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| {{#Wiki_filter:i k{N 8005050 %,77' | | {{#Wiki_filter:i k{N 8005050 %,77' Babcock &Wilcox nesea,cn aoo oe eionment omision P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 April 30, 1980 Mr. Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 License: CX-10, docket 50-13 Reference 1 BAW-1484-7 " Critical Experiments Supporting Close Proximity Water Storage of Power Reactor Fuel" July 3 9/9 Reference 2 Letter to Mr. Robert W. Reid from A. F. Olsen, dated October 18, 1979, requesting license amendment Reference 3 Letter to Mr. Robert W. Reid from A. F. Olsen, dated April 11, 1980, providing additional information in support of amendment request |
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| Babcock &Wilcox nesea,cn aoo oe eionment omision P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 April 30, 1980 Mr. Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 License: CX-10, docket 50-13 Reference 1 BAW-1484-7 " Critical Experiments Supporting Close Proximity Water Storage of Power Reactor Fuel" July 3 9/9 Reference 2 Letter to Mr. Robert W. Reid from A. F. Olsen, dated October 18, 1979, requesting license amendment Reference 3 Letter to Mr. Robert W. Reid from A. F. Olsen, dated April 11, 1980, providing additional information in support of amendment request | |
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| ==Dear Mr. Reid:== | | ==Dear Mr. Reid:== |
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| It has been brought to our attention by Mr. Harold Bernard and Ms. Jocelyn Mitchell of your staff, that we did not include in our analysis the effect of | | It has been brought to our attention by Mr. Harold Bernard and Ms. Jocelyn Mitchell of your staff, that we did not include in our analysis the effect of uncertainty in dp/dt at minimum critical moderator height for the accident condition. |
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| uncertainty in dp/dt at minimum critical moderator height for the accident condition. | |
| H2 p= C/2 (H + A)4 | | H2 p= C/2 (H + A)4 |
| ("9""*I " 1) | | ("9""*I " 1) |
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| Mr. Robert W. Reid April 30, 1980 Page 2 uncertainty is due to an uncertainty in the parameter C. Since equation 1 shows p to be cirectly proportional to C, we have considered the case where C is uncertain by 10.7%. | | Mr. Robert W. Reid April 30, 1980 Page 2 uncertainty is due to an uncertainty in the parameter C. Since equation 1 shows p to be cirectly proportional to C, we have considered the case where C is uncertain by 10.7%. |
| The reactivity addition rate is calculated fr,m the equation: | | The reactivity addition rate is calculated fr,m the equation: |
| 6p AC g= (Ho + A)3 (equation 2) | | 6p AC g= (Ho + A)3 (equation 2) where: |
| ,
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| where: | |
| n C/2 o = - A | | n C/2 o = - A |
| #ex + - 0.18 1 5 + A) p = | | #ex + - 0.18 1 5 + A) p = |
| excess reactivity (% AK/K) obtained for full | | excess reactivity (% AK/K) obtained for full moderator height by KENO calculation. |
| **
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| moderator height by KENO calculation. | |
| = | | = |
| A 0.0459 cm/sec = | | A 0.0459 cm/sec = |
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| In our supplemental submittal (Reference 3), we made the calculation using a value for pex of 20.6% AK/K, and a value for C of 61688 cm2 % AK/K. (The value of p was' raised from its previous value of 18.7% AK/K to account for a possible 1.hk AK/K error in the results of the KENO calculation.) The value obtained for dp/dt was 0.054% AK/K/sec (which we rounded up to 0.055 in our supplemental submittal). If we reduce C by 10.7%, we obtain a value' for dp/dt of 0.056% AK/K/sec. | | In our supplemental submittal (Reference 3), we made the calculation using a value for pex of 20.6% AK/K, and a value for C of 61688 cm2 % AK/K. (The value of p was' raised from its previous value of 18.7% AK/K to account for a possible 1.hk AK/K error in the results of the KENO calculation.) The value obtained for dp/dt was 0.054% AK/K/sec (which we rounded up to 0.055 in our supplemental submittal). If we reduce C by 10.7%, we obtain a value' for dp/dt of 0.056% AK/K/sec. |
| Being very conservative, we have examined the combined effect of (1) re-ducing C by'10.7%, (2) increasing p ex by 1.9% AK/K and (3) reducing the fuel | | Being very conservative, we have examined the combined effect of (1) re-ducing C by'10.7%, (2) increasing p ex by 1.9% AK/K and (3) reducing the fuel |
| , temperature coefficient by 10%. Results from the point kinetics model of the | | , temperature coefficient by 10%. Results from the point kinetics model of the maximum credible accident predict that the peak clad temperature would be l |
| !
