to 930827. W/Certificate of Svc ML20056C8601993-07-16016 July 1993 Memorandum & Order (Extension of Time).* Petitioner Suppl W/ Contentions Should Be Filed by 930813,util Response to Suppl within 10 Days After Svc & NRC Response to Suppl within 15 Days After Svc.W/Certificate of Svc.Served on 930719 ML20056C8971993-07-15015 July 1993 Joint Motion to Extend Date for Filing Petitioners Contentions.* W/Certificate of Svc ML20045D2201993-06-0808 June 1993 Response of Boston Edison Co to Commonwealth of Ma Atty General Request for Hearing & Petition to Intervene.* Util Will Defer Further Response Until Petitioner Files Suppl Re Specific Contentions.Certificate of Svc Encl ML20045D2271993-06-0808 June 1993 Response of Boston Edison Co to Ma Atty General Request for Hearing & Petition to Intervene.* W/Certificate of Svc & Notices of Appearance ML20045A6721993-05-27027 May 1993 State of Ma Atty General Request for Hearing & Petition to Intervene Re Plant Proposed Amend to License DPR-35 Increasing Allowed Fuel Assembly Storage Cells.* W/Certificate of Svc ML20045A6741993-05-27027 May 1993 Notice of Appearance.* Notice of Appearance of Undersigned for State of Ma Atty General BECO-92-135, Comments on Proposed NRC Generic Communication,Augmented Inservice Insp Requirements for Mark I & Mark II Steel Containments,Refueling Cavities & Associated Drainage Sys1992-12-21021 December 1992 Comments on Proposed NRC Generic Communication,Augmented Inservice Insp Requirements for Mark I & Mark II Steel Containments,Refueling Cavities & Associated Drainage Sys ML20115A6581992-10-0505 October 1992 Comments on Proposed Changes to SALP Program BECO-92-073, Comment Opposing Draft Rev 3 to Reg Guide 01.0091992-07-10010 July 1992 Comment Opposing Draft Rev 3 to Reg Guide 01.009 BECO-92-072, Comment Supporting Proposed Rule 10CFR50 Re Receipt of Byproduct & SNM1992-07-10010 July 1992 Comment Supporting Proposed Rule 10CFR50 Re Receipt of Byproduct & SNM ML20086K8791991-10-31031 October 1991 Petitions Commission to Reconsider 910730 Approval of Task Force Recommendation Stating That NRC Did Not Need to Reconsider NRC Reasonable Assurance Finding Re Emergency Preparedness for Pilgrim Station ML20135A4581991-06-12012 June 1991 Transcript of 910612 Meeting in Plymouth,Ma Re Pilgrim Task Force Public Hearing.Pp 1-148.W/certificate & Title Page BECO-91-067, Comment Opposing Proposed Rules 10CFR71,170 & 171, Rev of Fee Schedules;100% Fee Recovery1991-05-13013 May 1991 Comment Opposing Proposed Rules 10CFR71,170 & 171, Rev of Fee Schedules;100% Fee Recovery ML19332G5121989-12-0101 December 1989 Comment on Draft Reg Guide,Task DG-1001, Maint Programs for Nuclear Power Plants. Util Endorses Nuclear Power Industry Comments & NUMARC Position ML20235A9561988-12-0909 December 1988 Transcript of 881209 Meeting in Rockville,Md W/Public Officials Having Responsibility for Emergency Planning for Pilgrim Nuclear Power Plant.Related Info Encl.Pp 1-185 ML20205E1531988-10-14014 October 1988 Transcript of 881014 Meeting in Rockville,Md Re Discussion/ Possible Vote on Facility Restart.Pp 1-104.Supporting Documentation Encl ML20155D9391988-10-0505 October 1988 Second Interim Director'S Decision DD-88-17 Under 10CFR2.206 Re Request for Proceeding to Modify,Suspend or Revoke Ol.Portion of Petition Re Mgt Issues Denied.Portion Re Emergency Preparedness Issues to Be Addressed Later ML20205J3531988-10-0505 October 1988 Transcript of 881005 Meeting in Rockville,Md Re Status of Readiness for Restart of Facility.Pp 1-94 ML20206G9181988-09-29029 September 1988 Transcript of NRC 880929 Technical Meeting in Plymouth,Ma Re Review of Proposed Restart of Facility & NRC 881005 Meeting W/Util in Rockville,Md Re Readiness of Restart ML20153H0381988-08-26026 August 1988 Transcript of ACRS Ad Hoc Subcommittee on Pilgrim Restart 880826 Meeting in Plymouth,Ma.Pp 1-232.Related Documentation Encl ML20235T8761988-08-25025 August 1988 Rev 0 to Pilgrim Station Evacuation Time Estimates & Traffic Mgt Plan Update.* Apps A,B & M Encl ML20235T7301988-08-15015 August 1988 Rev 4 to Massachussetts Civil Defense Agency Area II Radiological Emergency Response Plan for Pilgrim Nuclear Power Station.* ML20235T6901988-07-28028 July 1988 Rev 5 to City of Taunton Radiological Emergency Response Plan for Pilgrim Nuclear Power Station.* Related Info Encl ML20247N7531988-07-28028 July 1988 Petition for Rulemaking PRM-50-53 Requesting NRC Action to Review Undue Risk Posed by BWR Thermal Hydraulic Instability.Nrr Should Issue Order Requiring All GE BWRs to Be Placed in Cold Shutdown for Stated Reasons 1999-09-17
