IR 05000311/1980006

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IE Insp Rept 50-311/80-06 on 800327-28.No Noncompliance Noted.Major Areas Inspected:Ultrasonic Exam of Reactor Pressure Vessel Nozzles,Including Observations & Discussions W/Licensee
ML18082A512
Person / Time
Site: Salem 
Issue date: 04/16/1980
From: Mcbrearty R, Lester Tripp
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18082A511 List:
References
50-311-80-06, 50-311-80-6, NUDOCS 8006030090
Download: ML18082A512 (3)


Text

U.S. NUCLEAR REGULATORY COMMISSION OFFICE.OF INSPECTION AND ENFORCEMENT Report: N /80:..06 Docket No. 50-31 T


Region I License. No... CPPR-53 Priority ------

Category ___ B

.... l._ __ _

Licensee:

Public**serV'ice Electric and Gas Compan Park Place Newark, New Jersey 07101 Facility Name:

Salem Nuclear Generating Station, Unit No. 2 Inspect.ion at:

Hancacks Bri.dge, New Jersey Insp~ction conducted:

Inspectors: ~~~~~~.e:..=-~~~~"YI----

Approved Inspection Summary:

Chief, Engineering Support 1, RC&ES Branch Inspection on March 27-28, 1980 (Report No. 50-311/80-06)

~~)f,/9~

dafe signed date signed

.

date. signed fj/d~~ned Areas *inspected:

Routine, unannounced inspection of the ultrasonic examination of reactor pressure vessel nozzles. This included observations and discussions with licensee and licensee contractor personne The inspection. involved 14 inspector hours onsite by one regional based NRC inspecto Results; No items of noncompliance were identifie * Region I Form 12 (Rev. April 77)

8006030090

.1

  • DETAILS Persons Contacted Public Service Electric and Gas Company
    • R. Brandt, Senior Engineer
  • R *. Griffith Sr., Project QAE (Acting)

A. Meyer, Site QA Engineer Westinghouse Electric Corporation

  • R. Powell, Site Manager
  • R; Rishel~ Associate Engineer
  • Elenotes those present at the exit intervie **Telephone contact onl.

Ultrasonic Examination of Reactor Pressure Vessel Nozzles As a result of sub-cladding cracks. found* in nozzles of reactor pressure vess.el s fabricated in Europe, and installed by the Westinghouse Electric* Corporation in the United State.s, the NRC requested an inspection of the:.Salem,. Unit 2 reactor vessel nozzle The examination, utilizing ultrasonic techniques,. was. requested to ascertain whether a condition similar to that found in the European vessels ex.ists in the domestically fabricated vessel at Sale The Westinghouse Electric Corporat.ion was contracted by the licensee to perform the requested examinatio *The inspector observed the ultransonic examination of portions of the following reactor vessel nozzles:

Loop 3 hot leg; Loop 3 cold leg; Loop 4hot leg; Loop 4 cold leg; The examination was done in accordance with Westinghouse procedure number MTA-MNA-851 entitled 11Ultrasoni c Test Procedure for Detection of Sub-Cladding Cracks in Reactor Vessel Nozzle Bore *

Test system sensitivity was established from 2 mm (5/64

) diameter flat bottomed hole The 70° refracted longitudinal angle beam examinati.on was calibrated using a hole_ drilled so that the flat bottom reflecting surface was* oriented perpendicular to the direction of the clad bead to simulate the anticipated orientation of possible defect Side drilled holes __ were used to calibrate the instrument sweep so that each screen division represented an increment of 2m This permitted the operators to read flaw depth directly from the cathode ray tube scree The angle beam examination was perfonned from the nozzle bore surface in two opposing circumferential direction The scan was done using a )50 mm diameter twin element, 2. 0 MH2 transducer with an l8mm f oca 1 distanc All recordable indications were investigated with a 2.0 MHz, 1/4

diameter-dual element, straight beam transducer in accordance with procedural* requirement The straight.beam examination _was calibrated using* a 2mm diameter flat bottomed hole drilled so that the flat reflecting surface was or.tented para lle 1 to the clad surface. of the calibration bloc All nozzle examinations were completed while the inspector* was at the site. -The. raw data were to be evaluated. at the Westinghouse faci 1 i ty in Pittsburgh,_ Pa.. and a report will be submitted_ to the Ti.censee when the data are evaluate The inspector found that procedura 1 requirements with respect to scanning and recording of indications were me No items of noncompliance were identifie.

Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1) on-March 28, 1980, at the conclusion of the inspectio The inspector summarized the purpose and scope of the inspection and the findings.