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| maximum credible accident predict that the peak clad temperature would be l | |
| l l | | l l |
| l L- - _ | | l L- - _ |
| i | | i |
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| | V Mr. Robert W. Reid April 30, 1980 Page 3 ' |
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| Mr. Robert W. Reid April 30, 1980 Page 3 ' | |
| raisgd to 832" F. This is still considerably below the acceptable value of 1050 F given in amendment 5. | | raisgd to 832" F. This is still considerably below the acceptable value of 1050 F given in amendment 5. |
| Thank you for your prompt consideration and if you require additional information, please contact me. | | Thank you for your prompt consideration and if you require additional information, please contact me. |
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| A. F. Olsen License Administrator nwt Attachment Subscribed and sworn to'before me this N NII day of 6 , 1980. | | A. F. Olsen License Administrator nwt Attachment Subscribed and sworn to'before me this N NII day of 6 , 1980. |
| F 6 /d(, | | F 6 /d(, |
| Notary Public Hy commission expires [k-/C'[//Yf | | Notary Public Hy commission expires [k-/C'[//Yf t}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARIA-98-313, First Final Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App a1998-09-0404 September 1998 First Final Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App a ML20239A1371998-09-0404 September 1998 First Final Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App a ML20239A4271992-06-0404 June 1992 Forwards Proposed Survey Plan for Pathfinder Generating Station,Sioux Fall,Sd, for Approval ML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20151A5041988-03-30030 March 1988 Forwards Executed Amend 22 to Indemnity Agreement B-8, Terminating Agreement ML20150D9721988-03-18018 March 1988 Informs of NRC Relocation to Stated Address.Mailing Address Unchanged.A Adams Project Manager & TS Michaels back-up Project Manager ML20147D0271988-02-26026 February 1988 Forwards Amend 22 to Indemnity Agreement B-8,order Terminating License CX-10,safety Evaluation & Environ Assessment ML20235K2791987-09-29029 September 1987 Forwards Insp Rept 50-013/87-01 on 870917-21.No Violations or Deviations Noted.Contractor Rept, Confirmatory Radiological Survey of CX-10 Area,Bldg A,Lynchburg Research Ctr Also Encl ML20235D6541987-09-16016 September 1987 Notification of 871027-28 Nuclear Fuel Cycle Licensee Workshop in Atlanta,Ga.Map & List of Hotels Encl.W/O Stated Encls ML20215B0101987-06-11011 June 1987 Informs of Recent Reorganization of Nrr.A Adams Designated as Facility Project Manager ML20214T5451986-11-24024 November 1986 Assigns Jj Dosa as Project Manager to Facility ML20199J9421986-07-0202 July 1986 Forwards Revised Section 8 of Dismantling Plan for CX-10 Reactor.Changes Due to Reorganization ML20206L5901986-06-24024 June 1986 Forwards Replacement Table 2-1 Providing Specific Info for Final Survey Rept for License CX-10 ML20140G7021986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactors & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20153H0171986-02-20020 February 1986 Advises That Ofc of Resource Mgt Will Be Sending Bill for 840807 Application for Decommissioning License CX-10. Discussion of 6-month Billing Process Submitted ML20138A0301985-11-27027 November 1985 Ack Receipt of 850828 & 1114 Ltrs Informing NRC of Steps Taken to Correct Violation Noted in Insp Repts 50-013/85-01 & 70-0824/85-05 IR 05000013/19850011985-10-25025 October 1985 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-013/85-01 & 70-0824/85-05.Damage to Drum Occurred During Transport & Due to Condition Normally Incident to Transportation