|
---|
Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217P5261999-10-20020 October 1999 Forwards Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217E9841999-10-14014 October 1999 Forwards Petition for Leave to Intervene Submitted on 991006 by Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20216F3591999-09-15015 September 1999 Informs That Encl SRM on COMSECY-99-016 Being Released to Public,Effective 990915.Encl Documents Including 990406 SRM in Response to Millstone Independent Review Team 990312 Rept & 990713 Memo from G Caputo Previously Released ML20211K1431999-09-0202 September 1999 Notification of 990920 Meeting with Util in Rockville,Md to Discuss Recent Developments in New England Re Industry Deregulation & Restructuring Affecting Nu Use of Performance Indicators as Operating Plant ML20210U1461999-08-13013 August 1999 Notification of 990827 Meeting with NNECO in King of Prussia,Pennsylvania to Discuss Engineering Initiatives & Backlog Management ML20210E9311999-07-26026 July 1999 Notification of 990825 Public Meeting in Waterford,Ct Re PSDAR for Plant Unit 1 ML20210K1421999-07-22022 July 1999 Informs That Recipient Designated Chairman of Millstone Assessment Panel & E Adensam,Designated Co-Chairman.Panel Established to Assist Region I & NRR in Coordination of NRC Resources for Performance Monitoring & Inspecting Millstone ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20209G0541999-07-13013 July 1999 Submits Director'S Guidance 99-001,effective Immediately,As Result of SRM in Response to Recommendations in Plant Independent Review Team Rept, ML20212J5161999-07-0101 July 1999 Documents,For Public Record,Interaction Between NNECO & NRC Staff Re Licensee Proposed Licensing Action Now Being Reviewed by NRC Staff ML20209D7721999-06-29029 June 1999 Notification of 990715 Meeting 99-39 with Util in Waterford, CT Re Corrective Action & Safety Conscious Work Environ/ Employee Concerns Program Team Exit Meeting ML20209D7621999-06-29029 June 1999 Notification of Meeting 99-40 on 990715 with Nuclear Energy Advisory Council in Waterford,Ct to Discuss Millstone Safety Conscious Work Environ/Employee Concerns Program ML20212H9471999-06-22022 June 1999 Informs That No Addl Work Required on TACs M91735 & M95118 & Closes TACs Administratively ML20196F0581999-06-21021 June 1999 Discusses Update of Status of Petition,Dtd 961125,as Amended by Ltr,Dtd 961223,by Petitioners Re Millstone,Units 1,2 & 3 & Haddam Neck Nuclear Facilities ML20207F0951999-06-0404 June 1999 Forwards Figure 1 to Millstone Combined Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05.Rept e-mailed on 990604 IR 05000336/19990041999-05-10010 May 1999 Forwards Database Used by Licensee to Track Questions Asked During Osti,Insp Rept 50-336/99-04.Summary of Licensee Responses Also Provided ML20206A6041999-04-23023 April 1999 Notification of 990506 Meeting with Util in Rockville,Md to Provide Northest Nuclear Energy with Opportunity to Discuss Status of Development of post-shutdown Decommissioning Activities Rept for Unit 1 ML20206A1791999-04-22022 April 1999 Forwards Supplemental Info Related to Questions Re 50 Mile Ingestion Pathway Associated with Millstone Nuclear Facility That Were Raised During 990414 Commission Meeting on Remaining Issues Re Proposed Restart of Unit 2 DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20206B2371999-04-19019 April 1999 Forwards Questions & Answers Addressing Long Island Emergency Planning Issue Raised at Commission Meeting ML20205N1641999-04-0606 April 1999 Notification of Significant Licensee Meeting 99-18 with Util on 990420 in King of Prussia,Pa to Discuss Plant Unit 3 Outage Plans ML20205J1961999-03-31031 March 1999 Discusses Clarification of Enforcement Discussion in 990319 Millstone Independent Review Team Rept ML20205C3041999-03-23023 March 1999 Notification of Significant