ML18078A507
| ML18078A507 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/24/1978 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 7812180022 | |
| Download: ML18078A507 (5) | |
Text
L a
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. 50-272 Public Service Electric and Gas Company ATTN:
Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Gentlemen:
2 4 NOV 1978 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.
Enclosures:
- 1.
IE Bulletin 78-12A
- 2.
List of IE Bulletins Issued in 1978 cc w/encls:
Sincerely, F. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station
UNITED STATES
-NUCLEAR REGULATORY COMMISSII FFICE OF INSPECTION AND ENFORC ENT WASHINGTON, D.C.
20555 IE Bulletin No.78-12A Date:* November 24, 1978 Page l of 2
- 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 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 consEfrvative pressure/
temperature operating limits.
Bulletin 78-12 was issued for the purpose 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 le, 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.
l The twelve nuclear units identified as having possible atypical pressure vessel weldments are: Three Mile Island Unit Nos. l 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. 4 and Zion Unit Nos. l and 2.
2 Weld material i"nformation submitted will be evaluated by NRC.
Requests for further information will be dependent upon results of these evalua-tions. Additional requests or instructions will 'be issued following these evaluations.
IE Bulletin No. 78-l2A.
Date:
November 24, 1978 Page 2 of 2
- 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 weld materials information provided to the NRC under Item l does in fact cover each reactor vessel for which the licensee is responsible.
- 3.
Responses to item l 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 NRC Regional Office and a copy should be forwarded to the U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Reactor Construction Inspection, Washington, D.C.
20555.
Approved by GAO, 8180225 (R0072); clearance expires 7/31/80.
Approval
- was given under a blanket clearance specifically for*identified generic problems.
Bulletin No.
78-01 78-02 78-03.
78--04 78-05 78-06 78-07
- Page 1 of 2 Subject Date Issued Issued To Flammable Contact -
1/16/78 Arm Retainers in G.E.
CR120A' Relays Terminal Block 1/30/78 Qualification Potential Explosive 2/8/78 Gas Mixture Accumula-tions Associated with BWR Offgas System Oper_ations Environmental Quali-2/21/78 fication of Certain Stem Mounted Limit Switcnes Inside Reactor Containment Malfunctioning of 4/14/78 Circuit Brea.ker Auxiliary Contact Mechanism-General Model CR105X.
Defective Cutler-5/31/78 Hammer, Type M Relays
. Wi th
- DC Co i l s Protection afforded 6/12/78 by Air-Line Respirators and Supplied-Air Hoods All Power Reactor Facilities with an Operating License (OL) or Construction Permit (CP)
All Power Reactor Facilities with an OL or CP All BWR Power Reactor Facilities with an OL or CP All Power Reactor Facilities wfth an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactor facilities with an OL or CP All Power Reactor Facilities with an OL, all Class*E and F Research Reactors with an QL, all Fuel Cycle Facilities with an OL, and all Priority l Material Licensees
Bulletin No.
78-08 78-09 78-: 10 78-11 78-12 78-13 LISTING OF IE BULLETINS ISSUED IN 1978 Subject Date Issued Radiation Levels from 6/12/78 Fuel Element Transfer Tubes
. BWR Drywell Leakage 6/14/78 Paths Associated with Inadequate Drywel 1 Closures Bergen-Paterson 6/27/78 Hydraulic Shock Suppressor Accumulator Spri_ng Cai 1 s.
Examination of Mark I 7/21/78 Containment Torus Welds Atypical Weld Material in 9/29/78 Reactor Pressure Vessel Welds Failures in Source Heads 10/27/78 of Kay-Ray, Inc. Gauges Models 7050, 7050B; 7051, 7051 B, 7060, 70608, 7061 and. 70618 IE. Bulletin No.78-12A November 24, 1978 P_age 2 of 2 Issued To All Power, Tesi, and Research Reactor Facilities with an OL having Fuel Element Tran.sf er Tubes.
All 8WR Power Reactor Facilities with an OL (for action) or CP* (for. information).
All Power Reactor Facilities with an OL or CP.
BWR Power Reactor Facilities with an OL for action: Peach
- Bottom* 2 and 3, Quad Cities 1 and 2, Hatch 1, Monticello and Vermont Yankee.
All other 8WR Power Reactor Facilities with an OL for information.
All Power Reactor Facilities with an OL or CP All General and Specific Licensees with the Subject Kay-Ray, Inc.
Ga.uges