ML15301A255

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Pilgrim - Response to Request for Additional Information Regarding Relief Request PRR-50, Implementation of Code Case N-702
ML15301A255
Person / Time
Site: Pilgrim
Issue date: 10/21/2015
From: Perkins E P
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15301A247 List:
References
TAC MF6362
Download: ML15301A255 (4)


Text

S'En tergyEntergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station600 Rocky Hill RoadPlymouth, MA 02360October 21, 2015U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001

SUBJECT:

Response to Request for Additional Information Regarding ReliefRequest PRR-50, Implementation of Code Case N-702 (TAC No.MF6362)Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power StationDocket No. 50-293License No. DPR-35

REFERENCE:

NRC Email to Entergy, "Request for Information Regarding Pilgrim ReliefRequest (PRR)-50, Implementation of Code Case N-702 (TAC No.MF6362), dated September 23, 2015LETTER NUMBER: 2.15.073

Dear Sir or Madam:

Pursuant to the request by the U.S. Nuclear Regulatory Commission staff for additionalinformation contained in the Reference, please find attached the Pilgrim Nuclear Power Stationresponse.Please contact me at (508) 830-8323 or Murray Williams at (508) 830-8275 if you have anyquestions.Sincerely,EveretP (Cip M a nag er," Regul atonryssurancEPP/mewAttachments:1. Response to Request for Additional Information Regarding Relief RequestPRR-50, Implementation of Code Case N-702 (TAC No. MF6362)2. Entergy Calculation M1 396, Structural Integrity Associates, "Evaluation ofProbability of Failure for Recirculation Inlet (N2) in the Nozzle-to-ShellWelds and Nozzle Blend Radii Regions at Pilgrim Nuclear Station,"1400071.301, Revision 0, February 2014,%

Letter Number: 2.15.073Page 2 of 2cc: Mr. Daniel DormanRegional Administrator, Region IU.S. Nuclear Regulatory Commission2100 Renaissance Boulevard, Suite 100King of Prussia, PA 19406-1415Ms. Booma Venkataraman, Project ManagerOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionMS O-8C2AWashington, DC 20555NRC Senior Resident InspectorPilgrim Nuclear Power Station To PNPS Letter 2.15.073Response to Request for Additional Information Regarding Relief Request PRR-50,Implementation of Code Case N-702 (TAC No. MF6362)(1 Page)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATIONREGARDING RELIEF REQUEST NO. PRR-50,IMPLEMENTATION OF CODE CASE N-702(TAC NO. MF6362)NRC Request 1By letter dated June 4, 2015 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML1 51 66A037), Entergy Nuclear Operations, Inc. (the licensee)submitted pursuant to Title 10 Code of Federal Regulations (10 CFR) 50.55(z)(1 ) a request foran 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 PowerPlant Components," on the basis that the proposed alternatives provide an acceptable level ofquality and safety for the Pilgrim Nuclear Power Station (PNPS). Pursuant to 10 CFR50.55a(z)(1 ), the licensee requested approval to implement the alternative of Code Case N-702in lieu of the code required 100% examination of all nozzles identified in the request.1. Attachment 1 to the licensee's letter, Section 4, Page 4, "Proposed Alternative and Basis forUse", states in relevant part:Therefore, a plant specific probabilistic fracture mechanics evaluation was performed tosupplement the criteria of Code Case N-702 and BWRVIP-241 in order to demonstratethat the probability of failure remains acceptable over this period of extended operation(to 60 years). This analysis was performed using the same methods as were used inBWRVIP-241, with PNPS specific fracture mechanics analyses*. The resultsdemonstrate that for the N2 nozzles at PNPS, the probability of failure was less than theNRC safety goal of 5.0 x 1 0- per year. Therefore, the probabilistic fracture mechanicscriteria of BWRVIP-241 remain applicable to the PNPS N2 nozzles.*The PNPS specific reference document for this statement is cited as Structural IntegrityAssociates, "Evaluation of Probability of Failure for Recirculation Inlet (N2) in the Nozzle-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 thereference document in order for NRC to review the probabilistic fracture mechanics analysis ofthe N2 nozzles at PNPS under this relief request, PRR-50.ResponseThe requested document is provided in Attachment 2 to this letter.Attachment 1 -Page 1 of 1