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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 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 ML20125C5711976-09-0909 September 1976 Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks 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] |
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' UNITED STATES GOVERNMI NT [ g,'
PIemorandwn TI U R. Nuller, Chief r Reactor Projects Branch No.1, DRL yN" i ;
3 RW '
B. Grimes, Reactor Projects Branch No. 3,4 /
Division of Reactor Licensing ( dvWW '
selytci: NORTIDGtN STATES ICWr.R, DOCKET NO. 50 263, STAFF MErff1NG MARCH 22, 1967; ACRS SUB00)Oi1 TITE FEt: TING MARCH 23, 1967 A. Staff Meeting On March 22, 1967, a meeting was beld in the Bethesda offices to discuss the Northern States Pbver Construction Permit application. An attendance liet is attached.
Areas modes and discussed planned at the meeting)were research, (2 the present (1) present storage knowledge capacity and use of fuel failu rate of the Minneapolis and St. Paul water intakes and the 20 and 40 year
. forecasts for these nuncipalities, (3) the disposition of liquid vastas during an MCA, (4) the length of time for a slu6 of pollutant to pass the Minneapolis water intake at a riverflow of IK)0 cfs and (5) the ade-quacy of the single diesel generator for emergency on-site power. Satis-factory presentations on the first four points were made by the applicant.
These four points were transmitted to D. R. Nuller by the ACRS Subcommaittee and are delineated in bis February 14, 1967, memo to files.
The emergency on-site power was disenssed from the standpoint of (1) reli-ability of the Northern States Power network, 2) probability of the loss of offsite power caused by an accident ani (3)(reliability of the proposed diesel generator. The G. E. proposed critarion on reliability of off-site power was handed out and is attached to this meno. The staff restated its position that two on-site power sources are required.
B. Subcommittee Meeting The subcommittee meeting covered the same points 1 as the staff meeting -
with the result that the first four points were satisfactorily resolved (the analysis on the 400 cfs river flow will be submitted as an amend-ment to the application) and the fellowing guestions were raised on the diesel generator reliability (1) Is the on-site power truly iniependent of offsite power? That is, could a single failure take out both power sources?- (Theapplicant's -
answer was that they were independent.)
(2) Would the plant be sbu+down if the diesel van not operablet g For example, the technical specifications mi bt 6 require shutdown if the
/ > diesel were out for more than a few hours. (NSP stated that there vere s many considerations in the decision to take a plant off the line. )
i L But U.S, Satings Bands Regularly on flu Payollkings Plan 9211200445 670327 l PDR ADOCK 05000263 l A PDR m ?
. . . . .- .- - ., -. . . - _ - . _ - - - - . - - - . _ - . _ = _ . .
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I THE FIIES !
(3) When vill adequate test and historical data on the proposed diesel (with modifications intended,to improve reliability) be available to confirm the 0 999 reliability as opposed to the present information which indicates a 0 99 reliability?
Brief presentations by the applicant on the following topies were requested: I i
(1) Differences from Quad-Cities. .
(2) Water supply and liquid vaste disposal.
(3) New research on fuel failure at G. E., blowdown forces on core '
internals and the resultant mechanical effects of cold water on the hot I core, and I (4) The above questions on the diesel generator should be answered. !
i Attachments:
Attendance List .
