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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20207L7711999-03-11011 March 1999
Summary of 990223 Meeting with NSP to Discuss Potential NRC Review Process for New Core & Thermal Hydraulic Computer Modeling Methods Currently Under Evaluation by NSP
ML20207L7611999-03-0909 March 1999
Summary of 990224 Meeting with NSP Re Implications of NSP Recently Extended Commitment for Monticello ITS Submittal, Implications of NRC Initiative Toward risk-informed TSs & Interfacing ITS Conversion
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20206S6301998-06-17017 June 1998
Summary of 980602 ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommitteemeeting in Rockville,Md Re GE Extended Power Uprate Program for Operating BWRs & NSP lead-plant Application for Power Uprate
ML20198Q5881997-10-31031 October 1997
Summary of 970910 Meeting W/Util in Rockville,Md Re Status of BWR Power Uprate Program.List of Attendees,Agenda & Handouts Encl
ML20211F8071997-09-22022 September 1997
Summary of 970911 Meeting W/Northern States Power Co in Rockville,Md Re Equipment Environ Qualification Program. List of Attendees Encl
ML20132D1331996-12-13013 December 1996
Summary of 961105 Meeting W/Northern States Power & GE to Discuss Contents of 960726 License Amend Request,Pertaining to Monticello Extended Power Uprate Program & Supporting Activities
ML20057F2811993-10-12012 October 1993
Summary of 930929 Meeting W/Util Re Installation of Water Level Monitoring Instrumentation at Plant.List of Attendees & Presentation Slides Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20056F8171993-08-0909 August 1993
Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20199L6471986-06-26026 June 1986
Summary of Operating Reactors Events Meeting 86-21 on 860623.Attendance List & Viewgraphs Encl
ML20125A4201978-09-11011 September 1978
Summary of 780824 NRC Meeting Held W/Ge,Tva,Nsp, & B & P Representatives to Discuss Swelling in Four GE High Density Spent Fuel Storage Racks in Monticello Spent Fuel Pool. (Encl to 7809210158)
ML20125C5621978-05-0101 May 1978
Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan
ML20125B9641978-03-20020 March 1978
Summary of 771027 Meeting W/Ge & Mark I Owners Group Re multiple-subsequent Actuations of Safety/Relief Valves Following Isolation Event
ML20127A4681978-03-0101 March 1978
Summary of 771129 Meeting W/Mark I Owners Group & GE in San Franciso,Ca Re Listed Topics,Including Results & Bases for long-term Program Decision Point 3.List of Attendees & Viewgraphs Encl
ML20140G4971978-02-0909 February 1978
Summary of 780119 Meeting W/Mark II Owners Group,Ge & BNL Re Status of safety-relief Valve Related Loads on Mark II Containment.Meeting Agenda,Attendee List & Presentation Matls Encl
ML20125C5681978-02-0303 February 1978
Summary of 780126 Meeting W/Nsp & GE Re Proposed Plant Spent Fuel Pool Expansion
ML20125B9961977-12-29029 December 1977
Summary of 771215 Meeting W/Util Re Fall 1977 Facility Feedwater Nozzle & Control Rod Drive Return Line Nozzle Mods
ML20127H6141977-11-11011 November 1977
Trip Rept of 771007 Visit to Facility to Observe Licensees Effort to Maintain Occupational Radiation Exposures ALARA During Repair of Feedwater Nozzles
ML20127K1931977-11-11011 November 1977
Trip Rept of 771007 Visit to Monticello Nuclear Plant Re Licensee'S Effort to Maintain Occupational Radiation Exposures ALARA
ML20127H6361977-11-0101 November 1977
Summary of 771020 Meeting W/Util & Nuclear Associates International Re Discussions on Proposed Submittal of Topical Rept,Documenting Core Analysis Sys Used at Plant. List of Attendees & Presentation Slides Encl
ML20127H3801977-09-15015 September 1977
Summary of 770824 & 25 Meeting W/Representatives of Mark I Owners Group in Bethesda,Maryland Re Results & Bases for Decision Point 2 in Mark I Owners LTP & Proposed Changes in Scope of LTP Due to Results of Decision Point 2
ML20127H3951977-09-14014 September 1977
Summary of 770808 Meeting W/Representatives of Mark I Owners Group in Bethesda,Maryland Re Structural Acceptance Criteria for Mark I Containment LTP
ML20127H2771977-09-13013 September 1977
