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| EXHIBIT II , . . | | EXHIBIT II , . . |
| NUCLEAR ENERGY GENERALh ELECTRIC PROJECTS DIVISION GENERAL ELECTRIC COMPANY.175 CURTNER AVE., SAN JOSE. CALIFORNIA 95125 , | | NUCLEAR ENERGY GENERALh ELECTRIC PROJECTS DIVISION GENERAL ELECTRIC COMPANY.175 CURTNER AVE., SAN JOSE. CALIFORNIA 95125 , |
| MC682,(408)925-5722 MFN-198-79 | | MC682,(408)925-5722 MFN-198-79 July 31,1979 PTPfPfin f;rpp J |
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| July 31,1979 PTPfPfin f;rpp J | |
| m AUG c 1979 | | m AUG c 1979 |
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| U. S. Nuclear Regulatory Commission Division of Systems Safety | | U. S. Nuclear Regulatory Commission Division of Systems Safety y jggcg Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Frank Schroeder, Acting Director Division of Systems Safety Gentlemen: |
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| y jggcg Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Frank Schroeder, Acting Director Division of Systems Safety Gentlemen: | |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| : 2. Steam Seoarator AP and Break Flow Discussion Attachment 2 presents the results from the mass and energy balance obtained from the TLTA data for the tests with and with.out ECC injection. These results clearly show that for the test with ECC injection, more liquid was entrained out the break and the buik discharged fluid quality was clearly lower. It is further concluded | | : 2. Steam Seoarator AP and Break Flow Discussion Attachment 2 presents the results from the mass and energy balance obtained from the TLTA data for the tests with and with.out ECC injection. These results clearly show that for the test with ECC injection, more liquid was entrained out the break and the buik discharged fluid quality was clearly lower. It is further concluded |
| ( that fluid conditions discharged from the break led to the differences in depressurization rate observed between the two tests. Attachment 3 provides analysis of the steam separator pressure drop data. The ip08 9 79092e0954 | | ( that fluid conditions discharged from the break led to the differences in depressurization rate observed between the two tests. Attachment 3 provides analysis of the steam separator pressure drop data. The ip08 9 79092e0954 |
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| GENER AL h ELECTRIC | | GENER AL h ELECTRIC |
| (. U. S. Nuclear Regulatory Commission July 31,1979 Page 2 | | (. U. S. Nuclear Regulatory Commission July 31,1979 Page 2 |
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| preliminary evaluation of the separator AP suggested that the steam | | preliminary evaluation of the separator AP suggested that the steam |
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| : 6. The Grid Spacer Water Accumulation Attachment 7 provides a discussion of the CCFL characteristics across a bundle. It is concluded that, while there is a potential for water accumulation to exist momentarily when there is a sudden reduction in the bundle inlet flow (e.g., during the flow coastdown period or lower plenum flashing period), accumulation will not occur during the reflood period. | | : 6. The Grid Spacer Water Accumulation Attachment 7 provides a discussion of the CCFL characteristics across a bundle. It is concluded that, while there is a potential for water accumulation to exist momentarily when there is a sudden reduction in the bundle inlet flow (e.g., during the flow coastdown period or lower plenum flashing period), accumulation will not occur during the reflood period. |