ML20137M4981985-08-28028 August 1985 Responds to NRC Re Violations Noted in Insp Repts 50-013/85-01 & 70-0824/85-05.Corrective Actions:Shipment of Fissle Class 2 Packages Suspended Until Checklist Containing Requirements for Shipments Developed ML20133P7361985-07-29029 July 1985 Forwards Insp Repts 50-013/85-01 & 70-0824/85-05 on 850610-14 & Notice of Violation ML20116D8891985-04-17017 April 1985 Requests Info Re Authorization for B&W to Dismantle & Decontaminate Reactor Facility Near Lynchburg,Va ML20101S5501985-01-29029 January 1985 Requests That Lynchburg Research Ctr Be Granted Authorization to Proceed W/Dismantling & Decontamination of Facility.All Fuel Possessed Under License CX-10 Shipped to DOE Oak Ridge,Tn Facility ML20099D1301984-11-15015 November 1984 Forwards Responses to 841012 Questions Re 840807 Application for Dismantlement & Termination of CX-10 Facility ML20091P5301984-06-0808 June 1984 Requests Exemption from Requirements of 10CFR50.54(r) Re Emergency Plan Due to Dismantling of CX-10 Facility ML20087N3721984-03-26026 March 1984 Forwards Endorsements 108 & 109 to Nelia Policy NF-83, Endorsement 110 to Nelia Policy NF-111 & Endorsement 42 to Maelu Policy MF-84 ML20082F1031983-11-22022 November 1983 Requests Waiver of Operator Requalification Program & 10CFR55.31(e) Requirement to Permit Operators & Senior Operators to Perform Fuel Handling Functions ML20082H6541983-11-15015 November 1983 Forwards Rev 3 to Security Plan.Rev Withheld (Ref 10CFR2.790) ML20082H6651983-09-19019 September 1983 Forwards Rev 3 to Page 6-2 of Reactor Security Plan.Page Withheld ML20065G7391982-09-27027 September 1982 Details Evaluation of Discrepancy Between Electronically Simulated Reactor & Channel Periods Revealed in Calibr Test Performed on Log-N-2 Channel.No Unsafe Condition Existed & No Tech Spec Violation Occurred ML20069G4001982-09-23023 September 1982 Forwards Emergency Plan,Revision 0 ML20062D7741982-08-0303 August 1982 Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC ML20062F2781982-07-20020 July 1982 Forwards Order Terminating License R-47 in Accordance w/810723 Application & Amend 21 to Indemnity Agreement 8 ML20054M8861982-06-18018 June 1982 Forwards IE Insp Rept 50-099/82-03 on 820525-26.No Noncompliance Noted ML20054L3881982-06-16016 June 1982 Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl ML20052A8801982-04-23023 April 1982 Advises That Dismantling & Decontamination of Facility Have Been Completed.Nrc Verification Survey & Facility Release for Unrestricted Use Requested.Survey Results Encl ML20041C6691982-01-26026 January 1982 Forwards Revisions to Facility Security Plan.Revisions Withheld (Ref 10CFR2.790) ML20010G2441981-09-10010 September 1981 Requests That Lynchburg Research Ctr Be Granted Exemption from Requirements for Submittal of Revised Emergency Plan Per 10CFR50.47.Proposed Plan Would Not Be Implemented Until After Facility Fuel Has Been Removed ML20009B2431981-07-0909 July 1981 Forwards Rept Re Critical Experiment Program Authorized by Amend 11 to License CX-10.Experimental Measurements Verified That Core Parameters Are within Prescribed License Limits ML20004D3711981-06-0404 June 1981 Requests Meeting W/Nrc to Discuss Requirements Re Planned Dismantling of Lynchburg Pool Reactor for Termination of License R-47 ML20004D3701981-06-0303 June 1981 Forwards Updated Security Plan.Plan Withheld (Ref 10CFR2.790) ML19347F2811981-05-13013 May 1981 Forwards Endorsement 98 to Nelia Policies NF-111 & NF-83 ML20003E4401981-03-31031 March 1981 Forwards Info Re Security Plan,In Response to NRC 810302 Request.Info Withheld (Ref 10CFR2.790) ML19345B6481980-11-25025 November 1980 Discusses NRC 801106 Ltr Requesting Submittal of Names of Personnel Responsible for Emergency Planning.Nrc Should Direct Such