ML20062E231

Forwards IE Bulletin 78-12A,suppl to IE Bulletin 78-12. W/Encl ANO:7811300055

ML20062E231
Person / Time
Site:	05000484
Issue date:	11/24/1978
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Dienhart A NORTHERN STATES POWER CO.
References
NUDOCS 7812050344
Download: ML20062E231 (1)

Text

_ _ _ _ _ - _ _ _ _

. - - . . . _ . ~ . . _ _ _

y ,.. _

l .

"*""%, PDN

.,/ - 4 UNITED STATES NUCLEAR REGULATORY COMMISSION f* . ,*, d I  ;-

REGloN lli 799 ROOSEVELT ROAD

<, . g, OLEN ELLYN,ILLINo15 60137 -

NOV Y 4 378 Docket No. 50-484 g Northern States Power Company ATTN: Mr. A. V. Dienhart Vice President - Tyrone Energy Park 100 North Barstow Street Eau Claire, WI 54701 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 power reactor facility 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.

1 l

Sincerely, bh ab-JamesG.Kep/IEr l Director

Enclosures:

1. IE Bulletin 78-12A

( 2. List of IE Bulletins Issued in 1978 l

l j cc w/encls:

Central Files Director, NRR/DPM J Director, NRR/ DOR I

PDR Local PDR NSIC TIC Regions I & IV l

l 78120503d k

.. .. .. ....~~...... .77I'... .

? T. - T - - 7 ~ ' ~ ' . . ^~ -- - : ' ~ ~ - ~ ' " - - " - - -

L.. . . - .. . ... . _ . _ _ . .,- .

7. .. . . . . .

i -

8 U.S. NUCLEAR REGULATORY COMMISS".ON i OFFICE OF INSPECTION AND EhFORCEMEliT R1,GION III Novenber 24, 1978 IE Bulletin No.78-12A ,

ATYPICAL WELD MATERIAL IN REACTOR PFISSUE VESSEL WELDS

. Description of Circumstances:

This Bulletin is a supplement to IE Bulletin 78-12, issued on

, Septenber 29, 1978, and the two documents should be considered together.

Bulletin 78-12 described the use of veld 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 veldnenta causes them to have higher than normal nil-ductility transition temperature characteristics which in turn requires more conservative pressure /tenpera-ture operating limits.

Bulletin 78-12 was issued for the purpose of verifying that similar atypical veld 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 requirenents of Dulletin 78-12 are being modified.

. I

~

Action To Be Taken By Licensees and Permit Holders:

, Tor all power reactor facilities with an operating license or a 1 .. construction permit, except those already identified as possibly having stypical weld material.V

. khe twelve nuclear units identified as having possible atypical

,. pressure vessel weldnents are: Three Mile Island Unit Nos. 1 and 2 Crystal River Unit No. 3, Arkansas Nuclear One Unit No.1. Oconee

. r_ - . Unit No. 3, Rancho Seco Unit No. 1. Midland Unit No. 1. Quad Cities Unit No. 2 Browns Terry Unit No.1, Turkey Point Unit No. 4 and

, " ion Unit Nos. I and 2. l

. . .. .......~.,. . . . ..

- - --.- T .. . ; . ;m q _ . . _ . r-- ~r'r . - - - -~ ~ ~

i.

IE Bulletin No.78-12A Nov i4, 1978 J

1. Provide all information available on veld materials t.,ed for each reactor vessel primary boundary ferritic weldment 2/ (Items Ic, Id.

2a, 2b, first sentence of 2c, 3 and 4 of Bulletin 78-12.) This infor=ation 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 veld 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 approprit te NRC Regional Offica 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 ur. der a blanket clearance specifically fer identified generic problems.

)

(

l 1

l 4

l P

.3/ Weld material information submitted will be evaluated by NRC. Requests for further information vill be dependent upon results of these evalua-tions. Additional requests or instructions will be issued following

'hese evaluations.

t

l >

l., . , .

i 3: - .

.+ ,

~. ;

IE Bulletin No.78-12A Date: November 24, 1978

.' LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued I? sued To No.

78-01 F1ancable 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 Po:rer 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 BWR Offgas System i Operations I

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 3' Mechanisc-Ceneral L *el CR105X 78-06 Defective Cutler- 5/31/78 All Power Reactor I

Raccer, Type M Relays Facilities with an With DC Coils OL or CP r

( , 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 Research Reactors with '

an OL, all Fuel Cycle Facilities with an OL, and all Priority 1

} Material Licensees Enclosure 1 Page 1 of 2

. . . , . . . . . . . _ . - ~ . . . . - - '

~ '

- " " * - - - * * , - * -

• ew.O e. . . , , , . , , __

__ - . - - . - . . . - - - . - - - - - - - ~ - --- -

I - v.

(. .

i IE Bulletin 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-Patusen 6/27/78 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. , Cauges Specific Licensees Models 7050, 7050B, 7051 with Kay-Ray Gauges 7051B, 7060, 7060B, 7061 and 7061B t

Enclosure 1 Page 2 of 2 l

l 1

_