| : 7. Justification of Conservatism of the Heat Transfer Coefficients used in SAFE The information provided in Attachment 6 demonstrates that the heat transfer coefficients used in the SAFE Computer Program between the nucleate boiling to the core spray cooling regimes are the appropriate | | : 7. Justification of Conservatism of the Heat Transfer Coefficients used in SAFE The information provided in Attachment 6 demonstrates that the heat transfer coefficients used in the SAFE Computer Program between the nucleate boiling to the core spray cooling regimes are the appropriate |
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| 1008 355 | | 1008 355 |
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| GEN ER AL $ ELECTRIC U. S. Nuclear Regulatory Commission | | GEN ER AL $ ELECTRIC U. S. Nuclear Regulatory Commission |
| (. July 31, 1979 Page 3 | | (. July 31, 1979 Page 3 |
| : 8. Discussion of Plant Choice For Leibnitz Rule Study - | | : 8. Discussion of Plant Choice For Leibnitz Rule Study - |
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| Response to this item was forvarded under separate cover by Reference 2. | | Response to this item was forvarded under separate cover by Reference 2. |
| : 9. Additional Evaluation of Model Comparisons Attachment 8 provides additional evaluation model comparisons of the TLTA tests with and without ECC injection. The comparisons show that the system is calculated to blowdown faster than measured due primarily to an overestimation of the break flow during the early period of the transient. | | : 9. Additional Evaluation of Model Comparisons Attachment 8 provides additional evaluation model comparisons of the TLTA tests with and without ECC injection. The comparisons show that the system is calculated to blowdown faster than measured due primarily to an overestimation of the break flow during the early period of the transient. |
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| Very truly yours, h,% . k:- | | Very truly yours, h,% . k:- |
| R. H. Bu hholz, Manager | | R. H. Bu hholz, Manager |
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| (. BWR Systems Licensing Safety and Licensing Operation RHB:gmm/421-423 Attachments cc: L. S. Gifford (Bethesda) | | (. BWR Systems Licensing Safety and Licensing Operation RHB:gmm/421-423 Attachments cc: L. S. Gifford (Bethesda) |
| L. Phillips (NRC) bec: E. A. Firestone | | L. Phillips (NRC) bec: E. A. Firestone estumspe 1008 356 |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20094K9541992-03-13013 March 1992 Forwards Supplemental Info Addressing Reasons for Delays Which Have Occurred in Schedule for Const of fossil-fueled Electric Generating Facility at Inola Station Site ML20092M4001992-02-20020 February 1992 Submits Addresses for DM Saunders & Jg Aronson,Per Request in Connection w/920226 Meeting.Addresses for R Butkin & M Graham W/Ok State Government Also Listed ML20092K4941992-02-14014 February 1992 Confirms 920205 Telcon Requesting Meeting Between NRC & Util on 920226 for Util to Present Matl Re Status of Inola Station Site to Demonstrate That Owner Have Satisfied Conditions Contained in 830307 Order ML20209H1221987-02-0202 February 1987 Final Response to FOIA Request.App I Documents Encl & Available in Pdr.App J Documents Withheld (Ref FOIA Exemption 5) ML20207L1381986-11-10010 November 1986 FOIA Request for Info Between Connelly & Officials at NRC Technical Training Ctr in Chattanooga,Tn Re Requirements for Training of NRC Inspectors & for Info Re IE Investigation Into NRC Inspector Training Requirements ML20199E4721986-02-0606 February 1986 Responds to FOIA Request for SECY-85-367A & SECY-85-371. Forwards Portions of Documents Listed in App.Info Also Available in Pdr.App Documents Partially Withheld (Ref FOIA Exemption 5) CY-85-367, FOIA Request for SECY-85-367A & SECY-85-3711985-12-13013 December 1985 FOIA Request for SECY-85-367A & SECY-85-371 ML20138Q8301985-12-0303 December 1985 Further Response to FOIA Request for Records Re Voluntary or Required