ML19274E719
| ML19274E719 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/19/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W FLORIDA POWER CORP. |
| References | |
| NUDOCS 7904240079 | |
| Download: ML19274E719 (2) | |
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UNITED STATES g* "80&g NUCLEAR REGULATORY COMMISSION
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REOloN 11 101 M ARIETT A ETREET,N.W.
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ATLANTA, GEORGI A 30303 os.,...../
MAR 191979 In Reply Refer To:
RII:JPO 50-302 Florita Power Corporation Attn:
Mr. W. P. Stewart, Director Power Production P. O. Box 14042, Mail Stop C-4 St. Petersburb, Florida 33733 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, KQ k
James P. O'Reilly b
Director
Enclosures:
1.
List of IE Bulletins Issued in Last Twelve Months cc w/ encl:
G. P. Beatty, Jr.
Nuclear Plant Manager P. O. Box 1228 Crystal River, Florida 32629 q 904240 0 7 7 g
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UNITED STATES NU ' LEAR REGULATORY C0!O'ISSION OFFICL OF INSPECTION AND ENFORCEMENT WC HINGTON, D.C.
20555 March 19, 1979 IE Bulletin No.78-12B ATYPICAL WELD MATERIAL IN REACTOR FRESSURE VEFFEL WELDS Description of Circumstances:
This Bulletin is a supplenant to IE Bulletins 78-12 and 12A and all three documents must be collectively considered to provide an adeauate 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 canufacturers and suppliers to discuss the requirements of the bulletins. During these neetings, detailed interpretation of the data requirements was provided based on the manufacturer's respective methods of fabrication and record systems.
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 Holders:
This bulletin applies to all power reactor facilities with an operating license or a construction pernit, except those already identified as possibly having atypical veld material.
Responses to the requirements in Bulletins 78-12 and 12A shall be submitted in writing 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 subt ted by May 29, 197o. The licensee's response shall include al. 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. ATproval was given under a blanket clearance specifically for identified generic problems.
Page 1 of 1 7904020054
IE Bulletin No.78-12B March 19, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Date Issued Issued To Bulletin Subject No.
78-05 Malfunctioning of L/1h/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 Hammer, Type M Relays OL or CP With DC Coils 78-07 Protection afforded 6/12/78 All Power Reactor 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 fron 6/12/78 All Power and Research Beactor Fuel Element Transfer Facilities with a Tubes Fuel Element transfer tube and an OL, 78-09 BWR Dr/well Leakage 6/1L/79 All BWR Power Reactor Facilities Paths Associated with with an OL or CP Inadequate Dryvell Closures 78-10 Bergen-Paterson 6/27/78 All BWR Pover Beactor Facilities Hydraulic Shock vith an OL er CP Suppressor Accumulator Spring Coils Page 1 of 2
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IE Bulletin No.78-12B March 19, 1979 LISTING OF IE BUI,LETIN.R ISSUED IN LAST TWELVE MONTES Date Issued Issued To Bulletin Subject No.
7 8-11 Examination of Mark I 7/21/78 BWR Power Reactor Facilities for Containment Torus g
action: Peach Welds Botto: 2 and 3.
Quad Cities 1 and 2, Eatch 1, Monti-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 Faterial 11/2L/78 All Power Reactor Facilities with an in Reactor Pressure OL or CP Vessel Welds 78-13 Failures In Source Heads 10/27/78 All general and specific licensees of Kay-Ray, Inc., Gauges with the subject Models 7050, 7050B, 7051, Kay-Bay, Inc.
7051B, 7060, 7060s, 7061 gauges and 7061B 78-Ik Deterioration of Buna-N 12/19/78 All GE BVR facilities vith an OL or CP Components In ASCO Solenoids 79-01 Environmental Qualifica-2/8/79 All Power Peactor Facilities with an tion of Class IE Equipment 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 ASME SA-312 Type 30L OL or CF Stainless Steel Pipe r nufactured by Spoele a
You.g.;,vn Welding and Engineering Company Pnge 2 of 2 y
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