ML12088A207: Difference between revisions
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| document type = Letter, Request for Additional Information (RAI) | | document type = Letter, Request for Additional Information (RAI) | ||
| page count = 3 | | page count = 3 | ||
| project = TAC: | | project = TAC:ME7095, TAC:ME7094 | ||
| stage = RAI | | stage = RAI | ||
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=Text= | =Text= | ||
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095) Dear Mr. Ajluni: By letter dated September 9,2011 (Agencywide Documents Access and Management System Accession No. ML 112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. Please provide your response to the request for additional information within thirty (30) days of the date of this letter. Sincerely, Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: Distribution via Listserv REQUESTS FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 "LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION TABLE 3.3.1-1" SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-348 AND 50-364 TAC NOS. ME7094 AND ME7095 The following is a listing of comments, questions, and clarifications noted during the initial review of the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 License Amendment Request (LAR) for Technical Specification (TS) Table 3.3.1-1. The control rod withdrawal at power (RWAP) safety analysis presented in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) was intended to demonstrate that core protection reactor trips prevent exceeding specified acceptable fuel design limits (SAFDLs). As such, the analytical methods used in the RWAP safety analysis use large conservatisms relative to fuel design limits. One reason for the focus on meeting SAFDLs with the RWAP safety analysis is the RWAP event has traditionally been considered to be non-limiting with respect to reactor coolant system (RCS) pressure limits. Please elaborate on the reasons for the change in the analytical approach of the RWAP safety analysis to now consider RCS overpressure conditions as opposed to the traditional focus on SAFDLs and supply technical justification in support of it. On page E1-4 of the LAR the worst case analyzed for the affect of RWAP on the RCS is presented. This case indicates that the rod cluster control assemblies (RCCAs) were released via the high pressurizer pressure Signal, but indicates the positive flux rate trip (PFRT) was responsible in other cases. Please provide the initial conditions and time sequence of events for the worst case analyzed (peak RCS pressure) RWAP RCS overpressure analysis in which the PFRT signal was responsible for releasing RCCAs. Please provide this information in a tabular form similar to that of the case presented on page E 1-4 of the LAR and indicate the maximum RCS pressure reached with and without the PFRT credit. The RWAP overpressure reanalysis results are presented in the LAR as a justification for crediting the PFRT, which is not currently done, and to ensure the associated response time for the PFRT, currently listed as "N/A" in the FNP UFSAR, is verified on a routine basis through the inclusion of SR [Surveillance Requirement] 3.3.1.14 in TS Table 3.3.1-1. Please provide clarification on the plans of Southern Nuclear Operating Company, Inc. to reflect the change in associated response time for PFRT and the RWAP overpressure reanalysis results in an update of the UFSAR, pursuant to the requirements of Title 10 of the Code ofFederal Regulations (10 CFR), Part 50, Section 50.71, "Maintenance of records, making of reports." | {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095) | ||
April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095) Dear Mr. Ajluni: By letter dated September 9, 2011 (Agencywide Documents Access and Management System Accession No. ML 112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. Please provide your response to the request for additional information within thirty (30) days of the date of this letter. Sincerely, IRA! Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource KHeller, NRR RidsNrrDssStsb Resource RidsNrrPMFarley Resource RidsNrrDeEicb Resource RAlvarado, NRR ADAMS Accession No.: ML12088A207 RULPL2-1/PM SS/SNPB/BC | |||
==Dear Mr. Ajluni:== | |||
By letter dated September 9,2011 (Agencywide Documents Access and Management System Accession No. ML 112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. Please provide your response to the request for additional information within thirty (30) days of the date of this letter. Sincerely, Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: Distribution via Listserv REQUESTS FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 "LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION TABLE 3.3.1-1" SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-348 AND 50-364 TAC NOS. ME7094 AND ME7095 The following is a listing of comments, questions, and clarifications noted during the initial review of the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 License Amendment Request (LAR) for Technical Specification (TS) Table 3.3.1-1. The control rod withdrawal at power (RWAP) safety analysis presented in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) was intended to demonstrate that core protection reactor trips prevent exceeding specified acceptable fuel design limits (SAFDLs). As such, the analytical methods used in the RWAP safety analysis use large conservatisms relative to fuel design limits. One reason for the focus on meeting SAFDLs with the RWAP safety analysis is the RWAP event has traditionally been considered to be non-limiting with respect to reactor coolant system (RCS) pressure limits. Please elaborate on the reasons for the change in the analytical approach of the RWAP safety analysis to now consider RCS overpressure conditions as opposed to the traditional focus on SAFDLs and supply technical justification in support of it. On page E1-4 of the LAR the worst case analyzed for the affect of RWAP on the RCS is presented. This case indicates that the rod cluster control assemblies (RCCAs) were released via the high pressurizer pressure Signal, but indicates the positive flux rate trip (PFRT) was responsible in other cases. Please provide the initial conditions and time sequence of events for the worst case analyzed (peak RCS pressure) RWAP RCS overpressure analysis in which the PFRT signal was responsible for releasing RCCAs. Please provide this information in a tabular form similar to that of the case presented on page E 1-4 of the LAR and indicate the maximum RCS pressure reached with and without the PFRT credit. The RWAP overpressure reanalysis results are presented in the LAR as a justification for crediting the PFRT, which is not currently done, and to ensure the associated response time for the PFRT, currently listed as "N/A" in the FNP UFSAR, is verified on a routine basis through the inclusion of SR [Surveillance Requirement] 3.3.1.14 in TS Table 3.3.1-1. Please provide clarification on the plans of Southern Nuclear Operating Company, Inc. to reflect the change in associated response time for PFRT and the RWAP overpressure reanalysis results in an update of the UFSAR, pursuant to the requirements of Title 10 of the Code ofFederal Regulations (10 CFR), Part 50, Section 50.71, "Maintenance of records, making of reports." | |||
April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095) | |||
==Dear Mr. Ajluni:== | |||
By letter dated September 9, 2011 (Agencywide Documents Access and Management System Accession No. ML 112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. Please provide your response to the request for additional information within thirty (30) days of the date of this letter. Sincerely, IRA! Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource KHeller, NRR RidsNrrDssStsb Resource RidsNrrPMFarley Resource RidsNrrDeEicb Resource RAlvarado, NRR ADAMS Accession No.: ML12088A207 RULPL2-1/PM SS/SNPB/BC | |||
* B memo dated DORULPL2-1/BC DORULPL2-1/PM SFigueroa NSalgado RMartin 03/29/12 102/12 04/04/12 04/04/12 OFFICIAL RECORD COpy | * B memo dated DORULPL2-1/BC DORULPL2-1/PM SFigueroa NSalgado RMartin 03/29/12 102/12 04/04/12 04/04/12 OFFICIAL RECORD COpy | ||
}} | }} |
Revision as of 15:09, 5 April 2018
ML12088A207 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
Issue date: | 04/04/2012 |
From: | Martin R E Plant Licensing Branch II |
To: | Ajluni M J Southern Nuclear Operating Co |
Martin R E | |
References | |
TAC ME7094, TAC ME7095 | |
Download: ML12088A207 (3) | |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095)
Dear Mr. Ajluni:
By letter dated September 9,2011 (Agencywide Documents Access and Management System Accession No. ML 112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. Please provide your response to the request for additional information within thirty (30) days of the date of this letter. Sincerely, Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: Distribution via Listserv REQUESTS FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 "LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION TABLE 3.3.1-1" SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-348 AND 50-364 TAC NOS. ME7094 AND ME7095 The following is a listing of comments, questions, and clarifications noted during the initial review of the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 License Amendment Request (LAR) for Technical Specification (TS) Table 3.3.1-1. The control rod withdrawal at power (RWAP) safety analysis presented in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) was intended to demonstrate that core protection reactor trips prevent exceeding specified acceptable fuel design limits (SAFDLs). As such, the analytical methods used in the RWAP safety analysis use large conservatisms relative to fuel design limits. One reason for the focus on meeting SAFDLs with the RWAP safety analysis is the RWAP event has traditionally been considered to be non-limiting with respect to reactor coolant system (RCS) pressure limits. Please elaborate on the reasons for the change in the analytical approach of the RWAP safety analysis to now consider RCS overpressure conditions as opposed to the traditional focus on SAFDLs and supply technical justification in support of it. On page E1-4 of the LAR the worst case analyzed for the affect of RWAP on the RCS is presented. This case indicates that the rod cluster control assemblies (RCCAs) were released via the high pressurizer pressure Signal, but indicates the positive flux rate trip (PFRT) was responsible in other cases. Please provide the initial conditions and time sequence of events for the worst case analyzed (peak RCS pressure) RWAP RCS overpressure analysis in which the PFRT signal was responsible for releasing RCCAs. Please provide this information in a tabular form similar to that of the case presented on page E 1-4 of the LAR and indicate the maximum RCS pressure reached with and without the PFRT credit. The RWAP overpressure reanalysis results are presented in the LAR as a justification for crediting the PFRT, which is not currently done, and to ensure the associated response time for the PFRT, currently listed as "N/A" in the FNP UFSAR, is verified on a routine basis through the inclusion of SR [Surveillance Requirement] 3.3.1.14 in TS Table 3.3.1-1. Please provide clarification on the plans of Southern Nuclear Operating Company, Inc. to reflect the change in associated response time for PFRT and the RWAP overpressure reanalysis results in an update of the UFSAR, pursuant to the requirements of Title 10 of the Code ofFederal Regulations (10 CFR), Part 50, Section 50.71, "Maintenance of records, making of reports."
April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095)
Dear Mr. Ajluni:
By letter dated September 9, 2011 (Agencywide Documents Access and Management System Accession No. ML 112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. Please provide your response to the request for additional information within thirty (30) days of the date of this letter. Sincerely, IRA! Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource KHeller, NRR RidsNrrDssStsb Resource RidsNrrPMFarley Resource RidsNrrDeEicb Resource RAlvarado, NRR ADAMS Accession No.: ML12088A207 RULPL2-1/PM SS/SNPB/BC
- B memo dated DORULPL2-1/BC DORULPL2-1/PM SFigueroa NSalgado RMartin 03/29/12 102/12 04/04/12 04/04/12 OFFICIAL RECORD COpy