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| | number = ML14043A006 | | | number = ML14043A006 |
| | issue date = 02/20/2014 | | | issue date = 02/20/2014 |
| | title = Nine Mile Point Nuclear Station, Unit No. 2 - First Round of Requests for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mella+) (TAC No. MF3056) | | | title = First Round of Requests for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mella+) |
| | author name = Vaidya B K | | | author name = Vaidya B |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Costanzo C | | | addressee name = Costanzo C |
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| | docket = 05000410 | | | docket = 05000410 |
| | license number = | | | license number = |
| | contact person = Vaidya B K, NRR/DORL/LPL1-1, 415-3308 | | | contact person = Vaidya B, NRR/DORL/LPL1-1, 415-3308 |
| | case reference number = TAC MF3056 | | | case reference number = TAC MF3056 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Christopher Costanzo Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. 0. Box 63 Lycoming, NY 13093 February 20, 2014 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 20, 2014 Mr. Christopher Costanzo Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. 0. Box 63 Lycoming, NY 13093 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NINE MILE POINT NUCLEAR STATION, UNIT NO.2-FIRST ROUND OF REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST PURSUANT TO 10 CFR 50.90: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+) (TAC NO. MF3056) | | NINE MILE POINT NUCLEAR STATION, UNIT NO.2- FIRST ROUND OF REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST PURSUANT TO 10 CFR 50.90: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+) (TAC NO. MF3056) |
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| ==Dear Mr. Costanzo:== | | ==Dear Mr. Costanzo:== |
| By letter dated November 1, 2013 (Agencywide Document Access and Management System (ADAMS) Package Accession No. ML 13316B090), as supplemented by letter dated January 21, 2014 (ADAMS Accession No. ML 14023A654), Nine Mile Point Nuclear Station, LLC (the licensee) submitted a license amendment request for Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would (1) allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) domain; (2) use of the Detect and Suppress Solution -Confirmation Density (DSS-CD) stability solution, (3) use of the TRACG04 analysis code; (4) increase the isotopic enrichment of boron-1 0 in the sodium pentaborate solution used to prepare the neutron absorber solution in the Standby Liquid Control System (SLS); and (5) increase the Safety Limit Minimum Critical Power Ratio (SLMCPR) for two recirculation loops in operation. The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your submission and has determined that additional information is needed to complete its review. The draft request for additional information (RAI) was transmitted to you by e-mail dated January 31, 2014 (ADAMS Accession No. ML 14031A178). In the telephone conversation with your staff, Mr. Kenneth Kristensen, on February 11, 2014, your staff committed your response to these RAis by March 10, 2014. The NRC staff's final version of the RAI is provided in the enclosure to this letter. Docket No. 50-41 0 | | |
| | By letter dated November 1, 2013 (Agencywide Document Access and Management System (ADAMS) Package Accession No. ML13316B090), as supplemented by letter dated January 21, 2014 (ADAMS Accession No. ML14023A654), Nine Mile Point Nuclear Station, LLC (the licensee) submitted a license amendment request for Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would (1) allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) domain; (2) use of the Detect and Suppress Solution - Confirmation Density (DSS-CD) stability solution, (3) use of the TRACG04 analysis code; (4) increase the isotopic enrichment of boron-1 0 in the sodium pentaborate solution used to prepare the neutron absorber solution in the Standby Liquid Control System (SLS); and (5) increase the Safety Limit Minimum Critical Power Ratio (SLMCPR) for two recirculation loops in operation. |
| | The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your submission and has determined that additional information is needed to complete its review. |
| | The draft request for additional information (RAI) was transmitted to you by e-mail dated January 31, 2014 (ADAMS Accession No. ML14031A178). In the telephone conversation with your staff, Mr. Kenneth Kristensen, on February 11, 2014, your staff committed your response to these RAis by March 10, 2014. |
| | The NRC staff's final version of the RAI is provided in the enclosure to this letter. |
| | Sincerely, |
| | ~d-~ |
| | ~ |
| | Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-41 0 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FIRST ROUND REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST RE: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS CONSTELLATION ENERGY NINE MILE POINT NUCLEAR STATION, UNIT 2 By letter dated November 1, 2013 (Agencywide Document Access and Management System (ADAMS) Package Accession No. ML 133168090), Constellation Energy (the licensee) submitted a license amendment request for maximum extended load line limit analysis plus (MELLLA+). The proposed amendment request would allow operation in the expanded MELLLA+ domain. Upon review of Attachment 10 (ADAMS Accession No. ML 133168107) to the submittal titled "Safety Analysis Report for Nine Mile Point Unit 2 Maximum Extended Load Line Limit Analysis Plus" (ADAMS Accession No. ML 133168113), the staff has the following requests for additional information: SRXB RAI1: Section 9.3.3 of Attachment 10 states that zirconium credit will be used in the Shumway correlation. The staff is aware of the zirconium data described in letter dated September 9, 2013 (ADAMS Accession No. ML 13253A 1 05) from GE Hitachi Nuclear Energy to the NRC staff. (a) Fresh fuel has little or no oxide at the start of the transient and the fresh fuel is often in the more reactive part of the core; therefore, it is the data of interest. Figure 6 of the September 9, 2013 letter has many data sets displayed together on it. Provide a plot showing clean zirconium separate from all the other data including SS, lnconel, zirconium oxide and any data that would be expected to have oxidized zirconium. (b) In the September 9, 2013 letter, much of the Hoffman (FKZ) data that has a rapid cooling rate early in the experiment may have been incorrectly interpreted as a quench. A closer examination of the data shows this initial cooling was due to startup of the test and that quench occurred much later at significantly lower temperatures. In addition, because of high temperatures during the tests and pre-conditioning of the rods, the rods are likely to have thick oxide layer thicknesses that are not representative of fuel in a commercial reactor undergoing an Anticipated Transient without Scram with Instability (A TWS-1) event. Provide a plot showing the data considered valid by the licensee for justifying Shumway as implemented in TRACG for the intended application (e.g. ATWS-1 under MELLLA+). Also provide textual justification to support the choice of the selected data and exclusion of the other data, focusing on comparing the applicable test conditions to the plant application conditions to support a conclusion that the data is applicable. Enclosure SRXB RAI2: Section 9.3.3 of Attachment 10 states: The plant-specific A TWS stability calculation was performed using the approved neutronic and thermal-hydraulic codes ... TRACG04. An error in the code was corrected by letter from GE Hitachi Nuclear Energy to the staff dated October 15, 2013 titled "Updated TRACG Quench Front Model Description and Qualification", which is currently under staff review. In the October 15, 2013 letter, GE noted: The quench front model has been updated to correct an error in the quench front heat transfer coefficient for bottom reflooding, and to better capture the heat transfer ahead of and behind the quench front. Please clarify which quench model is being used in the application.
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| Mr. Christopher Costanzo Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. 0. Box 63 Lycoming, NY 13093 February 20, 2014
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| ==SUBJECT:==
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| NINE MILE POINT NUCLEAR STATION, UNIT NO.2-FIRST ROUND OF REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST PURSUANT TO 10 CFR 50.90: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+) (TAC NO. MF3056)
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| | FIRST ROUND REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST RE: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS CONSTELLATION ENERGY NINE MILE POINT NUCLEAR STATION, UNIT 2 By letter dated November 1, 2013 (Agencywide Document Access and Management System (ADAMS) Package Accession No. ML133168090), Constellation Energy (the licensee) submitted a license amendment request for maximum extended load line limit analysis plus (MELLLA+). The proposed amendment request would allow operation in the expanded MELLLA+ domain. |
| | Upon review of Attachment 10 (ADAMS Accession No. ML133168107) to the submittal titled "Safety Analysis Report for Nine Mile Point Unit 2 Maximum Extended Load Line Limit Analysis Plus" (ADAMS Accession No. ML133168113), the staff has the following requests for additional information: |
| | SRXB RAI1: |
| | Section 9.3.3 of Attachment 10 states that zirconium credit will be used in the Shumway correlation. The staff is aware of the zirconium data described in letter dated September 9, 2013 (ADAMS Accession No. ML13253A105) from GE Hitachi Nuclear Energy to the NRC staff. |
| | (a) Fresh fuel has little or no oxide at the start of the transient and the fresh fuel is often in the more reactive part of the core; therefore, it is the data of interest. |
| | Figure 6 of the September 9, 2013 letter has many data sets displayed together on it. Provide a plot showing clean zirconium separate from all the other data including SS, lnconel, zirconium oxide and any data that would be expected to have oxidized zirconium. |
