ML19331D515
| ML19331D515 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/15/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mcdonald R ALABAMA POWER CO. |
| References | |
| NUDOCS 8009030123 | |
| Download: ML19331D515 (1) | |
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'o UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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ATLANTA. GEORGIA 3o303 AUG 15 BB0 In Reply Refer To:
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q Alabama Power Company ATTN:
R. P. Mcdonald Vice President-Nuclear Generation P. O. Box 2641 Birmingham, AL 35291 Gentlemen:
Enclosed is Revision I to IE Bulletin No. 80-19. The revision merely clarifies the areas of concern; therefore, the actions including dates of reports required by you with respect to your nuclear power facility is not changed.
In order to assist the NRC in evaluating the value/ impact of each Bulletin on licensees, it would be helpful if you would provide an estimate of the manpower expended in conduct of the review and preparation of the report (s) required by the Bulletin. Please estimate sepa rately the manpower associated with corrective actions necessary following identifiotion of problems through the Bulletin.
Should you have any questions regarding the revised Bulletin or actions required by you, please contact this office.
Sincerely, WD QMA
~
James P. O'Reill Director
Enclosures:
1.
IE Bulletin No. 80-19, Revision 1 2.
List Recently Issued IE Bulletins cc w/ encl:
A. R. Barton, Executive Vice President F. L. Clayton, Jr., Senior Vice President H. O. Thrash, Manager-Nuclear Generation O. D. Kingsley, Jr., Manager, Nuclear Engineering and Technical Services J. W. McGowan, Manager-Operations Quality Assurance W. G. Hairston, III, Plant Manager W. C. Petty, Manager-Quality Assurance (Design and Construction)
R. E. Hollands, Jr., QA Supervisor 8009030 g_3
SSINS No.: 6820 UNITED STATES Accession No.:
~4 NUCLEAR REGULATORY COMMISSION 8006190052 0FFICE OF INSPECTION AND EhTORCEMEhT WASHINGTON, D.C.
20555 August 15, 1980 IE Bulletin No. 80-19 a.
Revision 1
. FAILURES OF MERCURY-WETTED MATRIX RELAYS IN REACTOR PROTECTIVE SYSTF.MS OF OPERATING NUCLEAR P0hER PLANTS DESIGNED BY COMBUSTION ENGIhT.ERING BACKGROUND:
This bulletin addresses the failures of mercury-wetted relays used in the logic matrix of the reactor protective system (RPS) of nuclear power plants designed by Combustion Engineering (C-E). Except for Arkansas Nuclear One Unit 2 and Palisades, both of which use dry-contact matrix relays, the NRC understands that all other operating C-E plants use C.P. Clare Model HG2X-1011
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mercury-wetted matrix relays in the RPS.
Mercury-wetted matrix relaya manufactured by the Adams and Westlake Company were initially used in the Falisades plant; however, because of repeated failures of these relays, they were subsequently replaced with relays having d ry-conta cts.
GTE, the manuf acturer of these dry-contact relays, however, has since discontinued their production. Thus, although the dry-contact relays used at Palisades have performed without a failure since they were installed, they are not available for the other operating nuclear power plants designed by C-E.
OPERATING EXPERIENCES AND EVALUATION:
To date, operating nuclear power plants designed by C-E have reported thirty-one (31) failur s of mercury-wetted relays used in the logic matrix of the RPS.
Most of the reported failures were " failed-closed" type (i.e., the type that l
could inhibit a reactor trip), and four of the reported events involved multi-ple failures (i.e., three relay failures were detected during two tests; two l
other failures were detected during two different tests). Because of the re-dundancy within the RPS, no reported event would have prevented a reactor trip; however, the build-up of coincident " failed-closed" failures of certain sets of relays could result in trip failures for off-normal events.
The number of single and multiple relay failures reported gives rise to two (1) the total number of failures yields a much higher random failure concerns:
l rate than that used in other relsy failure estimates *, and (2) the number of
- Other relay failure estimates include (1) WASH-1400, " Reactor Safety Study",
NRC, October 1975; (2) IEEE Std 500-1977,"IEEE Guide to the Collection and Presentation of Electrical, Electronic, and Sensing Component Reliability Data for Nucleer Power Generating Stations", IEEE, New York;' and (3) NUREG/
CR-0942, " Nuclear P] ant Reliability Data System, 1978 Annual Reports of Cumulative Syste4 and Component Reliability", NRC.
