ML20148U079
| ML20148U079 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/24/1978 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 7812060261 | |
| Download: ML20148U079 (1) | |
Text
UNITED STATES PDR:HQ
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NUCLEAR REGULATORY COMMISSIOf1 LPD
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I* 'o REGION IV d
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5 611 RYAN PLAZA DRIVE, SUITE 1000 N3{C' AR LINGTON, TEXAS 76011 November 24,=1978 i
-Docket No.'50-298 i
i Nebraska Public Power District ATTN:' Mr. J. M. Pilant, Licensing &
Quality Assurance Manager Post Office Box 499 columbus, Nebraska 68601 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 I
required by you, please contact this office.
j Sincerely, fWa&f Karl V. Seyfrit Director
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins
' Issued in 1978 j
r i
)
7 812 0 6 0 2 6 l'
J UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND Etif0RCEMENT WASHIllGTON, D.C.
20555 IE Bulletin No.78-12A Date:
November 24,'1978 Page 1 of 2 ATYPICAL WILD MATEP,IAL IN PEACTOR 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 atypical weld material if:
l D The twElie nuclear. units identified as having possible atypical pressure vessel weldments are: Three Mile Islind Unit Nos.1 and 2, Crystal River Uni t No. 3, Arkansas Nuclear One Unit No.1, Oconee Unit No. 3, Rencho 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. 1 and 2.
[
,.7 IE Bulletin No.78-12A Date:
November 24, 1978 Page 2 of 2 1.
Provide all information available on weld materials used 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 information nay be provided to NRC through the vessel manufacturers or suppliers as appropriate to prevent duplication of data.
P Correlation of specific heat, lot or batch to specific weldments 1
in specific vessels is not required at this time.
(Last sentence i
of item 2c,Bulletin 78-12.) However, each licensee is required to verify that the weld materials information provided to the NRC
.j under Item 1 does in fact cover each reactor vessel for which the
-l licensee is responsible.
)
3.
Responses to Item 1 above shall be submitted in writing within i
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 i
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 Wds given under a blanket clearance specifically for identifica 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.
~_
November 24, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin' Subject Date Issued Issued To No.
78 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 Operating License (OL) or Construc-tion Permit (CP) 78-03 Poteritial Explosive 2/8/78 All BWR Power Gas Mixture Accum61a-Reactor Facilities tions. Associated with with an Operating BWR Offgas System License (OL) or Operation:
Construction Permit (CP) 78-04 Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an:
Stem Mounted Limit Operating License i
. Switches Inside (0L) or Construc-Reactor Containment tion Permit (CP) 78-05 Malfunctioning of.
4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operating License Mechanism - General (OL) or Construc-Electric Model-tion Permit (CP)
CR10SX 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer,. Type M Relays Facilities with an With DC Coils Operating License (OL) or Construc-tion Permit (CP)
~ Enclosure Page l'of 3~
i
+
+
November 24, 1978 78-07 Protection Afforded 6/12/78 All Power Reactor by Air-Line Facilities with an Respirators and Operating License (OL) and Supplied-Air all class E and F Hoods Research Reactors with an OL, all Fual Cycle Facilities with an OL, and all Priority 1 Material Licensees 78-03 Radiation Levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor Tubcs facilities with a l
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-Paterson 6/27/78 All BUR Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an Operating Spring Coils License (0L) or Construction Per-mit (CP) 73-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Facilities for Weld 3 action: Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch ', Mon ti-cello anc 'ermont Yankee Enclosure Page 2 of 3 wi...-..
9 IE Bulletin I;o.78-12A Date:
iloverr.ber 24, 1978 78-12 Atypical Weld Material 9/26/78 All Power Reactor
~
in Reactor Pressure Facilities wi th an Vessel Lids Operating License (OL) or Construc-tion Permit (CP) 78-13 Failures in Source 10/27/78 All General and Heads of Kay-Ray, Specific Licensees
,.c Inc., Gauges Models with Kay-Ray Gauges 7050, 70503, 7051, 7051B, 7060, 7050B, 7051 and 70618 8
/
i e
ed Enclosure Page 3 of 3
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