Redress of Sites Where Const Was Terminated, Including Crbr & Legal Analysis.Forwards App E Documents.App D & E Documents Available in Pdr.Photographs Also Available ML20132C1621985-09-18018 September 1985 Responds to 850612 & 14 Requests for Waiver of 10CFR170 Fees for Withdrawal of CP Application & for Informal Hearings.Requests Denied.Util Not Denied Opportunity in 1981 to Withdraw Application ML20134E3211985-08-14014 August 1985 Advises of Corporate Approval of Change in Planned Dates for Commercial Operation for coal-fired Inola Station,To Be Built on Site of Canceled Black Fox Station.Units 1 & 2 Scheduled for Completion in Dec 1996 & 1998,respectively ML20127A9961985-06-14014 June 1985 Forwards Application for Waiver of Withdrawal Fees Under 10CFR170.12(b) & Brief in Support of Application,Per 850129 Meeting ML20132B4151985-06-12012 June 1985 Forwards Application for Waiver of Withdrawal Fees Under 10CFR170.12(b).NRC Delays in Issuance of CPs Deprived Util of Opportunity to Effect Withdrawal Before 1981 Operative Date of Regulation Charging Withdrawal Fees ML20097C3231984-08-0909 August 1984 Responds to Questions Re Beam Stops ML20091R5721984-06-0808 June 1984 Requests Precise Delineation of Applicable Regulations & Accounting of Prof Staff Hours Expended Re Review Costs Charged for Withdrawal of CP Application.Waiver of Any Interest Penalty Requested ML20088A1641984-04-10010 April 1984 Reiterates 840322 Request for Return of Reed Rept Under 10CFR2.790(b)(5).Reconsideration of Positions Taken in Oct 1980 Split Vote Re Release of GE Repts Requested. Certificate of Svc Encl ML20087K0001984-03-22022 March 1984 Requests Reconsideration of 801009 Split Vote to Release Reed Rept & Sub-Task Force Repts.Return of Repts Requested. Separate Views of Commissioner Hendrie & Certificate of Svc Encl ML20080F8011984-02-0303 February 1984 Requests Deletion of Gw Muench & Rl Range from Address Label ML20136E5971983-10-28028 October 1983 Advises of 831110 Site Visit to Observe Implementation of 820830 Soil Stabilization & Erosion Control Plan ML20069D8691982-09-20020 September 1982 Forwards Black Fox Station Soil Stabilization & Erosion Control Program, Per ASLB 820618 Memorandum & Order.Plan Addresses Concerns Raised in NRC 820602 Submittal ML20054K1531982-06-23023 June 1982 Informs That Final Deficiency Repts for Listed Nonconformances Will Not Be Submitted Until Final Decision Is Made Re Const of Projects ML20054J0181982-06-22022 June 1982 Ack Receipt of Re Withdrawal of CP Application. NRC Responded in Timely Manner to Util Given TMI Accident & Need to Ensure Implementation of Lessons Learned from Accident ML20053D1821982-05-28028 May 1982 Forwards JB West 820527 Affidavit on NRC Concerns Expressed During 820517 Site Visit Re Potential Offsite Environ Impact of Erosion & Siltation in Areas of Inclined Reactor Pressure Vessel Haul Road from Barge Slip Facilities ML20041A5611982-02-16016 February 1982 Announces Cancellation of Black Fox Station,Confirming 820216 Verbal Notification.Site Will Be Preserved for Const of Future Power Generation Projects ML20040A9621982-01-18018 January 1982 Forwards Ok Corporation Commission 820115 Decision in Cause 27068 Re Util Application for Rate Increase ML20039E8561982-01-0606 January 1982 Forwards DF Guyot Affidavit & Interim Containment Loads Rept,Mark III Containment, Revisions 3 & 4.Matls Pertinent to Contentions 3 & 16 Litigated in Dec 1978 & Feb 1979 ML20039B7051981-12-11011 December 1981 Forwards Response to NRC 811203 Ltr Requesting Updated Info on Generic Issues A-10,A-31,A-36,A-42,A-43,A-44,A-45,A-46, A-47 & A-48 for SER Suppl.Svc List Encl ML20039C6051981-12-0909 December 1981 Suppls Response to 810912 & 0603 Ltrs Re Nonconformance Noted in QA Program Insp Rept 99900526/80-01.Revised Drawing List for Black Fox Facility Will Not