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1 a Novambar3,1983 l U$1TED STATES OF AMERICA 00CKETED NUCLEAR REGULATORY COMMISSION UMU BEFORE THE ATOMIC SAFETY AND LICENSING BOARD Qg -
In the Matter of: }
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Boston Edison Company ) 0FFlncp3ccy,r,j-[
00CXETrus g, scp.,,
(Pilgrim Nuclear Power Station, Docket No. 50-293 -OLA MANCH Unit 1) )
)
JOHN F. DOHERTY'S SUPPLEMENT.TO HIS PETITION FOR LEAVE TO INTERVENE On September 30, 1983, this Petitioner filed a " Request for a Hearing end Petition for Leave to Intervene" in response to the Applicant's (Licensee) request for an amendment to its operating license to permit eingle loop operation. The Licensee responded on0ctober 17, 1983, and the Staff on October 20, 1983. The Licensee also requested the Chair of the ASLB Panel appoint an ASLB for this Amendment, but urged denial of the Petition for lack of standing. The Staff, in its response supported the Petition, stating this Petitioner did have standing under the Commission's case law, but that this Petitioner must supplement his Petition with Con-tentions, pursuant to 10 CFR 2.714(a)(2).
Hence, this Supplement is filed pursuant to 10 CFR 2.714(a)(2).
Contentions
- 1. Licensee's technical specifications for operation with single loop in operation should include limits on the core plate pressure drop. Such l
j a limit would permit better regulation of core flow, leading to less variable l
within core coolant flow yielding more even cross-core power. The appli-l cation for a 50% power operation during single loop operation of the l
Cooper Nuclear Station (50-298) as noticed in the Federal Register of Sep-l tember 15,1983 (pg. 41537) sets such limits.
l l
- 2. If granted the right to operate "in excess of 70% rated power with on re-circulation pump out of service", the Licensee would have the first operating license right in Commission regulation not controlled by a stated power rating. The amendment has no time limit. The Board should require Licensee to 0311090099 831103 DR ADOCK 05000293 eda 9 93
2-
! operate at a stated power rating during single loop operation, which if exceeded would require shutdown, because: ,
A. Instrument drift or other malfunction may give false readings in the Average Power Range Monitors such that the plant operates above the power it is assumed operating; B. The Minimum Critical Power Ration (MCPR) for single loop operation for this plant is 1.08, which is 0.16 lower than for BWR 5, and BWR 6, reactors. Because of set-point drift in the APRMs and operator errors in reading these monitors, inadvertent operation at MCPR less than 1.07 is possible, and represents a hazard to the public safety because of i' fuel melting; C. The public is entitled to know through the Federal Register definite operating characteristics of the plant. The amendment says operation with one loop out of service at more than 458.5 MWe is allowed so long as APRM flux SCRAM trip and rod block settings are " appropriate" , Average Planar Linear Heat Generation Rate (APLHGR) are suitable and MCPR is higher than (presumably) two loop operation. By its language the proposed amendment is unclear, and does not put the public on notice as to what it proposes and how it may effect the public's Interests; D. At least one other plant, Cooper Nuclear Station (50-298), in its notice
- of amendment did so state a proposed power rating. ( 48 Fed. Reg 41,537, Sept. 15, I983).
- 3. As a condition of the license, the idle recirculation loop must be fully inoper-able, not merely out of service, because the danger of inadvertant start-up is present. Inadvertent start-up with the other recirculation pump running and producing in excesss of 70% rated power for the reactor would result in an overpower transient, exceeding the technical specifications for the plant for two recirculation loop operation, leading to fuel damage.
- 4. In event of a Loss of Coolant Accident (LOCA) due to recirculation line break in the operating loop, the operators of the plant would loose the option of supplying water to the core through the recirculation system if ECCS system failure or unavailability were to occur with the event.
- 5. The Licensee was recently ordered (September 2,1983) to shutdown by the Director of the Office of Nuclear Reactor Regulation because of suspected intergran-ular stress corrosion cracking (IGSCC) in the recirculation system piping, Residual Heat Removal System, Core Spray System and Reactor Cleanup System.
