ML20148G462
| ML20148G462 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/17/1978 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 7811130082 | |
| Download: ML20148G462 (2) | |
Text
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NUCLEAR REGULATORY COMMISSION 5
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- W ALNUT CREEK, C ALIFORNI A 94596 flovember 24, 1978 l
l Docket Nos. 50-460 50-3?7 50-508 d 50-509 50-513 Washington Public Power Supply System P. O. Box 968 3000 George Washington Way Richland, Washington 99352 At-ation: Mr. ft. O. Strand Managing Director Gentlemen:
I 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)withanoperatinglicenseoraconstructionpermit.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, f,
C n
e R. H. Engelken Director
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978 cc w/ enclosures:
M. E. Witherspoon, WPPSS A. D. Kohler, WNP-2, l'PPSS J. P. Thomas, WPPSS G. K. Dyekman, WPPSS N. Lewis, WA Energy Facility l
781130003d-3,
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l UNITED STATES tiUCLEAR REGULATORY COMMISSION OFFICE OF IllSPECTI0fl AND ErlFORCEMEflT WASHIilGTON, D.C.
20555 tiovember 24, 1978 IE Bulletin flo.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 considered together.
Bulletir, 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 requires 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 l
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 l
constructionpermit,eyceptthosealreadyidentifiedaspossiblyhaving atypical weld material :
I 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 fluclear One Unit flo.1, Oconee Unit No. 3, Rancho Seco Unit flo.1, Midland Unit flo.1, Quad Cities Unit No. 2, Browns Ferry Unit No.1, Turkey Point Unit No. 4 and Zion Unit Nos.1 and 2.
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IE Bulletin flo.78-12A f;ovember 24, 1978 1.
Provide all information available on weld materialg used for each reactor vessel primary boundary ferritic weldment.
(Itemsic,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.
l 2.
Correlation of specific heat, lot or batch to specific weldments in specific vessels is not required at this time.
(Lastsentence of Item 2c,Bulletin 78-12. ) However, each licensee is required i
to verify that the weld materials information provided to the NRC under Item 1 does in fact cover each reactor vessel for which ti.e 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 l
Commission, Offica 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.
2 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 these evaluations.
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Date: November 24, 1978 l
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LISTING 0F IE BULLETINS l
ISSUED IN 1978 Bulletin Subject Date Issued Issued To l
Ho.
78-01 Flam:nable 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 8WR 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 j
78-05 Malfunctioning of 4/14/78 All Power Reactor l
Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR10SX 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils 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 l
an OL, all Fuel Cycle l
Facilities with an OL, l
and all Priority 1 Material Licensees Page 1 of 2 l
flovember 24, 1978 l
l-LISTlilG OF IE BULLETIf1S ISSUED Ifl 1978 l
Bulletin Subject Date Issued Issued To flo.
78-08 Radiation 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 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL or CP Closures 78-10 Bergen-Paterson 6/27/76 All BWR Power 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 for Welds action:
Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-13 Failures in Source Heads 10/27/78 All General and of Kay-Ray, Inc., Gc uges Specific Licensees Models 7050, 70508, 7051 with Kay-Ray Gauges 70518, 7060, 7060B, 7061 and 7061B Page 2 of 2