ML20148T112
| ML20148T112 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Vogtle  |
| Issue date: | 11/24/1978 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | John Miller GEORGIA POWER CO. |
| References | |
| NUDOCS 7812040310 | |
| Download: ML20148T112 (1) | |
Text
_-
UNITED si ATES f
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NUCLEAR REGULATORY COMMISSION REGION 11 g-y
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101 M ARIETT A ST RE E T. N.W.
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ATL ANT A. GEORGI A 30303 x
y NOV 241978 In Reply Refer To:
RII:JPO 50-321, 50-366 50-424, 50-425 Georgia Power Company Attn:
Mr. J. H. Miller, Jr.
Executive Vice President 270 Peachtree Street, N. W.
Atlanta, Georgia
-30303 Gentlemen:
I 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 (les) 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,
.C g
ames P. O'Reilly D rector
Enclosures:
l.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978 78120403yo
6 Georgia Power Company l
cc w/ enc 1:
K. M. Gillespie Construction Project Manager Plant E. 1. Hatch P. O. Box 439 Baxley, Georgia 31513 H. Manry, Plant Manager Plant E. 1. Hatch P. O. Box 442 Baxley, Georg's 31513 k'. M. Johnston Project Construction Manager Vogtle Nuclear Plant P. O. Box 282 Waynesboro, Georgia 30830 l
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UNITED STATES NUCLEAR REGUIATORY COMMISSION OFFICE OF INSPECTION AND EITFORCDEIT WASHINGTON, D.C.
20555 November 2h, 1978 IE Bulletin No. 78-3 2A ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletin 78-22, issued on September 29, 2978, and the two documents should be considered together.
Bulletin 78-12 described the use of veld vire 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 causes them to have higher than normal nil-ductility transition temperature characteristics which in turn requires more conservative pressure / tempera-ture operating limits.
Bulletin 78-22 was issued for the purpose of verifying that similar atypical veld material was not also supplied to other vessel manufacturers l
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 perrit, except those already identified as possibly having stypical veld material 1:
1 The twelve nuclear units identified as having possible atypical pressure vessel veldments are:
Three Mile Island Unit Nos. I and 2, l
Crystal River Unit No. 3, Arkansas Nuclear One Unit No.1, Oconee Unit No. 3, Rancho Seco Unit No.1, Midland Unit No. 3, Quad Cities l
Unit No. 2, Browns Ferry Unit No.1. Turkey Point Unit No. L and Zion Unit Nos. 2 and 2.
1 1 of 2 W
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IE Bulletin No.78-12A November 2L, 1978 1.
Provide all information available on veld materials used for each reactor vessel primary boundary ferritic weldment.2 (Items Ic, Id, 2a, 2b, first sentence of 2c, 3 and L of Bulletin 78-12. ) This information may be provided to NEC through the vessel manuf acturers or suppliers as appropriate to prevent duplication of data.
2.
Correlation of specific heat, lot or batch to specific veldments in specific vessels is not required at this time.
(Last sentence of Item 2c,Bulletin 78-22. ) 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 appropriate NRC Regional Office and a copy should be forwarded to the U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Regetor Construction Inspection, Washington, D.C.
20555 Approved by GAO, E180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
2 Weld material information submitted vill be evaluated by URC.
Requests for further information vill be dependent upon results of these evalua-tions. Additional requests or instructions will be issued following these evaluations.
2 of 2
1 IE Bulletin No.78-12A Date: UcVember 2L, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.
78-11 Flammable 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 Power Reactor Qualification Facilities with an OL or CP 78-03 Potential Explosive 2/8/78 All B'#R Power Gas Mixture Accumula-Reactor Facilities tions Associated with with an OL or CF BWR Offgas System Operations 78-OL Environmental Quali-2/22/78 All Power Reactor fication of Certain Facilitie with an Stem Mounted Limit OL or CP Switches Inside Reactor Containment 78-05 Malfunctioning of L/1L/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mech anism-General Model CR105X 78-06 Defective Cutler-5/ 31/78 All Power Reactor 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 F and F Research Beneters with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees Page 1 of 2 l
l l'---
4 IE Bulletin No. 78 12A Date: November 21., 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Icsued 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 Dryvell Leakage 6/lb/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Dryvell with an OL or CP Closures 78-10 Bergen-Paterson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities Suppressor Accu =ulator with an OL or CP Spring Coils 7L22 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 2, Monti-cello and Vermont Yankee 7-22 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Yessel Welds OL or CP 8-23 Failures in Source Heads 20/27/78 All General and of Key-Ray, Inc., Gauges Specific Licensees Models 7050, 70503, 7052 vith Kay-Ray Gauges 7051B, 7060, 7060B, 7061 and 7061B Page 2 of 2 l
l
UNITED ST ATES gf I
g#'eRicoq'o, NUCLEAR REGULATORY COMMISSION fpf RECloN 11 3,,
g 101 M ARIE TT A ST R E E T. N.W.