Proposed Emergency Power Criterion i
Distribution:
DRL Reading RPB f3 Bending R. S. Boyd
, D. R. Nuller J. J. Shea B. Grimes D. Sullivan i
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- ATTENDANCE LIST MARCH 222 1%7
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- 0. E. NSP J. Violette R. Revell (Eargo Engineering)
W. Gilbert A. Dienhart
- - H. Hollingshouse A. Wani j A. P. Bray G. Neils i
L. Kisin R. Jensen i
I. Jacobs L. Schedin C. Concordia (Schenectady)
D. McElroy
- S. Simolen j E. Beers i
DRL
! R. S. Boyd D. R. Nuller
! J. J. Shes i B. Grimes i
D. Sullivan i
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~l111. Cl. NIL \L LLlflRIC Cu ll%W CitlTl 1410N 1 ti; 1M1.RGLNW IW1 R lne General Liectric Company has established a safety criterion i uhich utili:es a numerical goal fer the acallability of ptn.er needs t ;
to operate essential engineered safeguards for nudear plats. liii goal is e8tablish:d on the basis that the availability of pm.er :mt be w:ansurate hith, in fact better than, the availability of t.ie i
essential equipuent it se rves . 1he geal, which is considered to have adequate Inargin, is 4ct at 0.99t:99 for tRe reliability of 4
poter following a major accil'nt , such as loss of coolant.
4 lhe criterien can be a;' plied uniforuly acress all nuclear plant s for all sites anJ would anure that acceptable levels el poner integri ty are at tained, lhe total complex 01 power it derised fien; off-site networt sources, as hell as en site 3tandby sources. Pl an t .-
closely coupled to strong networhs are especially well enuewed with I
a reljable source of eff-site poher for use in emergencies. An evaluat ion of a particular nuclear plant on a particular- reactor site for purposes of satisfying this emergency power safety criterion '
I might indicate that , although a supplementary on-site power requirce.t l is required, it might only involve a conventional diesel source becam l
l of a very dependable off-site power network. On the other hand, tiie i
evaluation may indicate that since the off-site power network is not of the highest level of dependability, the on-site power source of diesel power must be designed for a higher level of availability, f
(
)
Mast ~ dome.[t ic plants are favorably sited so inat tot m ailabili t, ff-site power, even following a lo8S-of-cuolat saccioent in i .nerator: has been gous As of 0.999, in such a case, a eenventional peaki ng plant div a reveal that they can !
cator with a startint; ,
' reliability of 0.99 is adequate supplement a: 1 of de>1gn, testing, t te power to rreet the e,oal.
In some cases where the availability >f performance records, f-site power fall 3 below 0.999, then extra measures to assure ,,1rst and most efficient ,
r starting reliability en ine diesel such as augmentede:- devic d come by the above tet tensified suneillance and maintenwice wouldyed betoemplo meet an t wu, t .
sal .
In unusual cases wht re a plant is rather isolated fium thedby pewei states that,
~ rid network, such that eff site power availability may be loufficient sources of alk , ,
ere the extra measures mentioned above o are not ability sufficient t t,er perfonning t y the reliability goal, a redundant diesel generatore would b fcguards. "
d.
trn not only meets the it
>11eation of the criterion requires a detailed analy s s of th. i ' point of requiring a dt
.etworh associated with each pl,'nt.
In addition, a thoiough of standby power never anding of the cause and effect relatienship existing between
.ccident conditions.
ident requiring the operation of an engineered safeguard mean . ;
m d that two diesel gent power is evaluated under the hypothetical cenditions that the ovided for a single sited has occurred; no other assw:ptien is realistic or meaning .
such1ut an a,nterpretation a,s General Electric Company considers that when enthe criteri ,
terien, is not warranted, power availability is achieved by a combination of off oit< 21 increased overall safet J one on-site diesel generator, the further addition of a rac L,ompany plans to pursu t-site diesel generator is net the proper action t ,
o contithu.e evaluation and assessment ;
atly to plant safety, ,
ellability for all the est guided solely by a synthet
\
1 ? .
4 \- . .j -
i ,
i, An evaluation of the total pu..er couplex for the .Waticello fi Nuclear Generating P1; ult , Unit No.1 (Northem States Poher Co.)
i l ha8 been made. For the proposed reactor and site, a single diesel will provide a sufficient source of alternate power to assure a J.
capability for perfoming the functions required of the engineered j h safeguards. Perfemance of the NSP power network is covered in the l 1
l anther to Question 4 in Anend:acnt 6 and an analysis of the f
[ reliability of the power corplex 18 covered in the answer to i i Question 7 in Amendment 6.
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