Meeting 99-15 on 990407 with NNECO in Waterford,Ct,To Discuss Operational Safety Team Insp Exit Meeting for Millstone,Unit 2 ML20205J2011999-03-15015 March 1999 Forwards Annotated Draft Info Notice 99-XX Re Inadvertent Discharge of Carbon Dioxide Fire Suppression Sys in Cable Spreading Room,Reflecting Util Changes ML20207H4601999-03-0404 March 1999 Notification of 990318 Meeting with Northeast Nuclear Energy Co in Waterford,Connecticut to Discuss Exit Meeting Results of Millstone Unit 2 Independent C/A Program C/A Insp Performed by NRR ML20207K4071999-03-0404 March 1999 Notification of Significant Licensee Meeting 99-11 with Util on 990318 in Waterford,Ct to Discuss Plans,Schedules & Progress Toward Recovery of Plant,Unit 2 ML20207K4011999-03-0404 March 1999 Rev 1 to Notification of Significant Meeting 99-12 with Util on 990318 in Waterford,Ct to Discuss Recovery of Millstone, Unit 2.Location of Meeting Has Been Changed ML20206U3581999-02-0303 February 1999 Notification of Significant Licensee Meeting 99-08 with Util on 990217 Re 40500 Corrective Action Team Exit Meeting ML20202H7791999-02-0202 February 1999 Forwards Draft Request for Addl Info Re Loss of Main Feedwater Transient Analysis ML20202H7171999-02-0202 February 1999 Forwards Draft RAI Re Reg Guide 1.97 Deviation Request Involving Containment Area Radiation ML20202H7591999-02-0101 February 1999 Forwards Draft Request for Addl Info Re Radiological Consequences of Steam Generator Tube Rupture ML20202E4391999-01-28028 January 1999 Forwards Draft RAI Transmitted by Facsimile on 990127 to R Joshi of Licensee Staff Re post-LOCA Long Term Cooling. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20204J6171999-01-27027 January 1999 Responds to 990107 Memo Re OI General Event Inquiry Case 99-01S,NRC Handling of Harassment & Intimidation Complaints at Millstone.Listed C/As Have Been or Will Be Taken ML20202E1461999-01-27027 January 1999 Forwards Draft RAI Re Application of Leak Before Break for Surge Line Sent 990125.Memo & Encl Does Not Convey Formal RAI or Represent NRC Position ML20202E4511999-01-27027 January 1999 Requests Arrangements for Conference Call with Licensee to Discuss Listed Items Re Facility Electrical Mods ML20202E4361999-01-27027 January 1999 Forwards Draft RAI Transmitted by Facsimile on 990127 to R Joshi of Licensee Staff Re post-LOCA Long Term Cooling. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20202E3941999-01-27027 January 1999 Forwards Draft RAI Re RG 1.97, Deviation Condensate Storage Tank Level. Memo & Encl Does Not Convey Formal Request for Info or Represent NRC Position ML20202E4081999-01-27027 January 1999 Forwards Draft RAI Re Loss of Normal Feedwater Flow.Memo & Encl Do Not Convey Formal Request for Info or Represent NRC Position ML20202E4201999-01-25025 January 1999 Requests Responses to Listed RAIs So Review Can Be Completed ML20199A4251999-01-11011 January 1999 Informs That Time within Which Commission May Act to Review Decision of ASLB (LBP-98-28) Dismissing Proceeding in Docket Has Expired.Commission Declined Any Review.Decision Became Final Agency Act on 981229.With Certificate of Svc ML20198Q8621998-12-30030 December 1998 Notification of 990209 Meeting with Util in Waterford,Ct to Discuss NRC Regulatory Programs Applicable to Decommissioning Activities.Agenda Encl ML20206R2521998-12-28028 December 1998 Notification of Significant Licensee Meeting 98-94 with Util on 990111 to Provide Public Update on Status of Millstone Unit 2 Recovery Efforts ML20206R2601998-12-28028 December 1998 Notification of Significant Licensee Meeting 98-93 with Util on 990111 to Discuss Plans,Schedules & Progress Toward Recovery of Millstone Unit 2 ML20198D8551998-12-16016 December 1998 Notification of 981229 Meeting with Util in Rockville,Md to Discuss Status of Staff Efforts to Develop Std TSs for Permanently