ML20148T302
| ML20148T302 | |
| Person / Time | |
|---|---|
| Site: | Harris, Brunswick, Robinson  |
| Issue date: | 11/24/1978 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 7812040359 | |
| Download: ML20148T302 (1) | |
Text
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UNITED ST ATES
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NUCLEAR REGULATORY COMMISSION j
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44.....f NOV 2 41978 In Reply Refer To:
RII:JPO 50-325, 50-324 50-400, 50-401 50-402, 50-403 50-261 Carolina Power and Light Company ATTN:
Mr. J. A. Jones Executive Vice President Engineering, Construction and Operation 336 Fayetteville Street Raleigh, North Carolina 27602 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 constructien permit.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, f CT ames P. O'Reilly D ector m
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Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978 7812040357
Carolina Power and Light Company cc w/ enc 1:
A. C. Tollison, Jr.
Plant Manager Box 458 Southport, North Carolina 28461 R. Parsons, Proj ect Manager l
Shenron Harris Nuclear Power Plant P. O. Box 101 New Hill, North Carolina 27562 R. B. Starkey, Plant Manager P. O.
Box 790 Hartsville, South Carolina 29550
UNITED STATES NUCLEAR REGULATORY CO?dISSION OFFICE OF INSPECTION AND ENFORCE?C:T WASHINGTON, D.C.
20555 November 2L, 1978 IE Bulletin No.78-12A ATYPICAL WELD MATEEIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletin 78-12, issued on September 29, 2978, and the two documents should be considered together.
Bulletin 78-12 described the use of weld vire that failed to meet all i
l specified chemical properties in velds of twelve identified reactor pressure vessels. Use of the atypical veld material in vessel veldrents 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.
Actica 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 stypical veld material 1:
1 The twelve nuclear units identifled as having possible atyp? cal pressure vessel veldments are:
Three Mile Island Unit Nos. I and 2, Crystal River Unit No. 3, Arkansas Nuclear One. Unit No.
1, Oconee 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 Hos. l and 2.
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IE Bulletin No.78-12A November 2L, 1978 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 2c, 3 and h 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 78-22.) However, each licensee is required to verify that the veld materials information provided to the U?r under Item 2 does in fact cover each reactor vessel for which the licensee is responsible.
3.
Fesponses to item 1 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 NEC Regicnal Office and a ecpy should be forwarded to the U S. Nuclear Regulatory Ccamission, Office of Inspection and Enforcer t, Division of Reactor Construction Inspection, Washington; 20555 Approved by GAO, E180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
2 Weld material information submitted will be evaluated by NEC. Requests for further information vill be dependent upon results of these evalua-tions. Additional requests or instructions will be issued following these evaluations.
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IE Bulletin No.78-12A Date: November 2L, 1978 LISTING OF IE EULLETINS ISSUED IN 1978 Eulletin Subject Date Issued Issued To No.
78-01 Flammable Contact -
1/16/78 All Power Reactor Art Retainers in G.E.
Facilities with an CR120A Relays OL or CP 78-02 Terminal Block 1/30/78 All Power Reacter Qualification Facilities with an OL or CP l
78-03 Potential Explosive 2/8/78 All BWE Power Gas Mixture Accumula-Reactor Facilities tions Associated with with an OL er CP BWR Offgas System Operations 78-OL Environmental Quali-2/22/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit OL er CF Switches Inside Reactor Containment 73-05 Malfunctioning of L/1L/78 All Pever Reacter Circuit Breaker Facilities with an Auxiliary Contact OL er CP Mech anism-General Model CR105X 78-06 Defective Outler-5/11/78 All Power Reacter Hammer, Type M Relays Facilities with an With DC Coils OL or CP 7S-07 Protection afforded 6/12/78 All Power React or by Air-Line Respirators Facilities with an and Supplied-Air Roods OL, all class E and F Research Reacters with an OL, all Fuel Cycle Facilities with an OL, and all Prierity 1 Material Licensees Page I of 2
IE Bulletin Ho. 78 12A Date : November 2L, 1978 LISTING OF IE BULLETINS ISSUED IU 1978 Bulletin Subject Date Issued Issued To No.
78-08 Radiation Levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor Tubes Facilities with a Fuel Ele.ent transfer tube and an OL.
78-09 BWR Dryvell Leakage 6/1L/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drfvell with an OL or CP Closures 78-10 Bergen-Paterson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an OL or CP Spring Coils TM1 Examinatien of Mark I 7/21/78 BWR Power React er Containment Torus Facilities for Welds action:
Feach Botto: 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee 7.12 Atypical Weld Material 9/29/78 All Pcver Reacter in Reactor Pressure Facilities with an yessel Welds OL or CP 6-13 Failures in Source Heads 10/27/78 All General and of Kay-Ray, Inc., Gauges Specific Licensees Models 7050, 7050B, 7051 vitt. Key-Rey Gaures 7051B, 7060, 70603, 7061 and 7061B Page 2 of 2 l
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