ML19070A242: Difference between revisions

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| issue date = 03/11/2019
| issue date = 03/11/2019
| title = Acceptance Review Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds
| title = Acceptance Review Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds
| author name = Parker C J
| author name = Parker C
| author affiliation = NRC/NRR/DORL/LPLI
| author affiliation = NRC/NRR/DORL/LPLI
| addressee name = Bologna R D
| addressee name = Bologna R
| addressee affiliation = FirstEnergy Nuclear Operating Co
| addressee affiliation = FirstEnergy Nuclear Operating Co
| docket = 05000412
| docket = 05000412
| license number = NPF-073
| license number = NPF-073
| contact person = Parker C J
| contact person = Parker C
| case reference number = EPID L-2019-LLR-0013
| case reference number = EPID L-2019-LLR-0013
| document type = E-Mail
| document type = E-Mail
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:From: Parker, Carleen To: "phlashley@firstenergycorp.com" Cc: Collins, Jay
{{#Wiki_filter:From:           Parker, Carleen To:             "phlashley@firstenergycorp.com" Cc:             Collins, Jay; Danna, James; Cumblidge, Stephen
; Danna, James
; Cumblidge, Stephen


==Subject:==
==Subject:==
Acceptance Review - Beaver Valley Unit 2: Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (L-2019-LLR-0013)
Acceptance Review - Beaver Valley Unit 2: Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (L-2019-LLR-0013)
Date: Monday, March 11, 2019 8:43:00 AM Phil, By letter dated February 20, 2019 (Agencywide Document Access and Management System (ADAMS) Accession No. ML19051A108), FirstEnergy Nuclear Operating Company (FENOC) submitted a request for an alternative examination frequency for cold leg reactor vessel inlet nozzle to safe-end welds at Beaver Valley Power Station, Unit No. 2.Specifically, FENOC is proposing an alternative to the American Society of Mechanical Engineers' Boiler and Pressure Vessel Code Case N-770-2 inspection frequency requirements to volumetrically examine the reactor vessel cold leg nozzle to safe-end welds every second inspection period, not to exceed 7 years. The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this relief 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. Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment.
Date:           Monday, March 11, 2019 8:43:00 AM
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.
: Phil, By letter dated February 20, 2019 (Agencywide Document Access and Management System (ADAMS) Accession No. ML19051A108), FirstEnergy Nuclear Operating Company (FENOC) submitted a request for an alternative examination frequency for cold leg reactor vessel inlet nozzle to safe-end welds at Beaver Valley Power Station, Unit No. 2.
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 150 hours to complete. The NRC staff expects to complete this review by your requested date of February 28, 2020. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), the reasons for the changes, along with the new estimates will be communicated, during the routine interactions with the assigned project manager.
Specifically, FENOC is proposing an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-770-2 inspection frequency requirements to volumetrically examine the reactor vessel cold leg nozzle to safe-end welds every second inspection period, not to exceed 7 years.
These estimates are based on the staff's initial review of the application and they could change, due to several factors including requests for additional information and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.
The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this relief 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.
If you have any questions, please contact me. Carleen Carleen Parker Project Manager -   Beaver Valley and FitzPatrick Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301)415-1603 carleen.parker@nrc.gov}}
Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative 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.
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately [[estimated NRC review hours::150 hours]] to complete. The NRC staff expects to complete this review by your requested date of February 28, 2020. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), the reasons for the changes, along with the new estimates will be communicated, during the routine interactions with the assigned project manager.
 
These estimates are based on the staffs initial review of the application and they could change, due to several factors including requests for additional information and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.
If you have any questions, please contact me.
Carleen Carleen Parker Project Manager -
Beaver Valley and FitzPatrick Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301)415-1603 carleen.parker@nrc.gov}}

Latest revision as of 13:30, 5 March 2020

Acceptance Review Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds
ML19070A242
Person / Time
Site: Beaver Valley
Issue date: 03/11/2019
From: Carleen Parker
Plant Licensing Branch 1
To: Bologna R
FirstEnergy Nuclear Operating Co
Parker C
References
EPID L-2019-LLR-0013
Download: ML19070A242 (2)
v • d • e


Text

From: Parker, Carleen To: "phlashley@firstenergycorp.com" Cc: Collins, Jay; Danna, James; Cumblidge, Stephen

Subject:

Acceptance Review - Beaver Valley Unit 2: Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (L-2019-LLR-0013)

Date: Monday, March 11, 2019 8:43:00 AM

Phil, By letter dated February 20, 2019 (Agencywide Document Access and Management System (ADAMS) Accession No. ML19051A108), FirstEnergy Nuclear Operating Company (FENOC) submitted a request for an alternative examination frequency for cold leg reactor vessel inlet nozzle to safe-end welds at Beaver Valley Power Station, Unit No. 2.

Specifically, FENOC is proposing an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-770-2 inspection frequency requirements to volumetrically examine the reactor vessel cold leg nozzle to safe-end welds every second inspection period, not to exceed 7 years.

The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this relief 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.

Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative 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.

Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 150 hours6.25 days <br />0.893 weeks <br />0.205 months <br /> to complete. The NRC staff expects to complete this review by your requested date of February 28, 2020. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), the reasons for the changes, along with the new estimates will be communicated, during the routine interactions with the assigned project manager.

These estimates are based on the staffs initial review of the application and they could change, due to several factors including requests for additional information and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.

If you have any questions, please contact me.

Carleen Carleen Parker Project Manager -

Beaver Valley and FitzPatrick Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301)415-1603 carleen.parker@nrc.gov

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