Shut Down BWR Plants ML20196G0241998-12-0303 December 1998 Notification of 981214 Meeting in Waterford,Ct to Provide Update on Status of Millstone Employee Concerns Program & Safety-Conscious Work Environ Programs & Solicit Comments from Public Closing on 961024 Order ML20195D1171998-11-12012 November 1998 Notification of 981202 Meeting with Northeast Nuclear Energy in Rockville,Md to Brief NRC on Status of Plans for Decommissioning of Millstone Unit 1,including Potential Licensing Actions ML20195C9431998-11-10010 November 1998 Submits Revised Notification of 981124 Meeting with Util in Waterford,Ct Re NRC Evaluation of Plant Employee Concerns Program & safety-conscious Work Environ ML20195B6861998-11-10010 November 1998 Notification of 981124 Meeting with Listed Attendees in Waterford,Ct to Discuss Plant Employee Concerns Program, safety-conscious Work Environ & Lhc Findings & Recommendations ML20195C2321998-11-10010 November 1998 Notification of 981124 Meeting with Util in Waterford,Ct Re Exit Meeting for NRC Evaluation of Plant Employee Concerns Program & safety-conscious Work Environ 1999-09-02
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217J8951999-10-21021 October 1999 Staff Requirements Memo Re Affirmation Session on 991021, Rockville,Md (Open to Public Attendance) ML20217P5261999-10-20020 October 1999 Forwards Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217E9841999-10-14014 October 1999 Forwards Petition for Leave to Intervene Submitted on 991006 by Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone ML20217D3601999-10-13013 October 1999 Staff Requirements Memo on SECY-99-223 Re Millstone Independent Review Team 990312 Rept on Allegations of Discrimination in NRC Ofc of Investigation Cases Nda: 1-96-002,1-96-007 & 1-97-007 & Associated Recommendation 6 ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20216F3591999-09-15015 September 1999 Informs That Encl SRM on COMSECY-99-016 Being Released to Public,Effective 990915.Encl Documents Including 990406 SRM in Response to Millstone Independent Review Team 990312 Rept & 990713 Memo from G Caputo Previously Released ML20211K1431999-09-0202 September 1999 Notification of 990920 Meeting with Util in Rockville,Md to Discuss Recent Developments in New England Re Industry Deregulation & Restructuring Affecting Nu Use of Performance Indicators as Operating Plant ML20210U1461999-08-13013 August 1999 Notification of 990827 Meeting with NNECO in King of Prussia,Pennsylvania to Discuss Engineering Initiatives & Backlog Management ML20210E9311999-07-26026 July 1999 Notification of 990825 Public Meeting in Waterford,Ct Re PSDAR for Plant Unit 1 ML20210K1421999-07-22022 July 1999 Informs That Recipient Designated Chairman of Millstone Assessment Panel & E Adensam,Designated Co-Chairman.Panel Established to Assist Region I & NRR in Coordination of NRC Resources for Performance Monitoring & Inspecting Millstone ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20209G0541999-07-13013 July 1999 Submits Director'S Guidance 99-001,effective Immediately,As Result of SRM in Response to Recommendations in Plant Independent Review Team Rept, ML20216F3651999-07-0707 July 1999 Staff Requirements Memo Re COMSECY-99-016, Recommendations 2 & 3 of Mirt,Re Witness Credibility & OI Conclusions,Staff Requirements Memo ML20212J5161999-07-0101 July 1999 Documents,For Public Record,Interaction Between NNECO & NRC Staff Re Licensee Proposed Licensing Action Now Being Reviewed by NRC Staff ML20209D7721999-06-29029 June 1999 Notification of 990715 Meeting 99-39 with Util in Waterford, CT Re Corrective Action & Safety Conscious Work Environ/ Employee Concerns Program Team Exit Meeting ML20209D7621999-06-29029 June 1999 Notification of Meeting 99-40 on 990715 with Nuclear Energy Advisory Council in Waterford,Ct to Discuss Millstone Safety Conscious Work Environ/Employee Concerns Program ML20212H9471999-06-22022 June 1999 Informs That No Addl Work Required on TACs M91735 & M95118 & Closes TACs Administratively ML20196F0581999-06-21021 June 1999 Discusses Update of Status of Petition,Dtd 961125,as Amended by Ltr,Dtd 961223,by Petitioners Re Millstone,Units 1,2 & 3 & Haddam Neck Nuclear Facilities ML20207F0951999-06-0404 June 1999 Forwards Figure 1 to Millstone Combined Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05.Rept e-mailed on 990604 ML20212A8181999-05-25025 May 1999 Staff Requirements Memo Re SECY-99-010, Closure of Order Requiring Third-Party Oversight of Northeast Nuclear Energy Implementation of Resolution of Millstone Station Employee Safety Concerns IR 05000336/19990041999-05-10010 May 1999 Forwards Database Used by Licensee to Track Questions Asked During Osti,Insp Rept 50-336/99-04.Summary of Licensee Responses Also Provided ML20206B2261999-04-28028 April 1999 Staff Requirements Memo Re Briefing on Remaining Issues Related to Proposed Restart of Millstone Unit 2 (SECY-99-109) on 990414 in Rockville,Md.Briefing Open to Public Attendance ML20206B9511999-04-28028 April 1999 Staff Requirements Memo Re Briefing on Remaining Issues Concerning Proposed Restart of Millstone Unit 2 (SECY-99-109) on 990414 in Rockville,Md (Open to Public) ML20206B2501999-04-28028 April 1999 Staff Requirements Memo Re SECY-99-109,recovery of Millstone Nuclear Power Station,Unit 2.Commission Agreed with Staff Conclusions That Nene Satisfied 960814,independent Corrective Action Verification Program Order ML20206A6041999-04-23023 April 1999 Notification of 990506 Meeting with Util in Rockville,Md to Provide Northest Nuclear Energy with Opportunity to Discuss Status of Development of post-shutdown Decommissioning Activities Rept for Unit 1 ML20206A1791999-04-22022 April 1999 Forwards Supplemental Info Related to Questions Re 50 Mile Ingestion Pathway Associated with Millstone Nuclear Facility That Were Raised During 990414 Commission Meeting on Remaining Issues Re Proposed Restart of Unit 2 DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20206B2371999-04-19019 April 1999 Forwards Questions & Answers Addressing Long Island Emergency Planning Issue Raised at Commission Meeting ML20205H7291999-04-0606 April 1999 Staff Requirements Memo in Response to Millstone Independent Review Team 990312 Rept on Allegations of Discrimination in NRC Office of Investigations Cases 1-96-002,1-96-007, 1-97-007 & Associated Lessons Learned ML20205H7501999-04-0606 April 1999 Staff Requirements Memo in Response to EDO Memo Re OIG Inquiry,Case 99-01S & Remaining Issues from SECY-98-292.Commission Approved C/As Described in EDO Memo ML20205N1641999-04-0606 April 1999 Notification of Significant Licensee Meeting 99-18 with Util on 990420 in King of Prussia,Pa to Discuss Plant Unit 3 Outage Plans ML20205J1961999-03-31031 March 1999 Discusses Clarification of Enforcement Discussion in 990319 Millstone Independent Review Team Rept ML20205C3041999-03-23023 March 1999 Notification of Significant Meeting 99-15 on 990407 with NNECO in Waterford,Ct,To Discuss Operational Safety Team Insp Exit Meeting for Millstone,Unit 2 ML20205J2011999-03-15015 March 1999 Forwards Annotated Draft Info Notice 99-XX Re Inadvertent Discharge of Carbon Dioxide Fire Suppression Sys in Cable Spreading Room,Reflecting Util Changes ML20207G0521999-03-0909 March 1999 Staff Requirements Memo on SECY-99-010 Re Closure of Order Requiring independent,third-party Oversight of Northeast Nuclear Energy Co Implementation of Resolution of Millstone Station Employees Safety Concerns ML20207K4071999-03-0404 March 1999 Notification of Significant Licensee Meeting 99-11 with Util on 990318 in Waterford,Ct to Discuss Plans,Schedules & Progress Toward Recovery of Plant,Unit 2 ML20207K4011999-03-0404 March 1999 Rev 1 to