ML20148T126

Forwards IE Bulletin 78-12A,suppl to IE Bulletin 78-12. W/Encl ANO:7811300055

ML20148T126
Person / Time
Site:	Grand Gulf
Issue date:	11/24/1978
From:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Stampley N MISSISSIPPI POWER & LIGHT CO.
References
NUDOCS 7812040312
Download: ML20148T126 (1)

Text

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[p*AlCo 'o, UNITED ST ATES NUCLE AR REGULATORY COMMISSION d' [

, , . 7 REGION 11 7

• ,- g 101 M ARIETT A ST RE ET. N.W.

1. ATL ANT A, GE ORGI A 30303

%, ,6 In Reply Refer To:

RII:JP0 50-416, 50-417

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Mississippi Power and Light Company Attn: Mr. Norris L. Stampley Vice President of Production P. O. Box 1640 Jackson, Mississippi 39205 Gentlemen:

Enclosed is a supplement (IE Bulletin No.78-12A) to IE Bulletin No. 78-12 which requires action by you with regard to your power reactor facility (ies) with an operating license or a construction permit.

Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.

Sincerely, y .C

• ames P. O'Reilly D rector

Enclosures:

1. IE Bulletin 78-12A

2. List of IE Bulletins Issued in 1978 cc w/ enc 1:

W. L. Nail, Plant Superintendent P. O. Box 756 Port Gibson, !!ississippi 39150 7 812010 Uk {

a UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEVENT WASHINGTON, D.C. 20555 November 2h, 1978 IE Bulletin No.78-12A ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:

This Bulletin is a supplement to IE Bulletin 78-12, issued on September 29, 1978, and the two documents should be considel-ed together.

Bulletin 78-12 described the use of weld vire that failed to meet all specified chemical properties in velds of twelve identified reactor pressure vessels. Use of the atypical veld material in vessel veldments causes them to have higher than normal nil-ductility transition temperature characteristics which in turn requires more conservative pressure / tempera-ture operating limits .

Bulletin 78-12 was issued for the purpose of verifying that similar atypical veld material was not also supplied to other vessel manufacturers and used in reactor pressure vessel fabricatien. Recognizing that the scope of the record review required is extensive and time consuming, and to assure that responses provided are meaningful, the requirements of Bulletin 78-12 are being modified.

Action To Be Taken By Licensees and Permit Holders:

For all power reactor facilities with an operating license or a construction permit, except those already identified as possibly having 4 typical veld materia 11:

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1 The twelve nuclear units identified as having pcssible atypical pressure vessel veldments are: Three Mile Island Unit Nos. 1 and 2, Crystal Rive r Unit No. 3, Arkansas Nuclear One Unit No. 1, Ocenee Unit No. 3, Rancho Seco Unit No.1, Midland Unit No.1, Quad Cities Unit No. 2, Browns Ferry Unit No. 1, Turkey Point Unit No. L and Zion Unit Nos. I and 2.

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IE Bulletin No.78-12A November 2L, 1978 l

1. Provide all information available on veld materials used for each reactor vessel primary boundary ferritic weldment.2 (Items 1c, Id, 2a, 2b, first sentence of 2e, 3 and b of Bulletin 78-12. ) This information may be provided to URC through the vessel manufacturers or suppliers as appropriate to prevent duplication of data.

2. Correlation of specific heat, lot or batch to specific weldments in specific vessels is not required at this time. (Last sentence of Item 2c,Bulletin 78-12.) However, each licensee is required to verify that the veld materials information provided to the "PC under Item 2 does in fact cover each reactor vessel for which the licensee is responsible.

3. Responses to item I above shall be submitted in writing within 120 days of the date of this Bulletin supplement. Reports should be submitted to the Director of the appropriate URC Regional Office and a copy should be forwarded to the U.S. Nuclear Regulatory Commission, Office of Inspection tnd Enforcement, Division of Reactor Construction Inspection, Washington, D.C. 20555.

Approved by GAO, B180225 (R0072); clearance expires 7/31/80. Approval vac given under a blanket clearance specifically for identified generic problems.

2 Weld material information submitted vill be evaluated by URC. Requests for further information vill be dependent upon results of these evalua-tions. Additional requests or instructions vill be issued following these evaluations.

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IE Bulletin No.78-12A Date : November 2L, 1978 l

LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.

78-01 Flammable Contact - 1/16/78 All Power Reactor Arm Retainers in G.E. Facilities with an CR120A Relays OL or CP 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with an OL or CP 78-03 Potential Explosive 2/8/78 All BWR Power Gas Mixture Accumula- Reactor Facilities tions Associated with with an OL or CP BWR Offgas System Operations 78-Oh Environmental Quali- 2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit OL or CP Switches Inside Reactor Containment 78-05 Malfunctioning of h/1L/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mech anism-General Model CR105X 78-06 Defective Outler- 5/ 31/7 8 All Power Beactor Hammer, Type M Relays Facilities with an With DC Ceils OL or CP 78-07 Protection afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Prierity 1 Material Licensees Enclosure 1 Page 1 of 2

A IE Bulletin Ilo. 78 12A Date: November 2h, 1978 LISTING OF IE BULLETIIIS ISSUED In 1978 Bulletin Subject Date Issued Issued To No.

78-08 Rediation Levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor Tubes Facilities with a Fuel Element transfer tube and an OL.

78-09 BWB Dryvell Leakage 6/2L/78 All BW Power Paths Associated with Reactor Facilities Inadequate Dryvell with an OL or CP Closures 78-10 Bergen-Paterson 6/27/78 All BW Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an OL or CP Spring Colls 78-21 Examination of Mark I 7/21/78 BWE Power Reactor Containment Torus Facilities for Welds action: Peach Botto 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee 7-22 Atypical Weld Material 9/29/78 All Pcver Reactor in Reactor Pressure Facilities with an yessel Welds CL or CP 8-13 Failures in Source Heads 10/27/78 All General and of Key-Ray , Inc . , Gauges Specific Licensees Mcdels 7050, 7050B, 7051 vith Kay-Ray Gauges 7051B, 7060, 7060B, 7061 and 7061B Enclosure 1 Page 2 of 2