ML17340A967: Difference between revisions

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| number = ML17340A967
| number = ML17340A967
| issue date = 12/06/2017
| issue date = 12/06/2017
| title = 2017/12/06 NRR E-mail Capture - Acceptance Review: Beaver Valley Power Station Unit No. 2 - Proposed Alternative to ASME Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements (2-TYP-4-RV-02)(EPID: L-2017-LLR-0138)
| title = NRR E-mail Capture - Acceptance Review: Beaver Valley Power Station Unit No. 2 - Proposed Alternative to ASME Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements (2-TYP-4-RV-02)
| author name = Venkataraman B
| author name = Venkataraman B
| author affiliation = NRC/NRR/DORL/LPLI
| author affiliation = NRC/NRR/DORL/LPLI
| addressee name = Lashley P H
| addressee name = Lashley P
| addressee affiliation = FirstEnergy Nuclear Operating Co
| addressee affiliation = FirstEnergy Nuclear Operating Co
| docket = 05000412
| docket = 05000412
Line 14: Line 14:
| page count = 3
| page count = 3
| project = EPID:L-2017-LLR-0138
| project = EPID:L-2017-LLR-0138
| stage = Other
| stage = Acceptance Review
}}
}}


=Text=
=Text=
{{#Wiki_filter:1NRR-DMPSPEm ResourceFrom:Venkataraman, BoomaSent:Wednesday, December 06, 2017 12:18 PMTo:Lashley, Phil H.Cc:Danna, James
{{#Wiki_filter:NRR-DMPSPEm Resource From:                             Venkataraman, Booma Sent:                             Wednesday, December 06, 2017 12:18 PM To:                               Lashley, Phil H.
Cc:                               Danna, James


==Subject:==
==Subject:==
ACCEPTANCE REVIEW: Beaver Valley Power Station Unit No. 2- Proposed Alternative to ASME Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements (2-TYP RV-02)(EPID: L-2017-LLR-0138)Expires:Saturday, February 03, 2018 12:00 AMMr. Lashley, By letter dated November 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17318A030), FirstEnergy Nuclear Operating Company (FENOC, the licensee), submitted a proposed alternative request, 2-TYP RV-02, for Beaver Valley Power Station (Beaver Valley), Unit No. 2, in accordance with the provisions of 10 CFR 50.55a(z)(2). The licensee requested relief from the examination requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-729-4, "Alternative Examination Requirements for PWR [pressurized water reactor] Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds, Section XI, Division 1," for certain reactor vessel head penetration nozzles at Beaver Valley, Unit No. 2. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of the above 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. The NRC staff has reviewed your submittal 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 relief 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. Based on the information provided in your submittal, the NRC staff has estimated that the relief request will take approximately 120 hours to complete. The NRC staff expects to complete the review of the licensing action by September 28, 2018, as requested in your November 13, 2017, letter. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, 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 NRC staff's initial review of the application and they could change, due to several factors including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.  
ACCEPTANCE REVIEW: Beaver Valley Power Station Unit No. 2- Proposed Alternative to ASME Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements (2-TYP-4-RV-02)(EPID: L-2017-LLR-0138)
Expires:                         Saturday, February 03, 2018 12:00 AM Mr. Lashley, By letter dated November 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17318A030), FirstEnergy Nuclear Operating Company (FENOC, the licensee), submitted a proposed alternative request, 2-TYP-4-RV-02, for Beaver Valley Power Station (Beaver Valley), Unit No. 2, in accordance with the provisions of 10 CFR 50.55a(z)(2). The licensee requested relief from the examination requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-729-4, Alternative Examination Requirements for PWR [pressurized water reactor]
Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds, Section XI, Division 1, for certain reactor vessel head penetration nozzles at Beaver Valley, Unit No. 2.
The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of the above 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.
The NRC staff has reviewed your submittal 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 relief 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.
Based on the information provided in your submittal, the NRC staff has estimated that the relief request will take approximately [[estimated NRC review hours::120 hours]] to complete. The NRC staff expects to complete the review of the licensing action by September 28, 2018, as requested in your November 13, 2017, letter. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, 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 NRC staffs initial review of the application and they could change, due to several factors including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.
1


2If you have any questions, please contact me at (301) 415-2934. Sincerely, Booma Booma Venkataraman, P.E. Project Manager, NRR/DORL/LPL1 Office of Nuclear Reactor Regulation Booma.Venkataraman@nrc.gov 301.415.2934    
If you have any questions, please contact me at (301) 415-2934.
Sincerely, Booma Booma Venkataraman, P.E.
Project Manager, NRR/DORL/LPL1 Office of Nuclear Reactor Regulation Booma.Venkataraman@nrc.gov 301.415.2934 2


Hearing Identifier: NRR_DMPS Email Number: 29   Mail Envelope Properties   (Booma.Venkataraman@nrc.gov20171206121700)  
Hearing Identifier:     NRR_DMPS Email Number:           29 Mail Envelope Properties     (Booma.Venkataraman@nrc.gov20171206121700)


