ML20062E138
| ML20062E138 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/24/1978 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W FLORIDA POWER CORP. |
| References | |
| NUDOCS 7812040306 | |
| Download: ML20062E138 (1) | |
Text
.
=.
((
9tf UNITED sT ATEs ska MGoq'o,
,,,gg 4 l NUCLEAR REGULATORY COMMISSION
/
REGloN 11 3
s, f, o
2 g
ATLANTA, GEORGI A 30303 f
...+
NOV 2 41973 In Reply Refer To:
RII:JPO 50-302 Florida Power Corporation Attn:
Mr. W. P. Stewart, Directcr Power Production P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 GeEtlemen:
Enclosed is a supplement (IE Bulletin No.78-12A) tc. 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, f.c %.00--
p mes P. O'Reilly D rector
Enclosures:
1.
IE Bulletin 78-12A 2.
List of IE Bulletins r
Issued in 1978 7-k cc c./ encl:
G. P. Beatty, Jr.
c Nuclear Plant Manager i
P. O. Box 1228 i
Crystal River, Florida 32629 l
3812 0 4 9 g(g l
h
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEENT WASHINGTON, D.C.
20555 Nove=ber 2h, 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 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 veldments causes them to have higher than normal nil-ductility transition te=perature characteristics which in turn requires more conservative pressure /te=pera-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 atypical veld material 1:
1 The twelve nuclear units identified as having possible atypical pressure vessel veldments are: Three Mile Island Unit Nos. 1 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. k and Zion Unit Nos. I and 2.
1 of 2
--e v
w---
IE Bulletin No.78-12A November 2k, 1978 1.
Provide all information available on veld =aterials used for each reactor vessel primary boundary ferritic weld =ent.2 (Ite=s 1c, id, 2a, 2b, first sentence of 2c, 3 and h 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 weld =ents in specific vessels is not required at this time.
(Last sentence of Ite= 2c, Bulletin 78.12. ) However, each licensee is required to verify that the veld materials information provided to the NRC under Ite=;l does in fact cover each reactor vessel for which the 31censee is responsible.
3.
Responses to ite: 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 Cc==ission, Office of Inspection and Enforcement, Division of Reactor Construction Inspection, Washington, D.C.
20555 Approved by GAO, B180225 (R0072); clearance expires 7/31/d0. Approval was given under a blanket clearance specifically for identified generic problems.
1 2
Weld material information sub=1tted 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 folleving these evaluations.
2 of 2
IE Bulletin No.78-12A Date: Nove=ber 2k, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.
78-01 Fla==alale Contact -
1/16/78 All Power Reactor Arm Retainers in G.E.
Facilities with an CR120A Relays OL or CP 73-02 Terminal Block 1/30/78 All Power 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 Operations 78-Oh Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Li=it OL or CP Switches Inside Reactor Containment 78-05 Malfunctioning of h/1k/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Nechanis=-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 Protecticn afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all class E and F Research Reseters with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees Page 1 of 2
~
IE Bulletin No. 78 12A Date: November 2L, 1978 LISTING OF IE BULLETINS ISSUED IN 1978 Bulletin Subject Date Issued Issued To No.
78-08 Radiation Levels from 6/12/78 All Power and Fuel Ele =ent Transfer Research Reactor Tubes Facilities with a Fuel Element transfer tube and an OL.
78-09 BWR Dryvell Leakage 6/2h/78 All BWR Pcwer Paths Associated with Reactor Facilities Inadequate Dmell 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 78-11 Examination of Mark I 7/21/78 BWR fover Reactor Containment Torus Facilities for Welds action:
Peach Botte= 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee 7-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an yessel Welds oL or CP 8-13 Failures in Source Heads 10/27/78 '
Specific Licensees All General and of Kay-Ray, Inc., Gauges Models 7050, 7050B, 7051 with Kay-Ray Gauges 70513, 7060, 7060B, 7061 and 7061B Page 2 of 2
..