Requests to AF Olsen ML19338E9001980-10-0101 October 1980 Forwards Executed Amend 20 to Indemnity Agreement B-8, Modifying Prefatory Language of Paragraph 5,Article I Re Transportation ML19331D6741980-08-29029 August 1980 Forwards Tech Specs Incorporating Changes Proposed by 790501-02 Ltrs & Submitted in Connection w/780303 Request for Renewal of License R-47 ML19323F5901980-05-19019 May 1980 Forwards Revised Page & App to Amended Reactor Security Plan.Encl Withheld (Ref 10CFR2.790) ML20149K1911980-05-0707 May 1980 Generic Ltr 80-38 to All Nonpower Reactor Licensees Re NPR Physical Protection Requirements.Summary of Certain NPR Physical Protection Requirements Encl & Should Aid in Determining Safeguards Requirements Applicable to Facility ML19312D8631980-04-30030 April 1980 Submits Addl Info Re Equation for Effect of Uncertainty in Dp/Dt at Min Critical Moderator Height for Accident Condition ML19309E0731980-04-11011 April 1980 Submits Addl Info Re 791018 Amend Request.Describes Range of Allowable Nonmoderator to Moderator Ratio & Computer Codes Used for front-end Calculations for Analysis of Max Credible Accident ML19257B9261980-01-16016 January 1980 Forwards Page 18a for Insertion in 791023 Rept Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. 1998-09-04
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20239A4271992-06-0404 June 1992 Forwards Proposed Survey Plan for Pathfinder Generating Station,Sioux Fall,Sd, for Approval ML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML20151A5041988-03-30030 March 1988 Forwards Executed Amend 22 to Indemnity Agreement B-8, Terminating Agreement ML20199J9421986-07-0202 July 1986 Forwards Revised Section 8 of Dismantling Plan for CX-10 Reactor.Changes Due to Reorganization ML20206L5901986-06-24024 June 1986 Forwards Replacement Table 2-1 Providing Specific Info for Final Survey Rept for License CX-10 ML20137M4981985-08-28028 August 1985 Responds to NRC Re Violations Noted in Insp Repts 50-013/85-01 & 70-0824/85-05.Corrective Actions:Shipment of Fissle Class 2 Packages Suspended Until Checklist Containing Requirements for Shipments Developed ML20116D8891985-04-17017 April 1985 Requests Info Re Authorization for B&W to Dismantle & Decontaminate Reactor Facility Near Lynchburg,Va ML20101S5501985-01-29029 January 1985 Requests That Lynchburg Research Ctr Be Granted Authorization to Proceed W/Dismantling & Decontamination of Facility.All Fuel Possessed Under License CX-10 Shipped to DOE Oak Ridge,Tn Facility ML20099D1301984-11-15015 November 1984 Forwards Responses to 841012 Questions Re 840807 Application for Dismantlement & Termination of CX-10 Facility ML20091P5301984-06-0808 June 1984 Requests Exemption from Requirements of 10CFR50.54(r) Re Emergency Plan Due to Dismantling of CX-10 Facility ML20087N3721984-03-26026 March 1984 Forwards Endorsements 108 & 109 to Nelia Policy NF-83, Endorsement 110 to Nelia Policy NF-111 & Endorsement 42 to Maelu Policy MF-84 ML20082F1031983-11-22022 November 1983 Requests Waiver of Operator Requalification Program & 10CFR55.31(e) Requirement to Permit Operators & Senior Operators to Perform Fuel Handling Functions ML20082H6541983-11-15015 November 1983 Forwards Rev 3 to Security Plan.Rev Withheld (Ref 10CFR2.790) ML20082H6651983-09-19019 September 1983 Forwards Rev 3 to Page 6-2 of Reactor Security Plan.Page Withheld ML20065G7391982-09-27027 September 1982 Details Evaluation of Discrepancy Between Electronically Simulated Reactor & Channel Periods Revealed in Calibr Test Performed on Log-N-2 Channel.No Unsafe Condition Existed & No Tech Spec Violation Occurred ML20069G4001982-09-23023 September 1982 Forwards Emergency Plan,Revision 0 ML20062D7741982-08-0303 August 1982 Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC ML20052A8801982-04-23023 April 1982 Advises That Dismantling & Decontamination of Facility Have Been Completed.Nrc Verification Survey & Facility Release for Unrestricted Use Requested.Survey Results Encl ML20041C6691982-01-26026 January 1982 Forwards Revisions to Facility Security Plan.Revisions Withheld (Ref 10CFR2.790) ML20010G2441981-09-10010 September 1981 Requests That Lynchburg Research Ctr Be Granted Exemption from Requirements for Submittal of Revised Emergency Plan Per 10CFR50.47.Proposed Plan Would Not Be Implemented Until After Facility Fuel Has Been Removed ML20009B2431981-07-0909 July 1981 Forwards Rept Re Critical Experiment Program Authorized by Amend 11 to License CX-10.Experimental Measurements Verified That Core Parameters Are within Prescribed License Limits ML20004D3711981-06-0404 June 1981 Requests Meeting W/Nrc to Discuss Requirements Re Planned Dismantling of Lynchburg Pool Reactor for Termination of License R-47 ML20004D3701981-06-0303 June 1981 Forwards Updated Security Plan.Plan Withheld (Ref 10CFR2.790) ML19347F2811981-05-13013 May 1981 Forwards Endorsement 98 to Nelia Policies NF-111 & NF-83 ML20003E4401981-03-31031 March 1981 Forwards Info Re Security Plan,In Response to NRC 810302 Request.Info Withheld (Ref 10CFR2.790) ML19345B6481980-11-25025 November 1980 Discusses NRC 801106 Ltr Requesting Submittal of Names of Personnel Responsible for Emergency Planning.Nrc Should Direct Such Requests to AF Olsen ML19338E9001980-10-0101 October 1980 Forwards Executed Amend 20 to Indemnity Agreement B-8, Modifying Prefatory Language of Paragraph 5,Article I Re Transportation ML19331D6741980-08-29029 August 1980 Forwards Tech Specs Incorporating Changes Proposed by 790501-02 Ltrs & Submitted in Connection w/780303 Request for Renewal of License R-47 ML19323F5901980-05-19019 May 1980 Forwards Revised Page & App to Amended Reactor Security Plan.Encl Withheld (Ref 10CFR2.790) ML19312D8631980-04-30030 April 1980 Submits Addl Info Re Equation for Effect of Uncertainty in Dp/Dt at Min Critical Moderator Height for Accident Condition ML19309E0731980-04-11011 April 1980 Submits Addl Info Re 791018 Amend Request.Describes Range of Allowable Nonmoderator to Moderator Ratio & Computer Codes Used for front-end Calculations for Analysis of Max Credible Accident ML19257B9261980-01-16016 January 1980 Forwards Page 18a for Insertion in 791023 Rept Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. ML19260B2441979-12-0303 December 1979 Submits Addl Info in Support of Request for Amend to License CX-10.Discusses Probability of Max Credible Accident & Need for Amend to Tech Specs ML19256E2251979-10-26026 October 1979 Forwards Executed Amend 20 to Indemnity Agreement B-8 & Amend 2 to Indemnity Agreement G-2 ML19254E4591979-10-18018 October 1979 Requests Amend to License CX-10 to Authorize Critical Experiments Utilizing nonmoderator-to-moderator Ratios Described in Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. ML19276H0231979-08-15015 August 1979 Responds to 790730 Ltr Requesting Info from Nonpower Reactor Licensees Re Effect of Safeguards Rule.Upgrade Rule Necessitates Protection of Reactor as Category I Facility for Physical Protection Purposes ML19242A7741979-08-0101 August 1979 Forwards,Per s Ramos Request,Analyses of Design Basis Accident & Loca,In Support of Renewal of License R-47 ML19289E9111979-05-21021 May 1979 Forwards Executed Amend 1 to Indemnity Agreement G-2 & Amend 19 to Indemnity Agreement B-8 ML19305A3711979-03-0707 March 1979 Responds to 790301 Telcon Request.Forwards 1977 Form 10K, Annual Rept to Sec Supporting Renewal of License R-47. Form Is Last One Transmitted to Sec Re B&W Merger Into Jr Mcdermott Co ML19289D1831979-02-16016 February 1979 Responds to 790202 Ltr.Provides Details of Amounts & Enrichments of Snm.Agrees to Add License Condition Requiring Mod of Reactor Security Plan.Claims No Exemptions for Any SNM ML19269C5211979-01-29029 January 1979 Responds to NRC 780821 Ltr.Forwards Info Re Financial Data, Business Conducted,Organizational Structure,Radiological Monitoring,Safety Hazards & Tech Specs ML20147D7791978-12-0808 December 1978 Concurs That Inspec Rept Contains No Proprietary Info & Agrees to Placing It in NRC PDR 1992-06-04