Notification of Significant Meeting 99-12 with Util on 990318 in Waterford,Ct to Discuss Recovery of Millstone, Unit 2.Location of Meeting Has Been Changed ML20207H4601999-03-0404 March 1999 Notification of 990318 Meeting with Northeast Nuclear Energy Co in Waterford,Connecticut to Discuss Exit Meeting Results of Millstone Unit 2 Independent C/A Program C/A Insp Performed by NRR ML20203H1441999-02-19019 February 1999 Staff Requirements Memo Re Briefing on Status of Third Party of Oversight of Millstone Station Employee Concerns Program & Safety Conscious Work Environment on 990119 in Rockville,Md ML20206U3581999-02-0303 February 1999 Notification of Significant Licensee Meeting 99-08 with Util on 990217 Re 40500 Corrective Action Team Exit Meeting ML20202H7171999-02-0202 February 1999 Forwards Draft RAI Re Reg Guide 1.97 Deviation Request Involving Containment Area Radiation ML20202H7791999-02-0202 February 1999 Forwards Draft Request for Addl Info Re Loss of Main Feedwater Transient Analysis ML20202H7591999-02-0101 February 1999 Forwards Draft Request for Addl Info Re Radiological Consequences of Steam Generator Tube Rupture ML20202E4391999-01-28028 January 1999 Forwards Draft RAI Transmitted by Facsimile on 990127 to R Joshi of Licensee Staff Re post-LOCA Long Term Cooling. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20204J6171999-01-27027 January 1999 Responds to 990107 Memo Re OI General Event Inquiry Case 99-01S,NRC Handling of Harassment & Intimidation Complaints at Millstone.Listed C/As Have Been or Will Be Taken ML20202E4081999-01-27027 January 1999 Forwards Draft RAI Re Loss of Normal Feedwater Flow.Memo & Encl Do Not Convey Formal Request for Info or Represent NRC Position ML20202E1461999-01-27027 January 1999 Forwards Draft RAI Re Application of Leak Before Break for Surge Line Sent 990125.Memo & Encl Does Not Convey Formal RAI or Represent NRC Position ML20202E3941999-01-27027 January 1999 Forwards Draft RAI Re RG 1.97, Deviation Condensate Storage Tank Level. Memo & Encl Does Not Convey Formal Request for Info or Represent NRC Position ML20202E4511999-01-27027 January 1999 Requests Arrangements for Conference Call with Licensee to Discuss Listed Items Re Facility Electrical Mods ML20202E4361999-01-27027 January 1999 Forwards Draft RAI Transmitted by Facsimile on 990127 to R Joshi of Licensee Staff Re post-LOCA Long Term Cooling. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI 1999-09-02
[Table view] |
Text
. _. _ . . _ . . _ - _ .
_., ~.
l l
i g.. +"* ,~
L_, . . '....
, e '
i
.- u :
.yf a ,
y ,
l ICC:vb .
1/4/66 MMORANDWI - .,
To a Files Free : M. C. Caske. ACES Staff Subjoet: DEL-MILLSTOE POINT METIM AT 55758D4, MARYL&MD W l'2 * '
- O. ,
MCRieER 22 AND 23, 1M S' y Yd@[.
j Pf . Mv 4th. ,.
g;3 ,
Thie neeties was the first between M111stene Point representati ,c t-the DEL Staff regarding the "Desige and Analysis Report" which %
sitted aloeg with the application for a sometruction permit for .the%" ~ . g, M111steen Point toester. Copies ef the "Deatga and Analysis- Report" were forwarded to Committee Members em Nevee6cr 18, IMS. present at ,
this meeting were the following g M111 stems Point M. C. Caska, Staff 1. J. Cee, Caesultest R. A. Evans Division of Roseter Licensian- R. Riebsk E. R. Nine R. 8. Boyd LA. W. Wofford E. G. Case R. L. Deem b Ceneral Electrie Co.
'h ..
Irg g .v. s. Blase ~
- 1. 8l C. J. Black D. F. Sullivan' L..F. Fidryeh R. L. fedeces M.LFreshet W. D. Gilbert :
i Divistae of Safety Standards. C. 5. Johnese L. J. Riehardsee '
E . E. _
- y. ^^. s.. e.1 -
Am ~'
L omer > .. . . . . . . ... . .
t ,
sunmus >
MCG:vb , , _ _
om> .. . l..(U.k.k .... . . . . .. . . . . . . -- .....
rorm Arc.ain (n... $e ...........m..,,,a i _.mi..
9212080210 920611 PDR FOIA LAWRENC92-198~. PDR.
. - ~ . - . ..::. - . u . u .. a. . ..- - , ~ . , --..- - - , - .- ... . . . .
, m ,.
