ML20136F795
| ML20136F795 | |
| Person / Time | |
|---|---|
| Site: | Vogtle |
| Issue date: | 02/25/1985 |
| From: | Grimes B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20136E513 | List: |
| References | |
| FOIA-84-663 NUDOCS 8502270632 | |
| Download: ML20136F795 (3) | |
Text
,
4 r:',
O*
- [a.g g
UNITED STATES
[
}
NUCLEAR REGULATORY COMMISSION p
WASHINGTON. D. C. 20555
(.%...*/
FEB 2 51985 Docket Nos. 50-424 l'
and 50-425 t
I 4
MEMORANDUM FOR:
Thomas M. Novak, Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation FROM:
Brian X. Grimes, Director Division of Quality Assurance, Vendor, and Technical Training Programs Office of Inspection and Enforcement
SUBJECT:
V0GTLE: RESPONSE TO DES COMMENTS Coment 9 from the Educational Campaign for a Prosperous Georgia (ECPG) concerning the DES for the Vogtle Electric Generating Plant expresses a concern
-I by the inadequacy of the quality a@ssurance program at Plant Vogtle."that the D i
V The comment goes on to discuss concerns regarding construction violations, deficiencies, and other QC/QA problems reported for Vogtle. This portion of the coment concludes that "the DES fails to address these concerns."
The purpose of the QA program required by NRC regulations for the construction of nuclear power plants is to assure the health and safety of the public.
Appencix B of 10 CFR Part 50 indicates that the pertinentiQA requirements apply to activities affecting the safety-related functions of structures, systems, and components that prevent or mitigate the consequences of postulated accidents that l
could cause undue risk to the health and safety of the public. Thus the QA program for each nuclear power plant is addressed in its Safety Analysis Report (SAR) by the applicant and in its Safety Evaluation Report (SER) by the NRC.
The items commented on by ECPG regarding the QA program for Vogtle will be resolved to the satisfaction of the NRC staff, the Nuclear Safety Licensing Board, the Advisory Comittee on Reactor Safety, and the Nuclear Regulatory 1
Comission prior to licensing the plant. Therefore, there is no need to discuss tne applicant's QA program as part of the environmental rev w.
(
'Y /
Brian K. Grimes, Director Division of Quality Assurance, Vendor, i
,e -
and Technical Training Center Programs Office of Inspection and Enforcement b
l C;
~) h ] )
)
IG
, g d o..p- &
m
. h il.
-m---
Thomas M. Novak N..... '
Distribution:
OCS DQASIP Reading QUAB Reading J. M. Taylor, IE R. H. Vollmer, IE J. G. Partlow, IE B. K. Grimes, IE G. T. Ankrum, IE J. L. Milhoan, IE M. A. Miller, NRR
{
B. M. Bordenick, ELD i
1
' '.)'
i i
i i
HIE:QUAB I -QUAB IE: VAB pf a P
.- QAS.AD p' JGSpraul:hmc J
ilhoan G
rum 02/yM5 ur mes JGP ow 02/6/85 02M
/85 2/
85
./ /8%
e']
, y
)
~ - - - _
.m.
~ ~. -
.A.--
~.
l b
I g
DISTRIBUTION:
t l
R. Ballard W. Gammill B. Bordenick F. Congel J. Hulman J. Milhoan I
W. Regan i
V. Moore l
ccw/oencl:
R. Samworth
-l C. Billups
)!
G. LaRoche D. Chery A. Brauner L. Bykoski A. Toalston N. Fields
~
J. Swift J. Fairobent P. Easley J
S. Saba L. Beltracchi l
9 8
7 "" %
4 m
_ _ _