| | (b) In the September 9, 2013 letter, much of the Hoffman (FKZ) data that has a rapid cooling rate early in the experiment may have been incorrectly interpreted as a quench. A closer examination of the data shows this initial cooling was due to startup of the test and that quench occurred much later at significantly lower temperatures. In addition, because of high temperatures during the tests and pre-conditioning of the rods, the rods are likely to have thick oxide layer thicknesses that are not representative of fuel in a commercial reactor undergoing an Anticipated Transient without Scram with Instability (ATWS-1) event. Provide a plot showing the data considered valid by the licensee for justifying Shumway as implemented in TRACG for the intended application (e.g. ATWS-1 under MELLLA+). Also provide textual justification to support the choice of the selected data and exclusion of the other data, focusing on comparing the applicable test conditions to the plant application conditions to support a conclusion that the data is applicable. |
| | Enclosure |
| | |
| | SRXB RAI2: |
| | Section 9.3.3 of Attachment 10 states: |
| | The plant-specific A TWS stability calculation was performed using the NRC-approved neutronic and thermal-hydraulic codes ... TRACG04. |
| | An error in the code was corrected by letter from GE Hitachi Nuclear Energy to the staff dated October 15, 2013 titled "Updated TRACG Quench Front Model Description and Qualification", which is currently under staff review. In the October 15, 2013 letter, GE noted: |
| | The quench front model has been updated to correct an error in the quench front heat transfer coefficient for bottom reflooding, and to better capture the heat transfer ahead of and behind the quench front. |
| | Please clarify which quench model is being used in the application. |
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| ==Dear Mr. Costanzo:==
| | ML14023A654), Nine Mile Point Nuclear Station, LLC (the licensee) submitted a license amendment request for Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would (1) allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) domain; (2) use of the Detect and Suppress Solution - Confirmation Density (DSS-CD) stability solution, (3) use of the TRACG04 analysis code; (4) increase the isotopic enrichment of boron-10 in the sodium pentaborate solution used to prepare the neutron absorber solution in the Standby Liquid Control System (SLS); and (5) increase the Safety Limit Minimum Critical Power Ratio (SLMCPR) for two recirculation loops in operation. |
| By letter dated November 1, 2013 (Agencywide Document Access and Management ystem (ADAMS) Package Accession No. ML 13316B090), as supplemented by letter dated January 21, 2014 (ADAMS Accession No. ML 14023A654), Nine Mile Point Nuclear Station, LLC (the licensee) submitted a license amendment request for Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would (1) allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) domain; (2) use of the Detect and Suppress Solution -Confirmation Density (DSS-CD) stability solution, (3) use of the TRACG04 analysis code; (4) increase the isotopic enrichment of boron-10 in the sodium pentaborate solution used to prepare the neutron absorber solution in the Standby Liquid Control System (SLS); and (5) increase the Safety Limit Minimum Critical Power Ratio (SLMCPR) for two recirculation loops in operation. The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your submission and has determined that additional information is needed to complete its review. The draft request for additional information (RAI) was transmitted to you by e-mail dated January 31, 2014 (ADAMS Accession No. ML 14031A178). In the telephone conversation with your staff, Mr. Kenneth Kristensen, on February 11, 2014, your staff committed your response to these RAis by March 10, 2014. The NRC staff's final version of the RAI is provided in the enclosure to this letter. Docket No. 50-41 0
| | The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your submission and has determined that additional information is needed to complete its review. |
| | The draft request for additional information (RAI) was transmitted to you by e-mail dated January 31, 2014 (ADAMS Accession No. ML14031A178). In the telephone conversation with your staff, Mr. Kenneth Kristensen, on February 11, 2014, your staff committed your response to these RAis by March 10, 2014. |
| | The NRC staff's final version of the RAI is provided in the enclosure to this letter. |
| | Sincerely, Ira/ |
| | Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-41 0 |
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| ==Enclosure:== | | ==Enclosure:== |
| Sincerely, Ira/ Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNrrDorllpl1-1 Resource RidsRgn1 MaiiCenter Resource RidsNrrDssSnpb Resource DSchroeder, Region 1 LPL 1-1 R/F RidsNrrLAKGoldstein Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrDssEicb Resource RidsNrrDssStsb Resource RidsNrrPMNineMilePoint Resource RidsNrrDssSrxb Resource RidsNrrDssScvb Resource ADAMS Accession No.: ML14043A006 (*)Transmitted by memo dated 01/22/2014 OFFICE NRR/LPL 1-1\PM NRR/LPL 1-1\LA NRR/SRXB/BC(*) NRR/LPL 1-1/BC NRR/LPL 1-1\PM NAME BVaidya KGoldstein CJackson BBeasley BVaidya DATE 02/12114 02/12/14 01/22/14 02/19/14 02/20/14 OFFICIAL RECORD COPY