5 E
g ATLANTA GEoRGtA 30303
\\'
/
NOV 241978 In Reply Refer To:
RII:JPO 50-321, 50-366 50-424, 50-425 Georgia Power Company Attn:
Mr. J. H. Miller, Jr.
Executive Vice President 270 Peachtree Street, N. W.
Atlanta, Georgia -30303 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 (ies) 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,
. C h'$$.
p mes P. O'Reilly D rector w
~'
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins Issued in 1978
.7812040/,
.-m 7812o49,,9
Georgia Power Company cc w/ encl:
K. M. Gillespie Construction Project Manager Plant E. I. Hatch P. O. Box 439 Baxley, Georgia 31513 H. Manry, Plant Manager Plant E. I. Hatch P. O. Box 442 Baxley, Georgia 31513 W. M. Johnston Project Construction Manager Vogtle Nuclear Plant P. O. Box 282 Waynesboro, Georgia 30830 l
l
~~-
d UNITED STATES NUCLEAR REGULATORY COM!4ISSi.
OFFICE OF INSPECTION AND ENFORCE?ENT WASHINGTON, D.C.
20555 November 2h, 1978 IE Bulletin No.78-12A ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL kTLDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletin 78-12, issued on September 29, 2978, 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 velds of twelve identified reactor pressure vessels. Use of the atypical veld material in vessel veldrents 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 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 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 stypical veld materia 11:
1 The twelve nuclear units identified as having possible atypical pressure vessel veldments 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, Brovns Ferry Unit No. 1, Turkey Point Unit No. L and Zion Unit Nos. I and 2.
.1 of 2
IE Bulletin No.78-12A November 2L, 1978 1.
Provide all information available on veld materials used for each reactor vessel primary boundary ferritic weldment.2 (Items Ic, Id, 2a, 2b, first sentence of 2c, 3 and b 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 78-22. ) However, each licensee is required to verify that the veld materials information provided to the NRC l
under Item 2 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 l
2120 days of the date of this Bulletin supplement.
Reports should be submitted to the Director of the appropriate NEC 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, H180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
2 Weld material information submitted vill be evaluated by NBC. Requests for further information vill be dependent upon results of these evalua-tions. Additional requests or instructions vill be issued following these evaluations.
2 of 2
IE Bulletin No.78-12A Date: November 2L, 1978 LISTIIIG 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 OL or CP 78-02 Terminal Block 1/30/78 All Power Reactor Qualification Facilities with an OL or CP 78-03 Potential Explosive 2/8/78 All BW Power Gas Mixture Accumula-Reactor Facilities tions Associated with with an OL or CF BWR Offgas System Operations 78-OL Environmental quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit OL er CP Svitches Inside Reactor Containment 78-05 Malfunctioning of L/1L/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanise-General Model CR105X 78-06 Defective Cutlar-5/31/78 All Power Reactor Hanmer, 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 Roods OL, all class F and F Research Reartors with an OL, all Fue: Cycle Facilities with an OL, and all Priority 'l Material Licensees Page 1 of 2 l
l IE Bulletin No. 78 12A Date: November 2L, 1978 LISTING OF IE BULLETIUS l
I ISSUED In 1978 Bulletin Subject 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 Dryvell Leakage 6/lk/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Dryvell with an OL or CP Closures 78-10 Bergen-Pat erson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an OL or CP Spring Coils 78-22 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Facilities for Welds action:
Peach Botto 2 and 3.
Quad Cities 1 and 2, Hatch 2, Monti-cello and Vermont Yankee 7.12 Atypical Weld Material 9/29/78 All Power Reactor in Beactor Pressure Facilities with an yessel welds oL or CP 8-13 Failures in Source Heads 20/27/78 All General and of Key-Ray, Inc., Gauges Specific Licensees Models 7050, 70503, 7053 with Kay-Ray Gauges 7051B, 7060, 7060B, 7061 and To61B Page 2 of 2 j