ML17174A008
| ML17174A008 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Dresden, Browns Ferry, Salem, Indian Point, Cooper, Brunswick, Surry, North Anna, Vermont Yankee, Fort Calhoun |
| Issue date: | 06/28/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7909130056 | |
| Download: ML17174A008 (7) | |
Text
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JUH 2 81979 e D6cJc.v
- Sb~~L\\°l ME1't>RANDUM FOR:
B. Grimes, Assistant Director for Systems and Engineering, Division of Operating Reactors FROM:
G. Lainas, Chief, Plant Systems Branch, Division of Operating Reactors
SUBJECT:
- sTATUS OF PSB REVIEWS IN CONNECTION WITH LICENSEE's...____
RESPONSES TO IE BULLETIN 79-01 IE Bulletin 79-01 requires that all licensees review the enviT'.IOnnental qualification of electrical equipment installed in their plants and report the results to the NRC within 120 days of receipt of the Bulletin.
The bulletin further requires that any items of equipment found to be unqualified must be reported to the Director of the Division ~f Operating Reactors within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If plant operation.is to continue with the unqualified equipment, a safety basis must be included in the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report.
The purpose of this memorandum is to provide you with the status of our reviews in connection with the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notifications
- received to date.
'There have been 19 separate reports of equipment which the licensees believe may not be qualified to perform its safety function in an accident environment.
Each of these reports was reviewed by PSB and a detennination was made as.to whether the proposed resolution, including the bases for continued operation, where appropriate, was acceptable.
These detenninations were made in consultation with the DOR Project Managers and where necessary additional information was requested via telephone and telecopy from the licensees.
A sUJTmary of the status of all these reviews is provided 1n Enclosure 1.
With the exception of item 4 of Enclos*ure 1, all our reviews are complete and we have achieved a satisfactory resolution with the licensees.
In the case of i tern 4 (stem mounted 1 imi t switches on MS IV' s at Browns Ferry Units 1, 2 & 3), TVA does not propose to replace the unqualified limit switches.
While we do not believe that there is any irrrnediate hazard to the health and safety of the public we do believe that several conditions must be satisfied if the switches are not replaced. These conditions ar~ set forth in our memorandum to T. Ippolito dated June 6, 1979 (see Enclosure 2).
7 9091soC>r;-*h..
As the licensee reviews required in connection with IE Bulletin 79-01 continue. we expect to receive additional reports of equipment considered to be unqualified for its accident environrrent.
We will evaluate these reports immediately and update Enclosure 1 at appropriate intervals.
Con.tact:
E. Butcher, X28077
Enclosures:
As stated cc. w/encl osure:
- 0. Eisenhut S. Hanauer G. Lainas R. Satterfield V. Moore V. Thomas
- 0. Tandi E. Butcher
- OOR Branch Chiefs PSB Section A DOR AD's E. Jordan o.?1~
~- Lainas, Chief Plant Systems Branch Division of Operating Reactors
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