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| number = ML14042A514
| number = ML14042A514
| issue date = 02/18/2014
| issue date = 02/18/2014
| title = LaSalle County Station, Unit 1, Supplement Information Needed for Acceptance of License Amendment Request to Revise Pressure and Temperature Limit Curves
| title = Supplement Information Needed for Acceptance of License Amendment Request to Revise Pressure and Temperature Limit Curves
| author name = Purnell B A
| author name = Purnell B
| author affiliation = NRC/NRR/DORL/LPLIII-2
| author affiliation = NRC/NRR/DORL/LPLIII-2
| addressee name = Pacilio M J
| addressee name = Pacilio M
| addressee affiliation = Exelon Generation Co, LLC
| addressee affiliation = Exelon Generation Co, LLC
| docket = 05000373, 05000374
| docket = 05000373, 05000374
Line 14: Line 14:
| page count = 4
| page count = 4
| project = TAC:MF3270, TAC:MF3271
| project = TAC:MF3270, TAC:MF3271
| stage = Supplement
| stage = Acceptance Review
}}
}}


=Text=
=Text=
{{#Wiki_filter:Mr. Michael J. Pacilio Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2014 Exelon Generation  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2014 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
: Company, LLC President and Chief Nuclear Officer (CNO) Exelon Generation  
Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
: Company, LLC 4300 Winfield Road Warrenville, IL 60555  


==SUBJECT:==
==SUBJECT:==
 
LASALLE COUNTY STATION, UNIT 1- SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST TO REVISE PRESSURE AND TEMPERATURE LIMIT CURVES (TAC NOS.
LASALLE COUNTY STATION, UNIT 1-SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST TO REVISE PRESSURE AND TEMPERATURE LIMIT CURVES (TAC NOS. MF3270 AND MF3271)  
MF3270 AND MF3271)


==Dear Mr. Pacilio:==
==Dear Mr. Pacilio:==


By letter dated December 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13358A363),
By letter dated December 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A363), Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR) to revise Technical Specification (TS) 3.4.11, "RCS [reactor coolant system] Pressure and Temperature (PIT) Limits," for LaSalle County Station, Unit 1.
Exelon Generation  
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
: Company, LLC (EGC) submitted a license amendment request (LAR) to revise Technical Specification (TS) 3.4.11, "RCS [reactor coolant system] Pressure and Temperature (PIT) Limits,"
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following, as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
for LaSalle County Station, Unit 1. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following, as far as applicable, the form prescribed for original applications.
Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application  
In order to make the application complete, the NRC staff requests that EGC supplement the application to address the information requested by February 27, 2014. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review
: complete, the NRC staff requests that EGC supplement the application to address the information requested by February 27, 2014. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review M. Pacilio pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application.
 
If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
M. Pacilio                                   pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and the associated timeframe in this letter were discussed with Lisa Simpson of your staff on February 7, 2014. If you have any questions, please contact me by phone at (301) 415-1380 or email at Blake. Purnell@nrc.gov.
The information requested and the associated timeframe in this letter were discussed with Lisa Simpson of your staff on February 7, 2014.
Docket Nos. 50-373 and 50-37 4
If you have any questions, please contact me by phone at (301) 415-1380 or email at Blake. Purnell@nrc.gov.
Sincerely, Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374


==Enclosure:==
==Enclosure:==


As stated cc w/encl: Distribution via Listserv Sincerely, Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ADDITIONAL INFORMATION NEEDED FOR LICENSE AMENDMENT REQUEST REGARDING REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMITS EXELON GENERATION  
As stated cc w/encl: Distribution via Listserv
: COMPANY, LLC LASALLE COUNTY STATION, UNIT 1 DOCKET NO. 50-373 By letter dated December 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13358A363),
 
Exelon Generation  
ADDITIONAL INFORMATION NEEDED FOR LICENSE AMENDMENT REQUEST REGARDING REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMITS EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNIT 1 DOCKET NO. 50-373 By letter dated December 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A363), Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR) to revise Technical Specification 3.4.11, "RCS [reactor coolant system] Pressure and Temperature (Pff) Limits," for LaSalle County Station, Unit 1.
: Company, LLC (EGC) submitted a license amendment request (LAR) to revise Technical Specification 3.4.11, "RCS [reactor coolant system] Pressure and Temperature (Pff) Limits,"
The U.S. Nuclear Regulatory Commission (NRC) staff has performed an acceptance review of the submittal and has determined that additional information is needed before the staff can begin its detailed technical review.
for LaSalle County Station, Unit 1. The U.S. Nuclear Regulatory Commission (NRC) staff has performed an acceptance review of the submittal and has determined that additional information is needed before the staff can begin its detailed technical review. Background The LAR relies on methods described in General Electric-Hitachi (GEH) licensing topical report {TR) NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves" (ADAMS Accession No. ML092370487),
to determine the revised Prr limits. As a condition of TR NEDC-33178P-A, the licensee needs to determine the fluence values using an NRC-approved methodology.
The LAR states that two different methods were combined to determine the fluence values. The LAR states, "EGC has determined the dual methodology approach utilized to support this LAR results in more conservative fluence input to the Prr curves."
: However, the LAR states this determination was made using draft calculations.
The NRC staff has not approved the combination of two methodologies for determining fluence values. Therefore, the staff considers this a deviation from TR NEDC-33178P-A, as EGC was previously informed in a letter dated December 5, 2013 (ADAMS Accession No. ML 13269A323).
The LAR does not provide adequate justification for combining two methods to determine the fluence, since the staff cannot rely on draft information in its safety reviews.
Request Provide adequate justification for the combination of two methods for determining fluence.
Also, provide calculations and other supporting documents used for this justification.
Enclosure M. Pacilio pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application.
If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and the associated timeframe in this letter were discussed with Lisa Simpson of your staff on February 7, 2014. If you have any questions, please contact me by phone at (301) 415-1380 or email at Blake. Purnell@nrc.gov.
Sincerely, IRA/ Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-37 4


