ML19263C300
| ML19263C300 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/08/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | John Miller GEORGIA POWER CO. |
| References | |
| NUDOCS 7902210163 | |
| Download: ML19263C300 (2) | |
Text
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bg UNITED STATES km Riouq'o, NUCLEAR REGULATORY COMMISSION a
REGION 11 3.p o
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101 MARIETTA STREET N.W.
f ATLANTA, GEORGIA 30303 is
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E t.m In Reply Refer To:
RII:JPO 50-321, 50-366 Georgia Power Company Attn:
Mr. J. H. Miller, Jr.
Executive Vice President 270 Peacntree Street, N. W.
Atlanta, Georgia 30303 Gentlenen:
Enclosed is IE Bulletin 79-01.
It requires action by you with regard to power reactor facilities with an operating license except for the 11 SEP plants which are listed in Enclosure 3.
This Bulletin is also being sent for information to the il SEP plants and all power reactor facilities with a construction permit.
No action or written response is required for construction permit facilities or the 11 SEP plants.
Should you have quest, ions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely, W
Q NV h%m.-
James P. O'Reilly
^ % irector
Enclosures:
1.
List of IE Bulletins Issued in the past 12 months 3.
List of SEP Plants (11) 7902210Ki3
TF T.
" 17%
t Georgia Power Company cc w/ encl:
K. M. Gillespie Construction Project Manager Plant E. I. Hatch P. O. Box 439 Baxley, Georgia 31513 M. Manry, Plant Manager Plant E. I. Hatch P. O. Box 442 Baxley, Georgia 31513 E. D. Groover QA Site Supervisor Vogtle Nuclear Plant P. O. Box 282 Waynesboro, Georgia 30830 4
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 February 8, 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 78-0C was much broader than other previously issued Bulletins and Circulars (such so 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 IE Circular 78-08 have identified one component which licensaes 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 et both Duane Arnold and Quad Cities 1 and 2 Nuclear Generating Stations.
The unqualified switches are identified as NAMCO Models SL2-C-11, S}C1!L, sal-31, sal-32, D1200j,
EA-700 and EA-770 switches. According to the manufacturer, these switches are designed < nly for general purpose applications and are not considered suitable devit es for service in the LOCA environment. Consequently, switches are being replaced at the above power plants with qualified components.
Also, NFC 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 by 1E Circular 78-08 dated May 31, 1978.
Page 1 of 3
.6.m- -
r IE Bulletin No. 79-01 February 8, 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 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 opera tion.
Submit this information to the Director, Division of Reactor Opera-tions Inspection, Office of Inspection and Enforcement, Nuclear Regulatory Com=ission, Washington, D.C.
20555 with a copy to the appropriate NRC Regional Of fice 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, Nuclear Regulatory Commission, 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 Of fice.
- 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 metteds such as sequential, synergistic, etc., and 5) identification of the specific supporting qualification documentation.
Page 2 of 3 l
IE Bulle.in No. 79-01 February 8, 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 problems.
IE Bulletin No. 79-01 February 8,109 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subj ect 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 Malfunct13ning of 4/14/78 All Power Reactor Circuit B eaker Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR105X 76-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type 11 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 Licenstes 78- 08 Radiation Levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor Tube s Facilities with a Fuel Element transfer tube and an OL.
Page 1 of 2
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IE Bulletin No. 79-01 February 8, 1979 LISTING OF IE BULLLTINS ISSUED IN LAST TWELVE MONTHS Bulletin Subj ect 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 with an OL or CP Solenoids Page 2 of 2
Enclosure No. 3 SEP Plants i
Plant Red on III Dresden 1 I
Yankee Rove
8 III Big Rock Point 9-1 V
San Onofre 1 Haddam Neck I
III Lacrosse I
Oyster Creek
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I R. E. Ginna III c;
Dresden 2 I
Millstone III Palisades
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