ML19224A304
| ML19224A304 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/24/1978 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Herbein J METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7812150144 | |
| Download: ML19224A304 (1) | |
Text
J: s UNITED STATES
- g m*"IGuq'C, HUCLEAR REGULATORY COMMISslON
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REGION I 631 PARK AVENUE
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Docket Nos. 50-289 50-320 2 4 NOV By Metropolitan Edison Company ATTN: Mr. J. G. Herbein Vice President - Generation P. O. Box 542 Reading, Pennsylvania 19603
- 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 f acility(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,
??? ' N.
z~-
Boyce H. Grier
- " Director
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978 cc w/encls:
T. Broughton, Safety and Licensing Manager J. J. Barton, Project Manager R. C. Arnold, Vice President - Generation L. L. Lawyer, Manager - Generation Operations - Nuclear G. P. Miller, Superintendent J. P. O'Hanlon, Unit 1 Superintendent J. L. Seelinger, Unit 2 Superintendent - Technical Support I. R. Finfrock, Jr.
M". R. Conrad G. F. Trowbridge, Esquire gg Miss Mary V. Southard, Chairman, Citizens for a Safe Environment 781215oi4<]
a.075
UNITED STATES NUCLEAR REGULATORY COMMISSION UrFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No.78-12A Date:
November 24, 1978 Page 1 of 2 ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELOS Description of Circumstances:
This Bulletin is a supplement to IE Bulletin 78-12, issued on September 29, 1978, and the two documents should be considered together.
Bulletin 78-12 described the use of weld wire that failed to meet all specified chemical properties in welds of twelve identified reactor pressure vessels.
Use of the atypical weld material in vessel weldments causes them to have higher than normal nil-ductility transition tempera-ture characteristics which in turn requires more conservative pressure /
temperature operating limits.
Bulletin 78-12 was issued for the purcose of verifying that similar atypical weld material was not also supplied to other vessel manufacturers and used in reactor pressure vessel fabrication.
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 atypical weld materiall :
1.
Provide all information available on weld materials used for each reactor vessel primary boundary ferritic weldment.2 (Items ic, ld, 2a, 2b, first sentence of 2c, 3 and 4 of Bulletin 78-12.)
This in-formation may be provided to NRC through the vessel manufacturers or suppliers as appropriate to prevent duplication of data.
1 The twelve nuclear units identified as having possible atypical pressure vessel weldments are:
Three Mile Island Unit Nos.1 and 2, Crystal River Unit No. 3, Arkansas Nuclear One Unit No.1, Oconee Unit No. 3, Rancho Seco Unit Nc.1, Midland Unit No.1, Quad Cities Unit No. 2, Browns Ferry Unit No.1, Turkey Point Unit No. 4 and
- 7. ion Unit Nos.1 and 2.
2 Weld material information submitted will be evaluated by NRC.
Requests for further information will be dependcat upon results of these evalua-tions.
Additional requests or instructions will be issued following these evaluations.
3.076
flovember 24, 1978 Page 2 of 2 2,
Correlation of specific heat, lot or batch to spec.ific 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 weld materials information provided to the NRC under Item 1 does in fact cover each reactor vessel for which the licensee is responsible.
3.
Responses 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 f4RC Regional Office and a copy should be fonvarded to the U.S. fiuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Reactor Construction Inspection, Washington, D.C.
20555.
Approved by GAO, B180225 (R0072) clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
3.077
IE Bulletin No.78-12A 4ovember 24, 1978 Page 1 of 2 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 Operating License (0L) or Construction Permit (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 78-04 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 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils CL or CP 78-07 Prntection afforded 6/12/78 All Power Reactor by sir-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 Priority 1 Material Licensees 3.078
IE Bulletin No.78-12A November 24, 1978 Page 2 of 2 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.
78-08 Radiation Levels from 6/12/78 All Power, Test, and Fuel Element Transfer Research Reactor Tubes Facilities with an OL having Fuel Element Transfer Tubes.
78-09 BWR Drywell Leekage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL (for action)
Closures or CP (for information).
78-10 Bergen-Patcrson 6/27/78 All Fower Hydraulic Shock Reactor Facilities Suppressor Accumulator with an OL or CP.
Spring Coils 78-11 Examination of Mark I 7/21 /78 BWR Power Reactor Containment Torus Facilities with an OL Welds for action:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vermont Yankee.
All other BWR Power Reactor Facilities with an OL for information.
78-12 Atypical Weld Material in 9/29/78 All Power Reactor Reactor Pressure Vessel Facilities with an OL or Welds CP 78-13 Failures in Source Heads 10/27/78 All General and Specific of Kay-Ray, Inc. Gauges Licenscos with the Models 7050, 70508, 7051, Subject Kay-Ray, Inc.
7051 B, 7060, 7060B, 7061 Gauges and 7061B 3.07P