ML090930509

From kanterella
Jump to navigation Jump to search

Acceptance Review Email, Application for Relief Request No. ANO2-PT-001
ML090930509
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 09/05/2008
From: Wang A
Plant Licensing Branch IV
To: David Bice, James D
Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC MD9537
Download: ML090930509 (1)


Text

From: Alan Wang [1]

Sent: Friday, September 05, 2008 7:11 AM To: BICE, DAVID B; JAMES, DALE E

Subject:

Acceptance Review of Relief Request ANO2-PT-001, TAC# MD9537 Dale and Dave, I was not sure who you would like me to send our acceptance reviews so please let me know.

By letter dated July 31, 2008, Entergy Operations, Inc. (Entergy), proposed an alternative to the requirements of ASME Section XI IWB-5222(b) for Arkansas Nuclear One, Unit 2 (ANO-2). The alternative proposed to visually examine the extended reactor coolant pressure boundary (RCPB) piping between the first and second normally closed isolation valves during the Class 2 system leakage test conducted each inspection interval. The proposed alternative provides adequate assurance of the pipes leak tightness. 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 amendment 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) 415-1445.

Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation