05000346/LER-1978-108-03, /03L-0:on 781101,surveillance Requirements of Tech Spec 4.7.1.2 Found Not Completed.Caused by Procedural Deficiencies.Procedure Mods Written to Incorporate Tech Spec & Further Procedures Will Be Written for Remaining Testing

/03L-0:on 781101,surveillance Requirements of Tech Spec 4.7.1.2 Found Not Completed.Caused by Procedural Deficiencies.Procedure Mods Written to Incorporate Tech Spec & Further Procedures Will Be Written for Remaining Testing

ML113480150
Person / Time
Site:	Davis Besse
Issue date:	11/28/1978
From:	Jerrica Johnson TOLEDO EDISON CO.
To:	NRC/OI/RGN-III/FO
Shared Package
ML113480151	List: 05000346/LER-1978-108, Forwards LER 78-108/03L-0 05000346/LER-1978-108-03, /03L-0:on 781101,surveillance Requirements of Tech Spec 4.7.1.2 Found Not Completed.Caused by Procedural Deficiencies.Procedure Mods Written to Incorporate Tech Spec & Further Procedures Will Be Written for Remaining Testing
References
LER-78-108-03L, LER-78-108-3L, NUDOCS 7812050218
Download: ML113480150 (5)

LER-1978-108, /03L-0:on 781101,surveillance Requirements of Tech Spec 4.7.1.2 Found Not Completed.Caused by Procedural Deficiencies.Procedure Mods Written to Incorporate Tech Spec & Further Procedures Will Be Written for Remaining Testing

Event date:
Report date:
3461978108R03 - NRC Website

text

Docket No. 50-263 Docket No. 50-282 Docket No. 50-306 Northern States Power Company ATTH:

Yr. Leo Wachter Vice President Power Production and Systen:

Operation 414 Nicollet hall Minneapolis, MN 55401 Gentlemen:

1

~.

Enclosed is a supplement (IE Bulletin No.78-12A) to IE Bulletin No. 7B-12 which requires action by you with regard to your power reactor facilities with an operating license or a construction perlait.

Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.

Sincerely, James G. Keppler Director

Enclosures:

1. IE Bulletin 78-12A

2. List of IE Bulletins Issued in 1978 cc w/encls:

Mr. L. R.

Eliason, Plant M'anager ir. F. P. Tierney, Jr.,

Plant Manager Central Files Director, NRR/DPM Director, NRR/DOR PDR Local PDR NSIC TIC Anthony Roisman, Esq.,

Attorney John W. Ferman, Ph.D.

Nuclear Engineer RIII R)W RIII OFFICE Do Fiorelli/is 7

- ler SURNAME W 11/24/78 DATE Jm-4 A

F _t

+

4.

CENTRAL FILES N~OV 24.J-7

/

Ac)h -

NRC Form SNRCM 02040

- U.

S. GOVERNMENT PRINTING OFFICE:

1978-253-818

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III November 24, 1978 IE Bulletin No.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.

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 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 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

1. typical weld material./

Tkhe twelve nuclear units identified as having possible atypical pressure vessel weldments are: Three Mile Island Unit Nos. I 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. I and 2.

U IE Bulletin No.78-12A 2 -

November 24, 1978

'I

1.

Provide all information available on weld materials used for each reactor vessel primary boundary ferritic weldment / (Items 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.) 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 I 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, B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.

../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.

IE Bulletin No.78-12A Date: November 24, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Subject Date Issued Bulletin No.

78-01 78-02 1/16/78 1/30/78 2/8/78 2/21/78 4/14/78 5/31/78 6/12/78 Issued To All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP All BWR Power Reactor Facilities with 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 or CP All Power Reactor Facilities with an OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees Page 1 of 2 Flammable Contact Arm Retainers in G.E.

CR120A Relays Terminal Block Qualification Potential Explosive Gas Mixture Accumula tions Associated with BWR Offgas System Operations Environmental Quali fication of Certain Stem Mounted Limit Switches Inside Reactor Containment Malfunctioning of Circuit Breaker Auxiliary Contact Mechanism-General Model CR105X Defective Cutler Hammer, Type M Relays With DC Coils Protection afforded by Air-Line Respirators and Supplied-Air Hoods 78-03 78-04 78-05 78-06

• 1 78-07

IE Bulletin No.78-12A Date: November 24, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Subj ect Date Issued Bulletin No.

78-08 78-09 78-10 78-11 78-12 6/12/78 6/14/78 6/27/78 7/21/78 9/29/78 Radiation Levels from Fuel Element Transfer Tubes BWR Drywell Leakage Paths Associated with Inadequate Drywell Closures Bergen-Paterson Hydraulic Shock Suppressor Accumulator Spring Coils Examination of Mark I Containment Torus Welds Atypical Weld Material in Reactor Pressure Vessel Welds Failures in Source Heads of Kay-Ray, Inc., Gauges Models 7050, 7050B, 7051 7051B, 7060, 7060B, 7061 Issued To All Power and Research Reactor Facilities with a Fuel Element transfer tube and an OL.

All BWR Reactor with an All BWR Reactor with an Power Facilities OL or CP Power Facilities OL or CP BWR Power Reactor Facilities for action:

Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti cello and Vermont Yankee All Power Reactor Facilities with an OL or CP All General and Specific Licensees with Kay-Ray Gauges Page 2 of 2 10/27/78 and 7061B 78-13