==Subject:==
==Subject:==
ACCEPTANCE REVIEW: Beaver Valley Power Station Unit No. 2- Proposed Alternative to ASME Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements (2-TYP RV-02)(EPID: L-2017-LLR-0138)
ACCEPTANCE REVIEW: Beaver Valley Power Station Unit No. 2- Proposed Alternative to ASME Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements (2-TYP-4-RV-02)(EPID: L-2017-LLR-0138)
Sent Date:   12/6/2017 12:17:55 PM Received Date: 12/6/2017 12:17:00 PM From:   Venkataraman, Booma Created By:   Booma.Venkataraman@nrc.gov Recipients:     "Danna, James" <James.Danna@nrc.gov> Tracking Status: None "Lashley, Phil H." <phlashley@firstenergycorp.com> Tracking Status: None  
Sent Date:               12/6/2017 12:17:55 PM Received Date:           12/6/2017 12:17:00 PM From:                   Venkataraman, Booma Created By:             Booma.Venkataraman@nrc.gov Recipients:
 
"Danna, James" <James.Danna@nrc.gov>
Post Office:     Files     Size     Date & Time MESSAGE   3532     12/6/2017 12:17:00 PM   Options Priority:     Standard   Return Notification:   No   Reply Requested:   No   Sensitivity:     Normal Expiration Date:   2/3/2018 Recipients Received:      
Tracking Status: None "Lashley, Phil H." <phlashley@firstenergycorp.com>
}}
Tracking Status: None Post Office:
Files                           Size                   Date & Time MESSAGE                         3532                   12/6/2017 12:17:00 PM Options Priority:                       Standard Return Notification:           No Reply Requested:               No Sensitivity:                   Normal Expiration Date:               2/3/2018 Recipients Received:}}

Latest revision as of 13:26, 8 March 2020

NRR E-mail Capture - Acceptance Review: Beaver Valley Power Station Unit No. 2 - Proposed Alternative to ASME Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements (2-TYP-4-RV-02)
ML17340A967
Person / Time
Site: Beaver Valley
Issue date: 12/06/2017
From: Booma Venkataraman
Plant Licensing Branch 1
To: Lashley P
FirstEnergy Nuclear Operating Co
References
L-2017-LLR-0138
Download: ML17340A967 (3)
v • d • e


Text

NRR-DMPSPEm Resource From: Venkataraman, Booma Sent: Wednesday, December 06, 2017 12:18 PM To: Lashley, Phil H.

Cc: Danna, James

Subject:

ACCEPTANCE REVIEW: Beaver Valley Power Station Unit No. 2- Proposed Alternative to ASME Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements (2-TYP-4-RV-02)(EPID: L-2017-LLR-0138)

Expires: Saturday, February 03, 2018 12:00 AM Mr. Lashley, By letter dated November 13, 2017 (Agencywide Documents Access and Management System Accession No. ML17318A030), FirstEnergy Nuclear Operating Company (FENOC, the licensee), submitted a proposed alternative request, 2-TYP-4-RV-02, for Beaver Valley Power Station (Beaver Valley), Unit No. 2, in accordance with the provisions of 10 CFR 50.55a(z)(2). The licensee requested relief from the examination requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-729-4, Alternative Examination Requirements for PWR [pressurized water reactor]

Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds,Section XI, Division 1, for certain reactor vessel head penetration nozzles at Beaver Valley, Unit No. 2.

The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of the above 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.

The NRC staff has reviewed your submittal 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 relief 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.

Based on the information provided in your submittal, the NRC staff has estimated that the relief request will take approximately 120 hours5 days <br />0.714 weeks <br />0.164 months <br /> to complete. The NRC staff expects to complete the review of the licensing action by September 28, 2018, as requested in your November 13, 2017, letter. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, 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 NRC staffs initial review of the application and they could change, due to several factors including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.

1

If you have any questions, please contact me at (301) 415-2934.

Sincerely, Booma Booma Venkataraman, P.E.

Project Manager, NRR/DORL/LPL1 Office of Nuclear Reactor Regulation Booma.Venkataraman@nrc.gov 301.415.2934 2

Hearing Identifier: NRR_DMPS Email Number: 29 Mail Envelope Properties (Booma.Venkataraman@nrc.gov20171206121700)

Subject:

ACCEPTANCE REVIEW: Beaver Valley Power Station Unit No. 2- Proposed Alternative to ASME Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements (2-TYP-4-RV-02)(EPID: L-2017-LLR-0138)

Sent Date: 12/6/2017 12:17:55 PM Received Date: 12/6/2017 12:17:00 PM From: Venkataraman, Booma Created By: Booma.Venkataraman@nrc.gov Recipients:

"Danna, James" <James.Danna@nrc.gov>

Tracking Status: None "Lashley, Phil H." <phlashley@firstenergycorp.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 3532 12/6/2017 12:17:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: 2/3/2018 Recipients Received:

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