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| }} | | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC LPL 1-1 R/F RidsNrrDssStsb Resource RidsNrrDorllpl1-1 Resource RidsNrrLAKGoldstein Resource RidsNrrPMNineMilePoint Resource RidsRgn1 MaiiCenter Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrDssSrxb Resource RidsNrrDssSnpb Resource RidsNrrDssEicb Resource RidsNrrDssScvb Resource DSchroeder, Region 1 ADAMS Accession No.: ML14043A006 (*)Transmitted by memo dated 01/22/2014 OFFICE NRR/LPL 1-1\PM NRR/LPL 1-1\LA NRR/SRXB/BC(*) NRR/LPL 1-1/BC NRR/LPL 1-1\PM NAME BVaidya KGoldstein CJackson BBeasley BVaidya DATE 02/12114 02/12/14 01/22/14 02/19/14 02/20/14}} |
Letter Sequence RAI |
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MONTHYEARML14064A3232013-12-31031 December 2013
000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15.
Project stage: Request
ML14002A1702014-01-0202 January 2014
Unacceptable Application with Opportunity to Supplement - Nine Mile Point Nuclear Station, Unit 2 - MF3056, License Amendment Request - Maximum Extended Load Line Limit Analysis Plus
Project stage: Other
ML14002A2202014-01-0202 January 2014
Revised Unacceptable Application with Opportunity to Supplement - Nine Mile Point Nuclear Station, Unit 2 - License Amendment Request - Maximum Extended Load Line Limit Analysis Plus
Project stage: Other
ML14023A6542014-01-21021 January 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Commitment Date to Provide Supplemental Information
Project stage: Supplement
ML14028A3982014-01-28028 January 2014
MF3056 - Acceptance of Requested Licensing Action License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: Acceptance Review
ML14064A3222014-01-31031 January 2014
00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+).
Project stage: Request
ML14051A1382014-02-14014 February 2014
Response to Request for Supplemental Information to License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus
Project stage: Supplement
ML14043A0062014-02-20020 February 2014
First Round of Requests for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mella+)
Project stage: RAI
ML14064A3212014-02-25025 February 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Core Reload and Safety Limit Supplemental Information
Project stage: Supplement
ML14064A3242014-02-28028 February 2014
000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics.
Project stage: Request
ML14029A0392014-03-0505 March 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated November 1, 2013
Project stage: Withholding Request Acceptance
ML14051A0152014-03-0606 March 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated February 14, 2014
Project stage: Withholding Request Acceptance
ML14071A4662014-03-10010 March 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Response to Srxb RAI 1 and RAI 2
Project stage: Request
ML14071A2422014-03-12012 March 2014
NMP Unit 2, MF3056, 2nd Round of Draft RAIs - LAR License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: Draft RAI
ML14083A0232014-03-31031 March 2014
Second Round of Request for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: RAI
ML14139A4162014-05-14014 May 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Response to RAI STSB-1 and RAI STSB-2
Project stage: Response to RAI
ML14204A3692014-08-14014 August 2014
Third Round of Request for Additional Information & Enclosure 1, Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mellla+) (Tac No. MF3056)
Project stage: RAI
ML14072A0152014-09-0303 September 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated March 10, 2014
Project stage: Withholding Request Acceptance
ML14246A3962014-09-0303 September 2014
NMP Unit 2, MF3056, 4th Round of Draft RAIs - LAR License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: Draft RAI
ML14065A0902014-09-0303 September 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated February 25, 2014 (Tac No. MF3056)
Project stage: Withholding Request Acceptance
NMP2L2556, Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus2014-09-15015 September 2014
Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus
Project stage: Response to RAI
ML14260A1202014-11-0606 November 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated September 15, 2014 (Tac No. MF3056)
Project stage: Withholding Request Acceptance
ML14314A2142014-11-10010 November 2014
MF3056, E-mail Capture - LAR Mellla+, Simulator Audit Plan, November 20-21, 2014 at the Plant Site
Project stage: Other
ML14321A0642014-11-17017 November 2014
Point Unit 2, MF3056, LAR Mellla+, Supplement to the Simulator Audit Plan
Project stage: Other
ML14351A4282014-12-11011 December 2014
Updated TIP Comparisons for Current Operating Conditions, GE-PPO- 1GYEF-KG1-742, Enclosure 2
Project stage: Request
ML15002A1622015-01-26026 January 2015
Request for Withholding Information from Public Disclosure Submission Dated December 11, 2014, for Supplement Information for NRC Simulator Audit LAR for Mellla+
Project stage: Withholding Request Acceptance
ML15033A0022015-01-30030 January 2015
MF3056, LAR - Mellla+, Revised RAI - Neutron Fluence Calculation Related
Project stage: RAI
ML15051A4642015-02-18018 February 2015
Response to Fifth Request for Additional Information Concerning License Amendment Request for Maximum Extended Load Line Limit Analysis Plus
Project stage: Request
