ML12122A260

Relief Request - Proposed Alternative - Use of Alternate ASME Code Case N-770-1 Baseline Examination - ME8492

ML12122A260
Person / Time
Site:	Palisades
Issue date:	04/30/2012
From:	Mahesh Chawla Plant Licensing Branch III
To:	Erickson J, Gustafson O Entergy Nuclear Operations
Chawla M
References
TAC ME8492, N-770-1
Download: ML12122A260 (1)

Text

From: Chawla, Mahesh Sent: Monday, April 30, 2012 4:15 PM To: ERICKSON, JEFFREY S; GUSTAFSON, OTTO W Cc: Collins, Jay; Wallace, Jay; Audrain, Margaret; Jones, Donald; Hills, David; Giessner, John; Lerch, Robert; Taylor, Thomas; Scarbeary, April; Cumblidge, Stephen; Frankl, Istvan; Hardies, Robert

Subject:

Palisades - Relief Request - Proposed Alternative - Use of Alternate ASME Code Case N-770-1 Baseline Examination - ME8492 Jeff, This is the second set of RAIs with reference to the subject verbal relief request. Please provide this information in a timely manner keeping in mind the final goal of issuance on May 2, 2012. Also, please set up the teleconference for Wednesday 5/2/12 from 3.30 pm to 4.30 pm EDT and invite the folks on cc. Thanks OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION USE OF ALTERNATE ASME CODE CASE N-770-1 BASELINE EXAMINATION ENTERGY NUCLEAR OPERATIONS, INC.

PALISADES NUCLEAR PLANT DOCKET NO. 50-225 By letter dated April 26, 2012, Agencywide Documents Access and Management System (ADAMS) Accession Number ML121118A144, Entergy Nuclear Operations, Inc., (the licensee) submitted the proposed alternative Use of Alternate ASME Code Case N-770-1 Baseline Examination for U.S. Nuclear Regulatory Commission review and acceptance. The request proposed an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Case N-770-1, as required and conditioned by Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50) paragraph 55a(g)(6)(ii)(F)(3). Specifically, the licensee states that obtaining the required examination coverage of essentially 100 percent is unattainable due to limitations imposed by design and geometry, and requests relief from the required baseline examination coverage on the basis that compliance with the requirements would be a hardship without a compensating increase in the level of quality or safety, per 10 CFR 50.55a(a)(3)(ii). In order to complete our review, the Piping and NDE Branch requests additional information.

1. In the event that an axial leak were to occur in the PORV 4 DM Weld, please provide a response to the following:

a. What would be the effect of an axial flaw through the susceptible material of the DM weld

b. Describe the licensees ability to detect leakage from an axial flaw in this location

c. What actions would be available to mitigate the effect of an axial flaw causing leakage at this location on the reactor coolant system

2. Provide the basis for hardship to perform an eddy current examination for the PORV 4 DM Weld.

3. Provide the basis for hardship for performing addition ID surface examination for each of the welds covered by this relief request.

4. Provide the location and size of any PWSCC flaws found in any DM pressurizer, hot leg and cold leg weld temperature locations that would be covered by ASME Code Case N-770-1.

file:///Cl/...20-%20Use%20of%20Alternate%20ASME%20Code%20Case%20N-770-1%20Baseline%20Examination%20-%20ME8492.htm[5/1/2012 11:26:08 AM]