Be Completed Until Apr 1982 ML20005C1001981-11-0505 November 1981 Forwards Amend 18 to Psar.Amend Contains Matl Responsive to Two Hydrogen Control Requirements of near-term Cp/Mfg License Regulations Which Were Adopted by NRC on 810827. Related Correspondence ML20140B2771981-09-0909 September 1981 Forwards Amend 16 to Psar.Review Copies Forwarded w/810901 Ltr ML20010H4021981-09-0808 September 1981 Forwards Ok Corp Commission,Black Fox Station Economic Viability Study. Related Correspondence ML20140B2851981-09-0101 September 1981 Forwards Amend 16 to Psar.Remaining Copies Forthcoming.Amend Begins New Vol of Psar,Designated as Addendum I ML20010D1641981-08-18018 August 1981 Requests Svc List Be Revised Per Encl ML20009D9311981-07-0808 July 1981 Forwards Response to IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). ML20005A2541981-05-25025 May 1981 Responds to NRC 810423 Ltr Re Nonconformance Noted in QA Program Insp Rept 99900039/81-01.Corrective Actions:Quality Procedures Established to Ensure Control of Insp Activities in Accordance W/Ansi Requirements ML20005A2301981-05-18018 May 1981 Responds to NRC 810416 Ltr Requesting Info Re Status of Black Fox Unit 2 Reactor Vessel.No Activities Performed Since Last Visit ML20003E2571981-03-0202 March 1981 Forwards Ok Association of Electric Cooperatives 810122 Ltr Re Streamlining of Nuclear Plant Licensing & Development of Nuclear Power.Doe 810302 Response Encl ML20126E6991981-02-10010 February 1981 Opposes Facility ML20002D3261980-12-10010 December 1980 FOIA Request for Extracts of 27 safety-related Issues Identified by GE in Reed Rept ML20151B1111980-11-14014 November 1980 Suppls 800116 Response to FOIA Request for GE Reed Rept, & Excerpt Re 27 safety-related Issues.Forwards Commission Memo Re Release of Rept.Rept Cannot Be Released Pending Resolution of Claims.W/O Encl ML19345C2711980-10-29029 October 1980 Requests Info Re Facilities W/Active CPs Pending,License Definitions & Requirements for Floating Nuclear Plants ML19343A9241980-10-21021 October 1980 Petition Urging Support for Wide Use of Solar & Wind Power, & Phasing Out of Nuclear Power Plants,Especially Black Fox, as Soon as Possible ML19340B8331980-10-21021 October 1980 Petitions Govt Representatives to Promote Use of Solar & wind-powered Energy & Phase Out Operation of Nuclear Plants as Quickly as Possible ML19347B5701980-10-10010 October 1980 Demands,On Behalf of Ge,That NRC Return GE Reed Rept Immediately Due to NRC Denial of Request That Rept Be Withheld from Disclosure Under 10CFR2.790.Rept Must Not Be Placed in PDR ML19318B9751980-06-20020 June 1980 Advises That List of Matls to Be Used in Const of Fire Stops & Characteristics Re Flammability & Fire Retardancy Will Be Provided 1 Yr Subsequent to Receipt of CP ML19326D6371980-05-0505 May 1980 Opposes Const of Facilities Until Adequate Emergency Response Plan Can Be Developed.Recommends Responsibility for Emergency Response Plan Be Placed W/Independent Consulting Svc,Not State of Ok ML20126D3201980-04-0404 April 1980 Forwards Corp Commission of State of Ok 800403 Order Denying Request for Approval to Sell Bonds.Psc of Ok Presently Reviewing Order W/View of Filing Appeal W/Ok Supreme Court ML19309G5071980-04-0202 April 1980 Notifies That Representative of Intervenor State of Ok Will Attend NRC 800403 Meeting W/Cp Owners Group.Deplores Fact That Meeting Is First Interaction Between NRC & Applicants Re Development of Generic Policy ML20126D4031980-03-26026 March 1980 Forwards D Plant Expressing Concern Re Possible Meltdown at Facilities.Requests Response ML19309H4781980-03-26026 March 1980 Requests Response to Encl D&D Plant Request That Environ & Site Suitability Hearings in Licensing Proceeding Be Reopened to Address Class 9 Accidents ML18082A1641980-03-24024 March 1980 Forwards Licensee Supplemental Brief Re Motion for Directed Certification & for Stay.Pendency of Class 9 Issue Before Commission Noted in Licensee Motion for Directed Certification & for Stay.Discussed on Pages 7-10 1992-03-13
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20094K9541992-03-13013 March 1992 Forwards Supplemental Info Addressing Reasons for Delays Which Have Occurred in Schedule for Const of fossil-fueled Electric Generating Facility at Inola Station Site ML20092M4001992-02-20020 February 1992 Submits Addresses for DM Saunders & Jg Aronson,Per Request in Connection w/920226 Meeting.Addresses for R Butkin & M Graham W/Ok State Government Also Listed ML20092K4941992-02-14014 February 1992 Confirms 920205 Telcon Requesting Meeting Between NRC & Util on 920226 for Util to Present Matl Re Status of Inola Station Site to Demonstrate That Owner Have Satisfied Conditions Contained in 830307 Order ML20207L1381986-11-10010 November 1986 FOIA Request for Info Between Connelly & Officials at NRC Technical Training Ctr in Chattanooga,Tn Re Requirements for Training of NRC Inspectors & for Info Re IE Investigation Into NRC Inspector Training Requirements CY-85-367, FOIA Request for SECY-85-367A & SECY-85-3711985-12-13013 December 1985 FOIA Request for SECY-85-367A & SECY-85-371 ML20134E3211985-08-14014 August 1985 Advises of Corporate Approval of Change in Planned Dates for Commercial Operation for coal-fired Inola Station,To Be Built on Site of Canceled Black Fox Station.Units 1 & 2 Scheduled for Completion in Dec 1996 & 1998,respectively ML20127A9961985-06-14014 June 1985 Forwards Application for Waiver of Withdrawal Fees Under 10CFR170.12(b) & Brief in Support of Application,Per 850129 Meeting ML20132B4151985-06-12012 June 1985 Forwards Application for Waiver of Withdrawal Fees Under 10CFR170.12(b).NRC Delays in Issuance of CPs Deprived Util of Opportunity to Effect Withdrawal Before 1981 Operative Date of Regulation Charging Withdrawal Fees ML20097C3231984-08-0909 August 1984 Responds to Questions Re Beam Stops ML20091R5721984-06-0808 June 1984 Requests Precise Delineation of Applicable Regulations & Accounting of Prof Staff Hours Expended Re Review Costs Charged for Withdrawal of CP Application.Waiver of Any Interest Penalty Requested ML20088A1641984-04-10010 April 1984 Reiterates 840322 Request for Return of Reed Rept Under 10CFR2.790(b)(5).Reconsideration of Positions Taken in Oct 1980 Split Vote Re Release of GE Repts Requested. Certificate of Svc Encl ML20087K0001984-03-22022 March 1984 Requests Reconsideration of 801009 Split Vote to Release Reed Rept & Sub-Task Force Repts.Return of Repts Requested. Separate Views of Commissioner Hendrie & Certificate of Svc Encl ML20080F8011984-02-0303 February 1984 Requests Deletion of Gw Muench & Rl Range from Address Label ML20069D8691982-09-20020 September 1982 Forwards Black Fox Station Soil Stabilization & Erosion Control Program, Per ASLB 820618 Memorandum & Order.Plan Addresses Concerns Raised in NRC 820602 Submittal ML20054K1531982-06-23023 June 1982 Informs That Final Deficiency Repts for Listed Nonconformances Will Not Be Submitted Until Final Decision Is Made Re Const of Projects ML20053D1821982-05-28028 May 1982 Forwards JB West 820527 Affidavit on NRC Concerns Expressed During 820517 Site Visit Re Potential Offsite Environ Impact of Erosion & Siltation in Areas of Inclined Reactor Pressure Vessel Haul Road from Barge Slip Facilities ML20041A5611982-02-16016 February 1982 Announces Cancellation of Black Fox Station,Confirming 820216 Verbal Notification.Site Will Be Preserved for Const of Future Power Generation Projects ML20040A9621982-01-18018 January 1982 Forwards Ok Corporation Commission 820115 Decision in Cause 27068 Re Util Application for Rate Increase ML20039E8561982-01-0606 January 1982 Forwards DF Guyot Affidavit & Interim Containment