ML14174A675
| ML14174A675 | |
| Person / Time | |
|---|---|
| Site: | Robinson, Brunswick  |
| Issue date: | 02/05/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 7902280015 | |
| Download: ML14174A675 (6) | |
Text
R ft REOGU UNITED STATES A
(
o NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30303
-FEB 5 1979 In Reply Refer To:
RII:JPO 50-325, 50-324 50-261 Carolina Power and Light Company ATTN:
Mr.
J. A. Jones Executive Vice President Engineering, Construction and Operation 336 Fayetteville Street Raleigh, North Carolina 27602 Gentlemen:
Enclosed is IE Bulletin No. 79-01 which requires action by you with regard to your power reactor facility(ies) with an operating license.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely, James P. O'Reil y Director
Enclosures:
- 1.
- 2.
List of IE Bulletins Issued in the past 12 months 79022800 IS-
FEB 5 1979 Carolina Power and Light Company
-2 cc w/encl:
A. C. Tollison, Jr.
Plant Manager Box 458 Southport, North Carolina 28461 R. Parsons, Site Manager Shearon Harris Nuclear Power Plant P. 0. Box 101 New Hill, North Carolina 27562 R. B. Starkey, Plant Manager P. 0. Box 790 Hartsville, South Carolina 29550
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 February 5, 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 requested to examine installed safety related electrical equipment and determine 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 78-02) 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 response to Circular 78-08 have identified one component which licensees have found to be unqualified for LOCA environment service. 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 Arnold and Quad Cities 1 and 2 Nuclear Generating Stations. The unqualified switches are identified as NAMCO Models SL2-C-11, S3CML, SAl-31, SAl-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 licensee's 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 by IE Circular 78-08 dated May 31, 1978.
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IE Bulletin No. 79-01 February 5, 1979 Action to Be Taken By Licensees of All Power Reactor Facilities 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 available for review, identify your plans for determining qualification either by testing or engineering analysis or combination of these or by replacement with qualified equipment. Include your schedule for completing these actions and your justification for continued operation. Submit this information on items not having complete qualification data to the Director, Division of Reactor Operations Inspection, Office of Inspection and Enforcement, Nuclear Regulatory Commission, Washington, D.C. 20555 with a copy to the appropriate NRC Regional-Office within 120 days of receipt of this Bulletin.
- 4. Report any items which are identified as not meeting qualification requirements for service intended to the Director, Division of Operating Reactors, Office of Nuclear Reactor Regulation (NRC),
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 written report within 14 days of identification to NRR with a copy to the appropriate NRC Regional Office.
No additional written response to this IE Bulletin is required other than those 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.
IE Bulletin No. 79-01 February 5, 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 Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Hanner, 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 1 Material Licensees 78-08 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.
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IE Bulletin No. 79-01 February 5, 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 Power 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 78-12 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 Source Heads 10/27/78 All general and of Kay-Ray, Inc., Gauges specific licensees Models 7050, 7050B, 7051, with the subject 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B gauges 78-14 Deterioration of Buna-N 12/19/78 All GE BWR facilities Components In ASCO vith an OL or CP Solenoids Page 2 of 2