ML16055A369: Difference between revisions

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| issue date = 02/24/2016
| issue date = 02/24/2016
| title = Acceptance Review: Limerick 1 & 2 - Reduce Steam Dome Pressure Amendment Request (CACs MF7263 and MF7264)
| title = Acceptance Review: Limerick 1 & 2 - Reduce Steam Dome Pressure Amendment Request (CACs MF7263 and MF7264)
| author name = Ennis R B
| author name = Ennis R
| author affiliation = NRC/NRR/DORL/LPLI-2
| author affiliation = NRC/NRR/DORL/LPLI-2
| addressee name = Stewart G
| addressee name = Stewart G
Line 9: Line 9:
| docket = 05000352, 05000353
| docket = 05000352, 05000353
| license number =  
| license number =  
| contact person = Ennis R B
| contact person = Ennis R
| case reference number = CAC MF7263, CAC MF7264
| case reference number = CAC MF7263, CAC MF7264
| document type = Acceptance Review Letter, E-Mail
| document type = Acceptance Review Letter, E-Mail
| page count = 2
| page count = 2
| project = CAC:MF7263, CAC:MF7264
| project = CAC:MF7263, CAC:MF7264
| stage = Other
| stage = Acceptance Review
}}
}}


=Text=
=Text=
{{#Wiki_filter:From: Ennis, Rick Sent: Wednesday, February 24, 2016 2:06 PM To: Glenn Stewart (glenn.stewart@exeloncorp.com) Cc: David Helker Subject: Acceptance Review: Limerick 1 & 2 - Reduce Steam Dome Pressure Amendment Request - CACs MF7263 & 64   Glenn, By letter dated January 15, 2015 (ADAMS Accession No. ML16015A316), Exelon Generation Company, LLC submitted a license amendment request for Limerick Generating Station, Units 1 and 2. The proposed amendment would reduce the reactor vessel steam dome pressure associated with the Technical Specification (TS) safety limits specified in TS 2.1.1 and TS 2.1.2. The amendment would also revise the setpoint and allowable value for the main steam line low pressure isolation function in TS Table 3.3.2-2. The proposed changes address a Title 10 of the Code of Federal Regulations (10 CFR), Part 21 issue concerning the potential to violate the safety limits during a pressure regulator failure maximum demand (open) (PRFO) transient. The purpose of this e-mail is to provide the results of the NRC staff's acceptance review of this amendment request. 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.
{{#Wiki_filter:From:                         Ennis, Rick Sent:                         Wednesday, February 24, 2016 2:06 PM To:                           Glenn Stewart (glenn.stewart@exeloncorp.com)
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 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 it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1420. Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353  
Cc:                           David Helker
}}
 
==Subject:==
Acceptance Review: Limerick 1 & 2 - Reduce Steam Dome Pressure Amendment Request - CACs MF7263 & 64
: Glenn, By letter dated January 15, 2015 (ADAMS Accession No. ML16015A316), Exelon Generation Company, LLC submitted a license amendment request for Limerick Generating Station, Units 1 and 2. The proposed amendment would reduce the reactor vessel steam dome pressure associated with the Technical Specification (TS) safety limits specified in TS 2.1.1 and TS 2.1.2. The amendment would also revise the setpoint and allowable value for the main steam line low pressure isolation function in TS Table 3.3.2-2. The proposed changes address a Title 10 of the Code of Federal Regulations (10 CFR), Part 21 issue concerning the potential to violate the safety limits during a pressure regulator failure maximum demand (open) (PRFO) transient.
The purpose of this e-mail is to provide the results of the NRC staffs acceptance review of this amendment request. 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 (10 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 it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-1420.
Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
 
Docket Nos. 50-352 and 50-353}}

Latest revision as of 23:45, 30 October 2019

Acceptance Review: Limerick 1 & 2 - Reduce Steam Dome Pressure Amendment Request (CACs MF7263 and MF7264)
ML16055A369
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 02/24/2016
From: Richard Ennis
Plant Licensing Branch 1
To: Stewart G
Exelon Generation Co
Ennis R
References
CAC MF7263, CAC MF7264
Download: ML16055A369 (2)
v • d • e


Text

From: Ennis, Rick Sent: Wednesday, February 24, 2016 2:06 PM To: Glenn Stewart (glenn.stewart@exeloncorp.com)

Cc: David Helker

Subject:

Acceptance Review: Limerick 1 & 2 - Reduce Steam Dome Pressure Amendment Request - CACs MF7263 & 64

Glenn, By letter dated January 15, 2015 (ADAMS Accession No. ML16015A316), Exelon Generation Company, LLC submitted a license amendment request for Limerick Generating Station, Units 1 and 2. The proposed amendment would reduce the reactor vessel steam dome pressure associated with the Technical Specification (TS) safety limits specified in TS 2.1.1 and TS 2.1.2. The amendment would also revise the setpoint and allowable value for the main steam line low pressure isolation function in TS Table 3.3.2-2. The proposed changes address a Title 10 of the Code of Federal Regulations (10 CFR), Part 21 issue concerning the potential to violate the safety limits during a pressure regulator failure maximum demand (open) (PRFO) transient.

The purpose of this e-mail is to provide the results of the NRC staffs acceptance review of this amendment request. 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 (10 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 it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.

If you have any questions, please contact me at (301) 415-1420.

Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-352 and 50-353

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