ML15056A3792015-03-16016 March 2015
Request for Withholding Information from Public Disclosure Submission Dated February 18, 2015, for License Amendment Request Pursuant to 10 CFR 50.90 Maximum Extended Load Line Limit Analysis Plus
Project stage: Withholding Request Acceptance
ML15105A4432015-05-0404 May 2015
Draft Safety Evaluation for License Amendment Request - Mellla+
Project stage: Draft Approval
ML15114A1602015-05-0707 May 2015
Issuance of Simulator Audit Report License Amendment Request Regarding MELLLA Plus
Project stage: Approval
ML15096A0762015-09-0202 September 2015
Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus
Project stage: Approval
ML15210A3262015-09-0404 September 2015
LTR-15-0388-1 - John W. Stetkar Letter Nine Mile Point Nuclear Station Unit 2 Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request
Project stage: Other
2014-03-12
[Table View] |
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000220/20240022024-08-0505 August 2024
Integrated Inspection Report 05000220/2024002 and 05000410/2024002
ML24215A3002024-08-0202 August 2024
Operator Licensing Examination Approval
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
ML24198A0852024-07-16016 July 2024
Senior Reactor and Reactor Operator Initial License Examinations
RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024
Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024
License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
IR 05000220/20244012024-05-30030 May 2024
Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only)
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024
Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request
NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024
2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
IR 05000220/20240012024-05-10010 May 2024
Integrated Inspection Report 05000220/2024001 and 05000410/2024001
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024
Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024
2023 Annual Environmental Operating Report
NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024
Core Operating Limits Report
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
IR 05000220/20230062024-02-28028 February 2024
Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006)
NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024
Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
IR 05000220/20230042024-02-0101 February 2024
Integrated Inspection Report 05000220/2023004 and 05000410/2023004
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024
CFR 50.46 Annual Report
ML24004A2122024-01-0808 January 2024
Senior Reactor and Reactor Operator Initial License Examinations
ML23354A0012024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23278A1292023-12-14014 December 2023
Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines
NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023
Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station
IR 05000410/20243012023-12-14014 December 2023
Initial Operator Licensing Examination Report 05000410/2024301
ML23305A1402023-12-13013 December 2023
Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580
2024-09-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
ML23264A7992023-09-21021 September 2023
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1
ML23205A2432023-07-19019 July 2023
NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186)
ML23087A2912023-03-28028 March 2023
Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld
ML23061A0522023-03-0202 March 2023
Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus
ML23012A2002023-01-13013 January 2023
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401
ML22207A2162022-07-26026 July 2022
Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010
ML22194A9412022-07-13013 July 2022
Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail)
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22020A0642022-01-13013 January 2022
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles
ML21320A3472021-11-16016 November 2021
Request for Additional Information LAR to Revise TSs to Adopt TSTF-582, Revision 0
ML21306A3312021-11-0202 November 2021
Request for Additional Information Alternative Request GV-RR-10 (11/2/2021 e-mail)
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21117A0342021-05-0505 May 2021
Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893
ML21125A1282021-05-0404 May 2021
OPC Document Request - Feb 2021
ML21110A5112021-04-20020 April 2021
Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582
ML21088A2682021-03-30030 March 2021
Notification of Conduct of a Fire Protection Team Inspection
ML21062A0652021-03-0101 March 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting
ML21049A2572021-02-18018 February 2021
Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237)
ML20365A0092020-12-30030 December 2020
Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114)
ML20358A2602020-12-28028 December 2020
Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency
ML20272A2802020-09-28028 September 2020
Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times
ML20248H5192020-09-28028 September 2020
Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times
