|
|---|
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
_ ,__ 7 _ _ _ . . _ . _ _ _ _ . _ _ _ _ . _ _ __ - _ _ _ _ _ _ _
UNITED STATES f 4 ATOMIC ENERGY COMMISSION
~ M ' '
W ASHINGTON. D.C. 20549 l
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May 18, 1971 i
Roger S. Boyd, Assistant Director, BWR, Division of Reactor Licensing TH -D nald F. Knuyh, hief. BWR-1, Division of Reactor Licens'ng e cre.aLLL. V-\
MEETING ITH NORTHERN STATES POWER COMPANY (NSP) - MONTICELLO GENERATING PLANT (E-5979). CONCERNING TECH SPEC CHANGE NO. 2 - WASTE GAS SYSTEM, DOCKET N0.(50463]
Suntnary A meeting was held on May 11, 1971, with NSP to discuss Change No. 2 to ,
the Technical Specifications of the Monticello plant. An attendance list is enclosed.
Change No. 2 consists of proposed modifications to the gaseous radwaste '
system. The proposed modification will increase the holdup time of the condenser air ejector non-condensable gases from 30 minutes to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
The site boundary dose from this source alone is calculated to be 4 mrem / year, with other sources, ignored by the licensee, contributing an equal amount.
The proposed system consists of redundant hydrogen recombiners and compressors, y and 5 gas storage tanks which will hold gases at 300 psig.
We informed the applicant that the proposed system is an improvement over the existing waste gas system, but it probably does not meet the "as low as practicable releases" concept.
Discussion The proposed modifications, filed as a request for a change to the Tech-nical Specifications, is supposed to be reviewed by the Operations Committee and in turn the recommendations submitted to the Safety Audit Committee
~
for concurrence. The Vice-President is to take appropriate action (Table 6.1.1 of the Tech Specs). This has been emphasized to NSP on other occasionst however, the licensee stated that the safety committee had not completed its review yet. It was brought to the licensee's attention that this was
- j - a clear violation of the existing Tech Specs, i
The design of the proposed gaseous radwaste system was discussed, and the licensee agreed to the followingt j
j I 1.- All equipment will be designed toiseismic Class I requirements.
4
- 2. The five storage tanks will be located above the probable maximum j
flood level or will be_ protected from such a flood, dyd h2 P
0 3
.n . .
I6 .4 ,
i l Roger S. Boyd 2
- 3. Data on the operation of the recombiner using BWR effluents (vetting as well as iodine act as poisons on some catalysts) will be provided.
- 4. The equipment, from the air ejector to the compressor, will be designed to 350 psig (it-is 300 psia now).
- 5. There will be a particulate (fiter upstream of the compressors.
- 6. The handling of the liquid discharges (dilution steam and from the recombiner) will be delineated.
- 7. Modifications to the system (desuperheater has been deleted, etc.)
vill be documented.
- 8. The instrumentatier, will be shown more clearly.
- 9. Attention will be paid to the stack, which is not designed to take tornadoes.
- 10. Operation of the unit under normal and abnormal conditions will be documented.
We informed the applicant that we did not agree with the statement in the report' that "the pressurized tank. holdup and charcoal holdup systems will provide identical environmental result's for equal holdup time." We said we are of the opinion that a charcoal system, for approximately the same
' cost, could further reduce the curie release rate by a factor of 10. .
Under normal operating conditions, the licensee did not take into consi-deration contributions from steam turbine gland seal, plant startup. HPCI turbine testing, SGTS systems operation, containment purging, shine from l
other radvaste tanks, and possible leakage from the proposed pressurized gaseous radwaste system. The licensee stated that the estimated release rate from the turbine gland seal system listed'in the FSAR was in error; the boundary dose rate contribution should be 3.5 mrem / year instead of 0.35.
In the dose calculations, the contribution of halogens has not been con-sidered, and therefore the thyroid dose for accident conditions has not been calculated. The licensee stated that they had the impression that l
l halogens are collected in the recombiner. We understand that at KRB, j very low concentrations of halogens have been detected downstream of the l recombiner; however, we have no documented evidence.
We mentioned that we could foresee some operational problems. Venting of
? the wreng tank due to an operational error seems quite probable.
l l
. .m . . .- . . . . . . ... . . . . . .
1"",
/
Roger S. Boyd 3 We informed the applicant that the proposed changes to the Technical Speci-fications are inadequate. We will discuss these changes af ter we have finished the review of the proposed system; and to expect some reduction on the allowable curie release rate.
We summarized the meeting by saying that the proposed gaseous radwaste system is an improvement over the existing one, and with some modifications it probably would be accepted. Ilowever, if it is compared to other systems proposed for other BWR's, (it is compared to the charcoal delay in the NSP report), we could not recommend it to our management as meeting the "as low as practicable" concept. A new rule is in preparation, and when-ever this new rule is published, Monticello may have to make modifications if the radwaste system is installed as proposed.
'h f = = -
Victor Benaroya, Project loader Boiling Water Reactor Branch No. 1 Division of Reactor Licensing
Enclosure:
Attendance List 1
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4 ATTENDANCE LIST I NORTHERN STATES P0kTR COMPANY - HONTICE110 NUCLEAR GENERATING PLANT May 11. 1971 1,
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I D. F. Knuth E. Ward V. Benaroya C. E. Larson ,
R.~ Grill R. J. Jensen N. Thomasson ;
i SUNTAC-r l -
CO '
- 3. L. Renehan m I C. D. Telerabend . P. D. Arrowsmith i J. T. Sevier NUS 4
i
! A. W. DeAgazio 4
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4 9
9 1
t *- w w -e--*+ow m--veer'e--=a-w F--"*-wr--** W w e www- w * = v * - - ma *e vs#*Wr-rv- *w * <' *e+=-t* e-**~"wd *---w- + * -r-*e- *rw = -4 e- --c*-
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Roger S. Boyd 3 We informed the applicant that the proposed changes to the Technical Speci-fications are inadequate. We vill discuss these changes after we have finished the review of the proposed syatecit and to expect some reduction on the allovable curie release rate.
We summarized the meeting by saying that the proposed gaseous radwaste system is an improvement over the existing one, and with some nodifications it proonbly would be accepted. However, if it is compared to other systems proposed for other BWP,'s, (it is corepared to the charcoal delay in the llSP report), we could not recocunend it to our managedent as meeting the "as lov as pra:ticable" concept. A new rule is in preparation, and when-ever this new rule is published Monticello may have to make modifications if the radvaste system is installed as proposed.
!.5 /
Victor Benaroya, Project Leader Boiling Water Reactor Branch No. 1 Division of Reactor Licensing
Enclosure:
Attendance List Distribution:
Docket DRL Reading BWR-1 File PAMorris, DRL FSchroeder, DRL Asst. Directors, DRL BR. Chiefs, DRL/DRS ECCase, DRS RRMaccary, DRS BGrimes, DRL VBenaroya, DRL SMRari, DRL Compliance (2)
HDenton, SERSG omer > _. DRL : BWR.71 ...... ..DRL;BWRd.. . .
VBenaroyatkis SURNAME > .X. . .h.1. . . . .. .. ....N--- -
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