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20151A5041988-03-30030 March 1988 Forwards Executed Amend 22 to Indemnity Agreement B-8, Terminating Agreement ML20199J9421986-07-0202 July 1986 Forwards Revised Section 8 of Dismantling Plan for CX-10 Reactor.Changes Due to Reorganization ML20206L5901986-06-24024 June 1986 Forwards Replacement Table 2-1 Providing Specific Info for Final Survey Rept for License CX-10 ML20137M4981985-08-28028 August 1985 Responds to NRC Re Violations Noted in Insp Repts 50-013/85-01 & 70-0824/85-05.Corrective Actions:Shipment of Fissle Class 2 Packages Suspended Until Checklist Containing Requirements for Shipments Developed ML20101S5501985-01-29029 January 1985 Requests That Lynchburg Research Ctr Be Granted Authorization to Proceed W/Dismantling & Decontamination of Facility.All Fuel Possessed Under License CX-10 Shipped to DOE Oak Ridge,Tn Facility ML20099D1301984-11-15015 November 1984 Forwards Responses to 841012 Questions Re 840807 Application for Dismantlement & Termination of CX-10 Facility ML20091P5301984-06-0808 June 1984 Requests Exemption from Requirements of 10CFR50.54(r) Re Emergency Plan Due to Dismantling of CX-10 Facility ML20082F1031983-11-22022 November 1983 Requests Waiver of Operator Requalification Program & 10CFR55.31(e) Requirement to Permit Operators & Senior Operators to Perform Fuel Handling Functions ML20082H6541983-11-15015 November 1983 Forwards Rev 3 to Security Plan.Rev Withheld (Ref 10CFR2.790) ML20082H6651983-09-19019 September 1983 Forwards Rev 3 to Page 6-2 of Reactor Security Plan.Page Withheld ML20065G7391982-09-27027 September 1982 Details Evaluation of Discrepancy Between Electronically Simulated Reactor & Channel Periods Revealed in Calibr Test Performed on Log-N-2 Channel.No Unsafe Condition Existed & No Tech Spec Violation Occurred ML20069G4001982-09-23023 September 1982 Forwards Emergency Plan,Revision 0 ML20062D7741982-08-0303 August 1982 Forwards Amend 21 to Indemnity Agreement B-8,in Response to NRC ML20052A8801982-04-23023 April 1982 Advises That Dismantling & Decontamination of Facility Have Been Completed.Nrc Verification Survey & Facility Release for Unrestricted Use Requested.Survey Results Encl ML20041C6691982-01-26026 January 1982 Forwards Revisions to Facility Security Plan.Revisions Withheld (Ref 10CFR2.790) ML20010G2441981-09-10010 September 1981 Requests That Lynchburg Research Ctr Be Granted Exemption from Requirements for Submittal of Revised Emergency Plan Per 10CFR50.47.Proposed Plan Would Not Be Implemented Until After Facility Fuel Has Been Removed ML20009B2431981-07-0909 July 1981 Forwards Rept Re Critical Experiment Program Authorized by Amend 11 to License CX-10.Experimental Measurements Verified That Core Parameters Are within Prescribed License Limits ML20004D3711981-06-0404 June 1981 Requests Meeting W/Nrc to Discuss Requirements Re Planned Dismantling of Lynchburg Pool Reactor for Termination of License R-47 ML20004D3701981-06-0303 June 1981 Forwards Updated Security Plan.Plan Withheld (Ref 10CFR2.790) ML20003E4401981-03-31031 March 1981 Forwards Info Re Security Plan,In Response to NRC 810302 Request.Info Withheld (Ref 10CFR2.790) ML19345B6481980-11-25025 November 1980 Discusses NRC 801106 Ltr Requesting Submittal of Names of Personnel