ML20246G6362020-09-0202 September 2020
Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times
NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-08-28028 August 2020
Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
ML20239A7982020-08-25025 August 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2
ML20212L8702020-07-30030 July 2020
Request for Additonal Information Review of License Amendment Requests Regarding Riskinformed Categorization and Treatment of Structures, Systems and Components (L-2019-LLA-0290)
ML20213A9352020-07-30030 July 2020
Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times
ML20153A7042020-06-0101 June 2020
NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26
ML20135H1972020-05-14014 May 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval
ML20045E3582020-02-14014 February 2020
Draft Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates
ML19296A1862019-10-23023 October 2019
Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates (L-2019-LLA-0115)
ML19275H1362019-10-0202 October 2019
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879
ML19179A0612019-07-19019 July 2019
Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879
ML19151A8132019-05-31031 May 2019
Licensed Operator Positive Fitness-For-Duty Test
ML19025A1572019-01-25025 January 2019
Request for Additional Information Regarding Primary Containment Oxygen Concentration License Amendment Request
ML19025A1202019-01-24024 January 2019
NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing
ML18341A2212018-12-0707 December 2018
Request for Additional Information Regarding Emergency Tech Spec Change Re HPCS Completion Time (EPID -L-2018-LLA-0491)
ML18228A6932018-08-15015 August 2018
Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426)
ML18205A3922018-07-24024 July 2018
Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426)
ML18184A2882018-07-0303 July 2018
Request for Additional Information Regarding Removal of Boraflex Credit from Spent Fuel Pool License Amendment Request(L-2018-LLA-0039)
ML18102A2372018-04-12012 April 2018
NRR E-mail Capture - Calvert Cliffs, Ginna, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Schemes (EPID-L-2017-LLA-0237)
ML18067A1482018-03-0808 March 2018
Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation)
ML17331B1342017-12-12012 December 2017
2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding
ML17285B1962017-10-27027 October 2017
Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.
ML17272A0112017-10-10010 October 2017
Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control
ML17234A3592017-08-30030 August 2017
Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702
ML17241A2752017-08-29029 August 2017
Request for Additional Information Response MSA (MF7946,7) and FE (MG0087,8) E-mail Attachment
2024-07-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 20, 2014 Mr. Christopher Costanzo Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. 0. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.2- FIRST ROUND OF REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST PURSUANT TO 10 CFR 50.90: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+) (TAC NO. MF3056)
Dear Mr. Costanzo:
By letter dated November 1, 2013 (Agencywide Document Access and Management System (ADAMS) Package Accession No. ML13316B090), as supplemented by letter dated January 21, 2014 (ADAMS Accession No. ML14023A654), Nine Mile Point Nuclear Station, LLC (the licensee) submitted a license amendment request for Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would (1) allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) domain; (2) use of the Detect and Suppress Solution - Confirmation Density (DSS-CD) stability solution, (3) use of the TRACG04 analysis code; (4) increase the isotopic enrichment of boron-1 0 in the sodium pentaborate solution used to prepare the neutron absorber solution in the Standby Liquid Control System (SLS); and (5) increase the Safety Limit Minimum Critical Power Ratio (SLMCPR) for two recirculation loops in operation.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your submission and has determined that additional information is needed to complete its review.
The draft request for additional information (RAI) was transmitted to you by e-mail dated January 31, 2014 (ADAMS Accession No. ML14031A178). In the telephone conversation with your staff, Mr. Kenneth Kristensen, on February 11, 2014, your staff committed your response to these RAis by March 10, 2014.
The NRC staff's final version of the RAI is provided in the enclosure to this letter.
Sincerely,
~d-~
~
Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-41 0
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
FIRST ROUND REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST RE: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS CONSTELLATION ENERGY NINE MILE POINT NUCLEAR STATION, UNIT 2 By letter dated November 1, 2013 (Agencywide Document Access and Management System (ADAMS) Package Accession No. ML133168090), Constellation Energy (the licensee) submitted a license amendment request for maximum extended load line limit analysis plus (MELLLA+). The proposed amendment request would allow operation in the expanded MELLLA+ domain.