Loads Rept,Mark III Containment, Revisions 3 & 4.Matls Pertinent to Contentions 3 & 16 Litigated in Dec 1978 & Feb 1979 ML20039B7051981-12-11011 December 1981 Forwards Response to NRC 811203 Ltr Requesting Updated Info on Generic Issues A-10,A-31,A-36,A-42,A-43,A-44,A-45,A-46, A-47 & A-48 for SER Suppl.Svc List Encl ML20039C6051981-12-0909 December 1981 Suppls Response to 810912 & 0603 Ltrs Re Nonconformance Noted in QA Program Insp Rept 99900526/80-01.Revised Drawing List for Black Fox Facility Will Not Be Completed Until Apr 1982 ML20005C1001981-11-0505 November 1981 Forwards Amend 18 to Psar.Amend Contains Matl Responsive to Two Hydrogen Control Requirements of near-term Cp/Mfg License Regulations Which Were Adopted by NRC on 810827. Related Correspondence ML20140B2771981-09-0909 September 1981 Forwards Amend 16 to Psar.Review Copies Forwarded w/810901 Ltr ML20010H4021981-09-0808 September 1981 Forwards Ok Corp Commission,Black Fox Station Economic Viability Study. Related Correspondence ML20140B2851981-09-0101 September 1981 Forwards Amend 16 to Psar.Remaining Copies Forthcoming.Amend Begins New Vol of Psar,Designated as Addendum I ML20010D1641981-08-18018 August 1981 Requests Svc List Be Revised Per Encl ML20009D9311981-07-0808 July 1981 Forwards Response to IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). ML20005A2541981-05-25025 May 1981 Responds to NRC 810423 Ltr Re Nonconformance Noted in QA Program Insp Rept 99900039/81-01.Corrective Actions:Quality Procedures Established to Ensure Control of Insp Activities in Accordance W/Ansi Requirements ML20005A2301981-05-18018 May 1981 Responds to NRC 810416 Ltr Requesting Info Re Status of Black Fox Unit 2 Reactor Vessel.No Activities Performed Since Last Visit ML20003E2571981-03-0202 March 1981 Forwards Ok Association of Electric Cooperatives 810122 Ltr Re Streamlining of Nuclear Plant Licensing & Development of Nuclear Power.Doe 810302 Response Encl ML20126E6991981-02-10010 February 1981 Opposes Facility ML20002D3261980-12-10010 December 1980 FOIA Request for Extracts of 27 safety-related Issues Identified by GE in Reed Rept ML19345C2711980-10-29029 October 1980 Requests Info Re Facilities W/Active CPs Pending,License Definitions & Requirements for Floating Nuclear Plants ML19340B8331980-10-21021 October 1980 Petitions Govt Representatives to Promote Use of Solar & wind-powered Energy & Phase Out Operation of Nuclear Plants as Quickly as Possible ML19343A9241980-10-21021 October 1980 Petition Urging Support for Wide Use of Solar & Wind Power, & Phasing Out of Nuclear Power Plants,Especially Black Fox, as Soon as Possible ML19347B5701980-10-10010 October 1980 Demands,On Behalf of Ge,That NRC Return GE Reed Rept Immediately Due to NRC Denial of Request That Rept Be Withheld from Disclosure Under 10CFR2.790.Rept Must Not Be Placed in PDR ML19318B9751980-06-20020 June 1980 Advises That List of Matls to Be Used in Const of Fire Stops & Characteristics Re Flammability & Fire Retardancy Will Be Provided 1 Yr Subsequent to Receipt of CP ML19326D6371980-05-0505 May 1980 Opposes Const of Facilities Until Adequate Emergency Response Plan Can Be Developed.Recommends Responsibility for Emergency Response Plan Be Placed W/Independent Consulting Svc,Not State of Ok ML20126D3201980-04-0404 April 1980 Forwards Corp Commission of State of Ok 800403 Order Denying Request for Approval to Sell Bonds.Psc of Ok Presently Reviewing Order W/View of Filing Appeal W/Ok Supreme Court ML19309G5071980-04-0202 April 1980 Notifies That Representative of Intervenor State of Ok Will Attend NRC 800403 Meeting W/Cp Owners Group.Deplores Fact That Meeting Is First Interaction Between NRC & Applicants Re Development of Generic Policy ML20126D4031980-03-26026 March 1980 Forwards D Plant Expressing Concern Re Possible Meltdown at Facilities.Requests