Summary of 770617 Meeting W/Representatives of Mark I Owners Group & GE in Bethesda,Md Re Discussions on Structural Acceptance Criteria for Mark I Containment Long Term Program.List of Attendees & Meeting Agenda Encl
ML20141N3471977-05-20020 May 1977
Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl
ML20128F4251977-03-10010 March 1977
Summary of 770301 Meeting W/Util Re Proposed QA Program for Plants.Attendance List & Agenda Encl
ML20214G7031977-03-0303 March 1977
Summary of 770216-17 Meetings W/Mark II Owners Group,Ge & BNL in San Jose,Ca Re Monticello Test Results & Analytical Model Verification.Attendance List Encl
ML20127H4311977-02-18018 February 1977
Summary of 770202-04 Meeting W/Representatives of Mark I Owners Group in San Jose,Ca Re Discussions on Proposed Revs to Mark I Containment Long Term Program Action Plan & Review of Status of Ongoing Testing & Analytical Efforts
ML20125B9891976-11-12012 November 1976
Summary of 761028 Meeting W/Util & Consultant,Bechtel Power Corp Re Plant 10CFR50 App J Exemption Request.List of Attendees & Document from Util Encl
ML20140G2641976-10-0404 October 1976
Summary of 760921 Meeting W/Ge & Inel in Bethesda,Md Re Areas of Concern Developed During Review of Safety Relief Analytical Model Described in NEDE-20942-P.Attendance List Encl
ML20125C5711976-09-0909 September 1976
Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks
ML20125C5721976-09-0909 September 1976
Summary of 760819 Meeting W/Mark I Owners Group,(Ge) in Bethesda,Md Re Discussions on Mark I Containment Ltp.List of Attendees Encl
ML20125D6581976-08-18018 August 1976
Summary of 760717-08 Meeting W/Representatives of Mark I Owners Group in Bethesda,Md Re Discussions on Reassessed Content of Mark I Containment LTP & Recently Submitted Responses to Questions on STP Final Rept
ML20140G2531976-06-28028 June 1976
Trip Rept of 760614-17 Site Visits Re Relief Valve Test Sequence.Test Results Encl
ML20128C3711976-06-16016 June 1976
Summary of 760602 Meeting W/Mark I Owners Group in San Jose, CA Re General Guidelines for Defining Failure for Each Structural Failure Mode Being Considered in plant-unique Structural Analyses
ML20140G2591976-06-15015 June 1976
Trip Rept of 760529 Site Visit Re Witness of Safety/Relief Valve Tests.List of Attendees Encl
ML20127N9961976-05-24024 May 1976
Summary of 760513 Meeting W/Mark I Owners Group (GE) in Bethesda,Md Re Discussions on Program for plant-unique Torus Support Sys Analyses Presented in Ltr from GE to NRC .List of Meeting Attendees Encl
ML20127P0271976-05-0606 May 1976
Summary of 760408 Meeting W/Mark I Owners Group (GE) in Bethesda,Md Re Discussions on Plant Specific Analyses of Mark I Torus Support Structure.List of Attendees Encl
ML20126C2391976-04-19019 April 1976
Summary of 760401 Meeting W/Representatives of Mark I OG & GE in Bethesda,Md Re Revised Mark I OG Organization & Mark I Containment Reevaluation Schedule.List of Attendees Encl
ML20126C1851976-03-24024 March 1976
Summary of 760318 Meeting W/Util Re App I Requirements.List of Attendees & Agenda Encl
ML20126C2031976-03-0505 March 1976
Summary of 760226 Meeting W/Representatives of Mark I OG in Bethesda,Md Re BWR Mark I Containment Evaluation
ML20128D8921975-11-28028 November 1975
Summary of 751031 Meeting W/Util to Discuss Monticello Reactor Vessel Feedwater Nozzle Cladding Cracks.List of Attendees Encl
ML20235E9641975-08-0606 August 1975
Summary of 750717 Meeting W/Mark I Owners Group Re Role of Mark I Owners Group Program & Schedule for Determining Mark I Safety/Relief Valve & LOCA Dynamic Loads & Impact of Loads on Operating Mark I Plants.List of Attendees Encl
ML20128C7861974-10-0303 October 1974
Summary of 740919 Meeting W/Util in Bethesda,Md Re Reg Guides 1.3 & 1.7 Relative to post-accident Combustible Gas Control Requirements for Plant Containment
ML20128D9481974-04-0202 April 1974
Summary of 740322 Meeting W/Util in Bethesda,Md Re Plant Prompt Relief Trip Electrical Connections & Containment Penetrations
ML20127G6091974-03-14014 March 1974
Summary of 740220 & 21 Meeting W/Util,Bechtel & GE in Bethesda,Md Re Prompt Relief Trip & Stated Valves
1999-03-09
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20207L7711999-03-11011 March 1999
