ML18086B142

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Requests NRC Approval for Encl ASME Section Xi,Code Case N-307 as Applicable to Ultrasonic Exam of Reactor Vessel Studs.Approval Needed for Implementing in Performing Class I Bolting Exam During Jan 1982 Outage
ML18086B142
Person / Time
Site: Salem  PSEG icon.png
Issue date: 12/01/1981
From: Liden E
Public Service Enterprise Group
To: Varga S
Office of Nuclear Reactor Regulation
References
NUDOCS 8112210351
Download: ML18086B142 (4)


Text

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PS~G Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201 /430-7000 Mailing Address:

P.O. Box 570, Newark, New Jersey 07101 December 1, 1981 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention:

Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen:

REVISED CLASS I BOLTING EXAMINATION ASME SECTION XI, CODE CASE N-307 NOS. 1 AND 2 UNITS SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 AND 50-311 We are requesting NRC approval of the enclosed ASME Section XI, Code Case N-307, as applicable to ultrasonic examination of reactor vessel studs at our Salem Nuclear Generating Station.

In order to be consistent with ASME Section XI, a proposed code case was submitted to the American Society of Mechan-ical Engineers (ASME) on ultrasonic examination volume for Class I bolting (e.g., reactor vessel studs), Examination Category B-G-1 of ASME Section XI.

'The proposed Code Case N-307 was approved by ASME on January 15, 1981.

The latest NRC Regulatory Guide 1.147 outlines a list of acceptable code cases, on a generic basis, that were in effect as of March 18, 1980.

As a result, Code Case N-307 is not listed in the current revision of Regulatory Guide 1.147.

We request NRC approval of Code Case N-307 so that it may be implemented in performing Class I bolting examination of the reactor vessel studs during an upcoming January, 1982 outage of Salem Unit No. 1.

A copy of ASME Code Case N-307 is en-closed for your use *

. '-8IT22fo351 011201 '*

PDR ADOCK 05000272

  • I p PDR The Energy People 95-0942

Director of Nuclear Reactor Regulation

  • 12/1/81 Should you have any questions in this regard, do not hesitate to contact us.

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1 Manager - Nuclear Licensing RJT:li CC:

Mr. Leif Norrholm Senior Resident Inspector Mr. Gary C. Meyer Licensing Project Manager Mr. Guy A. Arlotto, Director Division of Engineering Technology EP1 1/2

I 4 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Meetill(I of October 31, 1980 Approved by Council, January lS, 1981 Thu Que 1hall espire on January 1 S, 1984 urale11 previowly annulled or reaffirmed.

CaeN-307 Revised Ultnsonlc Examination Volume for ca.. 1 Bolt*

Ing, EJ?amination Category B-G*1,Section XI, Division 1, When th* Examinltion1 Are Conducted from th* Center*

Drilled Hole Inquiry: When ultrasonic examinations are conducted from the center-drilled hole of Class l bolts or studs to satisfy* the examination requirements of Examination Category B-G-1, may the examination volume be limited to the cylindrical region defined by A-B-C*D-E-F -A in the attached sketch?

(See nest page for 11cetch)

Reply: It is the opinion of the Committee that, when conducting ultrasonic examinations from the center-drilled hole of Class l bolts or studs to satisfy the exami*

nation requirements of Examination Category B-G-1, the examination volume m~y be limited to the cylindrical region defined by A-B-C..O*E-F -A in the sketch referenced by the Inquiry.

679 CASI N-307 SUPP.4-NC

CASI ( contlnuecl)

N-307 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Edge of nut In bolted position UnthreadlJd part of bolt or stud (where present)

REVISED EXAMINATION VOLUME FOR CLASS 1 BOLTING* WHEN SCAN-NED FROM THE CENTER-DRILLED HOLE 680 SUPP.4-NC