Response ML19309H4781980-03-26026 March 1980 Requests Response to Encl D&D Plant Request That Environ & Site Suitability Hearings in Licensing Proceeding Be Reopened to Address Class 9 Accidents ML18082A1641980-03-24024 March 1980 Forwards Licensee Supplemental Brief Re Motion for Directed Certification & for Stay.Pendency of Class 9 Issue Before Commission Noted in Licensee Motion for Directed Certification & for Stay.Discussed on Pages 7-10 ML19344D6921980-03-18018 March 1980 Submits Addl Info in Support of 800206 Request for Extension to Review ALAB-573 Class 9 Accident Issue.Lack of NRC Opposition to Ok Request & Recent Proliferation of Info Support Extension ML19309B5141980-03-15015 March 1980 Suggests Hearings on Const of Reactor Did Not Address Meltdown Issues.Tulsa Should Not Be Made Site for Potential Nuclear Mistake.Utils Should Build Plants Away from Populated Areas.Requests Reopening of Hearings ML19309B5241980-03-15015 March 1980 Requests That NRC Hold Meetings in Tulsa,Ok Re Emergency Evacuation Zone Around Nuclear Plants.Plans Should Be More Thorough to Protect People If Meltdown Should Occur ML20126C6161980-03-15015 March 1980 Expresses Concern Re NRC Refusal to Address Meltdown Issue at Hearings.Class 9 Accident Is Distinct Possibility & Should Be Thoroughly Examined.Environ & Site Suitablity Hearings Should Be Reopened ML20126C5581980-03-15015 March 1980 Suggests Local self-reliant,self-sufficient Communities Are Solution to Present Problems.Opposes All Forms of Nuclear Power.Min Amount of Energy from Coal & Gas Should Be Needed for Mfg Useful Tools,Bicycles & Efficient Tractors ML19312D4881980-02-29029 February 1980 Requests Reopening of Environ & Site Suitability Hearings for Facilities to Explore Issue of Meltdown ML20126C0301980-02-29029 February 1980 Urges Meetings in Tulsa,Ok Re Emergency Evacuation Area Around Facility.Current Plans Are Inadequate 1992-03-13
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20005A2541981-05-25025 May 1981 Responds to NRC 810423 Ltr Re Nonconformance Noted in QA Program Insp Rept 99900039/81-01.Corrective Actions:Quality Procedures Established to Ensure Control of Insp Activities in Accordance W/Ansi Requirements ML20005A2301981-05-18018 May 1981 Responds to NRC 810416 Ltr Requesting Info Re Status of Black Fox Unit 2 Reactor Vessel.No Activities Performed Since Last Visit ML19208C4501979-07-31031 July 1979 Discusses Addl Info Re two-loop Test Appartus Per NRC 790524 Request.Forwards Summary of 790824 Meeting Slides, Results from Mass & Energy Balance,Scaling,Discussion & Vaporization Data Base.W/O Encl ML19208C4491979-07-20020 July 1979 Responds to NRC 790709 Ltr & Supplements GE 790615 Ltr Re two-loop Test Apparatus.Clarifies Addl Info to Be Provided by 790731 1981-05-25
[Table view] |
Text
__ __ _.- _ _ _ __ .__ _ . . _ _ _ _
EXHIBIT II , . .
NUCLEAR ENERGY GENERALh ELECTRIC PROJECTS DIVISION GENERAL ELECTRIC COMPANY.175 CURTNER AVE., SAN JOSE. CALIFORNIA 95125 ,
MC682,(408)925-5722 MFN-198-79 July 31,1979 PTPfPfin f;rpp J
m AUG c 1979
(
U. S. Nuclear Regulatory Commission Division of Systems Safety y jggcg Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Frank Schroeder, Acting Director Division of Systems Safety Gentlemen:
SUBJECT:
ADDITIONAL TLTA INFORMATION
Reference:
- 1) G. G. Sherwood letter to Frank Schroeder, dated
, ( 6/15/79, "Two Loop Test Apparatus (TLTA) Results"
- 2) R. H. Buchholz letter to Frank Schroeder, dated 7/13/79, "Leibnitz Rule in LOCA Models" Attached herein is the additional TLTA information requested by NRC during the May 24, 1379 meeting and committed by General Electric in Reference 1. Also included are additional model comparisons as requested by the NRC staff. The requested information is provided in eight attach-me its.which are summarized below for your convenience.