Responsible for Emergency Planning.Nrc Should Direct Such Requests to AF Olsen ML19338E9001980-10-0101 October 1980 Forwards Executed Amend 20 to Indemnity Agreement B-8, Modifying Prefatory Language of Paragraph 5,Article I Re Transportation ML19331D6741980-08-29029 August 1980 Forwards Tech Specs Incorporating Changes Proposed by 790501-02 Ltrs & Submitted in Connection w/780303 Request for Renewal of License R-47 ML19323F5901980-05-19019 May 1980 Forwards Revised Page & App to Amended Reactor Security Plan.Encl Withheld (Ref 10CFR2.790) ML19312D8631980-04-30030 April 1980 Submits Addl Info Re Equation for Effect of Uncertainty in Dp/Dt at Min Critical Moderator Height for Accident Condition ML19309E0731980-04-11011 April 1980 Submits Addl Info Re 791018 Amend Request.Describes Range of Allowable Nonmoderator to Moderator Ratio & Computer Codes Used for front-end Calculations for Analysis of Max Credible Accident ML19257B9261980-01-16016 January 1980 Forwards Page 18a for Insertion in 791023 Rept Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. ML19260B2441979-12-0303 December 1979 Submits Addl Info in Support of Request for Amend to License CX-10.Discusses Probability of Max Credible Accident & Need for Amend to Tech Specs ML19256E2251979-10-26026 October 1979 Forwards Executed Amend 20 to Indemnity Agreement B-8 & Amend 2 to Indemnity Agreement G-2 ML19254E4591979-10-18018 October 1979 Requests Amend to License CX-10 to Authorize Critical Experiments Utilizing nonmoderator-to-moderator Ratios Described in Hazards Evaluation Rept for Tightly-Packed Fuel Storage Critical Experiment Program. ML19276H0231979-08-15015 August 1979 Responds to 790730 Ltr Requesting Info from Nonpower Reactor Licensees Re Effect of Safeguards Rule.Upgrade Rule Necessitates Protection of Reactor as Category I Facility for Physical Protection Purposes ML19242A7741979-08-0101 August 1979 Forwards,Per s Ramos Request,Analyses of Design Basis Accident & Loca,In Support of Renewal of License R-47 ML19289E9111979-05-21021 May 1979 Forwards Executed Amend 1 to Indemnity Agreement G-2 & Amend 19 to Indemnity Agreement B-8 ML19305A3711979-03-0707 March 1979 Responds to 790301 Telcon Request.Forwards 1977 Form 10K, Annual Rept to Sec Supporting Renewal of License R-47. Form Is Last One Transmitted to Sec Re B&W Merger Into Jr Mcdermott Co ML19289D1831979-02-16016 February 1979 Responds to 790202 Ltr.Provides Details of Amounts & Enrichments of Snm.Agrees to Add License Condition Requiring Mod of Reactor Security Plan.Claims No Exemptions for Any SNM ML19269C5211979-01-29029 January 1979 Responds to NRC 780821 Ltr.Forwards Info Re Financial Data, Business Conducted,Organizational Structure,Radiological Monitoring,Safety Hazards & Tech Specs ML20147D7791978-12-0808 December 1978 Concurs That Inspec Rept Contains No Proprietary Info & Agrees to Placing It in NRC PDR 1988-03-30
[Table view] |
Text
i k{N 8005050 %,77' Babcock &Wilcox nesea,cn aoo oe eionment omision P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 April 30, 1980 Mr. Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 License: CX-10, docket 50-13 Reference 1 BAW-1484-7 " Critical Experiments Supporting Close Proximity Water Storage of Power Reactor Fuel" July 3 9/9 Reference 2 Letter to Mr. Robert W. Reid from A. F. Olsen, dated October 18, 1979, requesting license amendment Reference 3 Letter to Mr. Robert W. Reid from A. F. Olsen, dated April 11, 1980, providing additional information in support of amendment request
Dear Mr. Reid:
It has been brought to our attention by Mr. Harold Bernard and Ms. Jocelyn Mitchell of your staff, that we did not include in our analysis the effect of uncertainty in dp/dt at minimum critical moderator height for the accident condition.