Summary of 990223 Meeting with NSP to Discuss Potential NRC Review Process for New Core & Thermal Hydraulic Computer Modeling Methods Currently Under Evaluation by NSP
ML20207L7611999-03-0909 March 1999
Summary of 990224 Meeting with NSP Re Implications of NSP Recently Extended Commitment for Monticello ITS Submittal, Implications of NRC Initiative Toward risk-informed TSs & Interfacing ITS Conversion
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20206S6301998-06-17017 June 1998
Summary of 980602 ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommitteemeeting in Rockville,Md Re GE Extended Power Uprate Program for Operating BWRs & NSP lead-plant Application for Power Uprate
ML20198Q5881997-10-31031 October 1997
Summary of 970910 Meeting W/Util in Rockville,Md Re Status of BWR Power Uprate Program.List of Attendees,Agenda & Handouts Encl
ML20211F8071997-09-22022 September 1997
Summary of 970911 Meeting W/Northern States Power Co in Rockville,Md Re Equipment Environ Qualification Program. List of Attendees Encl
ML20132D1331996-12-13013 December 1996
Summary of 961105 Meeting W/Northern States Power & GE to Discuss Contents of 960726 License Amend Request,Pertaining to Monticello Extended Power Uprate Program & Supporting Activities
ML20057F2811993-10-12012 October 1993
Summary of 930929 Meeting W/Util Re Installation of Water Level Monitoring Instrumentation at Plant.List of Attendees & Presentation Slides Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20056F8171993-08-0909 August 1993
Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20199L6471986-06-26026 June 1986
Summary of Operating Reactors Events Meeting 86-21 on 860623.Attendance List & Viewgraphs Encl
ML20125A4201978-09-11011 September 1978
Summary of 780824 NRC Meeting Held W/Ge,Tva,Nsp, & B & P Representatives to Discuss Swelling in Four GE High Density Spent Fuel Storage Racks in Monticello Spent Fuel Pool. (Encl to 7809210158)
ML20125C5621978-05-0101 May 1978
Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan
ML20125B9641978-03-20020 March 1978
Summary of 771027 Meeting W/Ge & Mark I Owners Group Re multiple-subsequent Actuations of Safety/Relief Valves Following Isolation Event
ML20127A4681978-03-0101 March 1978
Summary of 771129 Meeting W/Mark I Owners Group & GE in San Franciso,Ca Re Listed Topics,Including Results & Bases for long-term Program Decision Point 3.List of Attendees & Viewgraphs Encl
ML20140G4971978-02-0909 February 1978
Summary of 780119 Meeting W/Mark II Owners Group,Ge & BNL Re Status of safety-relief Valve Related Loads on Mark II Containment.Meeting Agenda,Attendee List & Presentation Matls Encl
ML20125C5681978-02-0303 February 1978
Summary of 780126 Meeting W/Nsp & GE Re Proposed Plant Spent Fuel Pool Expansion
ML20125B9961977-12-29029 December 1977
Summary of 771215 Meeting W/Util Re Fall 1977 Facility Feedwater Nozzle & Control Rod Drive Return Line Nozzle Mods
ML20127H6361977-11-0101 November 1977
Summary of 771020 Meeting W/Util & Nuclear Associates International Re Discussions on Proposed Submittal of Topical Rept,Documenting Core Analysis Sys Used at Plant. List of Attendees & Presentation Slides Encl
ML20127H3801977-09-15015 September 1977
Summary of 770824 & 25 Meeting W/Representatives of Mark I Owners Group in Bethesda,Maryland Re Results & Bases for Decision Point 2 in Mark I Owners LTP & Proposed Changes in Scope of LTP Due to Results of Decision Point 2
ML20127H3951977-09-14014 September 1977
Summary of 770808 Meeting W/Representatives of Mark I Owners Group in Bethesda,Maryland Re Structural Acceptance Criteria for Mark I Containment LTP
ML20127H2771977-09-13013 September 1977
Summary of 770617 Meeting W/Representatives of Mark I Owners Group & GE in Bethesda,Md Re Discussions on Structural Acceptance Criteria for Mark I Containment Long Term Program.List of Attendees & Meeting Agenda Encl
ML20141N3471977-05-20020 May 1977
Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl
ML20128F4251977-03-10010 March 1977
Summary of 770301 Meeting W/Util Re Proposed QA Program for Plants.Attendance List & Agenda Encl
ML20214G7031977-03-0303 March 1977