The meet sigstftellust yeints noted durias the meeting were as follows:
- 1. Tha ndipresentatives indicated that no additions had been made to the eseign o(He Millstone Point Reactor as a result of the Acts letter regarding pressure vessel failures. hey believe that a major pressure vessel f ailure is incredit te sai, apparently, do not presently plant to make any additions to the zesign of their reactor systems as a result of the ACES letter. Thc og und Millstone Point representatives did, however, indicate that they would address themselves to the problems of pipe-uhipping and potentist missiles Alek were specifically pointed out in the ACRS letter regarding Dresden 2.
- 2. The design of the Millstone Point taaetoe and that of Dre:: den 2 are quite similar. Copies of a comparisen between the principal design features of tha tw2 tacilities were distributed at the meeting. A copy of this comperison is attached. Although there is a fairly large difference between the stated met eleotrical output of the two facilities, $3Ny v for Millstosa sad 715 lei for Dresden 2), the Millstone Point R hr sf,,f' graater capability for a stretch imersase is power. ~ h Sp: y *
- 3. Although Yankee Atowie Electria Cosyaay ed New Engt / (dr . . ,%-t ,
are not participeats in the Millstone Point project, Mr. Roger J.,
been retained as a comeultaat for the pro,4est and was present darkglf G ,
.pm port ion o f the meet ing .
4 Mr. Wof ford of the Hi1& stone Point organisation stated that he believes the Proposed Design Criteria for Escisar Power Plant Construction Permits will be of advantage to industry and that power co1mpanism may actually specify the criteria as requirements een asking for bids from reacter vendors. Be stated, however, that the criteria may proveet the addition of mee items in proposed reactor designs because variseses from the criteria may be tee difficult to justify. Be aise stated that, since the proposed criteria whiah have been ethlished are for cesstrwetion permits, he assumes a similc.r set of aritaria will be published for the operation of reactors. Mr. Gilbert of CR said that his company believes that the cri-teria are beates11y very good but that they have some difficulty in inter-pretatise of the werde in the criteria.
.u.
^
s isated that there might be a problem relative to the seismic desi414' .the facility but that the Regulatory Staff eeuld not say suuk11M.g , been reviewed by their comeuttants.
v8eu/4 es that a sitconium-water reaction would involve a maximas of 27.3% of the aircomium in the core, and the acetahame design is based on this velve. Ybe Del Staff was to discuss the subject of metal.
water reactions is detail with the applicant af ter the meeting om December 22 and 23,1965.
OmCE > . . . . . . . . . . .. . . . , . . . _ . . . . . . _ . . . . . .
SURNAME > . .. ...-. .. ..I*...,.....,
om > . - . . ..[ -
_ _ _ . . . . . . . . . . . . . . .. . . . - . . . . . . ~ . . . . . - . . . . _ . _
Ibrm AEC-3B iEev M1; e e sovis.s e** *e .na. ore a s a -ar a i - a
ir , s J.
~
. c
. < 7.* . These seis a auder of locked opes teclat!an' valves in the core -
and seaseineseg'spety ayatom 11nes. ne Dg!, 8taif was coeserand as to how the.eparettag organisation would insure that these valves are is a l 1eched spaa eseditism during resetor operation. ' Apparently reliance is to be placed on adotaistrative procedure to inevre that the valves are open, although the applicant indiented that this matter would be gives further consideration.
- 4. nere will be two MS EVA lines into the Millstone point plant.
hose will toes la on the same right of way, but probably on seperate towers. A lower voltage line, which will be used to provide power during the cometruction phase at the facility, will be retained and will also be available for emergency use. h is line will eens into the fasility by a differest route than the 345 ETA 11ase. As as-site emetgemey dieset 8*eerster will be provided at the site. In addittee, the possibility of connecting a gas turbine to the lower voltage lies to ingrove its reli-ability is being .imvestigated, t ;'..
- 9. Dr. Does stated that he does met believe emeegh has to test filters, under potesttal aseident seeditions, te prove / , 4 - e effeetiveness. Be quostimmed whether a faster ef asre than 2 $E,.p.}
used in the assident analysis for the deplettaa of iodine by w WW Q plateout, and filtraties. .; , , f q,-h '
- 10. CE has looked at possible feel displacement which might oesur during an accident, he preliminary results of this investigatise are that the maximum reactivity dich eas be added by such movemmat is approzi-mately $1.50 locally and a few cents relative to the whole sere.
