ML15266A531

NRR E-mail Capture - Request for Information Regarding Pilgrim Relief Request (PRR)-50, Implementation of Code Case N-702

ML15266A531
Person / Time
Site:	Pilgrim
Issue date:	09/23/2015
From:	Booma Venkataraman Plant Licensing Branch 1
To:	Will M Entergy Nuclear Operations
References
TAC MF6362
Download: ML15266A531 (3)

Text

NRR-PMDAPEm Resource From: Venkataraman, Booma Sent: Wednesday, September 23, 2015 10:11 AM To: mwill13@entergy.com Cc: Guzman, Richard

Subject:

Request for information regarding Pilgrim Relief Request (PRR)-50, Implementation of Code Case N-702 (TAC NO. MF6362)

Attachments: Pilgrim PRR50 REQUEST FOR ADDITIONAL INFORMATION (TAC MF 6362).docx Expires: Sunday, November 22, 2015 12:00 AM

Murray, By letter dated June 4, 2015 (Agency wide Documents Access and Management System (ADAMS) Accession No. ML15166A037), Entergy Nuclear Operations, Inc. (the licensee) submitted pursuant to Title 10 Code of Federal Regulations (10 CFR) 50.55(z)(1) a request for an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," on the basis that the proposed alternatives provide an acceptable level of quality and safety for the Pilgrim Nuclear Power Station (PNPS). Pursuant to 10 CFR 50.55a(z)(1), the licensee requested approval to implement the alternative of Code Case N-702 in lieu of the code required 100% examination of all nozzles identified in the request.

A draft request for information (RAI) was sent to you on September 22, 2015. Further to the conversation with you on September 23, 2015, no clarification call was held as it was agreed to be not required. It was agreed that PNPS will respond to the RAI with a supplement by October 22, 2015. Please treat this e-mail as transmittal of formal RAIs. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2934 or via email at Booma.Venkataraman@nrc.gov.

Thanks, Booma Booma Venkataraman, P.E.

Project Manager, NRR/DORL/LPL1-1 Office of Nuclear Reactor Regulation Booma.Venkataraman@nrc.gov 301.415.2934 1

Hearing Identifier: NRR_PMDA Email Number: 2405 Mail Envelope Properties (Booma.Venkataraman@nrc.gov20150923101100)

Subject:

Request for information regarding Pilgrim Relief Request (PRR)-50, Implementation of Code Case N-702 (TAC NO. MF6362)

Sent Date: 9/23/2015 10:11:22 AM Received Date: 9/23/2015 10:11:00 AM From: Venkataraman, Booma Created By: Booma.Venkataraman@nrc.gov Recipients:

"Guzman, Richard" <Richard.Guzman@nrc.gov>

Tracking Status: None "mwill13@entergy.com" <mwill13@entergy.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1521 9/23/2015 10:11:00 AM Pilgrim PRR50 REQUEST FOR ADDITIONAL INFORMATION (TAC MF 6362).docx 23074 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: 11/22/2015 Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. PRR-50 FOR THE FIFTH10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 (TAC NO. MF6362)

By letter dated June 4, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15166A037), Entergy Nuclear Operations, Inc. (the licensee) submitted pursuant to Title 10 Code of Federal Regulations (10 CFR) 50.55(z)(1) a request for an alternative to specific portions of the American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," on the basis that the proposed alternatives provide an acceptable level of quality and safety for the Pilgrim Nuclear Power Station (PNPS). Pursuant to 10 CFR 50.55a(z)(1), the licensee requested approval to implement the alternative of Code Case N-702 in lieu of the code required 100% examination of all nozzles identified in the request.

1. Attachment 1 to the licensees letter, Section 4, Page 4, Proposed Alternative and Basis for Use, states in relevant part:

Therefore, a plantspecific probabilistic fracture mechanics evaluation was performed to supplement thecriteria of Code Case N-702 and BWRVIP-241 in order to demonstrate that the probability offailure remains acceptable over this period of extended operation (to 60 years). Thisanalysis was performed using the same methods as were used in BWRVIP-241, with PNPSspecific fracture mechanics analyses*. The results demonstrate that for the N2 nozzles atPNPS, the probability of failure was less than the NRC safety goal of 5.0 x 10-6 per year.Therefore, the probabilistic fracture mechanics criteria of BWRVIP-241 remain applicable tothe PNPS N2 nozzles.

• The PNPS specific reference document for this statement is cited as Structural Integrity Associates, "Evaluation of Probability of Failure for Recirculation Inlet (N2) in theNozzle-to-Shell Welds and Nozzle Blend Radii Regions at Pilgrim Nuclear Station", 1400071.301, Revision 0, February 2014.

The above reference document was not provided with the submittal. Please provide the reference document in order for NRC to review the probabilistic fracture mechanics analysis of the N2 nozzles at PNPS under this relief request, PRR-50.