- 1. A Writeup to Support the May 24 Slides Attachment 1 is a summary of the May 24 meeting slides which presented the results of the recent TLTA tests. The relevant phenomena controlling the TLTA thermal hydraulic and bundle heatup response are identified and discussed. Comparisons of test results with and without Emergency Core Cooling (ECC) injection and a summary of the peak and low bur.dle power tests are also provided.
- 2. Steam Seoarator AP and Break Flow Discussion Attachment 2 presents the results from the mass and energy balance obtained from the TLTA data for the tests with and with.out ECC injection. These results clearly show that for the test with ECC injection, more liquid was entrained out the break and the buik discharged fluid quality was clearly lower. It is further concluded
( that fluid conditions discharged from the break led to the differences in depressurization rate observed between the two tests. Attachment 3 provides analysis of the steam separator pressure drop data. The ip08 9 79092e0954
GENER AL h ELECTRIC
(. U. S. Nuclear Regulatory Commission July 31,1979 Page 2
~
preliminary evaluation of the separator AP suggested that the steam
~
flow through the separator was lower for the test with ECC injected.
Results from Attachment 2 are utilized in Attachment 3 to further substantiate that the flow through the separator was indeed lower.
Additional analysis to include the possible effects of liquid entrainment out the separator are also included to demonstrate that the conclusions remain unchanged.
- 3. TLTA Scaling Discussion Attachment 4 summarizes the TLTA scaling basis and supporting aralysis. It is demonstrated that the relevant BWR LOCA thermal hydraulic phenomena can be evaluated in the TLTA.
- 4. Vaporization Data Base Attachment 5 provides further explanation of the facility and method used for the 1974 test which provided the data base for the vaporization correlation. Based on the recent results and data interpretation from the TLTA, it is concluded that the facility and system conditions in TLTA are similar to those of the 1974 vapori-
{
zation tests.
- 5. Side Entry Orifice CCFL Attachment 6 describes the conservatism resultir.g from not including Side Entry Orifice (SEO) Counter Current Flow limiting (CCFL) in the General Electric evaluation model. It states that inclusion of SEO CCFL would result in core uncovery delay and earlier reflooding which would result in improved heat transfer and lower PCT's.
- 6. The Grid Spacer Water Accumulation Attachment 7 provides a discussion of the CCFL characteristics across a bundle. It is concluded that, while there is a potential for water accumulation to exist momentarily when there is a sudden reduction in the bundle inlet flow (e.g., during the flow coastdown period or lower plenum flashing period), accumulation will not occur during the reflood period.
- 7. Justification of Conservatism of the Heat Transfer Coefficients used in SAFE The information provided in Attachment 6 demonstrates that the heat transfer coefficients used in the SAFE Computer Program between the nucleate boiling to the core spray cooling regimes are the appropriate
( values.
1008 355
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GEN ER AL $ ELECTRIC U. S. Nuclear Regulatory Commission
(. July 31, 1979 Page 3
- 8. Discussion of Plant Choice For Leibnitz Rule Study -
Response to this item was forvarded under separate cover by Reference 2.
- 9. Additional Evaluation of Model Comparisons Attachment 8 provides additional evaluation model comparisons of the TLTA tests with and without ECC injection. The comparisons show that the system is calculated to blowdown faster than measured due primarily to an overestimation of the break flow during the early period of the transient.
The information provided here closes out all the TLTA commitments made in Reference 1 and during discussions with the NRC staff. If further clarification is required, please contact R. N. Woldstad at (408) 925-2539 or L. F. Rodriguez at (408) 925-2460.
Very truly yours, h,% . k:-
R. H. Bu hholz, Manager
(. BWR Systems Licensing Safety and Licensing Operation RHB:gmm/421-423 Attachments cc: L. S. Gifford (Bethesda)
L. Phillips (NRC) bec: E. A. Firestone estumspe 1008 356
.