ML19209B937
| ML19209B937 | |
| Person / Time | |
|---|---|
| Site: | Catawba, Perkins, Cherokee  |
| Issue date: | 09/17/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dail L DUKE POWER CO. |
| References | |
| NUDOCS 7910110242 | |
| Download: ML19209B937 (1) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION n
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REGION 11 o
101 MARlETTA ST., N.W., SUITE 3100 o
ATLANTA, GEORGIA 30303 SEP 171979 In Reply Refer To:
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A Duke Power Company Attn:
L. C. Dail, Vice President Design Engineering P. O. Box 33189 Charlotte, North Carolina 28242 Gentlemen:
The enclosed Information Notice provides information with regard tc a potential unreviewed safety question involving high energy lines and control systems.
Sincerely,
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James
'Rei y Director
Enclosures:
- 2. List of IE Information Notices Issued in the Last Six Months
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+1133 271 7910110242 U4LM
SEP 171979 Duke Power Company.
cc w/ encl:
D. G. Beam, Project Manager Post Office Box 223 Clover, South Carolina 29710 J. T. Moore, Project Manager Post Office Box 422 Gaffney, South Carolina 29340 4 7m
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Accession No: 79082201B-SSINS:
6870 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 September 14, 1979 IE Information Notice No. 79-22 QUALIFICATION OF CONTROL SYSTEMS Public Service Electric and Gas Crwpany notified the NRC of a potential unreviewed safety question at their Salem Unit i facility. This notification was based on a continuing review by Westinghouse of the environmental qualificat'.ons of equipment that they supply for nuclear steam supply systems.
Based on the present status of this effort, Westinghouse has informed their customers that the performance of non-safety grade equipment subjected to an adverse environment could impact the protective functions performed by safety grade equipment.
These non-safety grade systems include:
Steam generator power operated relief valve control system Pressurizer power operated relief valve control system Main feedwater control system Automatic rod control system These systems could potentially malfunction due to a high energy line break inside or outside of containment. NRC is also concerned that the adverse environment could also give erroneous information to the plant operators.
Westinghouse states that the consequences of such an event could possibly be more limiting than results presented in Safety Analysis Reports, however, Westinghouse also states that the severity of the results can be limited by operator actions together with operating characterisitics of the safety systems. Further, Westinghouse has recommended to their customers that they review their systems to determine whether any unreviewed safety questions exist.
This Information Notice is provided as an early notification of a possibly significant matter. It is expected that recipients will review the information for possible applicability to their facilities. No specific action or response is requested at this time. If NRC evaluations;<so indicate, further licensee actions may be requested or required.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
No written response to this Information Notice is required.
s.
IE Information Notice No. 79-22 Enclosure September 17, 1979 Page 1 of 2 LISTING OF IE INFORMATION NOTICES ISSUED IN LAST SIX MONTHS Information Subject Date Issued To Notice No.
Issued 79-22 Qualification of Control 9/17/79 All Holders of cps Systems 9/14/79 All Holders of OLs 79-21 Transportation and Commer-9/11/79 All Licensees as Supple-cial Burial of Radioactive mental Information to Materials IE Bulletin Nos. 79-19
& 79-20 79-20 NRC Enforcement Policy 9/7/79 All Holders of Reactor (Rev. 1)
NRC Licensed Individuals OLs and cps and Production Licensees with Licensed Operators 79-20 NRC Enforcement Policy 8/14/79 All Holders of Reactor NRC Licensed Individuals OLs and cps and Production Licensees with Licensed Operators 79-19 Pipe Cracks in Stagnant 7/18/79 All Holders of Reactor (Correction - Borated Water Systems at OLs and cps Enclosure)
PWR Plants 79-19 Pipe Cracks In Stagnant 7/17/79 All Holders of Reactor Borated Water Systems At OLs and cps PWR Plants 79-18 Skylab Reentry 7/6/79 All Holders of Reactor OLs 79-17 Source Holder Assembly Damage 6/20/79 All Holders of Reactor Damage From Hisfit Between OLs and cps Assembly and Reactor Upper Grid Plate 79-16 Nuclear Incident at Three 6/2$/79 All Research Reactors Mile Island and Test Reactors with OLs 79-15 Deficient Procedures 6/7/79 All Holders of Reactor
' OLs and cps 79-14 NRC Position of Electrical 6/11/79 All Power Reactor Cable Support Systems Facilities with a CP 1130 274
IE Information Notice No. 79-22 Enclosure September 17, 1979 Page 2 of 2 LISTING OF INFORMATION NOTICES ISSUED IN LAST SIX MONTHS Information Subject Date Issued To Notice No.
Issued 79-13 Indication of Low Water 5/29/79 All Holders of Reactor Level in the Oyster Creek OLs and cps Reactor 79-12 Attempted Damage to New 5/10/79 All Fuel Facilities Fuel Assemblies Research Reactors, and Power Reactors with an OL or CP 79-11 T,ower Reactor Vessel Head 5/7/79 All holders of Reactor Insulation Support Problem OLs and cps 79-10 Nonconforming Pipe 4/16/79 All power reactor Support Struts facilities with a CP 9
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