ML19208A306
| ML19208A306 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/11/1979 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Cale J AFFILIATION NOT ASSIGNED |
| References | |
| NUDOCS 7909130346 | |
| Download: ML19208A306 (1) | |
Text
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I DISTRIBUTION Docket Files 50-280/281 Central Files /
JUN 2 91979 IE Files VDThomas Rdg Files ROI Rdg Files TP Rdg Files
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MD10RANDUM FOR:
F. J. Long, Chief, Reactor _ Operations and Nuclear Support 6
Branch, Region II.
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FROM:
E. L. Jordan, Assistant DireEter J
for Tdchnical Programs, IE
SUBJECT:
EVALUATION OF ENGINEERED SAFETY FEATURE TESTING REQUIREMENTS
~ FOR SURRY l AND 2.(AITS F24129H2)
The proposed equipment inodification to correct the undersized components in 3
i the 480 Volt emergency power systems in both Surry 1 and 2 Power Plants is being reviewed by NRR. This modification is intended to increase the 480 Volt emergency power system capacity to easily acconnodate the maximum connected load on each bus for all station conditions. The NRC formal acceptance of this design change _ cannot be made until the Staff has completed the above review j
and a review of the associated system test procedure for adequate system operation.
i These procedures have not as yet been submitted-by *% licensee for Staff review.
With respect to the request for " tech spec" changes to require this facility to perform a periodic " full load" test of the complete emergency power system, NRR has advised IE:HQS that they do not foresee the need to establish new operating requirements for these systems at either Surry 1 or 2 Pcwer Plants.
' Tf--TA% agrees with the present NRR position because " full load" testing of the emergency power systems at this facility is not practical due to system con-figuration being significantly different during an accident compared to normal operation.
If you have any questions concerning the above matters, please contact V. Thomas i
of my staff on 49-28180.
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Edward I..' Jordan, Assistant Director p' n,(p ] (Y;) Q
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i ! ';J J U gij for Technical Programs u d d.
k AD Division of Reactor Operations Inspection g 09 7 3 0 3 C //
cc:
N. C. Moseley, IE D. Tondi, NRR E. Reeves, NRR
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