Letter Sequence RAI |
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MONTHYEARML0806601082008-03-0505 March 2008 Supplemental Information Regarding Stretch Power Uprate License Amendment Request Project stage: Supplement ML0820010972008-08-0808 August 2008 Unit 3 - Request for Additional Information Regarding the Spent Fuel Pool Criticality Project stage: RAI ML0827701132008-09-30030 September 2008 Response to Request for Additional Information Regarding Spent Fuel Pool Storage License Amendment Request Project stage: Response to RAI ML0901402272009-02-0202 February 2009 Request for Additional Information Regarding the Spent Fuel Pool Criticality Amendment Request Project stage: RAI ML0900705162009-02-0303 February 2009 Request for Withholding Information from Pubic Disclosure Regarding Millstone Power Station, Unit No. 3 Project stage: Withholding Request Acceptance ML0919105142009-07-21021 July 2009 Spent Fuel Pool Criticality Amendment Request Schedule Project stage: Other ML0921803392009-08-0606 August 2009 Documents Referenced in July 21, 2009 Letter Project stage: Other ML1002004902010-01-26026 January 2010 Request for Additional Information Regarding Spent Pool Criticality Amendment Request Project stage: RAI ML1002700742010-01-27027 January 2010 Notice of Meeting with Dominion Nuclear Connecticut, Inc. to Discuss Responses to the Millstone Power Station, Unit No. 3 Spent Fuel Pool Criticality License Amendment Request for Additional Information Project stage: RAI ML1006101042010-03-0101 March 2010 Response to Request for Additional Information Questions 26, 27 & 29 Re Spent Fuel Pool Criticality License Amendment Request Project stage: Response to RAI ML1006403432010-03-0505 March 2010 Response to Questions 28 and 30 of Request for Additional Information Regarding a Spent Fuel Pool Criticality License Amendment Request Project stage: Request ML1007601162010-03-17017 March 2010 Summary of Meeting with DNC to Discuss Responses to the Request for Additional Information Regarding MPS3 Spent Fuel Pool Criticality License Amendment Request Project stage: RAI ML1007500242010-03-26026 March 2010 Issuance of Amendment Spent Fuel Pool Criticality Project stage: Approval 2009-08-06
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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23318A0952023-11-14014 November 2023 Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel ML23199A2832023-07-18018 July 2023 Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23089A1882023-03-29029 March 2023 Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report ML23073A1802023-03-14014 March 2023 Notification of Commercial Grade Dedication Inspection (05000336/2023010 and 05000423/2023010) and Request for Information ML22251A1292022-09-0909 September 2022 Request for Additional Information Related to Response to Generic Letter 2004-04 ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML21225A5022021-08-13013 August 2021 Request for Additional Information for North Anna Power Station, Units 1 and 2, Surry Power Station, Units 1 and 2, and Millstone Power Station, Units 2 and 3, Appendix E of Fleet Report Com-Naf-2 (EPID:L02021-LLT-0000) Public Version ML21195A2442021-07-13013 July 2021 NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21182A2902021-07-0101 July 2021 7/1/2021 E-mail - Request for Additional Information Alternative Frequency to Supplemental Valve Position Verification Testing Requirements ML21112A3082021-04-22022 April 2021 Request for Additional Information (E-mail Dated 4/22/2021) License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML21105A1152021-04-15015 April 2021 Request for Additional Information (e-mail Dated 4/15/2021) Proposed LAR for Addition of Analytical Methodology to the Core Operating Limits Report for a LBLOCA ML21078A0332021-03-18018 March 2021 NRR E-mail Capture - Millstone Power Station, Unit 2 - Request for Additional Information - Proposed LAR to Revise TSs for Steam Generator Inspection Frequency ML21076A4622021-03-17017 March 2021 NRR E-mail Capture - Draft RAI for Versatile Internals and Component Program for Reactors Vipre Code Review (L-2021-LLT-0000) ML21077A1652021-02-26026 February 2021 (02/26/2021 E-mail) Draft Request for Additional Information LAR to Revise Technical Specifications for Steam Generator Inspection Frequency ML21034A5762021-02-0303 February 2021 Request for Additional Information (e-mail Dated 1/3/2021) Alternative Request RR-05-06 Inservice Inspection Interval Extension for Steam Generator Weld Inspections ML20246G5612020-09-0202 September 2020 Request for Additional Information (E-mail Dated 9/2/2020) License Amendment Request for a One-Time Deferral of the Steam Generator Inspections ML20244A2902020-08-31031 August 2020 Request for Additional Information (E-mail Dated 8/31/2020) License Amendment Request to Revise Battery Surveillance Requirements ML20231A7172020-08-18018 August 2020 Request for Additional