ML19274E727
| ML19274E727 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/19/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 7904240160 | |
| Download: ML19274E727 (1) | |
Text
m UNITED STATES fg*M49 NUCLEAR REGULATORY COMMISSION i ( ) c(
3 REGION I g '," f
-l 3
631,AR K AVENUE Kma or enussi A renusvt.VANI A 19406 March 19, 1979 Docket Nos. 50-277 50-278 Philadelphia Electric Company ATTN: Mr. S. L. 6 ltroff Vice Presicent Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:
Enclosed is a supplement (IE Bulletin No.78-128) to IE Bulletin Nos.
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.
A written response is required.
Should you have any questions regarding tais Bulletin or the actions required by you, please contact this office.
Sincerely, udf Boyce H. Grier Director
Enclosures:
1.
IE Bulletin 78-12B 2.
List of IE Bulletins Issued in Last Twelve Months cc w/encis:
W. T. Ullrich, Station Superintendent Troy B. Conner, Jr., Esquire Eugene J. Bradley, Esquire Raymond L. Hovis, Esquire Warren Rich, Esquire 7004240160
~
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No.78-128 Date: March 19, 1979 Page 1 of 1 ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS Description of Circumstances:
This bulletin is a supplement to IE Bulletins 78-12 and 12A and all three documents must be collectively considered to provide an adequate response to the bulletins.
Following the issuance of IE Bulletin 78-12A, members 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 these meetings, 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 Permit Holders:
This bulletin applies to all power reactor facilities with an operating license or a construction permit, except those already identified as possibly having atypical weld 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 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.
g 7904020054
IE Bulletin No.78-12B Date: March 19, 1979 Page 1 of 3 LISTING 0F IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operating License Mechanism - General (0L) or Construction Electric Model CR105X Permit (CP) 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 E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority I Material Licensees 78-08 Radiation Levels from 6/12/78 All Power, Test and Fuel Element Transfer Research Reactor Tubes Facilities with an OL having Fuel Element Transfer Tubes 78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequata Drywell with an OL (for action)
Closures or CP (for information) 78-10 Bergen-Paterson 6/27/78 All BWR Power Reactor Hydraulic Shock Facilities with Suppressor Accumulator an OL or CP Spring Coils
March 19, 1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED)
Bulletin Subject Date Issued Issued To No.
78-11 Examination of Mark I 7/24/78 BWR Power Reactor Containment Torus Facilities with an OL Welds for action:
Peach Bottom 2 and 3, Duad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee. All other BWR Power Reactor Facilities with an OL for information 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-13 Failures In Sc'irce Heads 10/27/78 All General and of Kay-Ray, Inc., Gauges Specific Licensees Models 7050, 70508, 7051, with the subject 70518, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B Gauges 78-14 Deterioration of Buna-N 12/19/78 All BWR Power Reactor Components In ASCO Facilities with an OL Solenoids (foraction),andall other Power Reactor Facilities with an OL or CP (for information) 79-01 Environmental Qualifica-2/8/79 All Power Reactor tion of Class IE Equipment Facilities with an OL, except the 11 Systematic Evaluation Program Plants (for action), and all other Power Reactor Facilities with an OL or CP (for in-formation)
IE Bulletin No.78-12B Date: March 19, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED)
Bulletin Subject Date Issued Issued to No.
79-02 Pipe Sapport Base Plate 3/8/79 All Power Reactor Design Using Concrete Facilities with Expansion Anchor Bolts an OL or CP 79-03 Longitudinal Weld Defects 3/12/79 All Power Reactor in ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe OL or CP Spools Manufactured by Youngstown Welding and Engineering Company