Summary of 770216-17 Meetings W/Mark II Owners Group,Ge & BNL in San Jose,Ca Re Monticello Test Results & Analytical Model Verification.Attendance List Encl
ML20127H4311977-02-18018 February 1977
Summary of 770202-04 Meeting W/Representatives of Mark I Owners Group in San Jose,Ca Re Discussions on Proposed Revs to Mark I Containment Long Term Program Action Plan & Review of Status of Ongoing Testing & Analytical Efforts
ML20125B9891976-11-12012 November 1976
Summary of 761028 Meeting W/Util & Consultant,Bechtel Power Corp Re Plant 10CFR50 App J Exemption Request.List of Attendees & Document from Util Encl
ML20140G2641976-10-0404 October 1976
Summary of 760921 Meeting W/Ge & Inel in Bethesda,Md Re Areas of Concern Developed During Review of Safety Relief Analytical Model Described in NEDE-20942-P.Attendance List Encl
ML20125C5711976-09-0909 September 1976
Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks
ML20125C5721976-09-0909 September 1976
Summary of 760819 Meeting W/Mark I Owners Group,(Ge) in Bethesda,Md Re Discussions on Mark I Containment Ltp.List of Attendees Encl
ML20125D6581976-08-18018 August 1976
Summary of 760717-08 Meeting W/Representatives of Mark I Owners Group in Bethesda,Md Re Discussions on Reassessed Content of Mark I Containment LTP & Recently Submitted Responses to Questions on STP Final Rept
ML20128C3711976-06-16016 June 1976
Summary of 760602 Meeting W/Mark I Owners Group in San Jose, CA Re General Guidelines for Defining Failure for Each Structural Failure Mode Being Considered in plant-unique Structural Analyses
ML20127N9961976-05-24024 May 1976
Summary of 760513 Meeting W/Mark I Owners Group (GE) in Bethesda,Md Re Discussions on Program for plant-unique Torus Support Sys Analyses Presented in Ltr from GE to NRC .List of Meeting Attendees Encl
ML20127P0271976-05-0606 May 1976
Summary of 760408 Meeting W/Mark I Owners Group (GE) in Bethesda,Md Re Discussions on Plant Specific Analyses of Mark I Torus Support Structure.List of Attendees Encl
ML20126C2391976-04-19019 April 1976
Summary of 760401 Meeting W/Representatives of Mark I OG & GE in Bethesda,Md Re Revised Mark I OG Organization & Mark I Containment Reevaluation Schedule.List of Attendees Encl
ML20126C1851976-03-24024 March 1976
Summary of 760318 Meeting W/Util Re App I Requirements.List of Attendees & Agenda Encl
ML20126C2031976-03-0505 March 1976
Summary of 760226 Meeting W/Representatives of Mark I OG in Bethesda,Md Re BWR Mark I Containment Evaluation
ML20128D8921975-11-28028 November 1975
Summary of 751031 Meeting W/Util to Discuss Monticello Reactor Vessel Feedwater Nozzle Cladding Cracks.List of Attendees Encl
ML20235E9641975-08-0606 August 1975
Summary of 750717 Meeting W/Mark I Owners Group Re Role of Mark I Owners Group Program & Schedule for Determining Mark I Safety/Relief Valve & LOCA Dynamic Loads & Impact of Loads on Operating Mark I Plants.List of Attendees Encl
ML20128C7861974-10-0303 October 1974
Summary of 740919 Meeting W/Util in Bethesda,Md Re Reg Guides 1.3 & 1.7 Relative to post-accident Combustible Gas Control Requirements for Plant Containment
ML20128D9481974-04-0202 April 1974
Summary of 740322 Meeting W/Util in Bethesda,Md Re Plant Prompt Relief Trip Electrical Connections & Containment Penetrations
ML20127G6091974-03-14014 March 1974
Summary of 740220 & 21 Meeting W/Util,Bechtel & GE in Bethesda,Md Re Prompt Relief Trip & Stated Valves
ML20126B1771973-10-0909 October 1973
Summary of 730927 Meeting W/Util in Bethesda,Md to Discuss Util Plans to Replace Four Existing spring-loaded Safety Valves on Plant Steam Lines W/Four Addl Target Rock Relief/ Safety Valves
ML20128E0871973-09-11011 September 1973
Summary of 730906 Meeting W/Util in Bethesda,Md Re drywell- Torus Vacuum Breaker,Valve Position Indicators & Alarm Circuits to Assure Valve Closure & Changes to TS to Include Specific Vacuum Breaker Leak Test Requirements
ML20128D1981973-06-15015 June 1973
Summarizes 730517 Meeting W/Util in Bethesda,Md to Discuss Basis for Proposed Rev to Tech Specs Re Control Rod Reactivity Worth Limits
ML20125B3361972-10-30030 October 1972
Summary of 720930 ACRS Meeting W/Licensees in Washington DC Re Safety Review Monticello Full Term Operating License
1999-03-09
[Table view] |
Text
.