Information (e-mail Dated 8/18/2020) License Amendment Request to Revise TS Table 3.3-11 Accident Monitoring Instrumentation ML20184A0052020-07-0202 July 2020 Request for Additional Information (E-mail Dated 7/2/2020) Relief Request IR-3-33 for Limited Coverage Examiniations ML20075A0322020-03-15015 March 2020 Request for Additional Information (E-mail Dated 3/15/2020) Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity ML20050F9212020-02-19019 February 2020 Request for Additional Information (E-mail Dated 2/19/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating ML20023D0372020-01-23023 January 2020 Request for Additional Information (E-mail Dated 1/23/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating ML19361A0382019-12-23023 December 2019 12/23/19 E-mail from R.Guzman to S. Sinha - Draft Request for Additional Information Planned Audit of LAR to Revise TS 3.8.1.1 ML19277B9082019-10-0707 October 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time ML19248D7552019-09-0505 September 2019 Request for Additional Information Via E-mail from R.Guzman to S. Sinha Proposed License Amendment Request to Adopt 10 CFR 50.69 ML19169A0962019-06-17017 June 2019 NRR E-mail Capture - Request for Additional Information Emergency Action Level Scheme Change for Millstone Power Station - Units 1, 2, and 3, North Anna Power Station - Units 1 and 2, and Surry Power Station - Units 1 and 2 ML19162A0052019-06-10010 June 2019 NRR E-mail Capture - Draft RAIs for Dominion EAL Scheme Change ML19042A1822019-02-11011 February 2019 Request for Additional Information LAR for TS Changes to Spent Fuel Storage and New Fuel Storage, 02/11/2019 E-mail from R. Guzman to S. Sinha ML18291B3262018-10-18018 October 2018 Request for Additional Information LAR Regarding Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage, E-mail from R.Guzman to S.Sinha ML18277A1762018-10-0404 October 2018 Request for Additional Information LAR to Revise TS Action Statement for Loss of Control Building Inlet Ventilation Rad Monitor Instrumentation Channels (e-mail from R.Guzman to M.Whitlock, EPID: L-2018-LLA-0099) ML18213A1152018-08-0101 August 2018 Request for Additional Information Alternative Request P-06 'C' Charging Pump (08/01/2018 E-mail from R. Guzman to M. Whitlock) ML18171A1532018-06-20020 June 2018 Request for Additional Information Via E-mail from R.Guzman to W.Craft Alternative Requests for Inservice Testing Program (E-mail from R.Guzman to W.Craft) (EPID: L-2018-LLR-0012-LLR-0022) ML18137A3132018-05-17017 May 2018 Request for Additional Information Via E-mail from R.Guzman to W.Craft Proposed License Amendment Request to Revise ILRT Type a and Type C Test Intervals ML17297A8472017-10-27027 October 2017 Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools (CAC No. MF9430; EPID L-2016-LRC-0001) ML17033B6142017-02-0202 February 2017 Request for Additional Information, 2017/02/02 E-mail from R.Guzman to W.Craft Proposed Alternative RR-04-24 and IR-3-30 for the Elimination of Reactor Pressure Vessel Threads in Flange Examination (CAC Nos. MF8468/MF8469) ML17005A3282017-01-0505 January 2017 MPS2 EOC-23 and MPS3 EOC-17 Steam Generator Tube Inspection Reports - Requests for Additional Information ML16260A0062016-09-16016 September 2016 2016/09/16 E-mail from R. Guzman to W. Craft Request for Additional Information - License Amendment Request Realistic Large Break Loss of Coolant Accident Analysis (MF7761) ML16267A0022016-09-12012 September 2016 2016/09/12 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Revise ECCS TS and FSAR Ch. 14 to Remove Charging (MF7297) ML16133A3562016-05-12012 May 2016 E-mail from R. Guzman to C. Sly Request for Additional Information Supporting License Amendment Request to Remove Charging Credit ML16068A4142016-03-0808 March 2016 Request for Additional Information - Relief Request RR-04-19 Examination Cat R-A, Risk-Informed Piping Examinations (MF6569) ML16055A5302016-02-24024 February 2016 2016/02/24 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Adopt Dominion Core Design and Safety Analysis Methods (MF6251) ML16047A1712016-02-16016 February 2016 2016/02/16 E-mail from R.Guzman to M. Whitlock Request for Additional Information - Small Break Loss of Coolant Accident Re-Analysis (MF6700) ML16043A5232016-02-12012 February 2016 Request for Additional Information 2016/02/12 E-mail from R. Guzman to M.Whitlock Relief Requests IR-3-22 and IR-3-23 (CAC Nos. MF6573 and MF6574) ML16013A4772016-01-13013 January 2016 NRR E-mail Capture - Millstone Power Station, Units 2 and 3 - Request for Additional Information License Amendment Request for Removal of Severe Line Outage Detection (Slod) from the Offsite Power System - (MF6430, MF6431) ML16011A5172016-01-11011 January 2016 NRR E-mail Capture - Millstone Power Station, Unit 3, Reactor Vessel Surveillance Capsule Withdrawal Schedule - Request for Additional Information ML15349A8312016-01-0808 January 2016 Request for Additional Information License Amendment Request to Adopt Dominion Core Design and Safety Analysis Methods ML15337A1512015-12-0303 December 2015 NRR Email Capture - Millstone Unit 2 Request for Additional Information ML15279A1092015-10-0606 October 2015 NRR e-mail Capture - Millstone Power Station, Unit 3, NRC Staff Request for Additional Information - Relief Request Nos. IR-3-19,3-20,3-21 ML15275A1432015-10-0202 October 2015 2015/10/02 E-mail from R.Guzman to W.Craft - Follow-up Request for Additional Information TSTF-523, Revision 2, GL 2008-01, Managing Gas Accumulation 2023-07-18
