View source for L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl

{{Adams
| number = ML20072S373
| issue date = 01/04/1991
| title = Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl
| author name = Toelle S
| author affiliation = ASEA BROWN BOVERI, INC.
| addressee name = Murley T
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000317, 05000318, 05000335, 05000336, 05000361, 05000362, 05000368, 05000382, 05000389
| license number = 
| contact person = 
| case reference number = REF-PT21-91
| document report number = L-91-002, L-91-2, NUDOCS 9104150164
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 2
}}

=Text=
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A$f A BROWN DCrM January 4, 1991 LD 91-002 Dr. Thomas E. Murley, Director                                                                           l Of fice of Nuclear React.or Regulation Attn Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20553

==Subject:==
General Electric Reactor Trip Breakers

==Reference:==
Letter, E. T. Boulette (MY) to USNRC, MN-90-130
 ,        ,                          (ETB-90-109) dated December 28, 1990

==Dear Dr. Murley:==

This letter provides additional information regarding a 10 CFR 21 report made by Maine Yankee concerning General Electric reactor trip breakers (Reference).
Combustion Engineering has supplied other utilities with General Electric reactor trip breakers for use in safety grade equipment similar to that identified by Maine Yankee.
These utilities are listed in the Enclosure to this letter.
The information provided includes the basic component supplied and its function. This is consistent with the'10 CFR 21 requirement to identify the facility, the activity, or the basic component for such facility or such activity.
If you have any-questions on the above, please feel free to contact me or Mr. Mario Robles of my staff at (203) 285-5215.
Very truly yours, COMBUSTION ENGINEERING, INC.
L                                                                                                 _   /1 L                                                                          5. B.                    / / '
S. A. Toelle Manager Operating Reactor Licensing l                      SAT:lw l                      

==Enclosure:==
As Stated ABB Comt;ustion Engineering Nuclear Power q        _
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Enclosure to                                  ^
LD 91002 Supplemental Information Concerning General Electric Reactor Trip Breaker                                                                  ,
Utility                               flant                 . hiodd         Function                             System Baltimore Gas                          Calvert Cliffs -       AK 2A 251 Trip Breaker                             RPS(')
                    & Electric                             Units 1 & 2 Entergy Operations                     Arkansas Nuclear      AK 2A 251 Trip Breaker                              RPS( )
One Unit 2                                                                                        ,
Entergy Operations                     Waterford Steam       AK 2A 251 Trip Breaker                              RPS( )
                                                        . Electric Sta; ion -
Unit 3 Florida Power                          St. Lucie -            AK 2A 251 Trip Breaker                             RPS(3)
                    & Light                                Units 1 & 2 Northeast Utilities                    Millstone -           AK 2A 251 Trip Breaker                              RPS(')
Unit 2 Southern California                    San Onofre -           AK 2A 251 Trip Breaker                             RPS(3)
Edison                                 Units 2 & 3 NOTE:
(1) Reactor Protection System b
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