H2 p= C/2 (H + A)4
("9""*I " 1)
Hi Equation 1 gives the reactivity addition which results when the moderator height of the core is raised from Hi to H .2C & A are curve fitting constants.
Reference 1 from which the values for C & A were taken, gives values of 3%,
1% and 6.7% respectively for (1) the uncertainty in p due to the uncertainty in in experimental measurements; (2) the uncertainty in p due to error in the least squares fit; and (3) the uncertainty in p due to uncertainty in the delayed neutron fraction. If all three of these uncertainties are combined in the most unfavorable manner, a total uncertainty of 10.7% results.
We have examined the effect of distributing the total uncertainty between the parameters A & C of equation 1 and have concluded that the largest re-activity addition rate results-for the loose packed square core when all of the The Babcock & Wilcox Company / Established 1867
V o
Mr. Robert W. Reid April 30, 1980 Page 2 uncertainty is due to an uncertainty in the parameter C. Since equation 1 shows p to be cirectly proportional to C, we have considered the case where C is uncertain by 10.7%.
The reactivity addition rate is calculated fr,m the equation:
6p AC g= (Ho + A)3 (equation 2) where:
n C/2 o = - A
- ex + - 0.18 1 5 + A) p =
excess reactivity (% AK/K) obtained for full moderator height by KENO calculation.
=
A 0.0459 cm/sec =
maximum rate at which the moderator can rise with the loose packed square core loaded.
In our original application submittal (Reference 2), we made the calcu-lation of dp/dt using a value for p of 18.7% AK/K and a value for C of 61688 cm2 % AK/K. The value obtained for dp/dt was 0.047% AK/K/sec. If we reduce C by 10.7%, the value obtained for dp/dt is 0.049% AK/K/sec.
In our supplemental submittal (Reference 3), we made the calculation using a value for pex of 20.6% AK/K, and a value for C of 61688 cm2 % AK/K. (The value of p was' raised from its previous value of 18.7% AK/K to account for a possible 1.hk AK/K error in the results of the KENO calculation.) The value obtained for dp/dt was 0.054% AK/K/sec (which we rounded up to 0.055 in our supplemental submittal). If we reduce C by 10.7%, we obtain a value' for dp/dt of 0.056% AK/K/sec.
Being very conservative, we have examined the combined effect of (1) re-ducing C by'10.7%, (2) increasing p ex by 1.9% AK/K and (3) reducing the fuel
, temperature coefficient by 10%. Results from the point kinetics model of the maximum credible accident predict that the peak clad temperature would be l
l l
l L- - _
i
V Mr. Robert W. Reid April 30, 1980 Page 3 '
raisgd to 832" F. This is still considerably below the acceptable value of 1050 F given in amendment 5.
Thank you for your prompt consideration and if you require additional information, please contact me.
Yours very truly, BABCOCK & WILCOX COMPANY LYNCilBURG RESEARCll CENTER V
A. F. Olsen License Administrator nwt Attachment Subscribed and sworn to'before me this N NII day of 6 , 1980.
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Notary Public Hy commission expires [k-/C'[//Yf t