ML20148U094
| ML20148U094 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/24/1978 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 7812060269 | |
| Download: ML20148U094 (1) | |
Text
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@ R80g UNITED STATES D
NUCLEAR REGULATORY COMMIS$10N f
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R EGION IV o
5gr 611 RYAN PLAZA ORIVE, SUITE 1000 NSIC AR LINGTON, TEX AS 76011 o,,.g,*****j November 24, 1978.
Docket Nos. 50-368 50-313 Arkansas Power and Light Company A'iTH: Mr. William Cavanaugh III
~,
Executive Di ector of Generation and Construction Post Office Box 551 Little Rock, Arkansas 72203 Gentlemen:
Enclosed is a supplement (IE Oulletin No.78-12A) to IE Bulletin No. 78-12 which requires action by you with regard to your power reactor facilities with an operating licenso or a construction pennit.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, l
$O0Mh Karl V. Seyfrit Director
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978 7812060269
VillTED STATES NUCLEAR REGULATORY COMMISSIOll 0FFICE OF IflSPECTION AllD ENFORCEMEtiT WASHIt1GTON, D.C.
20555 IE Dulletin flo.78-12A Date: ilovember 24, 1978 Page 1 of 2 ATYPICAL WELD MATERIAL Ifl 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 temperature characteristics which in turn recuires more conservative pressure / tempera-ture 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 Culletin 78-12 are being modified.
Action Tc Ba 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 material 1]:
l jf The tGilve nuBear unIYs identiffed as having possible atypical pressure vessel weldments are:
Three Mile Island Unit Nos. 1 and 2, Crystal River Uni t No. 3, Arkansas Nuclear One Unit tio.1, Oconee Unit No. 3, Pancho Seco Unit flo. 1, Midland Unit No. 1, Quad Cities Unit No. 2, Browns Ferry Unit No.1, Turkey Point Unit No. 4 and Zion Unit Nos. 1 and 2.
Noveroer 24, 1978 Page 2 of 2 1.
Provide all infonnation available on vield materials used for each reactor vessel primary boundary ferritic weldment. 2]
(ftems Ic, Id, 2a, 2b, first sentence of 2c, 3 and 4 of Bulletin 78-12. ) This information may be provided to NRC 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. ) llowever, 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 NRC Regional Office and a copy should be forwarded to the U.S. Nuclear Regulatory Commission, Of fice of Inspection and Eniecement, 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.
l l
l l
[/ Weld material information 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 l
these evaluations.
November 24, 1978 LISTING OF IE BULLETINS ISSUED IN 19/8 Bulletin Subjec t Date Issued Issued To
' fio.
78-01 Flammable Contact 1/16/78 All Power Reactor Arm Retainers in G.E.
Facilities with an CR120A Relays Operating License (OL) or Construc-tion Permit (CP) 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with an Ooerating License (OL) or Construc-tion Permit (CP) 78-03 Potential Explosive 2/8/78 All BWR Power Gas Mixture Accumula-Reactor Facilities i
tions Asrociated with with an Operating' BWR Of'o System License (OL) or n
(
Operations Construction Permit (CP) 78-04 Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit Operating License Switches Inside (OL) or Construc-Reactor Containment tion Permit (CP) 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operatina License Mechanism - General (OL) or Construc-Electric Model tion Permit (CP)
CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type il Relays Facilities with an With DC Coils Operating License (OL) or Construc-tion Permit (CP)
Enclosure Page 1 of 3
flovember 24, 1978 78-07 Protection Afforded 6/12/78 All Power Reactor by Ai r-Line Facilities with an Respirators and Operating License (OL) and Supplied-Air all class E and F Hoods Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees 78-08 Radiation levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor Tubes Facilities with a Fuel Element Trans-fer Tube and an Operating License (OL) 78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an Operating Closures License (OL) or Construction Per-mit (CP) 78-10 Bergen-Pa terson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an Operating Soring Coils License (OL) or Construction Per-l mit (CP) 78-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Facilities for Welds action: Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee Enclosure Page 2 of 3
November 24, 1978 78-12 Atypical Weld tlaterial 9/26/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds Operating License (OL) or Construc-tion Permit (CP) 78-13 Failures in Source 10/27/73 All General and Heads of Kay-Ray, Specific Licensees Inc., Gauges ftodels with Kay-Ray Gauges 7050, 70508, 7051, 7051B, 7060, 70603, 7061 and 7061B 1
Enclosure Page 3 of 3