- 11. He questies was raised 4 ether, if an electrieal short resulted La two 4.oatrol rode beleg withdrama at a time, the safety system is ade-quate to cope with the power escursies which might result. GC % d amit analysed this situaties and is -to review the matter further.
- 12. C3 is to .iavestigate whether, during lees-et-seelaat assident conditions, hydraulie forces could be ersated dich might provoet the control rods free betag inserted into the sere.
,p # g e.
';j
. time,
@W was raised as to whether the mesteer instrumenta-englifiers, might be oveeleeded dwing a treasiest ee? , is set timeer with impet and a scram not oeser during a assient. GE is slee to investigate this matter.
A' ,
- 14. He M111stees point organisaties La te review whether the eles-trical breakers are sized -for direet aberts and whether shorts seeld oseur-which sould inactivate the whole Millstone peias electrieal system.
- 15. . It. wee stated that, in cases where double imelation valves are e u n !: , : 4- M :i; : q :: : ::=1 :,2 - - ;b ;;::Y:' L: &
oM*ki'** - ...~ . - _ . - . . .
su m = > .._ _ . . ._ _
om> . .. . . ..._._ . . . . _ . - . . _ . _ . . _ . . . . . . . _. ..
Wint A PC=8tM (Rev, &S3) . . . ... ., m .m. .,,ic e IH2?ta-o
- . - - - - _ - . - . - . - . - - . - . - . . - - . - . . - - - - - . - - - . . . ~ . - ...
. 1 i
.J'
,. 4: .
14 . W sepersed that they have analysed and insured that allevable bypees of abensels in the IBM (Intermediate Raese Monitors) and APM
(&rerees Jouer Range Monttortag) syetses vill ast result la inadequate eere peeteettet. .
- 17. Test switches are to be installed for the scramming of individual control rods in the Millatoes potat teactor. The strewitry for thest test switches commects both of the scram besses. CE is to review the safety implications of this lose of independenes of the two safety chamaels.
- 18. A ball valve and a shear valve will be provided la series to permit isolation of the TIP (Trave 11ag In-Core Prebe) system. In the event the movable cables in the system are inserted into the reester at the time isoistion smet be established, the she er valves, which will be explosively epestted, will sheer the sabia and toelate the system.
- 19. CE provided eeptes of inforestion regarding the reester f f;.-
NDr temperature semaiderations for the M111 stems Petet Reester. . 4.
of this information is attaebed. The DEL Staff inquired as to that the NDf of their pressure vessel sagles is representative of, ' ' ir through the thishones of the vessel. GB apparently did met have t priate perseas available to meswer this questies and stated that , , .
review the matter further. 1:e , yp
- 20. The DRL Staff asked how far the centrol red blades ~ would save downward in the event the collet fingers ta- the control rod actuatica sys.
ten were in an open position at the time a rod ejeettee assident seeerred.
It is not apparent how unch good, if any, the sostrol rod drive thiadele supports wow 1d de is occh a sese. This matter is aise to be reviewed further.
- 21. CE reported that their analyses show that their boiling water reae-tors all have good operational stability med that the degree of stability -
is approximately the ease for all of their reseters.
- 22. CE is to provide further information regardias the differesse between the-core and containeemt spray systems for Dresdam 2 and it111stane Point.
At thefigene athe mastias, it wee agreed that the Regulatory Staff and the W seteupt to meet the fe11 swiss sebedule DEL Questiene fewarded to applicaat
. Ame. ore t. .ti. r.t.r d
- '" 4M6 nmL seetiag with applisant February 16, 1966 (appros.) ACRS St6ees.mittee leasting June 1,.1964 Caestrusties permit iseeed -
Attachments:
Primeipal Design Features...between W 11;;: = h'r ^-Bu::'z %^;
- on4141%ce4. Point.M gi m Power 1ta.tten _ _.
l DATEp. . . . _ . . _ . . . . . ._ .a_..... .. _ . _ . . . _ ,
Form AEC.319 (Rev Mh s . ...e., m.E.* wnca 1.-ers t -s
.- . - .. . - . - . - . . - - , .- .- .- -.