ML20204C868
| ML20204C868 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/24/1978 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 7812050271 | |
| Download: ML20204C868 (1) | |
Text
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r UNITED STATES c/ *%,
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pt NUCLEAR REGULATORY COMMISSION i 21 1 y REGION 811 g, q, /, g 799 ROOSEVELT ROAD e
GLEN E LLYN, ILLINots 60137 NOV f 4 378 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN:
Mr. Sol Burstein Senior Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 53201 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 pow.tr reactor facilities 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, G k Director
Enclosures:
- 1. IE Bulletin 78-12A
- 2. List of IE Bulletins issued in 1978 cc w/encls:
Mr. G. A. Reed, Plant Manager Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC 78120scq 7r
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT i
REGION III i
November 24, 1978 IE Bulletin No.78-12A i
ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:
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This Bulletic is a supplement to IE Bulletin 78-12, issued on i
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 velds of twelve identified reactor pressure vessels. Use of the atypical veld material in vessel veldments csuses them to have higher than normal mil-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 stypteal veld material was not also supplied to other vessel manufacturers.
J 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 nodified.
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Action To Be Taken By Licensees and Permit Holders:
For all power reactor facilities with an operating license or a
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construction permit, except those already identified as possibly having 9 typical veld material.3/
i JNhhetwelvemuelearunitsidentifiedashavingpossibleatypical pressure vessel veldcents are: Three N31e Island Unit Nos.' I and 2, y.
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- - Crystal River Unit No. 3, Arkansas Nuclear One Unit No.1, Oconee s' -
Unit No. 3 Rancho Seco Unit No.1. NMdland Unit No.1, Quad Cities l
Unit No. 2, Browns Perry Unit No 1, Turkey Point Unit No. 4 and i
Zion Unit Nos. I and 2.
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r IE Bulletin No.~ 78-12A 2-November 24, 1978 J
1.
Provide all information available on veld materials used for each reactor vessel primary boundary ferritic weldmentc/ (Items 1c, Id, 2
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.) However, each licensee is required to verify that the weld materials infornation 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 Com=ission, 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.
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I 1/ Weld material information submitted will be evaluated by NRC. Requests for further information will be dependent upon results of these evalus-tions. Additional requests or instructions will be issued following these evaluations.
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i IE Bulletin No.78-12A Date: November 24, 1978 j
.g LISTING OF IE BULLETINS ISSUED IN 1978 i
Bulletin Subj ect Date Issued Issued To No.
78-01 Flammable Contact -
1/16/78 u l 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 i
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 i
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 Mechanisc4eneral Model CR10SX 78-06 Defective Cutler-5/31/78 All Power Reacter 1
1, 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 l
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Research Reactors with an OL, all Fuel Cycle Facilities with an OL,
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and all Priority 1 l
.l Material Licensees Page 1 of 2 l.
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IE Bulletic No.78-12A Date November 24, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subj ect 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 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 6/27/78 All BWR Power 1
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 s
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 Resetor 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., Gauges Specific Licensees Models 7050, 7050B, 7051 with Kay-Ray Cauges 7051B, 7060, 7060B, 7061 and 7061B Enclosure' 1 Page 2 of 2 1
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