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 26, 2010 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO.3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE SPENT FUEL POOL CRITICALITY AMENDMENT REQUEST (TAC NO. MD8251)
Dear Mr. Heacock:
By letter dated July 13, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072000386), Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for a stretch power uprate (SPU) of Millstone Power Station, Unit 3 (MPS3). Included in a supplement dated July 13, 2007 (ADAMS Accession No. ML072000281), was a request to amend the MPS3 spent fuel pool (SFP) storage requirements.
By letter dated March 5, 2008 (ADAMS Accession No. ML080660108), DNC separated the MPS3 SFP storage requirements request from the MPS3 SPU request.
By letters dated August 8, 2008, and February 2, 2009, the Nuclear Regulatory Commission (NRC) staff requested additional information (ADAMS Accession Nos. ML082001097 and ML090140227, respectively) regarding DNC's LAR. By letter dated September 30,2008, DNC responded to the August 8, 2008, request (ADAMS Accession No. ML082770113). By letters dated March 5 and March 23, 2009, DNC responded to the February 2, 2009, request (ADAMS Accession Nos. ML0906505130 and ML0908306670, respectively). The NRC staff has reviewed DNC's response to these requests for additional information and determined that additional information is required in order to complete the review.
The enclosed questions were sent to Mr. William D. Bartron, of your staff, in draft form to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. During a phone call with Mr. Bartron on January 21,2010, it was agreed that you would provide a response by February 26,2010.
D. Heacock -2 If you have any questions, please contact me at 301-415-1603.
Sincerely,
~nJJnders,~
Plant Licensing Branch, LPLI-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Request for Additional information cc wi encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION MILLSTOI\IE POWER STATION, UNIT 1\10. 3 SPENT FUEL POOL CRITICALITY LICENSE AMENDMENT REQUEST DOCKET NO. 50-423 By letter dated July 13, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072000386), Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for a stretch power uprate (SPU) of Millstone Power Station, Unit 3 (MPS3). Included in a supplement dated July 13, 2007 (ADAMS Accession No. ML072000281), was a request to amend the MPS3 spent fuel pool (SFP) storage requirements.
By letter dated March 5, 2008 (ADAMS Accession No. IVIL080660108), DNC separated the MPS3 SFP storage requirements request from the MPS3 SPU request.
By letters dated August 8, 2008, and February 2, 2009, the Nuclear Regulatory Commission (NRC) staff requested additional information (ADAMS Accession Nos. ML082001097 and ML090140227, respectively) regarding DNC's LAR. By letter dated September 30,2008, DNC responded to the August 8, 2008, request (ADAMS Accession No. IVIL082770113). By letters dated March 5 and March 23, 2009, DNC responded to the February 2, 2009, request (ADAMS Accession Nos. ML0906505130 and ML0908306670, respectively). The NRC staff has reviewed DNC's response to these requests for additional information (RAls) and determined that additional information is required in order to complete the review.
The August 8, 2008, and February 2, 2009, NRC letters contained questions 1-25, questions 26-30 are presented below.
- 26. In response to RAI # 5 DNC states:
NUREG/CR-6665, Reference 4, identifies both specific power and operating history effects as weakly correlated to increased reactivity for discharged fuel assemblies. The maximum impact noted in Reference 4 is approximately 0.0020011 Keff. This result is caused by reduced power operation near the end of assembly depletion. The depletion calculations supporting the analysis presented in WCAP-16721-P do not include part power operation. Instead, the soluble boron concentration is maintained at a constant value above the cycle average value for the entire depletion. The spectral hardening from the presence of boron, especially at the end of the cycle when the concentration is several hundred ppm above physical values, provides additional margin to account for this potential impact. The use of additional margin is the approach suggested in Reference 4 for accounting for the potential for operating history effects.