==Enclosure:==
===Background===
The LAR relies on methods described in General Electric-Hitachi (GEH) licensing topical report
{TR) NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves" (ADAMS Accession No. ML092370487), to determine the revised Prr limits. As a condition of TR NEDC-33178P-A, the licensee needs to determine the fluence values using an NRC-approved methodology.
The LAR states that two different methods were combined to determine the fluence values. The LAR states, "EGC has determined the dual methodology approach utilized to support this LAR results in more conservative fluence input to the Prr curves." However, the LAR states this determination was made using draft calculations.
The NRC staff has not approved the combination of two methodologies for determining fluence values. Therefore, the staff considers this a deviation from TR NEDC-33178P-A, as EGC was previously informed in a letter dated December 5, 2013 (ADAMS Accession No. ML13269A323). The LAR does not provide adequate justification for combining two methods to determine the fluence, since the staff cannot rely on draft information in its safety reviews.
Request Provide adequate justification for the combination of two methods for determining fluence. Also, provide calculations and other supporting documents used for this justification.
Enclosure


As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
ML14042A514 OFFICE   LPL3-2/PM       LPL3-2/LA             DSS/SRXB/BC       LPL3-2/BC            LPL3-2/PM NAME     BPurnell         SRohrer               CJackson         TTate                BPurnell DATE     2/18/14         21 12/14             2114/14           21 18/14             2118/14}}
PUBLIC LPL3-2 RidsNrrLASRohrer Resource RidsRgn3MaiiCenter Resource MHardgrove, NRR RGrover, NRR RidsNrrDoriDpr Resource RidsNrrPMLaSalle Resource RidsNrrDssStsb Resource SParks, NRR ADAMS Accession No ML 14042A514 OFFICE LPL3-2/PM LPL3-2/LA DSS/SRXB/BC NAME BPurnell SRohrer CJackson DATE 2/18/14 21 12/14 2114/14 OFFICIAL RECORD COPY RidsNrrDorllpl3-2 Resource RidsNrrDssSrxb Resource RidsNrrDeEvib Resource PPurtscher, NRR LPL3-2/BC LPL3-2/PM TTate BPurnell 21 18/14 2118/14}}

Latest revision as of 08:19, 4 November 2019

Supplement Information Needed for Acceptance of License Amendment Request to Revise Pressure and Temperature Limit Curves
ML14042A514
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 02/18/2014
From: Blake Purnell
Plant Licensing Branch III
To: Pacilio M
Exelon Generation Co
Blake Purnell, NRR/DORL 415-1380
References
TAC MF3270, TAC MF3271
Download: ML14042A514 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2014 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNIT 1- SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST TO REVISE PRESSURE AND TEMPERATURE LIMIT CURVES (TAC NOS.

MF3270 AND MF3271)

Dear Mr. Pacilio:

By letter dated December 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A363), Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR) to revise Technical Specification (TS) 3.4.11, "RCS [reactor coolant system] Pressure and Temperature (PIT) Limits," for LaSalle County Station, Unit 1.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following, as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment.

In order to make the application complete, the NRC staff requests that EGC supplement the application to address the information requested by February 27, 2014. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review

M. Pacilio pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.

The information requested and the associated timeframe in this letter were discussed with Lisa Simpson of your staff on February 7, 2014.

If you have any questions, please contact me by phone at (301) 415-1380 or email at Blake. Purnell@nrc.gov.

Sincerely, Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374

Enclosure:

As stated cc w/encl: Distribution via Listserv

ADDITIONAL INFORMATION NEEDED FOR LICENSE AMENDMENT REQUEST REGARDING REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMITS EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNIT 1 DOCKET NO. 50-373 By letter dated December 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A363), Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR) to revise Technical Specification 3.4.11, "RCS [reactor coolant system] Pressure and Temperature (Pff) Limits," for LaSalle County Station, Unit 1.

The U.S. Nuclear Regulatory Commission (NRC) staff has performed an acceptance review of the submittal and has determined that additional information is needed before the staff can begin its detailed technical review.

Background

The LAR relies on methods described in General Electric-Hitachi (GEH) licensing topical report

{TR) NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves" (ADAMS Accession No. ML092370487), to determine the revised Prr limits. As a condition of TR NEDC-33178P-A, the licensee needs to determine the fluence values using an NRC-approved methodology.

The LAR states that two different methods were combined to determine the fluence values. The LAR states, "EGC has determined the dual methodology approach utilized to support this LAR results in more conservative fluence input to the Prr curves." However, the LAR states this determination was made using draft calculations.

The NRC staff has not approved the combination of two methodologies for determining fluence values. Therefore, the staff considers this a deviation from TR NEDC-33178P-A, as EGC was previously informed in a letter dated December 5, 2013 (ADAMS Accession No. ML13269A323). The LAR does not provide adequate justification for combining two methods to determine the fluence, since the staff cannot rely on draft information in its safety reviews.

Request Provide adequate justification for the combination of two methods for determining fluence. Also, provide calculations and other supporting documents used for this justification.

Enclosure

ML14042A514 OFFICE LPL3-2/PM LPL3-2/LA DSS/SRXB/BC LPL3-2/BC LPL3-2/PM NAME BPurnell SRohrer CJackson TTate BPurnell DATE 2/18/14 21 12/14 2114/14 21 18/14 2118/14

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