ML19274E721
| ML19274E721 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/19/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stampley N MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 7904240087 | |
| Download: ML19274E721 (2) | |
Text
s UNITED STATES
/* atD,0, NUCLEAR REGue.ATORY COMMISSION Q
REGloN 11 101 MARIETTA STREET, N.W.
- r E E
[
ATLANTA, oEoRGIA 30303 o
MAR 191979 In Reply Refer To:
RII:JPO 50-416, 50-417 Mississippi Power and Light Company Attn:
Mr. Norris L. Stampley Vice President of Production P. O. Box 1640 Jackson, Mississippi 39205 Gentlemen:
Enclosed is a supplement (IE Bulletin No.78-12B) to IE Bulletin No. 78-12 and 12A 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 of fice.
Sincerely, AD Y'
James P. O'Reilly b
Director
Enclosures:
1.
List of IE Bulletins Issued in Last Twelve Months cc w/ encl:
W. L. Nail, Plant Superintendent P. O. Box 756 Port Gibson, Mississippi 39150 q 90424 0 0 T7
UNITED STATES NUCLEAR REGULATORY C0!CISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 Merch ay, 1979 IE Bulletin No.78-12B ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VEESEL WELDS Description of Circumstances:
This Bulletin is a supplement to IE Bulletins 78-12 and 12A and all three documenos cust be collectively considered to provide an adeounte response to the bulletins.
Following the issuance of IE Bulletin 78-12A, cenbers of the Office of Inspection and Enforcement staff met with representatives from the reactor vessel manufacturers and suppliers to discuss the requirements of the bulletins. During theae neetings, detailed interpretation of the data requirements was provided based on the manufacturer's respective methods of fabrication and record systers.
Recognizing that the scope of the record review is extensive, additional time to respond to the bulletins is provided by this supplement.
Action to be Taken by Licensees and Percit Rolders:
This bulletin applies to all power reactor facilities with an operating license or a construction permit, except those already identified as possibly having atypical veld material.
Responses to the requirements in Bulletins 78-12 and 12A shall be submitted in vriting in accordance with the following schedule:
1.
Generic reports from each reactor vessel manufacturer shall be submitted to the NRC by May 1, 1979 2.
The licensee responses shall be submitted by May 29, 1979 The licensee's response shall include all of the specific vessel information required by the bulletins which is not covered by the vessel manufacturers generic report and shall indicate that the licensee is satisfied that the generic report adequately represents data for the specific vessels covered by the licensee's report.
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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\\/ tAf-7 9 0 4 0 2 0 0 5 t!
IE Bulletin No.78-12B March 19, 1979 LISTING OF IE BULLL7 INS ISSUED IN LAST Tr/ELVE MONTHS Date Issued Issued To Bulletin Subject No.
78-05 Malfunctioning of h/1L/78 All Power Reactor Facilities with an Circuit Breaker OL or CP Auxiliary Contact Mechanism-General Model CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Facilities with an Ha==er, Type M Relays OL or CP k'ith DC Coils 78-07 Protection afforded 6/12/78 All Power Beactor Facilities with an by Air-Line Respirators OL, all class E and F and Supplied-Air 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 Research Reactor Fuel Element Transfer Facilities with a Tubes Fuel Elecent transfer tube and an OL.
78-09 Bk'E Dryvell Leakage 6/1h/79 All Bh'R Power Reactor Facilities Paths Associated with with an OL or CP Inadequate Dryvell Closures 6/27/78 All BW'R Power 78-10 Bergen-Paterson Reactor Facilities Hydraulic Shock with an OL or CT Suppressor Accumulator Spring Coils Page 1 of 2
IE Bulletin No.78-12B March 19, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTES Date Issued Issued To Bulletin Subject No.
7 8-11 Exa=ination of Mark I 7/21/78 BWR Power Reactor Facilities for Contain=ent Torus g
action: Peach Welds Botto: 2 and 3.
Quad Cities 1 and 2, Hatch 1, Menti-cello and Vermont Yankee 78-12 Atypical Weld Material 9/29/78 All Power Reactor Facilities with an in Reactor Pressure OL or CP Vessel Welds78-12A Atypical Weld thterial 11/2h/78 All Power Reactor Facilities with an in Reactor Pressure OL or CP Vessel Welds 78-13 Failurer In Source Heads 10/27/78 All general and specific licensees of Kay-Bay, Inc., Gauges with the subject Models 7050, 70503, 7051, 7051B, 7060, 7060B, 7061 tiy-Ray, Inc.
gauges and 7061B 78-Ik Deterioration of Buna-N 12/19/T8 All GE BWR facilities vith an OL or CP Components In ASCO Solenoids 79-01 Environ = ental Qualifica-2/8/79 All Power Reactor Facilities with an tion of Class IE Equipnent OL or CP 79-02 Pipe Support Base Plate 3/2/79 All Power Reactor Facilities with an Designs Using Concrete OL cr CP Expansion Anchor Bolts 79-03 Longitudinal Weld Defects 3/12/79 All Power Reactor Facilities and an in ASKE SA-312 Type 30b OL or CP Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Co=pany Page 2 of 2
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