In order to determine if the conservatism gained from taking credit for using a higher than actual soluble boron concentration during the simulated depletion of the fuel in the reactor is Enclosure
-2 enough to cover the 0.00200 t::. Keff, the NRC staff needs to know how much more than the actual boron concentration was used. Please provide additional information regarding how much soluble boron concentration was used during the simulated depletion of the fuel in the reactor compared to the actual.
- 27. In RAI #21 the licensee performed new criticality analysis using site specific burnup profiles.
- a. In RAI #21 the licensee determined penalties for burnups where the original analysis in WCAP-16721 was shown to be non-conservative. Those penalties were determined using a depletion code and criticality code different than that used in WCAP-16721. Since the development and utilization of the penalties constitutes more than just a comparison study, either provide a code validation or justify not performing a criticality code validation for the new code.
- b. In Table 21-6 there is a Burnup Worth column that is used to determine the penalty. Explain the basis and origin for that column.
- c. In RAI #21 the licensee indicates the depletion parameters used were the same as for WCAP-16721. Provide a list of the fuel assembly and depletion parameters used for each case in RAI #21.
- d. As part of the response to RAI # 21 the licensee states, "Since the limiting Top 1/3 Assembly comparison covers only existing No Blanket fuel from completed MPS3 cycles, credit has been taken for as-built fuel density, dish and chamfer fractions, Pre-Uprate (3411 MWt) core power, and as-operated cycle soluble boron concentration." In earlier RAI responses, the licensee took credit for having modeled these parameters conservatively.
- i. Since the No Blanket fuel modeling no longer has those conservatisms, explain how the earlier RAI responses are affected.
ii. Since these parameters had been modeled conservatively in the original analysis, there were no biases or uncertainties included for these parameters. Since the No Blanket fuel modeling no longer has those conservatisms, explain how the biases and uncertainties are affected.
- e. In its RAI #21 response, the licensee states the title to technical specification (TS) Figure 3.9-4 will be changed. That change was not provided as part of the revised TS markup. Please revise the marked-up TS page to indicate that change.
- 28. In ONC's response to RAI #5, ONC claims that ignoring the Integrated Fuel Burnable Absorber (IFBA) is conservative. In that response, ONC claims that it is conservative to ignore the presence of IFBA when performing the depletion portion of a spent nuclear fuel criticality analysis. ONC's submittal states they performed two sets of analyses; one in which all residual IFBA was artificially removed after the depletion, and one in which all residual IFBA was retained after the depletion. ONC's submittal indicates that when the
-3 residual IFBA is artificially removed the effect of neutron spectral hardening is shown, but when the residuallFBA is left in the fuel assembly, the residuallFBA overcomes the neutron spectral hardening with a conservative result.
There is no indication in NUREG/CR-6760 that any residual IFBA was artificially removed in reaching its conclusions. The information presented in NUREG/CR-6760 indicates that any residuallFBA was left in the fuel assembly when determining the effect. ONC response is inconsistent with NUREG/CR-6760 and has not been accepted by NRC staff in the past.
There is currently insufficient information in ONC's submittal to reconcile the different conclusions. Please provide a detailed comparison of ONC's analysis and the analysis performed in NUREG/CR-6760 and justify the differences.
- 29. In ONC's response to RAI #5, ONC states their fuel management does not use fixed burnable absorbers.
- a. Has MPS3 ever used any other flux suppression devices such as hafnium inserts to reduce the neutron dose to reactor vessel welds?
- b. If so, how do they affect the reactivity of the discharged fuel assemblies?
- 30. Please verify the average core exit temperature for nominal reactor coolant system (RCS) flow. Please verify the maximum core exit temperature for the minimum TS allowed RCS flow. Please provide the maximum fuel assembly exit temperature for the minimum TS allowed RCS flow. Please provide the moderator temperature used for each case in the RAI
- 21 responses.
D. Heacock -2 If you have any questions, please contact me at 301-415-1603.
Sincerely, Ira!
Carleen J. Sanders, Project Manager Plant Licensing Branch, LPLI-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Request for Additional Information cc w/ encl: Distribution via Listserv Distribution:
Public LPL1-2 R/F RidsNrrDorlLpl1-2 Resource RidsNrrLAABaxter Resource RidsNrrPMCSanders Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsRgn 1MailCenter Resource Ridsl'JrrDssSrxb Resource RidsNrrDorlDpr Resource KWood, NRR ADAMS Accession No.: ML100200490 *via e-mail OFFICE LPL 1-2/PM LPL1-2/LA DSS/SRXB LPL 1-2/BC NAME CSanders ABaxter* GCranston* HChernoff DATE 1/25/10 1/22/10 12/23/09 1/26/10 Official Record Copy