ML20210C877
| ML20210C877 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon, South Texas, 05000000 |
| Issue date: | 08/19/1975 |
| From: | Eicheldinger C WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20210C503 | List:
|
| References | |
| NS-CE-737, NUDOCS 8705060354 | |
| Download: ML20210C877 (2) | |
Text
W T K ___ _
T.T
~
_r
^
r
~
y.
O.-
g
(
v
'estinghouse Electric Corporation Power Systems anzs nneu@PmyWta1522 t
August 19.-1975 y
NS-CE-737 j J./.[. t C..fi, t;,I.)
{.'.
u fl' SEP*t Mr. B. C. Rusche, Director 0-I > '
Office of I!uclear Reactor Regulation
^'
U. S. fluclear Regulatory Comission y
L Washington, D.C.
20555 d,,)
k'.'7(i;
{,
Dear Mr. Rusche:
p i
At the generic meeting a year ago (August 7,1974) Westinghouse addressed F
NRC.(EICSB) concerns about wiring separatinn within the I and C protection racks.
It was then agreed that Westinghouse perform additional tests to F
demonstrate that credible electrical faults or noise induced on control cables external to the racks could not degrade protection system perform-ance below an acceptable level.
In support of the Diablo Canyon appli-cation. Westinghouse prepared for technical review a report on tnese tests.
(" Westinghouse Protection Systems floise Tests" - December,1974).
In the tests, the fluclear Instrumentation, Solid State Protection and 7100 Series 4
Process Control Systems were subjected to electrical faults and induced
. currents beyond those which could be reasonably postulated to occur.
F The results and conclusions have been accepted by the Staff and Westinghouse
. considers the tests applicable to all plants with these systems.
- At present, assessment of the 7300 Series Process Control System design k
employed in newer plants, such as North Anna, Joseph M. Farley, William B. McGuire, Catawba, includes a continuing evaluation by Westinghouse h
against current criteria as well as t!RC concerns.
Since these plants employ the fluclear Instrumentation and Solid State Protection Systems
[
previously tested, as described above Westinghouse has proposed additional testing to verify the 7300 Series Process Control System design only.
t In general, industry standards and llRC Regulatory Guides provide for analyses or tests to demonstrate design adequacy.
Westinghouse is in F
conformance with the applicable criteria in exercising the option to test the. subject design as implemented.
i h
Rev'd Off. of D{r,
- ]
of.'.*ut!ct:r Reactor I
Regulati i
0705060 154 siO430 PDR AD'1CK 05000490 A
y PDR h*
b...
- q'
(
t
W
.1 t.-
g MS-CE-737 f
i r;.
August 19, 1975 L
Page 2 p.
t EICSB reviewers have asserted that this option is no longer acceptable for the 7300 Series Process Control System. While we strongly disagrec a!
with this pos'ition, it is our desire to resolve the issue to our mutual satisfaction. Since many Westinghouse plants are affected, it is our desire to meet with appropriate members of your Staff to ' discuss this matter generically to determine a proper resolution.
)
Your prompt reply will be appreciated.
Very truly yours, t
e LBssa -
s; s~f L
j.
- p. Eiche1dinger, nager Nuclear Safety Department J
p FWM:PJ ll
.1
.1 d
l}
l
~
t a
1 6
N-i
)( >
l t
.I r
e
.....