ML19274D648
| ML19274D648 | |
| Person / Time | |
|---|---|
| Issue date: | 02/09/1979 |
| From: | Pappas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 7902210219 | |
| Download: ML19274D648 (3) | |
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FEB 12 379 State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jefferson Street Springfield, IL 62761 Gentlemen:
The enclosed IE Bulletin No. 79-01 titled " Environmental Qualifi-cation of Class IE Equipment" was sent to the following licensees on February 9, 1979, for action and information:
ACTION American Electric Power Service Corporation India.ia and Michigan Power Company D.
C. Cook, 1, 2 (50-315, 50-316)
Commonwealth Edison Company Dresden 3 (50-249)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Iowa Electric Light & Power Company Duane Arnold (50-331)
Northern States Power Company Monticello (50-263)
Prairie Island 1, 2 (50-282, 50-306)
Toledo Edison Company Davis-Besse 1 (50-346)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305)
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State of Illinois FEB 12 379 INFORMATION Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457)
Byron 1, 2 (50-454, 50-455)
Dresden 1, 2 (50-10, 50-237)
La Salle 1, 2 (50-373, 50-374)
Consumers Power Company Big Rock Point (50-155)
Midland 1, 2 (50-329, 50-330)
Palisades (50-255)
Dairyland Power Cooperative LACBWR (50-409)
Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462)
Northern Indiana Public Service Company Bailly (50-367)
Northern States Power Company Tyrone Energy Park 1 (50-484)
Public Service of Indiana M tble Hill 1, 2 (50-546, 50-547)
State of Illinois FEB 12.379 Union P.lectric Company Callavay 1, 2 (50-483, 50-486)
Sincerely,
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M1 J
8 Helen Pappas, Chief Administrative Branch
Enclosures:
1.
List of IE Bulletins Issued in the past 12 months 3.
List of SEP Plants (11) cc w/encls:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction Unit NRC 20b PDR Local PDR NSIC TIC
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III February 9,1979 IE Bulletin No. 79-01 ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Description of Circumstances:
The intent of IE Circular 78-08 was to highlight to all licensees important lessons learned from environmental qualification deficiencies reported by individual licensees.
In this regard, licensees were recucsted to examine installed safety-related electrical equipment anc deterinine that proper documentation existed which provided assurance that this equipment would function under postulated accident conditions.
The scope of IE Circular 78-08 was much broader than other previously issued Bulletins and Circulars (such as IEB 78-04 and IEB 76-02) which addressed specific component failures.
The intent of this Bulletin is to raise the threshold of IE Circular 78-08 to the level of a Bulletin; i.e., action requiring a licensee response.
Inspections conducted to date by the NRC of licensees' activities in rest inse to IE Circular 78-08 have identified one component which licensees have found to be unqualified for service within the LOCA environment.
Specificially, unqualified stem mounted limit switches (SMLS), other than those identified in previously issued IE Bulletin 78-04, were found to be installed on safety-related valves inside containment at both Duane Amold and Quad Cities 1 and 2 Nuclear Generating Stations.
The unqualified switches are identified as NAMCO Models SL2-C-11, S3CML, sal-31. SA1-32, D1200j, EA-700 and EA-770 switches. According to the manufacturer, these switches are designed only for general purpose applications and are not considered suitable devices for service in the LOCA environment.
Consequently, switches are being replaced at the above power plants with qualified components.
Also. NRC inspection of component qualification has identified equipment which does not have documentation indicating it is qualified for the LOCA environment.
The inspections have also identified that the licensees' re-review and resolution of problem areas are not receiving the level of attention from all licensees which the NRC believes is warranted.
Because of the protracted schedule for completion of the re-review, we are now requesting the power reactor facilities with operating licenses to expedite completion of their re-review program originally requested 17 IE Circular 78-08 dated May 31, 1978.
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IE Bulletin No. 79-01 February 9, 1979 Action to Be Taken By Licensees of All Power Reactor Facilities (Except Those 11 SEP Plants Listed on Enclosure 3) With An Operating License:
1.
Complete the re-review program described in IE Circular 78-08 within 120 days of receipt of this Bulletin.
2.
Determine if the types of stem mounted limit switches described above are being used or planned for use on safety-related valves which are located inside containment at your facility.
If so, provide a written report to the NRC within the time frame specified and to the address specified in Item 4 below.
3.
Provide written evidence of the qualification of electrical equipment required to function under accident conditions.* For those items not having complete qualification data avai!3ble for revies, identify your plans for determining qualification, either by testing or engineering analysis, or contination of these, or by replacement with qualified equipment.
Include your schedule for completing these actions and your justification for continued operation.
Submit this information to the Director, Division of Reactor Opera-tions Inspection. Office of Inspection and Enforcement, Nuclear Regulatory Comission Washington, D.C.
20555 with a copy to the appropriate NRC Regional Office within 120 days of receipt of this Bulletin.
4.
Report any it' ems which are identified as not meeting qualification requirements for service intended to the Director, Division of Operating Reactors, Office of Nuclear Reactor Regulation, Nuclear Regulatory Comission. Washington, D.C.
20555 with a copy to the appropriate NRC Regional Office within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of identification.
If plant operation is to continue following identification, provide justification for such operation.
Provide a detailed written report within 14 days of identification to NRR, with a copy to the appro-priate NRC Regional Office.
- This written evidence should include: 1) component description;
- 2) description of the accident environment; 3) the environment to which the component or equipment is qualified; 4) the manner of qualification which should include test methods such as sequential, synergistic, etc., and 5) identification of the specific supporting qualification documentation.
IE Bulletin No. 79-01 February 9,1979 No additional written response to this IE Bulletin is required other than those responses described above.
NRC inspectors will continue to monitor the licensees' progress in completing the requested action described above.
If additional information is required, contact the Director of the appropriate NRC Regional Office.
Approved by GAO B180225 (R0072); clearance expires 7/31/80.. Approval was given under a blanket clearance specifically for identified generic probl ems.
~_
IE Bulletin No. 79-01 February 9,1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
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 78-04 Environmental Quali-2/21/78 All Power Reactor fication of Certain Facilities with an Stem Mounted Limit OL or CP Switches Inside Reactor Containment 78-05 Malfunctioning of.
4/14/78 All Power Reacter Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanism-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 P.espirators 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 1 Material Licensees 78 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.
Page 1 of 2
IE Bulletin No. 79-01 February 9, 1979 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
78-09 BWR Drywell Leakage 6/14/78 All BWR Pcwer Paths Associated with Reactor Facilities Inadequate Drywell with an OL or CP Closures 78-10 Bergen-Paterson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an OL or CP Spring Coils 78-11 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 1, Monti-cello and Vermont Yankee 78 '2_
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~ P&xer Reactor in Reactor: Pressure Facilities with an Vessel Welds -
OL or-CP 78-13 Failures In Source Heads-10/27/78 All pneral and of Kay-Ray, Inc... Gauges ~
specific licensees Models s7050,.7050B,.7051, with the subject 7051B;.7060. 70608, 7061 '
Kay-Ray, Inc, and 70618 gauges 78-14' Deterioration of Duna-N 12/19/78 All GE BWR facilities Components In ASCO' with an OL.or CP Solenoids Page 2 of 2 1:
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SEP Plants Plant Regi,
~
Dresden 1 III Yankee'Rowe I
Big Rock Point III San Onofre 1 Y
Haddam Neck I
Lacrosse III Oyster Creek I
R. E. Ginna I
Dresden 2 III Millstone I
Palisades III Page 1 of 1
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