ML12339A267: Difference between revisions

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| number = ML12339A267
| number = ML12339A267
| issue date = 12/04/2012
| issue date = 12/04/2012
| title = South Texas Project, Unit 2 - 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 (TAC No. M
| title = South Texas Project, Unit 2 - 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
| author name = Singal B K
| author name = Singal B K
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV

Revision as of 08:42, 8 February 2019

South Texas Project, Unit 2 - 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: Singal B K
Plant Licensing Branch IV
To: Paul J
South Texas
Singal B K
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 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.

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.

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 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.

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