ML12339A267: Difference between revisions

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{{#Wiki_filter:From:Singal, Balwant To:"Paul, Jamie" Cc:Chappell, Coley
{{#Wiki_filter:From:           Singal, Balwant To:             "Paul, Jamie" Cc:             Chappell, Coley


==Subject:==
==Subject:==
Acceptance Review for Relief Request RR-ENG-3 TAC No. ME9806 Date:Tuesday, December 04, 2012 1:54:00 PMBy letter dated October 16, 2012, as supplemented by letter dated November 14, 2012, STPNuclear Operating Company (licensee) submitted Relief Request No RR-ENG-3-09 for South TexasProject, Unit 2.
Acceptance Review for Relief Request RR-ENG-3 TAC No. ME9806 Date:           Tuesday, December 04, 2012 1:54:00 PM By letter dated October 16, 2012, as supplemented by letter dated November 14, 2012, STP Nuclear Operating Company (licensee) submitted Relief Request No RR-ENG-3-09 for South Texas Project, Unit 2. The licensee request relief from the requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, requirements for the Essential Cooling Water System. The purpose of this letter 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.
The licensee request relief from the requirements of American Society ofMechanical Engineers Boiler and Pressure Vessel Code, Section XI, requirements for the EssentialCooling Water System.
Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) 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 purpose of this letter is to provide the results of the U.S. NuclearRegulatory Commission (NRC) staffs acceptance review of this relief request.
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 relief in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
The acceptancereview 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 alsointended 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(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would providean acceptable level of quality and safety, or that compliance with the specified requirements ofSection 50.55a would result in hardship or unusual difficulty without a compensating increase inthe level of quality or safety.
 
The NRC staff has reviewed your application and concluded that it does provide technicalinformation 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 in terms ofregulatory requirements and the protection of public health and safety and the environment.
Ifadditional information is needed for the staff to complete its technical review, you will be advisedby separate correspondence.
If you have any questions, please contact me at (301) 415-3016.
If you have any questions, please contact me at (301) 415-3016.
 
Balwant K. Singal Senior Project Manager (Comanche Peak and STP)
Balwant K. SingalSenior Project Manager (Comanche Peak and STP)Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.govTel: (301) 415-3016Fax: (301) 415-1222}}
Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222}}

Latest revision as of 18:44, 11 November 2019

Acceptance Review Email, Relief Request RR-ENG-3-09, Request for Relief from ASME Code Requirements; Deferral of Code Repair of Essential Cooling Water System Piping Until April 2013 Refueling Outage
ML12339A267
Person / Time
Site: South Texas STP Nuclear Operating Company icon.png
Issue date: 12/04/2012
From: Balwant Singal
Plant Licensing Branch IV
To: Paul J
South Texas
Singal B
References
TAC ME9806
Download: ML12339A267 (1)


Text

From: Singal, Balwant To: "Paul, Jamie" Cc: Chappell, Coley

Subject:

Acceptance Review for Relief Request RR-ENG-3 TAC No. ME9806 Date: Tuesday, December 04, 2012 1:54:00 PM By letter dated October 16, 2012, as supplemented by letter dated November 14, 2012, STP Nuclear Operating Company (licensee) submitted Relief Request No RR-ENG-3-09 for South Texas Project, Unit 2. The licensee request relief from the requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, requirements for the Essential Cooling Water System. The purpose of this letter 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(a)(3)(i) and 50.55a(a)(3)(ii) 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 staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed relief in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-3016.

Balwant K. Singal Senior Project Manager (Comanche Peak and STP)

Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222