Upon review of Attachment 10 (ADAMS Accession No. ML133168107) to the submittal titled "Safety Analysis Report for Nine Mile Point Unit 2 Maximum Extended Load Line Limit Analysis Plus" (ADAMS Accession No. ML133168113), the staff has the following requests for additional information:
SRXB RAI1:
Section 9.3.3 of Attachment 10 states that zirconium credit will be used in the Shumway correlation. The staff is aware of the zirconium data described in letter dated September 9, 2013 (ADAMS Accession No. ML13253A105) from GE Hitachi Nuclear Energy to the NRC staff.
(a) Fresh fuel has little or no oxide at the start of the transient and the fresh fuel is often in the more reactive part of the core; therefore, it is the data of interest.
Figure 6 of the September 9, 2013 letter has many data sets displayed together on it. Provide a plot showing clean zirconium separate from all the other data including SS, lnconel, zirconium oxide and any data that would be expected to have oxidized zirconium.
(b) In the September 9, 2013 letter, much of the Hoffman (FKZ) data that has a rapid cooling rate early in the experiment may have been incorrectly interpreted as a quench. A closer examination of the data shows this initial cooling was due to startup of the test and that quench occurred much later at significantly lower temperatures. In addition, because of high temperatures during the tests and pre-conditioning of the rods, the rods are likely to have thick oxide layer thicknesses that are not representative of fuel in a commercial reactor undergoing an Anticipated Transient without Scram with Instability (ATWS-1) event. Provide a plot showing the data considered valid by the licensee for justifying Shumway as implemented in TRACG for the intended application (e.g. ATWS-1 under MELLLA+). Also provide textual justification to support the choice of the selected data and exclusion of the other data, focusing on comparing the applicable test conditions to the plant application conditions to support a conclusion that the data is applicable.
Enclosure
SRXB RAI2:
Section 9.3.3 of Attachment 10 states:
The plant-specific A TWS stability calculation was performed using the NRC-approved neutronic and thermal-hydraulic codes ... TRACG04.
An error in the code was corrected by letter from GE Hitachi Nuclear Energy to the staff dated October 15, 2013 titled "Updated TRACG Quench Front Model Description and Qualification", which is currently under staff review. In the October 15, 2013 letter, GE noted:
The quench front model has been updated to correct an error in the quench front heat transfer coefficient for bottom reflooding, and to better capture the heat transfer ahead of and behind the quench front.
Please clarify which quench model is being used in the application.
ML14023A654), Nine Mile Point Nuclear Station, LLC (the licensee) submitted a license amendment request for Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would (1) allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) domain; (2) use of the Detect and Suppress Solution - Confirmation Density (DSS-CD) stability solution, (3) use of the TRACG04 analysis code; (4) increase the isotopic enrichment of boron-10 in the sodium pentaborate solution used to prepare the neutron absorber solution in the Standby Liquid Control System (SLS); and (5) increase the Safety Limit Minimum Critical Power Ratio (SLMCPR) for two recirculation loops in operation.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your submission and has determined that additional information is needed to complete its review.
The draft request for additional information (RAI) was transmitted to you by e-mail dated January 31, 2014 (ADAMS Accession No. ML14031A178). In the telephone conversation with your staff, Mr. Kenneth Kristensen, on February 11, 2014, your staff committed your response to these RAis by March 10, 2014.
The NRC staff's final version of the RAI is provided in the enclosure to this letter.
Sincerely, Ira/
Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-41 0
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL 1-1 R/F RidsNrrDssStsb Resource RidsNrrDorllpl1-1 Resource RidsNrrLAKGoldstein Resource RidsNrrPMNineMilePoint Resource RidsRgn1 MaiiCenter Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrDssSrxb Resource RidsNrrDssSnpb Resource RidsNrrDssEicb Resource RidsNrrDssScvb Resource DSchroeder, Region 1 ADAMS Accession No.: ML14043A006 (*)Transmitted by memo dated 01/22/2014 OFFICE NRR/LPL 1-1\PM NRR/LPL 1-1\LA NRR/SRXB/BC(*) NRR/LPL 1-1/BC NRR/LPL 1-1\PM NAME BVaidya KGoldstein CJackson BBeasley BVaidya DATE 02/12114 02/12/14 01/22/14 02/19/14 02/20/14
