ML20106A204
| ML20106A204 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/25/1984 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Srinivasan M Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20106A207 | List: |
| References | |
| FOIA-84-777 NUDOCS 8407310024 | |
| Download: ML20106A204 (3) | |
Text
,
{"
(
,f neroq'o, UNITED STATES i.
NUCLEAR REGULATORY COMMISSION o
1 L
ff WASHINGTON. D. C,20555 5
p
(
jl)). P 5 IM4 Docket No.: 50-445 L
MEMORANDUM FOR:
M. Srinivasan, Chief Power Systems Branch Division of Systems Integration FROM:
B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing
SUBJECT:
COMANCHE PEAK FSAR AMENDMENT 44, CLARIFICATION ON IEEE 420-1973 The Comanche Peak Amendment 44 provided clarification on conformance to IEEE 420-1973. A copy of the related FSAR pages,is' enclosed.
Werequestthatyouprovidean.SSERevaluation.IfthischangebyCOB, Friday, July 27, 1984.
Z t
, w-B.,J.
Yo ingblood, Chief Licenging Branch to. 1 Divipion'ofLicensing
Enclosure:
As stated cc: 0..Chopra S. Burwell a
I f
L N G7 n eg2_t vc 5e-fl-1
CPSES/FSAR 8.,1. 5.1.
NRC Reculatory Guides For description of compliance to the Regulatory Guides, see Appendix 1A(B) and 1A(N).
8.1.5.2 IEEE Standards
' 'i.
IEEE 338-1971, Trial-Use Criteria for Periodic Testing of Nuclear Power Generating Station Protectinn Systems Periodic testing of protection systems conforms to the requirements of this s~tandard.
'2.
IEEE 344-1975, Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations All Class IE equipment is seismically. qualified in accordance with
.this standard.-
s For details, see Sections 3.10B and 3.10N 3.
IEEE 387-1977, Criteria for Diesel Generator Units Applied as Standby Power Supplies for Nuclear Generating Stations The design criteria and the qualification and testing requirements of the diesel generator units confonn to the requirements of this standard.
4.
IEEE 420-1973 Trail-Use Guide for Class 1E Control Switchboards for Nuclear Power Generating Station.
All Class 1E control boards are. designed in accordance with IEEE 420-1973 3
requirements with following~ clarification:
I l
8.1-9 ArtENDMENT 3 NOVEf4BER 30, 1978 i
'f 4
- heb,
v
/
CpSES/FSAR s~
n ',
Lens and Buttons for approximately forty (40) safety system inoperable indication lights'and for sixteen (16) non-safety valve control devices
.areconstructedof"LEXAN"(polycarbonate)'and"CELON"respectively.
Thera indicating lights /buttone are grouped and enclosed in metal housing 3
to provide seperation between.them and other equipment on the main control b'oard."The housings are flush mounted on the front of the main control board.
Cable connectors are provided on the back plate of the housing for e'~xternal wiring.
Internal firN(uiilikely event) in the housthg will not significatly degrade the integrity of the main control board.
Wire'sp1,1ces are' used in limitied applications on field cables that terminetjincertainClassIEpanels,cabinetsorracks.
The normal design is to terminate field cables without the use of wire splices.
The wire splices are only used where additional length is required for the field wire and it was not judged reasonable to pull a/new field cable.
The use of such wire splices has been mibimized.
The wira splices are butt splices.
Th'e' crimping technique, device and n
materisis-used for the splices are identical to those used for the 44 terminal lugs in that panel.
The wire splices are only allowed on low power applications such as codt'rol' cables.
Since previously accepted cribping methods and, materials are used, the splices are limited to low power circuits and to field cables that already terminate in the panel,-
~
and the required wire separation and wire pun'dles support is maintained,-
the wire splices are not expected to significantly alter the heat load in the panel, the probability of a fire or the;oparability of any equipment or cables in that panel.
AMEN 0 MENT 44 OCTOBER 10, 1983 8.1-10