4 [
W# , UNITED STATES f0d
[dh\ ATOMIC ENERGY COMMISSION l
IE)' W ASHINGTON, D.C. 20545 October 15, 1969
\,
'N[
R. S. Boyd, Assistant Director for Reactor Projects, DRL f)
THRU: D. R. Muller, Chief, Reactor Project Branch #1, DRL POL REVIEW MEETING WITH NORTHERN STATES POWER COMPANY, MONTICELLO NUCLEAR GENERATING PLANT, DOCKET NO. 50-263 A meeting was held with Northern States Power Company (NSP) on October 2, 1969 to discuss the updating of the technical specifica-tions proposed by NSP and to clarify a number of the responses to DRL's questions submitted in Amendments 16 and 17. A summary of the salient points discussed at the meeting is presented below.
A list of attendees is attached.
A. DISCUSSION OF TECHNICAL SPECIFICATIONS In regard to revising NSP's proposed technical specifications, several approaches were discussed. Because of the similarity between Dresden 2 and Monticello, NSP indicated it intends to follow as closely as possible the format and content of the Dresden 2 technical specifica-tions. NSP hopes to have a revised draf t of the Monticello technicel specifications submitted to us by October 21, 1969.
A. Brauner discussed in detail the section on administrative controls.
In light of our current views, we indicated that this section as submitted in the early draf t of the proposed technical specifications would require extensive revision.
We also discussed a number of areas of potential disagreement. These areas included the allevable leakage rate from the primary coolant system, the containment leakage rate, the closure time of the main I
steam line isolation valves, and the stack limits. However, we told NSP that we had not completed our review in these areas.
E. DISC 1'SSION OF AMENDMENTS 16 AN'D 17
- 1. The non-destructive testing requirements for the primary coolant system pressure boundary of Monticello (Table A prepared by R. Maccary) was discussed with NSP. The applicant was somewhat f amiliar with the requirements of this table and stated that its evaluation to determine the extent of compliance would be completed within two weeks. NSP stated that it would be prepared to discuss this area with the Compliance inspectors at the next inspection scheduled for October 17, 1969.
9212030643 691015 PDR ADOCK 05000263 A pyg r
i s
F R. S. Boyd ,
- 2. L. Porse asked for clarification of a number of-areas related to the design and fabrication of the reactor pressure vessel. To indicate the influence which cold work had on material properties of the reactor vessel plate, the applicant agreed to provide a summary of the tensile and impact test results. ,
, In regard to the operational-transients to which the reactor 4 vessel is designed, the FSAR states that the vessel -is designed to take 50,000 temperature transients associated with the control-rod worth tests throughout the life time of the reactor. This appeared to be at variance with other BWR'c for which 400 tempera-ture transients associated with the control rod worth tests were i
specified. GE stated that the 50,000 number is related to a 10 F-transient, whereas the 400 number is related to a 30 F transient.
. 3. In regard to leakage detection from the primary coolant system i ve asked NSP to clarify what it meant by stating that provisions .
are made for determining the' source of leakage., NSP said 1t l . primarily would use visual means to determine the source of leakage. However, portable sonic and radiation instruments will be used to aid visual inspection when the drywell becomes accessible.
