ML19253B260
| ML19253B260 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/21/1979 |
| From: | Eisenhut D, Schroeder F Office of Nuclear Reactor Regulation |
| To: | Murley T NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| NUDOCS 7910100478 | |
| Download: ML19253B260 (2) | |
Text
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SEP 211979 MEMORANDUM FOR:
T. E. Murley, Director, Division of Reactor Safety Research FROM:
D. G. Eisenhut, Acting Director, Division of Operating Reactors F. Schroeder, Acting Director, Division of Systems Safety
SUBJECT:
MODIFICATION 5 TO FIRE TESTING RESEARCH PROGRAM
REFERENCE:
Memorandum for Thomas Murley from V. Stello and R. Mattson, dated June 11, 1979 In the referenced memorandum, D0R and DSS recommended that a series of fire tests be performed on actual plant configurations.
The first plant area to be tested under this program was the Rancho Seco Makeup Pump Room. The plant configurations to be tested were chosen on the basis that the plant areas contained redundant divisions of safe shutdown equipment / cables and that a fixed fire supp,ession system and divisional separation are relied upon to ensure operability of at least one safe shutdown division.
The Rancho Seco Makeup Pump Room contains a makeup pump and cables for a redundant high pressure injection pump.
The licensee has recently decided to reroute the high pressure injection pump cables to outside the Makeup Pump Room so that the safe shutdown capability will not be jeopardized by a fire in this room. As a result, the adequacy cf separation in this plant area is no longer a concern and, therefore, we request that the preparations to test this area be discontinued.
With the deletion of the Rancho Seco Makeup Pump Room from the test program, work should begin on the next plant configuration in the program schedule. Also, the Arkansas 1 Cable Spreading Room should be added to the test schedule as a substitute for the Rancho Seco configuration.
In the referenced memorandum, it was recommended that the Arkansas 1 Cable Spreading Room also be tested if additional funds are available.
Consequently, the test program should now include the following four plant areas to be tested in the order listed:
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. A.
Arkansas 1 Auxiliary Building Corridor B.
Brunswick Intake Structure Basement C.
Browns Ferry Reactor Building D.
Arkansas 1 Cable Spreading Room
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Fra'nk Schroeder, Acting Dire' tor D. G. Eisenhu% Acting Director c
Division of Reactor Safety Research Division of Operating Reactors
Contact:
E. Sylvester X-27173 cc:
D. Eisenhut F. Schroeder C. Long R. Feit G. Bennett G. Lainas R. Ferguson H. George E. Sylvester G. Harrison L. Tong B. Grimes V. Benaroya V. Moore D. Notley J. Boccio, BNL 1124 141