IE Bulletin No. 80-19, Revision 1 August 15, 1980 Page 2 of 2 multiple failures detected suggests the presence of a common-mode failure mechanism.
Such a common-mode failure mechanism could result in the build-up of specific " failed-closed" failures which, in turn, could result in antici-pated transients without scram (ATWS). Thus, the relatively high random
'faflure rate and the suggested common-mode failure mechanism, indicate that
- plants using mercury-wetted matrix relays in the RPS are more susceptible to scram failures than predicted in other studies.
i ACTIONS TO BE TAKEN BY HOLDERS OF CONSTRUCTION PERMITS OR OPERATING LICENSES FOR NUCLEAR POWER FACILITIES:
1.
Review your facility to determine whether C.P. Clare Model HG2X-1011 R1 mercury-wetted relays are used in the logic matrix of the RPS.
If R1 no such relays are used, you should submit a negative declaration to this effect and you need not respond to the remaining items in this bulletin. Your negative declaration shall be submitted to the appropriate NRC regional office within thirty (30) days of the date of this bulletin
'and a copy forwarded to the Director, Division of Reactor Operations Inspection, Office of Inspection and Enforcement, NRC, Washington, D. C. 20555.
2.
Licensees of operating facilities usinE the above relays in the logic R1 matrix of the RPS should increase the frequency of their surveillance R1 Until further notice, or until the mercury-wetted relays have tests.
been replaced with qualified relays of a different design, surveillance testing of the relays shall be initiated within ten (10) days of the date of this bulletin and repeated at intervals not exceeding ten (10) days thereafter.
The additional surveillance testing applies when operability R1 of the RPS is required by the Technical Specification. Upon detecting a R1 failed relay, the failed unit shall be replaced with a qualified dry-contact relay or a new mercury-wetted relay.
(The removed relay shall not be reused in the RPS.)
l 3.
Nuclear power facilities which are using or whose design includes the use l
of the above relays in the logic matrix of the RPS shall submit either R1 their plans and schedules for replacing the mercury-wetted relays with qualified relays of a different design, or justification for using the mercury-wetted relays. Responses to this item shall be submitted to the offices listed in Item 1, above, within ninety (90) days of the date of the original version of this bulletin, July 30, 1980.
R1 Approved by GAO, B180225 (R0072); clearance expires July 31, 1980.
(Application for renewal pending before GAO.) Approval was given under a blanket clearance specifically for identified generic problems.
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IE Bulletin No. 80-19, Revision 1 Enclosure August 15, 1980 RECENTLY ISSLED IE BULLETINS Bulletin Subject Date issued Issued To No.
80-19 Failures of Mercury-8/15/80 All nuclear power
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R*ev. 1 Wetted Matrix Relays in facilities having Reactor Protective Systems either an OL or a CP of Operating Nuclear Power Plants Designed by Combus-tion Engineering 80-20 Failures of Westinghouse 7/31/80 To each nuclear Type W-2 Spring Return power facility in to Neutral Control Switches your region having an OL or a CP 80-19 Failures of Mercury-7/31/80 All nuclear power Wetted Matrix Relays in facilities having Reactor Protective Systems either an OL or a CP of Operating Nuclear Power Plants Designed by Combus-tion Engineering 80-18 Maintenance of Adequate 7/24/80 All PWR power reactor Minin'um Flow Thru Centrifugal facilities holding OLs Charging Pumps Following and to those PWRs Secondary Side High Energy nearing licensing Line Rupture Supplement 2 Failures Revealed by 7/22/80 All BWR power reactor to 80-17 Testing Subsequent to facilities holding OLs Failure of Control Rods to Insert During a Scram at a BWR Supplement 1 Failure of Control Rods 7/18/80 All BWR power reactor to 80-77 to Insert Juring a Scram facilities holding OLs at a BWR 80-17 Failure of Control Rods 7/3/80 All BWR power reactor to Insert During a Scram facilities holding OLs at a BWR 80-16 Potential Misapplication of 6/27/80 All Power Reactor Rosemount Inc., Models 1151 Facilities with an and 1152 Pressure Transmitters OL cr a CP with Either "A" or "D" Output Codes 80-15 Possible Loss Of Hotline 6/18/80 All nuclear facilities With Loss Of Off-Site Power holding OLs
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