ML20062E979
| ML20062E979 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/24/1978 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Eric Turner HOUSTON LIGHTING & POWER CO. |
| References | |
| NUDOCS 7812130315 | |
| Download: ML20062E979 (6) | |
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I;ovember 24, 1978 In Reply Refer To:
RIV Dacket ilos. 50-498/IE Bulletin 78-12A 50-499/IE Bulletin 78-12A i
l Heuston Lighting & Power Company ATTit: Mr. E. A. Turner, Vice President Power Plant Construction and Technical Services Post Office Box 1700 1
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Houston, Texas 77001 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 facilities with an operating license or a construction permit.
j Should you have any questions regarding this Bulletin or.the acti is required by you, please contact this office.
Sincerely, l
d Karl V. Seyfrit Director 4
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978 I
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i i-781213 031 5 k'
UNITED STATES NUCLEAR REGULATORY C0:GtISSION OFFICE OF It SPECTION AND ENFORCEiENT I
UASHINGTON, D.C.
Date: flovember 24, 1978 Page 1 of 2 ATYPICAL MELD MATERIAL Ifl REACTOR PRESSURE VESSEL MELDS Description of Circumstances:
This Bulletin is a _ supplement to '.2 Bulletin 78-12, issued on September 29, 1978, and the two documents should be considered together.
i 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 tran'sition temperature characteristics which in turn requires more conservative pressure / tempera-ture operating limits.
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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, 'xcept those already identified as possibly having j
atypical weld materi, 4 If:
1 4
If The twelve nuclear units identified as having possible atypical pressure vessel weldments are: Three Mile Island Unit Hos.1 and 2, Crystal River Unit No. 3, Arkansas Nuclear One Unit No.1, Oconee Unit flo. 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.
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November 24, 1978 Page 2 of 2 1.
Provide all infonnation available on weld materials used for each reactor vessel primary boundary ferritic weldment. 2]
(Items 1c, Id, 2a, 2b, first sentence of 2c, 3 and 4 of Bulletin 78-12.) This infonntion may be provided to URC through the vessel menufacturers or suppliers as appropriate to pre. vent duplication of da:a.
2.
Correlation of specific heat, lot or batch to specific wel:'ments in specific vessels is not required at this time.
(Last ser.tence 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.
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3.
Responses to Item 1 above shall be submitted in writing within 120 days of the date of this Bulletin supplement.
Reports should be subnitted 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.
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]/~keld 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 i
LISTING OF IE BULLETINS ISSUED IN 1978-Bulletin Subject Date Issued Issued To No.
78-01 Flammable Contact 1/16/78 All Power Reactor Arm Retainers in G.E.
Facilities with an CR120A Relays Operatilig License (OL)orConstruc-tion Permit (CP)
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78-02 Terminal Block 1/30/78 All Power Reactor j
Qualification Facilities with an Operating License (OL)orConstruc-tion Pennit'(CP) 78-03 Potential Explosive 2/8/78 All.BWR Power Gas Mixture Accumula-Reactor Facilities tions Associated with with an Operating BWR Offgas System License (OL) or Operations 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 Pennit (CP) 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operating License Machanism - General (0L) or Construc-Electric Model tion Pennit (CP)
CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor llammer, Type M Relays Facilities with an With DC Coils Operating License-(0L) or Construc-tion Permit (CP)
Enclosure Page 1 of 3
November 24, 1978 78-07 Protection Afforded 6/12/78 All Power Reactor by Afr-Line Facilities with an Respirators and Operating License (OL) and Supplied-Air all class E and F Hoods Research Reactors with an OL, all Fuel Cycle Facilities, with an OL, and all Priority 1 Material Licensees 78-08 Radiation levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor
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Tubes Facilities with a Fuel Element Trans-i fer Tube and an Operating License (0L) 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 BWR Power Ilydraulic Shock Reactor Facilities Suppressor Accumulator with an Operating
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Spring Coils License (0L) or Construction Per-mit (CP) 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 Enclosure Page 2 of 3
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November 24, 1978
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78-12 Atypical Weld Material 9/26/78 All Power Reactor-in Reactor Pressure Facilities with an Vessel Welds Operating License (0L) or Construc-
. tion Permit (CP) 78-13 Failures in Source 10/27/78 All General and Heads _of Kay-Ray, Specific Licensees Inc., Gauges Models with Kay-Ray Gauges 7050, 7050B, 7051, 70518, 7060, 70608, 7061 and 70618 1
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Enclosure Page 3 of 3 f
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