In addition, radiochemical analysis of either air or water.
i samples can be used to establish whether: a leak source is steam or reactor water.
l
- 4. The applicant has agreed to place two area type radiation monitors l above and to the side of the spent fuel pool. In the event of an activity release these monitors will be capable of-detecting l
and isolating the reactor building and' initiate action of the standby gas treatment system f aster than. the action f rom the monitors located in the building ventilation exhaust plenum.
- 5. In Amendment 16 NSP stated-that the intake of airborne particulate or gaseous radioactivity into the control room is not a radio-logical problem and_therefore no. instrumentation or controls are provided for the design basis accident situations. NSP stated-that this was incorrect, and that radiation monitors are located in the control room. .
i The control room ventilation system is designed to normally draw fresh air from a port located on the outside wall of the control l room and the amount of air can be modulated from 0 to 100% :
recirculation of the conditioned air. The system is manually. I operated. Our concern is that in the' event of a steam-line' break- j i
l
6 i
1 i
4 R. S. Boyd -3 j accident in the turbine building, activity may be drawn into the control room before the inlet dampers could be closed. OE contends that any personnel dose associated with this event would be so small as to be unimportant. Nevertheless, we asked the 4
applicant to perform an analysis to justify this conclusion.
- NSP agreed to perform this analysis.
! 6. T. Ippolito asked how it -will be observed that one channel of-l a trip system has indeed tripped. NSP said that the tripping of an instrument system is alarmed in the control room; however, to
- know whether a single channel has tripped one must actually check j their relays. T. Ippolito said he thought that Dresden 2 would 4
provide indication for a single channel trip. NSP said that if
- Dresden provides this feature it would also. Subsequent to the meeting, we learned that indication of a single channel trip of the ECCS will be provided in Dresden 2.
- 7. In Amendment No. 17 it states that generally all quality assurance records will be maintained at their present storage location i.e.,
General Electric, Bechtel, NSP, or vendor where applicable. A check-list, which lists the quality assurance records available and their storage location, will be maintained by NSP. NSP will be notified prior to disposal of any quality assurance document.
We asked NSP to clarify _the last statement. NSP said it would correct the FSAR to make it clear that upon notif1 cation'of
- the intention to dispose of any records pertaining to safety items it will take possession of these records and maintain them
- at the site.
- 8. We questioned the simplified manner in which tor.1 mixing was assumed in- the river in the analysis predicting the concentration of liquid effluents at the Minneapolis and St. Paul water intakes.
-NSP~said it had made extensive thermal studies of the river to justify this mixing. We requested therefore, that they supply _
sufficient information to show this justification.
- 9. It appears that in the analysis of the potential radioactivity levels in the river resulting from the release of the contents of the radwaste tanks into the river that the dilution afforded by Leixing in the river was taken into account twice. NSP said that
, -it would recheck its analysis.
'I
L i
i R. S. Boyd -4 1
- 10. In regard to airborne effluent release limits, we asked NSP to clarify the bases, the monitor set points, and method of arriving at the joint effluent limit.
- 11. The offsite doses resulting from a primary system pipe rupture in the reactor clean-up system or RHR system was discussed. We noted that in the Easton application this same type of analysis was done assuming that the break occurred eight hours after shutdown of the reactor clean-up system. This assumption resulted in a more severe dose. NSP said it would recheck its analysis using this assumption.
l Af D. B. Vassallo, Project Leader Reactor Projects Branch #1 Division of Reactor Licensing 1
Enclosure:
Attendance list Distribution:
Docket File RL Reading RPB-1 Reading D. J. Skovholt S. Levine R. C. DeYoung RP Branch Chiefs CO (2)
N. Blunt D. B. Vassallo R. S. Lee
- C. J. DeBevec A.-Brauner T. Ippolito L. Forse I. Spickler i
4 1
j.
t 1
5 1
- -ATTENDANCE LIST 1 V l
3 NORTHERN STATES POWER COMPANY AEC/DRL
] E. Ward D. Muller j C. Ross -R. Lee
! M. Clarity D. Vassallo i
4 G. Jacobson C. DeBevec 1
A. Brauner-4 T. Ippolito*
L..Porse*
l 1. Spickler*
i GENERAL-ELECTRIC COMPANY l
L. Wolf i R. Vassar j J. Power
{ P. Poe 5 i
!- CO, REGION III l
C. Feierabend t
i
, l
, i I
l l i
l
! I
- - . -.. . . . - . . . . . . . - ,