(48 Fed. Reg. 40,035, Sept. 2, 1983) The Applicant should be required to e e b -e di ,e.. mm e4
- - - , .- - - - , - - , ,.,y =-- 9.py,,,ym ~. - _ . _ _ _ - - - - - . p7nw-., . . - -,_r,, ,,g-g, 4 ,. ,,.-r-,- m.,, .,
show that bringing the plant to safe shutdown is is more easily achieved following a large pipe break in the single operating loop of the recir-culation system with the reactor operating in excess of 70% of rated power than if there is the same large pipe break with two operating loops and the BWR at 100% (655 MWE) power.
- 7. In the event of a stuck open relief valve which results in considerable water loss from the reactor, natural circulation, which is used to maintain cooling, will be less available, should the water loss accident occur
]
when a single recirculation loop is out of service. Applicant should be
- required to show how it can make up for the loss of ability to turn to natural circulation cooling in event of loss of water accidents such as the stuck open relief valve event, or a main steam line break.
I
- 8. Operation of the Pilrrrim I with single loop oneration un-necessarily increases the effects of a pumo seizure event.
In this event, coolant wculd heat up and reduced flow vould cause steam blanketinr before core heat outout i could decline causing fuel rod crumble and melting. The danger differs in two loop operation, where the remaining pump in operation would urevent steam' blanketing. The basis for this Contention is in Accident Hazards of Atomic Power Plants, by Richard Webb, U. Massachusetts Press., 1976.,
- p. 32.
- 9. Single loop operation, in excess of 70% power, in event of a fast transient (for example, turbine trip) is more hazardous i
than two loop operation, because single loop operation will p aggrivate the strong variability seen in axial flow rate within a BWR fuel channel, causing the critical power ratio j
(CPR) to become too low and leading to fuel heat up with -
j consecuent departure from nucleate boiling. Oneration with single loop urcvides a non-uniform flow in the fuel channels which aggrivate the observed variability. That there is strong variability seen axially in flow rate in.BWR fuel channels is based on an article: " Critical Power Ratio in BWR Transient Analyses," in the Transactions of the American Nuclear Society, 33, Hov. 1979, p. 476-7.
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- 10. Operation in excess of 70% power with single loop operation will re-quire reduced oper.ating temperature. In the event of a pressure transient with an Anticipated Transient without SCRAM (AIWS) the !
reactor pressure vessel will be in a less ductile state when it encoun-ters the increased pressure and hence more open to fracture. Appli-
-cant should be required to show that here is suffficient margin in the reactor pressurve vessel to maintain integrity under pres-sure transient conditions (turbine trip, turbine trip without ,
bypass, steam line valve closure) and failure to SCRAM to avoid reactor pressure vessel fracture.
- 11. Single loop operation at in excess of 70% power is hazardous to this Petitioner's safety interest because reduced flow will cause !
recovery from a loss of feedwater heater transient to be of longer duration than with two loop operation. A loss of feed water heater transient may last long enough with two loop operation for pellet-clad interaction failure to occur, so with single loop operation, this ,
prospect increases in magnitude. A basis for this contention is '
provided in the. contents .of a document which this Petitioner' fs under f
a Prot.ective Order not to reveal. This Petitioner requests -
instructions from the Board in how protected information may be used $
as the basis for a Contention.
E
~
k Respectfully Submitted,
& l:-
ohn F. Doherty 9 Petitioner, pro se i
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e - - - , - - - --m--- e -
DOLKETED UNITED STATES OF AMERICA Mc NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD OFF1CE OF SECRt!A -
In the Matter of .
DOCKETygtpyd.r Boston Edison Company Docket No. 50-293
)l (Pilgrim Nuclear Power Station Unit 1) ))
CERTIFICATE OF SERVICE I certify that cocies of " JOHN F. DOHERTY'S SUPPLEMEIT TO 5 HIS PETITION FOR LEAVE TO INTERVENE" werp served via -
First Class U. S. Postal Service, this3tS of November, 1983, from Boston, Massachusetts. .
{
Thomas Dignan, Esq.
Ropes & Gray Docketing and Service Section 225 Franklin. Street Office of the Secretary E Boston, MA 02110 U.S. Nuclear Regulatory Commission f Washington, DC 20555 .
~
Atomic Safety arid Licensing Appeal [
Board Panel i U.S. Nuclear Regulatory Comission I B. PaulSafety
' Atomic Cotcer, and Jr.
Licens,ingChairman Board Washington, DC 20555 ?
Panel i U.S. Nuclear Regulatory Commission Elaine Chan , Esc. ' !
Washington, DC 20555 Staff Cohn'sel E U. S. Nuclear Regulatory Comm. I Dr. Oscar H. Paris Washington D. C. 20555 [
!
- Atomic Sa'ety and Licensing Board U. S. Nuclear Regulatory Commission [
Washington D. C. 20555 i Gustave A. Linenberger, Jr.
Atomic Safety and Licensing Board P. B. Nuclear Regulatory Commission -~
Washington D. C. 20555 3 Respectfully, fh John F. Doh ty
, ,